05000318/LER-1983-074, Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209

Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209 Ltr

ML20086Q165
Person / Time
Site:	Calvert Cliffs
Issue date:	02/09/1984
From:	Lyons W, Pieringer P, Russell L BALTIMORE GAS & ELECTRIC CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-83-074-03X, LER-83-74-3X, NUDOCS 8402270455
Download: ML20086Q165 (2)

LER-2083-074, Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209 Ltr

Event date:
Report date:
3182083074R00 - NRC Website

text

UPDATE REPORT A '

PREVIOUS REPORT DATE: 01-19-84

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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3 EVENT DESCRIPTION ANO PRO 8ABLE CONSEQUENCES h l 0 l2 ll Durine normal operarian. the main steam supply valve to the steam l Ml driven auxiliary feedwater (AFW) numos failed open causine 21 AFW oumn l l0l4ll to start. To repair the valve. the auto initiate capability for the l l0j5ll steam driven AFW pumps was defeated (T.S.3.7.1.2). The AFW system was l

@l returned to a normal lineup 17.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after being declared inoper=hle. l l0l7ll The motor driven pump remained operable throughout the event. l

,l Similar events: 50-318/83-35. 83-30 83-50. l OE CODE SUSC OE COMPONE NT CODE SUSCObE SWBC DE lois1 I c I a l @ L,,xJ @ L..zJ @ I v l A l t lv le Ix l @ L,,rJ @ b.. J @

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[I l o_j l The diaphragm's casing holes were elongated because of insufficient l l1l1ll torque on some of t e casinn can screws. A new diaphraam was installed l 11l2ll and properly toraued. The valve was then tested satisfactorily. Unit 2 l l1l3ll maintenance personnel have been instructed on proper actuator mainten- 1 1114ll ance IAW vendor's Tech Manuals. =

l STAT S  % POW E R OTNEW ST ATUS OtS C OV EN T DISCOVENT DE SCRIPTION lr Il 5. l. W h l 1l 0l 01@l N/A l bjh! onorator Observatinn

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RELE SEO RE E AMOUNT OF ACTIVITY LCC ATION OF R ELE ASE l116l W h W hl N/A l l N/A l 98U M SE R TTPE D E S C AlPTION 1117. l.l0 l 0 l 01@l Zl@l N/A l NUMSEN E S C RIPTIO.4 l, 1l s l l 0 l 0 l 0 l@l N/A l

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NAME OF PREPARER P. Pieringer/W. Lyons PHONE: (301) 269-4742/4861

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B ALTIMORE G AS AND ELECTRIC COMPANY P.O. BO X 14 7 5 B A LTIM O R E, M A R Y L A N D 2120 3 NUCLEAR POWER DEPARTMENT cQLVERT CLIFFS NUCLEA R POWER PL ANT LUSBY. M ARYL AND 20657 February 9, 1984 Dr. Thomas E. Murley Docket No. 50-318 Regional Administrator License No. DPR 69 U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

Attached is LER 83-74/3X, Revision 1, as required by 10 CFR 50.73.

Should you have any questions regarding this report, we would be pleased to discuss them with you.

Very truly yours, L

L. B. Russell '

Plant Superintendent LBR:WTL:bsb cc: Director, Office of Management Information and Program Control Messrs: A. E. Lundvall. Jr.

J. A. Tiernan

1. r 4

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