ML20073M279

Informs That Section 3.8.4.8 of FSAR Was Not Included in 830301 Submittal.Fsar Section & Revised FSAR Table 1.11-1, Page 4 Encl.Info Will Be Incorporated in FSAR Amend

ML20073M279
Person / Time
Site:	Hope Creek
Issue date:	04/15/1983
From:	Mittl R Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8304210463
Download: ML20073M279 (6)

Text

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a Pubhc Servica Electric and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430-7000 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 April 15, .19 83 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue-Bethesda, Maryland 20014 i

Attn: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:

HOPE CREEK. GENERATING STATION DOCKET NO. 50-354 FSAR SUBMITTAL This letter is to infonn you that Section 3.8.4.8 of Hope Creek Generating Station Final Safety Analysis Report was not included in the document as submitted to the Nuclear Regulatory Commission on March 1, 1983. Section 3.8.4.8 presents the justification for the deviations from Standard Review Plan Section 3.8.4 identified in Final Safe ty Analysis Report Table 1.11-1.

In addition, please note that additional deviations from Standard Review Plan Sections 3.8.2 and 3.8.3 have been identified, concerning the preparation of structural design reports for category I structures, and canpliance to ACI 349 for interior containment structures, respectively.

We arc . forwarding at this time, for your information and use, copies of the text for Hope Creek Generating Station Final Safety Analysis Report Section 3.8.4.8, additional Final Safety Analysis Report Standard Review Plan Rule Re-view Section 3.8.2.8.3, and revised Final Safety Analysis Report Table 1.11-1 page 4 of 25. This information will be formally incorporated into the Hope Creek Generating Station 1 Final Safety Analysis Report as part of the firs t C)C2[

amendment.

8304210463 830415 PDR ADOCK 05000354 A PDR The Energy People

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a Director-of Nuclear 4/15/83 Reactor' Regulation should ~you have any questions regarding this transmittal, do not hesitate to contact .us.

-Very truly yours,

.l M

R. L. Mittl General Manager -

Nuclear Assurance and Regulation DJD:li

-Attachment CC: D. H.-Wagner USNRC Licensing Project Manager EH2

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-3.8.'4.8 SRP Rule Review Acceptance criteria II.2 of SRP Section 3.8.3 and 3.8.4-requires Category I structures be- designed in accordance with Specification ACI. 349 as augmented by Regulatory Guide 1.'142. The Hope Creek Generating Station design was based on the requirements of Specification ACI --318-71.

The Category I structures concrete design for Hope Creek Generating Station began prior to the issue' of Specification ACI.349 (1976). As a result, all concrete design is based on using Specification ACI 318-71 with the following clarification:

The load combinations used are in conformance with ' ACI 349 except that . the 0.9 - load f actor on dead load as required by Regulatory Guide 1.142 was not used.

Based on parametric analyses, an adequate design margin exists to compensate for the ef fects of not using the reduced dead load factor.

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13 . 8 . 2 . 8 . 3 SRP Rule Review Acceptance criteria II.4f of SIT Section 3.8.2 and the relevant acceptance criteria of SRP Sections 3.8.3, 3.8.4 and 3.8.5 require that 1a design report be prepared and is considered acceptable if it contains the information specified in - Appendix C of SRP Section 3.8.4. .

Suf ficient. information is provided in the HCGS FSAR to outline the structural design of the Seismic Category I structures. This information includes such items as structural description and geometry, load combinations, materials used , applicable codes and standards, and camputer codes, as required by Regulatory Guide 1.70, Revision 3. As

required by 10CFR50 Appendix-B, information is also avail-able to enable an audit of these Seismic Category I struc-tures to inspect and verify their structural in teg r i ty . The information available for such an audit is consistent with the information requested in Appendix C to S RP ' 3 . . 8 4 .

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w HCGS FSAR TAKE 1.11-1 (Cont. ) Page 4 of:25 l

Section Acceptance Criteria Differences Discussed .

3.7.3 II.2.b 3.7.3.16 (Rev. 1)

Five cperating basis earthquakes (OBEs),. For NSSS couponents and equipment, 10 with a minimun of 10 cycles each, should equivalent peak OBE cycles are used.

be assumed during the plant life.

3.8.2 II.4.d (Rev. 1)

An analysis is to be performed to On Hcpe Creek this analysis has not 3.8.2.8 determine the ultimate pressure been performed.

retainirg capacity of the primary steel containment.

II.4.f Design report is considered acceptable Sufficient information is available in when it satisfies the guidelines of focus other than those outlined in Appendix C to SRP 3.8.4. Appendix C.

II.5 Table 3.8.2 lists allowable stress Allowable stresses used for testirg and limits for steel contairments, post-floodirg conditions are higher-than indicated in SRP Table 3.8.2.

3.8.3 II.2 (Rev. 1)

Interior structures of containment shall Interior structures are designed in 3.8.4.8 be designed in accordance with accordance with specification ACI specification ACI 349 as augmented by 318-71.

Regulatory Guide 1.142.

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HCGS FSAR TAILE 1.11-1 (Cont. ) Paje 4a of 25 Section Acceptance Criteria Differences Discussed ,

II.3.c(ii)(b)

Load factors for steel interior Design is based on Energy Balance 3.8.3.8 structures are specified when plastic methods.

design methods are-used.

II.4.e Design report described in Appendix C to Sufficient infonnation is available in 3.8.2.8 SRP 3.8.4 is reviewed. forms other than those outlined in Appendix C.

, 3.8.4 II.2 (Rev. 1)

Category I structures shall be. designed Category I structures re designed in 3.8.4.8 in accordance with Specification ACI 349 accordance with Specification ACI as augmented by Regulatory Guide 1.142. 318-71.

II.2 Conformance to Regulatory Guides. 1.10, Nonconformance, in part, with 3.8.1 1.55, and 1.94. Regulatory Guides 1.10, 1.55, ard 1.98.

II.4.d Design reports are acceptable if it Sufficient information is available in 3.8.2.8 contains the information specified in forns other than those outlined in Apperdix C. Appendix C.

a 3.8.5 II.4.e (Rev. 1) Design report is considered acceptable Sufficient information is available in 3.8.2.8 if it satisfies the guidelines of fonns other than those outlined in

Appendix C to SRP 3.8.4. Appendix C.

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