ML20207M829

Responds to & Submits Clarification of SER for Amend 205 to License DPR-69,as Requested During 990311 Telcons

ML20207M829
Person / Time
Site:	Calvert Cliffs
Issue date:	03/14/1999
From:	Cruse C BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-MA2334, TAC-MA2335, NUDOCS 9903190207
Download: ML20207M829 (2)

Text

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CHAutts 11. Cnost Baltimore Gas and Electric Company Vice President Calven Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby. Maryland 20657 410 495-4455

, March 14,1999 U. S. Nuclear Regulatory Commission Washington, DC 20555 s

ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Clarification to issuance of Amendment for Calvert Cliffs Nuclear Power Plant, Unit No. 2 (TAC No. MA 2334 and MA2335)

REFERENCE:

(a) Letter from Mr. A. W. Dromerick (NRC) to Mr. C. H. Cruse (BGE),

dated March 8,1999, Calvert Cliffs Nuclear Power Plant, Units Nos. I and 2 Issuance of Amen:! ment for Calvert Cliffs Nuclear Power Plant, Unit No. 2 (TAC No. MA2334 and MA2335) l (b) Telephone Conference, between Mr. J. K. Kirkwood, et al (BGE) and Mr. A. W. Dromerick, et al (NRC), March 11,1999, Clarification of Safety Evaluation Repoit for Amendment 205 to License No. DPR-69. (4ON (c) Telephone Conversation, between Mr. B. S. Montgomery (BGE), and Mr. A. W. Dromerick (NRC), March 11,1999, Clarification of Safety Evaluation Report for Amendment 205 to License No. DPR-69.

In response to Reference (a), and as requested in References (b) and (c), and the following information is provided:

On page 5 of the Safety Evaluation [ Reference (a)], the NRC states: "The licensee also stated that prior to removing each associated train of the Service Water (SRW) System from service, both Unit 2 Emergency Diesel Generators (EDGs) will have been removed from service, modified, tested, and returned to operable status." This statement was based on our best understanding of the outage plan as of July,1998. By way of clarification, please be aware that BGE has adoptM 'he outage sequence described below. This sequence represents a substantial improvement in the ove : c ' liability of our AC power supply during this period because it will reduce, by up to four days, the araouat of time the SRW system will be unavailable to the EDGs. The sequence is as follows:

9903190207 990314 7 PDR ADOCK 05000317 P o PDR _ f ..

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i Document Control Desk '

March 14,1999 Page 2

l. Remove No. 2B EDG from service - begin alignment to the cooling tower.

2. Tagout and begin modifications to No. 22 SRW Header (normal cooling for No. 2B EDG)..

3. ' Test No. 2B EDG and declare it operable (in accordance with Reference (a)]. l

4. Remove Nos. 2A and IB EDG from service to begin alignment of No.12 SRW Header to l No. 2A EDG.

5. *'mut and begin modifications to No. 21 SRW Header (No. 2A EDG cooling.).

/ hs. 2A and iB EDG and declare them operable.

I ry, '

'te Safety Evaluation [ Reference (a)], the NRC states: "At the shutdown Unit 2, SRW l m work is not planned during periods of high decay heat and periods of reduced reactor cos >> ., ~m inventory, which are poteatially risk significant plant operational states." During the phone call between Mr. Montgomery (BGE), and Mr. Dromerick (NRC), [ Reference (c)], we agreed that the statement was inaccurate because cf a typographical error, and the word "not" should be removed.

The stateme .t should read: "At the shutdown linit 2, SRW heat exchanger work is planned during periods of high decay heat and periods of reduced reactor coolant system inventory, which are potentially  !

risk significant plant operational states." I Also on page 7 of the Safety Evaluation [ Reference (a)], the NRC states: "At all times at least one of the Unit 2 EDGs will be operable, but with degraded reliability due to the alternate cooling configurations for these diesels. During reduced inventory, both Unit 2 EDGs are planned to be available." During the second reduced inventory period, our EDG configuratien will be as stated in reference (a), or in the s following configuration: I No. 2A DG is planned to be operable on No. 21 SRW subsystem; the No. OC Diesel Generator will be available; and No. 2B DG may be out-of-service for removal of the cooling tower, and restoration to No. 22 SRW subsystem. The configuration with No.2A DG operable on No. 21 SRW subsystem complies with the Limiting Condition for Operation 3.8.2, of our current Technical Specifications.

These two items of clari4ation do not affect any of the conclusions reached in our probabilistic risk l assessment, our 50.59 safety evaluation, or the conclusions stated in reference (a). The license amendment and revised Technical Specification Bases statement remain applicable.

Should you have questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, I j o g-CHC/JKK/bjd ,

cc: R. S. Fleishman, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident inspector, NRC S. S. Bajwa, NRC R.1. McLean, DNR A. W. Dromerick, NRC J. H. Walter, PSC l

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