ML20134E510

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Updates Util Re post-accident Sampling Sys.Sys Inoperable Due to Persistent Valve Leakage Problems.Boron Analyzer Repaired & Calibr.Pending Resolution of RCS Isolation Valve Leakage,Sys Should Be Operable by 850813
ML20134E510
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/08/1985
From: Russell L
BALTIMORE GAS & ELECTRIC CO.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20134E512 List:
References
NUDOCS 8508200294
Download: ML20134E510 (1)


Text

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  1. ,2 BALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 14 7 5 B A LTIM O R E. M A R YL A N D 21203 NUCLEAR POWER DEPARTMENT CALVERT CLIFFS NUCLEAR POWER PLANT Lusev.uARvLANo ross7 August 8,1985 Dr. Thomas E. Murley Regional Administrator U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

SUBJECT:

Calvert Cliffs Nuclear Power Plant Units 1 and 2 Inoperability of Post-Accident Sampling System

Dear Dr. Murley:

This is an update to my letter to you, dated July 22, 1985, on the status of the Post-Accident Sampling System (PASS). The System still remains inoperable due to persistent valve leakage problems.

The boron analyzer has been repaired and calibrated. The discrepancies with the on-line germanium detector have been identified and corrected. The dilution capability of the System has been performed and verified. The hydrogen and oxygen monitors have also been repaired and calibrated. Although the replacement parts for the pH monitor are on site and available, they have not been installed due to the pressure transients on the subsystem caused by valve leakage.

Leakage in the System has been detected from Unit 2 Reactor Coolant System (RCS). Although this isolation valve has been repaired and checked several times, it appears that it is unreliable in this application and must be replaced. Similarly, we expect unreliable performance from the Unit 1 RCS sample isolation valve. Leakage through these isolation valves prevents accurate determination of the dilution factor of the PASS grab samples, and thus renders the alternate method of obtaining post-accident samples inoperable.

Pending resolution of the above problem and satisfactory post-maintenance testing, the PASS and back-up sampling method is expected to be returned to operable status about August 13,1985.

If you have any questions concerning the above, please give me a call.

Sincerely, 85002 0

$h$17 PDR PDR L. B. Russell 6

Plant Superintendent LBR/djw cc:

Director, Office of Management Information and Program Control Mr. A. E. Lundvall, Jr.

Mr. J. A. Tiernan i