ML20094N741
| ML20094N741 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/09/1984 |
| From: | De Vincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19277H799 | List: |
| References | |
| GL-84-04, GL-84-4, SBN-703, NUDOCS 8408160371 | |
| Download: ML20094N741 (2) | |
Text
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b sua swa IPUBLIC SERVICE Engineedng ONice:
Compartyof New Hampshire 1671 Worcester Road Framingham, Massachusetts 01701 (6171 - 872 - 8100 August 9, 1984 S BN-703 T.F.
B7.1.2 i
United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos.
50-443 and 50-444 (b) Generic Letter 84-04, from Darrel G. Eisenhut to PWR Licensees, Construction Permit Holders and Applicants for Construction Permits, dated February 1, 1984
Subject:
Alternate Pipe Break Design Criteria
Dear Sir:
The Public Service Company of New Hampshire (PSNH) has been fo]Ioving the recent Nuclear Regulatury Commission actions and nuclear industry developmente as they pertain to alternate pipe break d.esign criteria.
In Reference (b),
the Staff has expressed their intention to revise existing criteria regarding postulated pipe breaks in the Reactor Coolant Loope of Westinghouse-supplied Nuclear Steam Supply Syatens.
The application of this mechanistic fracture anelysie technology to eliminate postulated double-ende'! ruptures in the Leactor Ccelent Loop piping of Seabrook Station Units 1 and 2 ia requested Ferein. In support of thfs reqacst, a plant-specific mechanistic fracture analysis developed for PSNH by Westinghouse is includea as Enclosure I to this letter. This report has been prepared in accordance with the NRC guidance delineated in Generic Letter 84-04 contain; information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld f rom public disclosure by the Commission and mer addresses with specificity the considerations listed in paragraph (b)(4) of o8$
Section 2.790 of the Commission's regulations. Accordiegly, it is respectfully requested that the information which is proprietary to eo Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations. Correspondence with respect to pg the proprietary aspects of the Application for Withholding or the supporting FDu Westinghouse affidavit should reference CAW-84-54 and should be addressed to SO R. A. Wiesemann, Manager, Regulatory and Legislative Af fairs, Westinghouse g4 Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.
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United States Nuclear $ Regulatory Commission August 9 1984 Attention:
Mr.- George Knighton, Chief Page 2 By way of this letter, PSNH. requests that the NRC approve the elimination of postulated breaks in 'the Reactor Coolant Loop piping ~ of Seabrook Station Units 1 and 2. 'The technical basis for this request is provided in Enclosure 1;.(WCAP-10567
" Technical Basis for Eliminating Large Primary Loop Pipe Rupture as the L tructural Design Basis for Seabrook Station Units 1 and 2").
S This report demonstrates.that the generic mechanistic fracture analysis
. performed by Westinghouse in WCAP-9558, Revision 2.(" Mechanistic Fracture Evaluation of Reactor Coolant Pipe Containing a' Postulated Circumferential Through Wall Break") envelopes the site-specific parameters of the Seabrook Units. Generic Letter. 84-04 documents the Staff's acceptance of WCAP-9558.
NRC' acceptance of our request for elimination of Reactor Coolant Loop pipe breaks would result in significant benefits in terms of reduced occupational radiation exposure and cost savings over the life of the units.
Quantification of the exposure reduction and cost savings by other ~ applicants (e.g., Duke Power) supports our significant savings premise..PSNH is presently quantifying these and other potential benefits and will forward this information when completed.
In summary, justification for our request to eliminate Reactor Coolant Loop pipe breaks and their associated consequences from any further consideration is founded on:
i 1.
Technically sound, NRC-accepted bases.
2.
A Reactor Coolant System pressure boundary leak Detection System which meets the. requirements of Regulatory Guide 1.45 (see Enclosure 1).
3.
Expected significant reductions in occupational radiation erposure and cost savings over the life of tLe units.
Pursucnt to the guidance delinaated in Generic Letter 84-04, PSNH hereby l
formally requests a partial exemption for Seabrook Station Units 1 and 2. f rom General Design Criteria 4 (CDC-4) of 10CFR50 Appendix A.
CDC-4 establishes requirements for protection of structures, systems, and components against the dynaalc effceta arsociated with postulated breaks in Reactor Coolant Loop l
piping.
These dynamic effects are specifically defined as the effects of missiles, pipe whipping, and fluid jets.
The granting of this exemption will not obviate the effects of Reactor Coolant Loop pipe breaks from consideration 3
. as a design basis for our Environmental Qualification Program and Engineered Safety Features. design.
I The Staff's expeditious review of WCAP-10567 (Enclosure 1) and acceptance of our request for partial exemption to GDC-4, would afford us the opportunity to fully realize-the benefits on Unit 1.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY J. DeVincentis Director of Engineering and Licensing Attachment cc:. Atomic Safety and Licensing Board Service List
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