|Person / Time|
BALTIMORE GAS & ELECTRIC CO.
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
|Download: ML20210S813 (4)|
- CucLos H. C UsE Baltimore Gas r.nd Electric Company Vice President Calvert Cliffs Nuclear Power Plant
, , Nuclear Energy 1650 Calven Cliffs Parkway L,usby, Maryland 2%57 410 495-4455 A Member ofthe Constellation Energy Group l
August 12,1999 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Control Desk
Calvent Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 1999 Refueling Outage; Summary of Completed Licensinn Actions Attachment (1) summarizes various open licensing actions for Baltimore Gas and Electric Company that were completed during the Unit 2 Refueling Outage, ending on May 6,1999.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, CIIC/ALS/ dim
1999 Refueling Outage Summary cc: R. S. Fleishman, Esquire 11. J. Miller, NRC J. E. Silberg, Esquire Resident inspector, NRC ,
S. S. Bajwa, NRC R.1. McLean, DNR l
A. W. Dromerick, NRC J.11. Walter, PSC ,
ATTACHMENT (1) l l
1999 REFUELING OUTAGE
i Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant - Unit 2 August 12,1999 i
r ATTACHMENT (1) ,
l 1999 REFUELING OUTAGE
Letter from Mr. C. II. Cruse (BGE) to NRC Document Control Desk, dated July 20,1998, License Amendment Request: Service Water IIeat Exchanger Replacement Letter from Mr. A. W. Dromerick (NRC) to Mr. C. II. Cruse (BGE), dated November 5,1998, Issuance of Amendment for Calvert Cliffs Nuclear Power Plant, Unit No. 2 (TAC No. MA2332)
During the 1999 refueling outage, we completed modifications to the Unit 2 Service Water (SRW) and Saltwater Systems. Specifically, to improve thermal performance of the SRW System and allow for higher bay water temperatures, the Unit 2 SRW shell and tube type heat exchangers were replaced with high efficiency plate and frame type heat exchangers. The Unit 1 SRW shell and tube type heat exchangers were replaced with high efficiency plate and frame type heat exchangers during the 1998 !
Unit I refueling outage. This completes the action required for these heat exchangers.
Letter from Mr. C.11. Cruse (BGE) to NRC Document Control Desk, dated ,
July 20,1998, License Amendment Request: One-time Technical Specification )
Change to Support the 1999 Refueling Outage.
Letter from Mr. A. W. Dromerick (NRC) to Mr. C. II. Crusc (BGE), dated March 8,1999, Issuance of Amendment for Calvert Cliffs Nuclear Power Plant, Unit No. 2 (TAC No. MA2334 and MA2335)
The amendment allowed a one-time change to the Technical Specification Bases for Technical Specification 3.8.2, and provided approval of BGE's analysis ofunreviewed safety questions as described in 10 CFR 50.59. The amendment was required to allow alternate cooling to the Unit 2 emergency diesel generators during replacement of the Unit 2 SRW heat exchangers. The amend nent was utilized during the Unit 2 refueling outage as intended to allow replacement of the SRW heat exchangers. This completes the action required for the subject license amendment request. We are in the process of removing this one-time change from the Technical Specification Bases.
l ATTACHMENT (1} j
.- l 1999 REFUELING OUTAGE
l SdBJECT: Long-Term Corrective Actions: CCNPP Bay Water Temperatures (TAC No. M87190)
(3) Letter From Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE),
(4) Letter From Mr. C. H. Cruse (BGE) to NRC Document Control Desk, dated August 28,1997, Individual Plant Examination of External Events for Severe Accident Vulnerabilities During a system design review conducted in 1989, BGE identified a potential vulnerability to the loss of 1 the non-safety-related portion of the SRW System during a Safe Shutdown Earthquake, which would cause a loss of inventory in the safety-related portion of the SRW System. This potential vulnerability was identified in Licensee Event Report 89-23-2. To resolve the potential vulnerability, BGE decided to assess the seismic adequacy of the non-safety-related portion of the SRW System and to strengthen the system by physically modifying five identified potential break points. The physical modifications are complete (reported in Reference 2). The effect of a seismic event on the non-safety related portion of the SRW system is addressed in Reference (4) above. The NRC staff concluded that BGE's proposal of including the SRW system seismic issue in its Individual Plant Examination of External Events program -
for final resolution to be acceptable (Reference 3). This completes the action required for the subject I licensee event report.