ML20141M377

Submits Revised Testing Schedule in Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Hx of at Least One Train of Each Safety Sys Tested

ML20141M377
Person / Time
Site:	Calvert Cliffs
Issue date:	08/04/1992
From:	Creel G BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-13, TAC-M73978, NUDOCS 9208120203
Download: ML20141M377 (2)

Text

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r; 's; c3ALTIMORE GAS AND ELECTRIC 1650 CALVERT CtJFFS PARKWAY . LUSBY, MARYLAND 20657-4702 GEOROE C< CREEL Vict PersiotNT .

nucle AR ENERGY (4eo) uso-44sa August 4,1992 U. S. Nuclear Regtdatory Commission Washington,DC 20555 NITENTION: - Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No.- 1; Docket No. 50-317 Revised Testing Schedule; NRC Generic Letter 89-13,

" Service Water System Prr'.' ems Affecting Safety Relned Equipment (TAC Nos. M73978)

REFERENCES:

(a) NRC Gene-ic Letter 89-13, dated July 18,1989, " Service Water System Problems Affecting Safety Related Equipment" (b) Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated January 29, 1990, Response to NRC Generic Letter 89-13, same subject (c) NRC Generic Letter 89-13, Supplement 1, dated April 4,1990, same subject Gentlemen:

'NRC Generic Letter 89-13, Reference'(a) outlined concerns regarding the safe operation and maintenance of the senice water systems and identified several recommendations associated with ensuring proper heat transfer cepability of senice water syttem components.

' Baltimore Gas and Electric (BG&E) Company's response to Generic Letter 89-13 was provided in Reference (b). In that response, we outlined a test program and stated all initial activities will be completed before plant stcrt-t.p (Mode 2) from the next refueling outages for each unit This letter is to inform you that@hile conducting the testing, we hwe found that some modifications to our O original plans are appropriate. In all cases we will have tested the heat exchangers of at least one train of each safety system as we committed in Reference (b). However,in some cases, as we review the data, we conclude that testing the heat enchangers in the other train is not necessary. In other

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cases, the data we measured was not conclusive because of available heat loads and instrument accuracies. In revising our test plans, we have ut!!ized the guidance of Reference (c) on cleaning,

- inspection or maintenance as acceptable alternatives to testing. For those testa that were conclusive,

y. heat transfer capabilities for the closed loop (Service Water and Component Cooling) heat /

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Document Control Desk August'4,1992

.Page 2 exchtngers were adequate. ' Additionally, our inspections of Unit 1 have shown that the cicaed loop systems are clean, indicating that our water chemistry quality has been better than we assumed in our original response. j In a follow-up letter, we will summarize the Generic Letter 89-1.' activities completed during the current Unit I refueling outage and justify the changes we made to our original test program. l l

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

Very truly yours,

( /

- GCC/JMO/ dim-cc: -- D. A; Brune, Esquire -

J. E. Silberg. Esquire R. \. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin,'NRC - l P. R. Wilson, NRC l R.I McLean DNR J. II. Walter, PSC 4W'e_ -

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