ML20128L717
| ML20128L717 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/23/1984 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2245A, NUDOCS 8507110429 | |
| Download: ML20128L717 (13) | |
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WORKING COPY JAN 9 1985 ISSUE DATE: 10/23/84 MEETING MINUTES OF THE OCTOBER 9, 1984 COMBINED ACRS SUBCOMMITTEES ON LIMERICK UNITS 1 AND 2 AND RELIABILITY AND PROBABILISTIC ASSESSMENT The cembined ACRS Subcommittee on Limerick Units 1 and 2 and Reliability and Risk Assment met on the afternoon of October 9, 1984 and October 10, 1984. The meeting was held at 1717 H Street, N.W., Washington, D.C. and except for a short session on the detailed security planning, was conducted in open session with a transcript being kept for the entire proceedings.
The meeting on October 9, 1984 began at 1:00 p.m. and adjourned at approximately 5:30 p.m.
The principle attendees were as follows:
W. Kerr, Subcommittee Chaiman M. W. Carbon, ACRS Member J. C. Ebersole, ACRS Member J. C. Mark, ACRS Member C. J. Wylie, ACRS Member D. A. Ward, ACRS Member G. A. Reed, ACRS Member 8507110429 841023 JY
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T Limerick /RPA Mtg Minutes October 9-10, 1984 M. Bender, ACRS Consultant P. Davis, ACRS Consultant A. Garcia, ACRS Consultant D. Powers, ACRS Consultant M. Trifunac, ACRS Consultant R. Savio, ACRS Staff, Designated Federal Official A. Schuencer, NRC R. Martin, NRC H. Kister, Region 1 F. Kantor, NRC J. Sears, NRC D. Matthews, NRC R. Skelton, NRC G. McCorky, NRC V. Boyer, PEC0 G. Leitch, PECO R. Kankus, PEC0 R. Weindorfer, PECO l
The Agenda for the meeting is included as Attachment A.
Selected handouts from this meeting are included as Attachment B an.d C.
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MEETING MINUTES NRC Staff Report - R. Martin, NRC Staff The NRC Staff began the discussions with a report of the status of the NRC Staff review of the plant.
The NRC Staff has issued the Safety l
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T Limerick /RPA Mtg Minutes October 9-10, 1984 Evaluation Report (through Supplement 1), the Environmental Impact Statement, the NRC Staff report on the NRC/BNL review of the Limerick PRA/ SARA (NUREG-1068 and the topical reports which document the results of the BNL review, NUREG/CR 3493, NUREG/CR 3028, and BNL 33835).
The ASLB has ruled on all issues on Limerick except offsite emergency planning with the hearings on this subject to begin in late November /early December.
The controlling element on the start of these hearings is the completion of the FEMA review on offsite emergency FEMA has observed and reported favorably on the July,1984 planning.
full scale emergency response plan exercise.
The NRC Staff summarized the status of the items still under NRC Staff review and the schedule for issuing the remaining Safety Evaluation Report and Evirionmental Impact Statement documents.
This infonnation i
is summarized on pages 1 thru 7 of Attachment B.
Region 1 Report - H. Kistner i
{
Representatives of Region 1 summarized the Region 1 participation in the licensing of the Limerick plant.
Region I has audited the process of plant construction, construction QA/QC programs, operating training, and the adequacy of emergency planning.
The Region 1 representative stated that the plant was well-managed and well-constructed and that their were no outstanding issues within Region l's area of review which would prevent the timely issuance of a operating license.
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Limerick /RPA Mtg Minutes October 9-10, 1984 PECO Presentations Leitch summarized the status of the PECO activities on the Mr.
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Limerick plant.
PEC0 has completed construction on Limerick Unit I and
<n the very is anticipating receiving a 5% power license from the NR.
near future.
A startup test program has been planned usin; the recent experience gained at the LaSalle, Susquehanna, Hanford 2 and Hatch 2 plants. The plan anticipated that the fuel load and zero power testing will take approximately 7 weeks, that low power testing will take approximately 31 weeks, and that power ascension will take apprximately The schedule has been arrived at by taking the shortest times 20 weeks.
achieved for the individual elements of the test program in recent BWR startups and adding 20% to those times.
The Mr. Kankus discussed the emergency planning for the Limerick plant.
on site appraisal by the NRC has been completed, a plan is in place, and a recent full scale exercise of the plan was run and observed by FEMA in July, 1984.
FEMA has reported favorably on this excerise.
The schedules for the implementation of this plan is given on page 8 of There was some discussion as to the basis for the model Attachment B.
used to develop the emergency plan.
It appeared that conventional It was methods and generic models had been used to a large extent.
suggested that the plan would benefit from the use of PRA insights, as and attention to any site unique features which could they existed, The NRC Staff believes that the implementation of influence the plan.
Limerick /RPA Mtg Minutes October 9-10, 1984 the emergency plan is proceeding smoothly and that a timely NRC approval should be forthcoming.
The security plan was discussed in closed session.
Mr. R. Weindorfer discussed detailed features of the plan with the Subcommittee. The plan relies strongly on psychological profile screening and the use of The long-term PEC0 employees as protection against insider sabotage.
security force is designed to have the capability to protect the plant against attack until such time as offsite police and military forces can be brought to the plant.
The security plan is in compliance with current NRC requirements.
Adjournrrent.
4
MILESTONES MARCH 1981
'OL APPLICATION AUGUST 1983
- SER OCTOBER 1983
'ACRS EEMBER 1983 SSER-1 APRIL 1984
- FES AUGUST 1984
- PRA REPORT OCTOBER 198/4 SSER-2,3
- HEARINGS FALL 1982
- dLWS (PID 3/8/83)*)
SPRING 1984
- OTHER (PID 8/29/84 RJTURE
- 0FFSITE EP
- PLANT CONSTRUCTION OCTOBER 1984 ESSENTIALLY COMPLETE
- P.O ISSUES STILL liLUGIERAT101
F SER ISSUES SECTION(S)
SSER ISSUES (PREVIOUSLY OPEN1 2.3.3, 13.3 3
- 2. TORNADO-MISSILE EFFECTS ON 3.5.2 3
- 3. PIPE BREAKS OUT51DE 3.6.1 2
CONTAINMENT
- 4. FEEDWATER ISOLATION CHECK 3.6.2 2
VALVES
- 5. INSTRUMENT LINE VIBRATION 3.9.2.1 1
MONITORING PROGRAM 3.10 2,3
- 6.
- SEISMIC / DYNAMIC QUALIFICATION 3.11 2
- ENVIRONMENTAL QUALIFICATIONS 4.4.7 2
- 7. INADEQUATE CORE COOLING 7.5.2.1
- 8. AlRBORNE PARTICULATE 5.2.5 1
RADIOACTIVITY MONITORING SYSTEM
- 9. SECOND ISOLATION VALVE FOR 6.2.4.2 1
HYDROGEN RECOMBINER.
~
- 10. PRESSURE DROP MEASUREMENT ACROSS 6.5 1
- 11. MANUAL INITIATION OF SAFETY 7.3.2.5 2
SYSTEMS l
- 12. POST-ACCIDENT MONITORING 7.5.2.3 3
l INSTRUMENTATION
- 13. MULTIPLE CONTROL SYSTEMS FAILURES AND HIGH-ENERGY LINE BREAKS AND CONSEQUENTIAL CONTROL SYSTEM 7.7.2.1 2
i FAILURES
- 14. 3-HOUR-FIRE-RATED BARRIERS FOR 9.5.1.4 2
STRUCTURAL STEEL l
- 15. ELECTRICAL CABLE AND CABLE
.9.5.1.4.5 2
TRAY PROTECTION I
l l
[
T b
SECTION(S) jjfj!
ISSUES (PREVIOUSLY OPEN)_
EFFECTS OF HYDROGEN EXPLOSION11.3.1 1
160 ON OFFGAS SYSTEM
- 17. ADMINISTRATIVE PROCEDURES 13.1.2.1 1
( APPLICABLE TMI ITEMS) 13.4 1
- 18. SIZE OF ISEG 15.2.2 1
- 19. RECLASSIFICATION OF EVENTS 15.2.2 1
- 20. ODYN CODE CALCULATION
- 21. ATWS EVENTS (GENERIC LETTER 15.8 2
83-28) 17 2
- 22. O LIST 18 3
- 23. CONTROL ROOM DESIGN REVfEW
- 24. CONTAINMENT EMERGENCY SUMP APPENDIX C 2
RELIABILITY
- 25. MODES AND CONSEQUENCE OF 19 3
MAIN COOLING TOWER FAILURES
- 26. MATERIALS FURNISHED BY RAY' MILLER, INC., AND TUBE-LINE APPENDIX K 2
CORPORATION 3.7.3.1 2
- 27. CONTROL ROOM CEILING 3.9.3.4 3
- 28. Two-STAGE TARGET ROCK VALVES 3.9.7 3
- 29. PIPE CLAMPS APPENDIX L 2
- 30. HAYWARD TYLER PUMPS
- 31. STRESS CORROSION CRACKING 19 2
MONITORING PROGRAM 6
F
$l SECTION(S) 11(R 1SSUES (PREVIOUSLY CONFIRMATORY
- 1. FSAR TABLES 3.2-1 AND 3.2-2 3.2.2 2
REVISIONS
- 2. PIPING IS0 METRICS AND PIPE 3.6.2 2
WHIP EFFECTS
- 3. STARTUP TEST SPECIFICATION 3.9.2.1 2
FOR B0P PIPING
- 4. REACTOR INTERNALS ANALYSIS 3.9.2.4 2
DOCUMENTATION
- 5. LOADING COMBINATIONS, DESIGN 3.9.3.1 3
TRANSIENTS, AND STRESS LIMITS
- 6. INSERVICE TESTJNG OF PUMPS 3.9.6, 3
AND VALVES 5.4.6.
1 5.4.7 1
4.2.1.2 1
- 7. FUEL RCD MECHANICAL FEACTURING 4.2.1.3 1
- 8. FUEL ASSEMBLY STRUCTURAL DAMAGE 4.2.3.3 FROM EXTERNAL FORCES
- 9. OVERHEATING OF GADOLINIA FUEL 4.2.3.2 3
PELLETS 4.2.3.3(1) 2
- 10. HIGH BURNUP FISSION GAS RELEASE 4.4.6 2
- 11. LOOSE-PARTS MONITOR 1NG SYSTEMS 5.2.4.3, 3
- 12. PRESERVICE INSPECTION PROGRAM 6.6.3 3
I
- 13. ALTERNATE SHUTDOWN COOLING FLOW 5.4.7 2
PATH l
l
- 14. ENVIRONMENTAL QUALIFICATION 6.2.1.3 2
ENVELOPE FOR DRYWELL
- 15. BULK-TO-LOCAL POOL TEMPERATURE6.2.1.7.3 2
/
DIFFERENCES l
6.2.1.7.3 2
- 16. CAPPING VACUM BREAKER DOWNCOMER
- 17. ANDERSON-GREENWOOD VACUUM BREAKER 6.2.1.7.3 2
l TESTS PROGRAM
- 18. APPLICABILITY OF MARK lli 6.2.1.8 2
CONCERNS
SECTION(S)
SSER ISSUES (PREVIOUSLY CONFIRMATORY
- 19. PROCEDURES FOR ISOLATING 6.2.4.1 2
FEDWATER BYPASS LINES
- 20. PROCEDURES FOR HYDROGEN 6.2.5 2
RECOMBINER OPERATION
- 21. PROCEDURES FOR TYPE A LEAKAGE TESTING FOR HYDROGEN RECOMBINERS6.2.5 2
AND COMBUSTIBLE GAS ANALYZER
- 22. FRACTURE TOUGHNESS OF CONTAIN-6.2.7 3
MENT PRESSURE BDUNDARY
- 23. PROCEDURES FOR RESPONSE TO 6.3.5 2
LOCA 6.3.5,
- 24. PLANT-SPECIFIC LOCA ANACYSIS 15.9.4 2
- 25. TEST RESULTS FOR STEAM EFFECTS6.3.5 2
ON CORE SPRAY DISTRIBUTION 7.2.2.1 3
- 26. INSTRUMENT SETPOINTS
- 27. Fall'URES IN REACTOR VESSEL 7.2.2.2 2
LEVEL SENSING LINES 7.2.2.9 2
- 28. ISOLATION OF CIRCUITS 7.2.2.10 2
- 29. APRM UPSCALE TRIPS
LOW WATER LEVEL j
7.4.2.2 3
- 31. AUTOMATIC SWITCHOVER OF RCIC
- 32. ROD SEQUENCE CONTROL SYSTEM, ROD WORTH MINIMlZER, AND THE 7.4.2.3 2
I ROD BLOCK MONITOR
- 33. CAPABILITY FOR SAFE SHUTDOWN l
FOLLOWING LOSS OF ELECTRICAL 7.4.2.1 2
POWER 7.4.2.3 3
- 34. REMOTE SHUTDOWN SYSTEM 9.5.1 2
35-59. FIRE PROTECTION ISSUES
- 60. SOLIDIFICATION / DEWATERING OF 11.4 3
SOLID WASTE (PROCEDURES)
- 61. OPERATING AND MAINTENANCE 13.5.2.1 2
l PROCEDURES
T.
SECTION(S)
}$EB ISSUES (PREVIOUSLY CONFIRMATORY 13.5.2.3 2
e.
- 62. EMERGENCY OPERATJNG PROCEDURES
- 63. ASSURANCE OF PROPER ESF 15.9.3 3
FUNCTIONING (ll.K.I.5)
- 64. PROCEDURES TO ENSURE OPERABILITY STATUS (ll.K.1.10) 15.9.3 2
- 65. AUTOMATIC RESTART OF RCIC 15.9.4 2
(II.K.3.13)
- 66. PRECLUDE SPllRIOUS ISOLATION OF15.9.4 2
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RADIOLOGICAL EMERGENCY RESPONSE PLAN PROCESS (RERP)
TIME FRAME SEQUENCE OF EVENTS EPZ DESIGNATED Counties and Municipalities Work March 1982 to Develop Boundaries RERP PROTOTYPE DEVELOPMENT (Basic Plans for Counties, 4/82 to 9/82 Municipalities, Schools, Health Facilities drafted)
STATE EMERGENCY MANAGEMENT 8/31/83 to 12/9/83 AGENCY REVIEW / COMMENT (Informal) 12/9/83 to 5/8/84 REGIONAL ASSISTANCE (RAC) REVIEW / COMMENT (Informal) 5/8/84 to 10/1/84 RERP REVISION (Based Upon RAC comments) 11/1/83 to 7/25/84 INITIAL ORIENTATION / TRAINING of Counties, Municipalities, etc.
May to July 84 PRACTICE DRILLS / CRITIQUES 7/25/84 FULL-SCALE OBSERVED EXERCISE RERP REVISION (Based on PEMA, FEMA, NRC, Comments 8/1/84 to 11/1/84 and Exercise Results) 12/1/84 (projected)
PUBLIC MEETING FEMA HEADOUARTERS FINDINGS AND DETERMINATIONS (formal)
Spring 1985 Spring 1985
(
PREPAREDNESS ESTABLISHED Ongoing ANNUAL RERP REVIEW AND REVISION l
l Ongoing ANNUAL RER TRAINING 1986 BIANNUAL EXERCISE
- s
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