ML20150F731

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Summary of NRC 880617 Interofc Meeting Re Industry Program & NRC Efforts to Address motor-operated Valve Performance. Agenda,List of Attendees & Viewgraphs Encl
ML20150F731
Person / Time
Issue date: 07/06/1988
From: Novak T
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Jordan E
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
References
NUDOCS 8807190022
Download: ML20150F731 (57)
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{{#Wiki_filter:'/ N UNITED STATES o$ i i. NUCLEAR REGULATORY COMMISSION ' s$ )~ WASHING TON, D. C. 20S56 \\,..... / JUL 0 61988 MEMORANDUM FOR: Edward L. Jordan, Director Office for Analysis and Evaluation of Operatinnal Data FROM: Thenas M. Nnvak, Director Division of Safety Programs Office for Analysis and Evaluation of Operational Da ta

SUBJECT:

NRC INTEROFFICE MEETING TO DISCUSS INDUSTRY PROGRAM AND NRC STAFF EFFORTS ADDRESSING MOTOR-0PERATED YALVE PERFORMANCE

REFERENCES:

1. USNRC, Menorandum from T. M. Novak to C. E. Rossi, et.

al., "Meeting to Discuss the Industry Progran and NRC Staff Efforts Addressing Motor-0perated Yalve Perfornance", May 16, 1988. ?. USNRC, Memorandum fron C. H. Berlinger to C. E. Rossi, "Divisicn Director Meeting to Discuss the Industry Progran and NRC Staff Efforts Addressing Motor-0perated Valve Performance", May 25, 1988. AEOD case study report C603 on motor operated valve performe.nce was issued 17 Decembar, 1986. Subsequently, the ED0 requested that NUMARC take the lead to establish indust.y iLitiatives to address notor oparated valve (MOV) performance and reliability problens and identified AEOD as the NRC point of contact for the industry effort. Since that time, AEOD/DSP has been rnonitoring the NUMARC effort. As suggested in reference 2, we asked NRR to arrange a meeting to discuss both NUMARC and NRC staff efforts on MOVs in order to coordinate the industry program with NRC issues. The moeting was held on June 17, 1988 in accordance with the agenda set by reference 2. is the meeting attendance list. is the meeting agenda. A copy of the discussion topics by each presenter in the sequance of the agenda is included as enclosures 3,4,5,6,7,8, and 9. The discussions brought out that r several staff efforts and the industry progran have aspects that interface each other and proposed actions should account for efforts in the different h prog rams. For example, the proposed extension of Bulletin 85-03, which is part of Generic Issue II.E.6.1, can be influenced by the Maintenance Program review of DLPQ and the industry programs coordinated by NUMARC. The broad range of issues identified by the agenda discussion topics clearly ) l indicates a need to coordinate the NRC staff and NUMARC efforts. I believe /) this was the concensus of meeting attendees. AE00 has been the contact for NUMARC and NRC staff coordination for a year and a half. DSP has served to monitor the initial NUMARC efforts conducted by INP0 and EPRI (NMAC). It r b $0N0 PNV

p jut.061988 3 Edward L. Jordan appears that both INP0 and NMAC will issue initial guidance documents this fall. and EPRI (NMACfrovide guidelines on elenents that constitute a good M0V progran INP0 plans to Y. will issue the Maintenance Guide for Limitorque SMB-000 operators. Thus, this seens to provide a logical transition point for overall coordination. We would plan to continue with OH-8 and NMAC. Therefore, we indicated that there is a need for management level responsibility to coordinate the MOV efforts by NUMARC/NRC and that one of the Progran Offices, preferably NRR, should assume the role. We believe this coordination role is an essential element to foster inplementation of thorough M0V programs at all operating plants. Original signed byi Thomas M. Novak Thomas M. Novak, Director Division of Safety Prograns Office for Analysis and Evaluation of Operational Data

Enclosure:

As stated cc w/o enclosures 3,4,5,6,7,8 and 9 T. E. Murley, NRR E. S. Beckiord, RES T. T. Martin, NRR D. Ross, RES B. K. Grines, NRR T. Speis, RES J. W. Roe, NRR G. Arlotto, RES C. E. Rossi, NRR W. Houston, RES L. Shao, NRR L. Spessard, AE0D M. Taylor, E00 Distribution A1.1 attendees (DCS CHel temes UPotapovs, NRR DSP R/F JTaylor JJankovich, NRR ROAB R/F JPartlow, EDO AGody, NRR EBrown ESullivan, NRR PDR MChiranal JHuang, NRR JRosenthal JVora, RES KBlack RBaer, RES MWillians GMillman, RES VBenaroya JNorberg, NRR Edordan WFarmar, RES \\N ROAB:DSP:AE0D ROAB:DSP:AE0D R0AW DSP:AE00 DSP:AE00 D: h3EBrown:ks MChiramalk JRo enthal VBenaroya vak 06/37/88 06/q/88 06/p/33 06/30/88 Of/f/88 f

' jb - '1 e' .s. ENCLOSURE 1 6/17 M0V ffEETING Nane Organization NTcKard J. Kiessel NRR/DOEA/0GCB cJin Richardson NRR/ DEST /EAD Tad Marsh NRR/ DEST /MEB Eileen~McKenna NRR/DLPQ/PEB Loren Plisco NRR/DLPQ/PEB Stephen Alexander NRR/DRIS/VIB Milton Vagins RES/DE/EMEB Owen Rothberg RES/DE/EIB Earl Brown AE0D/DSP/ROAB John Knox NRR/ DEST /SELB. Roy Woods RES/DRPS/RSPIB Frank Cherny RES/DE/EIB G. H. Weidenhamer RES/DE/E&MEB Bcb Bosnak RES/DE Carl H. Berlinger NRR/DOEA/0GCB J. E. Rosenthal AE00/DSP/R0AB Brian Grines NRR/DRIS W. Houston RES T. M. Novak AEOD/DSP s ? I A

,-v - 4 ^- - = .o .c l' ENCLOSURE 2 M0V MEETING AGENDA-a 9:00

f. M. Novak - Introdur. tory Remarks 9:15 R. J. 'Kiessel - Status of Bulletin 85-03, "Motor-0perated Valve Common Mode Failuras During Plant Transients Due to Improper Switch Settings" 9:30
0. O. Rothberg - Status of Generic Issue II.E.6, "In-Situ Testing of Valves" 9:45 G. H. Weidenhammer - Status of Generic Issue 87, "Failure of HPCI Steam Line Without Isolation" 10:00 E. M. McKenna - Maintenance Programs 10:30 E. J. Sullivan, Jr. - Inservice Testing Programs; 10 CFR 50.55a Rule Change; and EPRI Testing Task Group Efforts 11:00 E. J. Brown - NUMARC, INP0, and NMAC Efforts; ASME CM-8 Efforts 11:45 T. M. Novak - Program Coe,rdina tion Discussion 1

I r }

.7 =. ENCLOSURE 3 ~' 2 . T.11. Hovak NRC ACTIONS COORDINATE STAFF EFFORTS COORDINATE NUMARC/NRC EFFORTS PLANTS.lMPLEMENT THOROUGH MOV PROGRAM f d 4 I I L f F k h a 1 I ) F n,-- n ,n-. ,,n. ,:,.__,_,n,,,-,.,,,.. ., n e.- n._ ,-r., ,,. n - n,- c. v _ mn-n,-,, e.,,v,-, .-w,

i MOTOR OPERATED VALVE PEPFORMANCE INITIAL AE0D CONCERNS DOCUMENTED IN INITIAL CASE STUDY - 1982 DAVIS-BESSE IIT - AUGUST 1985 BULLETIN 85-03 ISSUED ON TESTINC 0F CAPTAIN MOVS GENERIC MOV STUDY REQUESTED BY ED0-AE0D CASE STUDY-ON MOV PERFORMANCE - DECEMBER 1986 ED0 REQUESTS NUMARC TO INITIATE MOV CORRECTIVE ACTION PROGRAM AE0D IDENTIFIED AS NRC CONTACT ACTIONS AS INDICATED IN AE0D/C603 MEETING FORMS BASIS FORM INDUSTRY INVOLVEMENT AND ACTION PLAN TO ADDRESS MOV PROBLEMS - SEPTEMBER 1987 SCOPE EXTENDED TO INCLUDE HYDRAULIC LOCKUP 0F MOVS - JANUARY 1988

I A AE0D/C603 RECOMMENDATIONS TO NUMARC IMPLEMENT RECOMMENDATIONS IN AE0D/C203 (1982) AND S503 (1985) METHODS AND PROCEDURES FOR SETTING TOROUE SWITCHES DEVELOP AND USE SIGNATURE TRACING TECHNIQUES ADDITIONAL ACTION ON IE CIRCULAR 77-07 (BYPASSING TOROUE SWITCH) REVIEW MOTOR BURNOUT, THERMAL OVERLOAD DEVICE USE DEVELOP PROCEDURES AND DIAGNOSTIC CAPABILITY TO DETERMINE ROOT CAUSE OF FAILURE DEVELOP STRONG TRAINING PROGRAM, INTERDISCIPLINARY EFFORT, SITE MANAGEMENT SUPPORT EXPAND SCOPE OF IE BULLETIN 85-03 !c

~' NRC M0V EFFORTS AEOD - POINT OF CONTACT WITH NUMARC - MONITOR INDUSTRY EFFORT (INP0 AND NMAC) OPERATING EVENTS - SPECI AL TASK ON HYDRAULIC LOCKUP WITH NUMARC NRR - DOEA FOLLOWUP 0F IEB 85-03 DEST INSERVICE TESTING (ASME SECT, XI) DRIS VEND 0R INSPECTIONS DLP0 MAINTENANCE PROGRAMS RES - DE GENRIC ISSUE 87 (ISOLATION VALVES), NPAR (EQUIPMENT AGING) DE OR (DSIR)? TMI ACTION ITEM ll,E 6 "INSITU TESTING OF VALVES"

~ y -s ~ a l NUMARC MOV PROGRAM INP0 HOLD INDUSTRY MOV WORKSHOPS AND INCORPORATES MOV EVALUATION IN PLANT-REVIEWS-EPRI - NMAC ADVISORY GROUP TO DEVELOP MOTORIZED VALVE REPAIR GUIDE (DUE APPIL 1988) AND APPLICATION GUIDE (DUE SEPTEMBER 1988) NRC PARTICIPATION IN INP0 EVALUATION NEED FOR REGULATORY ACTION CONTINUES UNDER REVIEW t

DJ & ENCLOSURE 4 /(, (,// y[ff-R. J. Kiessel

SUMMARY

OF BULLETIN 85-03 HISTORY Davis-Besse event on June 9, 1985 Valves originally aligned properly Erroneous operator action changed position of two valves Valves unable to be repositioned Pointed out need for recovery from inadvsttent valve operation NUREG-1154, "Loss of Main and Auxiliary reedweter Event at the Davis-Besse Plant on June 9, 1985," issued July 1985 Information Notice 85-50, "Complete Loss of Main and Auxiliary reedwater at the Davis-Besse Plant on June 9, 1985," issued July 8, 1985 Bulletin 85-03, "Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Se, tings," issued November 15, 1985 Bulletin 85-03, Supplement 1, issued Aprl! 27, 1988 Rerulted from inability to get BVR Owners' Group to address inadvertent valve operation Only applicable to DVRs Clearly stated requirement to consider inadvertent valve operation in determining the maximum diff rential pressure Eliminated limit to inservice testing program Provided revised schedule for any valves add d I L

o ~4 e..

SUMMARY

OF BULLETIN 85-03 REQUIREMENTS For all valves subject to inservice testing (10 CFR 50.55a(g)] in two high-pressure systems Determine the maximum design basis difforential pressure, incivding that from inadvertent operation Determine the motor-operator switch settings required for proper valve operation Ensure the motor-operator switches are set properly Test valve at maxiraum differential pressure Establish procedures to ensure that the motor-operator switch settings are maintained Consistent with Generic Letter 63-28 Program to be completed within 2 years Initial report to be submitted within 6 months identify valves and their maximum difforential pressures Describe program to meet bulletin criteria Provide schedule for completion of bulletin activities i Tinal report to be submitted within 60 days of completion Identify inoperable valves List pre-and post-bulletin switch settings

4 I f a

SUMMARY

OF BULLETIN 85-03 FINaf, REPORTS RECEIVED TO DATE 74 (out of 125) plants have submitted final reports Average of 24 valves per plant in program Msnimum -- LOL v a l v e s at Davis-Besse (includes all valves in safety-related systems) 8 valves at Dresden Units 2 and 3 and at Minimum Fort Calhoun Average of 1.5 valves per plant were inoperable 5.6 percent overall average Maximum - ,,,1) out of g (55.9 percent) valves at Arkansas Unit 1 32 plants (43 percent of plants reporting to date) have reported inoperable valves Average of 3.5 valves per plant 12.9 percent of the valves i l I l l

'EagePia. 1 06/15/88 e fit @L FEFORT STATUS OF IED 85-03 SLitVRY BY FL/NT t#tC AS CF June, 15, 1988 ( U 1E G tLtdE G PIMER TOTA. DWASS TOROLE LIMIT PU1EG PU1EE FG GNT UTILITY P U 1E G SWITCH SWITCH SWITCH OTHER ItOP It & FL/NT PVtE FEFLY Wt kES CWtCED OftED O-FNEED Dtetu.,is WLkES VA.kES fR7 TEAS 1 02/29/88 24 0 34 0 1 19 55.88 FR 7tCAS 2 02/09/88 41 0 39 0 0 11 26.83 ECA4 G VALLEY 1 04/10/08 24 0 0 0 0 0 0.00 ECA'ATt VfLLEY 2 07/31/87 16 7 10 0 11 0 0.00 Ef41DWOD 1 01/15/88 16 0 0 0 0 0 0.00 Ef@IDW OD 2 01/15/08 16 0 0 0 0 0 0.00 EfuG4IOC 1 05/25/08 25 0 0 0 0 0 0.Cc EROS 4IO: 2 05/25/08 26 0 0 0 0 0 0.CC BWOJ 1 01/15/08 16 2 0 0 0 0 0.00 BYFD4 2 01/15/88 16 5 0 0 0 0 0.00 CAL \\ERT O_IFFS 1 01/28/88 12 0 10 0 0 0 0.00 CA.tGT CLIFFS 2 01/28/88 12 0 3 0 0 0 0.CC CLItJTEN 1 03/02/87 23 14 12 6 20 0 0.00 CRGTA. RI(G 3 02/15/08 17 1 2 2 17 0 0.00 DAVIS-EESSE 1 04/22/87 165 26 0 19 164 17 10.30 DIAELO C/t#CN 1 09/14/87 27 0 19 0 0 0 0.00 DIAELO C4t#0N 2 C6/14/87 'Z/ 0 19 0 0 0 0.00 ITESDCN 2 01/15/88 0 0 6 0 0 1 12.50 DFESDEN 3 01/15/08 8 0 7 0 0 0 0.00 DLRE f(M1 D 01/15/88 24 0 18 12 17 0 0.00 FEFril 2 11/17/87 33 0 15 0 0 1 3.03 FITZPATRIO' 01/15/88 20 0 12 0 3 2 10.00 FCftT C/UCLN 1 08/07/87 8 6 8 2 0 0 0.CO FCRT ST. \\fdIN 01/14/88 13 13 0 0 13 0 0.Cc GF#tO GLLF 1 02/27/88 23 0 15 0 0 0 0.00 WMtIS 1 03/04.'87 26 0 0 0 0 0.CC ^ INDIfN FOltiT 2 02/26/88 13 0 11 0 0 1 7.69 INDIAN FOINT 3 01/15/88 10 10 9 4 3 0 0.CC PB(OEE 01/04/88 18 0 18 0 18 3 16.67 LAS/LI E 1 01/15/88 18 0 1 0 0 0 0.CC LASTLLE 2 01/15/88 19 0 7 0 0 0 0.00 LItCRIDC 1 11/17/87 34 0 0 0 0 8 23.53 t%ItE Yf(4 EE 12/15/87 20 0 19 0 20 0 0.CC POiTICELLO 03/15/88 19 10 11 10 0 0 0.CO NITE t11LE FOIrfT 1 C6/18/86 32 26 5 1 9 0 0.C0 NITE t11LE FOINT 2 11/13/87 21 0 13 0 0 0 0.CO tGTH f(IM 1 01/04/88 25 25 24 0 0 1 4.00 NCRTH /ttM 2 01/04/88 25 25 24 0 0 2 8.CC OCCME 1 01/14/88 14 14 12 14 0 3 21.43 OCDEE 2 01/14/88 14 14 11 14 0 2 14.29 OCD'EE 3 01/14/88 14 14 12 14 0 2 14.29 FYt.ISADES 01/15/88 24 0 23 0 0 2 8.33 PA.D \\GDE 1 01/15/03 33 0 26 0 0 0 0.CC FfLO VETE 2 01/15/08 33 0 26 0 0 0 0.00 l FfLO \\ G DE 3 01/15/08 33 0 31 O O O 0.CC l l

e Page No. 2 + 00/15/88 fit @L FEFORT STATUS CF IEB 85-03 ELitWRY BY FtJNT t#E AS CF June, 15, 1988 FU1EER P4.11EER titter TOTfL BYPASS TU CLE LIMIT tir1EER plt 1EER FER CENT UTILITY PU1EER SWITCH EMITCH SWITCH OT}ER ItIP INCP Ft/NT t#E FEFt.Y VfLWS OWILD OMEED CHWED Uto-t.Li6 VfLVES VfLWS FET4tY I 03/31/88 24 11 19 0 21 3 12.50 Ff%IRIE ISL/fD 1 04/08/08 21 0 19 0 0 0 0.CC FfMIRIE ISLMD 2 04/CO/88 21 0 19 0 0 1 4.76 CLAD CITIES 1 01/15/98 12 0 11 0 0 2 16.67 CUAD CITIES 2 01/15/88 12 4 9 0 0 2 16.67 Pf(D-O GECD 01/19/88 32 18 14 0 23 1 3.12 RIWR LEND 1 02/17/88 21 1 7 3 4 1 4.76 EA.EM 1 01/05/08 17 0 9 0 0 0 0.CO S/LEM 2 01/05/98 17 0 12 0 0 0 0.CO GM Cr{FFE 1 09/01/87 12 1 3 0 0 1 8.33 SM CPIFFE 2 09/01/87 23 22 11 O O 1 4.35 SM CNFFE 3 09/01/87 23 20 20 0 0 0 0.00 EEAEROO' i 11/30/87 30 7 5 6 22 0 0'.00 ECU7(M 1 02/12/88 21 0 11 0 0 3 14.29 SECU7(M 2 02/12/88 21 0 16 0 0 1 4.76 ST. LLCIE 1 01/14/88 29 0 23 0 0 0 0.00 ST. LLCIE 2 01/14/88 29 0 26 0 0 0 0.00 SLitrR 1 10/06/87 14 0 2 0 0 0 0.00 9_m_r%Yi% 1 01/12/88 22 11 11 11 10 6 27.27 9_m s HWA 2 01/12/88 22 1 12 0 5 4 18.18 TMI 1 06/25/87 12 10 12 1 1 0 0.CC TROJM 12/15/07 35 1 26 3 35 2 5.71 TLREY FOINT 3 01/14/88 14 0 14 0 0 0 0.00 VOGTLE 1 09/04/87 50 0 0 0 32 0 0.00 WATEFFERD 3 12/21/87 20 4 19 0 16 0 0.00 LW 2 12/18/87 21 0 20 0 0 4 19.05 LCLF CFEEX 01/14/88 34 34 27 34 0 2 5.88 ZICN 1 01/15/08 D 0 5 0 0 2 5.71 ZICN 2 01/15/88 35 0 0 0 0 1 2.86

      • Total ***

1776 357 894 156 465 112 Caution - A ::ero entry for the number of switch chary;e3 or for the number of other defects does not necessarily mean that none o curred. It probably means that the licensee simply did not report any data 0-the topic. To be sure, see the Ccmrents Report #or the facility. For-the 74 plants reporting to datet 5.56 is the average failure rate in percent. 9.4063 is the standard deviation of the failure rate in percent. For-the 32 plants reporting inoperable valves to date: 12.06 is the average failure rate in percent. 10.5547 is the standard deviaticr1 of the failure rate in percent.

'Page t'b. 1 CV./1S/80 fit #L TEFmT STATLE CF IEB 85-03 ELitVVtY BY FAILIJE RATE AS OF June 15, 1988 tU1EER tuEE PU1EER TOT 4. BYPASS TCr<LE LIMIT P&HR PU1EER FG CENT (JTILITY PU1EER EMITCH S4 ITCH S4 ITCH OTHER ItCP ItOP FtRIT tWE FEFLY VAL 4ES CWtIED OVN3ED CWtfED Lettsid VALkES VAL %ES (WREAS 1 02/29/88 34 0 34 0 1 19 55.88 S.EELDVtta 1 01/12/88 22 11 11 11 10 6 27.27 (R/ TEAS 2 02/29/88 41 0 37 0 0 11 26.83 LItERIO; 1 11/17/87 34 0 0 0 0 8 23.53 OCD E 1 01/14/88 14 14 12 14 0 3 21.43 ter 2 12/18/87 21 0 20 0 0 4 19.05 OF 8 4tte 2 01/12/88 22 1 12 0 5 4 18.18 LEWUEE 01/04/88 18 0 18 0 18 3 16.67 CLAD CITIES 1 01/15/88 12 0 11 0 0 2 16.67 OUAD CITIED 2 01/15/88 12 4 9 0 0 2 16.67 OCDEE 2 01/14/88 14 14 11 14 0 2 14.29 OCCN:E 3 01/14/88 14 14 12 14 0 2 14.29 SECUE7/AH 1 02/12/2 21 0 11 0 0 3 14.29 DFESDEN 2 01/15/88 8 0 6 0 0 1 12.50 FEFRY 1 03/31/88 24 11 19 0 21 3 12.50 DAVIS-EESSC 1 04/22/87 165 26 0 19 164 17 10.70 FITZPATRIOC 01/15/00 20 0 12 0 3 2 10 A PfLISACCS 01/15/88 24 0 23 0 0 2

3.,.S SftJCPCTTC 1 C9/01/87 12 1

3 0 0 1 8.33 PORTH AttM 2 01/04/88 25 25 24 0 0 2 8.CC INDI4W FOINT 2 02/26/88 13 0 11 0 0 1 7.69 WO_F CTEEK 01/14/88 34 34 27 34 0 2 5.EB TTC0fW 12/15/87 35 1 26 3 35 2 5.71 'ZICN 1 01/15/08 35 0 5 0 0 2 5.71 FftAIRIE ISL/to 2 04/08/EE 21 0 19 0 0 1 4.76 RItG EEND 1 02/17/88 21 1 7 3 4 1 4.76 SEOLD/AH 2 02/12/06 21 0 16 0 0 1 4.76 SAN CFCFFE 2 C9/01/87 23 22 11 0 0 1 4.35 PERTH fttM i 01/04/88 25 25 24 0 0 1 4.C0 RftO O EECD 01/19/88 32 18 14 0 23 1 3.12 PuHI 2 11/17/87 33 0 15 0 0 1 3.03 ZIC N 2 01/15/08 35 0 0 0 0 1 2.85 ECA\\G VfLLEY 1 04/18/88 24 0 0 0 0 0 0.CO EEA(ER Vftl.EY 2 07/31/87 16 7 10 0 11 0 0.CO EfeIDCOD 1 01/15/88 16 0 0 0 0 0 0.00 ECAID OOD 2 01/15/88 16 0 0 0 0 0 0.C0 EfUB4ICX 1 05/25/88 25 0 0 0 0 0 0.C0 EfUB4ICX 2 05/25/88 26 0 0 0 0 0 0.CO BWIN 1 01/15/88 16 2 0 0 0 0 0.CO BYTEN 2 01/15/08 16 5 0 0 0 0 0.Cc C4.\\ERT CLIFFS 1 01/28/88 12 0 it 0 0 0 0.CC Cft\\ERT CLIFFS 2 01/28/W 12 0 3 0 0 0 0.00 CLINTCN 1 03/02/87 23 14 12 6 20 0 0.CC CRYSTfL RIts 3 02/15/88 17 1 2 2 17 0 0.00 DIAELD C/W(CN 1 09/14/87 27 0 19 0 0 0 0.CC

e it. 2 Pag /15/98 06 FIN 0L FCFORT STATUS CF IED 85-03 SLitWsY BY FAILlFE RATE AS OF June 15, 1988 t U 1E G N f1EER tit 1E G TOTAL BYPASS TCTC.E LIMIT N.tEER PU1EER F G CENT UTILITY N f1EER SWITCH SWITCH S4 ITCH OTER It P IN:P Ft>WT fftE FUt.Y W1.NES CWtED CWtED OV(ED DC.FECTS WL4ES WLNES DI AELC' C/ MIN 2 09/14/87 27 0 19 0 0 0 0.CC DfESCEN 3 01/15/88 8 0 7 0 0 0 0.CC Dt.F(E (VN'LD 01/15/80 24 0 18 12 17 0 0.CC FORT C/LHIN 1 08/07/07 8 6 8 2 0 0 0.CC FORT ST. WlAIN 01/14/88 13 13 0 0 13 0 0.CC CRfND GLLE 1 02/27/88 23 0 15 0 0 0 0.00 H@RIS 1 03/04/87 28 0 0 0 0 0 0.CC INDIfN FOINT 3 01/15/88 10 10 9 4 3 0 0.00 LAS/t.LE 1 01/15/88 18 0 1 0 0 0 0.CC LASALLE 2 01/15/88 19 0 7 0 0 0 0.CC t%ItE Yft4EE 12/15/87 10 0 19 0 20 0 0.00 PDiTIrr1 i n 03/15/88 19 10 11 10 0 0 0,00 NITE MILE FOINT 1 09/18/86 32 26 5 1 9 0 0.CC NITE MILE FOINT 2 11/13/87 21 0 13 0 0 0 0.00 PfLO NETE 1 01/15/08 33 0 26 0 0 0 0.CC P/LO NEEDE 2 01/15/03 33 0 26 0 0 0 0.CC PfLO %EEDC 3 01/15/06 33 0 31 0 0 0 0.CC FFAIRIE ISLftO 1 04/CO/88 21 0 19 0 0 0 0.CC S/LD1 1 01/05/88 17 0 9 0 0 0 0.CC S/tB1 2 01/05/88 17 0 12 0 0 0 0.CC S/W ONOFTC 3 09/01/87 23 20 20 0 0 0 0.CC SEAEf00C 1 11/30/87 30 7 5 6 22 0 0.CC ST. LUCIE 1 ' 01/14/88 29 0 23 0 0 0 0.CC ST. LLEIE 2 01/14/88 29 0 26 0 0 0 0.CC SLitER 1 10/06/87 14 0 2 0 0 0 0.C0 TMI 1 06/25/87 12 10 12 1 1 0 0.CC T1J4EY FOINT 3 01/14/88 14 0 14 0 0 0 0.00 VOGTLE 1 09/04/87 50 0 0 0 32 0 0.CC MhnuG 3 12/21/87 20 4 19 0 16 0 0.CC

      • Total ***

1776 357 894 156 465 112 Cauticn - A ::ero entry for the nutnber of switch changes, or for the nutnber of cther defects does not necessarily rnean that tiene occurred. It probably rneans that the licensee sitnply did not report any data on the topic. To be sure, see the CcmTonts Report for the facility. For the 24 plants rep:arting to date: 5.56 is the average failure rate in percent. 9.4C63 is ttu standartl deviatico of tru failure rate in percent. For tin 32 plants reporting inoperable valves to date: 12.85 is tiu average failure rate in percent. 10.5547 is the standard deviatim of the f ailure rate in percent.

E!;Ct.05URE 5 Me-s ( O. O. Rothberg G3XE3IC

SS E II.E.S.1 IN SITU"EST XG OF VAMES i.

1 YO"03-0:?33ATED VAINES t ii .i ll ONEN ROTHBERG OFFICE OF RESEARCH JUNE 17,1988 O ,/

,-----,,-------,---,--------,.-,v-,,,,---

w.

-.p--

1 i. ED FOR ACTION TO INCREASE ~ TESTING /SURVEIILEXCEREqZREMEXTS

  • YOV FAILER3 RATES ii UND33 D3 SIGN BASIS r

CONJI"IONS A33 AT LEAST I AN ORJE3 07 YAGNITEDE l. HIGH3R TEAN P3EVIOLSLY ESTIMATED. i a

  • C'E3 RENT STR0KE-TIMING TEST YETHOD IS INADEQJATE TO ASSERE MOV OPERABILITY.

?.,? /- i t

si&s PROPCSED SCHEDULE s

  • SUBMIT CRGR ?ACKAG3 TO NRR BY END OF JUNE,1988.
  • SUBMIT CRGR PACKAGE TO CRGR i

BY ESD OF JULY, :.988, I

  • ISSUE GENERIC LETTER TO ALL POWER REACTOR OWNE3S BY ED OF AUGUS",1988.

'l

  • PREPARE DRAFT TEYPORARY r'

INSTR'JCTION FOR REGION GUIDANCE 1 BY END OF DECEMBER,1938,

  • PRPARE 3EVISION TO SRP SECTION 3.9.6, "INSERVICE T3 STING OF P'JEPS AND VALVES,"

i BY END OF JUNE,1989.

b4 ov + CO'NTEX:?S OF CRGR PACKAG3 os rev ::ssrxc/s:RVE"LLEXCE DRAFT GENERIC LETTER -TO ALL POWER REACTOR OWNERS -EXTENDS BULLETIN 85-03 REQUIREMENTS TO ALL SAFETY-RELATED MOVs, POSITION-CHANGEABLE MOVs, AND THE PORV BLOCK VALVES -REQUIRES OWNERS TO ADRESS A { SPECIFIC LIST OF DEGRADED l COND:"IONS. -CONTAINS IMPLEMENTATION 2M 4 SCHEDULE. -REQUIRES TESTING /SURVEILLENCE h .A FOR LIFE OF PLANT. 1

MsO9 a COE3XTS 07 03G3 PACKAG3 .\\..n...\\..L..E., v v.. L. I REGU:ATORY ANALYSIS -DETERMINISTIC ARGUMENTS EMPHASIZED VALUE-IEPACT ANALYSIS -PRA SUklARY

PA::L'B3 LATA :730Y BULL 3T:X 85-03 RES MEMO 0F Q.C. OF P3A 4

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q., P: ..,j% Document Name: 1-JDRAFT GENERIC LTR - MOV

,4 Recuestor's 10
.

HAWKINS Author's Name: orothberg' . Document Comentsi .c proposed crgr pkg re safety related mov testing #3 of 6 5 e 4 0 IQ h

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DRAFT GENERIC LETTER Proposal to Expand Periodic In Situ Testing and Inspection Requirements for Safety-Related Motor-Operated Valves (MOVs) T0: All holders of nuclear power reactor operating licenses (OLs) or construction pemits (cps). I

SUBJECT:

SAFETY-RELATED MOTOR OPERATED YALVE TESTING AND INSPECTION IE Bulletin 85-03, dated November 15, 1985, and Supplement 1 of NRC Bulletin 85-03, dated April 27, 1988, require that licensees develop and implement a program to ensure that valve motor operator switch settings (torque, torque bypass, limit, themal overicad), for motor operated valves (MOVs) in several specified systems,2are selected, set and maintained so that the MOVs will operate under design basis conditions for the life of the plant. NRC assessments of the reliability of all safety-related MOVs, based on extrapolations of the currently available results of valve surveillance perfomed in response to Bulletin 85-03, indicate that the program to verify switch settings must be extended in order to assure operability of all safety-related fluid systems. Our evaluation of the data indicates that, unless additional measures are taken, failure of safety-related MOV's to operate under design basis conditions will be much greater than had been previously estimated. The program will require that MOVs be tested, inspected, and maintained so as to provide the necessary asssurance that they will function over the entire range of differential pressures that the valves may be subjected to during both nomal operation and abnormal events within the design basis o' the plant. ..........c 1/ The term "safety-related" refers to those systems and components that are relied upon to remain functional during and following design basis events to ensure (i) the integrity of the reactor coolant pressure boundary. (ii) the capability to shut down the reactor and maintain it in a safe shutdown condition, and (iii) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the 10 CFR Part 100 guidelines. 2/ Design basis events are defined as conditions of nomal operation, including anticipated operational occurrences, design basis accidents, external events, and natural phenomena for which the plant must be designed to ensure functions (i) through (iii) above.

2 By this letter NRC extends the scope of the program outlined in IE Bulletin 85-03 to include all safety-related MOVs. In addition, those MOVs in all safety-related systems, that could be unintentionally moved (that is, not locked in position or with power removed) to a position that coule; interfere with the safety-related operation of any safety-related syst'm (to be referred to hereaf ter as position 4 changeable MOVs) are also to be iacluded in the program. The PORV bkck valves are also to be included in this prrgram. The Commission has determined, as part of the resolution of Generic Issue 7), "PORY and Block Valve Reliability", that PORV block valves should be te,ted as safety-related components. The program to respond to this letter shall consist of those action items, a. through d., described in IE Bulletin 85-03 and applied to all of the MOVs described above. Further, those actions outlined in the following paragraphs shall be applied to all safety-related MOVs, including those covered previously by Bulletin 85-03, all position-changeable MOVs and the PORY block valves. The action items, a through d, of Bulletin 85-03 are quoted in Appendix A of this letter for the convenience of the reader. The methods described in Appendix C of this letter are considered acceptable to demonstrate MOV operability for those MOVs that cannot be tested at pressure as required by action item c. of Bulletin 85-03. Action item d. of IE Bulletin 85-03 requires that licensees establish procedures to assure that correct switch settings an maintained throughout the life of each plant. As a clarification of the Bulletin requirements, note that the procedures for setting and maintaining MOV switches must account for nornal wear, deterioration of any of the critical MOV component parts, degraded electrical conditions, dirt accumulation, corrosion accumulation, and temperature effects as well as any misadjustments of the switches themselves that may have occurred over time, The selected assurance procedures must give plant personnel the capability to diagnose the conditions that would be the source of the misadjustment of the switch settings. It is insufficient to merely verify that the switch settings are unchanged from a previously established value. The switch settings must be verified, in accordance with the program implementation and verification schedule outlined below, to be appropriate for the condition of each MOV. The ASME Code Section XI stroke-timing test required by 10 CFR 50 does not satisfy this requirement, however, the switch settings need not be verified each time the stroke-timing test is performed. A number of root cause degraded conditions were discovered by plant owners, t.:her as a result of their efforts to comply with Bulletin 85-03 or from previous experiences. A list of these degraded conditions (including incorrect switch settings) is included in Appendix B to this letter. The program required by this letter shall address, as a minimum, those potentially degraded conditions listed in Appendix B for all of the motor operated valves outlined above. The program shall include specific analyses, tests, and inspections, as oppropriate to assure that each of the listed degradations are prevented or identified and corrected.

O 3 Verification of switch settings, as well as other tests or inspections that will specifically identify potential MOV degradations or misadjustments, shall be accomplished after maintenance or adjustment (including packing adjustrent) and at least every three years for each motor operated valve. All analyses, verifications, tests, and inspections required by this letter shall have been accomplished at least once for each MOV within four years of the date of this letter. All actions taken, including analyses, test, and inspections, shall be fully justified and documented for each MOV. The documentation shall include results and histcry of each as-found deteriorated condition, malfunction, test, inspection, analysis, repair, or alteration. Owners shall periodically (at least yearly after program implementation) tally total occurrences for any events and for each of the degradations listed in Appendix B in order to estimate trends of MOV operability. All documentation shall be retained on site and shall be made available for NRC audit upon request. Paragraphs b. and c. of Bulletin 85-03 (and supplement) call for plant owners to furnish justification for alternative action as described in those paragraphs. All documentation of such justifications shall be retained on site and shall be made available for NRC audit upon request. Nothing in this letter is intended to supersede or modify any requirement in Bulletin 85-03, or its supplerrent. Owners shall respond to the requirements, including reporting requirements, of Bulletin 85-03, for the MOVs listed therein, as before. The additional surveillance inspections and tests required by this letter shall also apply to Bulletin 85-03 MOVs but the documentation of the additional work'on these MOVs, as required by this letter, shall be retained on site and shall be made available for NRC audit upon request. Within two years of the date d this letter, licensees shall have documentation available on site for NRC aucis that: (1) contains the results of the desigt, basis review described in action item a. of IE Bulletin 85-03 and for all safety-related MOVs, position-changeable MOVs as described, and the PORY block valves, and (2) contains the program description and schedule to accomplish items b. through d. of IE Bulletin 85-03, as supplemented and clarified herein, for all safety-related MOVs, position-changeable MOVs as described, and the PORY block valves. For plants with an OL, the owner's schedule shall ensure that these item!.'.*e completed, and the program for MOV testing and surveillance, as outlined urein, is in place and fully implemented within three years or two refueling outages, whichever is later, of the date of this letter. For plants with a CP, the owner's schedule shall ensure that these items outlined herein are completed, and the program for motor operated valve testing and surveillance is implemented before the scheduled date for OL issuance or within three years from the date of this letter, whichever is later.

4 Accordingly, pursuant to 10 CFR 50.54(f) owners are requested to furnish, within 90 days lof the date of this letter, confirmation that the above schedule and requirements will be met. For any date that cannot be met, the owner shall furnish a proposed revised date,,iustification for any delay, and any planned compensating safety actions to be taken during the interim. The NRC staff will evaluate the owner's response and will take action, as appropriate, to assure that the requirements and commitments are enforced. This may include issuance of a Confirmatory or Show-Cause Order, if necessary. Owners are further requested to submit a final letter when the program outlined herein is in place and fully implemented. This request for information was approved by the Office of Management and Budget under a blanket clearance number 3150-0111 which expires September 30, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C., 20503. If you have any questions regarding this matter, please contact the NRC project manager or the technical contact listed below. T. E. Murley, Director Office of Nuclear Reactor Regulation Contacts: To be determined. h k

4 ~. Appendix A of Draft Generic letter Pertinent Action Items from NRC Bulletin 85-03, Dated November 20, 1985 and Supplement 1, Dated April 27, 1988 "a. Review and document the design basis for the operation of each valve. This documentation should include the maximum differential pressure expected during both opening and closing of the valve for both normal and abnonr.a1 events to the extent that these valve operations and events are included in the existing, approved design basis. (i.e., the design basis documented in pertinent licensee submittals such as FSAR analyses and fully approved operating and emergency procedures, etc). In addition, when determining the maximug differential pressure for valves that can be inadvertently mispositioned, the fact that the valve must be able to recover from such mispositioning shall be included." "b. Using the results from item a above, establish the correct switch setting. This shall include a program to review and revise, as necessary, the methods for selecting and setting all switches (i.e., torque, torque bypass, position limit, overload) for each valve operation (openingandclosing)." "The intent is to provide assurance that a program exists for selecting and setting valve operator switches to ensure a high reliability of safety system valves. If changing the switch settings is not sufficient to ensure the capability for repositioning a particular mispositioned valve, a justification for continued operation should be provided in the l bulletin response if the licensee does not elect to implement additional actions, such as administrative or procedural controls or equipment modi-l fications, to minimize the likelihood of valve malfunction." "c. Individual valve settings shall be changed, as appropriate, to those established in item b, above. Whether the valve setting is changed or not, the valve will be demonstrated to be operable by testing the valve at the maximum differential pressure determined in item a above with the exception that testing motor-operated valves under conditions simulating a break in the line containing the valve is not required. Otherwise, justification should be provided for any cases where testing with the maximum differential pressure cannot practicably be perfonned. This justification should include the alternative to maximum differential pressure testing which will be used to verify the correct settings." Any motor-operated valve that is not blocked from inadvertent operation from either the control room, the motor control center, or the valve itself shall be considered capable of being mispositioned."

m i 6 1 "Note: This bulletin is not intended to establish a requirement for valve testing for the condition simulating a break in the line containing the valve. However, to the extent that such valve open tion is relied upon in the design basis. a break in the line containing the valve should be considered in the analyses prescribed in items a and b above. The resulting switch settings for pipe break conditier.s should be verified, to the extent practical, by the same methods that would be used to verify other settings (if any) that are not tested at the maximum difential pressure." "Each valve shall be stroke tested, to the extent practical, to verify that the settings defined in item b above have been properly implemented even if testing with differential pressure can not be perfomed." "d. Prepare or revise procedures to ensure that correct switch settings are determined and maintained throughout the life of the plant.* Ensure that applicable industry recomendations are considered in the preparation of these procedures." "*This item is intended to be completely consistent with action item 3.2, ' Post-Maintenance Testing (All Other Safety-Related Components),' of Generic Letter 83-28, ' Required Actions Based on Generic Implications of Salem ATWS Events.' These procedures should include provisions to monitor valve perfonnance to ensure the switch settings are correct. This is particularly important if the torque or torque bypass switch setting has been significantly raised above that required."

I 0 7 Appendix B of Draft Generic Letter Summary of Coninon Motor-Operated Yalve Degraded Conditions 1. Incorrect torque bypass switch settings 2. Incorrect torque switch settings 3. Unbalanced torque switch

4.. Spring pack gap S.

Incorrect stem packing tightness 6. Excessive inertia 7. Loose or tight stem-nut locknut 8. Inc.orrect limit switch settings 9. Stem wear

10. Bent or broken stem
11. Worn or broken gears
12. Grease problems (hardening, migration into spring pack, lack of grease, excessive grease, contamination, non-specified grease)
13. Motor degradation
14. Incorrect or degraded wiring
15. Disk / seat binding
16. Water in internal parts or deterioration therefrom
17. Motor undersized (for degraded voltage conditions or other conditions)
18. Incorrect valve position indication
19. Misadjustment or failure of handwheel declutch mechanism
20. Relay problems (incorrect relays, dirt in relays, deteriorated relays, miswired relays)
21. Incorrect themal overload switch settings
22. Worn or broken bearings.
23. Broken or cracked limit switch ahd torque switch components
24. Missing or modified torque switch limiter plate
25. Improperly sized actuators
26. Hydraulic Lockup
27. Incorrect metallic materials for gears, keys, bolts, shafts, etc.

I

JV ^ y p 8 f Y Appendix C f Draft Generic letter The following methods are con idered to be acceptable (based on licensee responses to Bulleting 85-0 'that were found to be acceptable by the NRC Staff) to demonstrate design basi operability for those MOVs that cannot be tested at pressure, as described i action item c. of Bulletin 85-03: 1 1. Data from ins, rumented tests of at least four identical MOVs, con-ducted under# conditions ast extrapolated to design basis conditions, shall be used to establish the required performance criteria. The MOV that cannot be tested under pressure conditions shall be instru-mented and shall demonstrate operating characteristics at low-pressure or no-pressure conditions that provide objective evidence, based on the established performance criteria, that the MOV will function as required under its design basis conditions. Data from instrumented tests of at least 20 similarbOVs, d'extra conducted 2. under design basis conditions or lower pressure conditions lated to design basis conditions, shall be used to establish the required performance criteria. The NOV that cannot be tested under pressure conditions shall be instrumented and shall demonstrate operating characteristics at low-pressure or no-pressure conditions that provide objective evidence, based on the established performance criteria, that the MOV will function as required under its design basis conditions. 3. Data from an instrumented test of an identical MOV, conducted under both design basis conditions and lower pressure conditions, shall be used to establish the required perfortnance criteria. The MOV that cannot be tested under pressure conditions shall be instrumented and shall demonstrate operating characteristics at low-pressure or no-pressure conditions that provide objective evidence, based on the established performance criteria that the MOV will function as required under its design basis condition. I ldentical MOVs are MOVs equipped with the same manufacturer and model of operator. These MOVs are of the same valve type, same valve manufacturers, san _valvystefmiaQe_r and y _orf ge diamAt.e 4 {

  • Similar MOVs are MOVs equipped with the same manufacturer operator.

These b MOVs are of the same valve type and are of resonably similar size (+2"). k 'l

^ .. m ENCLOSURE 6 Vl GATE VALVE ISOLATION DURING HIGH ENERGY BWR LINE BREAKS (STATUS OF'GI-87) t G. H. WEIDENHAMER JUNE 17, 1988 t b i 1 A I

4 PROJECT PURPOSE PROVIDE DATA BASE FOR USE IN RESOLVING GI-87, "FAILURE OF HPCI STEAM LINE WITHOUT ISOLATION." SAFETY SIGNIFICANCE WILL ISOLATION VALVES IN SPECIFIC BWR HIGH ENERGY LINES CLOSE -AGAINST HIGH FLOWS IN THE EVENT OF A PIPE BREAK OUTSIDE CONTAINMENT?

e e Project Objective: Determine if isolation valves in high energy BWR lines that penetrate containment will close to i interrupt flow following a high energy line break i Characterize specific valve assemblies used in { BWR systems falling under the concerns of GI-87 Investigate the methods used to qualify the selected i l valve assemblies Perform research to address / resolve generic l deficiencies Develop basis for evaluating in-plant tests to provide assurance of valve operability BMG00057 9

~ t' Background Information: i I Systems of concern: - High Pressure Coolant injection (HPCI) - steam l - Reactor Core Isolation Cooling (RCIC) - steam ] - Reactor Water Cleanup (RWCU) - water 1 l Valves used in these systems: 2 10", 600 - 900 lb., flexible wedge gate valves - Limitorque SMB-type, motor operators, both AC and DC l - Manufactured by: Anchor / Darling Valve Co. } c c'% f Velan Valve Corporation Crane Company William Powell Company i il Walworth Company swoooo5s

~O

===. Background=== Information (. Cont'd): Utility specifications re~cuire pipe break flow interruption at system design conditions l c,ualification is typically analytical I Typical industry equation for determining valve closure thrug &y & e4 cw W M M 1 + P(A,;I + F, T = g( APX Ag .3 ) Of ten confirmed by opening valve at full differential pressure i sur l

TEST PLAN 'l ~ RWCU-LINES hM i f& ju =4 10 BLOW DOWN TESTS USING ANCHOR / DARLING 6"-GATE VALVE WITil OVERSIZED LIMITOROUE ACTUATOR k 4 BLOWDOWN TESTS USING VELAN 6"-GATE VALVE WITil TYPICAL LIMITOROUE ACTUATOR 'M STATUS (6/17/88) o ALL TESTS TO BE COMPLETED BY 6/24/88 o INTERIM REPORT DUE BY 9/30/88 FUTURE (FY 1989) o PERFORM STEAM TESTS FOR HPCI AND RCIC LINES o FINf,L REPORT DUE 6/30/89

~ e e Regulatory Concerns: l l Will provide information applicable to three highly visible j regulatory items i

  • Generic issue 87, "Failure of HPCI Steam Line Without Isolation" i
  • Generic issue ll.E.6.1, "In Situ Testing of l

Valves"

  • IE Bulletin 85-03, "Motor Operated Valve Common i

Mode Failures During Plant Transients Due to improper Switch Settings" fM000058 ~ 4

ENCLOSURE 7 E. N Ken-a Me k WW NRC MAINTENANCE TEAM INSPECTIONS 6/w/gp -lNSPECTION TREE COVERING ALL ASPECTS OF MAINTENANCE OVERALL PLANT PERFORMANCE MANAGEMENT ( COMMITMENT, ORGANIZATION, TECHNICAL SUPPORT) IMPLEMENTATION ( WORK CONTROL, ORGANIZATION. FACILITIES. STAFFING) 7[//-/.3[Ef D INITIATORS PROVIDE FOCUS FOR INSPECTION h[% OBSERVATION OF WORK IN PROGRESS PRA INSIGHTS RECENT COMPONENT FAILURES PREVIOUS INSPECTION REPORTS TOPICS OF INTEREST (CVs.MOVs. AIR SYSTEMS) INSPECTION FINDINGS INTEGRATED TO DEVELOP OVERALL ASSESSMENT WITH SEPARATE RATING OF ADEOUACY/ IMPLEMENTATION I S

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== ======== in===<r REmss PERxoC REuc. Mo owict mPru.a cm,uu o NN' an= =.- n. e g%amTA,=, ww is Ns-not nruuaA N7 110 RCKW & CON D T5 saw pua art ceas a superee WWDANG IN "UI, EHmnermam een 8 1 J/ w rtar'uums PRO @ESS e PR02DU1tAUZED I i e 0,05E-0VT Tf5TEW e vux DCWN NSPECTON AU1HC,mIAt0N1 REGMD e e 00CUWENTATXM e ftID6ACK CCWPLf!ED WORK 00CUWDff REMDr Pt02DutE3 Fal10aED e e ECMPWXT C0iTROL e SPARE PM11 CONTROL e RESQJ10N & OISatEPANCES WMAEMDIT OWtSTE e e Potsose. ouAunCAiONs 2 nuut u0RK PACKAss ApDendix 5

Federal Register / Vat; 53. No. Se f %.b4.j. March ES.1988 / Rdes and>Repdatiorie , o a. 9430 'se6 234. C5 Stat est. 83 54st 444, as sawoded EPFacTNs cart his heal Pohey "Activities Which Pcess If.e Basla of a i I (42 UAC 22x 22ath sec. 20s, as StaL 126-fStatementis affective March 23,19e8. Maintenance Progres' (42 UAC 3H61 Sections 1800-1aos atoo POR PWWtn udFOstasAfloat CCerTC p,tatenance Propsme inaued under sec.102. Pub. L el-19ow 83 Stal ack W. Roe. Director. Division af Esch commercial nudeat power plant &53 ss amended (u U AC. 4332). Section trace. Efts steo isaned under 5 USC 554. see Perfortnance and Quality Sections 2n4 L7eo 2.770 slao inued under s Evaluation. Office of Neeleer Reactor should dsvelop and implement a well-defined and eusetive program to as ute US C a&7. Secton L79o sleo issued under Regulstion U.S. Nucleet Reguletory t that maintenance actfrities are see 103. Se Stat am na amended (42 UAC-Commission. We shington. DC 10556, conducted to preserve or restore the 2133) and 5 USC SS15ections 2.800 and telephone (M1) 492-1004. avallability, performance and nhability 2.aos also issued under i USC 551. Sectos Laos also issued under s U.S C 553 and sec. Poucy of plant structures. systems, and (a2 USC.203el Subpart K also issued ander

Background

componenta.The propam should cleatly

29. Pub. L 45-254. 71 StaL 879, ae areended sec.1D. 88 Stat sis (41 US C 2:19h sec 1R The Commisslon has a propam to f*

"*E"

    • "'E "

Pub. L e7-425. 96 Stat 2230 (42 USC 10154). continually evaluate the operational systems used to control those activities. Append 2x A ateo lasued undet sec. 8. PA L perfonnam d adeat power plants. Further, the program should Include 91-6a0 e4 Stat.1473 (42 USC 2135). Analysis of operational events has feedback of specific results to ensure Appendix B eleo Lasued under sec.10. PA L sho*rn the1. In some casea, nudear correctin aetions, provisions for overall 90-24o. 90 Stat 1A42 (u USC 2o21b et seq )

2. Section VI.of Appendix C la (a

e$ propam eva untion. and the at ensures' identification of possible component or tevised to read as follows: with a bl5h de of reliability, that the system Mgn pWm equipment wi perform its intended APP'*dl* C4*ows) Statmot of Poacy function whan required. A limited NRC Aclivitie.t Which form the Basis of a and Procedun NRC Enforcement Acnes examinatien of nucisar powse plant Maintece Progtum maintenance progran has found a wid* M adequate program abould I 'caristfoain the efectfvenees of thesi considen V. Enforcomat Actions * *. F. Reope8kTCkwed Enforcement Aa/ons fo

  • Techn egy in the area: of als W ei cant rnctin maintenanca, 11 significant new infortnation ts recMyed of contri ulor to plant reliability proh'.ma

-Preventive snaintenance, abtained by NRC whch Indicataa that sa and. hence,is d safety concern. %e -Predicuve maintenance, cnfortement sanction was incorrectly Commisalon belleves safety can W -Surveillance: apphed. consideration may be given" enhanced by improving the

  • Engineering support and plant cUo e eNaYtn e, "8 effectiveness of maintenance programs modtfications, n or n throaghout the nudear industry.The correct the recorti. Reopening dedsions wiu Commission is proceeding with
  • Quahty assurance and quality dectene the seventy of a unction or to controh la made en a case by-case basis. are rulerasking consistent with this bellef.

enpected to occur rarely. and require the This Policy Statement is being issued to

  • Equipment history and trending:
  • Maintenance records:

specific appetrvel of the Depery Executive provide guuance to the industry while D6 rector For Repoul Ope.shons. the rulemaking proceeds.

  • Management of parts, tools. sad EM8:

Det et Wuhi toe.DC this 17th day of It is the objective of the Co.mniesion

  • Post.cnalntenance testing and March 1968.

est all components, systems and return to-service activities: For the Nuclear Regdatory Commission. structures of nuclear powar plana t. . Measures of ovetall program g.mu.t gm maintsined so that plant equjpraent will effectiveneu: Secretary of the Cocuruss/on, perform its intended function when Mtenance mansgement and [TR Doc. 66-4333 Filed 5-12-as, &as sm] required.To acco:nplish this objective, r stfon in the arta: of emo ceos noms each Ikansee should develop and alng. Implement a maintenance program which provides for the periodic ,,,4,seduling,

ging, evaluation. and prompt repair of pf ant

-Shih cowrage. M CFR Part g components, systems, and structure s is -Resource allocatforc , ensute theit ayaLlability.

  • Controlof contracted maintenance Final Commlaston Poney Statement on Demon of Malatenance services:

Watntenance of NucJest Power Piants

  • Radiological exposure control na Commisalon d4fmas maintenance amsev: Nuclear Regulatory as the aggregate of those functions (Mb a

Commission. required to preserve or restore safety.

  • personnal quajification and training:
  • Internal communications between reliability, and ava.Llability of plant ACTiost Rnal policy statement, stryc!ures. systems, and components, the maintenance organization and plant st.ruuaav: The Comm! salon beljeves Maintenance tr.dsdes not only activities operations and support groups; safety can be enhanced by knprovtng traditionally apodated with identifying

' Com:nanications between plant and the effective: ess of maintenance and correcting actuel or potential corporate management and the degraded conditions, t.e, repair, maintenance organlution. programs throughout the nuclear Industry.He Comm!ssion is T heding suneillanos, diagnostic aximinations. Malaterwmce recommindailons or with rulemaking conaletent with thle and preventive measures: but extends to requirements ofindividual vendors belief. This Policy Sta ternent is being all supporting functions for the conduct should receive appropriate attention m issued to provide guidance to the of 6ese activities.These activities and the develop: ment of the maintenance industry while the rulemaktna proceeds. functions are listed below under program. y-g

9431 Federal Register / W1. 53. No. 56 / Wednesday, March 23, l'968 / Rules and' Regulations erroneous M speed signal during ground one engine as a failure cf the cther engine,nfs AD supersedes AD 86 Future Commission Action operation with the bottoming govemor 51, Amendment 394473 (51 FR 44439; 'the Commission inteeds this Policy (BG) enabled. December 9.1986). Statement to provide guidance to the DATts: Effec:ive--May 9.1988. Interested persons have been afforded industry in imoroving maintenance Compliance ScAedu/e-As prescribed an opportunity to participate in the programs for their power reactor in the body of the AD. making of this amendment.No f acilities.The Commission will continue Incorporation by Reference-- to enforce existing requirements Approved by the Director of the Federal comments were received. Accordingly. the proposalis odopted without change. including those that address Register as of May 9.1988. AD 86-10-31. Amendment 394473 [51 maintenance practices and will take Aponssses:The applicable service whatever action that may be necessary bulletins (SB's) may be obtained from IR 44439). issued November 18,1986. to protect health and safety. Dowty Rotol Limited. Cheltenham Road requires that the engine BC be disabled The Commission expects to publish a East. Cloucester, England GL2 9QR when the aircraft power lever is Notice of Proposed Rulemaking in the General Electric Company,1000 positioned in the beta range (below near future that will establish basic Weste rn Avenue. Lynn, Ma s s a chusetta flight idle).The AD was needed to requirements for plant maintenance 01910; and Saab Scania AB. S48188. prevent PT overspeed and resulting uncontained failure caused by reaction programs. We believe that the contents Unkoping. Sweden. and bounds of the proposed rule will fall A copy of each SB is contained in of the fuel control to an erroneous R within the general framework described Rules Docket Number 86-ANE-21,in the speed signal during ground operation in this Policy Statement. Office of the Regional Counsel. Federal with the BG enabled. Consideration will also be given to Aviation Administration. New England AD B6-10-51 provides interim industry. wide efforts that already have Region.12 New England Executive Park, instructions to prevent M overspeed been initiated. We encourage interested Burlington, Massachusett 01803, and ed uncontained failure. Since these parties to provide their views on this may be examined between the hours of instnactions require special aircraft and important subject to the Commission, 8.00 a.m. and 4.30 p.m Monday through engu.c operating procedures which even at this early stage of the Friday, except Federal holidays. increase crew workload erd invalidate rulemaking process. Any notice of con runTwsn peronMADON CONTACT: the constant torque on takeoff function, proposed rulemaking that is published Barbara Carian. Engine Certification the FAA has determined that a second will provide, of course, a period for Branch ANE-141, EnF ne Certification overspeed protection system with an i public comment on its contents. Office. Aircraft Certification Division, improved level of safety precludes Ge Dated at washington.DC.this 17th day of Federal Aviation Administration.New need for these interim instructions : * ! Marth.1988. England Region.12 New England returns the aircraft and engine to pre-For the Nuclear Regulatory Commission. Executive Park. Burlington* AD 86-W51 operation. Massachusetts 01803 telephone (617) Conclusion y' Secretary of the Cornmission. 273-7066. [G Doc. 88-6334 bled 3-22-88,6.45 am) SVPPuMENTARY INroRMAnoec A The FAA has determined that this proposal to amend Part 39 of the Federal regulation affects 107 aircraft all of - Aviation Regulations (FAR) to include a which are in compliance with this AD.

      • CoM F5**

nm A g tb instauaun of a Thuefom ] certdy that this action (1)is DEPAR1 MENT OF TRANSPORTATION second overspeed protection system on not a "major rule" under Executive certain GE CT/-5A series turbopropeller Order 12291;(2)is not a "significant Federal Aviation Administration engines as installed in Saab-Fairchild rule" under DOT Regulatory Policies SF340A aircraft was published in the and Procedures (44 FR 11034; Fe$ruary 14 CFR Part 3g Federal Register on October 16.1987,(52 261979);(3) does not warrant preparation of a regulatory evaluation i et Numt>er 86-ANE 21; Amot. 39-FR 36458). The proposal was prompted by an as the anticipated impact is minimal; engine M overspeed and resulting and (4) will riot have a significant Airworthiness Directives; General uncontained failure caused by reaction economic impact, positive or negative. o e Nel c to an urone us PT on a substantial number of small entities Electric (GE) CT7-5A,-5A1, and -5A2 Turbopropellar Engines as Installed in 8 peed signal during ground operation under the criteria of the Regulatory Saab Fairchild SF340A Aircraft with the BG enabled. Flexibility Act. Since this condition is likely to exist Ust of Subjects in 14 CFR Part 39 ActNcy: Federal Aviation or develop on other engines of the same Administration (FAA). DOT. type design, a new AD is being issued Engines. Air transporation. Aircraft, Action: Final rule. that requires installation of a second Aviation safety. Incorporation by suuMARY:This amendment adopts a overspeed protection system on GE reference' new airworthiness directive (AD) which CT7-5A series turboprope!!er engines as Adoption of the Amendment i requires the installation of a second installed in Saab.Fairchild SF340A overspeed protection system on certain aircraft.This AD also requires Accordingly, pursuant to the authority CE CT7-5A series turbopropeller incorporation of engine BG deactivation delegated to me, the Federal Aviation engines as installed in Saab Fairchild switches in the power lever quadrant t Administration (FAA) proposes to SF340A aircraft.This AD also prevent an adverse yaw condition in the amend Part 39 of the Federal Aviatfor aircrr.ft that could occur due to a ' Regulations (FAR) as follows-supersedes AD 86-10-51. Amendment mismatched aircraft power condition 39-5473 (51 FR 44439; December 9.1986). resulting from an uncommanded power PART 39--{ AMENDED) This AD is needed to prevent eng6e increase of one engine.This would also 1.The authority citation for Part 39 power turbine (F) overspeed and prevent the crew from misinterpreting continues to read as follows: resulting uncontained failure caused by the uncommanded power increase of reaction of the fuel control to an

ENCLOSURE 8 T. Marsh IST PROBLEMS AND PLANS INTRODUCTION / BACKGROUND IST PROBLEM AREAS McGUIRE/GINNA INSPECTIONS ' NRC ACTIONS UNDERWAY POSSIBLE INDUSTRY ACTIONS CONCLUSIONS BACKUP SLIDES TECHNICAL PROBLEMS GENERIC LETTER 10 CFR 50.55(A) RULE CHANGE O r.,, _.-m__, w, ._,._-,..__.,_,,_.-__.,,-_,_,_m.,

s . a; L ' INTRODUCTION / BACKGROUND OBJECTIVE - TO ASSESS OPERATIONAL READINESS OF SAFETY v g 7LA b RELATED PUMPS AND VALVES, 10 CFR 50.55A REQUIRES PUMP AND VALVE IST PROGRAM IN ACCORDANCE WITH ASME CODE, SECTION XI, UPDATE IST PROGRAMS TO THE CURRENT CODE EDITION AND ADDENDA EVERY 10 YEARS, ALLOWS THE GRANTING OF RELIEF REQUESTS FOR CODE REQUIREMENTS THAT ARE IMPRACTICAL. STATUS APPROXIMATELY 33 PLANTS HAVE RECEIVED SERs. (29) APPR0XIMATELY 20 PLANTS HAVE SERS THAT ARE 0VT OF DATE (SUPERSEDED BY LATER SUBMITTAL) 61 PLANT PROGRAM SUBMITTALS '87 21 PLANT PROGRAM SUBMITTALS THIS YEAR FF INTERIM APPROVAL ON 32 0F THE 70 OTHER PLANTS, f f T% 4 m l

? IST PROBLEM AREAS TECHNICAL

  • INADEQUATE / DEFICIENT TESTING REQUIREMENTS IN ASME CODE
  • N0 STAFF OR ASME GUIDANCE EXISTS ON CODE IMPLEMENTATION
  • NO CERTIFIED INSPECTORS

. LEGAL

  • 10 CFR 50,55A INCONSISTENT WITH TECH SPECS
  • POORLY WORDED 10 CFR 50.55A (SELF-CONTRADICTORY)
  • TS 4.0,5 REQUIRES STAFF APPROVAL PRIOR TO IMPLEMENTING RELIEF REQUESTS

~ ADMINISTRATIVE

  • INTERIM RELIEF EXPlRED OR NONEXISTENT
  • LARGE VOLUME OF PROGRAMS / REVISIONS / RELIEF REQUESTS
  • LICENSEES IMPLEMENT NEW PROGRAM REVISIONS W/0 NRC APPROVAL OR PRIOR NOTIFICATION RESOURCES
  • COMPLEX PROBLEMS / RESOURCE INTENSIVE
  • LARGE CONTRACT - EG&G, 7 PEOPLE, $800K sa g JP r

r ENFORCEMENT

  • TECHNICAL SPECIFICATION PROBLEM
  • LACK 0F SERs HAMPERS INSPECTION EFFECTIVENESS
  • REGIONAL VARIATIONS IN INTERPRETATIONS 9

~ MCGUIRE DIAGNOSTIC INSPECTION IST PROBLEMS

  • CERTAIN SAFETY RELATED CHECK VALVES NOT IN THE IST PROGRAN
  • MOST CHECK VALVES WERE NOT BEING REVERSE FL0W TESTED

^

  • WITH>THE EXCEPTION OF THE PRESSURIZER AND STEAM GENERATOR SAFETY VALVES, NO SAFETY RELATED RELIEF VALVES WERE BEING TESTED i
  • IST PROGRAM,.LIKE MANY IST PROGRAMS, NOT REVIEWED / APPROVED BY STAFF R.E. GINNA IST INSPECTION
  • MANY SAFETY RELATED CHECK VALVES EITHER NOT IN IST PROGRAM GR NOT FULL FLOW TESTED
  • SYSTEM OPERABILITY QUESTIONED

NRC ACTIONS UNDERWAY w MEETING WITH VTILITIES TO GAIN THEIR PERSPECTIVES ON IST y PROBLEMS (APRIL-MAY 1987) M %% WORKING WITH ASME ON IMPROVING CODE REQU1REMENTS, GUIDANCE, AND TIMELINESS (0NG0ING) PARTICIPATINi IN IST INSPECTIONS AND OTHER REGION BASED' IST ACTIVITIES (ONG0ING) AEOD ASSESS TESTING FREQUENCY QUESTIONS (SEPTEMBER 1988) REQUEST TO RES TO REVISE 10 CFR 50.55A (MAY 1988) COMMISSION PAPER ON IST STATUS, PROBLEM AREAS, AND ACTION PLAN

  • NRR/ REGIONAL /RES/AE0D COUNTERPARTS AND INDUSTRY SYMPOSIUM (MARCH 1989) 15T M FA GENERIC LETTER TO ESTABLISH NEW POLICY AND GRANT INTERIM y

PROGRAM APPROVALS (AUGUST 1988)* PUBLISH NRC TECHNICAL GUIDANCE DOCUMENT (AUGUST)* REVISED LONG TERM APPROACH AND RULE (10CFR 50,55) ON INSPECTIONS VERSUS DETAILED PROGRAM REVIEWS (1990)*

  • = ITEMS THAT WILL REQUIRE CRGR REVIEW I

~

'e e POSSIBLE INDUSTRY ACTIONS IMPROVE ASME CODE ON IST TO INCLUDE MORE MEANINGFUL TESTING WITH TECHNICALLY DEFENSIBLE FREQUENCIES FORM OWNERS GROUP TO ADDRESS GENERIC PROBLEMS WITH IST WORKING WITH NUMARC OR OTHER HIGH PROFILE INDUSTRY GROUPS T0 INCREASE AWARENESS OF IST PROBLEMS AND COMMITMENTS T0 IMPROVE BETTER CORPORATE COORDINATION OF IST PROGRAM WITHIN THE UTILITY IMPROVED IST PROGRAMS, SUBMITTALS, AND TIMELINESS CONCLUSIONS CURRENT PROBLEMS WITH IST ARE DIVERSE, RESOURCE INTENSIVE AND ARE A RESULT OF PAST LACK 0F INDUSTRY AND NRC COMMITMENT MANY OF THE NEEDED IST IMPROVEMENTS ARE SIGNIFICANT AND WILL REQUIRE TIME, CONTINUED NRC MANAGEMENT SUPPORT AND INDUSTRY COOPERATION

TECHNICAL PROBLEMS CODE TESTING DOES NOT DETECT DEGRADATION IN TIME TO PREVENT FAILURE OF COMPONENTS CODE TESTING DOES NOT ALWAYS DETECT EXISTING FAILURES IN CHECK VALVES CODE TESTING DOES NOT ALWAYS DETECT INABILITY OF A POWER OPERATED VALVE TO OPEN/CLOSE /N) DOCUMENTED NRC OR ASME GUIDANCE DOES NOT EXIST FOR: SCOPE OF IST PROGRAMS NRC INTERPRETATION OF VARIOUS CODE REQUIREMENTS ACCEPTABLE / UNACCEPTABLE RELIEF REQUESTS

  • ' FORMAT AND COMMENT OF PROGRAMS FREQUENCY OF TESTING HAS NO FIRM TECHNICAL BASIS PROCEDURES ARE A SOURCE OF PROBLEM l

l CHECK VALVES PIVs L MOVs

GENERIC LETTER PURPOSE - T0 S0LVE SOME IMMEDIATE PROBLEMS RELATED T0 IST PROGRAMS, REVISIONS AND RELIEF REQUESTS - TO ARTICULATE FUTURE PLANS AND POLICIES REGARDING IST PROGRAMS, ELEMENTS 1. GRANTS INTERIM RELIEF FOR ALL IST PROGRAMS SUBMITTED 2. TECHNICAL SPECIFICATION IS NOW ENFORCEABLE 3. N0 MORE IMPLEMENTING UNAPPROVED RELIEF RE0 BESTS 4. SCHEDULE FOR COMPLETING REVIEWS 5. IST PROGRAMS MAY BE REVISED AND IMPLEMENTED WITHOUT PRIOR APPROVAL IF: A. CONTAINS NO NEW RELIEF REQUESTS, B. NON REDUCTION IN SCOPE, AND C. 50-59 EVALUATION 6. IF DO NOT MEET ALL THREE TESTS, PROGRAM REVISIONS CANNOT BE IMPLEMENTED WITHOUT PRIOR APPROVAL 7. ALL IST PROGRAMS SENT TO REGIONS AND PMs BEFORE IMPLEMENTED ^ 8. EMERGENCY RELIEF REQUESTS MUST SATISFY EXIGENCY TEST ~y

MAJOR OBJECTIVES OF 10 CFR 50.55A RULE MAKING ELIMINATE DETAILED REVIEWS OF IST PROGRAMS AND REllEF REQUESTS THROUGH SELF IMPLEMENTATION OF DETAILED TECHNICAL AND PROGRAM GUIDANCE, IN ACCOMPANYING REG, GUIDE CONDUCT IST INSPECTIONS AS A MAJOR CHECK ON ENSURING ADEQUATE IST PROGRAMS AND IMPLEMENTATIONS CONDUCT REGION BASED WORKSHOPS FOR UNIFORM IMPLEMENTATION INCORPORATE BY REFERENCE NEW ASME IST STANDARDS: OM 68 10 REQUIRE UNIFORM ONE TIME UPDATE TO OM 6 8 10 ELIMINATE MANDATORY UPDATING PROVISION ISSUE ACCOMPANYING REG, GUIDE ON CODE IMPLEMENTATION EXTEND OM 6 8 10 REQUIREMENTS, I.E. MOVS, PIVS, CHECK VALVES, PUMPS, AS NECESSARY CLARIFY CONFUSING AND CONTRADICTORY LANGUAGE IN CURRENT RULE

ENCLOSURE 9 E. J. Brown ,J, MOV EFFORTS I, NLFARC A. OVERVIEW MOV PROGRAM INPO EPRI ( W C) B. HYDRAULIC LOCKUP

  • EPRI ( H C)

II, ASE 08M - 8 STARRlP & PERIODIC PEPF0 PRANCE TESTING 0F K)VS I l l

INP0 EFFORT ON MNS [fTILITY SENIOR NUCLEAR PANAGERS ALERTED AB0lfT IPPORTANCE OF POV PERFORPANCE ADDED EPPHASIS DURING INPO EVALUATION AND ASSISTANCE VISITS VERIFY IPPLEMNTATION OF SOER 83-9 PAINTENANCE PERSONNEL INF0 PED OF MOV PROBLEMS AND S0Liffl0N TECHNIQUES IDEffTIFY GOOD POV PERF0WANCE AND C0tti)NICATE LESSONS LEARNED k w-- - -- - -, -,a, s- -e s --m., we---,,-,,,., --m,, ,,,+,y, n-m ,-, -,,-.y e------

.. = = -. p INP0 PLANT VISITS PLANALLPLAhTS SAT PEOPLE REVIEW AE0D PARTICIPATION AT 3 PLARS PROGRAMATIC REVIEW EVALUATION PROCESS OBSERVATIONS v a m. -e r e --me,-

+ ., EPRI (WC) 10/ EFFORTS A, OVERVIEW PROGRAM

  • TECHNICAL ADVISORY GROUP
  • CONTRACTOR PREPARES DOClfENTS
  • MAINTENANCE - PEPAIR GUIDE
  • APPLICATION GUIDE
  • AE0D PARTICIPATION B.

HYDRAULIC LOCKLP

  • AEOD/E702 3/19/87
  • Nlf1 ARC 12/87
  • EPRl/WAC 2/88
  • PROGRAM / PROGRESS t

e ',3',,, 08M 8 WORXGROUP hU' ARC CONSIDERS PART OF OVERALL KW PROGPAM OM 8 DRAFT G - PEV 2 08M C0mITTEE KGATIVE BALLOTS OM 8 DRAFT G - EV 3 REVISED 6/10/88 REQUIREENT - PRESERVICE BASELINE - INSERVICE BASELIE - NEW BASELINE FOR REPLACEKfff, PODIFICATION, REPAIR, MAINTENANCE - RECONFIRM EVERY TWO YEARS 4 .}}

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