ML19253C139
| ML19253C139 | |
| Person / Time | |
|---|---|
| Site: | North Anna, Midland, Washington Public Power Supply System, Perkins |
| Issue date: | 11/14/1979 |
| From: | Bournia A Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911300035 | |
| Download: ML19253C139 (24) | |
Text
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NOV 141979 Docket Nos.: 50-460/513 50-488/489 50-404/405 50-329/330 MEMORANDUM FOR:
Steven A. Varga, Acting Assistant Director, Light Water Reactors, Division of Project Management
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THRU:
Olan D. Parr, Chief, Light Water Reactors, Branch No. 3, Division of Project Management FR0!i:
Anthony Bournia, Project Manager, Light Water Reactors, Branch No. 3, Division of Project ifanagement
SUBJECT:
SUMMARY
OF MEETING WITH UTILITIES AND BABCOCK AND WILCOX (OaW) TO DISCUSS THE 10 CFR 50.54 REQUESTS
Background
A letter, dated October 25, 1979, was transmitted to all utilities affected, i.e., Washington Public Power Supply System (WPPSS), Tennessee Valley Authority (TVA), Virginia Electric Power Company (VEPCo) and Consumers Power Company (CPCo), indicating that under the authority of Section 132 of the Atomic Energy Act of 1954, as amended, and Section 50.54(f) of 10 CFR Part 50, additional information was requested to allow us to determine whether it is necessary to halt all or portions of the construction of their plants pend-ing the results of our study.
In addition, in this letter we specified that it would be beneficial for the utilities, B&W and the staff to meet to dis-cuss this matter.
This meeting was held on flovember 6,1979. lists the meeting attendees.
-Discussion At the November 6,1979 meeting with WPPSS, T7A, VEPCo, CPCo and B&W, our 10 CFR 50.54 request which was transmitted with our October 25, 1979 letter, was discussed.
In addition, we provided information relative to our Cyrstal River study which was initiated to quantitatively assess S&W system designs.
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4 Steven A. Varga NOV 141979 I
This study will attempt to identify obvious, high frequency accident sequences leading to core damage, as compared to the Reactor Safety Study.
The respective nuclear plants affected were WPPSS Nuclear Project, No. I and No. 4 Bellefonte Nuclear Plants, No.1 and No. 2, North Anna Power Station, Units 3 and 4 and Midland Plant, Units 1 and 2.
i The agenda of the meeting was as follows:
1.
Review of the 10 CFR 50.54 request 2.
Where do we go from here 3.
End product of our study 4.
The Crystal River Study 5.
Comments from B&W Dr. Ross, of the staff, in his opening remarks provided background as to the reason for the staff's 10 CFR 50.54 request and followed his presentation with a review of the October 25, 1979 letter. With respect to the second item of the agenda, Dr. Ross indicated that an ad hoc group will review the rasoonses from the utility. The group will consist of Mr. Novak who will head a review team of systems people and the assigned project manager for each respective plant.
It was noted that the utility responses were requested by December 3, 1979. We in turn proposed to review the responses by December 15, 1979, Dr. Ross indicated that this was an optimistic program for the staff. After our review is complete our findings will be transmitted to the Commission. Virginia Electric Power Company indicated that they would not be responding to our letter since at present they have ceased engineering and construction activities on the site.
Mr. Murphy made the presentation relative to the Crystal River Study. is the vu-graphs of his presentation.
It was suggested that the utilities should be cognizant of this on-going study.
Mr. LaBelle of Babcock and Wilcox described the work initiated by 3&'J in order to respond to request (a) of our October 25, 1979 letter and. requested guidance from the staff regarding this work. Enclosure 3 is the vu-graphs of his presentation. Mr. LaBelle requested clarification regarding the analyses that B&W will be performing to respond to our concerns. We stated that we were not only looking for severe overcooling occurrences from accident events but in addition from anticipated transients. We strongly advise them to consider both events.
Anthony Bournia, Project Manager,
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Mr. N. O. Strand Managing Director Washington Public Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 99352 0) cc:
Mr. B. D. Redd Jercme E. Sharfman United Engineers & Constructors, Inc.
Atomic Safety and 30 South 17th Street Licensing Appeal Soard Pi.iladelphia, Pennslylvania 19101 U. S. Nuclear Regulatory Commission Nicholas S. Reynolds, Esq.
Washington, D. C.
20555 DeBevoise & Liberman
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1200 Seventeenth St., N. W.
Washington, D. C.
20036 Mr. E. G. Ward Senior Project Manager Babcock & Wilcox Company P. O. Box 1260 Lynchburg, Virginia 23505 Robert Lazo, Esq., Chairman e-Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission f"'
Washington, D. C.
20555 e
Dr. Donald P. deSyl va Associate Professor of Marine Science Rosenthiel School of Marine and Atmospheric Science
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University of Miami Miami, Florida 33149 m
Dr. Marvin M. Mann Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission 0c.
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Washington, D. C.
20555 Richard S. Salanan, Chairman C'
Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission
.- l Washington, D. C.
20555
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Dr. John H. Buck Atomic Safety and Licensing Appeal Board
$I U. S. Nuclear Regulatory Commission Washington, D. C.
20555 4
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Mr. H. G. Parris Manager of Power Tennessee Valley Authority.
500A Chestnut Street, Tower II Chattanooga, Tennessee 37401 cc:
Herbert S. Sanger, Jr., Esq.
General Counsel Tennessee Valley Authority 400 Commerce Avenue, E11833 Knoxville, Tennessee 37902 Mr. E. G. Beasley Tennessee Valley Authority 400 Commerce Avenue, W10C131C Knoxville, Tennessee 37902 Mr. D. Terrill Licensing Engineer Tennessee Valley Authority 400 Chestnut Street Tower - II Chattanooga, Tennessee 37401 Mr, Dennis Renner Babcock & Wilcox Company P. O. Box 1260 Lyr.chburg, Vi rginia 24505 Mr. Robert B. Borsum Babcock & Wilcox Company Suite 420 7735 Old Georgetown Road Bethesda, Maryland 20014
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Mr. W. L. Proffitt Senior Vice President - Power Operations Virginia Electric & Power Company P. O. Box 26666 Richmond, Virginia 23261 cc: Mr. Anthony Garcbaradella Cl arence T. Kipps, Jr., Esq.
Office of the Attorney Ceneral 1700 Pennsylvania Avenue, N.W.
11 South 12th Street - Room 308 Washington, D. C.
20006 Richmond, Virginia 232 19 Carroll J. Savage, Esq.
Richard M. Foster, Esq.
1700 Pennsylvania Avenue, N.W.
211 Stribling Avenue Washington, D. C.
20006 Charlottesville, Virginia 22903 Mr. James C. Dunstan Michael W. P.aupin, Esq.
State Corporation Comission Hunton, Williams, Gay & Gibson Cornaont.ealth of Virginia P. O. Sox 1535 Blandon Building Richmond, Virginia 23212 Richmond, Virginia 23209 Mrs. June Allen Alan S. Rosenthal, Esq.
412 Owens Drive Atomic Safety and Licensing Appeal Eoard ibntsville, Alabama 35801 U.S. Nuclear Regulatory Comission Washington, D. C.
20555 Mr. James Torson 501 Leroy Michael C. Farrar, Esq.
Socorro, New Fexico 87801 Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Comission Mrs. Margaret Dietrich Washington, D. C.
20555 Route 2, Box 568 Gordonsville, Virginia 22942 Dr. John H. Buck Atomic Safety and Licensing Appeal Board Willi an H. Rodgers, Jr., Esq.
U.S. Nuclear Regulatory Comission Georgetown University Law Center Washington, D. C.
20555 600 New Jersey Avenue, N.W.
Washington, D. C.
20001 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Comission Mr. Peter S. Hepp Washington, D. C.
20555 Executive Vice President Sun Shipping & Dry Dock Company Mr. Michael S. Kidd P. O. Box 540 U.S. Nuclear Regulatory Comission Chester, Pennsyl vania 19013 P. O. Box 128 Spotsivania, Virginia 22553 Mr. R. B. Briggs Associate Director Dr. Paul W. Purdom 110 Evans Lane Department of Civil Enginering Oak Ridge, Tennessee 37830 Drexel thiversity Philadel rhia, rennsyl,vania 19101 1442 M2
Mr. W. L. Proffitt cc:
Dr. Lawrence R. Quarles Apartment No. 51 Kendal-at-Longwood Kennett Square, Pennsylvania 19348 Mr. Irwin B. Arcot Citizens Energy Forum P. O. Box 138 McLean, Virginia 22101 James B. Dougherty, Esq.
Potomac Alliance 1416 S Street, N.W.
Washington, D. C.
20009 1442 193
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Consumers Pover Company ccs:
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Michael I. Miller, Esq.
Mr. S. H. Howell 1;
Isham, Lincoln & Beale Vice President 4.
Suite 4200 Consumers Power Company
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One First National P1aza,
212 West Michigan Avenue I,
Chicago, Illinois 60603 Jackson, Michigan 49201 4.
Juilit.L. Daton, Ls.i.
Consur.ers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Mr. Paul A. Perry Secretary Consumers Pover Company 212 W. Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esq.
One IBM Plaza Chicago, Illinois 60611 Mary Sinclair 5711 Summerset Drive Midland, Michigan 48640 Frank J. Kelley, Esq.
Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 1
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Mr. Wendell Marshall Route 10 Midland, Michigan 48640 4
i Grant J. Merritt, Esq.
Thompson, Niel sen, K1 averkamp & James 4444 IDS Center 80 South Eighth Street Minneapolis, Minnesota 55402 i
Mr. Don van Farove, Chief Division of Radiological Health Department of Public Health P. O. Box 33035 Lansing, Michigan 43'JO9
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MEETING ATTENDEES NOVEMBER 5,1979 WPPSS PGL s G. C. Sorensen D. R. Swanson J. P. Thomas J. V. Hanson A. Hosler UECo' A. J. Friedman TVA D. L. Lambert B&W D. L. Terrill L. M. Mills C. W. Connell, Jr.
M. A. Linn G. D. Quale L. A. Haack G. F. Malan J. Raulston R. B. Borsum R. Christie D. W. LaBelle B. L. Day R. J. Ansell VEPCo E. A. Womack H. J. Taylor W. B. Rodill D. H. Roy E. S. Grecheck R. R. Steinke M. R. Terry W. Weaver H. J. Fortune V. Mani NiR,,C, CPCo D. B. Vassallo D. Ross D. T. Perry L. S. Rubenstein T. J. Sullivan T. M. Novak s
S. H. Howell R. P. Denise N. W. Salerno J. Murphy J. J. Zabritski G. R. Mazetis C. Graves D. Thatcher OECo R. A. Capra W. Hodges J. A. Hultz S. A. Varga B. M. Miller D. Hood A. Bournia Nucleanics Week S. Wynkoop
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ENCLOSURS g 1442 196
RISK SURVEY OF CRYSTAL RIVER UNIT 3 PROBABILISTIC AilALYSIS STAFF 0FFICE OF NUCLEAR REGULATORY RESEARCil U.S. NUCLEAR REGULATORY COMMISSI0tl NOVEMBER 1979 OUTLINE:
I.
LESS0fls LEARNED FROM Tile TMI ACCIDENT FOR NUCLEAR RISK ASSESSMENT
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II.
IllTEGRATED RELIABILITY EVALUATION PROGRAM III. PILOT STUDY:
CRYSTAL RIVER IV.
ASSISTANCE AND COLLABORATIOl1 REQUESTED FOR FPC, B&W, AllD GILBERT V.
AllTICIPATED OUTCOME O
w N
I.
LESS0flS LEARNED FROM Tile TMI ACCIDENT FOR NUCLEAR RISK ASSESSMENT A.
TMI DEMONSTRATED AN EVENT SEQUENCE LEADING TO CORE DAMAGE TilAT WAS MORE PROBABLE TilAN llASN-1400 SEQUENCES DUE TO EQUIPMENT AND llUMAN INTERACTIONS B.
TMI TRIGGERED A IlEW LOOK AT PLANT-TO-PLANT DIFFERENCES 1.
STUDY OF AUXILIARY FEEDWATER SYSTEM RELIABILITY IN CE AllD WESTINGil0VSE PLANTS INDICATES WIDE PLAllT-TO-PLANT VARIATION IN RELIABILITY
.2.
0 tiler EVIDENCE OF WIDE VARIATIONS IN RISK ATilS SUSCEPTIBILITY g
INTERFACING SYSTEMS LOCA N
STATI0llBLACK0UT G
CD
II.
INTEGRATED RELIABILITY PROGRAM A.
OBJECTIVES 1.
IDENTIFY AtlY llIGil-RISK ACCIDEllT SEQUENCES IN OPERATIllG PLANTS USIllG RSS METil0DS 2.
BUILD F00flDATI0flS FOR FURTIIER APPLICATIONS L0flG RAtlGE DEVELOPl1ENT OF RISK-OR RELIABILITY-BASED LICENSING ASSISTAtlCE TRAINIllG OF CADRE OF RISK AtlALYSTS RELIABILITY MODELS USEF!!L FOR:
o llUMAfl ERROR RISK ASSESSMENTS o
COMM0ll MODE FAILURE STUDIES o
SYSTEMS IllTERACTI0ll STUDIES x-o OPERATIONS EVALUATIO!l, ETC.
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B.
METil0DS 1.
EVENT TREE ANALYSIS 2.
SIMPLIFIED FAULT TREE ANALYSIS 3.
ESTIMATION OF RELEASE CATEGORIES FOR ACCIDENT SEQUENCES i
fl.
QUANTIFICATION OF PROBABILITY OF INITIATING EVENTS AND EQUIPMENT FAULTS INCLUDIllG PRE-EXISTING llUMAN-CAUSED FAULTS 5.
SENSITIVITY STUDIES FOR RELIABILITY OF OPERATOR RESPONSE, AS REQUIRED s3 no CD
III. PILOT STUDY - CRYSTAL RIVER A.
OBJECTIVES 1.
PROTOTYPE OF IREP RISK STUDIES 2.
ADDRESS Ball SENSITIVITY ISSUE 3.
ADDRESS INTEGRATED CONTROL SYSTEM INTERACT 10tl ISSUE B.
PROGRAM PLAN 1.
SURVEY BACKGROUllD DATA:
LER'S AllD A0'S FOR PRECURSORS, SYSTEMS IllTERACTI0flS ICS FAILURE MODES AND EFFECTS ANALYSIS DYNAMIC RESPONSE AflALYSES (TMI & ATWS STUDIES)
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2.
DE\\" t_0P EVEllT TREES.
CAllDIDATE TREES ARE:
TRANSIENTS o
LOSS OF 0FFSITE POWER o
STATION BLACK 0UT i
LARGE o
SMALL I
o VERY SMALL n"
o INTERFACING SYSTEMS LOCA
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3.
DEVELOP SIMPLIFIED FAULT TREES fl.
PRELIMINARY 00ANTIFICAT!0tl AND RESULTS 5.
PRELIMINARY FINDINGS AND RECOMMENDATIONS -
MARCll 1980 i
6.
DETAILED ANALYSFS, AS HECESSARY O
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IV.
ASSISTANCE AND COLLABORATION REQUESTED OF FLORIDA POWER CORP., BABC0CK AND WILC0X, AND GILBERT ASSOCIATES A.
COLLABORATION 1.
EVENT SEQUEllCE ANALYSIS AND SYSTEM RELIABILITY ANALYSIS WILL BE PERFORMED BY NRC; REVIEW BY 18PC, B&W, AND GA IS WELCOME 2.
CALCULATIONS OF Tile DYllAMIC RESP 0flSE OF Tile
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NSSS WILL DE REQUESTED OF Tile VENDOR.
NRC
. WILL REVIEW ANALYSES AND MAY USE AVAILABLE RES TECilNIQUES B.
flRC ACCESS TO PLANT AND PERSONNEL 1.
INSPECTIONS OF ACCESSIBLE SYSTEMS 2.
COMMutilCATION WITil 0PERATIONS AND MAINTEllANCE PERS0flflEL j.
3.
POSSIBLE Ofl-SITE OR HEAR-SITE ACCESS FOR FAULT TREE TEAM FOR VERIFICATI0fl 0F AS-BUILT DESIGN S$
C.
flRC ACCESS TO DESIGfl AND PROCEDURAL DATA
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V.
NITICIPATED OUTCOME A.
AC'llDENT SEQUENCES WHICH DOMIflATE Tile CORE DNiAGE P0TEllTIAL AND RISK ASSOCIATED WILL BE IDENTIFIED -
LIKELY CAllDIDATES ARE:
1.
STATI0il BLACK 0UT
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2.
INTERFACIllG SYSTEMS LOCA 3.
SMALL LOCA 8
4.
ATWS A ROUGli ESTIMATE OF Tile MAGNITUDE OF Tile INDIVIDUAL RISK WILL BE OBTAINED Z
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B.
ET/FT TECllllIQUES ARE ONE OF Tile BEST WAYS TO DISCOVER AND RANK ACCIDEllT RISK CONTRIBUTORS AND TO JUDGE IMPACTS OF IMPROVEMENTS
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1.
SYSTEMATIC METil0D OF DISCOVERY 2.
AVOIDANCE OF TUNilEL VISION:
ISOLATED FIXES MADE OUT OF CONTEXT TilAT (11 Gilt INCREASE, NOT IMPROVE, RISK LEVEL i
3.
REALISTIC INTEGRATI0ll 0F " SAFETY" AND "NON-SAFETY" SYSTEMS 11.
FOCUS ON FUNCTIONAL RELATIONSillPS OF SYSTEMS 5.
IDENTIFIES IlUMAN INVOLVEMEllTS Ill MULTIPLE FAILURE EVENTS
$2 ma CD CN
C.
WilERE RISK DOMINANT ACCIDENT SEQUENCES ARE FOUND, WE INTEND TO SUGGEST POSSIBLE OPTI0flS FOR IMPR0VIllG RELIABILITY AND REDUCING RISK D.
ASSIST NRR IN RESOLUTION OF CONCERNS RELATIVE TO STABILITY OF NSSS DESIGil e
N M
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ENCLOSURE 3 1442 208
d KEY FACTORS AFFECTING OVERC00LIllG EVdilT C0iiSEQUEilCES o
INITIATIO;l ilME AND RATE OF OVERC00LI.51G o
INITIATI0il TIME AilD RATE OF fiPI o
REDUCTIO?! OR TERMIllATIO;10F C00LD0'61 RATE (E.G., OPERATOR ACTIO:1, SG LEVEL C0:lTROL, MFW ISOLATION) 1442 209
'O f
CHARACTERISTICS OF SEVERE OVERC00LIiiG EVENTS o
REACTOR TRIPS 03 HIGH FLUX OR LOW RC PRESSURE o
ESFAS ACTUATED ON LOW RC PRESSURE OR LOW SG PRESSURE (1)
HPI ACTUATED (2)
MSIV/MFIV CLOSURE (3)
AFW ACTUATED o ESFAS (VIA F0GG-TYPE SYSTEM LOGIC) ISOLATES AFW FLOW TO DEPRESSURIZED OTSG o OVERC00Llis'G TERMINATED BY OTSG LEVEL CONTROL OR OPERATOR ACTION o HPI CONTROLLED OR TERMINATED BY OPERATOR ACTION 1442 210
LIMITING CONSEQUENCE ANALYSIS WORK SCOPE INITIATING SINGLE KEY SEf1SITIVITY EVENT FAILURE ASSUMPTIONS STUDIES REACTOR TRIP /
MAIN FEEDWATER o
102% FP FOR AT LEAST THE LIMITING CASE (S):
TURBINE TRIP OVERFEED o
E0L a
FULL DECAY HEAT STEAM PRESSURE MAIN STEAM o
FULL RC FLOW
~^
REGULATOR RELIEF VALVE o
MAXIMUM SHUTDOWN
- AT LOW RC PRESSU.1E ESFAS TR P' MALFUi1CTIO,'l STUCK OPEN R0D WORTH
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o RCS METAL HEAT SilALL SLC MAIN STEN 1 o
ONLY SAFETY SYSTEMS
(~ 2 FT )
RELIEF VALVE USED FOR f1ITIGATION STUCK OPEil o
FULL HPI CAPACITY (2 PUMPS)
DER SLB MAIN STEAM o
MAP 2 CODE RELIEF VALVE
- MAXI-MODEL FOR FIRST MINUTE I
STUCK OPEN
- MI!I-f;0 DEL FOR N
10 filflulE CASES N
o PLAiiT DESIGNS C
- 177 FA (2452 MWT)
- ?'S F A (:7n M"T)