Event Notification Report for April 4, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/03/2001 - 04/04/2001
** EVENT NUMBERS **
37634 37880 37883 37884 37885 37886 37887 37888 37889
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37634 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/27/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 12:47[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 12/27/2000|
+------------------------------------------------+EVENT TIME: 10:31[EST]|
| NRC NOTIFIED BY: RANDY HAISLET |LAST UPDATE DATE: 04/03/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|NLTR LICENSEE 24 HR REPORT O| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) DECLARED INOPERABLE |
| |
| The licensee was performing the procedure to reset the RCIC isolation, after |
| a surveillance was completed, when the closed inboard steam isolation valve |
| (MO-1301-16) went to dual indication while opening the outboard steam |
| isolation valve (MO-1301-17). Both steam isolation valves to the RCIC |
| turbine were closed and the RCIC system was declared inoperable. The |
| licensee is investigating the problem. |
| |
| Active limiting conditions for operation were entered for the RCIC system |
| and the primary containment isolation function of the RCIC inboard steam |
| isolation valve (MO-1301-16). |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * RETRACTED AT 1414 EDT ON 4/3/01 BY ERIC OLSON TO FANGIE JONES * * * |
| |
| The licensee is retracting this event notification. The following was |
| submitted as the basis for the retraction. |
| |
| "On December 27, 2000, the RCIC system was taken out of service to perform |
| routine surveillance in accordance with PNPS procedures 8.M.2-2.6.1 and |
| 8.M.2-2.6.4. After resetting the RCIC isolation after performance of the |
| High Steam Flow surveillance, operations personnel opened valve, MO-1301-17. |
| Approximately 5 seconds into the opening stroke, MO-1301-16, the inboard |
| isolation valve, gave dual indication. During the initial opening of the |
| MO-1301-17 valve, the RCIC turbine inlet steam line began to pressurize due |
| to trapped pressure between the MO-1301-16 and MO-1301-17 valves and |
| increased to approximately 437 psig when it began to decrease at about one |
| pound per two seconds. The Control Room operator then gave MO-1301-16 valve |
| a closed signal after the valve indicated dual indication for 16 seconds and |
| the valve then indicated full closed. The steam line continued to |
| depressurize at the same rate until operations closed the MO-1301-17 valve. |
| This indicated that although MO-1301-16 showed dual Indication, it was |
| closed and the seating surfaces were tight and the containment isolation |
| function was operable. |
| |
| "The test that was being performed was testing the primary containment |
| isolation system (PCIS) and this surveillance was satisfactory with both |
| inboard and outboard isolation valves closing upon initiation. Additionally, |
| MO-1301-16 was stroke timed in accordance with PNPS procedure 8.5.5.4 and |
| the times were within the expected limits. |
| |
| "After the initial indication of leakage, the Control Room management |
| conservatively declared MO-1301-16 and the RCIC system inoperable until |
| further investigation could be performed. Troubleshooting was conducted in |
| accordance with PNPS procedure 3.M.1-34. The conclusion was that while dual |
| indication had occurred, the valve had been closed and primary containment |
| isolation was operable. |
| |
| "For (a)(2)(i) (B): not reportable. The initial indication of leakage |
| through containment Isolation valve MO-1301-16 was evaluated. The source of |
| the pressure was steam trapped between the isolation valves during the |
| previous testing. The valve was subsequently determined to have been closed |
| and containment isolation was maintained. |
| |
| "For (a)(2)(v): not reportable. There was no component or system failure. |
| The containment isolation function was maintained. |
| |
| "For (a)(2)(vii): not reportable. It was determined that there was no |
| component or system failure. The containment isolation function was |
| maintained. |
| |
| "Please note that RCIC was 'made' inoperable by closing the referenced |
| motor-operated valves (MO-1301-16 and MO-1301-17) to perform their primary |
| containment isolation function in accordance with Technical Specification |
| 3/4.7.A.2. After the operability determination, the valves were opened and |
| RCIC was again operable per TS 3/4.5.D." |
| |
| The licensee notified the NRC Resident Inspector. The R1DO (Jack McFadden) |
| was informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37880 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/02/2001|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 06:53[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/02/2001|
+------------------------------------------------+EVENT TIME: 04:02[CST]|
| NRC NOTIFIED BY: BEAUDIN |LAST UPDATE DATE: 04/04/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|10 CFR SECTION: | |
|*DEG 50.72(b)(3)(ii)(A) DEGRAD COND DURING OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 1 PERCENT OF STEAM GENERATOR # 3 TUBES FOUND TO BE POTENTIALLY |
| DEGRADED. |
| |
| At approximately 0402 CT on 04/02/01, Comanche Peak discovered that more |
| than 1% (52 out of 4772 tubes) of the inspected tubes in Steam Generator # 3 |
| are potentially degraded. The degraded tubes are being evaluated to be |
| removed from service. This event meets the criteria of C-3 as described in |
| their Technical Specification section 5.5.9. Additional data is being |
| collected and will be analyzed to assist in determining the cause of the |
| event. An LER will be issued to further document this issue. The other |
| three Steam Generator tubes are being inspected. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
| |
| * * * UPDATE ON 04/03/01 AT 0653 ET BY RAUL MARTINEZ TAKEN BY MACKINNON * * |
| * |
| |
| GREATER THAN 1 PERCENT OF STEAM GENERATOR # 4 TUBES FOUND TO BE POTENTIALLY |
| DEFECTIVE. |
| |
| At approximately 0500 CT on 04/03/01 Comanche Peak discovered that more than |
| 1% (49 out of 4777 tubes) of the inspected tubes in Steam Generator # 4 are |
| potentially defective. The defective tubes are being evaluated to be |
| removed from service. |
| |
| This event meets the criteria of C-3 as described in the their Technical |
| Specification section 5.5.9. Additional data is being collected and will be |
| analyzed to assist in determining the cause of the event. |
| |
| The licensee is presently inspecting Steam Generators 1 and 2. R4DO (Linda |
| Smith) notified. |
| |
| The NRC Resident Inspector will be notified of this update by the licensee. |
| |
| ***** UPDATE AT 0015 EDT ON 04/04/01 FROM RAUL MARTINEZ TO LEIGH TROCINE |
| ***** |
| |
| GREATER THAN 1% OF THE INSPECTED STEAM GENERATOR #2 TUBES WERE FOUND TO BE |
| POTENTIALLY DEFECTIVE. |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At approximately 2237 [CDT] on [04/03/01,] Comanche Peak Unit 1 discovered |
| that more than 1% of the inspected tubes in steam generator #2 [were] |
| potentially defective. The defective tubes are being evaluated to be |
| removed from service." |
| |
| "This event meets the criteria of C-3 as described in [...] Technical |
| Specification section 5.5.9 and is being reported pursuant to the |
| requirements of 10 CFR 50.72(b)(3)(ii)(A). Additional data is being |
| collected and will be analyzed to assist in determining the cause of the |
| event." |
| |
| "[The total number] of inservice tubes in [steam generator] #2 = 4,476 |
| tubes[, and the total number] of tubes discovered defective at this time = |
| 52 tubes." |
| |
| The licensee plans to notify the NRC resident inspector. The NRC operations |
| officer notified the R4DO (Linda Smith). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37883 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MALLINCKRODT, INC. |NOTIFICATION DATE: 04/03/2001|
|LICENSEE: MALLINCKRODT,INC. |NOTIFICATION TIME: 11:59[EDT]|
| CITY: MINNEAPOLIS ST. PAUL REGION: 3 |EVENT DATE: 04/03/2001|
| COUNTY: STATE: MN |EVENT TIME: [CDT]|
|LICENSE#: 24-17450-02MD AGREEMENT: N |LAST UPDATE DATE: 04/03/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL JORDAN R3 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WILLIAM CRAWFORD | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PHARMACY RECEIVED GENERATOR WITH SLIGHTLY HIGH SURFACE READING |
| |
| The Mallinckrodt Pharmacy received a generator with a surface reading of |
| slightly greater than the 200 millirem per hour from the Mallinckrodt |
| facility in St. Louis, Missouri. There was no surface contamination, the |
| swipe test was negative. The package had a transport index of 6.0 with a |
| yellow 3 label package with transport index of 1.5. The manufacturer has |
| been notified and is investigating the event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37884 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 04/03/2001|
|LICENSEE: GEO SOLUTIONS |NOTIFICATION TIME: 14:10[EDT]|
| CITY: SAN LUIS OBISPO REGION: 4 |EVENT DATE: 04/03/2001|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: 6286-40 AGREEMENT: Y |LAST UPDATE DATE: 04/03/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |CHARLES COX NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RECA OMAR | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MOISTURE DENSITY GAUGE RUN OVER AND DAMAGED |
| |
| Geo Solutions reported to the State of California that a Humbolt moisture |
| density gauge was run over at a work site in Atascadero, CA. The case is |
| cracked, but the insides appear intact. The licensee is contacting the |
| vendor for proper handling. There is no further information at this time. |
| |
| * * * UPDATED AT 1732 EDT ON 4/3/01 BY RECA OMAR TO FANGIE JONES * * * |
| |
| Geo Solutions Radiation Safety Officer made a further report about the |
| gauge. The source is intact, the electronics are still working, and a |
| survey indicated no leakage. The gauge has been placed in storage until the |
| vendor takes possession and performs a leak test. A construction bulldozer |
| ran over the gauge. |
| |
| The R4DO (Linda Smith) and the NMSS EO (Patricia Holahan) were notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37885 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/03/2001|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 15:03[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/03/2001|
+------------------------------------------------+EVENT TIME: 12:00[CDT]|
| NRC NOTIFIED BY: ERNEST MATES |LAST UPDATE DATE: 04/03/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| NOTIFICATION OF LOCAL GOVERNMENT AGENCY DUE TO SPURIOUS SIREN ACTUATION |
| |
| The licensee notified Claiborne County Civil Defense that a single offsite |
| emergency siren sounded spuriously for about 25 minutes today starting about |
| 1200 CDT. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37886 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/03/2001|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 16:12[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/03/2001|
+------------------------------------------------+EVENT TIME: 16:09[EDT]|
| NRC NOTIFIED BY: C. D. MARPLE |LAST UPDATE DATE: 04/03/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KEN BARR R2 |
|10 CFR SECTION: | |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STATE AGENCY NOTIFIED OF INJURED LOGGERHEAD TURTLE FOUND IN THE INTAKE |
| CANAL |
| |
| The licensee notified the Florida Fish and Wildlife Conservation Commission |
| regarding an injured loggerhead turtle found in the plant's intake canal. |
| The turtle will be sent out for rehabilitation. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37887 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/04/2001|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 02:19[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/03/2001|
+------------------------------------------------+EVENT TIME: 23:58[CDT]|
| NRC NOTIFIED BY: RON WIGGINS |LAST UPDATE DATE: 04/04/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 27 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 27% POWER DUE TO A RECIRULATION PUMP TRIP FOR |
| UNKNOWN REASONS WHILE THE UNIT WAS IN SINGLE LOOP OPERATION |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[The] unit was operating [in] single loop (2A [recirculation] pump |
| operating) when the 2A [recirculation] pump tripped. The [nuclear station |
| operator] manually scrammed the unit as required by procedure. During the |
| event, Group II and III isolations were received. All equipment operated as |
| expected. [The] unit is [currently] stable in Mode 3. Restart is being |
| evaluated." |
| |
| The licensee stated that reactor vessel water level decreased to +5 inches |
| and that the Group II and III isolation setpoint was +8 inches. The Group |
| II and III isolations have been reset, and ventilation has been restored. |
| |
| The normal reactor feedwater system is currently being utilized to supply |
| water to the reactor vessel, and containment parameters are normal. The |
| steam dumps to the condenser were available but not needed. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37888 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/04/2001|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 07:22[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/03/2001|
+------------------------------------------------+EVENT TIME: 23:51[CDT]|
| NRC NOTIFIED BY: DAVID TIDWELL |LAST UPDATE DATE: 04/04/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KEN BARR R2 |
|10 CFR SECTION: | |
|*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM ON WEST SCRAM DISCHARGE VOLUME HIGH WATER LEVEL DUE TO |
| APPARENT LEAKAGE THROUGH THE SCRAM VALVES |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During a refueling outage while picking up a hold order on the control rod |
| drive system, water level in the scram discharge volume instrument volume |
| started to rise from apparent leakage through the scram valves. At 2351 |
| [CDT,] a reactor scram was received on the west scram [discharge volume] |
| high water level. All expected alarms and actuations were received. All |
| control rods were initially 'full in,' and no rod movement occurred." |
| |
| The licensee stated that there was nothing unusual or misunderstood and that |
| all systems functioned as required. The licensee also stated that at the |
| time of the event, work was being performed on the scram discharge volume |
| drain valves which prevented the scram discharge volume from draining. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37889 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/04/2001|
| UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 10:50[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/04/2001|
+------------------------------------------------+EVENT TIME: 10:12[EDT]|
| NRC NOTIFIED BY: DAVE WILLIAMS |LAST UPDATE DATE: 04/04/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |KEN BARR R2 |
|10 CFR SECTION: |TAD MARSH NRR |
|AAEC 50.72(a)(1)(i) EMERGENCY DECLARED OBSO|RICHARD WESSMAN IRO |
| |GARY BELCHER FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR COOLANT SYSTEM LEAKAGE >10 GPM AS OBSERVED FROM CONTROL ROOM |
| INDICATIONS |
| |
| "EMERGENCY PLAN ENTRY DUE TO CONTROL ROOM INDICATION OF REACTOR COOLANT |
| SYSTEM LEAKAGE GREATER THAN 10 GPM. IT APPEARS THAT SHUTDOWN COOLING RELIEF |
| VALVE V-3483 LIFTED WHILE ATTEMPTING TO PLACE '1A' TRAIN OF SHUTDOWN COOLING |
| IN SERVICE. WHEN V-3481, HOT LEG SUCTION VALVE, WAS OPENED, APPROXIMATELY |
| 300 GALLONS OF REACTOR COOLANT WAS DIVERTED TO A HOLDUP TANK OVER A PERIOD |
| OF 2 MINUTES. THE LEAK, ESTIMATED AT 150 GPM, WAS ISOLATED BY CLOSING HOT |
| LEG SUCTION VALVE V-3480. AN UNUSUAL EVENT WAS ENTERED AND TERMINATED |
| IMMEDIATELY AT 1012 HOURS AS THE LEAK HAD BEEN TERMINATED AT THE TIME OF THE |
| NOTIFICATION. |
| |
| "THIS EVENT IS SIMILAR TO EVENT #37882." |
| |
| RCS PRESSURE AND TEMPERATURE IS CURRENTLY 260 PSIG AND 250 DEGREES F, |
| RESPECTIVELY. THE RELIEF VALVE SETPOINT IS 330 PSIG. FOLLOWING THE |
| PREVIOUS EVENT, THE RELIEF VALVE V-3483 WAS REMOVED AND BENCH TESTED WITH NO |
| ABNORMALITIES RELATED TO THE SETPOINT PRESSURE FOUND. PRESENTLY, THERE ARE |
| TWO (2) RCPs RUNNING WITH A THIRD AVAILABLE AND THE "1B" SHUTDOWN COOLING |
| TRAIN IN SERVICE. THE LICENSEE PER A PROCEDURAL REQUIREMENT INVOLVING LOW |
| PRESSURE OPERATION OF THE RCPs (RCP SEAL PROTECTION) IS IN A 12 HOUR TIME |
| PERIOD ENDING AT 1600 HOURS. THE CURRENT PLANS ARE TO INCREASE RCS PRESSURE |
| TO GREATER THAN 350 PSIG. BOTH STEAM GENERATORS ARE AVAILABLE TO REMOVE |
| DECAY HEAT. UNIT 1 HAS BEEN SHUTDOWN FOR APPROXIMATELY 50 HOURS. AN EVENT |
| RESPONSE TEAM HAS BEEN ASSEMBLED TO RECOMMEND APPROPRIATE CORRECTIVE ACTIONS |
| FOLLOWING COMPLETION OF AN INVESTIGATION. |
| |
| THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021