ML19031B569

LER 1977-020-01 for Salem Unit 1 Reactor Coolant System Leakage ≫ 10 Gpm

ML19031B569
Person / Time
Site:	Salem
Issue date:	04/12/1977
From:	Schneider F Public Service Electric & Gas Co
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1977-020-01
Download: ML19031B569 (3)

Text

Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Vice President Production April 12, 1977 Mr. James P. O'Reilly Director of USNRC Office of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-20/3L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 77-20/3L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, CC: Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control

( 3 copies)

• _ __.L_,.. ..:*---- ... \

Report Number: e20/3L R~port Date: 4/5/77 Occurrence Date: 4/4/77 Facility Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Reactor Coolant System Leakage > 10 GPM.

CONDITIONS PRIOR TO OCCURRENCE:

Operational Mode I - Reactor Power: 40%

DESCRIPTION OF OCCURRENCE:

At 0900, Reactor Coolant System total identified leakage was determined to be 10.096 GPM. This being greater than the 10.0 GPM allowed by Tech-nical Specification Action Statement 3.4.6.2(b) was implemented. At 0946, Reactor power was decreased and the unit taken out of service to investigate the leakage.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Packing leakage past the stems on 13 & 14RC20 (RTD Bypass Throttle Valves) was the cause of the excess leakage. This leakage is piped thru stem leakoff lines to the RCDT.

ANALYSIS OF OCCURRENCE:

Action Statement (b) for LCO 3.4.6.2 states that with any Reactor Coolant System leakage greater than any one of the limits, excluding pressure boundary leakage, reduce the leakage rate to within limits within four hours or be in at least Hot Standby within the next six hours. The leak-age was reduced to within the limits, therefore, the LCO was not violated.

CORRECTIVE ACTION:

Valves 13 & 14RC20 were placed on their backseat and the stem leakage decreased. RCS leak rate was then determined to be less*than 3 GPM.

FAILURE DATA:

Not applicable.

Prepared by T. L. Spencer

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Station SORC Meeting No. 41-77

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LICENSEE EVENT REPORT

.CONTROL BLOCK I 6

UCENSEE L.ICENSE EVENT NAME l..ICENSE NUM8ER TYPE TYPE

@ill!NIJ-1s1G1s1~1 l50101-10101010101-101gJ 14111 lllllJo ~

REPORT REPORT CATEGORY TYl9£ SOURCE OOCKET NUM8ER EVENT CATE REPORT CATE fOT1l coN'TI P I 0 I

~ s-;-g IL I.

59 l!:!J 60 I 0 I 51 0 I -I 0 I 2 I 71 61 2J IO I 4 I O I 4 17 I 7 I 69 74 I 0 14 I 0 I 5 I 7 I 7J 75 EVENT DESCRIPTION

@))!During Mode- 1 operation, identified RCS leakage was determined to be greater 7 8 9 . 80

@E than 10 GPM. Action Statement (b) for LCO 3.4.6.2 was im lemented and th 7 8

@]!] unit taken out of se*rvice. 13 & 14RC20 were placed*on.their backseat and 7 8

[fili]lleakage was reduced to less than 3 GPM. This is the 1st occurrence of I 7 8 9

~I this type. (77-20/3L) ao 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT COCE CODE COMPONENT COOE SUPPL.I ER MANUFACTURER VtOl..ATION

[fil]l£W l..E.J I Z I Z I Z I Z I Z..J.Z.j LZ.I I Z I 919 19 I illJ 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

~!Packing leakage past the stems on the RTD Bypass thru the valves (13 I

@::00?and 14RC2 O) caused the excess leakage.

80 I

7 8 9 ao 1G:@]'::"-~~~~--~~------~--~~~~----~~~-------------------------""'1 ag ao FACIL.ITV METHOCOF r:r."I STATUS 'II.POWER OTHE*R STATUS CISCOVERV CISCOVERY DESCRIPTION l..!.J.!J ~. I 01 41 01 I~~~N~/~A.__~__.I l.QJ IRCS leak rate surveillance 7 IJ 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY 1..0CATION OF REL.EASE r!::EJ8 ~ W I N/A I l~~~~~--"'N~/~A--~...,.._~~~~I 7 9 10 11 44 ~ ~

PERSONNEL EXPOSURES r.i:"I NUM8ER TYPE DESCRIPTION

~1010101 lZJ ~I~~--=N=/~A--~~~~~~~~~~~~~~~---..lJ 7 8 9 11 12 13 §)

PERSONNEL INJURIES NUM8ER DESCRIPTION 7

~10101011 8 9 h

~,.--~~~~N~/~A~~~~~~~~~~~---~~~~~___,..,il 12 80 OFFSITE CONSEQUENCES

~19 . N/A LOSS OR DAMAGE TO FACILITY TVP!: CESCRIPTION J1 la!l/J . ~o N/A PUBLICITY.

l2J!J .

7 8 9 eo

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ADDITIONAL FACTORS -..i 1 a ao

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1 &~e~--~-~-----~----~--~----~-------------~ao NAME: _ _ _ _ _ _ T_._L_._*s_,p._e_n_c_e_r________ PHONE: ( 6 0 9) Jff5-7 0 0 0 Ext. Salem- 528