ML19294A503

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Responds to NRC Requesting Overpressure Protection Tech Specs.Requests Extension to 790215 for Submission Due to Receipt of New Info
ML19294A503
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 12/01/1978
From: Naughton W
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 7812070211
Download: ML19294A503 (2)


Text

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Commonwealth Edison

- One First National Plaza, Chicago, Illinois Address Reply to: Post Ofhce Box 767

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Chicago, Illinois 60690 December 1, 1978 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Zion Station Units 1 and 2 Overpressure Protection Technical Specifications NRC Docket Nos. 50-295 and 50-304 References (a) :

October 13, 1978 letter from W.

F.

Naughton to Director of Nuclear Reactor Regulation concerning Zion Station Units 1 and 2 Overpressure Protection Technical Specifications (b) :

August 28, 1978 letter from A.

Schwencer to Cordell Reed requesting overpressure protection technical specifications

Dear Mr. Denton:

Per Reference (a), Commonwealth Edison Company indicated that the overpressure protection technical specifications requested by the NRC Staff in Reference (b) were being drafted and would be completed around December 1, 1978.

However, during this period, Commonwealth Edison received the results of the first metal surveillance capsule removed from the Zion units.

Since the Zion Technical Specifications require recalculation of the Zion heatup and cooldown curves whenever new results for the metal surveillance program become available, Commonwealth Edison is in the process of revising these operating curves to reflect the results of the capsule irradiation.

Therefore, since these curves are essential for determining the overpressure protection setpoints, the proposed overpressure technical specifications are not available at this time.

Currently, Zion Station is operating under the proposed setpoints including the effects of the atypical weld metal issue.

However, the new capsule data will require additional analyses to incorporate the effect of the atypical weld metal issue.

These analyses will be performed by Westinghouse and are expected to be (

7812070211 W

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Commonwealth Edison NRC Docket Nos. 50-295/304 Mr. Harold R.

Denton: December 1, 1978 completed by the end of December 1978.

Upon receipt of these analyses, Commonwealth Edison will evaluate the effects to overpressurization and associated operating consequences and formulate appropriate overpressure protection technical specifications.

Thus, with your concurrence Commonwealth Edison will submit by February 15, 1979 the overpressure protection technical specifications requested by the NRC Staff in Reference (b) together with revised heatup and cooldown curves required by 10 CFR 50 Appendix G.

This submittal will be in advance of the next scheduled Zion refueling outage which is for Zion Unit 2 in March 1979.

One (1) signed original and thirty-nine (39) copies of this letter are provided for your use.

Very truly yours, kY William F. Naughton Nuclear Licensing Administrator Pressurized Water Reactors