ML20148S382
| ML20148S382 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Three Mile Island, Braidwood, Rancho Seco, 05000000 |
| Issue date: | 03/31/1988 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| IEB-79-09, IEB-79-9, IEB-80-10, IEB-83-04, IEB-83-08, IEB-83-4, IEB-83-8, IEIN-83-18, IEIN-83-76, IEIN-84-29, IEIN-85-058, IEIN-85-58, OREM-88-013, OREM-88-13, NUDOCS 8804180374 | |
| Download: ML20148S382 (18) | |
Text
{{#Wiki_filter:/i W ll N MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING March 29, 1988 MEETING 88 13 On March 29, 1988 an Operating Reactors Events meeting (88-13) was held to brief senior managsrs from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on March 22, 1988. The list of attendees is included as Enclosure 1. The events discussed and the significant elements of these events 'a're presented in Enclosure 2. Enclosure 3 presents a report-to-date of long-term followup assignments and a sumary of reactor scrams. No significant events were identi-fied for input to NRC's performance indicator program. Three events were sug-gested for long-tenn followup. Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
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cc: T. Murley J. Sniezek F. Miraglia J. Forsyth, INPO E. Jordan S. Sands E. Peckjord R. Hernan W. Russell, RI M. Masnik B. Davis, RIII G. Kalman J. Nelson Grace, RII M. Slosson R. D. Martin, RIV J. Stoltz J. B. Martin, RV G. Knighton W. Kane, RI R. Capra L. Reyes, RII D. Muller E. Greenman, RIII J. Callan, RIV D. Kirsch, RV S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan L. Shao J. Partlow B. Grimes F. Congel E. Weiss S. Black T. Martin J. Stone R. Hernan H. Bailey J. Guttmann A. Thadani S. Rubin a e
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MAR 31 W MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING March 29, 1988 - MEETING 88-13 On March 29, 1988 an Operating Reactors Events meeting (88-13) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which , occurred since our last meet'. ig on March 22, 1988. The list of attendees is included as Enclosure 1. The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents a report-to-date of long-term followup assignments and a sumary of reactor scrams. No significant events were identi-fied for input to NRC's performance indicator program. Three events were sug-gested for long-tenn followup. I k W - yheLanning,ChieD Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated. cc w/Enclo.: - See Next Page
. l ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-13) i March 29, 1988 NAME ORGANIZATION NAME ORGANI7ATION W. Lanning NRR/00EA S. Varga NRR/DRP P. Baranowsky NRR/D0EA G. Klingler NRR/PMAS C. Schulten NRR/00EA J. Thompson NRR/DOEA M.L. Reardon NRR/DOEA H. Berkow NRR/PDP-2 T. Silko AEOD J. Stone NRR/RVIB M. Padovana RES/INSP D. Crutchfield NRR/DRSP N. Fields NRR/DOEA D. Neighbors NRR/PD1-1 0.D.T. Lynch, Jr. NRR/PRPB D. Moran OSP/TVA D.R. Muller NRR/PD3-2 S. Sands NRR/PD3-? G. Holahan NRR/DRSP C. McCracken NRR/EAD F. Miraglia NRR/ADP T.M. Novak AEOD/DSP C.E. Rossi NRR/DOEA J. Rce NRR/DLPQ J. Sniezek NRR P
ENCLOSURE 2 OPERATIN.G REACTORS EVENTS BRIEFING 88-13 l LOCATION: 12-B-11 WHITE FLINT TIIESDAY, MARCH 29, 1988, 11:00 A.M. l THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 21449, BRAIDWOOD 182 USE OF UN0llALIFIED LUBRICANTS. GENERIC ISSUE uE CIRCUIT BREAKER PROBLEMS INDIAN POINT 2 REFUELING WATER STORAGE TANK l.EAKAGE TO RIVER e
BRAIDWOOD 1/2 UN00ALIFIED GREASE IN MOTOR OPERATORS MARCH 29, 1988 PR03LEt1 MIXING OF LITHIUM-LEAD AND CALCIUM-BASED GREASES IN THE GEAR BOXES OF LIMITOROUE MOTOR OPERATORS CAN RESULT IN CHEMICAL REACTIONS THAT REDUCE THE LUBRICATING PROPERTIES OF THE GREASE - CAUSE INADEOUATE MAINTENANCE IN CHANGING GREASE, PROCEDURES DID NOT PROVIDE GUIDANCE ON METHOD TO BE USED FOR CHANGING GREASE. INADE0VATE FEEDBACK 0F OPERATING EXPERIENCE, POTENTIAL 0A/0C BREAKDOWN. SAFETY SIGNIFICANCE LIMITOROUE MOTOR OPERATORS WITH SAFETY APPLICATIONS COULD BE SUSCEPTIBLE TO COMMON CAUSE FAILURE, DISCUSSI0!I
- PROBLEM AT BRAIDWOOD FOUND AS A RESULT OF Rill EO INSPECTION MARCH 4, 1988, IDENTIFED AT BYRON 1 IN 1985,
- EPRI REPORT NP-4916 (1/87) IDENTIFIED THE INCOMPATIBILITY OF THESE GREASES,
- THE REVISED LIMITOROUE PROCEDURES AND RECOMMENDATIONS ON THE CHANGING 0F LUBRICANTS FOR MOV OPERATORS MANUFACTURED AFTER 1979 ;
WERE NOT HIGHLIGHTED AND SOME LIMITOROVE CUSTOMERS DID NOT RECEIVE THE REVISED PROCEDURES AND RECOMMENDATIONS,
*INP0ISSUEDSER84-07,"MIXINGOFGSEASESINLIMITOROUEMOTOROPERATORS MAY CAUSE OPERATOR FAILURE",
- WHEN MIXED TOGETHER, THE GREASES REACT CHEMICALLY OVER TIME AND MAY RESULT IN THE FOLLOWING:
- BREAKDOWN INTO A "DRIED MUD-LIKE" SUBSTANCE I
CONTACT: S. SANDS
REFERENCE:
MORNING REPORT 03/24/88 i
l.
- BREAKDOWN INTO A WATERY L10VID, OR
- SEPARATION INTO A HARD CAKE-LIKE SUBSTANCE AND A WATERY LIQUID.
- THIS PROBLEM !MPACTED ALL SAFETY-RELATED LIMITOROUE VALVE OPERATORS, N0 KNOWN OPERATIONAL PROBLEMS TO DATE,
- 15% OF THE VALVES INSPECTED THUS FAR HAD SOME EVIDENCE OF CONTAMINATION,
- IN THOSE 15% SAMPLED, SOME HAD UP TO 6% CONTAMINATION (I.E.,
LITHIUM BASE IN THE CALCIUM-BASED GREASE),
- CURRENT STATUS: ALL LIMITOROUE VALVE OPERATORS WILL UNDERG0 A VISUAL INSPECTION,
- THOSE IDENTIFIED AS HAVING POSSIBLE CONTAMINATION WILL BE ANALYZED BY PERFORMING AN ASTM PENETRATION TEST ON THE GREASE, FOLLOWUP REGION ISSUED CAls TO BOTH UNITS: UNIT 1 WAS SHUTDOWN FROM 25% POWER; UNIT 2 PREVIOUSLY SHUTDOWN BY E0 PROBLEMS WITH I BUNKER RAMO PENETRATION.
MEETING MARCH 28 WITH LICENSEE, REGION Ill AND NRR (BY TELEPHONE) i TO DISCUSS RES0 Lilt 10N OF THIS ISSUE AT BRAIDWOOD, CHEMICAL ENGINEERING BRANCH HAS LEAD FOR FOLLOWUP, , VIB WILL D0 INSPECTION AT LIMITOROUE IN EARLY MAY, e
GE CIRCUIT BREAKER PROBLEM THREE MILE ISLAND 1 AND RANCHO SEC0 MARCH 16 AND MARCH 23, 1988 PROBLEM UNDERVOLTAGE TRIP ATTACHMENT (UVTA) ON GE REACTOR TRIP BREAKERS FAILED DURING ROUTINE SURVEILLANCE, 1 1 CAUSE BINDING OR MISALIGNMENT OF LINKAGE IN UVTA. SIGNIFICANCE ATWS IMPLICATIONS, DISCUSSION o ON MARCH 16, 1988 A TMI REACTOR TRIP BREAKER, GE MODEL AK 1-15-2, FAILED A MONTHLY SURVEILLANCE DUE TO AN INOPERABLE UVTA, o ON MARCH 23, 1988 A RANCHO SECO PEACTOR TRIP BREAKER, GE MODEL AK 2-25, FAILED A MONTHLY SURVEILLANCE DUE TO AN INOPERABLE UVTA, o THE TMI RTB UVTA FAILED BECAUSE THE TRIP PADDLE HAD JAMMED AGAINST THE ARMATURE PREVENTING THE arf 1ATURE'S MOVEMENT. l 0 THE RANCHO SEC0 FAILURE TO TRIP ALSO RESULTED FROM MECHANICAL BINDING. ! o IN BOTH UVTAs THE SMALL CIRCULAR DISK AT THE END OF EACH ARMATURE WAS FOUND TO HAVE BEEN IMPROPERLY INSTALLED. O PRIOR ACTUATIONS HAVE CAUSED AREAS OF UNHSUAL WEAR BETWEEN THE DISK l AND THE TRIP PADDLE WHICH, IN TURN, FACILITATED MECHANICAL BINDING, RESULTING IN FAILURE OF THE UVTAs, o DURING BOTH INCIDENTS THE SHUNT TRIP ATTACHMENT OPERATED PROPERLY. o BREAKERS AT BOTH UNITS WERE REPLACED. o THE TMI L-ICENSEE IS EXAMINING THE FAULTY BREAKER.FOR ROOT CAUSE DETERMINATION, THE RANCHO SECO LICENSEE IS RETURNING THE FAULTY BREAKER TO GE FOR INSPECTION, { l 0 THE UVTA ON GE TYPE AK 2 BREAKERS HAS BEEN THE SUBJECT OF THREE IE BULLETINS (IEB NOS. 79-09, 83-04, AND 83-08) AND FOUR IE NOTICES (IE IN 83-18, IE-76, 84-29, AND 85-58 (SUPPLEMENT)), CONTACT: N. FIELDS
REFERENCE:
MORNING REPORT 03/17/88, PRELIMINARY NOTIFICATION 03/?u/88 (PNO-V-88-23)
9
* -2 FOLLOWUP 0 ADD OfAL GENER C C Ut Cp ton UhCER CONS DEPIT of O
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INDIAN POINT UNIT 2 REFUElfNG WATER STORAGE TANK LEAKAGE TO RIVER MARCH 28, 1988 PROBLEM 8400 GALLONS OF WATER LEAKED FROM REFUELING WATER STORAGE TANK INTO THE HUDSON RIVER. SIGNIFICANCE THE WATER WAS CONTAMINATED, WITH APPR0XIMATELY 0.03 CI 0F CoS8 AND Co60 (0.1% MPC) 0F CONTAMINATION BEING RELEASED. DISCUSSION
- ON WEDNESDAY, MARCH 23, 1988 OPERATORS TOPPED OFF THE RWST TANK (395,000 GALLON CAPACITY). (TECH SPEC VALUE: 345,000)
- ON FRIDAY, MARCH 25, 1988 THE NIGHT SHIFT OPERATORS DETERMINED THEY HAD A RWST LEAK WHEN THE TANK NEEDED TOPPING 0FF AGAIN.
- A 1.5 GPM LEAK 0F RWST WATER INTO THE STEAM HEATING C0!L CONDENSATE RETURN LINE RESULTED IN THE LOSS OF RWST INVENTORY OVER A 90 HOUR PERIOD.
THE LEAK WAS ISOLATED AT 3:00 AM ON SATURDAY.
- A HOLDING TANK IS LOCATED IN THE AUXILIARY BUILDING WHICH FEEDS A i HOLDING TANK FOR ALL NON-NUCLEAR CONDENSATE RETURN LOCATED IN THE TilRBINE BUILDING.
- STEAM IS SUPPLIED TO THE RWST HEATING COILS FROM THE NON-NUCLEAR STEAM HEATING SYSTEM (NSS) B0ILER WITH MOST OF THE CONDENSATE RETURNED TO THE NSS BOILER AND THE EXCESS BEING DELIVERED TO A CANAL RETURN TO THE !
HUDSON RIVER.
- LAST CYCLE THEY ALSO HAD A H0LE WHICH WAS REPAIRED DURING THE LAST OUTAGE.
- THE AUXILIARY BUILDING TANK IS INSTRUMENTED WITH RADIATION MONITORS, HOWEVER THESE MONITORS ARE NOT REQUIRED TO BE OPERABLE BY TECHNICAL SPECIFICATIONS.
- THE LICENSEE HAS BEEN MONITORING TH,E AUXILIARY TANK CONTAMINATION LEVELS I ON A WEEKLY BASIS BECAUSE THE RADIATION MONITORS WERE IN0PERABLE. THE i LAST SAMPLE WAS TAKEN ON TUESDAY DURING THE DAY SHIFT. BULLETIN 80-10 RESPONSE APPEARS TO BE ADE0VATE.
THIS EVENT WAS REPORTED ON NATIONAL TELEVISION. CONTACT: C. SCHULTEN
REFERENCE:
ERN-11870, MORNING REPORT 03/28/88
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- 1. PLANT SPECIFIC OATA BASEC CN INITIAL REVIEll 0F E0.72 REPORTS FOR THE WEEX OF INTEREST. PERIOD IS MIONIGHT SUNDAY THROUGH MIDNIGHT: SUNDAY SCRANS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R00 MOTION AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUT 00WN IN ACCORDANCE WITH A PLANT PROCECURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.
- 2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UhRELATED TO CAUSE OF SCRAM.
- 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR PROCEDURAL DEFICIENCIES. AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING) SYSTEM DESIGN, OR UNKNOWN CAUSE. , 't i
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