ML20128D915
| ML20128D915 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/23/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8505290242 | |
| Download: ML20128D915 (4) | |
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Electnc and Gas Company 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 May 23, 1985 Director of Nu' clear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
REQUEST FOR ADDITIONAL INFORMATION - OUALITY ASSURANCE HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In a letter to Public Service Electric and Gas Company (PSE&G)' dated' March 7, 1985, the NRC staf f requested addi-tional information regarding the quality assurance program to be implemented at Hope Creek during the operations phase.
The information below provides PSE&G's response to this request for additional information.
Item 1 - Information Requested FS AR Amendment 8 (page 1.8-11) added the words underlined below to - PSE&G's commitment to Regulatory Guide 1.26:
"In addition, items designated
'R' in Table 3.2-1 will be included in the OA Program during operation to the extent required by Regulatory Guide 1.143."
Regulatory Guide 1.143, " Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed. in Light-Water-Cooled Nuclear Power Plants," addressed QA for design and construction, but it does not address OA for opera-tions.
Identify what GA measures will be applied to items des ig nated
'R' in Table 3.2-1 during the operations phase of the Hope Creek Generating Station.
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PSE&G Response
-Items designated
'R' are covered by the OA Program during operations.
Section 17.2.2 of the HCGS FSAR states, in part:
a.
"This (0A) program is applied to items and activi-ties that can-affect the health and safety of the public,..."
During the operational phase, this includes...,"
-and-b.
" Safety-related activ ities delineated in Regulatory Guide 1.33 and summarized in Table 17.2-1, Section A and additional NRC requirements contained in Table 17.2-1, Section B."
This section further states:
"The quality assurance program is applied during the operational phase using a graded approach to the extent consistent with the item's or activity's importance to saf ety."
Table 17.2-1, Hope Creek Q Activities / Services states, in part:
The listing below identifies those activities and serv ices, to which the quality assurance program applies during operations:
A.
-Safety-related activities delineated in Regula-tory Guide 1.33, Appendix A (see Regulatory Guide for further breakdown of activities)..."
-and-
"6.
Control of radioactivity (a)
Liquid radioactive waste system (b)
Solid waste system (c)
BWR gaseous effluent system.."
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'5/23/85' i
. Item 2 - Information Requeste'd FSAR Amendment 9 -addresses PSE&G's -QA Program for fire pro-tection~ in several locations:
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a)
Page.,20 of Table 11.1-l, describing differences J
from SRP acceptance criteria, states:
...certain fire-system camponents purchased and installe'dl prior to Julyll,-1978,_such as the fire water storage tanks,. the tank heaters and associ-ated controls, and the valve pit heaters.are' excluded from the ' F ' program."
b)
Section 9.5.1.1.19 on page 9.5.12, discussing the QA program for Bechtel's responsibilities, says the s ame thing. :
c)
Comment 61-added to page 40 of Table 3.2-1, states:
"'F' Program is not retroactive-to camponents purchased and. installed prior to July 1,1978.
Fire water storage tanks, the tank heaters and associated controls, and the_ valve pit unit. heaters are excluded.from the
'F' program."
Clarify that each of'these statements-refer to the
' design and construction phase, and ideptify what GA measures.will be ' applied to these itenis during the.
operations. phase.
PSE&G Response The OA program for fire protection will be applied to the above components during the operations phase.
The last sentence of comment 61, Table 3.2-1, will be revised to read:
" Fire' water storage-tanks, the tank heaters and associ-ated-controls, and the valve pit unit heaters are i
excluded from the
'F' Program during the design ~ and construction phase, but will be included in the OA Program for fire protection during the operations phase."-
In -addition, applicable drawings and - specifications will be revised as required to reflect F-designated classification.
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Dir. ~ Nuc. - Reac. Reg.
4 5/23/85 Item Information Requested ~
- FS AR: Amendment ~ 9 -(page 33 of Table 3.2-1) changed the 'seis-
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mic category ofothe unit vent stacks from I to NA and the corresponding QA requirements from.Y (10 CFR 50, Appendix B) to N (QA requirements not' applicable)'. ' Justify or eliminate-thes e. changes.
PSE &G ' Response '
The unit vent: stack, ~ North and South (including structural
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steel support-framing) is not seismic category I.
The j ustification-is as - follows :
a) - Adequate ventilation would 'still be available for all safety-related equipment inLthe event of blockage or failure of these vent paths.
b).. FS AR Section 11.5.2.2.1 also states that, during acci-dent conditions, allLflows_from compartments that could.
be. ex pected to release significant radioactive materials can be isolated.
c)
J rhe. only ' radiation. monitoring - systems that are located in the unit vent stacks, north and south, are classified as non-Class'lE,-as described in FSAR Sections 11.5. 2. 2.1 and 11.5. 2.2. 2 i respectively.
Should there be any further questions or concerns regarding the above subjects, please contact us'.
' Very truly yours,
O
- C
- D. H. Wagner USNRC Licensing, Project Manager A.
R. Blough IUSNRC Senior Resident Inspector
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