ML20069F779
| ML20069F779 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/14/1983 |
| From: | Downey T HOUSE OF REP. |
| To: | Palladino N NRC COMMISSION (OCM) |
| Shared Package | |
| ML20069F748 | List: |
| References | |
| REF-GTECI-A-17, REF-GTECI-SY, TASK-A-17, TASK-OR NUDOCS 8303240077 | |
| Download: ML20069F779 (3) | |
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ElasMitgtoit,D.C. 20515 February 14, 1983 9
Honorable Nunzio Palladino
. Chai nnan The Nuclear Regulatory Commission 1717 H Street, NW Washington, D.C. '20555
Dear Mr. - Chairman:
I am deeply concerned over the latest revelations, provided by a top NRC
' official, about the safety of the Shoreham Nuclear Power Plant.
My purpose in writing is to request more information about the new position of Mr. James Conran so that I might assess more clearly this recent safety-related issue.
As I understand the concerns raised by Mr. Conran, they center on systems integration and the identification of safety related components.
Mr. Conran now believes that the plant should not be allowed to operate until possible~ adverse systems interactions have been identified and corrected.-
Indeed, he said that "LILC0 truly does not understand what is required minimally for safety."
I am alarmed after reading Mr. Conran's submission that a plant could be 95 percent complete while this type of basic analysis remains incomplete.
I read in the 1981 NRC Annual Report (the latest report submitted to Congress) that Tas,< Number A-17 of unresolved safety issues is " systems interactions."
I also noted that in 1978, NRC had scheduled that a Phase I report would be issued by September,1979, and that a Phase II report would be issued in September,1980.
To date, NRC has issued neither, nor does it have plans to issue these staff reports.on unresolved safety issues. What technical basis then does the NRC or LILC0 suggest supports an operating license without a detailed systems interaction study being done?
l Additionally, I would like to have the following information as soon as possible:
1.
a definition of systems interaction l
i 2.
several examples of the type of systems interaction Mr.
Conran, the NRC or LILC0 think could have adverse effects on Shoreham along with detailed listings of the consequences and probabilities associated with these interactions f
- 8303240077 830316 i
PDR COHHS NRCC CORRESPONDENCE PDR
s._
Chairman Nunzio Palladino.
Page 2:
- 3. : a copy of the NRC task ' action plan for the. resolution of the. systems
' interaction unresolved safety issue (A-17)
.4.
a complete history. of the original schedule of the resolution of A-17 all delays and the budget 'and person-years assigned to this issue -
since its identification'i,n-1978 l
5.
if A-17 has been delayed or the resolution schedulefextended as
_Mr. Conran alleges, when was this decision gade, by'whom, and:
- for what reasons-Again, my interest is.in finding the ~ answers Long Islanders need to more
. clearly. understand what the existence of Shoreham Nuclear Power Plant in Ltheir community means.
I' hope-you will facilitate my representation of.their.
concern by answering _these questions as fully.and as expeditiously as possible.
,j Sincerely,
/
7 THOMAS J. DCWNEY Member of Cc ngress
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Enclosure:
Table 3.
Schedule for Resolution of Current Unresc1ved Safety Issues, The 1981 Annual Report of the U.S. Nuclear Regulatory Commission.
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Table 3. Schedule for Resolution of Current Unresolved Safety ISSUES Schedule for Schedule for Issuing Staff issuing Staff Schedule for f
Report "For Report "For Issuing Final l
Comment" in Comment" Staff Report i.
Task 1978 NRC asof asof No.
Unresolved Sqfety Issue Annual Report Nov.16,19813 Nov.16,1981' r
I A.1 Water Hammer Dec.1980 Aug.1982 Jari.1983 A-3 PWR Steam Generator Ebe Integrity Early 1980 Nov.1981 Mar.1982 A-4 PWR Steam Generator Ebe Integrity Early 1980 Nov.1981 Mar.1982 A.5 PWR Steam Generator Ebe Integrity Early 1980 Nov.1981 Mar.1982 A-Il Reactor Vessel Material Toughness July 1979 Complete Sept.
Jan.1982 1981 A.12 Steam Generator and Reactor Vessel Aug.1979 Complete Nov.
Jan.1982 Supports 1979 A.17 Systems Interactions Phase 1 - Sept.
1979 Phase 11 - Sept.
1980 A-39 SRV Pool Dynamic Loads' Oct.1979 Jan.1982
~
A-40 Seisinic Design Criteria Phase 1 - 1979 Oct.1981 Jan.1982 a
Phase 11 - 1981 A-43 Containment Emergency Sump Not Scheduled June 1982 Nov.1982 A-44 Station Blackout Not Scheduled Oct.1982 March 1983 A-45 Shutdown Decay Heat Removal Require.
Not Scheduled Oct.1985 ments A-46 Seismic Qualification of Equipment in Not Scheduled Dec.1983 Operating Plants A.47 Safety Implications of Control Systems Not Scheduled A-48 Hydrogen Control Measures and Effects Not Scheduled of Hydrogen Burns 8SRV denotes Safety Relief Valve 2See " Unresolved Safety Issues Summary: Aqua Book" (NUREG-0606, Vol. 3 No. 4, Nov.16,1981).
comment" for Task A.ll, " Reactor Vessel Materials Table 3. Important elemeats in the implementation of Toughness." The "for comment" reports describe the these tasks are: (1) the provision of a public ccmment technical studies conducted by the NRC staff or its period following the issuance of the staff's technical contractors and the safety conclusions that constitute resolution, followed by discussion and disposition of the NRC staff's resolution of each of the issues. Pub-the comments received in a final report; (2) provision lic and industry comment is solicited and considered for the incorporation of the technical resolution into on each, and the final report includes a summary the NRC's Regulations, Standard Review Plan, Regu-and assessment of all of the comments received.
latory Guides or other official guidancel and (3) pro-The present schedule for the completion of work vision for application of the final technical resolution on each of the Unresolved Safety issues is given in to operating plants.
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