ML20024D246

Supplemental LER 81-097/01X-1:on 811106,during Inadvertent Safety Injection Actuation,Boron Injection Tank Inlet Valves 1SJ4 & 1SJ5 Failed to Open Fully.Caused by Boron Buildup. Stems Cleaned.Design Change implemented.W/830713 Ltr

ML20024D246
Person / Time
Site:	Salem
Issue date:	06/29/1983
From:	Frahm R, Zupko J Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-81-097-01X, LER-81-97-1X, NUDOCS 8308030380
Download: ML20024D246 (4)

Text

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 77)

. LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT CR TYPE ALL REQUIRED INFORMATION) 1 6 7

0 1 8 9 lN lJLICENSEE lS l Gl CODE Sl1 l@l 0 l 0 l -l 0LICENSE 14 15 l 0 l NUMBER 0 l 0 l 0 l - l 025l 0 26l@l4LICENSE l 1l TYPE ll 1lJOllhl57 CAT l 68 l@

COWT l0l11 5$R l60Lhl 0l 5l 0l0DOCKET l 0lNUMBER 2l 7 l 2 h]68l l 1 l 0 EVENT l 6 lDATE 8 l 1 @l 0 75l 6 lREPORT 2 l 9DATE l 8 l 380l@

7 8 61 69 74 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lO12l lOn November 6, 1981, during an inadvertent safety injection actuation, Boron Injection l lo l3 l l Tank Inlet Valves 1SJ4 and ISJS failed to open fully. Promet notification was performed lo l4 l las required. The occurrence constituted a failure which by itself could have oreventedl l o I s I lthe fulfillment of the functional requirements of the system as analyzed in the FSAR. l 1016 l lin accordance with Technical speci fication 6 4 1_An_ l 10171 1 I I O ls l l I 7 8 9 80 DE CODE SUBC E COMPONENT CODE SUBC DE S E

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.,,. SEQUENTI AL OCCURRENCE REPORT REVISION LE R RO EVENT YEAR REPORT NO. CODE TYPE N O.

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44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h l 1 l o l l The valves did not open due to boron buildup on the stems. The stems were cleaned andl li li l l the motor operator torque settings for the open direction were increased to the maximud i1 12Il allowed. A design change was implemented to repack the valves with an improved packind, I1 I3l l The valves will be inspected for boron buildup wenkiv- a ancign changa ic imanruny 4n l lijA l l allow individual leakoff monitoring. _

l 7 8 9 80 A S  % POWER OTHER STATUS S OV RY DISCOVERY DESCRtPTION W (D_jh l 0 l 0 l 0 l@l N/A l hl Operational Event l ACTIVITY CONTENT RELE ASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q *d* h d@l N/A l l N/A l PERSONNEL EXPOS ES NuMBE R DESCRIPTION 1 7 l 0 l 0 l 0 lhlTvPEZlhl N/A l PERSONNEL NJURIES NUygER DESCRIPTION @

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LOSS OF OR DAMAGE TO FACILITY 4 TYPE DESCRIPTION 8308030380 830629 f4 7 1 9 l Zl@l10 N/A PDR ADOCK 00000 jy l-l l 7 8 9 b j 80

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7 8 9 10 68 69 80 5 9-4309 NAME OF PREPARER PHONE: {

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- ~~O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 13, 1983 Dr. Thomas E. Murley Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-097/0lX-1 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.8e, we are submitting supplemental Licensee Event Report for Reportable Occurrence 81-097/0lX-1.

Sincerely yours, J. M. Zupko, Jr.

General Manager -

Salem Operations RF:kls CC: Distribution b

The Energy People 4 y'l

% 2189 po'.O 1131

4 Report Number: 81-097/ 01X-1  ;

Report Date: 06-29-83 Occurrence Date: 11-06-81 Facility: Salem Generating Station Unit 1 Public Service Electric & Gas' Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Emergency-Core Cooling Systems - Boron Injection Tank Inlet Valves -

Inoperable. l This report was initiated by Incident Report 81-445.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 3 - Rx Power 0 % - Unit Load 0 MWe.

DESCRIPTION OF OCCURRENCE:

On November 6,1981, during routine Mode 3 operation, an inadvertent safety injection actuation occurred and Boron Injection Tank Inlet Valves 1SJ4 and 1SJ5 failed to open fully. Prompt notification of the NRC Resident Inspector was performed, with written confirmation transmitted within.the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

APPARENT CAUSE OF OCCURRENCE:

1 The' valves did not open fully due to increased mechanical drag caused by a buildup of crystallized boron around the valve stem. The valve 1

torque setting in the open direction, recommended-by the manufacturer 4

to be set between 2 and 3.5 on the adjustment dial, was set at the-low

- end of the range (dial setting of 2). The increased drag tripped the l torque switch.

I ANALYSIS OF OCCURRENCE:

-The operability of the boron injection system as part of the Emergency Core Cooling System (ECCS) ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by Reactor Coolant System-(RCS) cooldown.- RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident, or a steam line rupture.

The occurrence constituted a failure or malfunction of one or more components which prevents 'r o could prevent, by itself, the fulfillment

! of the functional requirements of system (s) used to cope with

! accidents analyzed in the FSAR. As such it is reportable in

! accordance with Technical Specification 6.9.1.8e.

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'LER ,81-097/01X-1 CORRECTIVE ACTION:

The boron buildup was removed, and the torque settings, in open direction, of Valves 1SJ4 and 1SJ5 were increased from 2 to 3. The i valves were cycled and surveillance testing was satisfactorily performed. In addition, Valves 1SJ12 and 1SJ13 were inspected for boron buildup and cleaned, and the torque settings were adjusted to a setting of 3 Finally, the corresponding Salem Unit 2 valves were also inspected and torque settings adjusted where deemed necessary.

Based on a subsequent engineering evaluation of the problem, Design Change Requests 1EC-1611 and 2EC-1612 were issued to repack the valves with an improved Grafoil-type packing. The change was completed on Unit 2 during the recent unit refueling outages, all valves involved were repacked with the improved packing. Completion of Unit 1 valves is scheduled for the next extended shutdown.

In order to further insure stem leakage does not interfere with valve operation, Design Change Requests 1EC-1649 and 2EC-0752 will be issued to modify the valve leak-off lines to allow individually monitoring leak-off. A procedure for weekly inspection for boron buildup will be implemented; the procedure requires cleaning of the valve stem in the event buildup is discovered.

FAILURE DATA:

Limitorque Corporation AC Motor Operator 1SJ4 and 1SJ5 Prepared By R. Frahm (Dene'ral Manager -

Salem Operations SORC Meeting No.83-086 1

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