ML20062E539

Application for Amend to Licenses DPR-53 & DPR-69,adding List of safety-related Hydraulic Snubbers to Tech Spec Table 3.7-4

ML20062E539
Person / Time
Site:	Calvert Cliffs
Issue date:	07/30/1982
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Clark R Office of Nuclear Reactor Regulation
Shared Package
ML20062E542	List: ML20062E539 ML20062E551
References
NUDOCS 8208100141
Download: ML20062E539 (3)

Text

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N' ,y B ALTI MORC GAS AND ELECTRIC CHARLES CENTER . P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ARTHUR E. LUNDVALL. JR.

VtCE Pats, DENT su m v July 30,1982 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 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 I l

Gentlemen:

Baltimore Gas and Electric Company hereby requests an Amendment for Operating Licenses DPR-53 & DPR-69, for Calvert Cliffs Unit No.1 & 2, respectively, with the submittal of the enclosed proposed change to the Technical Specifications.

PROPOSED CHANGE Add the following snubbers to Table 3.7-4 of the Unit I and Unit 2 Technical Specifications as shown on Attachment 1:

r 1-28-1 Unit 1 Auxiliary Feedwater Pump Room 22' l-28-2 Unit 1 Auxiliary Feedwater Pump Room 22' OO!

l-28-3 Unit 1 Auxiliary Feedwater Pump Room 22' 3 1-45-4 Unit 1 MSIV Penetration Room 29' l-45-5 Overhead 5' Under MSIV Room 26'

• l-45-9 Unit 1 MSIV Penetration Room 29' v/ b ~

1-45-10 Unit 1 MSIV Penetration Room 29' l-45-10 A 2-36-3 Unit 1 MSIV Penetration Room 29' Unit 2 Auxiliary Feedwater Pump Room 18' Y O.D O 2-45-4 Unit 2 MSIV Penetration Room 29' 2-45-4A Unit 2 MSIV Penetration Room 29' 2-45-5 Unit 2 MSIV Penetration Room 29' 2-45-6 Unit 2 MSIV Penetration Room 29' 2-45-7 Overhead 5' Under MSIV Room 26' 2-71-8 Unit 2 Loop #22A Drain Line 25' 8208100141 820730 PDR ADOCK 05000317 P PDR

l

.* ,o Mr. Robert A. Clark July 30,1982 Page 2 DISCUSSION AND JUSTIFICATION (BG&E FCR 82-120)

In this submittal we are adding 15 existing snubbers to the safety-related snubber surveillance program. Recently it came to our attention, while reviewing a main steam line reanalysis for Unit 1, that certain snubbers associated with the Unit I main steam line had been unintentionally omitted from our safety-related snubber surveillance program.

In response to the problem associated with the Unit 1 Main Steam System we initiated a review by our Architect / Engineer of all safety-related systems with the intent of identifying additional snubbers of the same status as those identified for the Unit 1 Main Steam System. The results of that review produced 15 additional snubbers associated with the Unit I and 2 auxiliary steam supply to auxiliary feedwater pumps, main feedwater systems, and the Unit 2 reactor coolant drain line. A visual inspection has been completed on the 14 of these snubbers which are accessable. All 14 accessable snubbers have been upgraded to safety-related standards, testing is complete, and all have been declared operational.

The last snubber was identified during the final stages of the review, and is located on the reactor coolant loop #22A drain line, downstream of two normally closed manual valves. An analysis was done of this section of piping assuming the snubber was inoperable. Piping stresses for the faulted conditions (SSE, dead weight and pressure) are below Code allowables of 2.4 hS . A review of all supports in this section of piping indicates that loads are not significantly increased to affect support performance, except for one anchor (not a snubber) located in the downstream piping. For this anchor, local deformation of some members may occur, but the anchor will remain intact to provide integrity of the safety-related piping.

This change to our safety-related snubber program adds components described in our original safety analysis report. We have concluded from the results of analysis that the operability of the loop #22A drain line is not degraded to the extent that the public health and safety is compromised by continued operation of Unit 2.

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.

FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170, Paragraph 170.22, that this Amendment request consists of Class ill & I amendment for Calvert Cliffs Unit No.1 &

2, respectively, and accordingly, we are including BG&E Check No. B063798 in the amount of $4,400.00 to cover the fee for this request.

( l Mr. Robert A. Clark July 30,1982 Page 3 BALTIMORE GAS AND ELECTRIC COMPANY r

By: j- w dw/ ,

Vice Presiddnt -yupply AEL/ LOW /gla 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 Corporation.

WITNESS my Hand and Notarial Seal: [ Lbt[L ' /

Notary Pljblic h

My Commission Expires: Al t/ 'r / [b G' d cc: 3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NPC R. E. Architzel, NRC