ML20247R916

Application for Amend to License NPF-67,changing Tech Spec Table 3.6-1 to Provide Backup Air Supply Sys to Containment Bldg Compressed Air Sys

ML20247R916
Person / Time
Site:	Seabrook
Issue date:	09/21/1989
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247R922	List: ML20247R916 ML20247R929
References
NYN-89116, NUDOCS 8910020106
Download: ML20247R916 (2)

Text

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New Hampshire.

NYN-8 9116 September -21, 1989 United. States Nuclear Regulatory Commission Washington, DC 20555 Attention: ' Document Control Desk

References:

Facility Operating License NPF-67 Docket No. 50-443

Subject:

Request for License Amendment; Plant Instrument Air Cross-Connect to Containment Building Air System Gentlemen:

Pursuant to 10 CFR 50.90, New Hampshire Yankee (NHY) hereby proposes to amend the Seabrook Station Ope. rating License (Facility Operating License NPF-67).by incorporating.the proposed change, provided herein as Enclosure 1 into the Seabrook Station Technical Specifications. This proposed change

-results from the addition of cross-connect piping from the Plant Instrument Air System, outside Containment, to the Containment Building Compressed Air l

System, inside Containment. Plant reliability will be enhanced by providing a back-up air supply.to the Containment Building Compressed Air System.

The basis for this proposed change is provided in Enclosure 2 which includes a safety evaluation.

Based upon the information contained in, NHY has cuncluded that the proposed change does not involve un Unreviewed Safety Question pursuant to 10 CFR 50.59, nor does it involve a Significant Hazard Consideration pursuant to 10 CFR 50.92.

New Hampshire Yankee has reviewed the proposed change utilizing the criteria specified in 10 CFR 50.92 and has determined that the proposed change would not 1.

Involve a significant increase in the probability of consequences of any accident previously evaluated. The activation of a previously spare piping penetration to the containment will allow utilization of the Plant Instrument Air System to backup the Containment Building Compressed Air System during Modes 5 and 6.

The Containment Building Compressed Air System is non-safety related and not is relied upon for safe shutdown. The new penetration piping is designed to Quality Group B standards and is subject to testing per 10 CFR 50, Appendix J.

The activation of this penetration will not effect the existing offsite dosage analysis since the analysis already assumes the maximum possible bypass leakage. The total containment integrated leakage, as well as local leakage rates, will remain within 10 CFR 50, Appendix J, limits.

This cross-connect will not be used during Modes 1-4, therefore, incoming instrument air will not affect containment peak pressure.

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New Hampshire Yankee Division of Public Service Company of New Hampshire

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P.O. Box 300

• Seabrook, NH 03874

• Telephone (603) 474-9521

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- United States Nuclear" Regulatory Commission September 21', 1989 Attentions Document Control Desk Page 2 2.

Create the possibility of a new or different kind of accident from any previously evaluated.. The additional Type "C" penetrations maximum leakage.in conjunction with the' combined leakage'of the

. existing Type "B and

'C' penetrations will not exceed the total' leakage allowed by 10 CFR 50 Appendix J for bounding radiation doses to within the dose guidelines of-10 CFR Part 100'during accident conditions.

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Involve a significant reduction in a margin of safety. The bases for the Technical. Specifications indicate that allowable' leakages will be consistent with assumptions made in the offsite dose analyses.-

' If you have any' questions regarding this request,.please contact Mr.' Richa'd R. Belanger at:.(603) 474-9521, extension 4048.

r Very truly yours.

Ted C. Feigenbaum Senior Vice President-

- and Chief Operating Officer Enclosures-cc:

Mr.. William T. Russell Regional. Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406

'Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission

-Division of Reactor Projects Washington, DC 20555 Mr. George L. Iverson, Director

.0ffice of Emergency Management State Office Park south 107 Pleasant Street Concord, NH 03301 Mr. Antone C. Cerne NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 l

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