ML20038C524

Corrects Error in & Adds Requirements to 810413 Proposed Tech Spec Changes to Bring Integrated Primary Containment Leak Rate Test Requirements Closer to App J Requirements

ML20038C524
Person / Time
Site:	Quad Cities
Issue date:	12/02/1981
From:	Rausch T COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20038C525	List: ML20038C524 ML20038C526
References
NUDOCS 8112110187
Download: ML20038C524 (3)

Text

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8 Commonweilth Edison l ,

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v one First National Plaza. Chicago, tilinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690

/? GQ~ gy December 2, 1981 L /

h I& fg Uhg Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation k% . $/

U.S. Nuclear Regulatory Commission d

, Washington, DC 20555 #M 4 gM ' -'

Subject:

Quca Cities Station Units 1 and 2 Supplement to Proposed Amendments to Appendix A, Technical Specifications, for Facility Operating Licenses DPR-29 and DPR-30 Regarding Appendix J Requirements NRC Docket-Nos. 50-254/265 Reference (a): R.F. Janecek letter to H. R. Denton dated April 13, 1981

Dear Mr. Denton:

In Reference (a), Commonwealth Edison proposed Technical Specification changes to Operating Licenses DPR-29 and DPR-30 for Quad Cities Units 1 and 2 that would bring integrated primary

'  : containment leak rate test (IPCLRT) requirements more closely in line with 10 CFR 50, Appendix J requirements.

4 The purpose of this lettter is to correct two minor errors in our Reference (a) request, and to add two additional requirements:

1. Section 3.7.A.2.a.1 - overall integrated leakage rate should be I La, 1.0 percent of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P a-

2. Section 3.7.A.2.a.2 - similarly, overall integrated leakage rate should be6Lt, 1.0 percent of the j containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of

P-t l 3. Addition o f new section 3.7. A.2.d specifyino a maximum leakage rate for the personnel air lock o f 3.,5% of La-

4. Addition o f new section 4.7. A.2.d.3 requiring local leak rate testing of bolted double gasketed seals af ter opening and subsequent reclosing.

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8112110187 811202 Q PDR ADOCK 05000254 P P,DR g

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Items 3 and 4 bsve been added to address the September 22, 1980 amendment of 10 CFR 50 Appendix J.

The specific changes, which have been reviewed and cpproved by On-site and Off-site review are included in the attachment to this letter. The af fected pages have been resubmitted in entirety to minimize any confusion.

Please address any questions concerning this matter to this office.

Three (3) signed originals and thirty-seven (37) copies of this transmittal are provided for your use.

Very truly yours, u wmr.,(bl(wuel Thomas J. Rausch Nuclear Licensing Administrator Boiling Water Reactors cc: RIII Inspector - Quad Cities SUBSCRIBE 0 and SWOR to beforo me this t/ day of h , 1981 I

OuduAt. & Lib Notary Public I

2949N

Attachment 1 Quad Cities Station Unit 1 Proposed Amendment to Technical Specifications for Facility Operating License DPR-29 Revised Pages: 3.7/4.7-2 3.7/4.7-3 3.7/4.7-4 l

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