ML18095A527

LER 90-026-01:on 900906,ASME Code 3 Piping Leakage Occurred Due to Equipment failure.W/901010 Ltr

ML18095A527
Person / Time
Site:	Salem
Issue date:	10/10/1990
From:	LABRUNA S, POLLACK M J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-026, LER-90-26, NUDOCS 9010230162
Download: ML18095A527 (7)

Text

" e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station 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 SUPPLEMENTAL LICENSEE EVENT REPORT 90-026-01 October 10, 1990 This Licensee Event Report supplement is being submitted to address an additional ASME Code 3 pipe leak discovered since the original issue of the LER. This is a voluntary report pursuant to the requirements of Code of Federal Regulations lOCFR 50.73. MJP:pc Distribution 1 t -. 9(11010 -on1n230 ADOCK ---PDC The Energy People Sincerely yours, S. LaBruna General Manager -Salem Operations 95-2189 (10M) 12-89

• NllC.._M_ U.S. NUCLEAll llEGULATOllY co.illDION -OVED C.. NO. 31111-0IOI LICENSEE EVENT REPORT (LER) EXPIRES: l/JllW P:ACI LITY NAME Ill Salem Generating Station -Unit 1 I OOCKET NUM9Ell 121 I .. ,.,H Ill! o 1 s Io Io tot 2 t 7 t 1 loF O I TITLE C'I ASME Code 3 Piping Leakage Caused By Equipment Failure EVENT DATE (Ill LER NUMBER Clll REPORT OATE 171 OTHER FACILITIES INVOLVED Ill MONTH QAY YEAR YEAR lt tt MONTH DAV YEAR FACI LITV NAMEll DOCKET NUMBERCSI Salem -Unit 2 o t s t o t o 1 o I 3 11 t 1 o 19 ol 6 9 o 9 jo -d 216 -ol 1 1 lo 11 o 9 I o OPERATING THll REPORT II IUBMITTED PURIUANT TO THE REQUIREMENTI OF 10 CFll §: (Ch<<:lc ont or,,,_ of lilt followfn1J CUI Z0.41111Ccl ll0,731olCZIClwl

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--Voluntary ll0.731oll21Cllll 1111:731011211.1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pollack -LER 6 jO I 9 3 I 31 9 1-1 21 0 12 t2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICRllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT I I I I I I I I MANUFAC TUR ER I I I I I I IUPPLEMENTAL REPORT EXPECTED 1141 r--, YES (If ya, comp/ti. EXPECTED DATE/ AaSTRACT ILim/r ft> 1400 _,,.,, l.1 .. *pproxlmti.ly fifi.tn rlngl**IPI**

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/inn/ 11111 SYSTEM I I -CO!o!PONENT MANUFAC TUR ER I I I I I I I I I I I I EXPECTED SUBMl$SION DATE 1161 MONT I I This Licensee Event Report (LER) addresses several 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 lOCFR 50.72. In all cases, Salem Unit 1 *Technical Specification 3.4.10.1 Action c and Salem Unit 2 Technical Specification 3.4.11.1 Action c were complied with. The Salem Unit 1 and Unit 2 Technical Specification for "Structural Integrity" are ideritical except for their number (i.e., 3.4.10.1 vs. 3.4.11.1).

The root cause of the listed ASME Code III component leakage has been attributed to equipment failure. -The component leaks were the result of erosion/corrosion factors. The components which exhibited leakage were declared inoperable in accordance with Technical Specifications.

The components were not declared operable until completion of repairs, which were done in accordance with the ASME code for Class Code III components.

The requirements of the Technical Specifications were complied with in all cases. An ongoing program, at Salem Generating Station, for the upgrade of Service Water System piping is continuing.

The scope and priotization of pipe replacement will be reviewed and mo9ified, as applicable, based upon the leaks identified in this report. NRCF-311 19-831 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 90-026-01 PAGE 2 of 6 Energy Industry Identification System (EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE:

ASME Code III piping leakage caused by equipment failure Event Date: See Table in Description of Occurrence Section Report Date: 10/10/90 This report was initiated by Incident Report Nos.90-388, 90-456,90-463, 90-512,90-517, 90-531,90-540, 90-585, and 90-657. CONDITIONS PRIOR TO OCCURRENCE:

N/A DESCRIPTION OF OCCURRENCE:

This Licensee Event Report (LER) addresses several 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 lOCFR 50.72. In all cases, Salem Unit 1 Technical Specification 3.4.10.1 Action c and Salem Unit 2 Technical Specification 3.4.11.1 Action c were complied with. The Salem Unit 1 and Unit 2 Technical Specification for "Structural Integrity" are identical except for their number (i.e., 3.4.10.1 vs. 3.4.11.1).

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:

• ) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 90-026-01 PAGE 3 of 6 DESCRIPTION OF OCCURRENCE: (cont'd} . COMPONENT DATE Unit 2 No. 24 6/11/90 Containment Fan Coil Unit (CFCU) (BKf CONCERN Service Water (SW} System fBI} minor leakage from motor cooler Technical Specification Applicability:

Unit 1 12B Component No. 24 CFCU leakage was identified with the Unit in Mode 4; CFCUs are required to be operable in Modes 1, 2, and 3. Therefore, the Technical Specification Action Statement for inoperable CFCUs did not apply. 7/02/90 cooling (CC) Heat Exchanger (CC} Inlet flange weld cracked; SW leak (SW side) of approximately 15 gpm Technical Specification 3.7.4.1 Applicable.

It states: "At least two independent service water loops shall be OPERABLE.

ACTION: With only one service water loop OPERABLE, restore at least two loops 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." Unit 2 12 7/05/90 2" inlet SW pipe developed through wall minor pipe leak Auxiliary Feedwater (AFW) Room Cooler {VF} Technical Specification Applicability:

The room coolers are not identified in Technical Specifications; however internal procedural requirements, which provide the administrative limits for being out of service, were met. Unit 1 14 7/23/90 Thru wall SW leak CFCU downstream side of the 14SW223 valve Technical Specification Applicability:

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DESCRIPTION OF OCCURRENCE:

COMPONENT DATE DOCKET NUMBER 5000272 (cont'd) CONCERN LER NUMBER 90-026-01 PAGE 4 of 6 No. 14 CFCU leakage was identified with the Unit in Mode 4; CFCUs are required to be operable in Modes 1, 2, and 3. Therefore, the Technical Specification Action Statement for inoperable CFCUs did not apply. Unit 2 21 7/23/90 Thru wall minor SW leak & 22 Chillers {KMJ 4" Supply Line Technical Specification Applicability:

None (other than 3.4.10.1)

Unit 1 11 SW Pump 7/28/90 SW Casing leak (leakage drains to the sump via a drain line) Technical Specification 3.7.4.1 applicable; however, the Unit was in Mode 5 during the period the No. 11 SW Pump was inoperable, therefore the Action Statement did not apply since the LCO is only applicable in Modes 1, 2, 3 and 4 Unit 1 12SW74 8/01/90 valve (12 CFCU Flow Tap Valve) Thru wall minor SW leak at P-3 connection Valve was tagged out at time of discovery Technical Specification Applicability:

No. 12 CFCU leakage was identified with the Unit in Mode 4; CFCUs are required to be operable in' Modes 1, 2, and 3. Therefore, the Technical Specification Action Statement for inoperable CFCUs did not apply. Unit 2 2MS57 8/14/90 Thru wall main steam (MS) leak at body of Check Valve valve for the MS & Turbine Bypass AFW Pump Drain Header Technical Specification Applicability:

None Unit 1 #12 Charging Pump Room Cooler 9/06/90 The outlet SW pipe developed a through wall pipe leak Technical Specification Applicability:

The room coolers are not identified in Technical Specifications; however internal procedural requirements, which provide the administrative limits for being out of service, were met.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE APPARENT CAUSE OF OCCURRENCE:

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

The ASME Class Code III components which exhibited leakage are located in the Auxiliary Building except for the CFCUs which are located in Containment.

The unavailability of one CFCU does not significantly affect the capability to mitigate the consequences of a design base accident since the CFCU's are 1DO% redundant to the Containment Spray System (which was operable at the time of the events). An increase in Containment Sump inleakage is the primary indication of the development of RCS or other system leakage. Continuous monitoring of the sump inleakage allow early detection of a potential problem and provides a basis for initiation of appropriate actions to identify, isolate, and repair the leak. Due to the small size of the CFCU SW leakage involved, had it remained undetected during a LOCA, it would have had negligible immediate impact on Containment Sump boron concentration, chloride concentration, and pH levels. Therefore, the CFCU SW leakage did not affect the health or safety of the public. The components which exhibited leakage were declared inoperable in accordance with Technical Specifications.

The components were not declared operable until completion of repairs, which were done in accordance with the ASME code for Class Code III components.

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 24 CFCU 12B CC Heat Exchanger

1. 2 AFW Room Cooler DATE OF REPAIR 6/11/90 7/05/90 7/10/90 REPAIR Affected tube was plugged Piping repaired per Code (reference DR No. SMD 90-213) Piping repaired per Code (reference DR No. SMD 90-214)

' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station *Unit 1 CORRECTIVE ACTION: (cont'd) COMPONENT 14 CFCU (14SW223}

21 &: 22 lers 4" Supply Line 11 SW Pump 12SW74 valve 2MS57 Check.* #12 Charging Pump Room Cooler DATE OF REPAIR 8/04/90 8/17/90 8/16/90 8/17/90 9/12/90 DOCKET NUMBER 5000272 REPAIR LER NUMBER 90-026-01 PAGE 6 of 6 Piping repaired per Code (reference DR No. SMD 90-228) Piping will be repaired per Code (reference DR No. SMD 90-233) Damaged discharge head replaced per Code Piping repaired per Code (reference DR No. SMD 90-236) Replaced valve as per Code (reference DR No. SMD 90-247) Piping* repaired per Code (reference DR No. SMD 90-258) An ongoing program, at Salem Generating Station, for the upgrade of Service Water System piping is continuing.

The scope and

• priotiz*tion of pipe replacement will be reviewed and modified, as applicable, based upon the leaks identified in this report. General Manager -Salem Operations MJP:pc *SORC Mtg.90-140