ML19209A286
| ML19209A286 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/26/1979 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19209A287 | List: |
| References | |
| NUDOCS 7910030466 | |
| Download: ML19209A286 (2) | |
Text
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Commonwealth Edison One First National Plaza, Chicago. Ilhnois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 September 26, 1979 Dr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Zion Station Units 1 and 2 Revision to Proposed Change to Facility Operating License Nos.
DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304 Reference (a):
February 26, 1979 letter from C. Reed to H.
R.
Denton submitting proposed overpressure protection technical specifications Dear Dr. Denton Reference (a) requested a license amendment to revise the Zion Station Technical Specifications to provide overpressure protection as required by the NRC Staff.
Recently, while preparing for refueling outage surveillances, Commonwealth Edison Ccmpany noted that the proposed change of Reference (a) inadvertently pre-cluded surveillance testing on the safeguards system during refueling outages.
Attachment A to this letter alleviates this oversight by correcting Pages 82 and 83 of Reference (a).
The remaining pages submitted in Reference (a), Pages 73, 94, 164, 168 and 174 are correct as submitted.
More specifically, the words "and the reactor head is installed" were omitted in three places on Pages 82 and 83 of Reference (a).
These words are necessary in order to meet the Zion Station Technical Specification Surveillance Requirements of Section 4.8.4.B, i.e.,
this change allows safeguards equipment to be placed back in service when the reactor head is not installed.
The revision in Attachment A does not affect overpressure protection because overpressurization of the reactor vessel cannot occur when the reactor head is removed.
In addition, this revision clarifies when the low temperature low pressure setpoint for the PORVs is required, i.e., when the reactor head is installed.
The proposed technical specification changes in Attachment A have been reviewed and approved by Commonwealth Edison On-Site and Off-Site Review with the conclusion that there are no unreviewed safety questions.
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NRC Docket Nos. 50-295/304 Dr. Harold R.
Denton September. 26, 1979 Please address any additional questions that you might have to this office.
Three (3) signed originals and thirty-seven (37) copies of this letter are provided for your use.
Very truly yours, dl.
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Peoples Director of Nuclear Licensing WFNamae rttachment SUBSCRIBED and SWORN to before me this Nf-6 day of dcdl(4n(t0 t-1979.
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