ML20101F760

Informs of Intended Issuance of Amend 9 to FSAR by 850215. Table of FSAR Commitments for Oct & Nov 1984 & Corresponding Resolutions Encl.Response to Commitment to Be Included in FSAR Amend 9 Encl

ML20101F760
Person / Time
Site:	Hope Creek
Issue date:	12/17/1984
From:	Mittl R Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8412270292
Download: ML20101F760 (9)

Text

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9 Puthc Serece O PS G Company Electnc and Gas 80 Park Plaza, Newark, NJ 07101/ 201430 8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation December 17, 1984 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 FSAR COMMITMENT STATUS THROUGH NOVEMBER 1984 Public Service Electric and Gas Company plans to issuo Amendment No. 9 to the Hope Creek Generating Station Final Safety Analysis Report by February 15, 1985. This Jetter is provided to document the status of Hope Creek Generating Station responses to NRC requests for additional information which were forecasted to be responded to by October and November 1984.

Attachment I is a tabulation of the Hope Creek Generating Station Final Safety Analysis Report commitments for October and November 1984, and the corresponding resolution for each commitment. Attachment II provides response to a commitment forecasted to be responded to in October 1984, which will be included in Amendment No. 9.

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B412270292 841217 PDR ADOCK 05000354 A pyg ilfl The Energy People m m sw m m

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. I e-s' Director of Nuclear Reactor Regulation 2 12/17/84 1

Should you'have'any questions in-this regard, please contact e us.

Very truly yours, l4 1

Attachment I - Hope Creek Generating Station PSAR Commitment Status through November 1984 Attachment II. - Response to Question 210.12 C D. H. Wagner (w/ attach)

USNRC Licensing Project Manager W. H. Bateman (w/ attach)

USNRC Senior Resident Inspector MP84 123/06 1/2

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' ATTACHMENT'I-Page 1 of 2;

, . HOPE-CREEK 1 GENERATING STATION'

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. FSARiCOMMITMENT/ STATUS THROUGH' NOVEMBER:1984

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PSAR1 COMMITMENT LOCATION COMMITMENT' RESOLUTION '

, , II. FSAR Section16.2.3.2.3- This' commitment concerns-providing . the results of the feedwater bypass leakage analysis. 1This information

, will be provided in January

'1985.

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2.. FSAR Table 13~.1-la This. commitment concerns providing resumes for seve ral' Nuclea r. D,epartment

management Tand technical .

services and support person-nel. This information will be ^ provided - by - Februa ry 1985.' -

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3. Ouestion/ Response This commitment concerns Appendix - providing applicability of 7 JOuestion 210.12 additional. requirements.in Reg. Guide 1.84, -with . regard to Code Case 1711 (N-100), ,

to 12 remaining safety-related safety-relief valves. .This information ' is

.provided in' Amendment 8 to

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the HCGS FS AR .

-f 14 . Ouestion/ Response .This commitment concerns LAppendix:

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providing applicability of OuestionJ210.12 the _ electrode dispersal requirements of Code Case

- 1644. This information is.

provided'in A*tachment II and will be included in Amendment 9 to the HCGS FSAR.

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.Ouestion/ Response This commitment concerns

-Appendix: . f providing results of .the Ouestion 210.20' stress analysis for the feedwater swing check valve. This information will be provided in ' January b' 1985.

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Page 2'of 2

[ FSAR COMMITMENT LOCATION COMMITMENT RESOLUTION I 6. _0uestion/ Response This commitment concerns F Appendix:: providing preventive mainte-Question 410.87. nance procedures for Mois -

ture Separator, Emergency

. Instrument Air Compressor and Instrument Air Filter changeout.- This information will be provided in June 1985.

7. DSER Open Item No. 262 This commitment concerns providing Radiological i Effluent Technical Specifi-cations (RETS). This infor-mation will be provided in December 1984.

' STATUS OF SEPTEMBER 1984 FSAR COMMITMENTS MADE IN FSAR COMMITMENT STATUS LETTER TO NRC (

REFERENCE:

R. L. MITTL (PSE&G)-TO A.1SCHWENCER, DATED OCTOBER 29, 1984,

[ . ATTACHMENT.I)

! 8. NRC Generic Letter 83-28 This commitment concerns L Response: providing station operating L

(PSE&G to NRC, 3/30/84) procedures referenced in the

! response to NRC Generic Letter 83-28 of 3/30/84.

This information will be provided ' in December 1984.

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j 9. Question / Response Re: TMI Item:I.A.3.1: This Appendix: commitment. concerns having Ouestion 100.6 the HCGS simulator opera-tional.for training. The Hope Creek simulator is scheduled to be operational for training in January 1985.

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M P84 164/15 2-cag u-

6 ATTACHMENT II

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.'.- - WA 10 N O P. 6 9 3 4 4 BCGS FSAR 8/84 i

QUESTION 210.12 (SECTION 5.2)

Table 5.2-2 identifies certain ASME Code Cases that have been used in the construction of components for the Hope Creek Generating Station. A number of theme Code Cases are identified in Regulatory Guides 1.84 and 1.85 as conditionally acceptable.

That is, Regulatory Position C.1 of each guide identifies additional conditions that should be imposed in addition to those conditions specified in each Code Case. The Code Cases that are identified in Regulatory Guide 1.84 as conditionally acceptable are: 1636/1636-1, 1711, 1734, 1818, N'192, and N-275. The Code Cases that are identified in Regulatory Guide 1.85 as conditionally acceptable are: 1644/1644-3, 4, 6, N-71-9, and N-249. Code Case N-253-1 which is not in the Regulatory Guides is also conditionally acceptable.

Demonstrate that you are in compliance with the additional conditions applicable to each of the above conditionally approved Code Cases that are identified in Regulatory Guides 1.84 and 1.85.

RESPONSE

Code Case 1636-1 (N-70) was invoked in the design of the safety auxiliaries cooling system (SACS) pumps. Regulatory Guide 1.84 states that the design guidance in this code case is acceptable subject to the restriction that the stress limit designations of

" Upset," " Emergency," and " Faulted" should be established and justified in the design specification.

HCGS complies with this additional regulatory requirement. The i

loading combinations are specified in the design specification.

Code case 1711 (N-100) was invoked in the design of a number of safety-related safety-relief valves. Regulatory Guide 1.84 states the design guidance in this code case is acceptable subject to the requirement that the FSAR demonstrate how the pressure relief function is assured if the stress limits utilized for the upset operating condition are in excess of those specified in the code case.

All of the safety-relief valves at HCGS that use Code Case 1711 (N-100), with the exception of the 10 valves found on the primary containment instrument gas compressor skids and theWe 2 on have the instrument gas receiver tanks have been reviewed.

determined that all the valves were specified as active. This designation requires that the stress limits for the. faulted Thus, the condition meet normal loading condition allowables.

additional requirements in Regulatory Guide 1.84 are not applicable.

210.12-1 Amendment 7

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HCGS FSAR 8/34 f C '

We are still evaluating the applicability of the additional A revised response will 3"

requirements to the 12 remaining valves.

be provided in October 1984.

Code Cases 1734 and 1818 were invoked in the fabrication of ~

certain pipe supports. Regulatory Guide 1.84 states that the design guidance in these code cases is acceptable subject to the additional welding restrictio..s found in the regulatory guide.

NCGS complies with these additional regulatory requirements. The applicable design specifications permit the use of Code Case 1734 and/or ISIS subject to the limitations recommended by Regulatory i Guide 1.84. l

Code flexibleCase metal N-192 instrumentwas invoked in the fabrication hose assemblies and on ofcertain certainstandby

! Regulatory diesel generator skid-to-facility connectors.

Guide 1.84 states that this code case is acceptable subject to i

the requirement that ,the applicant should provide design data to l

demonstrate compliance with Paragraph NC/ND-3649.

l Information to comply with thins additional regulatory This requirement ~

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e _ci!! M provided 2 2:17 10"^"under separate cover. 4

. pear. h st A; A f^dm-information is considered to be propriety. @Cuc w 34 m Code Case N-275 was invoked in the fabrication safety- y o)f cor related pipe. Regulatory Guide 1.84 states that the design guidance in this code case is acceptable subject to the additional welding restrictions in the regulatory guide.

HCGS complies with these additional regulatory requirements. The fiCGS piping design specification permits the use of Code Case N-275 cubject to the limitations recommended by Regulatory Guide 1.84.

Code Case 1644 and its various revisions has been invoked in numerous applications. Regulatory Guide 1.85 states that'this code case is acceptable subject to the limitations on maximum ultimate tensile strength and, in the case of Code Case 1644-9 (N-71-9), the additional requirements for electrode dispersal.

Most of the BCGS specifications, which invoke Code Case 1644 (N-71), invoke a specific revision of the Code Case, and direct the vendor to comply with the additional regulatory requirements.

For those specifications that did not identify a specific j revision and direct conformance with the additional regulatory -

requirements, a review has been performed.to confirm that the terials is below 170 kai.

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v 1 10 8a 0 ?. 6 9 3 4 4 SCGS FSAR 3/34 Use of Code Case 1644-9 (N-71-9) is subject to the additional precautions cited in Regulatory Guide 1.85.

Use of Code Case N-249 is permitted for the containment hydrogen recombiner technical specification. To date, this code case has not been invoked.

Code Case N-253-1 provides rules for the construction This of ASME code components which experience elevated temperatures.

case was invoked in the design of the containment hydrogen recombiners. This code case was invoked on HCGS because there are portions of the containment hydrogen recombine; s that operate at temperatures in excess of 800*F.

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210.12-3 A endment 7

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