ML20134N472

Application for Amend to License DPR-69,changing Tech Specs to Provide Increased Flexibility for Acceptable Main Steam Safety Valve Surveillance Testing.Fee Paid

ML20134N472
Person / Time
Site:	Calvert Cliffs
Issue date:	08/29/1985
From:	Poindexter C BALTIMORE GAS & ELECTRIC CO.
To:	Butcher E Office of Nuclear Reactor Regulation
Shared Package
ML20134N473	List: ML20134N472 ML20134N488
References
NUDOCS 8509050158
Download: ML20134N472 (3)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

' I. /BALTI M ORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 CHRis H. POINDEXTER VICE PaESIDENT Ewo ~ Eta.~o =D comuauctio~ August 29,1985 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 ATTENTION: Mr. E. J. Butcher, Jr., Acting Chief Operating Reactors Branch #3 Division of Licensing S UBJECT: Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Request for Amendment -

Main Steam Safety Valve Settings and Operability

REFERENCES:

(a) Mr. A. E. Lundvall, Jr., (BG&E), to Mr. J. R. Miller, (NRC), letter dated February 22,1985, " Unit 1 Cycle 8 License Application" (b) Mr. D. H. Jaffe, (NRC), to Mr. A. E. Lundvall, Jr., (BG&E), letter dated May 20, 1985, Docket No. 50-317, " Safety Evaluation of Calvert Cliffs Unit 1 Cycle 8" Gentlemen:

The Baltimore Gas and Electric Company hereby requests an Amendment to its Operating License No. DPR-69 for Calvert Cliffs Unit No. 2 with the submittal of the proposed changes to the Technical Specifications. Similar changes were requested for Unit 1 by Reference (a) and approved in Reference (b).

PROPOSED CIIANGE (BG&E FCR 84-3002)

Remove existing pages from the Unit 2 Technical Specifications and replace with the attached marked-up pages.

DISCUSSION The proposed Technical Specification changes are intended to provide increased flexibility for acceptable Main Steam Safety Valve (MSSV) surveillance testing. Safety analyses incorporating the revised MSSV Technical Specification setpoints show acceptable results relative to pressure boundary and fuel design criteria. In addition, the revised specification for operable MSSV required for MODE 3 operation ensures that adequate relief capacity exists to remove decay heat and reactor coola t pump heat.

h905^

P 050029 050 8 i 00! tal p%h r3

E

, Mr. E. J. Butcher, Jr.

August 29,1985 Page 2 DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS This proposed change to the Technical Specifications has been reviewed against the standards of 10 CFR 50.92 regarding significant hazards considerations. The changes do not constitute a significant hazard, in that operating in accordance with the proposed change wculd not:

(i) involve a significant increase in the probability or consequences of an accident previously evaluated, or No modification to plant equipment is made by this proposed change; therefore, the probability of an accident is not increased.

Consequences of accidents are within the acceptable criteria specified by the Standard Review Plan (NUREG-0800).

(ii) create the possibility of a new or different kind of accident from any accident previously evaluated, or No modification to plant equipment is made by this proposed change.

Therefore, no new accident scenario is created.

(iii) involve a significant reduction in the margin of safety.

Safety analyses incorporating the revised MSSV setpoints show that peak primary and secondary system pressures are less than 110% of the respective system design pressures, which is the criterion specified as acceptable by the Standard Review Plan. Specified acceptable fuel design limits are not exceeded.

The proposed change applies a previously used calculational model or design method.

Results of the change are within the acceptable criteria specified by the Standard Review Plan. Therefore, the change is consistent with example (vi) of exampics of amendments that are not likely to involve significant hazards considerations, as given in Federal Register Notice page 14870, dated April 6,1983.

SAFETY COMMrl'rEE REVIEW These proposed changes to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations and Off-Site Safety Review Committees, and they have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.

E

. Mr. E. J. Butcher, Jr.

August 29,1985 Page 3 FEE DETERMINATION Pursuant to 10 CFR 170.21, we are including BG&E Check Number A306412 in the amount of $150.00 to the NRC to cover the application fee for this request.

Very truly yours, 4 t' Am\

STATE OF MARYLAND :

TO WIT CITY OF BALTIMORE  :

Chris II. Poindexter, 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 Corporation.

WITNESS my lland and Notarial Scal: [M L

At gotary Public My Commission Expires: // [

/

CilP/JFW/ tim Attachments ec: D. A. Brune, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC T. Foley, NRC T. Magette, DNR