ML18095A474

LER 90-032-00:on 900809,inservice Testing Program Discovered Not in Compliance.Caused by Inadequate Administrative Control.Review of Administrative Controls for Compliance W/Surveillance Frequency Changes initiated.W/900907 Ltr

ML18095A474
Person / Time
Site:	Salem
Issue date:	09/07/1990
From:	Miller L, Pollack M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-032, LER-90-32, NUDOCS 9009180133
Download: ML18095A474 (6)

Text

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Public Service Electric an9 Gas Company P.O. Box 236, Hancocks Bridge, New Jersey 08038 Salem Generating Station Septeniber _7, 1990 U. s. Nuclear Regulatory Commission.

Document.Control Desk.

Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-7 5 -

DOC.KET _NO.* 50-311 *

• UNIT NO.* 2 LICENSEE EVENT REPORT 90-032-00 Th~s Libensee Event Report is being submitted:prirsuaiit to the requ~rements 6f the Code of Federal Regulations. 10CFR .*

50. 7 3 .(a) ( 2) ( i) ( B) .-

• This report is required within thirty ( 30) *days of discovery~

Sincerely yours,

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L. K. Miller General Manager -

Salem Operations MJP:pc Distribution

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I PACILITY NAME (II Salem.Generating station Un.it 2 O .I 51 O I 0 I O I 3 11 I l 1 !oF o J 5 TITLE l'I Tech. Spec. 4.!J.5 Noncompliance Due To Inadequate.Adininistrative Control EVENT DATE 1111 LER NUMB.ER 111 REPORT DATE 171 OTHEll FACILITIES INVOLVED Ill MONTH QAY YEAR . YEAR tt SE~~~~~~AL (j ~~~~?.: MOl\ITH_ DAY YEAR FACILITY NAMU . DOCKET NUMBERISI 01&1010101 I I 9 0

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.LICENSEE CONTACT FOR THIS LEll (121 NAME . TELEPHONE lllUMBER AREA CODE M. J. Pollack ~ LER Coordinator 61 0 19 313 19 I -:- 1 2 10 I 21 2 COMPLETE ON.E LINE FOR EACH COMPONENT FAILURE DEICRllED IN.THIS llEPORT 1131 CAUSE SYSTEM COMPOlllEl\IT SYSTEM COMPONENT MANUFAC.

TUR ER I I / I. I I I I . I I I I I I I I I I I I.* I I I I I I I I I IUPPLEMENTAL REPORT EXPECTED.114i MONTH

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~1110 SUBMISSION f 1 YES fit yn, com~11ro EXPECTED SUBMISSION DATE! .

DATE 1161 I I I AaaTRA_CT (l.lmlr ro 14QO 11/>>Cll, _l.1., ~pproxlm1toly flftoon 1/ngl**11MC* ty1>>wrlrron. /innl 11&1 On 8/9/90., it was discovered by Operations Department* p~rsonnel that the Ing~rvice ~esting (I~T) program, per Tech. Sp~c~ Surveillarice 4.0.5, had not been. complied with. The Nos. 21 Component Cooling (CC}.

Pump, 23 CC Pump and 26 Service Water (SW) Pump surveillance frequency had not been increased as.* per the IST Program resulting in a surveillance not being performed within the required time.frame. When a pump is placed in "alert", the interval between surveillances is halved. This was not done: for these pumps and consequently, a surveillance was missed. The cc Pumps were last surveilled on 5/6/90-thereby requiring the next surveillance to be completed on or before 7/2/~0. The 26SWPUmp was iast: surveilled on 6/7/90.thereby requirin~

• the next surveillance to be completed on or before 8/3/90. The root

• cause* of ihis event h~s beeri atiributed to inadequate administrative control. Contributing to the cause of the SW Pump.missed surveillance was.~ersonnel erro~. A srirveillance frequency chan~e form had not been initiated for the No. 26 SW Pump after its 6/7/90 surveillance. *The recurring tasks for the* cc Pumps and the SW Pump were corrected as required. The Nos. 21 and 23 CC Pumps were s.uccessfully surveilled on 8/9/90 and 8/11/90. Review of the administrative controls, wJ:iich ensure compliance with surveillance frequency changes, has beeri initiated. Until completion of thl.s review and implementation of

_programmatic modifications, interi~ procedural modifications.have been made. This event will be reviewed by Operations Departmerit management with applicable departmEmt personnel.

NRC Form 381 IM31

LIC~NSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating.Station DOCKET NUMBER LER NUMBER PAGE.

Unit 2 5000311: 90-032-00 . 2 of 5.

PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Indust;ry Identificatfon System (EIIS) codes are identified in the text a:s (xxl IDENTIFICATION OF OCCURRENCE:

Technical Specification. *4 ._O. 5- ( Inserv1ce Te~ti~g Surveillance Program) _noncompliance due to inadequate'administrative control Discovery

. ~ . Date:. 8/09/90 Report Date: 9/07/90 This- ~:eport was initiated by Incident Report Nos.90-562 and 90-580.

CONDITIONS . PRIOR* TO OCCURRENCE: .

. Mode 5 . (Cold ShutdoWn)

DESCRIPTION OF OCCURRENCE:

On August 9, 1990, it was* discovered by Operations Departmen_t.*

personnel that the Inservice 'resting (IST) pr:ogram, per Technical Specification Surveillance 4. 0. 5, had not been complied with. The .

Nos. 21 Component Cooling (CC) Pump,* 23 CC Pump and 26 Service .Water (SW) {Bii Pump surveilTance frequency had not been increased as per the IST Program resulting in a surveillance not* being performed; for thes~ .pumps, within the required*. time frame.

This surveillance noncompliance was discovered during performance of Integrated Operating Procedure IOP-2 ("Cold Shutdown To Hot Standby")

Check-Off-Sheet (COS} 1. It requires verification that components required to be operable in Mode 4 (Hot Shutdown) have .been surveilled within the time period specified in the IST Program.

When a puinp is placed in "alert" due* to surveillance results, the surveillance* frequency is'doubled. For the above three (3) pumps, the interval between surveillances should have been changed from every 92 days to every 46 days. However, the frequency was not changed and consequently, a surveillance was missed. The CC .Pumps were/last surveilled on May 6, 1990 thereby requiring the next '

surveillance to be completed on or before July 2, -1990. The Unit was in Mode 4 on July 2, 1990. The 26SW Pump was last. surveilled on June 7, 1990 thereby requiring the next surveillance to be completed on or before August 3, 1990. The Unit was.in Mode 5 on August 3, 1990.

Technical Specification Surveillance 4.0.5 States:

~"Sur~eillance Requirements for inservice inspection and testipg of ASME Code .Class 1, 2 and 3 components shall be applicable as

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LICENSEE EVENT.REPORT (LER) TEXT CONTINUATION*

Salem Generating Station DOCKET NUMBER LER NUMBER PAGE

. Unit 2. . 5000311 90:.:..032-00 ,* 3 of 5 .

DESCRIPTION OF OCCURRENCE: (cont'd}

foilows:

a.

• Inserviceinspection of ASME Code Class 1,.2 and~

c;:omponents and inservice testing of* ASME Code Class 1, 2 and 3 pumps and valves shall be performed in I

accordance with Section XI of the, -ASMB Boiler -- and I ;l?resslire Vessei Code and applicable.Addenda as i required by 10 CFR 50, Section .so.ssa(g), except where specific written relief has been granted by the Commission pursuant .to 10 CFR 50, Section 50.55a(g) <6> .

, I

.APPARENT CAUSE OF OCCURRENCE:

The root cause of this event has been attributed to inadequate administrative control.

'The system to modify surveillance frequencies, in place when the.CC.

Pumps and the SW.Pump were put in "a-lert", involved the use of Nuclear Department Administrative Procedure NC.NA-AP.zz...:.ooo9(Q) r '

"Work Control Process'". A form is provided"by this procedure to modify recurring task frequency. When a surveillance *frequency modification was required~, the original NC .NA-AP. zz_:0009 (Q) form would be sent to the Technical- Specification Coordinator with a copy forwarded *to Pl~nnirig. *. The Technical Specification Surveillance Co9rdinator was respons'ible to revise the recurring task frequency upon receipt of.a form ..

• Verification, by the department requesting the surveillance frequency change, to ensure that the change had been implemented was not req.uired.

Although a recurring task frequency modification form was initiated (as indicated from Operations Department records) for the CC Pumps, i t was not received by the Technical Specification Coordinator. '

• • .Subsequently, the surveillance frequency was not changed.

Contributing to the cause of the SW Pump missc!d ~urveillance was personnel error. Investigations revealed that a surveillance.

frequency change formhad not been initiated for the No. 26 SW Punip.

When .the pump was last surveilled, on June 7, 1990,* initial review by Operations personnel indicated that the pump had ,failed the *

• surveillance; however, further.review by System.Engineering resulted in the pump passing that surveillance (although i t was placed in "alert" status). * * *

.ANALYSIS OF OCCURRENCE:

The IST program is intended to.ensure the operational readiness of safety related valves and pumps. The CC Puinps and SW Pumps are part of this program ..

The Component.Cooling System is required to be operable in Modes l;

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

.. Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 90-032-00 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd)*

2, 3, and 4. Operability of the system ensures sufficient cooling capacity for continued operation of various safety related equipment during normal and accident.conditions. It is a closed loop system with two.(2) independent, parallel trains~ There are three (3) pumps, one for each train and the third is used as a backup.

The Nos. 21 and 23 cc Pumps were successfully surveilled on August 9, 1990 and August 11 .. 1990, respective1y. Therefore, during.the period*

in which the surveillance was overdue, these pumps were operable.

The SW System ensures sufficient cooli~g capacity for cont~nued operation of safety-related equipment during normal and accident conditions. The system consists of tw~ (2) cross connected headers (3 pumps per header) which provide redundant cooling capacity consistent with assumptions used in the Updated Final Safety Analysis Report*(UFSAR) analyzed acc~dent conditions.

• During the time period when the No. 26 SW-Pump surveillance was not.

completed in accordan~e with the IST Program, the other .five* (5) SW Pumps were operable. Therefore, both SW Headers were operable and capable of mitigating the consequences of a d~sign base accident.

Since the. SW headers and the CC Pumps were operable, this situation did not affect the health or safety of the public. However, since the requirements of Technical Specification 4.0.5 ~as not fully complied with, this event is reportable to the Nuclear Regulatory Commission in accordance with Code of Federal Regulations 10CFR

• 50.73(a) (2) (i) (B).

CORRECTIVE ACTION:

The recurring tasks for the CC Pumps and the SW Pump were corrected as required.

The Nos. 21 and 23 cc_ Pumps were successfully surveilled on.August 9, 1990 and August 11, 1990, respectively.

Review. of the administrative controls, which ensure compliance with surveillance frequency changes, has been initiated. Until completion of this review and implementation of programmatic modifications, interim procedural modifications have been made. These modifications include:

Revision of the 4.0.5-P surveillance procedures (for both Salem Units) clarifying the process by which recurring task frequencies are changed, as per NC.NA-AP.ZZ-0009(Q). _

Revision of Operational Directive Procedure OD-77, "Supervisor Routine Log", to require weekly verification (by the Shift Supervisor) that recurring tasks have been updated.

LICENSEE.EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 90-032-00 5 of 5 CORRECTIVE ACTION: (cont'd)

This*event will be.reviewed by Operations Department management with applicable department personnel.

General Manager -

Salem Operations MJP:pc SORC Mtg.90-124