ML20154R780
| ML20154R780 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/22/1988 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Corbin McNeil PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8810040353 | |
| Download: ML20154R780 (31) | |
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Docket Nos.
50-277 fh00 50-278 Philadelphia Electric Company ATTN: Mr. C. A. McNeill Executive Vice President-Nuclear Correspondence Control Desk P.O. Box 7520 Philadelphia, Pennsylvania 19101 Gentlemen:
Subject:
Summary of Meeting on Selected Potential Restart Impact Issues A meeting was held in the Region I office at Philadelphia Electric Company's (PECo) request on 3eptember 7, 1988.
The licensee presented information on selected potential restart impact engineering issues. Attachment 1 is the attendance list and the agenda is provided as Attachment 2.
Licensee handouts were provided for each area discussed and are attached as follows:
Attachment Subject 3
Introduction 4
Control Panel Mounting 5
Open Commitments and Findings 6
Limitorque Operation at Reduced Voltage 7
Hanger Walkdown 8
Splice Inspections 9
Diesel Generator Control Circuit Modification (Cardox Interface)
NRC thanked the licensee for the information.
No commitments vere made.
Sincerely, ORIGINAL. SIGNED BY EDWARD C. WENZINGER E. Wenzinger, Chief Projects Branch No. 2 Attachements: As stated 0FFICIAL RECORD COPY MTG SUMMRY ON PB RESTART -
0001.0.0 09/14/88 y
0010040353 000922 I
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Philadelphia Electric Company 2
i 22 SEP 1988 i
I cc w/ enc 1:
John S. Kemper, Sr., Senior Vice President-Nuclear i
J. W. Gallagher, Vice President, Nuclear Services E. C. Kistner, Chairman, Nuclear Review Board Dickinson M. Smith, Vice President, Peach Bottoa Atomic Power Station Jack Urban, General Manager, Fuels Department, Delmarva Power & Light Co.
John F. Franz, Plant Manager, Peach Bottom Atomic Power Station j
Troy B. Conner, Jr., Esquire W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric Bryan W. Gorman, Manager, External Affairs Eugene J. Bradley, Esquire, Assistant General Counsel (Without Report)
Raymond L. Hovis Esquire i
Thomas Magette, Power Plant Siting, Nuclear Evaluations I
W. M. Alden, Director, Licensing Section Doris Poulsen, Secretary of Harford County Council Public Document Room (POR)
Local Public Document Room (LPOR) i Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania bec w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, ORMA (w/o enc 1)
Section Chief, ORP PA0 (2) SALP and All Inspection Report, Robert J. Bores, DRSS R. Martin, NRR B. Clayton, ECO L
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William ('f/rh1 RIjuRP RI.ORP r
Linville nger 9h88 9/li/88 9
/88 0FFICIAL RECORD COPY MTG
SUMMARY
ON PB RESTART -
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09/14/88 i
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ATTACHMENT 1 PEACH BOTTOM SCHEDULE IMPACT ISSUES MEETING ATTENDEES SEPTEMBER 7, 1988 NRC C. Anderson Chief, Plant Systems Section, DRS J. Strosnider Chief, Materials & Processing Section, DRS T. Martin Director, Division of Reactor Safety W. Johnston, Deputy Director, DRS J. Linville Chief, Reactor Projects Section 2A, ORP T. Kosy Senior Reactor Engineer, DRS E. Wenzinger, Sr.
Chief, Projects Branch No. 2, ORP J. Williams Project Engineer, DRP PECo W. Alden Director-Licensing T. Shannon Project Manager G. Hunger, Jr.
Manager, Mechanical Engineering D. O'Rourke Structural Branch Head R. Hess Supervisory Engineer P. Manzon Engineer P. Tutton Supervisory Engineer W. Bowers Manager, Power & Control Systems D. Mellott Engineer R. Rock Electrical Engineer D. Thompson, Jr.
Senior Engineer D. Foss Peach Bottom Compliance Engineer Other H. Abendroth Atlantic Electric R. Reichel Delmarva Powir
i ATTACHMENT 2 f
PIIILADELPIII A ELECTRIC COMPANY SEPTEMBER 7,1988 l
INTRODUCTION - T. SIIANNON fI
- CONTitOL PANEL MOUNTING D. O'ItOURKE II - OPEN COMMITMENTS AND FINDINGS - D. FOSS 111 - LIMITOltQUE OPEllATION AT REDUCED VOLTAGE - R. IIESS i
l IV IIANGEll WALKDOWN - P. TU'ITON 4
V
- SPLICE INSPECTIONS R. ROCK VI - DIESEL GENERATOR CONTilOL CIRCUlT MODIFICATION (CARDOX INTEltFACE)
D. MELOTT
i ATTACHMENT 3 PHILADELPHIA ELECTRIC COMP ##
NUCLEAR EtGINEERifJG DEPARTMENT PEACH BOTT m RESTART IMPACT ISSUES o
PURPOSE OF MEETitG
- Presentation of Selected Impact issues BACKGPOt.to
- Definition of a Restart Schedule inpact Issue Identification of Issues
- All Hands input Starting Late 1987
- Review of issues at other Plants, Browns Ferry, Sequoyah, Rancho Seco.
- Prioritiration of Issues
- Disposition Required
- Status Acceptable As Is
- Physical Work / Study Required but not for Restart
- Physical Work / Study Required Prlor to Restart
- Each Disposition included Considerations such as
- Root Cause Identification
- identification of ProgranTnatic issues
- Action Plan and Scheduto
- Prevention of Recurrance COffTROLS PROVIDED BY OVERSIGHT TASK FORrE COMPRISED OF:
- Plant t% nager
- Plant Project Mana0er
- Engineering Division Manager
- Engineering Project Manager
- Vice President - Engineering at Gilbert Ccrmorwealth
t PHILADELPHIA ELECTRIC COMPNJY iA) CLEAR EPGitJEER!tG DEPARTPENT PEACH BOTTCt4 RESTART IMPACT ISSUES (cont'c) o STATUS
- All 61 Issues Identified have boon Resolved
- Mod Packages required for restart issued / physical work in progress or ccmplete
- Docunentation Package Being Assembled S
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ATTACHMENT 4 l
l CO\\ TROL PA\\.EL AhCHORAGE ISSUE f
INVESTIGATION MODIFICATION OF CONTROL PANEL ANCHORAGE I
l ADDRESSED PANELS IN MAIN CONTROL ROOM AND OUTSIDE CONTROL ROOM l
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- s typic AL CONTROL-PANEL ANCHCRAGE DETA I L.
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- col \\~~ROL PANEL ANCHORAGE i
BACKGROUND 1
QUESTION FROM l
RESIDENT INSPECTOR PECO INVESTIGATION EVALUATION l
ENGINEERING ANALYSIS NEEDED TO ACCESS INSIDE OF PANELS
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CO\\ TROL PANEL A\\CHORAGE I
CORRECTIVE ACTIONS MODIFY ALL PANELS IN THE CONTROL ROOM EVALUATE ALL PANELS
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IN CABLE SPREADING ROOM j
-MODIFY AS NEEDED-EVALUATE ALL S/R PANELS j
IN BALANCE OF PLANT
-MODIFY AS NEEDED-l
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CO \\ T ROL PA \\ EL A \\iCHO RAG E RESULTS ALL CONTROL PANELS IN THE CONTROL
- ROOM, CABLE SPREADING
- ROOM, AND S/R PANELS IN THE BALANCE OF THE PLANT HAVE BEEN EVALUATED MODIFIED AS NECESSARY.
WORK PREFORMED ON SCHEDULE WITH NO DEFECTS.
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ATTACHMENT 5 PEACH BOTTOM ATOMIC POWER STATION Plant Division Technical Section September 7, 1988 Operating Experience / Commitment Tracking Operating Experience i
1.
Present Program (implemented 7/1/88)
NuclearGroupAdminProcedure(NGAP) implemented 7/1/88 NGAP development based on INPO guidance and 1987 ISEG effectiveness evaluation t
Station Administrative Guideline implemented 7/1/88 L
Depth of review ensured by Superintendent concurrence, Regulatory and i
Corporate perform sanity check Corrective Actions tracking in newly implemented Commitment Tracking Program Operating Experience information distributed to station staff
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Pertinent OE information forwarded to training Bi-weekly and monthly reports to management 4
HQA performs annual effectiveness review Currently Received 6]_ total items in new program No items overdue for review Host itens being reviewed within 30 days 5
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OEAP Backlog (Pre 3/88 open items)
Initial scope (open items) SOERs. SILs, TILs, INNS, SERs that rs! quire review and/or closure documentation TOTAL:
442 Comitted to INP0 to reduce the Lacklog review of SILs, SERs, INNS to 50% by 7/88 - 100% by 12/88.
50% commitment met.
SOER recommendation backlog initially 60, projected open at end of l
Sept. 18 Commitment Trar. king 1.
Present Program (implemented 7/1/88)
Coordinated Corporately and implemented at site NGAP and site administrative guideline approved and implemented Overview Defined scope of documents are funnelled through CTC Individual commitments placed in data base Assigned to P8 (bulk), Limerick (bulk), NED, Nuclear Support 2
Site assigns to appropriate individual (3), tracks completion Annual assessment performed by QA High level of management involvement Management involved in commitment problem areas Bi-weekly and monthly reports to management i
2.
NRC Of List Backlog Compatability of data bases, closure package to resident 3/1/88 - 129 open items Since 3/1/88, 37 incoming, 66 closed by NRC Currently, 45 under NRC review, 55 remain open with PECO
ATTACHMENT 6 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 MOTOR OPERATED VALVE (MOV)
REDUCED VOY,TAGE OPER ATION
B ACKGROUND :
ORIGINAL MOV'S SPECIFIED FOR OPERATION AT 90% RATED VOLTAGE IlEGINNING IN 1979, MOV'S SPECIFIED FOR OPERATION AT 80% RATED VOLTAGE VOLTAGE REGULATION STUDY IDENTIFIED REDUCED VOLTAGE TO MOV'S UNDER CERTAIN CONDITIONS VOLTAGE REGULATION STUDY 51AGNITUDE OF REDUCED VOLTAGE DURATION OF REDUCED VOLTAGE WilEN REDUCED VOLTAGE OCCURS
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OCCURS WITillN ONE hilNUTE OF ACCIDENT INITIATION S051E OCCURRENCES VERY SIIORT IN DURATION, LESS TilAN ONE SECOND MllEN CAUSED llY IN.RUSil CURRENT J
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BULLETIN 85-03 PROGR AM REVIEW / DOCU51ENT Af0V DESIGN BASIS ESTABLISil 51AXI51U51 DIFFERENTIAL PRESSURES DE510NSTRATE VALVE OPERABILITY (510 VATS)
INADVERTENT VALVE OPERATION IIPCI AND RCIC SYSTE51S (50 VALVES)
PECo EXPANDED PROGRAM TO INCLUDE ALL SAFETY RELATED AIOV'S (233 VALVES)
REDUCED VOLTAGE PROGRAM l
ALL SAFETY RELATED jf 0V'S REVIEWED FOR ABILITY TO PF.RFOR51 AT REDUCdD VOLTAGE un t (2 )
e ENGINEERING EVALUATION l'
REQUIRED TORQUE LESS TIIAN 155 AVAILABLE TORQUE AT 80%
VOLTAGE h!ANUALLY INITIATED MOV, 41 NOT REQUIRED 15thlEDIATELY AFTER ACCIDENT FUNCTIONAL REVIEW PERFORh1ED 18
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TISIE OF VALVE OPERATION DIRECTION OF TRAVEL DESIGN BASIS DIFFERENTIAL PRESSURE INADVERTENT OPERATION DETAILED REVIEW 19 USED llIGIIER RUNNING EFFICIENCY, NOT PULLOUT EFFICIENCY FOR VALVES REQUIRED TO CLOSE USED MOVATS TO CONFIRh1 TIIAT ACTUAL DESIGN 51ARGIN EXISTS TOTAL SCOPE = 233 (3 )
CONCLUSION ALL SAFETY RELATED MOF'S WERE EVALUATED FOR REDUCED VOLTAGE OPERATION AND ALL WILL PERFORM SAFETY FUNCTION.
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ATTACHMENT 7 l
Peach Bottom Atomic Power Station Units 2 Assessment of Adequacy
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Piping Systems Supports e
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I BACKGROUND:
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- DISCREPANCIES IN SMALL PIPE l
SUPPORTS WERE IDENTIFIED IN UNIT 2.
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- AN ASSESSMENT PROGRAM WAS INITIATED FOR UNIT 2 SAFETY-RELATED SYSTEMS.
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APPROACH:
- ASSESS AVAILABLE INFORMATION l
- PERFORM A QUALITY ASSURED WALKDOWN AND EVALUATION PROGRAM ON A SAMPLE OF PIPING SYSTEMS.
FOCUS:
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- 3 INCH AND SMALLER Q-LISTED PIPING.
- LARGER PIPING SYSTEMS WERE i
EXCLUDED BASED ON-i
- RECENT MAJOR MODIFICATIONS i
- ONGOING ISI PROGRAM 02 PROGRAM 14 PROGRAM i
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SMART SAMPLING:
- APPROXIMATELY 10% OF ALL 3 INCH l
AND SMALLER Q-LISTED PIPING WAS WALKED DOWN (50 WALKDOWN PKGS.)
- 10% SAMPLING CONSERVATIVELY j
j BIASED ON:
- HIGH TEMPERATURE / PRESSURE i
- LARGE CONCENTRATED WEIGHTS i
- LARGE DIFFERENTIAL MOVEMENTS i
- Q/NON-Q PIPING INTERFACE
- PLANT LOCATION I
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RESULTS:
- APPROXIMATELY 500 DISCREPANCIES WERE FOUND:
- 50% DIMENSIONAL
- 40% SUPPORT RELATED
- 10% OTHER l
- DETAILED ANALYSIS OF 8 SELECTED PACKAGES FOUND ALL TO BE OPERABLE
- 6 LONG TERM I
- 2 INTERIM (79-02 supl.1) l
- EVALUATION OF REMAINING 42 PACKAGES l
- 50% COMPLETE I
- ALL FOUND TO BE OPERABLE 1
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CONCLUSIONS:
ADEQUATE MARGINS FOR OPERABILITY EXIST IN O PIPING.
i ALL SUPPORTS MEET, AS A MINil.<i. 'YI,
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79-02 SUPL.1 INTERIM CRITERIA NON-Q PIPE NEAR Q / NON-Q BOUNDARY IS ADEQUATE.
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l CONCLUSIONS:(CONT'D)
- MANY HANGER ISOMETRICS FOR l
2 INCH AND SMALLER PIPE DO NOT REFLECT FIELD CONDITIONS.
- 21/2 AND 3 INCH PIPING HAVE l
FEWER DISCREPANCIES THAN SMALLER PIPING.
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- MOST ANOMALIES WERE THE RESULT OF ORIGINAL CONSTRUCTION.
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ACTIONS:
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- ASSURE LONG TERM OPERABILITY OF EVALUATED SYSTEMS.
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- UPGRADE NON-Q SYSTEMS NEAR l
Q-BOUNDRY.
- REPAIR ALL VISUAL DISCREPANCIES.
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- RESOLVE DISCREPANCIES IN REMAINING 42 WALKDOWN PACKAGES
- FORECAST COMPLETION 10/30/88.
- UPDATE PECO PHYSICAL DRAWINGS.
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FINAL CONCLUSIONS / COMMENTS
- ALL SYSTEMS EVALUATED WERE l
FOUND OPERABLE.
- PIPING AGREES WITH P&lD'S
- ALL PIPING SYSTEMS ARE OPERABLE.
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ATTACHMENT 8 i
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l PEACH BOTTOM l
ATOMIC POWER STATION 1
UNITS 2 AND 3 I
l INSPECTION AND REWORK OF CLASS 1E l
HE AT SIIRINK IN T,INE SPLICES l
MODIFICATION 2355 i
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R.II. ROCK SEPTE\\ liter 7.1988 4
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PROBLEM DEFINITION i
lhlPROPER SELECTION, APPLICATION AND INSTALLATION OF RAYCllEN!
IIEAT SilRINKARLE TURING :
CAUSES.
- 151 PROPER TUBE DIAhlETERS
+ lhlPROPER llEAT SilRINK GVERLAP ONTO WIRE JACKET
- USE OF llEAT SilRINK DIRECTLY OVER OPEN HRAIDING
. IhlPROPER HENDING OF SPLICES INSIDE JUNCTION HOX
. IIEAT SilRINK 151P110PERLY SilRUNK d
I EFFECTS
. SPL11 TING OR HURSTING OF llEAT SilRINK TUHING DUE TO CIRCUSIFERENTIAL STRESS AND ELECTRICAL,SIIORTING FAILURE
. hlOISTURE INTRUSION ATSPLICE ENDS
. LOSS OF SEALANT INTEGRITY DUE TO 510lSTURE WICKING TilROUGli WOYEN FABRIC i
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BACKGROUND :
i IEN 86 JJ (JUNE 26, 1986) - IDENTIFIED PRollLEhlS WITil 151Pl!OPER INSTALLATION AT FOUR PLANTS (DAYJS.IlESSE, DRESDEN, COhtSIANCilE PEAK, WATTS HAK), INSTALLATION DISCREPENCIES WITil RAYCIIEN! IIEAT SilRINK TUlllNG IIAVE ALSO llEEN REl'ORTED AT OTilER PLANTS SINCE lEN 86 53.
PHAPS RESPONSE :
HEVIEWED INSTALLATION SPECIFICATION (E lJI7) AND SIAINTENANCE DIVISION STANDARD WORK INSTRUCTIONS. E-1317 AND SWl'S WERE REVISED TO ENIIANCE AND CLARIFY IIEAT SIIRINK REQUIRE 51ENTS.
NO INSPECTIONS WERE PERFOR5tED SINCE PROCEDURES WERE TilOUGilT TO IIE SUFFICIENT, (2 )
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PB APS NRC INSPECTION :
NO'S 50 277/8718 AND 50 271/8718 UNRESOLVED ITE51 CONCERNING IIEAT SIIRINK TUlllNG APPLIED OVER UNISIPREGNATED 11R AIDS DISCOVERED DURING INSPECTION OF UNIT 2 STANDIlY G AS TREAT 5 TENT 480 YOLT 510 TOR LEAD SPLICE SGT 510 TOR LEAD WAS 151PREGNATED E.1317, REV JJ DID NOT SPECIFICALLY ADDRESS RE510 val, OF UNACCElrrAllLE IIRAIDED CAllLE COVERING
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O PLAN TO RESOLVE EIF 511/ SEPT.161987) S ANIPLE SPLICE INSPECTION 19 DEVICES WITil IN LINE SPLICES INSPECTED (UNIT 2) 17 SOLENOID VALVES 2 hl0 TORS RESULTS:
ISIPROPER TUBE DIAMETERS I5IPROPER OVERLAPS l
IMPROPER llENDING RADIUS IMPROPER ADilERENCE OF TUlllNG TO JACKET Af()D 2355 (NOV. 2J.1987) INSPECT AND HEWORK SPLICES s
UNIT 2 :
INSPECT AND REWORK IF NECESSARY,274 ELECTRICAL,INSTRUMEN TATION AND CONTROL t
DEVICES WITil SPLICES (SOLENOID VALVES, MOTORS, PRESSURE SWITCilES, LEVEL SWITCIIES)
ALL UNIT 3 SIMilAR SPLICES WERE REWORKED l
INSPECTION CRITERIA :
DEVICES WITil PIGTAIL LEAD WIRE CONNECTIONS ELECTRICAL PENETRATIONS AND MOTOR OPERATED VALVFS COVERED IN OTilER MODIFICATIONS j
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STATUS UNIT 2 274 DEVICE SPLICES INSPECTED Sf AY 20,1988 REWORK C05f PLETED ON 198 DEVICES AUGUST 12,1988 TESTING CONIPLETED ON 186 DEVICES AUGUST 12,1988 FORECAST TO C051PLETE UNIT 2 SEPTE5 filer 20,1988 UNIT 3 DEYlCES S1511LAR TO UNIT 2 WILL IlE REWORKED. WORK IS FORECAST TO llE C051PLFTE IlY FEBRUARY 1,1989 l
NESULTS ACilEIVED RESOLVED ll?N S6 53 CONCERNS FOR I'IIAI'S ADDRESSED NRC I?O INSPECTION UNRESOLVED ITESIS ESTAllLISilED A LEVEL OF QUALITY AND CONFIDENCE WITil RAFCllE31IN LINE SPLICES (5 )
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CORRECTIVE ACTION TO PREVENT RECURRENCE ISSUED RMC/IliM NUCLEAR PRODUCT GUIDE. I AS A CONTROLLED VENDOR DOCUMENT PnArs No. 6280. E.57 1 I?-1317 "WIRE AND CAllLE, NOTES AND DETAILS POWER, CONTROL AND INSTRUMENTATION" CURRENTLY UNDER hl AJOR REVISION, R AYCllE51 IIEAT SilRINK SI' LICE SECTION WILL REFERENCE 6230.E.571 FOR:
SELECrlON OF TURING INSTALLATION 51ETl10DS INSPECTION OF INSTALLATION TRAINING (6 IIR CLASS IlY RAYCIIEM)
LECTURE (INSTALLATION / INSPECTION TR AINING)
II ANDS ON EXPERIENCE TRAINING QUIZ TRAINING COVERED :
WCFS.N.NPKY NPKS AND N51CK TUlllNG AND KITS I
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4 AREAS TR_AINED :
1 NQA ENGINEERING CRAFTS PEOPLE (7 )
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EFFECTIVENESS OF ACTION TO PREVENT RECURRENCE TRAINING WAS EFFECTIVE BASED ON RESULTS OF IIANDS ON INSPECTION AND QUIZ RESULTS IIIGIIER LEVEL OF STATION AWARENESS CONCERNING RAYCIIEM SPLICES BASED ON QUESTIONS BACK TO ENGINEERING i
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ATTACHMENT 9 r-i i
PEACH BOTTOV ATOM C POWER STAT ON UNITS 2 & 3 i
DIESEL GENERATOR /
CARDOX SYSTEM INTERFACE D.S.MELLOTT l
Sept. 7,1988 i
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CONDITIC:N DESCRIPTION As originally designed and installed the Fire Suppression (Cardox) System in the Diesel Generator Building is non-seismic and nonsafety-related.
Upon actuation of the Cardox System a diesel generator trip signal is initiated.
Automatic actuation of the Cardox System is blocked on a LOCA signal.
ie inadvertant actuation of the Cardox System can trip t1e diesel generators via initiation of t1e trip signal or can suffocate t1e diesel engine because the diesels obtain combustion air from within the diesel generator room.
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t RESOLUTIO\\ ALTER \\K~lVES Upgrade the Cardox System to meet safety-related standards. (Alt A)
Convert the automatic Cardox System to a manual system and add an auto-matic deluge system. T1e diesel trip signal would be de eted. (Alt B)
Relocate the di 3sel generator air intake such that combustion air is received from outside the diesel generator rooms. (Alt C)
Add a LOOP bloc < in addition to the existing LOCA b ock within the Cardox circuitry. Blocking devices and master selector valves to be up-i graded to meet safety-related stan-dards. ( Alt D)
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r SELECTED RESOLU-lO\\l 1
- Alternative "A" was selected based on cost / schedule estimates, licensing assessments, as well as potential impact on Unit 2 Restart
- Modification 2390 initiated to upgrade the Cardox System control and initiation components and circuits to meet safety-related standards.
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VOJ 2390 S V V ARY i
- Specific components and circuits being upgraded include:
Cardox Contro Panels j
Heat Detectors EMPC Pus, Button Stations Master Selector Valves
- -eat detectors to be changed from combination rate-of-rise and fixed temperature type to j
rate compensation type due to seismic qua ification concerns.
- Number of leat detector ocations j
clanged from four to eight.
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