ML18102A424

Suppl to 960610 Application for Amends to Licenses DPR-70 & DPR-75 Re Changes to TS Control Room Emergency Air Conditioning Sys.Related Change to Design Makeup Flow Rate Being Proposed,As Discussed in Attachment 1

ML18102A424
Person / Time
Site:	Salem
Issue date:	09/20/1996
From:	Storz L Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N96284, NUDOCS 9609300211
Download: ML18102A424 (6)

Text

Public Service Electric and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations LR-N96284 SEP 2 01996 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENT TO REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:

By letter LR-N96154, dated June 10, 1996, Public Service Electric

& Gas Company (PSE&G) submitted a request to amend Technical Specification (TS) 3/4.7.6 pertaining to Salem-Generating Station's Control Room Emergency Air Conditioning System (CREACS). This letter provides a supplement to that request.

The requested change revised the CREACS TS to reflect a control room design in which the common Salem Unit 1 and 2 Control Room envelope is supplied by two trains, one from each unit. In that submittal, PSE&G proposed a revision to the surveillance flow rate from 7410 cfm +/-10% to 8000 cfm +/-10% and stated that the impact on the Chilled Water System had yet to be assessed.

PSE&G has completed this evaluation and as a result, it has been determined that the Chilled Wate*r System can maintain ambient temperature s85° F with the revised flow values and no change to the total surveillance flow rate value is necessary. However, a related change to the design makeup flow rate from s2500 cfm to s2200 cfm is being proposed, (refer to Attachment 1) , as a result of additional design and licensing basis reviews that were performed on associated systems.

PSE&G has determined that alignment of the Auxiliary Building Ventilation System within thirty minutes could not be supported as an input assumption into the dose analyses. Rather, a more conservative value of two hours has been evaluated. This change, however, resulted in an unacceptable dose at the previously specified maximum makeup flow value, 2500 cfm, and minimum total flow rate, 7200 cfm. In order to compensate for the increased time assumption to align the ABV and meet the minimum total flow rate specified, (e.g., worse case dose consequences), a reduction 9609300211 960920 PDR ADOCK 05000272 P PDR l:I>t, Printed on

~ Recycled Paper f

Docum~nt Control Desk 2 SEP 201996 LR-N96284 in the maximum amount of outside air specified in surveillance requirement 4.7.6.1.d.3 is proposed, 2200 cfm.

Peliminary assessment of the dose to control room operators from a Loss of Coolant Accident, the bounding accident analysis for Control Room dose, has determined that the proposed revisions result in doses that are within General Design Criteria 19 limits. PSE&G will notify the Staff when the supporting calculations have been finalized.

Also, an editorial error is being corrected in the propos~d revision to Surveillance Requirement 4.7.6.1.c pertaining to the testing after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation. The current Unit 1 TS allows testing options and denotes this by the words "either" and "or." These words were inadvertently left in the proposed surveillance though the revised requirement stipulates only one acceptable method of testing.

PSE&G has reviewed the previously submitted evaluation in accordance with the three standards set forth in 10CFR50.92 and has concluded that no change is necessary as a result of the revised pages and the conclusion of no significant hazards consideration remains valid.

Should you have any questions regarding this supplement, we will be pleased to discuss them with you.

Sincerely, - I

• x~

t7/&c 193 Attachment c Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 i I

I Mr. L. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 95-4933

SEP 2 01996 Document Control Desk 3 LR-N96284 Mr. C. Marschall (X24)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933

SEP 2 01996 pocument Control Desk 4 LR-N96284 SRM/pf r BC Senior Vice President - Nuclear Engineering (N19)

General Manager - Salem Operations (S05)

Director - QA/NSR (XOl)

Manager - Nuclear Business Relations (N28)

Manager - Salem Operations (SOl)

Manager - System Engineering - Salem (S02)

Manager - Nuclear Safety Review (N38)

Salem Mechanical Engineering Manager (N51)

Onsite Safety Review Engineer - Salem (Xl5)

Station Licensing Engineer - Salem (X09)

R. Chan J. Duffy J. Giessner H. Druckman General Solicitor, R. Fryling, Jr. (Newark, 5G)

Mark J. Wetterhahn, Esq.

Records Management (N21)

Microfilm Copy Files Nos. 1.2.1 (Salem) 2.3 (LCR S95-21)

REF: LR-N96284 STATE OF NEW JERSEY SS.

COUNTY OF SALEM L. F. Storz, being duly sworn according to law deposes and says:

I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief.

KIMBERL VJO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission expires on My Commission Expires April 21, 1998

~ ~

e Qqcvment Control Desk LR-N96284 Attachment 1 LCR S95-21 Supplement SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS REVISION OF CONTROL ROOM VENTILATION SPECIFICATION TECHNICAL SPECIFICATION PAGES WITH MARKED UP CHANGES The following Technical Specifications for Facility Operating License No. DPR-70 and DPR-75 are affected by this supplement:

Technical Specification Page 4.7.6.1.c 3/4 7-20 4.7.6.1.d* 3/4 7-21 4.7.6.1.c 3/4 7-16 4.7.6.1.d.3 3/4 7-17

• LCR S95-21 adds requirement to Unit l; similar surveillance requirement did not exist previously.

Revision to Insert 4 of LR-N96154, Attachment 3, Pages 4, 5 of 25

c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by eith~-r~

-+/--;... c:v;;ifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of 2 99% for radioactive methyl iodide when the sample is tested at 30°C, 95% relative humidity Ar

d. At least once per 18 months by:

1. (As proposed in LR-N96154)

2. (As proposed in LR-N96154)

3. Verifying that the system can maintain the control room at a positive pressure 2 l/8 11 water gauge relative to the adjacent areas during system operation with makeup air being supplied through the HEPA filters and charcoal adsorbers at the design makeup flow rate of ~ 5-&G- cfm.

2200

4. (As proposed in LR-N96154)

5. (As proposed in LR-N96154)