ML18012A787

LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr

ML18012A787
Person / Time
Site:	Harris
Issue date:	05/19/1997
From:	Donahue J, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-97-111, LER-97-010, LER-97-10, NUDOCS 9705270290
Download: ML18012A787 (5)

Text

C2tTEGORY 1 REGULATORY INFO%CATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9705270290 DOC.DATE: 97/05/19 NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VERRILLI,M.

Carolina Power 6 Light Co.DONAHUE,J.W.

Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET t 05000400

SUBJECT:

LER 97-010-00:on 970418,design deficiency determined re reactor coolant pump motor oil collection sys.Caused by RCP OCS design detail.RCP OCS enclosures for each of three installed RCP motors have been modified.W/970519 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR

)ENCL t SIZE: TITLE: 50.73/50;9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.C E 05000400 RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES RECIPIENT LTTR ENCL.ID CODE/NAME 1 1 ROONEY,V 1 AEOD/SPD/JAB 1~FME CENTER~1"RRR'/DEfEELB 1 NRR/DRCH/HHFB 1 NRR/DRCH/HOLB 1 NRR/DRPM/PECB 1 NRR/DSSA/SRXB 1 RGN2 FILE 01 1 1 LITCO BRYCEgJ H 1 1 NOAC QUEENER,DS 1 1 NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 D N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-.2083)

TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 Carolina Power 8 Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 MAY 1 9 997 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washirgton, DC 20555 Seriai: HNP-97-111 10CFR50.73 SHEARON HARMS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 97-'010-00 Sir or Madam: In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.

This report describes a design deficiency in the Oil Spill Protection System for the Reactor Coolant Pump motors.Sincerely, MV J.W.Do ahue Director of Site Operations Harris Plant Enclosure Mr.J.B.Brady (HNP Senior NRC Resident)Mr.L.A.Reyes (NRC Regional Administrator, Region II)Mr.N.B.Le (NRC-NRR Project Manager)+dan 97052702'i'705i9 PDR ADOCK 05000400 S PDR IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII State Road 1134 New Hill NC NHC FORM 366 f(.95)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED BY OMB NO.3150 0104 EXPIRES 04/30/99 ESTIMATED BURDEN PER RESPONSE TO COMPLY IT)TH THIS MANDATORY INFORMATION COHECTION REOUEST: 50.0 HRS.REPORTED LESSONS LEARNED ARE INCOR@ORAT(0 IN'TD THE LICENSING PROCESS AND fED BACK TO INDUSTRY.FORWARD COL(MENTS REGARDING BURDEN ESTIMATE TO THE INfORMAT)ON AND RECORDS MANAGEMENT BRANCH HB f33L US.NUClEAR REGUlATORY COMMISSION,')VASHINGTON, DC 20555000).

ANO TO THE PAPERWORK REDUCE)ON PROJECT l3150 OI OIL Off)CE Of MANAGEMENT AND BUDGET, WASHINGTON, OC 20503, FACILITY NAME (I)Harris Nuclear Plant Unit-1 DOCKET NUNIBER (3)50-400 PAGE (3)1 OF 3 TITLE (4)Design Deficiency

-Reactor Coolant Pump Motor Oil Collection System.MONTH OAY YEAR 18 97 EVENT DATE (5)LER NUMBER (6)SEQUENTIAL REVISION NUMBER NUMBER 97-010-00 MONTH OAY YEAR 19 REPORT DATE (7)FACiLITY NAI'IE FACILITY NAME OTHER FACILITIES INVOLVED (6)OOCKET NUMBER DOCKET NUMBER 05000 OPERATING MODE (9)POWER LEVEL (10)oor'0.2201(b) 20.2203(a)(1) 20.2203(BH2)(i) 20.2203(B)

(2)(v)20.2203(a)(3)(i) 20.2203(a)(3)(ii)50.73(e)(2)(i) 50.73(a)(2)(ii)

X 50 73(e)(2)(iii) 50.73(a)(2)(viii) 50.73(B)(2)(x) 73.71 r more)I1 1)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUiREMENTS OF 10 CFR 0: (Check one o 20.2203(e)(2)(ii)

~20.2203(a)

(2)(iii)20.2203(a)

(2)(iv)20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

LICENSEE CONTACT FOR THIS LER (12)50.73(B)(2)(iv) 50.73(B)(2)(v), 50.73(d)(2)(viU OTHER Specify in Abs((act below or in NRC Form 366A NAME Michael Verrilli Sr.Analyst-Licensing.

TELEPHONE NUMBER Iiirorrrde Ares Code)(919)362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONEN)'ANUFACTURER REPORTABLE TO NPROS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS SUPPLEMENTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SUBMISSION DATE).X No EXPECTED SUBMISSION DATE (15)MONTH OAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single.spaced typewritten lines)(16)On April 18, 1997, with the plant in Mode-6 (Refueling) for refueling outage 7, a walkdown performed by Harris Nuclear Plant (HNP)Engineering and Fire Protection personnel determined that the Reactor Coolant Pump motor Oil Collection System (OCS)did not meet applicable design requirements.

Specifically, a six inch wide gap exists in the OCS enclosure at the base of the upper lube oil cooler on each of the three installed Reactor Coolant Pump (RCP)motors, which could allow RCP oil to splash or spray out in the event of a lube oil cooler or lube oil piping leak.During subsequent investigation, additional design discrepancies were also identified and are described in the event description.

HNP Final Safety Analysis Report (FSAR)Section 9.5.1 states that the RCPs are equipped with an oil collection system that is designed and installed such that failure will not lead to a fire during normal and design basis accident conditions.

It also states that the system is capable of collecting oil from all potential pressurized and unpressurized leakage sites in the RCP lube oil systems.This design was established to meet the fire protection program requirements of NUREG-0800/NRC Branch Technical Position CMEB 9.5-1.The deficient RCP OCS enclosure does not satisfy these design requirements and is being reported per 10CFR50.73.a.2.iii as operation outside the design basis of the plant.C This condition was caused by inadequate RCP OCS design detail and a lack of knowledge on the part of HNP construction and start-up personnel regarding the design basis for the system, which allowed the OCS enclosures to be incorrectly fabricated during initial plant construction.

Corrective actions will include modifying the RCP OCS cnclosurcs for the installed RCPs to satisfy design requirements.

This will be completed prior to plant re-start from the current refueling outage.The spare RCP motor has been placed on hold and will be modified prior to use in the plant.

NRC FORM 366A I4.95)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGUULTORY COMMISSION FACILITY NAME II)Shearon Harris Nuclear Plant Unit//1 OOCKET 50 400 LER NUMBER (6)SEQUEN'rlAL REVISION NUMBER NUMBER 97-010-00 PAGE (3)2 OF 3 TEXT/II more spore is reevied, vse eddddroel oopr'es ol Ar'RC perm 3664/I)i)EVENT DESCRIPTION:

On April 18, 1997, with the plant in Mode-6 (Refueling) for refueling outage 7, a walkdown performed by Harris Nuclear Plant (HNP)Engineering and Fire Protection personnel determined that the Reactor Coolant Pump motor Oil Collection System (OCS, EIIS Code:AB-PSX) did not meet applicable design requirements.

Specifically, a six inch wide gap exists in the OCS enclosure at the base of the upper lube oil cooler on each of the three installed Reactor Coolant Pump (RCP)motors, which could allow RCP oil to splash or spray out in the event of a lube oil cooler or lube nil oiping leak.The deficient OCS enclosure was initially identified on the spare RCP motor located in a site warehouse prior to refueling outage 7 during preparations for replacing the"B" RCP motor.Following identification of the deficient condition on the spare motor, the above mentioned walkdown confirmed that the installed RCP motors also had the gap in the OCS enclosure.

Previous identification of this gap was made difficult due to the"B" RCP's physical location and lack of access to the aiea needed to observe the gap;Additional RCP OCS design discrepancies were also identified/confirmed during the April 18, 1996 walkdown.These included: (1)the lower oil pot drain valve pipe nipple which extends beyond the motor casing, thereby creating a leak path outside the OCS enclosure if drain valve leakage occurs, (2)the upper oil pot has an oil catcher with a drain line, which drains to the catch tanks.This drain line was found capped on 2 of three RCP motors, (3)The"B" RCP has several overhead fire protection sprinklers.

If activated, these sprinklers could spray enough water into the open upper OCS catch pans to fill the catch tanks, thus making them unavailable for containing oil.(This condition only applied to the"B" RCP motor where overhead fire protection sprinklers are provided to protect safety-related cable/conduit for the Pressurizer Power Operated Relief Valves)HNP Final Safety Analysis Report (FSAR)Section 9.5.1 states that the RCPs are equipped with an oil collection system that is designed and installed such that failure will not lead to a fire during normal and design basis accident conditions.

It also states that the system is capable of collecting oil from all potential pressurized and unpressurized leakage sites in the RCP lube oil systems.This design was established to meet the fire protection program requirements of NUREG-0800/NRC Branch Technical Position CMEB 9.5-1.The deficient RCP OCS enclosures do not satisfy these design requirements and are being reported per 10CFR50.73.a.2.iii as operation outside the design basis of the plant.CAUSE: This condition was caused by inadequate RCP OCS design detail, which allowed the system to be incorrectly fabricated during initial plant construction.

A factor that also contributed to the improperly constructed OCS enclosures was a lack of knowledge on the part of HNP construction and start-up personnel regarding the design basis for the system.SAFETY SIGNIFICANCE:

The were no actual safety consequences associated with this event.Each of the three RCP motors have operated for approximately 10 years with no major oil leaks.If a large oil leak had occurred in the upper lube oil cooler or the cooler supply piping, the deficient OCS enclosures could have allowed oil to leak or be sprayed on to hot components, potentially causing a fire in the containment building.This is being reported per 10CFR50.73.a.2.iii as operation outside the design basis of the plant.PREVIOUS SIMILAR EVENTS: There have been no previous HNP LERs related to a potential fire hazard caused by the RCP Oil Collection System.Tliere have been other industry RCP oil leak/oil fire events documented in NRC Information Notices 8<-09, 94-58 and INPO Operating Experience Entry 08123.Idowever, none of these events/conditions involved a gap in the RCP OCS enclosure that would allow RCP oil to create a potentia'.

fire hazard.

NRI EORM 366A (4.95)LICENSEE EVENT REPORT tLER)TEXT CONTINUATION U.S.NUCLEAR REGUUITORT COMMISSION EACILITT NAME (I)OOCKET LER NUMBER (6)PAGE(3)Shearon Harris NUclear Plant.Unit//'1 TEXT pl mort spsstis rttrrdtd, ost oddrrd)ooi sopas or ARC form 36SlU (IT)50400 sEOUENnAL RE)AS)ON NUMBER NUMBER 97-010-00 3 OF 3 CORRECTIVE ACTIONS COMPLETED:

1.The RCP OCS enclosures for the each of the three installed RCP motors have been modified/repaired to resolve the gap at the base of the upper lube oil cooler.This was completed on the"A" and"C" RCP motors during the current refueling outage (RFO 7).The"B" RCP OCS enclosure was corrected on the spare motor prior to RFO 7.The additional deficient conditions identified/confirmed during the April 18.1997 walkdown have been resolved with the except'.an of the"B" RCP motor upper ca:ch pans, which could potentially be filled with water from overhead fire pi~iection sprinklers.(reference planned action)erl below)These were completed on April 14, 1997.3.The old"B" RCP motor removed during RFO 7 has been plaE.d on hold pending completion of modifications on its OCS enclosure.

CORRECTIVE ACTIONS PLANNED: 1.The"B" RCP motor upper catch pans, which could potentially be filled with water from overhead fire.protection sprinklers, will be modified to resolve the concern: This will be completed per ESR b'97-00297 prior to plant re-start from the current refueling outage.0 iC AH)