Event Notification Report for May 17, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/14/1999 - 05/17/1999
** EVENT NUMBERS **
35636 35658 35675 35707 35712 35713 35714 35715 35716 35717 35718 35719
35720 35721 35722 35723 35724 35725
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35636 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/26/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 23:47[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/26/1999|
+------------------------------------------------+EVENT TIME: 23:15[EDT]|
| NRC NOTIFIED BY: GREG SOSSON |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLIFFORD ANDERSON R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF TWO LOCAL POWER RANGE MONITORS INDICATING INCONSISTENTLY WITH |
| THE REMAINING LOCAL POWER RANGE MONITORS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Upon review of local power range monitor (LPRM) data for Unit 1, [two] |
| LPRMs were determined be indicating inconsistently with the remaining LPRMs. |
| The cause is believed to be reversed cable inputs to the LPRM drawer. The |
| problem is believed to be under-vessel." |
| |
| "As a result of this condition, the 'B' and 'D' [average power range |
| monitors (APRMs)] and both rod block monitor [(RBM)] channels were declared |
| inoperable at 2315 [on 04/26/99]. This condition has existed since the |
| previous refueling outage [which was exited] in June [of] 1998." |
| |
| "The suspect LPRMs are being bypassed which will restore the APRMs and RBMs |
| to an OPERABLE status." |
| |
| "Generic investigations are in progress; however, initial review of |
| operating data indicates normal operation of [the] remaining LPRMs. This |
| investigation will analyze any impact on thermal limits and fuel |
| performance." |
| |
| The licensee stated that the RBMs are not required for operability at this |
| time. However, the unit is currently in a 12-hour limiting condition for |
| operation (LCO) which requires insertion of a half scram for the two |
| inoperable APRMs. This LCO will be exited when the LPRMs are bypassed. The |
| licensee does not anticipate any problems meeting this LCO action statement. |
| The licensee also stated that with the exceptions noted above, all systems |
| functioned as designed and there was nothing unusual or misunderstood. |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| * * * RETRACTION AT 1413 ON 05/14/99 FROM DALE BEGIAN TAKEN BY STRANSKY * * |
| * |
| |
| "This notification is a retraction of a notification made on 04/26/99 (event |
| 35636) involving the discovery of two local power range monitors (LPRM) |
| indicating inconsistently with the remaining LPRMs. A review has concluded |
| that the event did not involve operation outside the plants design basis or |
| an inoperable (RBM) or (APRM)." |
| |
| "The notification identified concerns with a potential adverse impact on the |
| operation of the rod block monitor (RBM) or average power range monitor |
| (APRM) resulting from two LPRM detectors on the same LPRM string having |
| their connection wiring swapped. This condition was discovered following |
| startup from a recent plant shutdown. During a new control rod pattern |
| adjustment on April 26, 1999, it was identified that LPRMs 40-17B and 40-17C |
| were indicating inconsistently with the remaining symmetrical LPRMs and |
| axial power levels." |
| |
| "The LGS 1 design requirements for minimum number of LPRM inputs from a four |
| string array into the RBM was met, and the monitor, although degraded, |
| remained operable. The swapped LPRM inputs were within a 4 rod grouping and |
| did not significantly impact their associated averaging circuitry which |
| inputs to the RBM and APRM. These inputs were within the acceptable ranges |
| and, therefore, did not impact operability of the RBM or APRM." |
| |
| "Currently, the affected LPRMs are bypassed in accordance with Tech Spec |
| limitations. The LPRM wiring connections will be checked and corrected in |
| the next Unit 1 refuel outage." |
| |
| The NRC resident inspector will be informed of this retraction. The NRC |
| operations officer notified the R1DO (Caruso). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35658 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/30/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 09:56[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/30/1999|
+------------------------------------------------+EVENT TIME: 09:10[EDT]|
| NRC NOTIFIED BY: CHUCK SMITH |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - PLANT SECURITY REPORT - |
| |
| A VULNERABILITY TO UNAUTHORIZED/UNDETECTED ENTRY INTO A PLANT VITAL AREA WAS |
| DISCOVERED. COMPENSATORY MEASURES WERE IMMEDIATELY TAKEN UPON DISCOVERY. |
| (CONTACT THE HOO FOR ADDITIONAL DETAILS.) |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| ***UPDATE ON 05/14/99 AT 1326 EST FROM HERB TORBERG TAKEN BY MACKINNON*** |
| |
| This follow-up report is due to the ongoing Restart Readiness Assessment |
| Program walkdown of vital area barriers. Another vulnerability to |
| unauthorized/undetected entry into a plant vital area was discovered. |
| Compensatory measures were immediately taken upon discovery. (Contact the |
| HOO for more details.) |
| |
| The licensee notified the NRC Resident Inspector. The R3DO (Roger |
| Lanksbury) was notified by the NRC operations officer. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35675 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/05/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 04:38[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/05/1999|
+------------------------------------------------+EVENT TIME: 02:00[EDT]|
| NRC NOTIFIED BY: GREG SOSSON |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES LINVILLE R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ISOLATION OF THE 'B' LOOP DRYWELL CHILLED WATER INBOARD SUPPLY AND RETURN |
| VALVES DURING PERFORMANCE OF A SPECIAL PROCEDURE TO DEENERGIZE A SAFEGUARDS |
| BUS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 05/05/99 at 0200 hours, it was discovered that an [engineered safety |
| feature (ESF)] actuation occurred on the Unit 2 Drywell Chilled Water (DWCW) |
| system. This isolation occurred at approximately 2300 on 05/02/99 during |
| performance of a special procedure to deenergize the D22 safeguards bus." |
| |
| "With Unit 2 in OPCON 5, the 'B' loop DWCW inboard supply and return valves |
| HV-087-222 and HV-087-223 isolated when the power supply to an interposing |
| relay was deenergized per a special procedure on 05/02/99. This special |
| procedure did not properly address the valve closure. During this special |
| procedure, power was later removed from both valves. This removed control |
| room indication of their position, and their closure was not immediately |
| detected. Later, station personnel observed increasing drywell |
| temperatures. The follow-up investigation revealed the isolation valves were |
| closed by local verification." |
| |
| "Additional investigation found several containment atmosphere sample valves |
| and primary containment instrument gas [primary containment isolation |
| valves] that also closed during the loss of power. These conditions were |
| also expected but not properly documented in the special procedure." |
| |
| The licensee notified the NRC resident inspector. |
| |
| ***RETRACTION ON 05/14/99 AT 1643 EDT FROM DAVID NEFF TAKEN BY MACKINNON*** |
| |
| A review of the closure of two primary containment isolation valves has |
| concluded that the event did not involve a valid ESF actuation signal and |
| that the equipment affected did not involve the minimum actuation logic for |
| the isolation control system. Therefore, an ESF actuation did not occur. |
| |
| The NRC Resident Inspector will be notified of this retraction by the |
| licensee. The R1DO (John Caruso) was notified by the NRC operations |
| officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35707 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA BUREAU OF RAD CONTROL |NOTIFICATION DATE: 05/12/1999|
|LICENSEE: CITRUS MEMORIAL HEALTH FOUNDATION, IN|NOTIFICATION TIME: 17:32[EDT]|
| CITY: INVERNESS REGION: 2 |EVENT DATE: 05/12/1999|
| COUNTY: STATE: FL |EVENT TIME: [EDT]|
|LICENSE#: 2067-1 AGREEMENT: Y |LAST UPDATE DATE: 05/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RUDOLPH BERNHARD R2 |
| |JOE HOLONICH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ADAMS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE FLORIDA BUREAU OF RADIATION CONTROL REPORTED A RADIOLOGICAL INCIDENT, |
| #FL99-066, WHICH OCCURRED AT THE CITRUS MEMORIAL HEALTH FOUNDATION, INC., |
| LOCATED IN INVERNESS, FLORIDA. |
| |
| SIX IMPLANTED I-125 SEEDS MEASURING 0.265 mCi EACH WERE REMOVED FROM A |
| PATIENT AT THE FACILITY. WHEN THE SEEDS WERE TO BE RETRIEVED FOR SHIPMENT |
| BACK TO THE MANUFACTURER, ONLY ONE COULD BE FOUND. A THOROUGH SURVEY OF THE |
| ROOM AND SEWER TRAPS FAILED TO LOCATE THE OTHER FIVE SEEDS. THE MISSING |
| MATERIAL WAS PROBABLY LOST IN THE SANITARY SEWER. A STATE INSPECTOR IS |
| INVESTIGATING THE INCIDENT. |
| |
| ***UPDATE ON 05/14/99 AT 1454 HOURS FROM JERRY EAKINS TAKEN BY MACKINNON*** |
| |
| ON 05/11/99, THE LICENSEE PERFORMED A PROSTATE IMPLANT USING I-125 SEEDS IN |
| PRE-LOADED APPLICATORS. SIX SEEDS IN TWO APPLICATORS WERE UNUSED AND TAKEN |
| TO THE STERILE PROCESSING DEPARTMENT (SPD). ON 05/12/99, MS. PETKUS |
| RETRIEVED THEM TO SHIP BACK TO THE RADIOPHARMACY AND FOUND ONLY ONE SEED. A |
| THROUGH SURVEY OF THE SPD INCLUDING THE SEWER TRAPS FAILED TO LOCATE THE |
| MISSING FIVE SEEDS. THE STATE INVESTIGATOR VISITED THE LICENSEE ON |
| 05/13/99. HE DUPLICATED THE RADIATION SURVEYS OF THE LICENSEE AND WAS |
| UNABLE TO FIND THE MISSING SEEDS. THE LICENSEE AND THE STATE INSPECTOR HAVE |
| INTERVIEWED ALL THE PERSONNEL INVOLVED. IT IS SUSPECTED THE SEEDS WERE LOST |
| WHEN THE APPLICATORS WERE OPENED BY MISTAKE FOR STERILIZATION. THE CAUSE OF |
| THIS INCIDENT IS THE FAILURE OF THE LICENSEE TO CONTROL ACCESSIBILITY OF THE |
| BRACHYTHERAPY SOURCES TO AUTHORIZED PERSONNEL. THIS INCIDENT IS DEFERRED TO |
| RADIOACTIVE MATERIALS. |
| |
| THE R2DO (R. BERN HARD) AND NMSS EO (BRAIN SMITH) WERE NOTIFIED BY THE NRC |
| OPERATIONS OFFICER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35712 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/14/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 00:30[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/13/1999|
+------------------------------------------------+EVENT TIME: 23:00[CDT]|
| NRC NOTIFIED BY: RICH CHEAR |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 4 Startup |4 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY THAT THE LEAK RATE OF A MAIN STEAM ISOLATION VALVE IS GREATER THAN |
| THE INBOARD LEAKAGE CONTROL SYSTEM PROVEN TREATMENT FLOW RATE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Clinton Power Station has identified that the Inboard Main Steam Isolation |
| Valve (MSIV) Leakage Control System (LCS) is not calibrated to process the |
| design MSIV leakage of 28 standard cubic feet per hour (scfh) per one main |
| steam line. One MSIV has been identified as having a leakage rate of 22.5 |
| scfh which is greater than the Inboard LCS proven treatment flow rate of |
| 21.3 scfh. Currently, the engineering team is still investigating." |
| |
| The licensee stated that the unit was in a 30-day technical specification |
| limiting condition for operation as a result of this issue. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35713 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 05/14/1999|
| UNIT: [] [] [3] STATE: CA |NOTIFICATION TIME: 01:54[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 05/13/1999|
+------------------------------------------------+EVENT TIME: 21:44[PDT]|
| NRC NOTIFIED BY: MATT THURBURN |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 M/R Y 97 Power Operation |0 Hot Standby |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP AND MANUAL INITIATION OF EMERGENCY FEEDWATER DUE TO THE |
| LOSS OF BOTH MAIN FEEDWATER PUMPS DURING THE PERFORMANCE OF MAINTENANCE ON |
| THE FEEDWATER CONTROL SYSTEM (Refer to event #35721 for a similar event |
| that occurred on 05/15/99.) |
| |
| At 2144 PDT on 05/13/99, both main feedwater pumps tripped for unknown |
| reasons. Reactor operators recognized this loss, manually tripped the |
| reactor from 97% power, and manually initiated emergency feedwater. All |
| rods fully inserted, and all systems functioned as required. There were no |
| engineered safety feature actuations other than the manual initiation of |
| emergency feedwater. The main steam isolation valves remained open, none of |
| the relief valves opened, and there was no loss of offsite power. |
| |
| The reactor is currently stable in Mode 3 (Hot Standby). The reactor |
| coolant pumps, normal charging and letdown, and pressurizer heaters and |
| sprays are being utilized for primary system transport, level, and pressure |
| control. All containment parameters are normal. Emergency feedwater is |
| supplying water to the steam generators, and secondary steam is being dumped |
| to the main condenser. Offsite power is available. The 'A' emergency |
| diesel generator is currently out of service for planned maintenance. |
| However, the 'B' emergency diesel generator and the crossties from the other |
| unit are available if needed. |
| |
| The cause of the loss of both feedwater pumps is under investigation. The |
| licensee stated that maintenance personnel were performing voltage checks in |
| the feedwater control system at the time of the event. |
| |
| The licensee notified the NRC resident inspector and plans to issue a |
| media/press release. |
| |
| ********** HOO NOTE: Based on plant status calls that occurred on 05/15/99 |
| and 05/16/99, the cause of this event was determined to be a failed relay in |
| the feedwater control system which resulted in closure of feedwater |
| regulation valve #3FV1121 for the #2 steam generator (E088). This in turn |
| resulted in high discharge pressure on both main feedwater pumps. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35714 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 05/14/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 09:13[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/14/1999|
+------------------------------------------------+EVENT TIME: 07:13[CDT]|
| NRC NOTIFIED BY: RANDY HASTINGS |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: |JIM LYONS NRR |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |FRANK CONGEL IRO |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP AND MANUAL SAFETY INJECTION DUE TO A STEAM LEAK ON THE |
| 4B FEEDWATER HEATER STEAM SIDE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Unit 1 experienced a manual reactor trip [from 100% power] at 0713 CDT due |
| to a steam leak on the 4B feedwater heater steam side. The control room |
| operators also manually safety injected at 0716 [CDT] due to decreasing |
| pressurizer level. The steam leak has been isolated. All equipment |
| operated as designed during the event. No injuries have been reported. |
| [The licensee is] currently performing the [safety injection] termination |
| procedure. The unit is currently stable at 2,010 psig and 538�F. No |
| release did occur or is occurring." |
| |
| The licensee stated that the auxiliary feedwater pumps started. The |
| emergency diesel generators also started but did not load. These actions |
| were expected as a result of the manual safety injection. All rods fully |
| inserted as a result of the manual reactor trip, and the main steam |
| isolation valves were manually closed. In addition, the licensee stated |
| that the manual safety injection was considered to be an engineered safety |
| feature actuation and that there were no emergency core cooling system |
| injections. |
| |
| The reactor is currently stable in Hot Shutdown. The reactor coolant pumps, |
| normal charging and letdown, and pressurizer heaters and sprays are being |
| utilized for primary system transport, level, and pressure control. All |
| containment parameters are normal. Auxiliary feedwater is supplying water |
| to the steam generators, and secondary steam is being dumped to atmosphere |
| because the main steam isolation valves were manually closed. There has |
| been no history of steam generator tube leakage. Offsite power is |
| available, and the emergency diesel generators are running unloaded at this |
| time. |
| |
| The licensee notified the NRC resident inspector and plans to notify |
| Kewaunee County, and Manitowoc County, and the state. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35715 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/14/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 10:37[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/14/1999|
+------------------------------------------------+EVENT TIME: 07:52[CDT]|
| NRC NOTIFIED BY: RONALD GIULIANI |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 4 Startup |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 4% POWER DUE TO A LEVEL TRANSIENT ASSOCIATED WITH |
| A FEED REGULATING VALVE MALFUNCTION |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "While in steady state conditions of 4% [reactor] power and 34" reactor |
| level [at] 0723 [CDT], the [motor-driven reactor feed pump] feed regulating |
| valve (1FW004) malfunctioned causing a level excursion to [approximately] |
| 42". This level transient was controlled by [manually] isolating feedwater |
| to the reactor vessel. Reactor level returned to [approximately] 30"[, and |
| at approximately] 0738 [CDT], feedwater was reestablished to the vessel. As |
| reactor feed was established, the transient was not able to be controlled |
| and level increased. [At] 0752 [CDT], the motor-driven reactor feed pump |
| tripped on a level 8 signal [when level reached 52"], and the reactor mode |
| switch was then manually placed into the [shutdown] position. This caused a |
| reactor scram. All rods fully inserted. All systems functioned as expected |
| following the scram [with one exception described below]. The plant is in |
| Mode 3 and is proceeding to Mode 4. Feedwater is being supplied to the |
| vessel from the [condensate and condensate booster] system. Reactor |
| pressure is [approximately] 430 psig and is steady. The plant will be |
| cooled down to Mode 4 in a controlled manner using bypass valves and |
| shutdown cooling." |
| |
| "[Reactor core isolation cooling (RCIC)] was being tested at the time of the |
| scram. [However,] RCIC did not trip on level 8. This will be investigated. |
| It is possible that the level channels required for this trip did not reach |
| the trip setpoint. RCIC was manually tripped after the scram to control |
| cooldown rate." |
| |
| The licensee stated that the reactor protection system trip on level 8 was |
| bypassed because the unit was in Mode 2 with the mode switch in the startup |
| position. |
| |
| The licensee notified the NRC resident inspector and plans to issue a |
| media/press release. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35716 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/14/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 12:49[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/14/1999|
+------------------------------------------------+EVENT TIME: 07:30[EDT]|
| NRC NOTIFIED BY: BRETT BOISMENER |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN CARUSO R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A CONTRACT SUPERVISOR TESTED POSITIVE FOR ALCOHOL. |
| |
| A CONTRACTOR FULFILLING A SUPERVISOR POSITION WAS STOPPED BY SECURITY PRIOR |
| TO ENTERING THE PROTECTED AREA DUE TO THE ODOR OF ALCOHOL. THE INDIVIDUAL |
| WAS ESCORTED TO FITNESS FOR DUTY WHERE A FOR-CAUSE TEST WAS CONDUCTED. THE |
| TEST RESULTS WERE CONFIRMED POSITIVE FOR ALCOHOL. THE INDIVIDUAL'S |
| UNESCORTED ACCESS WAS IMMEDIATELY REVOKED. THE INDIVIDUAL'S SUPERVISOR WILL |
| BE REQUIRED TO PERFORM AN IMPACT OF QUALITY AND SAFETY REVIEW OF THE |
| INDIVIDUAL'S WORK. (CONTACT THE NRC OPERATIONS OFFICER FOR ADDITIONAL |
| INFORMATION.) |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35717 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 05/14/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 13:34[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 05/14/1999|
+------------------------------------------------+EVENT TIME: 12:50[EDT]|
| NRC NOTIFIED BY: J. SCHORK |LAST UPDATE DATE: 05/14/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN CARUSO R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A FLOOD PATH WAS DISCOVERED BETWEEN THE UNIT 1 TURBINE BUILDING AND CONTROL |
| BUILDING. |
| |
| Two penetrations between the Three Mile Island Unit 1 Turbine Building (a |
| non-flood protected structure) and the Control Building (a flood protected |
| structure) have been found to allow the free flow of flood waters from the |
| Turbine Building into the Control Building in the event of the maximum |
| predicted flood at Three Mile Island. This is a non-conformance made to the |
| NRC (originally made to the AEC) as documented in Section 2.6.5.i of the |
| Three Mile Island Final Safety Analysis Report. |
| |
| The flood protection procedure will be modified as soon as possible to |
| require the installation of plugs in the identified flow path in the event |
| of a pending flood. Additionally, a review of the event of the identified |
| condition will be performed in an Licensee Event Report. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35718 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CITY OF NEW YORK DEPT. HEALTH |NOTIFICATION DATE: 05/14/1999|
|LICENSEE: BETH ISREAL MEDICAL CENTER |NOTIFICATION TIME: 16:00[EDT]|
| CITY: NEW YORK CITY REGION: 4 |EVENT DATE: 05/14/1999|
| COUNTY: STATE: NE |EVENT TIME: 12:00[CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/14/1999|
| DOCKET: Y |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES CAIN R4 |
| |BRAIN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICHARD BORRI | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE EVENT REPORTED BY THE CITY OF NEW YORK DEPARTMENT OF HEALTH |
| |
| |
| THE CITY OF NEW YORK DEPARTMENT OF HEALTH REPORTED THE FOLLOWING |
| INFORMATION: |
| |
| JEMS SANITATION LOCATED IN LYNDHURST, NEW JERSEY, HAD RECEIVED A SHIPMENT OF |
| MUNICIPAL WASTE WHICH SET OFF THEIR RADIATION DETECTORS. THE MUNICIPAL |
| WASTE IS BEING SHIPPED BACK TO BETH ISRAEL MEDICAL CENTER LOCATED IN NEW |
| YORK CITY. THE CITY OF NEW YORK DEPARTMENT OF HEALTH WILL INVESTIGATE THIS |
| EVENT. NO FURTHER INFORMATION COULD BE GIVEN BY THE CALLER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35719 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/15/1999|
| UNIT: [] [2] [3] STATE: IL |NOTIFICATION TIME: 09:47[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/15/1999|
+------------------------------------------------+EVENT TIME: 04:56[CDT]|
| NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 05/15/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE OF A CONTROL ROOM HVAC REFRIGERATION AND CONDENSING UNIT TO RESTART |
| DURING SURVEILLANCE TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0456 hours on May 15, 1999, the 'B' Control Room HVAC Refrigeration and |
| Condensing Unit (RCU) would not restart during surveillance testing. The 'B' |
| RCU is a single train system and, therefore, is believed to be reportable |
| per ComEd Reportability Manual SAF 1.17. The 'B' RCU is required to operate |
| during design basis accidents to remove the heat from the Main Control Room. |
| The Air Filtration Unit remains operable. This places both units in a |
| 30-day Tech. Spec. LCO." |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35720 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 05/15/1999|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 18:25[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 05/15/1999|
+------------------------------------------------+EVENT TIME: 14:56[CDT]|
| NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 05/15/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE TRIP/REACTOR SCRAM DURING MAIN TURBINE MECHANICAL OVERSPEED TESTING |
| |
| While the licensee was resetting the mechanical overspeed trip during main |
| turbine mechanical overspeed testing, the main turbine tripped which |
| generated an automatic reactor scram. All control rods fully inserted into |
| the core. The resulting scram caused reactor vessel water level to lower to |
| below the primary containment isolation system group 2 (drywell), group 3 |
| (reactor water cleanup), group 6 (ventilation), and group 8 (traversing |
| incore probes) isolation setpoint resulting in those isolations along with |
| control room emergency ventilation system and the standby gas treatment |
| system initiations. Reactor feedwater is maintaining reactor vessel water |
| level, and the turbine bypass valves are maintaining reactor vessel |
| pressure. All emergency core cooling systems and the emergency diesel |
| generators are fully operable if needed. None of the safety-relief valves |
| opened, and the offsite electrical grid is stable. |
| |
| The licensee is investigating what caused the turbine trip/reactor scram. A |
| Licensee Event Report will be filed with the NRC within 30 days concerning |
| this event. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35721 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 05/16/1999|
| UNIT: [] [] [3] STATE: CA |NOTIFICATION TIME: 04:08[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 05/15/1999|
+------------------------------------------------+EVENT TIME: 23:58[PDT]|
| NRC NOTIFIED BY: MATT THURBURN |LAST UPDATE DATE: 05/16/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 M/R Y 24 Power Operation |0 Hot Standby |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO FAILURE OF A MAIN FEEDWATER REGULATING VALVE AND |
| SUBSEQUENT INCREASING STEAM GENERATOR WATER LEVELS (Refer to event #35713 |
| for a similar event that occurred on 05/13/99.) |
| |
| While operators were making preparations to place the turbine on line, |
| feedwater regulation valve #3FV1111 for the #1 steam generator (E089) failed |
| open. Operators attempted to manually close the valve, but the valve did |
| not respond. As steam generator water levels trended up, a pre-trip alarm |
| on high steam generator level was received, and operators manually tripped |
| the reactor from 24% power at 2358 PDT on 05/15/99. (Steam generator water |
| levels did not reach the trip setpoint.) All rods fully inserted, and all |
| systems functioned as required. There were no engineered safety feature or |
| emergency core cooling system actuations, and none were required. The main |
| steam isolation valves remained open, none of the relief valves opened, and |
| there was no loss of offsite power. |
| |
| Reactor coolant system (RCS) cooled down farther than normal following the |
| manual trip due to the overfeeding of the steam generators. RCS temperature |
| normally stabilizes at approximately 545�F. However, during this transient, |
| the RCS cooled down to approximately 530�F before operators tripped the main |
| feedwater pump and manually initiated auxiliary feedwater. |
| |
| The reactor is currently stable in Mode 3 (Hot Standby). The reactor |
| coolant pumps, normal charging and letdown, and pressurizer heaters and |
| sprays are being utilized for primary system transport, level, and pressure |
| control. All containment parameters are normal. Auxiliary feedwater is |
| supplying water to the steam generators, and secondary steam is being dumped |
| to the main condenser. Offsite power is available. The emergency diesel |
| generators and emergency core cooling systems are operable and available if |
| needed. |
| |
| The cause of the feedwater regulation valve failure is under investigation. |
| The licensee stated that there were no maintenance activities ongoing at the |
| time of the event. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35722 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/16/1999|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 07:34[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/16/1999|
+------------------------------------------------+EVENT TIME: 04:52[CDT]|
| NRC NOTIFIED BY: ROYCE BROWN |LAST UPDATE DATE: 05/16/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE A REACTOR COOLANT PUMP TRIP |
| |
| The Unit 1 reactor automatically tripped from 100% power due to a loss of 1C |
| reactor coolant pump flow. The 1C reactor coolant pump tripped due to an |
| undervoltage condition on the 1H 13.8-kV auxiliary bus. All rods fully |
| inserted, and all systems functioned as required. Main feedwater isolated |
| on the plant trip, and auxiliary feedwater actuated as expected. The |
| pressurizer and steam generator power-operated relief valves remained closed |
| during the event, and the main steam isolation valves remained open. There |
| was no loss of offsite power, and there were no emergency core cooling |
| system injections. |
| |
| The unit is currently stable in Mode 3 (Hot Standby). The 1C reactor |
| coolant pump is still secured, and primary system transport control is being |
| maintained with the reactor coolant pumps in the remaining three loops. |
| Normal charging and letdown and pressurizer heaters and sprays are being |
| utilized for primary system level and pressure control. Auxiliary feedwater |
| has been secured, and main feedwater is supplying water to the steam |
| generators. Secondary steam is being dumped to the condenser. Offsite |
| power is available, and the emergency diesel generators and emergency core |
| cooling systems are operable and available if needed. |
| |
| The cause of the undervoltage on the 1H 13.8-kV auxiliary bus is being |
| investigated. The 1H 13.8-kV auxiliary bus has protection circuits that |
| strip the two big loads (the reactor coolant pump and circulating water |
| pump) on undervoltage. At this time, it appears that the feed to the |
| protection circuitry on the C phase may have failed. Preliminary |
| indications reveal that the bus itself did not fail. There were no |
| maintenance or surveillance activities occurring at the time of the event. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35723 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/16/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 08:35[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/16/1999|
+------------------------------------------------+EVENT TIME: 08:05[EDT]|
| NRC NOTIFIED BY: KENNETH GRACIA |LAST UPDATE DATE: 05/16/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN CARUSO R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INOPERABILITY OF PRIMARY CONTAINMENT DUE TO MAIN STEAM ISOLATION VALVE |
| (MSIV) LEAKAGES IN EXCESS OF LOCAL LEAK RATE TESTING LIMITS |
| |
| Local leak rate testing of the MSIVs on main steam line 'C' revealed |
| leakages in excess of the 1% per day technical specification leakage limit. |
| The revealed leakages of 280 standard liters per minute (slm) and 255 slm |
| exceed the limit of 210.5 slm. These MSIVs are containment isolation |
| valves, and this makes the primary containment system inoperable. However, |
| the unit is currently shut down with the vessel head removed as part of a |
| refueling outage. |
| |
| The licensee stated that secondary containment was not lost because the main |
| steam line plugs are in place in the vessel's steam nozzles (before the |
| MSIVs). Therefore, the ongoing fuel shuffle has not been suspended. The |
| licensee has suspended all work on lines in the drywell that would open |
| anything downstream of the plugs. The licensee cannot commence work on the |
| MSIV until a contingency plan is developed to either establish secondary |
| containment downstream of the valves or finish fuel moves so that secondary |
| containment would no longer be required. The first fuel shuffle is |
| scheduled to be completed by midnight tonight. |
| |
| Contingency plans are to repair the MSIVs during the ongoing refueling |
| outage. |
| |
| Prior to this issue, one of the MSIVs in the 'C' main steam line failed its |
| quarterly stroke-time test. The valve was declared inoperable, and the |
| second MSIV in the 'C' main steam line was closed to isolate the line on |
| 03/27/99. The unit remained at 80% reactor power until commencement of the |
| current refueling outage on 05/08/99. Prior to 03/27/99, the 'C' main steam |
| line was in service. |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35724 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/16/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 13:34[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/16/1999|
+------------------------------------------------+EVENT TIME: 08:43[CDT]|
| NRC NOTIFIED BY: C. WALRATH |LAST UPDATE DATE: 05/16/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO SMALL AIR POCKETS IN THE |
| HIGH AREAS OF THE COMMON RESIDUAL HEAT REMOVAL TRAIN INJECTION LINES |
| |
| Small air pockets in high point areas of common residual heat removal train |
| injection lines. The licensee is unable to completely remove the small air |
| pockets at this time. The licensee entered Technical Specification 3.0.3 at |
| 0843 CST. Unit 1 commenced reactor shutdown at 1231 CST. All emergency |
| core cooling systems are fully operable except the residual heat removal |
| system, which is available to perform its required functions but is not |
| operable. The emergency diesel generators are fully operable, and the |
| electrical grid is stable. |
| |
| The licensee continues to troubleshoot in trying to remove the air pockets. |
| |
| The NRC Resident Inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35725 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/17/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 01:29[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/17/1999|
+------------------------------------------------+EVENT TIME: 00:00[EDT]|
| NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 05/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN CARUSO R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF POWER SIGNAL ON THE 'A' TRAIN GENERATOR LOAD SEQUENCER |
| |
| A loss of power signal occurred when the licensee restored the 'A' train |
| generator load sequencer as part of restoration from an 'A' train bus |
| outage. At the time, most of the major components were tagged out of |
| service and deenergized because the unit was 'B' train protected due to the |
| 'A' train outage. However, some of the smaller components (valves and |
| dampers) did move when the loss of power signal occurred. The licensee |
| believes that the signal was valid because the sequencer remembered that the |
| bus was deenergized earlier this evening. |
| |
| Nothing that actuated affected the licensee's ability to cool the core or |
| the spent fuel pool. In addition, anything needed by technical |
| specifications was not affected. Therefore, the licensee believes that the |
| affect on the plant was minimal. All systems functioned as required, and |
| all affected components have subsequently been restored to normal. |
| |
| The cause of this event is currently under investigation. At this time, the |
| licensee hypothesizes that either there was something tagged out that was |
| confusing the sequencer or that the procedure sequence did not reset the |
| sequencer memory. The licensee stated that the procedures were followed |
| step by step. It was also noted that the procedure had a large revision bar |
| and that something may have been left out. The licensee plans to |
| investigate whether or not the procedure step sequence was proper. The |
| licensee also plans to correct this problem before the unit enters Mode 4 |
| (when the sequencer is required to be operable by technical specifications). |
| The current estimated restart date is 06/15/99. |
| |
| The licensee notified the NRC resident inspector, the applicable state and |
| local agencies, and the Department of Environmental Protection. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021