ML20023D873
| ML20023D873 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/27/1983 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20023D874 | List: |
| References | |
| NUDOCS 8306060105 | |
| Download: ML20023D873 (3) | |
Text
4 BALTI M ORE GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 BALTIMORE, MARYLAND 21203 ARTHUR c. LUNDVALL. JR.
VicE PRESIDENT SU PPLY U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 ATTENTION:
Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Request for Amendment Gentlemen:
The Baltimore Gas and Electric Company hereby requests an amendment to its Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Unit Nos. I and 2, respectively, with the submittal of the following proposed change to the Technical Specifications.
CHANGE NO.1 Remove existing page 3/4 6-19 of Unit Nos. I and 2 Technical Specifications and insert new revised pages 3/4 6-19, Attachment I to this submittal.
DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS Under an earlier modification, the SIAS signal was removed from RC Drain Tank Oxygen Sample Valve 1(2)-SV-6529, and the valve was modified by installing a key switch to operate the valve.
This valve was redesignated as the sample return valve to the containment for the Post Accident Sampling System required for NUREG-0737, item II.B.3. Administrative controls have been implemented to ensure the valve is maintained closed during reactor operations.
This will ensure that the containment integrity requirements of 10 CFR 50 are met.
This change will not result in the probability of an accident not previously analyzed in the Updated Final Safety Analysis Report.
The Updated Final Safety Analysis Report classifies the Post Accident Sampling System Return Line as a Type IV fluid penetration. The criteria specified for this type of penetration is as follows:
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e Mr. R. A. Clark May 27,1983 Page 2
" Lines which penetrate the containment structure and are connected to either the containment structure atmosphere or the reactor coolant system, but which are never opened during reactor operation, have valves with provisions for locking in a closed position".
This classification meets the requirements of 10 CFR 50, General Design Criterion 55, which states in part:
"Each line that is part of the reactor coolant pressure boundary and that penetrates primary reactor containment shall be provided with containment isolation valve as follows, unless it can be demonstrated that the containment isolation provisions for a specific class of lines. such as instrument lines, are acceptable on some other defined basis".
In this case, the other defined basis is the key operated switch, fuses normally being removed, and administrative control of the keys associated with that key switch. The Post Accident Sampling System will not normally be utilized until the reactor is completely shutdown. For post accident purposes only, the valve may be opened for short periods under administrative control. Therefore, the criterion for this type of containment penetration is satisfied.
This proposed change does not increase the probability of occurrence of an accident or malfunction of equipment important to safety previously evaluated in the Updated FSAR. This is because of dual protection for ensuring the valve is maintained in the closed position, during reactor operation,i.e., the fuses being removed and the key which must be inserted and operated to open the valve under administrative control. In addition, the PASS System is not safety-related, as specified by NUREG-0737.
This proposed change does not result in any reduction in the margin of safety. Section 3/4 6.4 of the Technical Specification Bases states that, "The Operability of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment."
Sy adminstrative1y controlling the valve as previously described, the valve is maintained closed unless actually in use. The surveillance requirements for containment isolation valves will adequately ensure the valve remains operable.
With the above considerations, the change has been determined to involve no significant hazards consideration, in accordance with 10 CFR 50.92.
SAFETY COMMITTEE REVIEW This proposed change to the Technical Specifications has been reviewed by our Plant Operations and Safety and Off-Site Safety Review Committees, and they have concluded that implementation of this change will not result in an undue risk to the health and safety of the public.
Mr. R. A. Clark May 27,1983 Page 3 FEE DETERMINATION We have determined, pursuant to 10CFR Part 170, paragraph 170.22, that this Amendment Request consists of a Class ill and I amendment for Calvert Cliffs Unit Nos.
amount of $pectively, and accordingly, we are including BG&E Check No. B178457 in the I and 2, res 4,400.00 to cover the fee for this request.
BALTIMORE GAS AND ELECTRIC COMPANY
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By:
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v4.M tre Vice Presidebt-$lupply AEL/LES/sjb STATE OF MARYLAND :
TO WIT:
CITY OF BALTIMORE :
Arthur E. Lundvall, Jr., being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to provide the response on behalf of said orporation.
WITNESS my Hand and Notarial Seal:
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J. A. Biddison, Esquire G. F. Trowbridge, Esquire D.11. Jaffe, NRC R. E. Architzel, NRC R. E. Corcoran, Chief (DHMH)
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