ML19031B039

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LER 1978-040-03 for Salem Unit 1 Inoperability of Makeup Valve from Demineralized Water Plant
ML19031B039
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/03/1978
From: Librizzi F
Public Service Electric & Gas Co
To: Grier B
NRC/IE, NRC Region 1
References
LER 1978-040-03
Download: ML19031B039 (3)


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,,0 PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 2011622-7000 c;

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August 3, 1978

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Mr. Boyce H. Grier .::C.g:;o  :--- c::\J

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Director of USNRC  ::0  ;;Em

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Off ice of Inspections and Enforcements ,.,,

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Region 1 (./) (.!*I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 78-40/03L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 78-40/03L. This report was required to be reported by July 15, 1978. Tnis report is late due to a breakdown in the administrative controls associated with LER processing. Based on past reporting experience, this breakdown is considered to be an isolated case, therefore, no further corrective action is planned.

Sincerely yours, F. P. Librizzi General Manager -

Electric Production CC: Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control ~

7322:=:(1(>:::5 I (3 copies)

The Energy People 95*2001 300M 10-74

  • J Report Number:

e 78-40/03L RE?port., Date: 8/3/78 Occurrence Date: 6/15/78 Facility: Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 ~[

IDENTIFICATION OF OCCURRENCE:

I' Auxiliary Feed Water Storage Tank Level Less Than Allowed by Technical Specifications

  • l

. CONDITIONS PRIOR TO OCCURRENCE:

Hot Standby, Mode 3 DESCRIPTION OF OCCURRENCE:

During Mode 3 operation while feeding the steam generators from the

~*xiliary feedwater storage, the normal supply valve from the demin-eralizer water plant (1DR6) became inoperable due to a malfunction in the valve operator. At 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />, the auxiliary feedwater storage tank level decreased to less than the 200,000 gallons required by Technical Specification 3.7.1.3. Action Statement "a" for LCO 3.7.1.3 was implemented. The valve operator on valve 1DR6 was readjusted and by 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, the storage tank level had been returned to within Technical Specification limits.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The cause of this occurrence was the malfunction of the valve operator on 1DR6. Alternate sources of water from the demineralized water plant were available during this event.

ANALYSIS OF OCCURRENCE:

Technical Specification 3.7.1.3 allows four (4) hours to restore an inoperable auxiliary feedwater storage tank to operable status. The tank was returned to operable status in one hour. The unit remained in Mode 3 throughout this event.

CORRECTIVE ACTION:

Valve operator on valve 1DR6 was readjusted and normal supply to the auxiliary feedwater storage tank was regained. Tank level was raised to > 200,000 gallons.

I I FAILURE DATA:

N/A

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)~_;L,,, J Prepared by~---T~.__.L_.;......;s~p...__e~n~c~e-r_*~~~--

Manager - Salem Generating Station SORC Meeting No. 49-78

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'i'~RC FO~M 366 U.S. NUCLEAR REGULATORY COMMISSION 17 771

  • " .** .,. .CENSEE EVENT REPORT CONTROL BLOCK: I I I I I I 10 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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[ill]  :;~~~! L1JG) I o I s I oI o I o I 2 I 7 I 2 IC?)I o I 6 I 1 I s I 7 I a I© I o I a I o 13 I 1 I a 10 I 7 8 60 61 DOCKET NUMBER 68 69 EVENT CATE 74 75 REPORT CATE 80 :I EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @ _ :I

!While feeding the steam generators from the auxiliary feedwater storage I

[]]IJ 1tank, the makeup valve (1DR6) from the demineralized water plant became I

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(]]:!]!inoperable. Auxiliary feedwater tank level decreased to less than allowed

[[TI] !by T.S. 3.7.1.3. This is the first occurrence of this type. Alternate

[]JI] lflowpaths were available.

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7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAi.VE COOE_ CODE SUBCOOE COMPONENT CODE SUBCOOE SUBCOOE filI] IW 161@ 1.Ll@ W@ lzlzlzlzlzl I@ W@ W@

7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION t;:;\ LER'RO LVENTYEAR REPORT NO. CODE TYPE NC.

'.:.:.J REPORT NUMBER I7 I 8I 21 22 I

23 I IOl4IOI 24 26 1......-1 27 lol 31 28 29 LIJ 30 1=I 31 w

32 ACTION FUTURE EFFECT SMUTOOWN t:;::;,, ATTACMMENT NPRD4 PRIME COMP. COMPONENT TAKEN ACTION ON Pl.ANT METMOO MOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LLl@W@

33 34 W@

35 LJ 36 Io I 01 01 01 37 40 W@

41 UU@) W@

42 43 IzI 44 9 I 9 I 9 I@

47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

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1..I IJI[] !Tank level was restored to within T. S. limits within one hmir OJI]

7 8 9 80 N~LITY STATUS  % POWER OTHER STATUS \;:;:)

9 METHOD OF DISCOVERY DISCOVERY OESCl'llPTION A

6' rrm Lill 7 8 9 lo I 0 lo !@I 10 12 1'J N/A 44 I Ls.J~I Operating Event "5 46 80 ACTIVITY CONTENT I:';\

REI.EASED OF REI.EASE AMOUNT OF ACTIVITY *.LOCATION OF RELEASE@

IJEJ W@ LLI@I 7 8 9 10 11 N/A 44 I N/A 80 PERSONNEi. EXPOSURES t:::::\

~TYPE~ DESCRIPTION I I I IIIIJ 1 o1 o 1 o l~We~_...:N~/..:;A,;;..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___,

NUMBER 7 8 9 11 12 13 80 PERSONNEL INJURIES Q..

NUMBER DESCRIPTION\!.!;

~I 7 8 9 olol ol(§)L----------~NwA.:-----------------------------------------------------------~

11 12 80 l.OSS OF OR DAMAGE TO FACll.ITY G

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IIIIJ TYPE DESCRIPTION L.z..J@)~-----------.....:.:N~A:.:,_ ___________________________________~

I I 7 8 9 10 80

'UBLICITY C\ NRC USE ONLY .,

ISSUEOC,;\ OESCRll'TION ~

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7 8 9 10 68 69 80 ;;

NAMEOFPREPARER~~--T ___* __ L_.~s __p_e_n_c_e__r~~-~-- PHONE: (609)365-7000 Salem E:h"i:.~

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