ML20128K749

Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl

ML20128K749
Person / Time
Site:	Millstone, Hatch, Davis Besse, Salem, Catawba, Oyster Creek, Crystal River, Rancho Seco, LaSalle, 05000000
Issue date:	07/12/1985
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Thompson H Office of Nuclear Reactor Regulation
References
NUDOCS 8507240212
Download: ML20128K749 (15)

Text

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. JUL 121985 MEMORANDUM FOR: Hugh L. Thompson, Jr. , Director Division of Licensing FROM: Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON JULY 1, 1985 - MEETING 85-11 On July 1,1985, an Operating Reactor Events meeting (85-11) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 12, 1985. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enc 1csure 3.

Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with regard to their respective responsibilities and advise ORAB if the target completion date cannot be met. If an assignee has any questions, please contact D. Tarnoff, x29526. ,

Dennis M. Crutchfield, Assistant Director for Safety Assessment,-DL

Enclosures:

DISTRIBUTION As Stated Central ' Files4 NRC PDR ORAB Rdg cc w/ enc 1: ORAB Members See next page Y

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JUL 121985

. MEMORANDUM FOR: Hugh L. Thompson, Jr., Director Division of Licensing FROM: Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON JULY 1, 1985 - MEETING 85-11 On July 1, 1985, an Operating Reactor Events meeting (85-11) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 12, 1985. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with regard to their respective responsibilities and advise ORAB if the target completion date cannot be met. If an assignee has any questions, please contact D. Tarnoff, x29526.

b Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

Enclosures:

DISTRIBUTION -

_ As Stated Central Files NRC PDR ORAB Rdg l cc w/ enc 1: ORAB Members l See next page TM ORAB:DL SL:0RAB:DL .0 AD  :

l DTarnoff:dm RWe sman GHol/lan CD DCr;tchfield 7/f/85 7 /85 7/7/85 7//2/.85

Hugh L. Thompson, Jr. cc: H. Denton G. Lainas R. Bernero P. Baranowski, RES J. Knight E. Rossi, IE T. Speis R. Hernan C. Heltemes F. Schroeder T. Novak G. Knighton W. Russell D. Silver

, J. Taylor J. Lyons E. Jordan D. Brinkman F. Rowsome E. Weiss W. Minners R. Baer L. Shao A. DeAgazio T. Ippolito J. Stolz S. Varga D. Powell J. Zwolinski E. Butcher E. Sullivan S. Miner D. Beckham A. Bournia G. Edison G. Rivenbark K. Seyfrit G. Lanik T. Murley, R-I J. Nelson Grace, R-II J. Kepper, R-III R. D. Martin, R-IV J. B. Martin, R-V R. Starostecki, R-I R. Walker, R-II C. Norelius, R-III R. Denise, R-IV .

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__ D. Kirsch, R-V .

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l ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-11)

JULY 1, 1985 E. Weiss, IE:DEPER R. J. Wright, DE T. S. Rotella, ORB #5 F. Rosa, NRR/ICSB W. Minners, DST /SPEB R. Wayne Houston, DSI F. Schroeder, DST D. Eisenhut, DD/NRR S. Varga, DL H. Thompson, D/DL G. Rivenbark, DL T. P. Speis, DST R. Karsch, DL R. Woodruff, IE/DEPER J. Stone, IE:VPB R. Baer, IE/DEPER H. Booher, DHFS G. Lanik, IE/DEPER R. Hernan, NRR/PPAS G. Lainas, DL D. R. Powell, IE/DEPER/EAB D. Crutchfield, DL -

J. E. Lyons, DL J. Zwolinski, DL S. Black, DL J. Donohew, Jr., DL R. Singh, IE/EAB F. Miraglia, DL J. Stolz, DL R. Bernero, DL F. Manning, RES/DRA0 G. Holahan, DL H. Ornstein, AE00 R. Wessman, DL S. Rubin, AE0D M. Chiramal, AE00 K. Seyfrit, AE00 A. Bournia, LB#2/DL J. P. Knight, DE

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ENCLOSURE 2 OPERATING REACTOR EVENTS BRIEFING (85-11)

JULY 1, 1985 DAVIS BESSE UNIT 1 -

LOSS OF MAIN FEEDWATER AND AUXILIARY FEEDWATER - UPDATE OF JUNE 9, 1985 EVENT OYSTER CREEK -

UNCONTROLLED LEAKAGE OF REACTOR COOLANT OUTSIDE CONTAINMENT

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RANCHO SEC0 -

RCS HIGH POINT VENT LEAK RANCHO SEC0 -

STARTUP PROBLEMS

SUMMARY

LASALLE UNIT 2 -

EQ MODIFICATION PROBLEMS AND LOSS OF ALL ECCS

DAVIS-BESSE 1 -

LOSS OF MAIN FEEDWATER AND AUXILIARY FEEDWATER UPDATE OF JUNE 9, 1985 EVENT (A DEAGAZIO) NRR 37 INCIDENT INVESTIGATION TEAM (IIT) HAS:

INTERVIEWED LICENSEE PERSONNEL ESTABLISHED A TENTATIVE SEQUENCE OF EVENTS ESTABLISHED LIST OF " QUARANTINED" EQUIPMENT ESTABLISHED TROUBLESHOOTING GUIDELINES IIT IS PREPARING THEIR REPORT l!CENSEE HAS STARTED " TROUBLESHOOTING" EQUIPMENT FAILURES AND MALFUNCTIONS RESPONSES TO CONGRESSMAN MARKEY'S QUESTIONS HAVE BEEN PREPARED REGION MONITORING ONSITE ACTIVITIES -

POSSIBLE SYSTEM / EQUIPMENT PROBLEMS IDENTIFIED SFRCS MANUAL TRIP ON LOW STEAM PRESSURE /VICE LOW S/G LEVEL TERRY TURBINE PERFORMANCE VALVE TORQUE SWITCHES FUSES PULLED ON STARTUP FW PUMP

0YSTER CREEK - UNCONTROLLED LEAKAGE OF REACTOR COOLANT OUTSIDE CONTAINMENT JUNE 12, 1985 (D. POWELL, IE)

WITH REACTOR AT 99% POWER, FAILURE OF THE ELECTRIC PRESSURE REGULATOR CAUSED A TURBINE BYPASS VALVE TO OPEN RESULTING IN A REACTOR PRESSURE DECREASE, FOLLOWED BY MSIV CLOSURE AND REACTOR SCRAM.

SCRAM DISCHARGE VOLUME DRAIN VALVES FAILED TO FULLY SHUT /

SEAT CAUSING REACTOR COOLANT TO BE DISCHARGED TO THE REACTOR BUILDING DRAIN TANK.

RELEASE OF STEAM FROM FLOOR DRAINS AND PAINT BLISTERING ON HOT PIPE CAUSES PORTION OF REACTOR BUILDING DELUGE SYSTEM TO ACTIVATE SCRAM SIGNAL NOT RESET FOR 36 MIN ALLOWING CONTINUOUS REACTOR COOLANT FLOW TO THE DRAIN TANK. CAUSE WAS 600 PSI I INTERLOCK ON MSIV CLOSURE / LOSS OF CONDENSER VACUUM.

SAFETY SIGNIFICANCE - (1) LOCA OUTSIDE CONTAINMENT, (2) POTENTIAL EQUIPMENT MALFUNCTION DUE TO FIRE DELUGE SYSTEM, (3) EXCESSIVE CRD SEAL TEMPERATURES.

CAUSE-VALVE SPRING ON VALVE V15-134 (VELAN) VALVE UNDERSIZED

-VALVE V15-121 (VALTAK) STROKE DISTANCE INSUFFICIENT TO TIGHTLY SEAT THE VALVE. (1/8" OPENING)

-!MPROPER POST-INSTALLATION TESTING OF VALVES CORRECTIVE ACTIONS - REPLACED 400 LB SPRING WITH 1100LB SPRING, ADJUSTED VALVE STROKE DISTANCE CHECKED CRD SEALS FOR DAMAGE, CHECKED EQUIPMENT, NO DAMAGE FOUND.

NRC FOLLOWUP ACTION - IE NOTICE IN PREPARATION.

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o RANCHO SEC0 - RCS HIGH POINT VENT LEAK JUNE 23, 1985 (G, RIVENBARK, NRR) l l -

PLANT IN HOT STANDBY RESTARTING FROM A REFUELING OUTAGE.

l 20 GPM NON-ISOLATABLE PRIMARY COOLANT LEAK ON HIGH POINT YENT ON B STEAM GENERATOR HOT LEG TMl MODIFICATION INSTALLED 1983 REFUELING OUTAGE.

l 120* THRU WALL LEAK AT WELD CAUSE APPEARS TO BE MISSING SUPPORTS AND FATIGUE FAILURE l -

LICENSEE ACTIONS:

STRESS ANALYSIS TO IDENTIFY OVERSTRESSED AREAS (BOTH HOT LEG VENTS)

REPAIR SYSTEMS INSTALL SUPPORTS INSPECT AND EVALUATE OTHER SYSTEMS .

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l REGION V CONSIDERING ENFORCEMENT ACTION I

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RANCHO SECO - STARTUP PROBLEMS

SUMMARY

(G. RIVENBARK, NRR)

- MARCH 15, 1985 SHUTDOWN FOR 90 DAY REFUELING OUTAGE

- JUNE 1, 1985 EDG CONTROL CIRCUIT PROBLEM - DESIGN ERROR PRESENTED AT JULY 12, 1985 BRIEFING

- JUNE 5, 1985 REACTOR TRIP BREAKER FAILURE PRESENTED AT JULY 12, 1985 BRIEFING

- JUNE 11, 1985 NUCLEAR SERVICE COOLING WATER PUMP FEEDER BREAKER TRIPPED ALSO TRIPPED JUNE 12 AND 13, 1985 REPLACED BREAKER

- JUNE 12, 1985 200 GALLON WATER LEAK INTO REACTOP

, BUILDING. RELIEF VALVE ON LET DOWN ,

SYSTEM LIFTED REPAIRED RELIEF VALVE

- JUNE 14, 1985 REACTOR CRITICAL

- JUNE 18, 1985 SHUT DOWN FROM 15% POWER OIL BLOCKAGE IN MAIN TURBINE LUBE OIL SYSTZM

- JUNE 23, 1985 NON ISOLATABLE LEAK IN HIGH POINT VENT IN B STEAM GENERATOR HOT LEG CURRENT PLANS FOR STARTUP UNCERTAIN l

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LA SALLE UNIT 2 - E0 MODIFICATION PROBLEMS AND LOSS OF ALL ECCS 6/5 - 6/10, A, BOURNIA (NRR)

PROBLEM - NO ECCS AVAILABLE FOR FIVE DAYS AS A RESULT OF BREAKDOWN IN MANAGEMENT CONTROL AND QA DURING INSTALLATION OF RV LEVEL SWITCHES AS PART OF EQ UPGRADE.

EVENT OCCURRED WHILE CHANGING SWITCHES FROM NON-QUALIFIED TO QUALIFIED. CAUSED BY: ERROR IN DESIGN DRAWINGS INADEQUATE INSPECTION INADEQUATE TESTING SAFETY SIGNIFICANCE - PLANT WAS IN COLD SHUTDOWN

- REPEAT OCCURRENCE OF INADEQUATE MODIFICATION CONTROL

, REPEAT OCCURRENCE OF INADEQUATE MODIFICATION CONTROL ,

PROBLEM DISCOVERED BY LICENSEE DURING UNRELATED ACTIVITY IN

• PREPARATION FOR LEAK RATE TESTING.

CORRECTIVE ACTIONS - REGION lil IS AWAITING THE LICENSEE'S OFFICIAL RESPONSE REGARDING CORRECTIVE ACTICNS.

ENFORCEMENT MEETING WAS HELD ON JUNE 24, 1985 WITH THE t

LICENSEE. POTENTIAL ESCALATED ENFORCEMENT BEING CONSIDERED.

THESE CHANGES SCHEDULED FOR UNIT 1 IN SEPTEMBER 1985 IE INVESTIGATING TO DETERMINE IF GENERIC ERROR ON DESIGN DRAWINGS FROM G.E.

p. .

ENCLOSURE 3 OPERATING REACTOR EVENTS MEETING FOLLOWUP ITEMS AS OF MEETING 85-11 CLOSED BY:

MEETING FACILITY / RESPONSIBLE TASK COMPLETION DOCUMENT /

l NO./DATE EVENT DIV./ INDIVIDUAL DESCRIPTION DATE MEETING, ETC. COMME liTS 8/7/84 Salem 2-Stuck open relief DL-D. Fischer Determine if Velan (PORV) 7/30/85 AEOD report valve /ECCS actuation block valve qualified to in preparation July 25, 1984 close against 7/25/84 will address steam blowdown transient that issue.

at Salem 2. Check EPRI Test Program results.

4/10/84 Ranco Seco-Main DL-P. Kadambi Summarize B&W licensing 7/30/85 Staff review generator hydrogen responses to questions of B&W explosion - partial subsequeist to Rancho Seco Owners Group '

loss of NNI loss of NNI event and Submittal of March 19, 1984 present at follow-up 1/11/85 is in OR Events Briefing. progress.

'd 1/3/85 Crystal River 3 ICSB-F. Rosa Consider need for 7/30/85 ICSB is Temporary loss of NNI additional requirements considering December 28, 1984 on alarms / annunciators Oconee 1. loss of annuncia.

(4/25/84) in analysis of i requirements.

5/7/85 Catawba 2-Both RHR DL-K. Jabbour Follow-up briefing after 8/1/85 PM is awaiting trains overpressurized evaluation of overpress. licensee's April 19, 1985 effects on various submittal.

. , systems and corrective actions.

CLOSED BY:

MEETING FACILITY / RESPONSIBLE TASK COMPLETION DOCUMENT /

NO./DATE EVENT DIV./ INDIVIDUAL DESCRIPTION DATE MEETING, ETC. COMMENTS '

5/7/85 Catawba 2-Volume control DL-K. Jabbour Schedule meeting with 8/1/85 Closed.

tank failure R-II and DHFS (with Telecon of April 20, 1985 licensee if appropriate) 6/26/85 '

i to evaluate operator with DHFS activities. and R-II.

5/7/85 Salem 2-Pressure / DL-S. Varga Discuss with R-I the 7/7/85 Closed.

temperature transient management aspects of S. Varga April 13, 1985 recent events at Salem. discussed w/R-I, which plans to monitor via routine SALP program.

5/7/85 Millstone 2-Eddy current ORAB/DE Review SCOG letter on 8/1/85 MTEB is test of steam generator E. Murphy / eddy current testing reviewing tubes, April 10, 1985 H. Conrad issue, in view of EPRI 5/13/85 i Millstone 2 findings. letter and l will address I follow-up issue.

5/30/85 Hatch 1-Stuck Open ORAB-M. Caruso Will develop TIA to 7/30/85 In progress.

Safety Relief Valve coordinate IE Notice and further investigative efforts.

1 CLOSED BY:

MEETING FACILITY / RESPONSIBLE TASK COMPLETION DOCUMENT /

NO./DATE EVENT DIV./ INDIVIDUAL DESCRIPTION DATE MEETING, ETC. COMMENTS 85-10 6/12/85 Davis Besse-Loss of all DSI-0. Parr Re-examine staff review 8/30/85 In progress main feedwater and DL-A. DeAgazio of acceptability / diversity auxiliary feedwater of Davis Besse AFW system.

June 9, 1985 85-10 6/12/85 Davis Besse-Loss of all DST-T. Speis Determine status of 8/30/85 Status of Remaining two main feedwater and DL-D. DeAgazio implementation of TMI implement. issues auxiliary feedwater items, generic issues, of TMI (generic June 9, 1985 MPAs at Davis Besse issues issues & MPAs that may be related closed - in progress.

to 6/9/85 event. H. Thompson to H. Denton memo of 6/12/85.

85-10 6/12/84 Davis Besse-loss of all DL-A. DeAgazio Provide H. Denton with 8/30/85 In progress.

main feedwater and (1) comparison between auxiliary feedwater Davis Besse 1 and THI-1 June 9, 1985 of TMI action plan implementation status; (2) comparison of MFW and AFW systems at Davis Besse 1 and TMI-1; (3) status of startup FW pump upgrade.

l CLOSED BY:

MEETING FACILITY / RESPONSIBLE TASK COMPLETION DOCUMENT /

NO./DATE EVENT DIV./ INDIVIDUAL DESCRIPTION DATE MEETING, ETC. COMMENTS 85-11 7/1/85 Oyster Creek-Uncontrolled DST-M. Minners Pressure isolation valve 8/30/85 leakage of reactor coolant has lead; testing requirement to outside containment DE-F. Cherny be addressed in CRGP June 12, 1985 will assist briefing.

85-11 7/1/85 Oyster Creek-Uncontrolled DHFS-H. Booher Determine efficacy 8/30/85 leakage of reactor coolant of EPG/ operator action and outside containment excessive response time.

June 12, 1985 85-11 7/1/85 Rancho Seco-RCS high point DL-S. Miner Determine status of 8/30/85 vent leak, June 23, 1985 IEB 79-14.

85-11 7/1/85 Rancho Seco-Startup DL-S. Miner Schedule conference call 7/12/85 problems-June 1985 with Region and licensee prior to restart to determi.e plant read Ness for oper dtns.

85-11 7/1/85 LaSalle 2-EQ modification IE-R. Baer Consider issuance of 8/30/85 problems and loss of all IE Notice.

ECCS June 5-10, 1985

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