ML19031B571

LER 1977-018-01 for Salem, Unit 1, No. 14 Reactor Coolant Loop T/Tavg Protection Channel IV Inoperable

ML19031B571
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 1977-018-01
Download: ML19031B571 (5)

Text

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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 Off ice 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 77-18/3L 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 77-18/3L. 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)

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Report Number: ~18/3L Rep~rt Date: 4/5/77 Occurrence Date: 3/14/77 Facility Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

No. 14 Reactor Coolant Loop ~T/Tavg Protection Channel IV Inoperable.

CONDITIONS PRIOR TO OCCURRENCE:

Operational Mode 1, Reactor Power: 75%; Generator Output: 835 MWe DESCRIPTION OF OCCURRENCE:

During Mode 1 operation, a functional test was being performed on No. 14 Reactor Coolant Loop ~T/Tavg Protection Channel No. IV~ At 2237, the Shift Supervisor and Performance I&C Foreman were informed tRe trip point for this channel exceeded the Technical Specification. A calibration check defined the problem area. The channel was re-calibrated and the function test re-run with satisfactory results. The channel was declared operable at 0110, 3/l5/77.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

This is the second occurrence of this type for this channel, caused by channel drift. Common failure mode for channel drift has not been established since each occurrence showed drift of a different component.

Ambient condition changes in the protection channel area were negligible.

ANALYSIS OF OCCURRENCE:

Startup or power operation is permitted by Tech Specs providing the affected channel is placed in the tripped condition within one hour.

This places the associated reactor protection system in a more con-servative 1 out of. 3 mode rather than the normal 2 out of 4. The affected channel was in the tripped condition throughout the occurrence.

The limiting conditions for operation were not violated. At no time was there any danger to the safety of the general public or site personnel.

CORRECTIVE ACTION:

All of the reactor protection ~T/Tavg channels are being evaluated and reset as part of Phase III testing. The Performance Department is attempting to determine what are the contributing factors for the chan-nel drift and will begin changing components if problem re-occurs with any specific component.

Re~ort 77-18/3L 4/5/77 FAILURE DATA:

This is the second failure of this channel to pass the function test due to channel drift. No specific component failure has been identified.

The channel manufacturer is Hagen Controls.

Prepared by A. Kapple

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Manager - safem Generating Station SORC Meeting No. 41-77

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LICENSEE EVENT REPORT CONTROL BLOCK 6

LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE REPORT REPORT CATEGORY TYl'E SOURCE OOCKET NUMBER EVENT CATE REPORT DATE I011lcoN'TlRJ..Qj LW UJ I015101-10121712J 1013111417171 101410151717J r-'"i 57 58 59 60 61 69 74 75 EVENT DESCRIPTION

@:ill I During Mode 1 operation, function test showed that #14 Reactor Coolant I 7 8 9 . . BO

[fil!l Loo  !:::.T/Tav Protection Channel IV tri oint exceeded .Tech S ec Limit.

7 8 9

@El The channelwas calibrated and the function test re-run satisfactorily.

7 8

[fil§] I The !:::.T/Tavg channels. I,II & III were operable throughout this occurrencei 7 8 9 80

~I All !:::.T/Tavg protection channels are being evaluated and reset as part of I 7 8 9 . PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT

• CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

@m L1..1.AJ L!J 1 *r I NI SI Tl RLUJ l!!J IHI O 1115 I 44 47

~

7 8 9 10 11 12 17 43 48 CAUSE DESCRIPTION ug have not been* established as each occurrence showedCommon

!Olill The cause has been attributed to channel drift.

~I failure componenqs drift of a different!

so 7 8 9 so

[ilfill component. Re-calibration returned the channel to normal operation. I 7 8 9 so FACILITY METHOOOF r.l;1 STATUS '!I.POWER OTHi;.R STATUS OISCOVERV OISCOVERV DESCRIPTION

~ Llli- 10 17 15 I I.,.,.__N_,,./-.A"---*-.,.-!I l£.J N/A 7 0 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

[ili]8 7

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9

~10 I~11,.------"----44~

N/A I I N/A 4""5=--------------------~80 I

• PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION

~I 1 sg 0 I 0 I 011I LU 12 I1~3------'-'--------------------------~aa~

. N/A j PERSONNEL INJURIES NUMBER DESCRIPTION GE)IO 10101 NA 7 8 9 h 12 80 OFFSITE CONSEQUENCES fiT511 * . N/A

~9 .

LOSS OR DAMAGE TO FACILITY l' la!~

TVP OESCRIPTION p . ~o N/A PUBLICITY G]l]"=---------------------'.:..r-=-----------------------------------------~

7 89 so AOOITIONAL FACTORS (I]!]I EVENT & CAUSE DESCRIPTIONS Continued on Page 2 I 7 8 9 so l!lil':'-----------------------------------------------------------------~

7 8 9 so NAME: _ _ _ _ _..;;.A;;..";;....._w.;..;_~-K_a_p p_l_e~------

__ PHONE: (609) 365-7000 Ext.Salem-62:

Licensed Event Report 77-18/3L Page 2 ~

EVENT DESCRIPTION (Continued)

• 1

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• l Phase III testing. Component replacement will be made if problem reoccurs with any specific component. This is the second occurrence of this type for Channel IV. (77-18/3L)

CAUSE DESCRIPTION (Continued)

Protection channel is manufactured by Hagen Controls.