ML20203C906
| ML20203C906 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/20/1998 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-06, GL-96-6, NUDOCS 9802250285 | |
| Download: ML20203C906 (2) | |
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Cnce.ts 11. Ccosr-Ilattimore Gas and Electric Cornpany Vice President Calvert Cliffs Nucle:r Power Plant Nuclear Energy 1650 Cahen Cliffs Parkway Lust >y, Maryland 20657 410 495-4455 i
February 20,1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Revision to Commitmenis in 120-Day Response to Generic Letter 96-06, "Arsurance of Equipment Operability and Cor.tainment Integrity During Design-Basis Accident Conditions" The purpose of this letter is to notify you that we are revising our commitments made in response to Reference (a), as detailed in Reference (b), and revised by Reference (d). In Reference (c), Baltimore Gas and Electric Company requested approval of an unreviewed safety question concerning pressurization of the Service Water System. The pressurization modification was part of the Baltimore Gas and Electric Company response to Generic Letter 96-06 and was considered necessary because of a water hammer concern at the containment air coolers.
Following the direction given in Supplement I to Generic Letter 96-06, we have revisited our analysis of the water hammer event in the Service Water System. The preliminary results of a new analysis of the system responr0 to a loss-af-coolant accident cancurrent with a loss of offsite power incident indicates that the effects of a water hammer event will be less severe than originally thought and will not require the plant modifications described in References (b),(c), and (d). The analysis is now in the final review phase, but we are confident that the results will not significantly change.
Accordingly, we will not undertake modification of the Unit 1 Service Water System in 1998. We also will not fully implement the Unit 2 modification to the Service Water System. The Service Water System head tanks for both units will remain vented to the atmosphere. We have reviewed the operability determinations we made in support of Reference (b). We have concluded that they are still j
correct. Because of this change in commitment, ve request that the Nuclear Regulatory Commission
- suspend review of Reference (c) until further notice. Upon finalizing our rcised analysis, we will submit our response to the geceric letter.
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e Docum:nt Control Desk February 20,1998 -
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Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very 'ruly yours,
,, gj j A,%Y CilC/EMT/bjd cc:
R. S. Fleishman, Esquire
- 11. J. Miller, NRC-J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I 1, NRC R. I. McLean, DNR A. W. Dromerick, NRC J.11. Walter, PSC
REFERENCES:
(a)
Letter from Mr. B. K. Grimes (NRC) to Mr. C. H. Cruse (BGE), dated Septembsr 30, 1996, NRC Generic Letter 96-06:
" Assurance of Equipment Operability and Containment Integrity During Design-Besis Accident Conditions" (b)
Letter from Mr. C.11. Cruse (BGE) to NRC Document Control Desk, dated January 28,1997,120-Day Response to Generic Letter 96-06,
" Assurance of Equipment Operability and Containment Integrity During Design Basis Accidere. Conditions" I
(c)
Letter from Mr. C 11. Cruse (BGE) to NRC Document Desk., dated March 6,1997, License Amendment Request: Modification to the Service Water llead Tanks (TAC No. M98083)
(d)
Letter from Mr. C.11. Cruse (BGE) to NRC Document Control Desk, dated May 2,1997, Revision to Commitments in 120-Day Response to Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions" 4
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