ML20211Q616
| ML20211Q616 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, Hope Creek, Diablo Canyon, Cook, 05000000, Fort Saint Vrain, Bailly |
| Issue date: | 07/23/1986 |
| From: | Holahan G, Holanhan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8607250192 | |
| Download: ML20211Q616 (22) | |
Text
T A SS 1W6 s
MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON July 21, 1986 - MEETING 86-25 On July 21, 1986, an Operating Reactor Events meeting (86-25) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 14, 1986. 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 followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.
t Completion dates have been assigned for items in Enclosure 3.
Each assignee should review Enclosure 3 with regard to their respective responsibilities.
Note that several assignments are approaching the due date.
Please be responsive i
and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
M/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
l See Next Page DISTRIBUTION. _
Central File.-. 9 NRC PDR ORAS Rdg ORAS Members
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R. Vollmer K. Heitner J. Taylor H. Berkow C. Heltemes D. Wagner T. Murley, Reg. I M. Haughey J. Nelson Grace, Reg. II E. Adensam J. Keppler, Reg. III J. Wigginton R. D. Martin, Reg. IV W. Jones J. B. Martin, Reg. V M. Licitra R. Starostecki, Reg. I G. Knighton S. Ebneter, Reg. I H. Schierling R. Walker, Reg. II S. Varga C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin i
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R SS M ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-25)
JULY 21, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR W. Swenson ORAS/NRR M. Virgilio ORAS/NRR A. Nolan INEL/ EGG W. Haass IE/VPB M. Caruso ORAS/NRR M. Licitra NRR/PBD7 D. Wagner NRR/BWD3 M. Haughey NRR/BWD3 R. Benedict NRR/BF0B T. Greene NRR/F0B J. Clifford NRR/PPAS D. Muller NRR/BWD2 W. Regan NRR/PBF0 H. Berkow NRR/SSPD D. Lynch NRR/SSPD C. Ader 0CM/TR G. Murphy ORNL/NOAC M. Chiramal AE0D C. Miller NRR/PWRB H. Bailey IE/DEPER G. Lanik IE/DEPER A. Dromerick IE/DEPER L. Marsh NRR/DPLB W. Paulson NRR/PWRB I. Ahmed NRR/PWRB B. Jones IE/DEPER E. Weiss IE/DEPER R. Hernan NRR/PPAS R. Ramirez NRR/ DBL E. Jordan IE R. Baer IE/DEPER F. Rowsome NRR/DHFT C. Thomas NRR/PWRB F. Schroeder NRR/PWRB F. Miraglia NRR/PWRB R. Bernero NRR/ DBL D. Tarnoff ORAS/NRR
ENCLOSURE 2 s
OPERATING REACTOR EVENTS BRIEFING 86-25 JULY 21, 1986 FORT ST. VRAIN PROBLEMS IN EMERGENCY DIESEL GENERATORS CONTROL SYSTEM HOPE CREEK RECURRENT SPURIOUS LEVEL INDICATION PROBLEMS D.C. COOK UNIT 2 START JP WITH 2 0F 4 POWER RANGE NUCLEAR INSTRUMENTS IN0PERABLE PALO VERDE UNIT 1 REACTOR TRIP WITH COMPLICATIONS OTHER EVENT OF INTEREST DIABLO CANYON UNIT 2 THREE RECENT REACTOR TRIPS e---
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FORT ST. VRAIN - PROBLEMS IN EMERGENCY DIESEL GENERATORS CONTROL SYSTEM JULY 16, 1986 - (K. HEITNER, NRR)
PROBLEM:
SINGLE FAILURE DESIGN WEAKNESS IN EMERGENCY DIESEL GENERATOR (EDG) UNDERVOLTAGE START SYSTEM SIGNIFICANCE:
ONE OF SEVERAL SINGLE FAILURE WEAKNESSES DISCOVERED IN EDG CONTROL SYSTEMS DISCUSSION:
DEC. 18, 1984 - FAILURE OF DIESELS LED TO REVIEW OF EMERGENCY POWER SYSTEMS JULY 10, 1985 - STAFF CONCLUDED THAT FORT ST VRAIN COULD BE OPERATED SAFELY IN INTERIM WITH OTHER P0TENTIAL EDG SINGLE FAILURE AND INDEPENDENCE PROBLEMS SEPT. 13, 1985 - LICENSEE SUBMITS RESULTS OF SYSTEM REVIEW.
STAFF FINDS PROBLEMS PERSIST:
- COMMON RELAYS
- LOGIC FAULTS THE LICENSEE WILL PROPOSE RESOLUTION FOR THE EDG PROBLEMS IDENTIFIED TO DATE PRIOR TO RESTART F0LLOW-UP:
STAFF TO COMPLETE ITS REVIEW 0F EDG CONTROL SYSTEMS BY END OF AUGUST 1986; THEN MEET WITH LICENSEE ON ALL EDG CONTROL PROBLEMS l
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15%
EQUIP. RELATED
>15%
9 4.6 5.4 (68%)
PERS. RELATED(6) >15%
1 2.0 2.0 (25%)
OTHER(7)
>15%
O O.3 0.6 ( 7%)
- Subtotal **
10 6.9 8.0
- POWER <15%
EQUIP. RELATED
<15%
2 1.6 1.3 (54%)
PERS. RELATED
<15%
1 1.0 0.9 (38%)
OTHER
<15%
0 0.1 0.2 ( 8%)
- Subtotal **
3 2.7 2.4
- Total ***
13 9.6 10.4 MANUAL VS AUTO SCRAMS TYPE NUMEER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1
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AUTOMATIC SCRAMS 12 8.9 9.4 i
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o NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
2.
REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
4.
IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
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BASED ON 100 OPERATING REACTORS 6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
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7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
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ENCLOSURE 3 C
p Page No.
1 07/22/B6 OPERATING REACTORS EVENTS MEETINS FOLLOWUP ITEMS AS OF MEETING 86-25 ON JULY 21, 1996 (IN ASCENDING MEETINS DATE, NSSS VENDOR, FACILliY ORDER)
MEETIN6 FACILITY RESPONS! ELE TASK DESCRIPil0N SCHEDULE CLDSED DATE COMMENTS NUMBER /
MSSS VENDOR /
DIVISION /
COMPLET. EY DOCUMENT, MEETING EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETING,ETC.
DATE B6-10 OYSTER CREEK NRR / HOUSTON W RESOLVE THE QUEST 10N OF THE 10/30/06 0 FEN
//
FOLLOWUF ACTION TO 03/31/E6 SE / LEVEL
/
ACCEPTABILITY 0F BLIND SWITCHES
/ /
BE INCORPORATED IN SWITCH SETPOINT AND DELETION OF DAILY CHANNEL
/ /
REVIEW 0F JUNE DRIFT CHECK 1,1986 EVENT AT LASSALLE B6-21 VERMONT YANKEE NRR /HOLAHAN 6.
DETERMINE STATUS AND 09/20/96 OPEN
//
06/23/B6 SE / PROBLEMS
/
EFFECTIVENESS OF STAFF AND
/ /
WITH SCRAM LICENSEE ACT10N DN
/ /
SOLENDID YALVES POST-MAINTENANCE TESTINS (BL 23-28). DEVELOP RECOMMENDATIONS FOR FURTHER ACTION 86-21 TURKEY POINT NRR /RDSA F.
CONSIDER REVIEWING ELECTRICAL 08/30/06 0 FEN
//
06/23/B6 W / POTENTIAL
/
SYSTEM OF PLANT WITH SIMILAR
/ /
FAILURE OF ALL SWINS BUS DESIGN
/ /
EMER6ENCY DIESEL SENERATORS B6-23 FERRY NRR / HOUSTON W.
DBTAIN AND REVIEW INFORMATION 09/29/66 0 FEN
//
07/07/06 6E / FIRE IN
/
RELATED TO RECURRENCE OF FIRE
/ /
OFFBAS CHARC0AL AND INVESil6 ATE PROPOSED
/ /
BEDS ACTIONS B6-23 MULTI NRR / HOUSTON W.
DETERMINE APPROFRIATE 09/30/E6 0 FEN
//
07/07/06 NA /
/
RESULATORY REQUIREMENTS PASED
/ /
EWRS-RESIDUAL ON RECSMMENDATIONS DISCUSSED AT / /
HEAT REMOVAL BRIEFING PUMP / WEAR RINS FAILURES -
FDLL0iUP B6-23 MULT!
hRP /EERLihSEF C.
ASSURE NRR AND IE COORDINATION OB!30/G6 0 FEN
//
07/07/E6 NA /
/
TO DETEFMINE THE HEED FOR AN IE
/ /
PWRS-INADEGUATE EltLETIN
/ /
DESIGN OF ECCS FUMP MINIMUM FLOW PATHS m
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