ML17325A421

LER 86-020-01:on 851102,main Steam Safety Valves Discovered Out of Spec During Surveillance Testing.Caused by Lack of Procedural Instructions.Safety Valves Setpoints Reset. W/871029 Ltr

ML17325A421
Person / Time
Site:	Cook
Issue date:	10/29/1987
From:	Droste J, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-86-020, LER-86-20, NUDOCS 8711030484
Download: ML17325A421 (13)

Text

REGULA Y INFORMATION DISTR IBUTIO YSTEM (R IDS)

ACCESSION NBR: 8711030484 DOC. DATE: 87/10/29 NOTARIZED: NO DOCKET FACIL: 50-315 Donald C. Cook Nuc lear Poeer P lant'nit 1 ~ Indiana 05000315 AUTH. NAME AUTHOR AFFILIATION DROSTEi J. B. Indiana h Michigan Electric Co.

SMITHI W. Q. Indiana h Michigan Electric Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 86-020-01: on 851102> main steam saf et'alves discovered out of spec during surveillance testing. Caused bg lack of procedural instY uctions. Safety valves setpoints reset.

W/871029 l tr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL l SIZE:

TITLE: 50. 73 Licensee Event Report (LER) Incident Rpti etc.

REC IP IENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 PD3-3 PD 1 1 WIGGINGTQNI D 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 AEOD/DSP/NAS 1 1 AEOD/DSP/RQAB 2 2 AEQD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEBT/ ICSB 1 1 NRR/DEST/MEB 1 NRR/DEBT/MTB 1 1 NRR/DEST/PSB 1 NRR/DEST/RSB 1 1 NRR/DEST/SQB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 NRR/DREP/RPB NRR S/SIB 1 NRR/PMAS/ ILRB 1 1 I 02 1 RES DEPY GI 1 1 RES TELFORDi J 1 RES/DE/EIB 1 1 RQN3 F ILE 01 1 1 EXTERNAL: EGS.G GROHI M 5 5 H ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NS IC HARR ISI J 1 1 NSIC MAYSI G 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NRC Form 388 U.S. NUCLEAR REOULATORY COMMISSION (84)3)

APPROVED OMB NO. 3150010l EXPIRES: SI31I85 LICENSEE EVENT REPORT (LER)

FACILITY NAME (I) DOCKET NUMBER (2) PA E 3 D. C. Cook Nucd.ear Plane Unit 1 0 5 0 0 0 1 OF TITLE (S)

Main Steam Safet Valves Out of S ecification Due to Set oint Dr f EVENT DATE (5) LER NUMBER (8) REPORT DATE (7I OTHER FACILITIES INVOLVED (8)

.">~/'. SEQVSNTIAL REVrSION FACILITYNAMES DOCKET NUMBER(s)

MONTH OAY YEAR YEAR NUMBER NUMBER MONTH OAY YEAR 0 5 0 0 0 D (

02 85 8 6 020 0 1 1 0 2 9 8 7 ol the folloylno) (11 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR g: )Check one or more OPERATINO MODE (0) 20A02(b) 60,73(s) (2) Bv) 73.71(b) 20AOS(c)

POWER 20AOS(s)(1) (I) 50.35(c) (1) 50.73(s) (2)(v) 73.71(c)

LEVEL (10) 0 0 20AOS( ~ )(1)(8) 50.3d(c) 12) 60.73(s)(2)(v8) OTHER (Specify In Abrsrect below end In Test. HRC Form xe 'V 20AOS4) () I Bll) 60.73(s) (2) (vill)(A) 35b'A) r 50.73(s)12)(l)

'h 20AOS(s) (1) (lv) 50.73(s)(2) (5) 50.7 3 (s) (2) (vill)(8) 20AOS(s)11) (v) 60.73(sH2) (III) 50.73 (s) (2) (x)

LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE J. B. Droste Maintenance Superintendent 6 164 65- 59 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13I CAUSE SYSTEM COMPONENT MANUFAC. REPORTABLE r~ SP CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE .

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~

TURER TO NPRDS TURER TO NPRDS

à RV D24 3 &Wm SUPPLEMENTAL REPORT EXPECTED (to) MONTH OAY YEAR EXPECTED SUBMISSION DATE 05)

YES (If yer. complete EXPECTED SUBhtISSIDH DATE)

ABsTRAcT ILlmlt to )coo rpecet, I 8, epprorrlmetely fifteen rlnoleepece typewrlnen tinsel (18)

This is a supplemental report to a previously submitted LER, 315/86-20-00.

v On November 2, 1985, with the reactor in Hot Stand-By, eight of twenty Unit, 1 Main Steam Safety Valves (MSSV) lift setpoints were found out of specification of twenty Unit 2 MSSV lift setpoints were, during surveil-lance testing. Four discovered out of specification during surveillance testing on'June L'

23, 1986. ~

Also, similar surveillance test failures on October 16, 1983 and July 2, 1984 were not properly reported. These events were determined to be report'able on August 25, 1986 after a review of documentation on MSSV setpoint verification.

A lack of procedural instructions contributed to the failure to report the events within 30 days as required by 10CFR50.73. In each case the setpoints were corrected and left operable prior to completion of the MSSVs'ift

. Surveillance Test Procedure (STP) . The apparent MSSV setpoint drift could have been attributable to two factors, 1) testing method, and; 2) setpoint

.drift due to valve design/application. The investigation concluded that the old testing method had a high probability of contributing to the apparent MSSV setpoint drift. To prevent recurrence, MSSV setpoints have been tested with an improved testing method. Also, the applicable STP has been modified to ensure that future MSSV failures are promptly reported.

e)P I

EI7>ZOSO4m PDR ADOCK 0 Sooosln PDR 8

NRC Form 358

NRC Fnnn 388A U.S. NUCLEAR REOULATORY COMMISS (9831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150M104 EXPIRES: 8/31/88 FACILITY NAME (ll DOCKET NUMBER (31 LER NUMBER (81 PACE (31 SEOUENTIAI. REVISION YEAR NUMBER NVMSER D. C. Cook Nuclear Plant -Unit l o s o o o 31 586 020 0 102 OF 0 TEXT ///'mme <<>>ce/4/eee/RRL I>>ed/d/Fee/NRC Femi 38SA'4/(IT(

Conditions Prior to Occurrence Unit One in Mode 3 (Hot Stand-By), 0 percent reactor thermal power.

Unit Two in Mode 3 (Hot Stand-By), 0 percent reactor thermal power.

Descri tion of Event This is a supplemental report to a previously submitted LER, 315/86-20-00.

On August 25, 1986, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> during a review of Main Steam Safety Valve (MSSV) (EIIS/SB-RV) setpoint verification documentation, it was discovered that reportability requirements of 10CFR50.73 had not been met. Eight of the twenty Unit 1 MSSV's were found outside of the setpoint range acceptance criteria of Surveillance Test Procedure (STP) **12MHP4030.STP.002 (Main Steam Setpoint Verification Secondary System Safety Valve Settings) when tested on November 2, 1985. Four of twenty Unit 2 MSSV's also failed to meet this accep-tance criteria when tested on June 23 and 24, 1986. As a result of a procedure deficiency, these events were not promptly identified as being reportable. It was also determined that similar surveillance test failures of MSSV's which occurred in October 1983 and July 1984 were not properly identified and reported. Upon discovery of the low setpoint values the MSSV setpoints were immediately adjusted to bring the values within the Technical Specification required range. The action statement, for Technical Specification 3.7.1.1 was complied with during the performance of the testing. The main steam headers of each of the four steam generators (EIIS/SB-SG) in both Unit 1 and Unit 2 are equipped with 5 safety valves for a total of 20 valves per unit.

The required relief pressure setpoint range and their as-found conditions for Unit 1 and Unit 2 safety valves are listed below for-t:he valves found out of specification:

Unit 1 (1983) Technical Valve Specification As-Found Valve Identification Steam Required Range Setpoint Serial No. No. Generator (psi) ~(si)

BN-6305 SV-1B-1 1054-1076 1079 BN-6306 SV-1B-2 1054-1076 1032 BN-6311 SV-1A-2 1054-1076 1046 NRC FORM CSEA *U,B,OPO:1988.0I

NRC Form 366A U.S, NUCLEAR REGULATORY COMMISS

($ 83)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. 3160-0)04 EXPIRES: 8/31/88 FACILITYNAME (1 l OOCKET NUMBER 12) LER NUMBER (6) PAGE (3)

YEAR gs$ h SEQUENTIAL ..NN'EVISION M6) NUMBER '~R NUMBER D. C. Cook Nuclear Plant Unit 1 o s 0 o 0 3 8 6 02 0 0 1030F TEXT Ã/IKTBe>>co Er Bh)(r)N/, I>>o I//dor>>/NRC Form 38//AS/(IT)

Unit 2 (1984) Technical Valve Specification As-Found Valve Identification Steam Required Range Setpoint Serial No. No. Generator (psi) ~(si)

BN-6324 SV-1A-3 1054-1076 1078 BN-6327 SV-1B-4 1054-1076 1036 BN-6329 SV-1B-3 1054-1076 1053 BN-6338 SV-2A-2 1064-1086 1038 BN-6341 SV-3-2 1074-1096 1072 Unit 1 (1985) Technical Valve Specification As-Found Valve Identification Steam Required Range Setpoint No.

'erial Na. Generator ~(si) (psi)

BN-6304 SV-1B-3 1054-1076 1081 BN-6305 SV-1B-1 1054-1076 1099 BN-6306 SV-1B-2 1054-1076 1106 BN-6308 SV-1A-1 1054-1076 1087 BN-6312 SV-2B-2 1064-1086 1089 BN-6314 SV-2B-1 1064-1086 1058 BN-6315 SV-2B-3 1064-1086 1054 BN-6321 SV-3-2 1074-1096 1132 Unit 2 (1986) Technical Valve Specification As-Found Valve Identification Steam Required Range Setpoint Serial No. No. Generator ~(si) ~(si)

BN-6327 SV-1B-4 1054-1076 1052 BN-6334 SV-2A-1 1064-1086 1063 BN-6338 SV-2A-2 1064-1086 1057 BN-6343 SV-3-1 1064-1086 1063 No other structures, components or systems that were related to the events were inoperable at the times of occurrence.

NRC'FORM SBBA *U.S.GPO:16661

NRC Form 366A U.S. NUCLEAR REOULATORY COMMISS (983)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3)EOM)04 EXPIRES: 8/3)/88 FACILITY NAME ul DOCKET NUMBER (2) LER NUMBER (6) PACE (3)

YEAR SEQUENTIAL )(."A REVISION F>@ NUMBER NUMBER D. C. Cook Nuclear Plant Unit 1 osooo 6 0 2 0 0 10 /6 OF TEXT /Ãrrrcoo g>>r>> lr nr)rr)or/, r>>o eo //r/or>>/HRC Form 388AS J (17)

Cause of Event The apparent MSSV setpoint drift could have been attributed to two factors,

1) testing method, and; 2) setpoint drift due to valve design/application.

The investigation concluded that the old testing method was inherently less accurate and had a high probability of contributing to the apparent MSSV setpoint drift.

The failure to report the incorrect readings at the time of the event is considered to be due to a procedure deficiency. The STP lacked reportability instructions in instances where the safety valves failed to be within specifications.

Anal sis of Event The safety valve setpoints discovered in this event were found to be out of compliance with the Technical Specification (T/S) 3.7.1.1 requirements and therefore reportable per 10CFR50-73 (a) (2) (i) (B). The Unit 2 as-found setpoints were below the required values in most cases. The Unit 1 as-found setpoints were mixed. Some were below the Technical Specification require-ments, and some were above. The lowest average setting that was found was for SV-lB-2 (BN-6306) at 1032 psi, and the highest was for SV-3-2 (BN-6321) at 1132 psi.

The following FSAR Chapter 14 accident analyses consider secondary-side pressure relief:

1. Loss of External Electrical Load (Appendix 14C.3.6)

2. Loss of Normal Feedwater (Appendix 14C.3.7)

3. Loss of All A.C. Power to the Station Auxiliaries 4 Steam Generator Tube Rupture (14.2.4)

5. Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in Large Pipes which Actuates the ECCS (Appendix 14E.l)

The maximum relief requirement is associated with the loss-of-load accident.

The analysis assumes that the steam dump was not available and that there was no power-operated relief valve actuation.

The deviation from the Technical Specification setpoint is judged to have minimal effect on the ability of the plant to accomodate this accident. The installed relief capacity is approximately 117 percent of the steam generation rate at full power. Thus, with a reactor trip following an accident, judged that there would be adequate capacity to relieve the steam generated it is during the transient. Thus, the pressure reached would be a function of the setpoint plus the accumulation which occurs as the valve opens.

NRC FORM 366A *U,B.OPO:(9884 r

NRC Fo m 388A U.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150&104 EXPIRES: 8/31/BB FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

YEAR K?('EC UENTIAI. REV/SION NUMBER  ?+B NUMBER D. C. Cook Nuclear Plant Unit 1 0 5 0 0 0 3 1 5 8 0 2 0 0 1 0 5oF0 5 TEXT ///'mo/o 4//4co /Fo//oko/5 I/w ////ooo/NRC %%dnn 35/IA'4/(IT)

Using the highest as-found setpoint to obtain a conservative peak pressure estimate, it is judged that the peak pressure would have been below the ASME code allowable of 110 percent of design pressure.

The low "as-found" setpoints would have resulted in the early opening of the safety valves during the accident. However, because opening of the safety valves has been considered in the accident analysis, and the magnitude of the deviation was small, plant safety.

it is judged that this would not have adversely affected Corrective Action The immediate corrective action, as required by **12MHP4030.STP.002, was to reset the safety valves setpoints to within their specified ranges. To prevent recurrence, future MSSV setpoints will be tested with an improved testing method. This will provide a more accurate determination of the MSSV setpoints.

The procedure has been modified to include instructions on reportability.

The new instructions include:

A requirement to fails to lift notify the Shift Supervisor in its specified range.

immediately if a safety valve (NOTE I This step is necessary to allow the initiation of any Technical Specification 3/4 7.1.1 action statement requirements as testing is conducted while in Hot Stand-By. The Shift Supervisor will again be notified when the valve is operable.)

A requirement to initiate a condition report as documentation of any safety valves failing to be in compliance.

Failed Com onent Identification Main Steam Safety Valve Manufacturer: Dresser Consolidated Valves Model: 3707RA-RT21 EIIS Code: RV Previous Similar Events

.LER 315/87-007-00, Main Steam Safety Valves Out of Specification Due to Apparent Setpoint Drift.

NRC FORM 366A *U.S.GPO:19884).824 538/455 I

Indiana Michigan Power Company

~

Cook Nuclear Plant P.O. Box 458 Bridgman. Ml 49106 616 465 5901 INblANA MICHIGAN POWER October 29, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-315 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:

86-020-1 Sincerely, W. G. Sm Jr.

Plant Manager WGS:afh Attachment cc: John E. Dolan A. B. Davis, Region M. P. Alexich III R. F. Kroeger H. B. Brugger R. W. Jurgensen NRC Resident Inspector R. C. Callen G. Charnoff, Esq.

D. Hahn INPO D. Wigginton, NRC PNSRC A. A. Blind Dottie Sherman, ANI Library J. G. Feinstein/B. P. Lauzau

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