ML20005A354
| ML20005A354 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/25/1981 |
| From: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-02-03.B1, TASK-2-3.B1, TASK-RR A01452, A1452, NUDOCS 8106300241 | |
| Download: ML20005A354 (4) | |
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General Of fices e Selden Street, Bedin, Connecticut J
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Docket No. 50-245 A01452 cy t_
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Director of Nuclear Reactor Regulation
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Attn 14r. Dennis M. Crutchfield, Chief V-
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Washington, D.C.
20555
References:
(1)
D. G. Eisenhut letter to SEP Plant Licensees, dated January 14, 1981.
(2)
W. G. Counsil letter to D. G. Eisenhut, dated February 27, 1981.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 SEP Topic II-3.G.1, Capability of Operating Plant to Cope with Design Basis Flooding Conditions As part of the redirection of the Systematic Evaluation Program, Reference (1), Northeast Nuclear Energy Company (NNECO) committed to develop Safety Assessment Reports (SAR's) for certain SEP topics which would be submitted for Staff review. NNECO detailed this commitment and provided a schedule for submittal of SAR's in Reference (2).
In accordance with this commit-ment, NMECO hereby provides the Safety Assessment Report for SEP Topic II-3.B.1, Capability of Operating Plant to Cope with Design Basis Flooding conditions, which is included as Attachment 1.
We trust the Staff will appropriately use this information to develop a Safety Evaluation Report for this SEP topic.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY DW W. G. Counsil Senior Vice President 8106300 W 9
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SEP Topic II-3.B.1, Capability of Operating Plant to Cope with Design Basis Flooding Conditions l'
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.I Millstone Nuclear Power Station Unit No. 1 SEP Safety Ascessment Report Topic II-3.B.1; Capability of Operating Plant to Cope With Design Basis Flooding Conditions
1.0 INTRODUCTION
The objective of this topic is to assure that structures, systems, and components required for safe shutdown are adequately protected against floods.
Topic ll-3.B will review the flooding potential and protection requirements. This topic will review against current criteria the capability of the operating plant to cope with these requirements.
2.0 CRITERIA Regulatory Guide 1.59 (Revision 2) states that:
The conditions resulting from the worst site related flood probable at a nuclear power plant; i.e.,
PMF, seismically induced flood, hurricane, seiche, surge, heavy local precipitation, with attendant wind generated wave activity constitute the design basis flood conditions that safety-related structures, systems, and components identified in Regulatory Guide 1.29 must be designed to withstand and retain capability for cold shutdown and maintenance thereof.
3.0 DISCUSSION Topic ll-3.B-1 is a subtopic of Topic ll-3.B.
The discussion contained in the assessment for Topic ll-3.B is also applicable to this review and should be referred to in conjunction with the following.
The plant is provided with flood protection to elevation 19' (MSL).
Various flood gates exterior to the site are included as a part of this protection and are normally kept in the closed position. A procedure exists within the station emergency plans to verify that these gates are properly secured during the onset of a storm. No further action is required to maintain the protection level of 19' (MSL).
3.1 ASSOCIATED SEP TOPICS o_
ll-3.A Hydrologic Description o
ll-3.B Flooding Potential and Protection Requirements o
11-3.C Safety-Related Water Supply (UHS) o 111-3.A Effects of High Water Level on Structures o
Ill-3.C In-service Inspection of Water Control Structures o
XV-1 Technical Specifications
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4.0 CONCLUSION
Based on the above and the conclusions presented in the assessment of Topic II-3.B, NNECO concludes that Millstone Unit 1 has the capability
- to cope with the design basis flooding conditions, therefore assuring that safe shtudown related structures, systems, and components are adequately protected against floods.
5.0 RFFERENCES 1.
Regulatory Guide 1.59, " Design Basis Floods for Nuclear Power Plants" 2.
Standard Review Plan Section 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4.4 Potential Dam Failures (Seismically Induced) 2.4.5 Probable Maximum Surge and Seiche Flooding 2.4.7 Ice Effects 2.4.10 Flooding Protection Requirements 3.
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