ML20207S313

Application to Amend License NPF-57,revising Tech Spec Table 3.6.5.2-1 Re Isolation Times for Secondary Containment Ventilation Sys Automatic Isolation Dampers,Imposing More Restrictive Surveillance Requirements.Fee Paid

ML20207S313
Person / Time
Site:	Hope Creek
Issue date:	03/13/1987
From:	Corbin McNeil Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N87024, NUDOCS 8703190264
Download: ML20207S313 (5)

Text

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• Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electnc and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038 609 339-4800 Vice President.

Nuclear NAR 13 1g87 NLR-N87024 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Dear Sir:

REQUEST FOR AMENDMENT FACILITY. OPERATING LICENSE HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10 CFR 50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance with the requirements of 10 CPR 170.21, a check in the amount of $150.00 is enclosed. In accordance with the requirements of 10 CFR 50.91(b) (1), a copy of this request for amendment has been sent to the State of New Jersey as indicated below.

This amendment requests revision to the maximum isolation times for secondary containment ventilation system automatic isolation dampers in Technical Specification Table 3.6.5.2-1. This change imposes more restrictive surveillance requirements and provides consistency between the Technical Specifications and FSAR Section 9.4.2.3. This submittal includes three (3) signed originals, including affidavits, and forty (40) copies pursuant to 10 CFR 50.30(b) and (c).

Should you have any questions on the subject transmittal, please do not hesitate to contact us.

Sincerely, x

Enclosure (check)

Affidavit i

' Attachments (2)

C703190264 870313 I PDR ADOCK 05000354 8I P pop g /D yo)

NAR 13 g Document Control Desk 2 C Mr. D. H. Wagner NRC Licensing Project Manager Mr. R. W. Borchardt NRC Senior Resident Inspector Director, Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Regional Administrator, Region I U.S. Nuclear Regulatory. Commission 631 Park Avenue King of Prussia, PA 19406

Ref: LCR 87-03 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

Corbin A. McNeill, Jr., being duly sworn according to law deposes and says:

I am Vice President of Public Service Electric and Gas Company, and as such, I f

• nd the matters set forth in our letter dated March 13, 1987, concerning License Change Request 87-03 for Hope Creek Generating Station, io true to the best of my knowledge, information and belief.

Subscribejj and SwornJ o before me this /wJ rh day of 71/]As))

, 1987 Notary Public of New Jersey DEORIS D.HA0001 pdhW W Cassaden EmpiresitNEh 14.IIII My Commission expires on

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PROPOSED CHANGE TO Ref. LCR 87-03 TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION DESCRIPTION OF CHANGE Change the maximun isolation times provided in Technical Specifications Table 3.6.5.2-1 from the present 10 seconds to 7 seconds for the four dampers listed.

REASON FOR CHANGE FSAR Section 9.4.2.3 states that "the exhaust air transit time between the refueling area monitors and the Reactor Building Ventilation System (RBVS) exhaust system isolation dampers is greater than the combined time for damper closure and the monitor response. The exhaust air transit time is 12 seconds and the combined nonitor response and damper closing time is within 11 seconds."

The Refueling Floor Exhaust Radiation - High Trip Function Response Time is given as a maximun of 4.0 seconds in Technical Specifications Table 3.3.2-3. Adding this maximun value to the maximum damper closure time allowed by Technical Specifications Table 3.6.5.2-1 yields a combined monitor response / damper closure time of 14 seconds. This value is in conflict with, and less conservative than, the FSAR statement above. Revising the damper isolation times from 10 seconds to 7 seconds in Table 3.6.5.2-1 will conservatively correct the Technical Specifications and bring them into agreement with the FSAR.

SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS This change does not involve a significant increase in the probability or consequences of any previously evaluated accident or malfunction of equipment important to safety The change is administrative in nature... constituting an additional limitation in the existing Technical Specifications table by providing a nore stringent surveillance requirement.

This proposed change does not create the possibility of a new or different kind of accident from any previously evaluated because there is no change to existing plant

. equipment, procedures, or operating parameters. This

! change makes an existing surveillance requirement agree with original design statements by conservatively decreasing the allowable overall response time for a i radiation monitor - damper closure evolution. Actual measured response times are already within the proposed

, response time limits.

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1., .- . . .

Ref.'LCR 87-03 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS (Cont'd)

This proposed change does not involve a significant reduction in any margin of safety. Conversely, the change ensures surveillance response time requirements that, by preventing times in excess of stated FSAR response times, will enhance the margins of safety presently provided by the affected table.

Based on the above, we have determined that this proposed change does not involve a Significant Hazards Consideration. Additionally, we suggest that this change conforms to example (ii) of the guidance provided by the Commission in 48FR14870 of the Federal Register for Amendments Not Likely To Involve A Significant Hazards Consideration, in that, the change introduces a more stringent surveillance limitiation into the existing Technical Specifications.

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