ML18095A766

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LER 91-003-00:on 910110,leakage Noted in Svc Water Sys Charging Pump 21 Cooler Piping.On 910130,leakage Noted in Svc Water Sys Charging Pump Cooler 22 Piping.Caused by Equipment Failure.Piping repaired.W/910220 Ltr
ML18095A766
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/20/1991
From: Labruna S, Pollack M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-003-01, LER-91-3-1, NUDOCS 9103040123
Download: ML18095A766 (5)
v • d • e


Text

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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bddge, New Jersey 08038 Salem Generating Station February 20, 1991 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 91-003-00 This Licensee Event Report is being submitted to address ASME Code pipe leaks. This is a voluntary report pursuant to the requirements of Code of Federal Regulations 10CFR 50.73.

Sincerely yours, S. LaBruna General Manager -

Salem Operations MJP:pc Distribution 9103640123 910220

~:DR ADOCK 05000311

-=- F'DR The Energy People 95-2189 (10M) 12-89

!ill1C Form 31111 19-831

  • LICENSEE EVENT REPORT (LER)
  • U.S. NUCLEAR REGULATORY COMMllllON Al"PROVED OMI NO. 311111-0ICM EXPIRES: 8/31185 FACILITY NAME 111 DOCKET NUMBER 121 I rAu~ 131 Salem Generating Station - Unit 2 o 15 I o Io I o 13 I 11 1 1 loF O14 TITLE C*I ASME Code Class 3 piping leakagec-:caused by equip~ent failure '

EVENT DATE (Ill LER NUMBER (81 REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH QAY YEAR YEAR lt SE~~~~~~AL tf ~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI OPERATING THiii REPORT 11 IUBMITTED PURSUANT TD THE REQUIREMENTI OF 10 CFR §: (Check on* or mo,. of th* fol/owin11J 1111

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- ll0.73(oll2lllll ll0.73C.ll21 Ulll ll0.73(oll2llwlllllll ll0.73loll211KJ Voluntary LICENSEE CONTACT FOR THIS LER 1121 NAME TE~EPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 6 1 0 19 3 1 3 I 9 1- I 2 I0 p. ~

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICRIBED IN THIS REPORT 1131

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CAUSE SYSTEM COMPONENT *MANUFAC. MANUFAC*

TUR ER 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 (1'1 EXPECTED n ~NO SUBMISSION DATE 1151 YES (If yn, compl*tl EXPECTED SUIMISSION DATE!

I I I AISTRACT (Limit ID 1400 ,,,...,, I.*.* *ppro*lm*toly f i ' - vn11l..,1>><0 ry1>>wrltton /inn} (181 This Licensee Event Report (LER} addresses two (2) occurrences of ASME Code 3* piping leakage. Based upon discussion with the Nuclear Regulatory Commission (NRC}, notifications were made for each

.occurrence as agreed in accordance with Code of Federal Regulations 10CFR 50.72. In all cases, Technical Specification 3.4.11.1 Action c was complied with.* The root cause of the listed ASME Code 3 component leakage has been attributed to equipment failure. The equipment failure component SW leaks were the result of erosion/corrosion factors. The components which exhibited leakage were declared inoperable in accordance with Technical Specifications and the appropriate Action Statements met .. The components were not declared operable until completion of repairs, which were done in accordance with the ASME code for Class Code components. An ongoing program, at Salem Generating Station, for the upgrade of Service Water System

_,P_iping is continuing. The scope and prioritization of pipe

-replacement and the need for additional inspections is being reviewed and modified, as applicable. A detailed weekly walkdown, by System Engineering, of Room Cooler SW pipe (initiated as per Salem Unit 2 LER 311/90-042-00) to provide ea.rly identification of SW leakage is continuing. This compliments routine Operations Department operator observation, of Room Cooler areas, performed each shift.

NRCF<<m-19-831

Salem Generating Station

  • DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 2 5000311 91-003-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE:

ASHE Code Class 3 piping leakage caused by equipment failure Event Date: See Table in Description of Occurrence Section Report Date: 2/20/91 This report was initiated by Incident Report Nos.91-025 and 91-073.

CONDITIONS PRIOR TO OCCURRENCE:

N/A DESCRIPTION OF OCCURRENCE:

This Licensee Event Report (LER) addresses two (2) occurrences of ASME Code 3 piping leakage. Based upon discussion with the Nuclear Regulatory Commission (NRC), notifications were made of each occurrence. This was done, as agreed, in accordance.with Code of Federal Regulations 10CFR 50.72.

In all cases, Salem Unit 2 Technical Specification 3.4.11.1 Action c (as applicable) were complied with.

Salem Unit 2 Technical Specification 3.4.11.1 states:

"The structural integrity of ASME Code Class 1, 2 and 3 components shall be ~aintained in accordance with Specification 4.4.11.1.

Salem Unit 2 Technical Specification 3. 4*.11.1 Action "c" states:

"With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service."

Identified leakage from ASME Class Code 3 components/piping include:

COMPONENT DATE CONCERN Unit 2 No. 21 1/10/91 Service Water (SW) System {BI} minor leakage Charging Pump (approximately 1 drop/5 minutes) on inlet

{BQI cooler piping piping to the Lube Oil Cooler, Gear Oil Cooler and Room Cooler {VFI; Discovered by Maintenance Department personnel I

'/

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

  • Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 91-003-00 3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd)

COMPONENT CONCERN Technical Specification Applicability:

To support pipe repair, the room cooler was declared inoperable. Subsequently, (as addressed by the Analysis of Occurrence section) the Charging Pump was declared inoperable and Technical Specification 3.5.2 Action Statement "a" was *applied (and complied with). It states:

"With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."

Unit 2 No. 22 1/30/91 Service Water (SW) System {Bil minor leakage Charging Pump on outlet piping to the Lube Oil Cooler and Cooler Piping Gear Oil Cooler; Discovered by System Engineering during the weekly SW System piping inspection Technical Specification Applicability:

The support pipe repair, the Room Cooler was declared inoperable. Subsequently, (as addressed by the Analysis of Occurrence section) the Charging Plimp was declared inoperable. Therefore, Technical Specification 3.5.2 Action Statement "a" was applied (and complied with).

APPARENT CAUSE OF OCCURRENCE The root cause of the listed ASME Code component leakage has been attributed to equipment failure. The above listed component leaks were the result of erosion/corrosion factors.

ANALYSIS OF OCCURRENCE:

The room coolers, in conjunction with the once through ventilation system, are designed to iimit the ambient temperature at vital pumping equipment. This helps assure long-term and reliable operation of the vital equipment. Based upon PSE&G Engineering Evaluation S-C-ABV-NEE-0504E, "Engineering Evaluation on the Effect An Inoperable Room Cooler Has on the Operability of Vital Pumps", operability of the vital pumps is affected by the availability of associated Room Coolers. Therefore, with a Room Cooler inoperable the vital pumps in that room are considered inoperable.

Engineering assessment of the structural integrity of the affected piping was vigorously pursued (i.e., radiographs taken); however, repairs of the affected piping were initiated and completed prior to completion of the assessment.

The ASME Code components which exhibited leakage are located in the

Salem Generating Station

  • DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 2 5000311 91-003-00 4 of 4 ANALYSIS OF OCCURRENCE: (cont'd)

Auxiliary Building. Applicable components were declared inoperable in accordance with Technical Specifications. They included components which either exhibited leakage or were made inoperable to support leakage repair. The affected components were not declared operable until compl~tion of repairs, which were done in accordance with the ASME code. The requirements of the Technical Specifications were complied with in all cases. Therefore, the events identified in this LER involved no undue risk to the health or safety of the public.

However, due to the concern that the NRC has expressed in regard to ASME Code component repairs (reference Generic Letter 90-05), these events are being reported as a "voluntary" LER in accordance with the guidance of NUREG 1022, "Licensee Event Report System".

CORRECTIVE ACTION:

In all cases, repair of the affected components was completed in accordance with the ASME Code. Specifically:

COMPONENT DATE OF REPAIR REPAIR 21 Charging 1/12/91 Piping repaired per Code (reference DR No.

Pump Area SW SMD 91-005)

Cooler Inlet Piping 22 Charging 1/31/91 Piping repaired per Code (reference DR No.

Pump Area SW SMD 91-028)

Cooler Inlet Piping An ongoing program, at Salem Generating Station, for the upgrade of Service Water System piping is continuing. The scope and prioritization of pipe replacement and the need for additional inspections is being reviewed and modified, as applicable.

The detailed weekly walkdown, by System Engineering, of Room Cooler SW pipe (initiated as per LER 311/90-042-00") to provide early identification of SW leakage is continuing. This compliments routine Operations.Department operator observation, of Room Cooler areas, performed each shift.

General Manager -

Salem Operations MJP:pc SORC Mtg.91-018

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