ML18095A471

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LER 90-026-00:several Occurrences of ASME Code 3 Piping Leakage Occurred Starting on 900611.Caused by Equipment Failure.All Affected Components Repaired Per ASME Code. W/900906 Ltr
ML18095A471
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/06/1990
From: Miller L, Pollack M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-026-01, LER-90-26-1, NUDOCS 9009180126
Download: ML18095A471 (7)
v • d • e


Text

Public Service Electric_ and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08-038 Salem GenEiJrating Station September 6, 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 LICENSEE EVENT REPORT 90-026-00 This Licensee Event Report is being submitted as a voluntary LER pursuant to the Code of Federal Regulations 10CFR 50.73. It addresses several occurrences of ASME Code 3 piping leakage.

Sincerely yours, L. K. Miller General Manager -

Salem Operations MJP:pc Distribution 9009180126 900906 PDR ADOCK 05000272 S PDC The Energy People 95-2189 (10M) 12-89

  • , e- U.I. NUCLEAll llEOU\.ATOllV ~-ION Al'l"f!OVED OMI NQ. l1ll0--01CM EXPIRES: 11311'i15 LICENSEE EVENT REPORT ILERJ FACILITY NAME C11 DOCKET NUMeEll 121 I r-~~ 1;i11

, Salem Generating Station - Unit l o 15 Io Io Io 1217 12 1 !oF 016 TITLE l'I ASME Code 3 piping leakage due to equipment failure

'

EVENT DATE CBI LER NUMBER 1111 REl'ORT DATE 171 OTHER FACILITIES INVOLVED Cll MONTH DAV YEAR VEAR rt SE~~~~~~AL 1x ~t':i?.: MONTH DAY YEAR FACILITY NAMEI DOCKET NUMBERISI Salem Unit 2 o I s I o I o' I o13 i1 ~

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1-- l>>low *nd In TOltt, NRC Form ll0.73_111121111

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LICENSEE CONTACT FOR THll LEA 1121 llO.73(11121MU1111 ll0.731111211*1 Voluntary TELEPHONE NUMBER AREA CODE M. J. Pollack - LER coordinator COMPLETE.ONE LINE FOR EACH COMPONENT FAILURE DEICRllED IN THll llEl'ORT 1131 CAUSE SYSTEM COMPONENT MANUFAC. SYSTEM MANUFAC.

TUR ER 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 IUPPLEMENTAL REPORT EXPECTED 11'1 MONTH DAY Y&lAR EXPECTED

~NO SUISM1$SION

--i YES (If yn, compl*rt EXPECTEO SVBMISSION OA TEI DATE 1151 I I I AalTRACT (Limit to 14()() ~.,. I.*.* *pproxlm*rtly fif!Hn r/ng/Hpoco rypowrlmn /inn} (181 This Licensee Event Report (LER) addresses several occurrences of ASHE Code 3 *piping leakage. Based upon discussion with the Nuclear Regulatory Commission (NRC) notifications were made within four (4) hours 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). The root cause of the listed ASHE 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 ASHE code for Class Code III components. The requirements of the Technical Specifications were complied with in all cases.

NRC Form 3118 19-1131

  • .a
    • . . . -

LICENSEE EVENT REPORT (LER).TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER.NUMBER PAG~

Unit 1 5000272 90-026-00 2 of 6.

PLANT AND SYSTEM IDENTIFICATION:

wes~inghouse ~re~su~ized Water ~eactor Energy*Industry Identification System* (EIIS) codes. are.identified* in the text as {xxl

. IDENTIFICATION OF OCCURRENCE:.

ASME Code III piping ieakage caused by equipment failure

. *Event Date:.. See Table in Descripti_on of Occurrence Section Report Date: :9/06/90

-' .

This report was initiated by Incid~nt Report Nos.90-388, 90-456,

- 9~~463~ 90-~12,90-517, 90-531,90-540, and 90-585.

CONDITIONS PRIOR. TO OCCURRENCE:.

N/~

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 within four (4) hours of each.occurrence.- This was done as agreed in accordance with*

tode 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 wit;h . . The Salem Unit 1 and Unit 2 Technical*Specification for-"Structural Integrity" are identical except for their number

( i . e * , 3

  • 4
  • 1 O
  • 1 vs . 3
  • 4
  • 11 . 1)
  • ~The. structural integrity of ASME Code* Class 1, 2 and_ 3 components* shall be maintained.in accordance with Specification
4. 4 .10 .1. -

"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 c.omponents/piping include:*

I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION I

  • salem Generating Station DOCKET NUMBER LER NUMBER PAGE--

u__n_i_t-=1'----~~~~-*~-"--~~~~~--=5~0~0~0~2~7~2=--~~~~9~0~--0=-=26~00"'-~~~~3--=o=f'---=6~*--'--

DESCRIPTioN-oF*OCCURRENCE: (cont'd)

COMPONENT. - CONCERN

. Unit 2. No. 24 6/11/90 Service Water (SW) System {Bii minor leakage Containment . from motor cooler_ *

  • Fan Coil Unit (CFCU) {BKI*

Technical Specification Applicability:

No. 24 CFCU leakage was identified with the Unit in Mode-4; CFGUs *are required to be operable in Modes l, 2, and 3. **

Therefore, *the Technical Spec::ification Action Statement for inoperable CFCUs did not a~ply. -

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

-Exchanger {CC I 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 wi.thin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."

Unit 2 #2 7/05/90 2".inlet SW pipe developed through wall-

. A\utiliary 'minor pipe leak Feedwater {AFW)

Room Cooler {VFI Technical Specification Applicability:

The room coolers are not identified in Technical Specifications; however internal procedural requirements which address the operability of equipment,- in the room served by the cooler, were met.

Unit 1 14 7/23/90 Thru wall SW leak CFCU downstream side of the 14SW223 valve Technical Specification Applicability:

e- e*

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 90-026-00 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

.

CFCU~

.

did not .apply.-**

Unit 2 21 7/23/90 T~ru wall, minor SW leak

& 22 Chillers

. {KM}* 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 SU:mP 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 ~re required to be operable in Mo4es 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.

APPARENT CAUSE OF OCCURRENCE:

' -

The root cause of the listed. ASME Code III component leakage has been

. a*ttributed to equipment failure. The above listed component leaks were the result of erosion/corrosion factors.

ANALYSIS OF OCCURRENCE:

' '

The ASME Class Code II! 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

~* .

LICENSEE EVENT.REPORT (LER) TEXT CONTIN'UATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 9_0-026-00 5 of 6.

. ANALYSIS OF OCCURRENCE: (cont'd) significantly affect the capability to m~tigate the .consequences of a

. design base a~cident since the CFCU's are 100% redundant* to the Containment Spray System (which was-operable at the time of the*

everits).

  • An increase in Containment Stimp_inleakage is th~ 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 actioris to idehtify, is6late, and. repair the leak~ Performance of an
  • RCS water inventory balance in ~onjunction with a containment entry to loc~te the source of the inieakage is the appropriate a*c..tion. .

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 :boron. concentration, chloride* concentration, and

  • pH. levels. *

. ,

. .

The components which exhibited leakage were declared inoperable .in accordance with.Technical Specifications. The components were not

. declared operable until complet:lon of repairs, w:nich 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 affect~d 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 7/05/96 Piping repaired per Code (reference DR Nb.

Exchanger SMD 90-213)'

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

Cooler

  • SMD 90-214) 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

LICENSEE' EVENT REPORT *(LER) TEXT CONTINUATION S-alem Generating* Station DOCKET NUMBER LER NUMBER PAGE

~U=n=i~t'----=1:.,-_~~~~~~~'----~~~~----=5~0~0~0~2~7~2=---~~~~9=-=0_-~026-00~--~~~-=6~-=o=f~-~6c___.c._

CORRECTIVE ACTION: (cont'd)

COMPONENT .DATE OF REPAI:R REPAIR ll_SW Pump 8111190 Damaged discharge head replaced per Code 12SW74 valve - 8/16/90 Piping repaired per code _-(reference DR No.

- v' SMD 90-236) 2MS57 Check 8/17/90

)

Replaced_valve as per Code (reference DR No.

SMD 90-247)

  • .*. . :;:;: ~

..

General Manager*_

Salem Operations MJP:pc SORCMtg.90-123

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