ML20236F877
| ML20236F877 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/28/1987 |
| From: | Lo R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20236F881 | List: |
| References | |
| NUDOCS 8708040058 | |
| Download: ML20236F877 (5) | |
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[pna % UNITED STATES
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, ,I{ NUCLEAR REGULATORY COMMISSION 3'
E WASHINGTON, D. C. 20555 July 28, 1987
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Docket No.: 50-322 LICENSEE: Long Island Lighting Company FACILITY: Shoreham Nuclear Station, Unit - 1 i
SUBJECT:
SUMMARY
OF MEETING WITH LILCO ON JULY 21, 1987 REGARDING THE DESIGN OF A SUPPLEMENTAL CONTAINMENT SYSTEM (SCS) i At the request of Long Island Lighting Company (LILCo), a meeting between the l NRC staff and the nanagement of LILCo was held in Bethesda, MD, on July 21, i 1987. The purpose of the meeting was for the staff to receive a briefing from LILCo on its plan to design and construct a Supplemental Containment System (SCS) for the Shoreham Nuclear Station. The discussions in the meeting were transcribed and a copy of the transcript is provided as Enclosure 1.
The principal speakers included LILCo's Vice President, Mr. John Leonard and Dr. Thomas Murley who led the staff in discussing the safety aspects of the SCS. The meeting was also attended by Mr. Gregory Minor, representing Suffolk Centy, N.Y., which is a party intervening in the licensing proceedings of the Shorehen, plant. A list of attendees, along with the viewgraphs used in LILCo's ,
presentation are included in Enclosure 1. The following summary notes the salient peints of the discussion. The associated pages nf the transcript are shown in parentheses, j J
The primary purpose of the SCS is to provide a mechanism to relieve the pressure in the wetwell Pirspace for a class of low probability /high consequence severe accidents which could challenge the structural integrity of the containment (9). The Shoreham containment design pressure is 48 psig and the ultimate structural pressure is approximately 130 psig (10). The pressure setpoint of the rupture disc in the vent path leading to the Filtra Building of the SCS will be set at 60 psig. This setpoint is chosen to ensure the integrity.
of the drywell floor seal (12). The Filtra Building will be similar to the Swedish installation at the Barseback plant. It consists of a steel-lined concrete structure with a volume of 10,000 cubic meters containing about 14,000 kg of quartzite-type gravel material as the filter medium (22). The desi basis for the SCS is OA Category I to the Containment Pressure Boundary (gnCPB) and QA Category II beyond the CPB. The mechanical design basis is ASME III, Class 2 up to the CPB and ASME III, Class 3 beyond the CPB (31,88). ,
The main concerns raised by the staff during the meeting were related to assurance that no potentially unsafe conditions will be introduced by the SCS. The following is a highlight of some of the staff's concerns and questions:
i 8708040058 870728 PDR ADOCK 05000322 Tf" PDR l
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't How will the activatier of filtered venting be considered in conjunction with the unfiltered venting procedure in the E0P (18).
Analyses to quantify the reduction of public risk (24).
Analyses on the releases from the SCS in new accident sequences where the containment is recoverable (25, 26, 41-43, 50).
Response of the SCS to a short duration pressure pulse in the containment (38).
Analyses of accident sequences which could lead to pump cavitation and core damage because of the pressure relief, although the containment integrity is maintained (44, 52-54).
Concerns about the potential of the containment approaching a negative pressure in the event that the containment spray is activated (81-83).
LILCo irtends to review the transcript and respond to the staff's concerns which are not limited to those highlighted above. LILCo would wish to obtain the resolution of the safety concerns and staff guidance on design requirements prior to committing major design and construction contracts (104). The schedale for project completion is 36 months following the award of the design contract.
- t 02'c Ronnie Lo, Project Manager Project Directorate PDI-2 Division of Reactor Projects !/II
Enclosure:
As stated cc w/o enclosure:
See next page l
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T Mr. John D. Leonard, Jr. Shoreham Nuclear Power Station Long Island Lighting Company (list 1) (
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cc:
Stephen B. Latham, Esq. Gerald C. Crotty, Esq.
John F. Shea, III, Esq. Ben Wiles, Esq.
Twomey, Latham & Shea Counsel to the Governor Attorneys at Law Executive Chamber Post Office Box 398 State Capitol -
33 West Second Street Albany, New York 12224 a Riverhead, New York 11901 Herbert H. Brown, Esq.
) 1 Alan S. Rosenthal, Esq., Chairman Lawrence Coe Lanpher, Esq.
Atomic Safety & Licensing Appeal Board Karla J. Letsche, Esq.
U.S. Nuclear Regulatory Commission 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. .
I Hunton & Williams Dr. Monroe Schneider 707 East Main Street North Shore Committee Post Office Box 1535 Post Office Box 231 Richmond, Virginia 23212 Wading River, New York 11792 Howard A. Wilber Fabian G. Palomino, Esq. i Atomic Safety & Licensing Appeal Board Special Counsel to the Governor U.S. Nuclear Regulatory Commission Executive Chamber - State Capitol Washington, D.C. 20555 Albany, New York 17224 l
Atomic Safety & Licensing Board Panel Anthony F. Earley, Jr. , Esq.
U.S. Nuclear Regulatory Commission General Counsel Washington, D.C. 20555 Long Island Lighting Company 175 East Old County Read ;
Atomic Safety & Licensing Appeal Board Hicksville, New York 11801 i Panel U.S. Nuclear Regulatory Commission Mr. Lawrence Britt Washington, D.C. 20555 Shoreham Nuclear Power Station Post Office Box 618 Gary J. Edles, Esq. Wading River, New York 11792 Atomic Safety & Licensing Appeal Board U.S. Nuclear Regulatory Commission 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 11778 New York State Department of Public Service Regional Administrator, Region I Three Empire State Plaza U.S. Nuclear Regulatory Commission Albany, New York 12223 631 Park Avenue ,
King of Prussia, Pennsylvania 19406
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Long Island Lighting Company Shoreham(1) cc:
Robert 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 Department of Law 475 East Main Street State of New York Patchogue, New York. 11772 Two World Trade Center Room 46-14 New. York, New York 10047
, Mr. William Steiger Plant Manager Shoreham Nuclear Power Station Post Office Box 628 l Wading River, New York 11792 MHB Technical Associates 1723 Hamilton Avenue - Suite K San Jose, California 95125 Honorable Peter Cohalan l Suffolk County Executive l County Executive / Legislative Building Veteran's Memorial Highway l Hauppauge, New York 11788 i
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Mr. Jay Dunkleberger !
New York State Energy Of# ice '
Agency Building 2 Empire State Plaza Albany, New York 12223 ,
4 Ms. Nora Bredes !
! Shoreham Oppnnents Coalition 4 l
195 East Main Street i Smithtown, New York 11787 1 Chris Nolin New York State Assembly Energy Connittee 626 Legislative'0ffice Building l
Albany New York 12248 l Peter S. Everett, Esq.
l Hunton & Williams l 2000 Pennsylvania Avenue, NW ,
Washington, D.C. 20036 4
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, a How will the activation of filtered venting be considered in conjunction with the unfiltered venting procedure in the E0P (18).
Analyses to quantify the reduction of public risk (24).
Analyses on the releases from the SCS in new accident sequences where the f containment is recoverable (25, 26, 41-43, 50).
Response of the SCS to a short duration pressure pulse in the containment !
(38). i Analyses of accident sequences which could lead to pump cavitation and core damage because of the pressure relief, although the containment integrity is maintained (44, 52-54).
Concerns about the potential of the containment approaching a negative pressure in the ; vent that the containment spray is activated (81-83).
1 LILCo intends to review the transcript and respond to the staff's concerns which are not limited to those highlighted above. LILCo would wish to obtain the resolution of the safety concerns and staff guidance on design re prior to committing major design and construction contracts (104)quirements
. The i
schedule for project completion is 36 months following the award of the design -
contract. 1 1
/s/
Ronnie Lo, Project Manager i Project Directorate PDI-2 '
Division of Reactor Projects I/II j
Enclosure:
As stated cc w/o enclosure:
See next page l
! DISTRIBUTION tFocket; File w/ enclosure j svarga w/o enclosure PDI-2 Rdg.~w/ enclosure" BBoger w/o enclosure NRC PDR/LPDR w/ enclosure RLo/GRivenbark w/ enclosure WButler w/o enclosure (NRC Attendees) w/o enclosure )
PDI-2/P. PDI-2/D RLo:ca >7 WButler i 1 /27/87 q/g87 J