Event Notification Report for March 25, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/24/1999 - 03/25/1999
** EVENT NUMBERS **
35434 35464 35468 35501 35503 35504 35505 35506 35507 35508
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35434 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/02/1999|
| UNIT: [] [2] [] STATE: WI |NOTIFICATION TIME: 18:21[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/02/1999|
+------------------------------------------------+EVENT TIME: 16:45[CST]|
| NRC NOTIFIED BY: SHORT |LAST UPDATE DATE: 03/24/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 1 Startup |1 Startup |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER LEAKING BACK INTO MAIN FEEDWATER SYSTEM |
| |
| THE LICENSEE DISCOVERED THAT THE AUXILIARY FEEDWATER SYSTEM WAS LEAKING BACK |
| INTO THE MAIN FEED SYSTEM ("B" FEED LINE) PAST TWO IN-SERIES CHECK VALVES. |
| THESE CHECK VALVES ARE CONSIDERED CONTAINMENT ISOLATION VALVES. LEAKAGE IS |
| IN EXCESS OF THEIR ALLOWABLE LIMITS. AUXILIARY FEEDWATER IS CURRENTLY |
| FEEDING THE STEAM GENERATORS. THE LEAKAGE HAS BEEN ISOLATED USING MANUAL |
| VALVES. THE UNIT WAS IN STARTUP FOLLOWING A REFUELING OUTAGE WHEN THE |
| CONDITION WAS FOUND. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| |
| ***RETRACTION ON 03/24/99 AT 1132ET BY RANDY HASTINGS TAKEN BY MACKINNON*** |
| |
| Subsequent evaluation has clarified that only one of the series check valves |
| performs a containment isolation function, 2CS-476AA (Reference PBNP FSAR |
| Figure 5.2-3). The main steam and feed water system are considered a closed |
| system inside containment and the piping is part of the containment |
| boundary. That boundary remained intact during this event. Accordingly, |
| the integrity of the containment boundary was never in question and this |
| condition did not result in a principal safety barrier being seriously |
| degraded. |
| |
| An engineering evaluation has also been completed to assess whether the |
| leakage observed past these check valves would have resulted in less than |
| the required auxiliary feed water flow to be available for decay heat |
| removal. This evaluation concluded that even with check valve leakage in |
| excess of that observed during this event, the auxiliary feed water system |
| was capable of providing sufficient flow to the steam generators to meet the |
| design basis for decay heat removal. R3DO (Pat Hiland) notified. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35464 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/12/1999|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 15:08[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/12/1999|
+------------------------------------------------+EVENT TIME: 13:14[CST]|
| NRC NOTIFIED BY: PHIL SHORT |LAST UPDATE DATE: 03/24/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER 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 100 Power Operation |100 Power Operation |
|2 N Y 73 Power Operation |73 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - AUXILIARY FEEDWATER SYSTEM FOR BOTH UNITS INOPERABLE FOR 4 MINUTES - |
| |
| UNIT 1 IS OPERATING AT 100% POWER, AND UNIT 2 IS OPERATING AT 73% POWER. |
| |
| ON 03/12/99, DURING AN ENGINEERING EVALUATION, LICENSEE ENGINEERING |
| DEPARTMENT PERSONNEL DETERMINED THAT THE UNIT 2 TURBINE-DRIVEN (TD) |
| AUXILIARY FEEDWATER (AFW) |
| PUMP FLOW RATE HAD BEEN SET INCORRECTLY DURING A PREVIOUSLY PERFORMED TEST. |
| LICENSEE PERSONNEL DETERMINED THAT THIS CONDITION AFFECTED THE ENTIRE AFW |
| SYSTEM. (PORTIONS OF THE AFW SYSTEM ARE SHARED BY BOTH UNITS.) |
| |
| AT 1314 CST ON 03/12/99, THE LICENSEE ADMINISTRATIVELY DECLARED THE UNIT 1 |
| TD AFW PUMP, THE UNIT 2 TD AFW PUMP, AND THE TWO SHARED MOTOR-DRIVEN (MD) |
| AFW PUMPS INOPERABLE (AND THUS, THE ENTIRE AFW SYSTEM) AND ENTERED TECHNICAL |
| SPECIFICATION LIMITING CONDITION FOR OPERATION ACTION STATEMENT 15.3.0.B |
| (a.k.a. 3.0.3). ALL FOUR AFW PUMPS REMAINED FUNCTIONAL. THIS CONDITION IS |
| CONSIDERED TO BE OUTSIDE THE DESIGN BASES OF THE PLANT. |
| |
| AT 1318 CST ON 03/12/99, THE LICENSEE TRIPPED THE UNIT 2 TD AFW PUMP AND |
| DECLARED IT INOPERABLE, ENTERED TECH SPEC LCO A/S 15.3.4.C.1 (72 HOUR |
| SHUTDOWN LCO), DECLARED THE OTHER THREE AFW PUMPS OPERABLE, AND EXITED TECH |
| SPEC LCO A/S 15.3.0.B. THUS, ONLY THE UNIT 2 PORTION OF THE AFW SYSTEM IS |
| INOPERABLE. |
| |
| THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| |
| ***RETRACTION ON 03/24/99 AT 1128ET BY RANDY HASTINGS TAKEN BY MACKINNON*** |
| |
| An engineering evaluation has subsequently been completed to assess whether |
| the error in adjustment of the 2P-29 discharge throttle valves, which could |
| have accelerated the drain down of supply water to the AFW pumps in the |
| event of an external event induced break in the AFW suction line from the |
| condensate storage tanks, could have resulted in the AFW pumps being |
| inoperable once the pumps were switched to the alternate source of water |
| (service water). This evaluation concludes that the postulated air |
| entrainment mechanism does not result in operation of the AFW pumps outside |
| their design basis before, during or after the pump's suctions are switched |
| to service water. Accordingly, it was not necessary to declare the AFW |
| system out of service and this condition was not reportable pursuant to 10 |
| CFR 50.72. R3DO (Pat Hiland) notified. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35468 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/12/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 17:39[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/12/1999|
+------------------------------------------------+EVENT TIME: 17:31[EST]|
| NRC NOTIFIED BY: JOE RUTTAR |LAST UPDATE DATE: 03/24/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM MOSLAK 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| -Control room personnel access door latch mechanism may not withstand HELB |
| pressure in the turbine building- |
| |
| A licensee preliminary review of an error in an analysis assumption for the |
| pressure applied to a control room personnel access door (#C-49-1) due to a |
| high energy line break (HELB) in the turbine building indicates that the |
| door latch mechanism might not withstand the applied pressure. |
| |
| The control room door has been latched with an alternative latching |
| mechanism and will remain closed against this pressure so there are no |
| current operability concerns. |
| |
| This situation results in a historical condition where Unit 3 may have |
| operated outside its design basis. Engineering evaluation is continuing. A |
| conservative decision has been made to report this condition as a condition |
| outside the design basis of Unit 3 pursuant to 10CFR50.72(b)(1)(ii)(B) |
| pending the results of this evaluation. |
| |
| The Licensee informed the NRC Resident Inspector. |
| |
| * * * UPDATE at 1237 on 03/24/99 by DALE BRODSKY to JOLLIFFE * * * |
| |
| A mockup test of the door latch and hinges was conducted on 03/19/99 at the |
| door manufacturer's facility. This test determined that the door hinges and |
| latch will withstand a total pressure in excess of that resulting from a |
| HELB in the turbine building. Additionally, the pressure on this door will |
| actually be less than the pressure in the turbine building due to its remote |
| location and tortuous path. |
| |
| Therefore, this condition is not reportable to the NRC pursuant to |
| 10CFR50.72(b)(1)(ii)(B) as a condition outside the design basis of Unit 3 |
| and thus, the Licensee desires to retract this event. |
| |
| The Licensee informed the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R1DO Jack McFadden. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35501 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 03/23/1999|
|LICENSEE: J & M TESTING, INC |NOTIFICATION TIME: 13:01[EST]|
| CITY: CHIPLEY REGION: 2 |EVENT DATE: 03/10/1999|
| COUNTY: STATE: FL |EVENT TIME: 14:15[EST]|
|LICENSE#: 1763-1 AGREEMENT: Y |LAST UPDATE DATE: 03/24/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |DON COOL, NMSS EO |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHARLES ADAMS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - AGREEMENT STATE REPORT - TWO LOST PORTABLE NUCLEAR SOIL MOISTURE DENSITY |
| GAUGES - |
| |
| At 1415 on 03/10/99, during a Florida state inspection of J & M Testing, |
| Inc., two portable nuclear soil moisture density gauges were determined to |
| be missing. These are old gauges that were not being used and were last |
| seen during an inventory taken on 12/28/98. The Chipley, FL police |
| department has been notified. |
| |
| Specifications of the gauges are as follows: |
| 1. Manufacturer: CPN, Model: BRC (1977); Serial No C7304NE147; Isotopes: 8 |
| mCi Cs-137; 50 mCi Am-241/Be |
| 2. Manufacturer: CPN, Model: BRC (1974); Serial No C7404NE50; Isotopes: 8 |
| mCi Cs-137; 50 mCi Am-241/Be |
| |
| Charles Adams, FL Bureau of Radiation Control, notified NRC Region 2 (FL |
| Radiological Incident No. FL99-07). |
| |
| ******************** UPDATE AT 0745 ON 03/24/99 FROM CHARLES ADAMS TO |
| TROCINE ******************** |
| |
| The State of Florida Bureau of Radiation Control called to correct the FL |
| Radiological Incident No. The number should have been FL99-037. |
| |
| The NRC operations officer notified the R2DO (Lesser) and NMSS EO (Cool). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35503 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/24/1999|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 10:50[EST]|
| RXTYPE: [3] CE |EVENT DATE: 03/24/1999|
+------------------------------------------------+EVENT TIME: 00:00[CST]|
| NRC NOTIFIED BY: GREGORY SCOTT |LAST UPDATE DATE: 03/24/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Discovery of false information provided by a contract employee granted |
| access to the site. |
| Immediate compensatory measures taken upon discovery. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| Call HOO for more information. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35504 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/24/1999|
| UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 17:37[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 03/24/1999|
+------------------------------------------------+EVENT TIME: 13:00[EST]|
| NRC NOTIFIED BY: THERESA MELTER |LAST UPDATE DATE: 03/24/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|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 Y 99 Power Operation |99 Power Operation |
|2 N Y 99 Power Operation |99 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SECURITY REPORT - |
| |
| PLANT SECURITY COMPUTER SYSTEM DEGRADATION. COMPENSATORY MEASURES |
| IMMEDIATELY TAKEN UPON DISCOVERY. REFER TO THE HOO LOG FOR ADDITIONAL |
| DETAILS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35505 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/24/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:12[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/24/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:26[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/24/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |PATRICK HILAND R3 |
| DOCKET: 0707001 |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KEVIN BEASLEY | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - Power to C-746-Q Building Criticality Accident Alarm System lost when a |
| bird contacted an overhead electrical line - |
| |
| At 1326 CST on 03/24/99, air circuit breaker #23B5B tripped due to a bird |
| contacting an energized portion of the overhead electrical line. As a |
| result of this breaker tripping, power was lost to the C-746-Q Building |
| Criticality Accident Alarm (CAA) System beacons. CAA System audibility for |
| the C-746-Q Building was lost,. However, the breaker tripping did not |
| affect the detectability of the CAA System. Power to the C-746-Q Building |
| was restored and the CAA System was declared operable at 1337 CST. |
| |
| The inaudibility of the CAA Systems is reportable as a 24-hour event report |
| per 10CFR76.120(c)(2). (Paducah Problem Report No ATR-99-1691; Paducah |
| Event Report No PAD-1999-022). |
| |
| The NRC Resident Inspector has been notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35506 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 03/25/1999|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 00:18[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/24/1999|
+------------------------------------------------+EVENT TIME: 21:00[CST]|
| NRC NOTIFIED BY: DAVID H. HANKS |LAST UPDATE DATE: 03/25/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| High Pressure Core Spray (HPCS) Division 3 Diesel Generator declared |
| inoperable. |
| |
| |
| HPCS (Division 3) EDG oil level was discovered to be out of specification |
| low during normal rounds. The Division 3 EDG was conservatively declared |
| inoperable until further evaluations can be performed to determine final |
| disposition of oil leakage from its inspection cover. The licensee entered |
| Technical Specification 3.8.1 (72 hour limiting conditioning of operation). |
| All Emergency Core Cooling systems including HPCS are fully operable. |
| Earlier in the day an undervoltage spike on the electrical grid caused the |
| Division 3 EDG to start. The diesel was properly secured. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35507 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/25/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/24/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/25/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND R3 |
| DOCKET: 0707002 |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
|OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TSR allowed one of two smoke detectors to be inoperable during withdrawal |
| operations when both smoke detectors have to be operable during withdrawal |
| operations. |
| |
| On March 10, 1999, Operations personnel identified a deficiency in a TSR |
| requirement for the Pigtail line Isolation System at ERP (extended range |
| product), LAW (low assay withdrawal), and TAILS, (TSR 2.5.3.4). The TSR |
| required action allowed continued withdrawal operations if one (1) smoke |
| detector was inoperable. The Pigtail Line Isolation System requires two (2) |
| Pyrotronics Smoke Detectors to actuate for the isolation valve to close. |
| Operation personnel initiated a Compensatory Action (CA-99-009) for this |
| anomaly to isolate the withdrawal cylinder and manifold per TSR 2.5.3.4b if |
| one smoke detector is declared inoperable. |
| |
| Initially there was no evidence that the Pigtail Line Isolation System had |
| been allowed to operate any applicable mode (modes II or III) with one or |
| more inoperable smoke head. As a follow up investigation to this |
| deficiency, a search of the BPS system (problem report database) was |
| conducted. This search identified that on July 8, 1998, a Pyrotronic smoke |
| head at the Law IA withdrawal position had been declared inoperable and |
| cylinder filling operations had been allowed to continue. |
| |
| This event is reportable due to a Safety System required by the TSR not |
| being available or operable and no redundant equipment was available to |
| perform the required safety function. |
| |
| The NRC Resident Inspector was notified of this event by the certificate |
| holder. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35508 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/25/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 02:34[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/25/1999|
+------------------------------------------------+EVENT TIME: 01:30[EST]|
| NRC NOTIFIED BY: GRANT FERNSLER |LAST UPDATE DATE: 03/25/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOCAL LEAK RATE TEST PERFORMED ON THE "A" LOOP FEEDWATER CONTAINMENT |
| PENETRATION FAILED. |
| |
| |
| An Appendix "J" Local Leak Rate Test was performed on the "A" Loop |
| Feedwater containment penetration. The penetration piping was unable to be |
| pressurized and therefore the leakrate exceeded Tech Spec limits. The |
| penetration is isolated and the condition does not represent an immediate |
| threat to the public health or safety. |
| |
| The NRC Resident Inspector will notified of this event by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021