ML19256A524
| ML19256A524 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/21/1978 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901080334 | |
| Download: ML19256A524 (11) | |
Text
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 s;
s DEC 2 1 1978 Docket No:
50-322 APPLICANT:
Long Island Lighting Company (LILCO)
FACILITY:
Shoreham Nuclear Power Station
SUBJECT:
SUMMARY
OF MEETINGS HELD ON DECEMBER 14, 1978 Meetings were held in Bethesda, Maryland with representatives of L.ILC0 and Stone & Webster.
The purpose of the morning meeting was to discuss the status of the unresolved issues in the Shoreham review.
A list of attendees is shown in Enclosure 1.
The purpose of the afternoon meeting was to discuss the Shoreham design for containment isolation and leakage testing.
The list of attendees for this meeting is shown in Enclosure 2.
As a result of an internal management meeting, the Shoreham open issues were placed into four categories.
The listing of issues in these categories is provided'in Enclosure 3.
The status of each of these issues was discussed with the applicant.
For some of these issues the applicant stated that additional information would be submitted.
We told the applicant that we will prepare a Preliminary Safety Evaluation Report that would summarize our evaluation of the majority of the Shoreham application.
We will also identify those portions of our review which have not been completed.
This report will be submitted for NRC management review on February 7, 1979 and is tentatively scheduled for publication on February 21, 1979.
We also told the applicant that we will send the Caseload Forecast Panel to Shoreham to evaluate the status of construction.
During the afternoon meeting, the applicant discussed each of the containment isolation valves that were identified by the staff as potential problem areas.
They presented their proposed methods of leakage testing for these valves.
As a result of this meeting, LILCO will prepare a submittal 790108033
. DEC 2119M providing additional information on each of the valves identified by the staff.
In addition to the discussion on leakage testing, we also had more detailed discussion on some of the open issues identified in the morning meeting.
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jJd 'ry N. ' lson, Project Manager
/ Light Water Reactors Branch No. 4
.<_ Division of Project Management
Enclosures:
- 1. Attendance List
- 2. Attendance List
- 3. Outstanding Issues
Long Island Lighting Company DEC 211973 ccs:
Edward M. Barrett, Esq.
General Counsel Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Edward J. Naish, Esq.
General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 J. P. Novarro Project Manager Shoreham Nuclear Power Station P. O. Box 618 Wading River, New York 11792 Jeffrey Cohen, Esq.
Deputy Commissioner and Counsel New York State Energy Office Agency Building 2 Empire State Pla::a Albany, New York 12223 Howard L. Blau Blau and Cohn, P. C.
380 North Broadway Jericho, New York 11753 Irving Like, Esq.
Reilly, Like and Schnieder 200 West Main Street Babylong, New York 11702 Mr. Andrew W. Wofford Vice President Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801
DEC 211978 ENCLOSURE 1 ATTENDANCE LIST J. Wilson NRC W. Museler LILCO A. Wofford LILCO G. Dawe SSW B. McCaffrey LILCO D. Robare GE C. Grochmal SWEC C. Gilbert SWEC D. Vassallo NRC R. Boyd NRC R. Mattson NRC R. Tedesco NRC S. Varga NPC R. Bosnak NRC F. Schroeder NRC V. Benaroya NRC 4
ENCLOSURE 2 DEC 21 '379 ATTENDANCE LIST J. Wilson NPC C. Gilbert SWEC D. Robare GE W. Mills NRC B. McCaffrey LILCO J. Notaro LILCO G. Dawe S6W J. Calvo NRC R. Scholl NRC S. Brown NRC T. Su NRC J. Shapaker NRC
ENCLOSURE 3 DEC 211978 1.7 Outstanding Issues We have identified certain outstanding issues in our review which have not been resolved with the applicant. We will complete our review of these items prior to issuance of an operating license.
We will discuss the resolution of each of these items in a supplement to this report. These items are listed below and are discussed further in the sections of this report as indicated.
1.
Design Basis Flood - (2.4.5)
(3.4) 2.
Internally Generated Missiles - (3.5.2) 3.
Pipe Break Analyses - (3.6) 4.
Mark II Containment Closure Report - (3.8.1) (3.8.2)
(6.2.1.4)
(6.2.1.7) (6.2.2) 5.
Seismic Qualification Review - (3.9.1.2)
(3.9.2.2)
(3.10)
(5.2.1) (7.5) 6.
LOCA Loadings - (3.9.1.4)
(5.2.1)
(6.2.1.5) 7 MSIV Control System - (3.11) 8.
Topical Report NEDM-10672 - (3.11) 9.
CRD System Return Line Reroute - (4.6) (5.2.10)
- 10. Feedwater Nozzle - (5.2.1)
- 11. Target Rock Safety / Relief Valves - (5.2.4) (6.3.1)
- 12. Leakage Detection for RCPB - (5.2.7) 13.
Reactor Core Isolation Cooling System - (5.4.1) (7.4.1)
- 14. Steam Bypass - (6.2.1.6) (7.3.6)
- 15. TLTA Tests - (6.3)
- 16. MSIV Leakage Control System - (6.6) (15.3.3)
. 17.
Instrumentation Systems Required for Safety - (7.6.1) (7.6.4)
(7.6.5) (7.7) (15.1)
- 18. Leakage Detection System - (7.6.2)
- 19. Non-Safety Grade Equipment - (7.6.11)
(15.1 )
- 20. Fire Protection - (9.5.1) 21. Emergency Planning - (13.3) 22.
Industrial Security - (13.7) 1.8 Confirnatory Issues We have identified certain issues in our review which have been resolved with the applicant. However, as a conditiun of our acceptance, we need to verify that the applicant has implemented the resolution in his design. These items are listed below and are discussed further in the sections of this report as indicated.
1.
Pipe Support Base Plates - (3.9.2.1) (5.2.1) 2.
Environmental Qualification of Electrical Equipment - (3.11)
(8.4.3)
(8.4.8) 3.
MCPR - (4.4) 4.
Target Rock Safety / Relief Valves - (5.2.4) (6.3.1) 5.
Inservice Inspection Program - (5.2.6) 6.
Appendix G - (5.3.1) 7.
Appendix H - (5.3.1) 8.
Containment Isolation and Leakage Testing - (6.2.4) (6.2.6)
(6.3.1)
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. 9.
Passive Failures - Post LOCA - (6.3.1)
- 10. Manual ADS - (6.3.2)
- 11. MSIV Leakage Control System (7.6.8) (8.4.7)
- 12. LPCI - (7.3.1)
- 13. Hydrogen Recombiner - (7.3.7)
- 14. Startrek System - (7.6.6)
- 15. Motor Space Heater - (7.6.6)
- 16. Diesel Generator Test (8.3.1)
- 17. Reactor Containment Electrical Penetrations - (8.4.3)
- 18. RPS Response Time Tests - (14.0) 1.S License Conditions 1.
GEXL Correlation - (4.4) 2.
Loose Parts Monitoring System - (4.4) 3.
Residual Heat Removal System - (5.4.2) (6.3.1) (7.4.2) 4.
Reactor Trip System Power Supply - (7.2.5)
16.0 TECHNICAL SPECIFICATIONS The technical specifications in a license define certain features, characteristics, and conditions governing operation of a facility that cannot be changed without prior approval of the Commission. The finally approved technical specifications will be made a part of the operating license.
Included will be sections covering safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls.
At the time of submittal of the Final Safety Analysis Report, the applicant had proposed to use standard specifications. Shortly thereafter, we informed the applicant ^ that we intended to use the standard technical specifications for General Electric boiling water reactors as the basis for development of the final technical specifica-tions for Shoreham.
The standard technical specifications for General Electric Company plants which will serve as the basis for the technical specifications for Shoreham have been updated as a result of their application to technical specifications for other plants and also as a result of continued discussion with the General Electric Company and applicants with General Electric Company reactors.
The staff is currently working with the applicant to finalize the technical specifications for Shoreham. On the basis of our review to date, we conclude that normal plant operation within the limits of the technical specifications will not result in potential offsite exposures in excess of the 10 CFR Part 20 limits. Furthermore, 4
the limiting conditions for operation and surveillance requirements will assure that necessary engineered safety features will be available in the event of malfunctions within the plant.
During our review of the Shoreham application, we identified certain issues which must be included in the technical specifications as a condition of our acceptance. These issues are listed below and are discussed further in the sections of this report as indicated.
1.
Sediment monitoring in intake canal (2.4.8) 2.
Jetty Monitoring in intake canal (2.4.8) 3.
Emergency procedures for sealing waterproof doors (2.4.10) 4.
Canal Slopes (2.5.5) 5.
Fuel Burnup uimit (4.2) 6.
Crud deposition (4.4) 7.
Loose Parts Monitoring System (4.4) 8.
Control Rod Drive Pump Trip (4.6) 9.
Leakage through RCPB - (5.2.7)
- 10. MSIV Leakage Control System - (6.6)
- 11. Spent fuel cask crane (9.1.4)
- 12. Single recirculation loop operation (15.1)
- 13. Steam line break (15.3.1) e a
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MEETING SU 4fARY DISTRIBIRICN DEC 211978 Docket File w e pnq h$
NRR Reading LWR #4 File E. Case R. Boyd D. Vassallo W. Gamill J. Stol::
R. Baer
- 0. Parr S. Varga C.leltemes L. Crocker D. Cmtchfield F. Williams R. Mattson R. DeYoung Project Manager: J. Wilson Attorney, ELD M. Service IE (3)
ACRS (16)
L. Dreher L. Rubenstein R. Denise
Participants:
W. Mills J. Calvo R. Scholl S. Brown T. Su J. Shapaker V. Benaroya F. Schroeder R. Bosnak R. Tedesco R. Mattson
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