ML18095A765

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LER 91-002-00:on 910117,RHR Pump 11 Room Cooler Leakage Noted on Metal Weld of Inlet Control Valve.On 910124,leakage Noted on SI Pump Room Cooler & Auxiliary Feedwater Pump Cooler.Caused by Equipment failure.W/910220 Ltr
ML18095A765
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-91-002-02, LER-91-2-2, NUDOCS 9103040112
Download: ML18095A765 (6)
v • d • e


Text

OPS~G

  • l Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, 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-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 91-002-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (iv). This report is required to be issued within thirty (30) days of event discovery.

Sincerely yours,

~~J~tv-~---- L

s. LaBruna General Manager -

Salem Operations MJP:pc Distribution

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9103040112 910220 PDR ADOCK 05000272 S PDR The Energy People 95-2189 ( 1OM) 12-89

NRC Fa<m 3M 19-<131

  • LICENSEE EVENT REPORT (LER)
  • U.S. NUCLEAR REGULATORY COMMllllON APPROVED OMll NO. 31!50--0104 EXPIRES: 8131185 I

I FACILITY NAME 111 DOCKET NUMBER 121 P"u" 1.s1 Salem ~nerating Station - Unit 1 0 I 5 I 0 I 0 I 0 I 2 I 7 f2 I 1 OF 01 5 TITLE 141 ASME Code Class 3 Piping Leakage Caused By Equipment Failure EVENT DATE (81 LER NUMBER (81 REPORT DATE (71 OTHER FACILITIES INVOLVED (Ill MONTH QAY YEAR YEAR Jt SE~~~~~~AL It ~~'m.~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI o b. 1I1 9 1 ~ 1 ""'-- q ol 2 - ol o o 12 21 o 9 ~ o1s1010101 I I OPERATING THll REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS Of 10 CFR §: (Chock an* or maro of th* fallowing} (111 MOOE Ill 1 20.40!51cl l50.73loll2Hi*I 73.711bl l50.311(cll 1 I

- l50.73l*llZIM 73.71(cl

-- l50.381cl(21 80.73111121111

-- l50.731*1121Mll l50.731oll21MllllAI OTHER (Sf>>C/fy in Ab1tnct IH/aw *nd In T1xr. NRC Form 366AI

- 80.73(111211111 80.7311112111111 -

LICENSEE CONTACT FOR THIS LER 1121 l50.731oll21MllllBI 80.73(111211*1 Voluntary NAME TELEPHONE NUMBER AREA CODE M. J. pollack - LER Coordinator COMPLETE QNE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC- MANUFAC*

TURER SYSTEM COMPONENT 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 SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YjlAR EXPECTED

~NO SUBMISSION I YES l/f yn, campl*to EXPECTED SUBMISSION DA TEI DATE 1151 I I I AllSTRACT (Limlr ta 1400 1pocn, I.*** 1ppraxlm1toly fif!Hn 1ing/..,poce typowrirton /ino1J (1111 This Licensee Event Report (LER) addresses three (3) occurrences of ASME Code 3 piping leakage at dissimilar metal weld locations. Based upon discussion with the NRC, notifications were made for each occurrence as agreed in accordance with Code of Federal Regulations 10CFR 50.72. In all cases, Tech. Spec. 3.4.10.1 Action "c" was complied with. The root cause of the listed ASME Code component leakage has been attributed to equipment failure. The leaks are believed to be the result of galvanic corrosion at dissimilar metal weld sites. These welds were made. in 1983.as part of design changes which upgraded the Room Coolers. The "new" Room Cooler pipe (upstream and downstream) was type 316 stainless steel and was welded to the 0 existing SW pipe (carbon steel). The components which exhibited leakage were declared inoperable in accordance with Tech. Specs. 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 piping 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 early identification of SW leakage is continuing. This compliments routine Operations Department operator observation, of Room Cooler areas, performed each shift.

NRC Form 3M 19-831

Salem Generating Station

  • DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 . 5000272 91-002-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION:

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

ASME 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.91-050, 91-060, and 91-061.

CONDITIONS PRIOR TO OCCURRENCE:

N/A DESCRIPTION OF OCCURRENCE:

This Licensee Event Report (LER) addresses three (3) occurrences of ASME Code 3 piping leakage. Based upon disc.ussion 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 1 Technical Specification 3.4.10.1 Action c (as applicable) were complied with.

Salem Unit 1 Technical Specification 3.4.10.1 states:

"The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.

Salem Unit 1 Technical Specification 3.4.10.1 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 CONCERN No. 11 1/17/91 Service Water (SW) System {BIJ minor leakage; Residual Heat Through wall leak discovered on dissimilar Removal Pump (RHR) metal weld downstream of the SW inlet control (BA) Room Cooler {VF) valve for the Room Cooler;

Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 . 5000272 91-002-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd)

COMPONENT DATE CONCERN Discovered by System Engineering during the weekly SW System piping inspection Technical Specification Applicability:

The room cooler was declared inoperable. Subsequently, (as addressed by the Analysis of Occurrence section) the RHR Pump was declared inoperable and Technical Specification 3.5.2.c 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 />."

No. 13 Steam 1/24/91 SW System minor leakage; Through wall leak Driven Aux. discovered on dissimilar metal weld on Feedwater Pump {BAI piping spool 1-SW-2070A; Discovered by Room Cooler System Engineering during the weekly SW System piping inspection Technical Specification Applicability:

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.

To support pipe repair, the room cooler was declared inoperable. Subsequently, (as addressed by the Analysis of Occurrence section) the Aux. Feedwater Pump was declared inoperable and Technical Specification 3.7.1.2.b Action Statement "a" was applied (and* complied with). It states:

"With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps 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 at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."

No. 11 Safety 1/24/91 SW System minor leakage; Through wall leak Injection Pump on dissimilar metal weld on outlet pipe of Room Cooler Room Cooler; Discovered by System Engineering during the weekly SW System piping inspection

Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 91-002-00 4 of 5 DESCRIPTION OF OCCURRENCE: (cont'd)

Technical Specification Applicability:

Engineering assessment of the structural integrity of the affected piping was vigorously pursued; however, repairs of the affected piping were initiated and completed prior to completion of the assessment.

To support pipe repair, the room cooler was declared inoperable. Subsequently, (as addressed by the Analysis of Occurrence section) the Safety Injection Pump was declared inoperable and Technical Specification 3.5.2.b 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 />."

APPARENT CAUSE OF OCCURRENCE The root cause of the listed ASME Code component leakage has been attributed to equipment failure. The above listed leaks (at dissimilar metal weld sites) are believed to be the result of galvanic corrosion. The dissimilar metal welds were part of design changes (circa 1983) which involved an upgrade of the Room Coolers. As part of this upgrade, new Room Cooler pipe (upstream and downstream} (type 316 stainless steel) was welded to the existing SW pipe (carbon steel}.

The current program for SW System piping upgrade, addresses the concerns associated with known dissimilar metal welds.

ANALYSIS OF OCCURRENCE:

The room coolers, in conj~nction with the once through ventilation system, are designed to limit 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.

The ASME Code components which exhibited leakage are located in the 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 completion 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

~*

  • Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 91-002-00 5 of 5 ANALYSIS OF OCCURRENCE: (cont'd)

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 ASHE 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 No. 11 RHR 1/19/91 Piping repaired per Code (reference DR No.

Pump Room SMD 91-016)

Cooler SW Piping 13 Aux. Feed- 1/26/91 Piping repaired per Code (reference DR No.

Water Pump Room SMD 91-024)

Cooler SW Piping 11 SI Pump 1/26/91 Piping repaired per Code (reference DR No.

Room Cooler SMD 91-025A)

SW 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 saiem Unit 2 LER 311/90-042-00) to provide early identification of SW leakage is continuingo 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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