ML112410930

LER 81-014/01T-0:on 810409,relief & Safety Valves Found to Be Out of Spec Setpoint.Cause Unknown.Relief Valve Pilot Assemblies Were Cleaned & Reworked.Safety Valves Will Be Disassembled & Reworked

ML112410930
Person / Time
Site:	Duane Arnold
Issue date:	04/23/1981
From:	Rager M IES Utilities, (Formerly Iowa Electric Light & Power Co)
To:	NRC/OI/RGN-III/FO
Shared Package
ML112410931	List: ML112410930 ML20003G190
References
LER-81-014-01T, LER-81-14-1T, NUDOCS 8104280452
Download: ML112410930 (5)

Text

REGULATORP INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:8104280452 DC.DATE: 81/04/23 NOTARIZED: NO DOCKET #

FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTHONAME AUTHOR AFFILIATION R;AGERM.S. Iowa Electric Light & Power Co.

RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director

SUBJECT:

LER 81-014/017-0:on 810409,relief & safety valves found to be out of spec setpoint,Cause unknown.Relief valve pilot assemblies were cleaned & reworkedSafety'valves will be disassembled & reworked, DISTRIBUTION CODE: A00S2 COPIES RECEIVED:LTR TITLE: Incident Reports

,LENCL. SIZE:, L NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: IPPOLITOT. 04 3 3 INTERNAL: A/D COMP&STRU06 A/D ENV TECH 07 1 A/D MATL & QU08 A/D OP REACTOO9 1 A/0 PLANT SYSIO1 A/D RAD PROT 11 1 A/) SFTY ASSEI ACC EVAL 6R 14 1 AEUD AEOD/DMU 3 ASLBP/J.HARD AUX SYS BR 15 1 CHEM ENG BR 16' CONT .SYS BR 17 1 CORE PERF.BR 16 DIRENGINEERI20 1 DIRHUM FAC $21v DIR,SYS INTEG22 1 EFF TR SYS BR23 EQUIP QUAL BR25 1 GEUSCIENCES 26 I&C SYS BR 29 1 I&E; 05 JORDANE,/IE 1 LIC GUID1BR 30. MATL ENG BR 32 1 MECH ENG BR 33 NRC POR 02 1 OR ASSESS BR 35 POWER SYS BR 36 1 BR3 9 REACT SYS BR 40 1

01. REL& RISK A 41 1 SFY PROGEVA42 STRUCT ENG UR44 1 EXTERNAL: ACHS 46 16 16 LPDR 03 1 1 NSIC 0 1{ 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 61 ENCL 61

Iowa Electric Light and Power Company April 23, 1981 DAEC-81-257 Mr. James G. Keppler, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission - Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Licensee Event Report No.81-014 (14 day)

File: A-118a

Dear Mr. Keppler:

In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold Energy Center and Regulatory Guide 10.1, please find attached a copy of the subject Licensee Event Report. (Total of 3 copies transmitted).

Very truly yours, Daniel L. Mineck Chief Engineer Duane Arnold Energy Center Docket 50-331 ahc ent DLM/MSR/pl cc: Director, Office of Inspection and Enforcement (40)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Director, Management Information and Program Control (3)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D. C. 20555 NRC Resident Inspector - DAEC Iunne Arnoid Enerv Center

• PO. Box 351

• Cedar Rapids, Iowa 52406 319/851-5611

U. S. NUCLEAR REGULATORY COMMISSiON NRC FORM 388 (7-M LICENSEE EVENT REPORT

- CONTROL SLOCK: L (PLEASE PRINT OR TY*M ALL REQUIRED INFORMATON) 64 NUMBER 25 26 LICINS1 E JO 7 89 LICENS91CE 14LsCEN34 CON'T CON T LIJ 0 15 10 10 1313 1 n 14 n I9q 1 1 10 1 4 12 L3LL.J SI OOCKET NUMBEA 61 69 EVENT OATS 74 75 AEPORT DATE O s C 60 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES oI Durin-g annual testing of relief (R/V')-and safety (SlyV) valvec, fiyr. RIV-,

owere found with out-of-spec as found setpoints, One S/V initially liftpd I

5sFT4 at an out of tolerance value and began leaking after testing- One R/V wa I

r-051 13 PSI high, one R/V was 3-PSI low, and two--R/Vs were 9 PST low. T-c-2-2 I 1 j ro 61lists required setpcdints. Out of sper stpoint--wi1rl not rpjr-r e "eSp

-I 07loverpressure protection sys capability. Two-prey reports(R.0- 80-10 and 7 J

60

-o7 18-18)have been submitted since 1977 valve installation, 7s9SYSTEM CAUSE CAUSE COMP. VALVE CODE SUSCODe COMPONENT CODE SUSCODE SUBCOOE COE 9

S LF E IB 13 VI AIL VIEIXI3 LPJ0 II 1 t 10VISION 7 a EVENT YEAR 0 12 SEQUENTIAL REPORT NO.

OCCUR COO EcE E TYPE NO.

[81_j -REPOT 0 11 14j j 101 1 Li NUMBER 21 22. 23 24 26 27 29 29 30 Stp EFFECT SHIUTDOWN AT'TACHMENT 4PAO-A PRIME OP COMPON ENT ACTION FUTURE MANUFACTURE ONACTION ONPLANT mET)400 HOURS SU ITTEO FORM tU6. SUPPLIER IT 1 2 10~J

'4 47 36 3 40 42 43 33 34 35 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS 0 io Cause unknown. Test facility did not identify a-definitive cr:ise tinr tie

-aeqmh ip-, iwipr crpanrd alnd ra liout of- specification setponints- Ell pilIot worked as required and retested satis factorily. S/V will be disassembled and reworked prior to retestinai R/V are Taraet Rock Type 67F-6X10- S/V pring safety valve.

7 ri 82 ls Drssow *a nsres odel YAu 300 (o METHOO OF FACILITY DISCOVERY DISCOVERY DESCRaPTION STATUS %POWER 01141R STATUS \...

E [H @J101 01 01 NA LL~J(DIsurveillance Testing g8 to 12 '1 45 4so ACTIVITY CONTENT LOCATION OF RELEASE 0 RELEASEO OF RELEASE AMOUNT OF ACTIVITY I NA E I 1 @ 17J(l NA '5 4s 7 8 9 10 i tA

• PERSONNEL EXPOSURES SLUAMER TYPE OESCRIPTiCN o 10 10lOQZ@LIJ1I 1 2 13 NA I 89 PERSONNEL INJURIES NUMBER OSCAlPTIN In I I9 I t 12 LOSS OF OR DAMAGE TO FACILITY 4 TYPE OESCRIPTION 7 8 9 Z L(I) 10 NA so PUBLICITY NRC USE ONLY ISSUED OtSCRIPTION W@I

_(70 NA t I. 1 11L 1 I 1 1I1 7 9 10 68 69 8o.

..NAM...F Ri.P . Matthew S. Rage r

• 319-851-5611

.DUANE ARNOLD ENERGY CENTER*.

Iowa Electric Light and Power .Company Licensee Event Report - Supplemental Data Docket No. 050-0331 Licensee Event Report Date: April 23, 1981 Reportable Occurrence No: 81-014 Event Description During annual surveillance testing of safety/relief valves, four relief valves were found to have out of specification as-found setpoints. Additionally, one safety valve initiallylifted at an out of tolerance value and was leaking at the completion of testing. All six main steam relief valves and one safety valve were tested. The following is a tabulation of as-found test results:

Valve Serial No. Required Setpoint As-Found Setpoint S/V BM 8491 1240 +/- 12 PSI 1310 PSI R/V 189 1100 t 11 PSI 1080 PSI R/V 218 1080 +/- 11 PSI 1094 PSI R/V 226 1090 +/- 11 PSI 1076 PSI R/V 227 1110 +/- 11 PSI 1090 PSI R/V 199 1100 +/- 11 PSI 1100 PSI R/V 176 1110 +/- 11 PSI 1119 PSI The safety valve initially lifted at 1310 PSI. Subsequent tests found the valve to lift at 1253 PSI (1PSI out-of-tolerance) and then the valve lifted within Techni cal Specifications 2.2.1.C limits four consecutive times..

Although four relief valves were found to lift at setpoints in excess of their nameplate setpoint tolerances, there was one valve with an as-found setpoint within tolerance for each of the Technical Specifications required relief valve settings.

There have been two previous event reports submitted (See RO 78-18 and 80-10) since the installation of Target Rock model 67F-6x10 pressure relief valves in 1977.* The testing was performed at Wyle Laboratories in Huntsville, Alabama while DAEC was in a normal refueling outage.

Cause Description Cause unknown. Test facility personnel were unable to determine a definitive cause for the out-of-tolerance setpoints.

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.DUANE ARNOLD ENERGY CENTER Iowa Electric Light and Power Company Licensee Event Report - Supplemental Data Docket No. 050-0331 Licensee Event Report Date: April 23, 1981 Reportable Occurrence No: 81-014 Corrective Action The relief valves were disassembled, cleaned and reworked. The valves were sub sequently retested and performed satisfactorily. The relief valves are Target Rock 67F-6X10 Safety Relief Valves.

The safety valve will be disassembled and reworked prior to retesting. The safety valve is a Dresser Industries model 3800 Spring Safety Valve. The surveillance test frequency will be increased such that this valve will again be tested during.

the 1982 refueling outage.

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