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 Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-026, LER-90-26, NUDOCS 9010230162
Download: ML18095A527 (7)

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" OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 10, 1990 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 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 10CFR 50.73.

Sincerely yours, S. LaBruna General Manager -

Salem Operations MJP:pc Distribution t -. 9(11010 -

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• LICENSEE EVENT REPORT (LER) EXPIRES: l/JllW OOCKET NUM9Ell 121 I ..,.,H Ill!

I P:ACI LITY NAME Ill Salem Generating Station - Unit 1 o 1s 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 SE~~~~~~AL tt ~~~~ MONTH DAV YEAR FACI LITV NAMEll DOCKET NUMBERCSI Salem - Unit 2 o t s t o t o 1o I 3 11 t 1 o 19 ol 6 9 o 9 jo - d 216 - ol 1 1 lo 11 o 9 Io THll REPORT II IUBMITTED PURIUANT TO THE REQUIREMENTI OF 10 CFll §: (Ch<<:lc ont or,,,_ of lilt followfn1J CUI OPERATING I -

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~NO SUBMl$SION r--, YES (If ya, comp/ti. EXPECTED SUBMl~ION DATE/ DATE 1161 I I I AaSTRACT ILim/r ft> 1400 _,,.,, l.1.. *pproxlmti.ly fifi.tn rlngl**IPI** ryptwrlti.n /inn/ 11111 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 10CFR 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

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 90-026-01 2 of 6 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor 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 10CFR 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 DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 90-026-01 3 of 6 DESCRIPTION OF OCCURRENCE: (cont'd}

. COMPONENT DATE CONCERN Unit 2 No. 24 6/11/90 Service Water (SW} System fBI} minor leakage Containment from motor cooler Fan Coil Unit (CFCU) (BKf Technical Specification Applicability:

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.

Unit 1 12B 7/02/90 Inlet flange weld cracked; SW leak (SW Component side) of approximately 15 gpm cooling (CC) Heat Exchanger (CC}

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 Auxiliary minor pipe leak 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 DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 90-026-01 4 of 6 DESCRIPTION OF OCCURRENCE: (cont'd)

COMPONENT DATE CONCERN 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 7/28/90 SW Casing leak (leakage drains to the sump Pump 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 Thru wall minor SW leak at P-3 connection valve (12 CFCU Valve was tagged out at time of discovery Flow Tap Valve)

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 9/06/90 The outlet SW pipe developed a through wall Charging Pump pipe leak Room Cooler 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

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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 DATE OF REPAIR REPAIR 24 CFCU 6/11/90 Affected tube was plugged 12B CC Heat 7/05/90 Piping repaired per Code (reference DR No.

Exchanger SMD 90-213)

1. 2 AFW Room 7/10/90 Piping repaired per Code (reference DR No.

Cooler SMD 90-214)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE

• Unit 1 5000272 90-026-01 6 of 6 CORRECTIVE ACTION: (cont'd)

COMPONENT DATE OF REPAIR REPAIR 14 CFCU 8/04/90 Piping repaired per Code (reference DR No.

(14SW223} SMD 90-228) 21 &: 22 Chil- Piping will be repaired per Code (reference lers 4" Supply DR No. SMD 90-233)

Line 11 SW Pump 8/17/90 Damaged discharge head replaced per Code 12SW74 valve 8/16/90 Piping repaired per Code (reference DR No.

SMD 90-236) 2MS57 Check.* 8/17/90 Replaced valve as per Code (reference DR No.

SMD 90-247)

1. 12 Charging 9/12/90 Piping* repaired per Code (reference DR No.

Pump Room SMD 90-258)

Cooler 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