ML18093A213

LER 87-008-00:on 870603,failure to Take Vibration Measurements Required by Inservice Testing (IST) Program Discovered.Caused by Inadequate Upgrade of IST Surveillance Procedures.Procedures Will Be revised.W/870702 Ltr

ML18093A213
Person / Time
Site:	Salem
Issue date:	07/02/1987
From:	Pollack M, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-008-02, LER-87-8-2, NUDOCS 8707110019
Download: ML18093A213 (5)

Text

. )* ,. __ ; * "'I

• NllC Far111

• U.I. NUCLEAR REQULATOllY -OVED OMI N0. 3190-0104 LICENSEE EVENT REPORT (LER) llACILITY NAME C1I I DOCKET NUMIEll CZI I .. ,.,.., 1o11 Salem Generating Station -Unit 1 0 I 5 I 0 I 0 I 0 12 I 71 2 1 I OF a 14 TITLE "I Failure to Implement Portions of the Inservice Testinq (IST) Proqram EVENT DATE 1111 LER NUMBER Hll REl'ORT DATE 171 OTHEll FACILITIES INVOLVED Cl) MONTH QAY YEAR YEAR Wt MONTH DAV VEAR F4CILITV NAMES DOCKET NUMBERISI 01s1010101 I I al6 a I 3 3 17 al ala -ala a I 1 a '2 ah 8 7 01S1010101 I I Ol'liRATING MODI! Ill THll REPOllT 11 IUIMITTED PURIUANT TD THE llEQUlllEMENTI OF 10 CFll §: /Chd one or mOIW of 1111 followin11J 1111 2U02Cbl ZD.408Ccl llG.73C.llZIUwl llG.73C.IC21M llG.73C.ICZIClrlll ll0.73C.IC211wlllllAI llG.73C.IC211wtHICll llG.731*1C21Cxl 73.7111>1 73.711*1 --llG.aCclC11

--llG.alclCZI

--ll0.73C.IC2IOI

-llG.73C.ICZICHI

--ll0.73C.ICZllHIJ LICENSEE CONTACT FOR THll LEA C1ZI NAME AREA CODE -OTHER ($olt:lfy in Ablwet -below ond In Toxt, NRC Form 366AI TELEPHONE NUMBER M. J. Pollack -LER Coordinator 6 I a 19 3 13 19 I -14 I a I 2 12 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRllED IN THll REl'OllT 1131 MANUFAC:.

TUR ER CAUSE SYSTEM COMPONENT I I I I I I I I I I I I I I IUP'PLEMENTAL REPORT EX,ECTED 11" I YES (If yll, ""'"Pi.to EXPECTED SUBMISSION DATE/ AUTRACT (l.imit ID 1400 _.,, i.o., 1ppra*im1r.ly fiftHn ringl**ll>>C*

ry-itton /ina/ 11111 I I I I I I I I MANUFAC* TUR ER I I I I I I EXPECTED SUBMISSION DATE 1151 MONTH DAV I I I On. June 3, 1987, while preparing a general pump trending program using existing data,* it was discovered that vibration measurements, required by the IST Program, on the Diesel Generator (D/G) Fuel Oil Transfer Pumps and D/G Lube Oil Pre-Circ Pumps have not been taken. This is contrary to PSE&G commitments made to the Nuclear Regulatory Commission in 1984 and the Technical Specification IST program surveillance requirement as detailed in Technical Specification 4.0.5. The root cause of the event has been attributed to inadequate upgrade of the IST surveillance procedures.

The requirement for vibration monitoring was inadvertently left out of the surveillance the subject pumps when these procedur:es were upgraded to conform with the IST Program. The vibration monitoring surveillance requirement will be added to the applicable surveillance procedures upon completion of the accumulation of base line data.

• This data will include measurement frequency, measurement location and allowable vibration limits. NRC Fann* IM31 a7o71ioo19 970702 PDR ADOCK 05000272 S PDR . *-_:

..... .. -:;_ . . . ..... : ....

. ' . \ . ,*_* )* *' .:: ...... , '. ** .. :: . . *--**.*. ':., .. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 87-008-00 PAGE 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

• IDENTIFICATION OF OCCURRENCE:

Failure to Implement Portions of the Inservice Testing (IST) Program Discovery Date: 06/03/87 Report Date: 07/02/87 This report was initiated by Incident Report No.87-210 CONDITIONS PRIOR TO OCCURRENCE:

N/A DESCRIPTION OF OCCURRENCE:

On June 3, 1987, while preparing a general pump trending program using existing data, it was discovered that vibration measurements, required by the IST Program, on the Diesel Generator (D/G) Fuel Oil Transfer Pumps and*D/G Lube Oil Pre-Circ Pumps have not been taken. This is contrary to PSE&G commitments made to the Nuclear Regulatory Commission in 1984 and the Technical Specification IST program surveillance requirement as detailed in Technical Specification 4.0.5. Technical Specification Surveillance Requirement

4.0.5 states

nsurveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows: a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by HJ CFR 50, Section 50. 55 (g) , except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55(g) (6) (i).a The NRC Safety Evaluation of April 12, 1983 requires safety related pumps and valves in the Emergency Diesel Generator Auxiliary Systems to be included in the IST Program. Commitments made to the NRC in 1984 which included the requirements of the NRC safety evaluation, were made part of the IST Program Manual (as of April 1, 1984), for both Salem Unit 1 and Salem-Unit 2. These commitments included requirements for vibration measurements for the pumps in question.

!

• ' ... -* ... , . . .. . . ...... *.-** ... :: *. ' ............. . -.. . . ...

' .. '* * *' ** ** * \I.... * '** * * * *

• LICENSEE EVENT REPORT (LER) TEXT.CONTINUATION Salem Generating Station Unit 1 APPARENT CAUSE OF OCCURRENCE:

DOCKET NUMBER Sf/Jf/Jf/J272 LER NUMBER 87-f/Jf/J8-f/Jf/J PAGE 3 of 4 The root cause of the event has been attributed to inadequate upgrade of the IST surveillance procedures.

The requirement for vibration monitoring was inadvertently left out of the surveillance procedures for the subject pumps when these procedures were upgraded to conform with the IST Program. LER 272/86-f/Jf/J2-f/J0 identified several deficiencies (involving inadequate testing of certain valves) in the implementation of the IST program. As part of the Corrective Actions to LER 272/86-f/J02-llJllJ, the admi.nistration of the IST Program was reviewed and revised accordingly.

The program was organized into one document, n1sT Program Manualn. In preparing this manual, those testing deficiencies not previously identified were addressed.

These deficiencies included vibration monitoring of the pumps specified in this LER. However, the pump vibration monitoring was not included in the surveillance procedures.

ANALYSIS OF OCCURRENCE:

The two (2) D/G Fuel Oil Transfer Pumps are used to.supply the Day Tanks with fuel oil. To ensure continued acceptable pump operation and to detect degradation, surveillance has been performed every 91/J days as per the IST Program. The parameters monitored include pump flow and differential pressure.

However, as identified by this LER, vibration monitoring has-not been performed since first committed in 1984. Those parameters which have be.en monitored make it unlikely that a pump problem would go undetected even though vibration monitoring has not been performed.

Additionally, these pumps are lf/Jf/J% redundant of each other. The three (3) Diesel Generator Lube Oil Pre-Circ Pumps (one per D/G) are used to circulate-oil to a heater and to engine parts. The coating of the parts with heated oil prevents unnecessary wear of engine parts. This helps to ensure the D/G's meet their design criteria as specified in the Technical Specifications (start in 11/J seconds).

Also, the pumps supplement the main shaft driven Lube Oil Pump(s) if main engine lube oil pressure falls below 60 psi. As addressed by OD-12 nTech Spec Interpretationsn, a D/G is not identified as inoperable if its Pre-Circ Pump is inoperable.

The D/G would be run periodically and the oil temperature would be closely monitored to ensure the D/G's operation when needed, as specified in OD-12. To ensure proper operation of the pumps, surveillance monitoring includes lube oil pressure, lube oil temperature and vibration monitoring.

As identified by this LER, vibration monitoring has not been performed since first committed in 1984. However, the temperature and pressure monitoring were performed as required.

This would make it unlikely that a pump problem would go undetected.

Any two D/G's and their associated vital busses ca:n supply sufficient power for operation-of-required safeguards equipment for a design basis loss-of-coolant accident (LOCA) coincident with a loss of

. *: ... * * ** :!..* .':* ...... -. . .. ... ... ** . *. " .. : .. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit l DOCKET NUMBER SfiHHJ272 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 87-008-00 . .. --*. -.. .'* .. . . PAGE 4 of 4 offsite power. It is unlikely any D/G would be inoperable due to low main engine lube oil pressure due to both its main shaft pump and its associated Lube Oil Pre-Circ Pump not operating as required.

CORRECTIVE ACTION: The vibration monitoring surveillance requirement will be added to the applicable surveillance procedures upon completion of the accumulation of base line data. This data will include measurement frequency, measurement location and allowable vibration limits. A special audit of the IST Program is not necessary due to the 1986 programmatic review (required when the IST Manual was put together) and comprehensive Quality Assurance audit {which stressed valve testing requirements) of the IST Program conducted in 1986 (as addressed by LER 272/86-002*-00).

Additionally, during the recent preparation of the pump trending program, the pumps specified in the IST Program were reviewed.

No other pump surveillance concerns were identified.

Therefore, additional programmatic discrepancies are considered unlikely.

The routinely scheduled Quality Assurance audits are considered adequate.

• MJP:pc SORC Mtg.87-049 .

GeneJ:

-Salem Operations

. ' ' . \ . **** ;. : J" * *' -'** ***. ** .. *

• e OPSIIBG */ Pub I ic Service Electric and Gas Company P .0. Box E Haricocks Bridge, New Jersey 08038 / Salem Generating Station July 02, 1987 u. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 87-008-00 . .. . *. This Licensee Event Report is being submitted pursuant to the requirements of 10CFR 50.73(a) (2) (i). This report is required within thirty (30) days of discovery.

MJP:pc Distribution The Energy People Sincerely

yours, General Salem Operations 95-2189 {1 i M) 12-84