ML20214L611
| ML20214L611 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/26/1987 |
| From: | Lo R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8706010023 | |
| Download: ML20214L611 (26) | |
Text
7 May 26, 1987 h
Docket No. 50-322 O
LICENSEE: Long Island Lighting Company FACILITY: Shoreham Nuclear Station, Unit 1
SUBJECT:
SUMMARY
OF MEETING WITH LILCO ON MAY 12 and 13,1987 A neeting was held between the NRC staff and its consultants from the National Labs and LILCO and its technical consultants on May 12 and 13, 1987. On April 14, 1987, LILCO submitted a request before the Comission for authorization to operate Shoreham at 25% of the rated power. The request package includes information relevant to the safety of Shorehan when operated both at 25% power and at full power. The purposes of the meeting were to discuss the parameters used in LILC0's accident analysis and to discuss the various safety improvements such as modifications to the Standby Liquid Control System and the corium ring.
The list of attendees is enclosed.
During the first day of the meeting, LILC0 discussed the staffs' questions related to the probabilistic accident assessment (PRA). Specifically, some of the areas covered are: (1) credits for station modifications in PRA; (2) operator response time assumptions; (3) assumptions for dominant accident sequences: fission product inventory, release fractions, release energies and locations, release durations and dose contributions; (5) containment analysis parameters. The second day of the meeting included a tour of the Shoreham plant and covered the systems and equipment such as on-site AC power, the corium ring, the Alternate Rod Injection System, which LILC0 clains to have improved the overall safety of the Shoreham Station. The viewgraphs LILCO used during the meeting are enclosed.
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8706010023 870526 /S/
PDR ADOCK 05000322 p PDR. Ronnie Lo, Project Manager Project Directorate PDI-2 Division of Reactor Projects I/II
Enclosures:
As stated DISTRIBUTION Docket File OGC - Bethesda NRC PDR Edordan LPDR JPartlow FDI-2 Rdg. NRC Participants WButler ACRS (10)
Plo/GRivenbark PDI-2/P, PDI-2/D l RLo: car WButler #y
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l Mr. John D. . Leonard, Jr. Shoreham Nuclear Power Station Long Island Lighting Company (list 1)
CC*
Stephen B. Latham, Esq. Gerald C. Crotty, Esq.
John F. Shea, III, Esq. Ren Wiles, Esq.
-Twomey, Latham & Shea Counsel to the Governor Attorneys at Law Executive Chamber Post Office Pox 398 State Capitol 33 West Second Street Albany, New York 12274 Riverhead, New York 11901 Herbert H. Brown, Esq.
Alan S. Rosenthal, Esq., Chairman Lawrence Coe Lanpher, Esq.
Atomic Safety A Licensing Appeal Board Karla J. Letsche, Esq.
U.S. Nuclear Pegulatory Comission Kirkpatrick & Lockhart Washington, D.C. 20555 South Lobby - 9th Floor 1800 M Street, N.W.
Washington, D.C. 20036-5891 W. Taylor Reveley, III, Esq.
Hunton A Williams Dr. Monroe Schneider 707 East Main Street North Shore Comittee Post Office Box 1535 Post Office Box 231 Richmond, Virginia 23212 Wading River, New York 11792 Howard A. Wilber Fabian G. Palomino, Esq.'
Atomic Safety & Licensing Appeal Board Special Counsel to the Governor U.S. Nuclear Regulatory Commission Executive Chamber - State Capitol Washington, D.C. 70555 Albany, New York 12274 l Atomic Safety 8 Licensing Poard Panel Anthony F. Earley, Jr., Esq.
U.S. Nuclear Regulatory Comission General Counsel Washington, D.C. 20555 Long Island Lighting Company 175 East Old County Road Atomic Safety 8 Licensing Appeal Board Hicksville, New York 11801 Panel U.S. Nuclear Regulatory Commission Mr. Lawrence Britt Washington, D.C. 20555 Shoreham Nuclear Power Station Post Office Box 618 Gary J. Edles. Eso. Wading River, New York 11792 Atomic Safety 8 Licensing Appeal Roard U.S. Nuclear Regulatory Comission Martin Bradley Ashare, Esq.
Washington, D.C. 20555 Suffolk County Attorney H. Lee Dennison Building Richard M. Kessel Veteran's Memorial Highway Chairman & Executive Director Hauppauge, New York 11788 New York State Consumer Protection Board Room 1725 Resident Inspector 250 Broadway Shoreham NPS New York, New York 10007 U.S. Nuclear Regulatory Commission Post Office Box B Jonathan D. Feinberg, Esq. Rocky Point, New York 11773 New Yerk State Department of Public Service Regional Administrator, Reofon I Three Empire State Plaza U.S. Nuclear Reaulatory Comission Albany, New York 12223 631 Park Avenue King of Prussia, Pennsylvania 19406 ,
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Lorg Island Lighting Company Shoreham (1) cc:
Rc.nert Abrams, Esq. Mr. Francis J. Gluchowski Attorney General of the State Assistant Town Attorney of New York Town of Brookhaven ATTN: Peter Bienstock, Esq. Department of Law Decertment of Law 475 East Main Street State of New York Patchogue, New York 1177F Two Porld Trade Center Room 46-14 New York, New York 10047 Mr. William Steiger Plant Manager Shoreham Nuclear Power Station Post Office Box 628 Wading River, New York 11792 MHB Technical Associates 1723 Hamfitnn Avenue - Suite K San Jose, California 95125 honorable Peter Cohalan Erffolk County Executive Cn'mtv Executive / Legislative Building Vateran's Memorial Highway Hauppauge, New York 11788 Mr. Jay Dunkleberger New York State Energy Office t, rey Building 2 Empire State Plaza Albany, New York 12223 Ms. Nora Bredes Shoreham Opponents Coalition 195 East Main Street Smithtown, New York 11787 Chris Nolin New York State Assenbly Energy Comnittee 676 Legislative Office Building Albany, New York 12248 Peter S. Everett, Esq.
Hunton & Williams 2000 Pennsylvania Avenue, NW Washington, D.C. 20036
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- ................................ 25% POWER PRA I
\ CIASS I (SS B%) l
............ CIASS IV (14.8%) .......
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l ....................... \ ................. .................... tN ......................... .................... t ........................... CIASS I (57.8%) ' . ' . . " . " ........ 1 ............................ I CIA 38 C (15.2%) ............................ CLASS III (1.9%) - . . . " . . . . " . .
........... CIAss I (sr.3%)
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PLANT SPECIFICS (CONTAINMENT CONFIGURATION, REACTOR CORE DETAILS, - ENGINEERED SAFEGUARD SYSTEMS) If CORE & CONTAINMENT RESPONSE SCOPING < > ANALYSIS l A SYSTEMS 1 I ANALYSIS & CONTAINMENT m ADJUSTMENTS PLANT DAMAGE " ' S AT S EVENT TREES REQUIRED 1 SK IMPORTANCE & ACCEPTABLE REPRESENTATIVE NRANKING RESULTS 1 r TO OFF SITE l FROM RADIONUCLIDE CONTAINMENT CONem FNCE l i RELEASE AND & RELEASE STATES #- r FREQUENCIES AND 'v AND RISK TRANSPORT ANALYSIS , SOURCE TERMS ANALYSIS - (MAAP 3.0) (CRACIT,CRAC2) i Figure 21 Elements of Containment Event Tree Analysis l 2-4
Table 3-2 SHOREHAM CONTAINMENT EVENT TREE END STATE CATEGORIZATION RELEASE MODE QUALITATIVE ATTRIBUTES "A States" Core Cooling Recovered with: A1 - Containmentintact "B States" Core melt with containment failure in the short term (i.e., prior to or shortly after vessel breach) B1, B5* - Slow release through the pool with RB retention B2, B6* - Slow release through the pool water B3,B7*
- Slow release bypusing the pool with RB retention B4,B8* -
Slow release bypassing the pool
. B9 -
Moderate release through the pool with significant RB retention B10 - Moderate release through the pool B11 - Moderate release bypassing the pool but with RB retention B12 - Moderate release bypassing the pool B13 - Large puff release through the pool B14 - Large puff release bypassing the pool "C States" Core melt with containment failure induced by operator venting long after vessel breach and release from the fuel C1 - Vented release through the pool C2 - Vented release bypassing the pool "D States" Core melt with mitigated release in the long term i D1 - Design leakage rates determine release magnitudes of noble gases (no ex vessel releases) D2 - Design leakage rates determine release
, magnitudes of noble gases and particulates t
*Small and large containment failure leakage size, respectively. For small leakage size, the noble gases are estimated to be released in two whases, an initial puff followed by a slow release for several hours because of the lack of sufficient fission product driving force.
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I l FREQUENCY CET END STATE SOURCETERMS PLANT DAMAGE GIVEN GIVEN CET l STATE (PDS) PDS END STATE lA IB hD2 Kr-Xe Cst- Te 10 Sr ID B1
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+
RANK IN TERMS OF RISK FOR DOMP4 ANT SEQUENCES V REPRESENTATIVE SEQUENCES 2 FOR RELEASE CATEGORIES ,
+ SEE SECTON 2
++ SEE SECTON 4 FIGURE 5-1 CET RELEASE CHARACTERIZATION AND BINNING PROCESS FOR RISK IMPORTANCE RANKING 5-4
~ v v v v a Tablo 4.5-2 . ev . T Supe 4ARY OF ACCIDENT SEQUENCE FREQUENCIES y (25% POWER INITIAL START-UP), S w SEISMIC DOMINANT FIRE INDUCED INDUCED CLASS / SUBCLASS SEQUENCE CORE MELT, CORE MELT, CORE MELT, CLASS DESIGNATOR CATEGORY FREQUENCY FREQUENCY FREQUENCY TOTAL Class ! A Internal 1.5E-5 3.7E-8 1.8Ea8 1.5E-5 : B Seismic 3.6E-7 - 1.9E-6 2.3E-6 C Internal 6.6E-10 - - 6.6E-10 D Internal 4.2E-6 4.2E-7 - 4.6E-6 Class II Fire c" 1.0E-9 4.8E-10 1.5E-9 i Class III A Internal c" - - c" E 8 Internal 2.4E-8 - - 2.4E-8 4 C Internal 7.0E-7 - - 1.0E-7 D Internal 1.1E-7 - - 1.1E-7 Class IV Internal 3.9E-6 - - 3.9E-6 Class V Internal 1.2E-8 - - 1.2E-8 SRPV - Seismic - .- 8.0E-7 8.0E-7 TOTAL NA 2.5E-5 4.6E-7 2.7E-6 2.8E-5
+ All frequencies per reactor year.
++ c = less than 1.0E-9/ reactor year.
- Totals may not match due to round-off.
I i
RELEASE CHARACERISTICS USED FOR RELEASE MODE GROUPING . _ RELEASE MODES _ QUALITATIVE ATTRIBUTES PRIMARY OTifER CONTRIBITTORS CONTRIBUTORS BINNEDCONSERVATIVELY RC1 No pool scrubbing B14 Large leakage size with driving force Low reactor building retention Short duration,early release RC2 No pool scrubbing B8 B12(Small leakage with driving force)* Large leakage size; but B4 (Smallleakage 1 without driving force without driving force) low reactor building retention Moderate duration,early release - 4 I RC3 Pool terubbing B13 l Y' Large leakage size with B10(Small leakage with driving force)* j 0 IAw reactor building retention B9(Small leakage with driving force and Short duration,early release reactor building retention) RC4 No pool scrubbing B7 B6(Pool scrubbing without reactor building Smallleakage size retention)
- or B11 B2(Poolscrubbing withoutreactorbuilding Largeleakage size retention) without the driving force Reactor building retention B3 B1(Pool scrubbing with reactor building Long duration with containment retention) attenuation, early release B5(Pool scrubbing with reactor building
, retention) RCS Late release with and Cl,C2 without pool scrubbing RC6 Designleakage(contained D1,D2 release) Recovered core melt states
- Failure modes involving small leakage are defined to include a small break size which limits the equivalent flow rates obtained after containment failure. (see Section 3.2.1) The availability of a driving force would not substantially change the leakage rates if the flow is restricted by the hole size. Hence, the residence time is considered equivalent to the case where a large leakage size is obtained but no driving force is available.
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0.0 80 100 120 140 160 i PRESSURE (PSI) Figure D.7 Sensitivity to Cumulative Containment failure Probability Distribution D-17
r .- , m. _ _ am- - . - w c-- s~ w_ 2 . _ . .----- or. _. . ----_----------=-C TABLE D-3 CONTAINMENT FAILURE MODE DISTRIBUTION Failure Mean Conditional Failure Probability Locadon Capacity Pressure (psig) psig) 100 110 110 13.0 14Q 110 Wetwell 130 1.0 .93 .90 .82 .775 .774 DrywellHead 140 <10-5 .07 .10 .18 .225 .227 3.6x104 DrywellWall 174 10 5 10-5 10-5 a10-5 5.9x10~4
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De ratio of the wetwell failure to the total containment failure probability is found to be asymptotic to a value of 0.774 as the containment pressure exceeds the mean capacity at either location. S D 19 e
r o M M M E E TABLE 3-6 SUp9tARY OF FIRE RESULTS FOR SNPS BY CRITICAL ROOMS AND CORE VULNERABLE CLASSES ACCORDING TO THE SNPS PRA DEFINITIONS (REACTOR AT 25% POWER) MEAN FIRE-INDUCED CORE DAMAGE FREQUENCY (RY-1) CLASS CLASS CLASS CLASS CLASS
- CLASS ROOM g IA IB IC ID I II Room 1.3x10-8 --- ---
1.4x10-7 1.5x10-7 2.8x10-10 1.53x10-7
* *Y 2.4x10-8 2.8x10-7 3.0x10-7 7.7x10-10 pgg, 3.05x10-7 TOTAL 3.7x10-8 --- ---
4.2x10-7 4.5x10-7 1.0x10-9 4.60x10-7 i
*This is the summation over classes IA, IB, IC and ID
.=
TABLE 3-8 SUDMARY OF SEISMIC RESULTS FOR SNPS MCCI BY EVENT TREE DESIGNATOR AND CORE DAMAGE ACCIDENT CLASSES ACCORDING TO THE SNPS PRA DEFINITIONS, EARLY PLANT OPERATIONS AT 25% POWER MEAN SEISMICALLY-INDUCED CORE DAMAGE FREQUENCY (RY-1) EVENT CLASS CLASS CLASS DESIGNATOR IA IB II . RPV SUPPORT RING FAILURE 8.0x10-7(S-5) 8.0x10-7 I 'ta b" CONTROL BUILD-ING OR CABLE 3.0x10-7 I8~4I TRAY FAILURE 3.0x10-7 SERVICE WATER SYSTEM 1.1x10-6 (S-3) 1.1x10-6 FAILURE 1.8x10-7 (E-5) 4. 8x10-10 (E-14) LOSP 1.8x10-8(E-6) 2.1x10-10(E-12) 4.7x10-7 2.7x10-7 (E-7) TOTAL 1.8x10-8 1.9x10-6 4.8x10-10 8.0x10-7 2.7x10-6 NOTE: Mean sequence frequency, number in parenthesis corresponds to event- tree sequence numbers. See Figure 3-13 for "S" designation seismic sequences and Figure 3-15 for "E" designation LOSP tree sequences.
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4 4
SUMMARY
OF SIIOREllAM PRA RELEASE CATEGORIES (25% POWER) 3 l RELEASE REPRESENTATIVE 4 RELEASE SEQUENCE FREQUENCY ( CATEGORY - SEQUENCE - . CIIARACTERISTICS I (Per Reactor-Year) .t ii l RCI e KI'WS Class IV plant damage ,
, short duration and
{ 6.4E-7 ) state with overpressure failure m e m ev rei m e. j in the drywell or werwell with Noble gases and a few percent j 1 downcomers failure, bypassin'gthe - of particulates are j4,' pool with minimum reactor building released. retention. Suppression poolis ' 1 saturated providing sustained gas ilow rates. , ;. ',. 4
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QUALITATIVE ATTRIBUTES . PRIMARY OT1tER CONTRIBUTORS g CONTRIBUTORS BINNED CONSERVAllVELY ? t 3 RCI No pool scrubbing B14 . Large leakage size ~. with driving force y-Low reactor bm.lding retention . Shortduration,earlyrelease. - - u
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No pool scrubbing =- .- 2
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- Failure modes involving small leakage are defined to include a small break size which limits the eq uivalent flow rases obtained afeer containment failure. (see Section 3.2.1) The availability of a driving forte would not substantia 11y c kge the leakage rases if the flow is restricted by the hole size. Hence,the reMeam time is considered equivalent so the case where a large leakage size is obtained but no driving force is available. - .
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