ML19031B179

LER 1977-006-01 for Salem Unit 1 #12 Reactor Coolant Flow Channel 1 Inoperable

ML19031B179
Person / Time
Site:	Salem
Issue date:	02/15/1977
From:	Schneider F Public Service Electric & Gas Co
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1977-006-01
Download: ML19031B179 (4)

Text

Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Vice President Production February 15, 1977 Mr. James P. O'Reilly "Director of USNRC Off ice of Inspections and Enforcements Region l 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-06/3L Pursuant to the requirements of Salem Generating Station Unit No. l Technical Specifications, Section 6.9.l, we are submitting Licensee Event Report for.Report~ble Occurrence 77-06/3L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, I ~~f

• 1 1 °'1' CC: Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control (3 copies)

Report*Nurnber:

Report Date:

Occurrence Date:

77-06/3L 1-20-77 1-20-77

• Docket....FUe

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Facility: Salem Generating Station Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

1. 12 Reactor Coolant Flow Channel 1 inoperable.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power: 22%

Generator Load: 140 MWe DESCRIPTION OF OCCURRENCE:

At 0732 the RMS channel RllA (Containment Air Particulate} alarmed.

Channel RllA was reading approximately 3000 cprn verifying a valid alarm. The Shift Supervisor implemented the Radiation Incident procedure. No personnel were in the containment at the time of the occurrence. The Shift Supervisor and Health Physics personnel entered the containment and found steam leaking in the area around No. 12 SI Accumulator. Control Room personnel reported that No. 12 RC Flow Channel 1 was pegged high. Operation personnel found the leak to be corning from No. 12 RC Flow Device.which was then isolated.

RC Flow Channel 1 Bistable was placed in the tripped condition as required by Tech. Spec. Action Statement 7 for Table 3.3-1.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The apparent cause of this occurrence was improper installation of the "Swagelok" tube fitting during construction of the panel. The fitting apparently backed off causing the leak.

ANALYSIS OF OCCURRENCE:

There are three (3) channels of flow instrumentation installed in each loop of the reactor coolant system. Technical Specification Action Statement No. 7 for Table 3.3~1 allows Startup or Power Operation to continue with one channel inoperable until the perfor-mance of the next required channel function test, provided the failed channel is placed in the tripped.* condition. No. 12 RC Flow Channel 1 was placed in the tripped condition, therefore the limiting condition for operation was not violated. At no time was there any danger to.

the health and safety of the general public or site personnel.

Report 77-06/3L 1-20-77 CORRECTIVE ACTION:

The failed fitting was replaced from spares and tested. The test was satisfactory.

FAILURE DATA:

Manufacturer: Swagelok Size: 3/8 inch Material: 316 Stainless Steel Prepared by T. L. Spencer Manager - ~lem Generating Station SORC Meeting No. 13-77

LICENSEE EVENT REPORT e CONTROL BLOCK 6

LICENSEE. LICENSE EVENT NAME LICENSE NUMBER. TYP TYPE IO IO 1-1 o I o I oI oI oI -1 OI O~ . ~ 41 11 11 11 lJo 10 11 I 15 . 2 ~

REPORT REPORT .

CATEGORY TYl'E SOURCE DOCKET NUMBER EVENT CATE REPORT DATE

~ CON'T~; I OJ ~ . ~ bP I 51 0 I -1 0 I 2 I 71 2J '3sOI 1121OI71 ~J 1 01 JI 216171 75

!J EVENT DESCRIPTION

@:fill During Mode I operation, No. 12 Reactor Coolant Flow Channel 1 became 7 8 9

@:§]I inoperable due to a tube fitting failure. Two (2) redundant flow 7 8 9

@El channels were operable in No. 12 Coolant Loop *. The tube fitting was 7 8 (iI!J I replaced from spares and -tested satisfactorily._ This is the first I 7

~I 89 occurrence cf this type (77-06/3L).

80 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT

. CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

@mt :n .pl 7 8 9 10 l!Ll 1.1 II IN IS IT IR..J!Lj 12 17 LL.I 43 IXl9!9!91 44 47 ~

CAUSE DESCRIPTION rii'J8l I A "Swagelok" tube fitting backed off causing the leak. This event I W9 . 80 l2..l!l I was apparently caused by improper installation durimi construction. I 7 8 9

[I]fil..,,_..._ ______________________________""""'-______________________________""""

1 a9 ea FACILITV METHOD OF i."'i.'1 STATUS '!It POWER OTHe-A STATUS DISCOVERY DISCOVERY DESCRIPTION L!.1.:..1 Lfil . 10 12 12 *I I~,___N_/_A____"""""""'I @J I N/A 7 0 9 10 12 13* 44 45* 46 80

. FORMOF ACTIVIT't CONTENT REL.EASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

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_N.J./~A;;.;,*-----------~! 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7

I90 I 0 1011I lZJ 12 l~_*_---.N.._/=A......

13

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PERSONNEL INJURIES NUMBftR DESCRIPTION a9 1lillJIOIOIOI h I""12_ _ _ _ _ _ _N/A __,,_ ___....___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _"""'eIo OFFSITE CONSEQUENCES

~19 . *. ' N/A

• LOSS OR DAMAGE TO. FACILITY TVPI! CUCAIPTION 7GJ!11z118~ ~10--------'----------:;:N~/A~*-------------------------------------------cJ Id GEJ..,,_ ___________________..,.+-"".__________...______________________________

PUBLICITY

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7 89 80 ADDITIONAL FACTORS*

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• NAME: _ _T~**,_.,;L;;;,,,._-S_.p_e_,_n_c_e_r __________ PHONE: ( 609 ).365-7000 Ext.Salem-528 !

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