ML20084M988
| ML20084M988 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/14/1984 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8405160246 | |
| Download: ML20084M988 (2) | |
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o BALTI M ORE GAS AND ELECTRIC CHARLES CENTER.P.O. BOX 1475 BALTIMORE, MARYLAND 21203 May 14,1984 ARTHUR c. LUNDVALL, JR.
WcE PRESIDENT Suppo Director of Nuclear Reactor Regulation Attention: Mr. 3. R. Miller, Chief Operating Reactors Branch #3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos.1 & 2; Dockets Nos. 50-317 and 50-318 Post--Accident Sampling System
References:
- 1. NRC Memorandum from W. Johnston to G. Lainas, " Safety Evaluation of Post-Accident Sampling System of Calvert Cliffs Nuclear Power Plant," dated June 24,1983.
- 2. BG&E letter from A. E. Lundvall, Jr. to R. A. Clark (NRC),
dated November 30,1982.
Gentlemen:
At your request, we have reviewed the information contained in Reference I and have the following comments on same:
Criterion: (2)
There is a possibility for confusion with respect to the dilution of grab samples. All samples are taken in an undiluted form: no capability to dilute the sample at the sample point exists. Samples are diluted prior to analysis as necessary, up to a ratio of 2500:1.
Procedure development guidelines for final core damage assessment were the product of an effort by the Combustion Engineering Owners Group. Rese were received on February 28,1984. 'We will implement the Calvert Cliffs final core damage assessment procedure no later than February 28, 1985. Als development period is consistent with NRC guidance which states that one year from receipt of generic guidelines is a reasonable period for finalizing a plant-specific core damage assessment procedure. Interim core damage assessment procedures are in place as part of our Emergency Response Plan Implementing Procedures.
Criterion: (4)
Our oxygen sampling capabliity was described in our previous submittals. Your SER states, " verification that concentrations are less than 0.1 ppm is possible."
Our system provides the capability to measure oxygen concentrations from 0 to 5 volume percent with an
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accuracy of 2% of that range.
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Mr. 3. R. Mill:r May 14,1984 Miscellaneous:
Our current plans are to submit technical specifications for surveillance by the end of June,1984. The system has already been tested and placed in operation but radiologically contaminated samples have not been taken. A sample of the reactor coolant system liquid is planned, and should be accomplished before the end of June.
We believe that the above information will be helpful to you in finalizing your safety evaluation for the post-accident sampling system. Please contact us if you have any questions in this regard. You should also refer to Reference 2, which constitutes our primary licensing submittal for PASS. Additionalinformation addressing the concerns of Reference 1 for Criterion 10 is forthcoming.
Sincerely,
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e AEL/MDP/BSM/vf cc: D. A. Brune, Esq.
G. F. Trowbridge, Esq.
Mr. D. H. Jaffe, NRC Mr. T. Foley, NRC Mr. 3. C. Ventura, Bechtel Mr. M. A. Michelsen, CE
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