ML18046A807

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Comments on NRC Draft Evaluation of SEP Topic III-7.C. Concurs W/Nrc Conclusion That If Delamination Did Not Occur During or After Prestressing & Subsequent Containment Testing,Likelihood Would Be Diminished
ML18046A807
Person / Time
Site: Palisades Entergy icon.png
Issue date: 07/21/1981
From: Vincent R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-03-07.C, TASK-3-7.C, TASK-RR NUDOCS 8107240297
Download: ML18046A807 (2)


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July 21, 1981 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch lfo 5 US Nuclear+RE;!gulatoryfCb:rflr)ri;'s:s'ion -

Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC III-7.C, DELAMINATION OF PRESTRESSED CONCRETE CONTAINMENT STRUCTURES s

By letter dated May 21, 1981, the NRC t~ansmitted for comment a draft evaluation of SEP Topic III-7.C.

Cons.umers Power Company has completed*

its review *of this document, and offers the following comments:

l. We agree with the NRC conclusion on page 3 that if delamination did not* occur during or shortly after prestressing and_ ~::1E-8_e:_q.ue_nt containment testing, the chance that it will o'ccur diminishes.

In view of the delamination inspection performed previously and the length of time which has elapsed since initial prestressing, we consider the possibility of dome delamination to be remote.

In addition, the original structural integrity test and the periodic integrated leak rate tests have and will continue to periodically verify the integrity of the entire containment building.

In view of all the above factors, and the fact tnat over the past decade, the concrete in the dome would have become even stronger.than it was during early testing, we conclude that periodic delamination testing is unwarranted.

The containment integrated leak rate tests which are required by Technical Specifications are considered adequate for continued assurance of structural integrity.

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Mr Dennis M Crutchfield, Chief Palisades Plant July 21, 1981

2.

The exterior surface of the confainment dome is presently coated with a layer of urethane foam approximately three inches thick.

The testing recommended by the staff evaluation is not feasible without removal of this coating.

Even if this coating were removed in the future, we still feel there is little safety benefit to be gained that would offset the cost of routine delamination inspections.

Robert A Vincent Staff Licensing Engineer CC Director, Region III, USNRC NRC Resident Inspector-Palisades

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