ML20024C323

Updated LER 82-038/03X-1:on 820817,RCIC Steam Line High Differential Pressure Alarm Received.Caused by Air in Sensing Lines to Pressure Switches.Cross Threaded Cap Found on in-line Snubber.Snubber replaced.W/830624 Ltr

ML20024C323
Person / Time
Site:	Pilgrim
Issue date:	06/24/1983
From:	Harrington W, Vender J BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
83-158, LER-82-038-03X, LER-82-38-3X, NUDOCS 8307120518
Download: ML20024C323 (2)

Text

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UPDATE REPORT PREVIOUS REPORI DATE: 08/16/82 N~C FOC3 364 U.S. NuCLS A2 RReubAT@ny CSMMi%t2M APP 4VJ.) GY EMS LICENSEE EVENT REPORT 315 > 88 H W/r3*so (PLE ASE PRINT oR TYPE ALL REQUIRED INFORMATION)

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EVENT DESCRIPTloN AND PROBABLE CON 3EOUENCES h I o 12 l lon 8/17/82, while starting up from a cold shutdown, a RCIC steam line high dif- l 02 [ferential pressure alarm _was received. Pressure was less than 5 psi and coolant l o 4 l temperature was approximately 214 degrees F. During the cause determination, the [

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lS l@lZ l@ lZl@ IZ l@ l 010l 010 l [N j @ (.NJ @ lN_J@ lI l2 l0 l 4 l CAUSE DESCRIPTION AND CORRECTIVE ACTIONS O27 l 1 l o l l Air in the sensing lines to the'trif ferential pressure switches (DPIS #'s 1350-1A g l 1 l i l l & IB) was found to be the cause. The instruments were blown down. one at a time. l l i l 2 l l tested for operability and re. turned to service. The startup then continued. In- l 1 3 l_vestigation_rsvealed _ a cross threaded cap on an in-line snubber was the source l l1l4Ilof the air.

The snubber was replaced. MR #82-13-23. l

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NAMF 0F PREPARER . J. Vender PHONE: 617-746-7900

...,e BOBTON EDISON COMPANY 000 BovLaTON STREET BOSTON M AssACHUSETTs 02199 WILLIAM D. HARRtNGTON ccmaan ween posesoame ru o kaan June 24, 1983 BECo. Ltr. #83-158 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Docket Number 50-293 License DPR-35

Dear Sir:

The attached Licensee Event Report UPDATE 82-038/03X-1, "RCIC Differential Pressure Switches, "DPIS 1360-lA & IB", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specifica-tion 6.9.B.2.b.

If there are any questions on this subject, please contact us.

Respectfully submitted, William D. Harrington WDH/mg

Enclosure:

LER-82-038/03X-1 UPDATE cc: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Standard BECo. LER Distribution ll Y