ML20151K736

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Summary of Operating Reactors Events Meeting 88-15 on 880412.List of Attendees & Viewgraphs Encl
ML20151K736
Person / Time
Site: Fermi, 05000000, Fort Saint Vrain
Issue date: 04/15/1988
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-88-015, OREM-88-15, NUDOCS 8804210394
Download: ML20151K736 (20)


Text

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i APR i. 6 ! ant MEMORANDUM FOR: Charles E. Rossi, Director ,

Division of Operational Events Assessment Office of Nuclear Reactor Regulation 1

) FR0ft: Wayne Lanning, Chief i Events Assessment Branch l l Division of Operational Events Assessment 1

' Office of Nuclear Reactor Regulation

SUBJECT:

THE OPERATING REACTORS EVENTS ftEETING April 12, 1988 MEETING 88 15 ,

l

! On April 12, 1988 an Operating Reactors Events meeting (88 15) was held to brief senior managers from NRR, RES, AE00 and Regional Offices on events which occurred since our last meeting on April 5, 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. One significant event was identified for input to NRC's performance irdicator program. No events were

suggested for icng. term followup. ,

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l Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Re.gulation

Enclosures:

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DATE :04//e//88 :04/dl/88  :  :  :  :

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T. Murley J. Sniezek F. Miraglia J. Forsyth, INPO E. ilordan M. Virgilio E. Beckjord T. Quay W. Russell, R! K. Heitner B. Davis, RI!! J. Calvo J. Nelson Grace, Rii R. D. Martin, RIV J. B. Martin, PV W. Kane, RI L. Reyes, RII E. Greenman, RIII J. Callan, RIV

0. Kirsch, RV S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan L. Shao J. Partlow B. Grimes F. Congel E. Veiss S. Black T. Martin J. Stone R. Fernan H. Bailey J. Guttrann A. Thadani S. Rubin l

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UNITED STATES '

E o NUCLEAR REGULATORY COMM! JION h  : WASHINGTON, D. C. 20555 s o #

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APR14 M '

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ItENORANDUM FOR: Charles E. Rossi, Director j , .

Division of Operational Events Assessment c '

Office of Nuclear Reactor Regulation . ,

7 FROM: Wayne Lanning, Chief Events Assessment Branch -

Division of Operatienal Events Assessment j 4 Office of Nuclear Reactor Regulation i ,

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING April 12, 1988 - MEETING 88-15 I s

On April 12, 1988 an Operating Reactors Events meeting (88-15) was held to \r ,

brief senior managers from NRR, RES, AE0D and Regional Offices on events which q) a; occurred since our last meeting on April 5, 1988. The list of attendees is '

include:d 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 summary of reactor scrams. One significant event was identified for input to NRC's performance indicator program. No events were ,

suggested for long-term followup. ,

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Wayne Lanning, Chief i Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

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, ENCLOSilRE 1

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, LIST OF ATTENDEES f

bb' RATING REACTGRS EVE:iTS BRIEFING (88-15)

April IP, 1988 NAM" ORGANIZATION NAME ORGANIZATION W.'Lanning *$2/DOEA J. Roe NRR/DLP0 H.L. Reardon NAR/DOEA R. Karsch NRR/D0EA T. Purley NI R T. Quay NRR/DRSP D. Cittchfield NRR/DRSP V. Benaroya AEOD/DSP C.J Haughney NR3./DRIS L. Rubenstein NRR/DRSP T. Martin OEDO J. Zwolinski NRR/ DEST R. Lobel .NRA/COEA G. Holahan NPR/DRSP M. Callahan GPA/CA S. Newberry NRR/ DEST J. Guttlar.n SECY R. Emch NRR/00EA J, Scarborough OCM/KR E. Butcher NRR/POEA C.S. Menson NRR/PREB T.P. Gwynn OCM/LZ B. Watson RII C. Ader OCM/TP E. Branagan NRR/PPPB G. Klingler NRR/PMAS R. k'codruff NPP./CGEA T. Dunning NRR/D0EA T. Elsasser 0CM//C B. Boger NRR/ADRI C. Miller CCM/F9 R. Scholl NRR/DOEA P. Ba anossky NR4/D0EA

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ENCLOSURE 2,.  ;

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OPERATING REACTORS EVENTS BRIEFING 88-15 i

LOCATION: 12-B-11 WHITE FLINT l TilESDAY, APRIL 12, 1988, 11:00 A.M.

THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 21449, FT, ST VRAIN RCS LEAKAGE l

FERfil 2 RECENT PROBLEMS l

i GENERIC ISSUE GENERIC LETTER 87 ALTERNATIVES 10 STANDARD TECH SPEC REQUIREMENTS APPLICABLE TO LIMITING CONDITIONS FOR OPERATION & SURVEILLANCE REQUIREMENTS l

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FORT ST VRAIN RCS LEAKAGE APRIL 7, 1988 PROBLEM

- SMALL llNPLANNED RELEASE OF RADI0 ACTIVITY WHILE THE REACTOR WAS AT 72% POWER ON 4/7/88, CAUSE

- A NEOPRENE EXPANSION JOINT IN ONE OF THE CIRCULATING WATER LINES FAILED FLOODING ROTH PUMP MOTORS, SIGNIFICANCE

- CRACKS IN CORE SUPPORT FLOOR LINER.

- WITH INCREASING RCS PRESSURE AND iEMPERATURE, A PATH EXISTS FOR VENT!NG RADIDACTIVITY FROM THE PCRV TO THE ENVIRONMENT.

DISCUSSION

- BOTH CIRCULATING PUMPS AND MOTORS ARE IN AN OUTDOOR PIT,

- THE CIRCULATING LINES ARE APPR0XIMATELY 40 INCHES IN DIAMETER.

- A 4 FT CIRCUMFERENTIAL RIP DEVELOPED IN ONE OF THE EXPANSION JOINTS CAUSING LOSS OF THE COOLING TOWER AND MAIN CONDENSER.

- THE UNIT COOLED DOWN ON STEAM RELIEF VALVES AND DHR,

- THE CONCRETE CORE SUPPORT FLOOR IS SHEATHED (LINER) AND COOLED,

- COOLING SYSTEM LEAKS REQUIRED INSTALLATION OF A VENT SYSTEM WHICH VENTS TO THE RADI0 ACTIVE WASTE GAS SYSTEM,

- LINER LEAKS RESULT IN RADI0 ACTIVITY BEING TRANSFERRED FROM THE PCRV TO THE ENVIRONMENT VIA THE CORE SUPPORT FLOOR AND ITS VENT SYSTEM.

FOLLOWUP

- THE LICENSEE IS PLANNING MODIFICATIONS TO REDUCE THE LIKELIHOOD OF UNPLANNED RELEASES OF RADI0 ACTIVITY,

- REGION IV HAS THE LEAD, CONTACT: ROGER WOODRUFF

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FERMI !!NTT 2 RECENT PROBLEMR APRIL 9, 1988 PROBLEM OPERATOR ACTIVITIES RESULTED IN THE FLOW 0F B0 RATED WATER INTO THE l

REACTOR VESSEL, LOSS OF SHUTDOWN COOLING, RHR PUMP DEAD HEADED, j MLS1 THE CAUSE GF THE BORATED WATER PROBLEM WAS IMPROPER CONTROL ROOM l INSTRUCTIONS FOR A REQUEST TO DEVIATE FROM APPROVED SURVEILLANCE PROCEDURES, THE CAUSE OF THE RHR PUMP PROBLEM IS STILL'UNDER INVESTIGATION, SIGNIFICANCE LICENSEE HAS IN PLACE A "CONTROL OF LICENSE ACTIVITIES" PROGRAM THAT RESULTED FROM A 1987 CHANGE IN OPERATING MODE EVENT CAUSED BY IMPROPER OPERATOR ACTIVITIES, DISCUSSION BORATED WATER PROBLEM:

  • PLANT IN COLD SHUTDOWN,
  • STANDBY LIQUID CONTROL SYSTEM SURVEILLANCE WAS BEING PERFORMED WHICH REQUIRES A S0ulB VALVE TO BE FIRED WITH THE DEMINERALIZED i WATER TANK ALIGNED FOR INJECTION,
  • THE OPERATOR DECIDED TO CONTINUE THE SURVEILLANCE AFTER THE SOUlB FIRING WHEN A MAINTENANCE SCHEDULING PROBLEM CAUSED A DELAY IN REPLACING THE SOUIB VALVE,
  • PERMISSION HAD NOT BEEN RECEIVED FROM THE CONTROL ROOM TO REALIGN TO THE SBLC TANK,
  • BORATED WATER PASSED THROUGH THE POSITIVE DISPLACEMENT PUMP INTO THE REACTOR VESSEL DUE TO THE DRIVING HEAD FROM THE ELEVATED TANK,
  • APPROXIMATELY 130 GALLONS WENT ONTO THE VESSEL, NO REASON HAS BEEN GIVEN FOR WHAT ACTION (S) TERMINATED THE EVENT, CONTACT: CARL SCHULTEN

REFERENCE:

50,72 #11980

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RHR SHUTD0llN COOLING PROBLEM:

  • PLANT WAS IN SHUTDOWN COOLING (COLD SHilTDOWN) WITH ONE OF TWO LOOPS OUT-OF-SERVICE FOR NAINTENANCE
  • THE MINIMUM FLOW VALVE OF THE OPERABLE S/D COOLING LOOP l!AS ISOLATED PER A LICENSEE 50.59 EVALUATION
  • THE MIN FLOW VALVE HAD FAILED ITS LEAK RATE TEST.
  • 50.59 EVALUATION REASONED THE-RHR PUMP WOULD TRIP IF THE SUCTION VALVE WERE ISOLATED ON THE RECEIPT OF NORMAL RHR S/D COOLING ISOLATION SIGNALS
  • THE INJECTION VALVE ISOLATED (BUT NOT THE SUCTION VALVE) WITHOUT TRIPPING THE PUMP.
  • THE'RHR PUMP RAN FOR 30-35 MINUTES WITH THE PUMP INJECTION VALVE ISOLATED
  • RHR PUMP LIFE MAY BE SIGNIFICANTLY REDUCED.

FOLLOWQP THE LICENSEE IS SCHEDULED TO MEET WITH REGION 111 AND DISCllSS THESE EVENTS l

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GENERIC LETTER 87-09 i

CHANGES TO SECTIONS 3.0/4.0 0F TECH SPECS SPEC 3.0,4 - LCO COMPLIANCE FOR MODE CHANGES REMOVE UNNECESSARY RESTRICTIONS ON MODE CHANGES l

l SPEC 4.0,3 - MISSED SURVEILLANCE IS DEFINED AS FAILURE TO SATISFY OPERABILITY REQUIREMENTS OF LC0 REDUCE UNNECESSARY FORCED SHUTDOWNS SPEC 4.0.4 - SURVEILLANCE COMPLIANCE FOR MODE CHANGES MINOR CHANGE FOR CONSISTENCY OF REQUIREMENTS CONTACT: TOM DilNNING

SPECIFICATION 3.0.4 EXISTING REQUIREMENT PRECLUDES A CHANGE IN MODES IF LCO IS NOT MET WITP0llT RELIANCE ON '

ACTION REQUIREMENTS l NUMEROUS EXCEPTIONS 10 SPEC 3,0.4 ALTERNATIVE REQUIREMENT i ALLOWS A CHANGE IN MODES IF ACTION RE0lilREMENT PERMITS UNLIMITED CONTINUED OPERATION l

PRECLUDES A CHANGE IN MODES IF ACTION REQUIREMENTS ENDS WITH A FORCED SHUTDOWN REMOVE EXCEPTIONS TO SPEC 3.0.4 IN INDIVIDUAL SPECIFICATIONS SPECIFICATION 4.0.3 EXISTING REQUIREMENT FAILURE TO PERFORM A SURVEILLANCE WITHIN ITS SPECIFIED TIME INTERVAL IS DEFINED AS A FAILURE TO MEET THE OPERABILITY REQUIREMENTS OF AN LC0 l ALTERNATIVE REQUIREMENT i

ALLOW ACTIONS TO BE DELAYED UP TO 24 HOURS TO COMPLETE A SURVEllLANCE WHEN ALLOWED OUTAGE TIME LESS THAN 24 H0llRS (INCLllCES NO ALLOWED OUTAGE TIME CASE, l.E., IMMEDIATE SHUTDOWN)

CLARIFIED THAT THE SPECIFIED TIME INTERVAL IS THE ALLOWED SURVEILLANCE INTERVAL PER SPEC 4.0.2

CLARIFIED THAT THE TIME LIMITS OF ACTION REQUIREMENTS ARE APPLICABLE WHEN IT IS IDENTIFIED THAT A SilRVEILLANCE HAS NOT BEEN PERFORf'ED WITHIN THE ALLOWED SURVEILLANCE INTERVAL SPECIFICATION 4.0.4 EXISTING REQUIREMENT PRECLUDES MODE CHANGE IF SURVEILLANCE HAS NOT BEEN PERFORMED IN SPECIFIED TIME INTERVAL CLARIFICATION NOTE THAT LIMITATION SHALL NOT PREVENT PASSAGE THROUGH OR TO MODES TO COMPLY WITH ACTIONS (SIMILAR PROVISION AS IN SPEC 3.0.4 FOR LCOs) 1

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TO1E: fa n e m nt awaty n st f e r- Itanatarm f ollcwup nay tuve tmi awliyw tj to nailtiple trisw;tes iswi .* n1rmale= TfC m y tuv s inn ab itipuwt to <>1mt lar events at enilt iple pl.uit<3, i.e., TfC #67244 was awary nal to 6 f fli

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REA;i : 3::AM SUP1ARY -

  • WEEK EN INS 04/03/2E
1. FLANT SFE:IFIC DATA LATE SliE LN!T PCWIR SIENAL CAL 5E CCf.:LI- YTD YTD YTL CATICNE AiOV! IEL0i TCTAL 1!1 !!!

04/04/55 lir EE V;LLEY 2 100 c E;j!?= INT N: 0 2.

O!IC4rii r;;i St. VFa!N 1 72 M E:JLIFsINT .%: 1 0 1 01/07/21 ::: !i. VSA!N 1 7: ? E UlFFINT %0 ~2 0 2 C4<0'/!i V;ITLE 1 100 A EGLIF?ihi 52 3 0  ?

04/07/Ei FOINT EEL:a 2 100 A tijltnENT YES 1 0 1 04/015! Ll'IE!:r 1 0A LW) N:i', N2 0 1 1

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'CTE!

1. PLANT SPECIFIC OATA SASEC Ch INITIAL REVIEW OF EC.72 REPORTS FCR THE WEEK OF INTEREST. PERIOD IS MIONIGHT SUNDAY THROUGH MIDNIGHT: SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH.3ESULT IN R00 MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF-PLANNED SHUTOOWN IN ACCORDANCE WITH A PLANT PROCECURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.
2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UliRELATED 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.

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