ML18153C132

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LER 90-002-00:on 900205,two Control Rods of Control Bank D Differed from Rod Group Demand Counter by Greater than 12 Steps.Caused by Inadequate Procedures.Rampdown Stopped & Individual Rod Position Indicators adjusted.W/900307 Ltr
ML18153C132
Person / Time
Site: Surry Dominion icon.png
Issue date: 03/07/1990
From: Kansler M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-118, LER-90-002-01, LER-90-2-1, NUDOCS 9003150362
Download: ML18153C132 (5)


Text

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r-ACCELERA'TED DISTRIBUTION . DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9003150362 DOC.DATE: 90/03/07 NOTARIZED: NO DOCKET#

FACIL: 50-281 Surry Power Station,.*.unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION

. KANSLER,M. R. Virginia Power ,(Virginia Electric & Power Co.)

RECIP.NAME RECIPIENT AFFILIATION

._:"r\:'*. R

SUBJECT:

LER 90-002-00: on 9oc(205, inoperable individual rod position I indicators due to i:hstrument drift .

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  • DISTRIBUTION CODE: IE22T ¢OPIES RECEIVED:LTR ( ENCL { SIZE: 4 s TITLE: 50.73/50.9 Licensed Event Report ( LER) , JncidentRpt, et_c______

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NOTES: lcy NMSS/FCAF /PM.*_.:/ 05000281 I A

RECIPIENT COPIES . RE~IPIENT COPIES ID CODE/NAM,E LTTR ENCL . _ID :..C-ODE/NAME LTTR ENCL . D PD2-2 LA 1 1 PD_:1Jf* PD 1 1 BUCKLEY,B 1 1 D INTERNAL: ACNW 2 2 ACRS ,, 2 2 s AEOD/pO.!-\. 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DET/ECMB 9H '.1 1 NRR/DET/EMEB9H3 1 1 NRR/DET/ESGB 8D 1 ,1 _NRR/DLPQ/LHFBll 1 1 NRR/DLPQ/LPEBlO 1 1 NRR/DOEA/OEABll 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DS'l;'/SICB 7E 1 1 NRIY...D.£fil/~B8 Dl 1 1 NRR/DST/SRXB 8E RES/DSIR/EIB 1

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EXTERNAL: EG&G WILLIAMS,S 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 *_.l NSIC MURPHY ,*G.A. 1 1 R NUDOCS FULL TXT 1 .1 I

NOTES: 1 1 o.

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D NOTE TO ALL "RIDS" RECIPIENTS:

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PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 'llXJ79) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38

VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 315 Surry, Virginia 23883 March 7, 1990 U.S. Nuclear Regulatory Commission Serial No.: 90-118 Document Control Desk Docket No.: 50-281 Washington, D.C. 20555 License No.: DPR-37 Gentlemen:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Unit 2.

REPORT NUMBER 90-002-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and ~dll be reviewed by Corporate Nuclear Safety.

Very truly yours, Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323

POW 28-06-01

' NRC F,.,in 3H U.S. NUCLEAR REGULATORY COMMISSION 19-831 APPROVED 0MB NO. 3160-0104 EXPIRES: 1/31/1111 LICENSEE EVENT REPORT (LERI

,J FACILITY NAME,111 DOCKET NUMBER (21 PAGE 131 Surry Power Station, Unit 2 1]0FJ°'13 T!TLE ;4*

!o 1s10101012,s, 1 Inoperable Individual Rod Position Indicators Due to Instrument Drift EVENT DATE (51 LEA NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVEO 181 MONTH CAY YEAR YEAR t:t SE~~~~~~AL (\ ~~1~'r.: MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI ol 2 oI s 9 o 9I o - oI oI 2 - o lo oI3 o 11 9 I o OPERATING THIS REF'ORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS QF 10 CFR S: tCeock o"* o* ~o** of 1"* *o,ro.,,,ngi !111 MODE 191 73.71 lbl 20.4051cl S0.7Jl1112llovl I--

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II0.38 (cl!21 II0.73(11(21!11 II0.73(11(21(*1il II0.73(olt21!*111l!AI

..__ OTHER /S,>>cify in Ab1tnct

/Mlow *nd in T*xr, NRC Form 366A}

- II0.73t11t21tlll II0.73t11t21UIII II0.73(11!:ZI !*liiltBI II0.73tolt21txl LICENSEE CONTACT FOR THIS LEA (121 NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station Manager 8 1 0 I 4 3 1 5 I 7 1- I 3 i 1 I 31 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 r:,:::::::::,:;:::::}:::-::::-:-:-:-.

REPORTABLE I:::':{:,::::::;

CAUSE SYSTEM COMPONENT MANUFAC*

TURER TO NPRDS }2}]:-:::::::::::  ::::::-:-:, -:,

::::::':':-: CAUSE SYSTEM COMPONENT MANUFAC*

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  • I I I I I I I I I I I I I I I IUPPLEMENTAL REPORT EXPECTED t141 MONTH DAY YEAR EXPECTED

.n YES /If yn, *"-Pl*to EXPECTED SC/8/lf/SSION DATE/ . ~ NO

  • SUBMISSION DATE !151 I t I On February 5, 1990 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> with Unit 2 at 777, power during a rampdown from 1oor, power for cleaning the condenser water boxes, the control room operator observed that the Individual Rod Position 11 Indicato:rs (IRPis) for two control rods of control bank "D differed from the rod group demand counter by greater than 12 steps. The IRPis were declared inoperable in accordance with Technical Specification 3.12.E. The cause of the event was inadequate procedures in that no specific criteria had been provided for stopping a power ramp when trends indicated that IRPis were drifting out of specification. The rampdown wa:s stopped and the IRPis adjusted to within the required T.S. tolerance. Operating procedures are being revised to require that a power ramp be stopped if an IRPI deviates 10 or more steps from the rod .grbup demand counter.

NRC Form 3M 19-831

HIIC fOIIM>MA U.1. NUCLlAII IIEOUU.TOIIY COMMISSION IMIII . Arl'ROVED OMI HO. 3150-0ICM

  • IXl'IIIU: 4/'XJlll2 ATED IURDEH l'EII IIESl'ONIE TO COMl'LY WTH nos ll~!ENSEE EV- REPORT (LER)
  • IIMATION COLLECTION IIEOUEST: IO.O HAS. fORWAIIO CIC*MENTS IIEGARDING IURDEN ESTIMATE TO THE IIECOIIDS TEXT CONTINUATION NtlD IIEl'ORTI MANAGEMENT IRANCH IP.S301 U I NUCLUJlt I RIEGULATORY COMMISSION WASHINGTON rx;' 20556 AND TD THE PAl'ERWORK IIEOUCTION l'IIOJECT 13150-0ICMI' OHta OIi' MANAGEMENT AND IIUDGET, WASHINGTON, DC 20503.

fACILITY NAME 111 DOCKET NUMSEII 121 LEII NUMHII Ill l'AOI IJI

'\':*::. SE QUENT I At.. ll"fVISIO" Surry Power Station, Unit 2 ~" ~U,.._9[11111

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o 1s1010101 2 181l 910 o I o12 o,o 012 OF 0 13 1.0 pescription of the Event On February 5, 1990 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> with Unit 2 at 77"/.

power during a rampdown from 100% power to clean condenser water boxes, two Unit 2 "D" bank Individual Rod Position Indicators (IRPI) (EIIS-ZI) for control rods (EIIS-ROD) F-6 and K-6 were observed by the control room operator to differ from the control rod group "D" dema*nd counter position (EIIS-GTR) by greater than twelve steps.

The IRPis, F-6 and K-6, were declared inoperable at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> in accordance with Technical Specification 3.12.E. The IRPis were calibrated and returned to s,ervice on February 5, 1990 at 2332 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.87326e-4 months <br />.

2.0 Safety Consequences and Implications The IRPis provide individual control rod position indication in the main control room. The control rod group demand counters which indicate control rod group position as demanded by the rod control system (EIIS-AA) remained operable during the event. In addition, inoperable IRPis do not affect the operation of the control rod assemblies (EIIS-ROD) and all control rods were capable of being dropped if required, into the reactor core. Therefore, the health and safety of the public were not affected.

3.0 Cause Thi::! cause of the event was inadequate procedures in that no specific criteria were provided for stopping a power ramp when trends indicated IRPis were drifting out of specification. IRPis are known to drift when reactor coolant system temperature changes. Reactor coolant temperatures had dropped approximately six (6) degrees Fahrenheit, coincident with the unit rampdown, when the IRPis were observed to have deviated from the demand counters by greater than twelve steps.

Operators were alerted to a 10 step IRPI deviation by a computer alarm, however, the rampdown was not stopped until a 12 step deviation was noted.

NIIC , _ *"18-891

NIIC fOIIMJMA U.1. NUCUAII IIEQULATOIIY COMMISSION

!MIii . Al'l'ROVED OMI HO. 3150~1~

IXP'IIIU: 4/l1J/'12

' TED IURDEN rEII IIESP'ONIE TO COMPLY WTH THIS Llt:ENSEE EV. REPORT (LERI -OfllMATION COLLECTION l'IEOUEST: IIO.O HRS. l'ORWAl'IO CIC)IAIENTI IIEGARDING IUl'IDEN ESTIMATE TD THE IUCOfU>IS TEXT CONTINUATION A///IO l'IEl'ORTI MANAGEMENT IRANCH 1'~301, U.I. NUCLLUI IIEGULATORY COMMISSION, WASHINGTON DC 206&11 AND TC 1'NE P'AP'EfllWOIIK fllEDUCTION P'"°-'ICT f31II0~1~1* OFl'la OF IIANAGEMENT AND IUDGET, WASHINGTON, DC 40603, fACILITY NAME Ill DOCKET NUMIEII 121 UII NUMIEl'I Ill 'P'AQl 131 Surry Power Station, Unit 2 0 15 1°1010121811 910 o I ol 2 4, 0 _Immediate Corrective Action(s)

The rampdown was stopped and primary temperature stabilized. The affected IRPis were calibrated to within the required T.S. toleranca and were returned to service at 2332 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.87326e-4 months <br />.

5.0 Additional Corrective Action(s)

None.

6.0 Action(s) Taken to Prevent Recurrence Following past occurrences of similar events, operators were instructed to more closely monitor IRPis during planned primary temperature changes and i:nitiate appropriate corrective actions when trends indicate the IRPis are drifting out of SP.ecification.

These instructions, however, did not provide specific criteria for stopping a power ramp when such drift occurred. To prevent recurrence, operating procedures are being revised to require that a power ramp be stopped when an IRPI deviat~s 10 or more steps from the rod group demand counter.

7.0 Similar Events Unit 1 LERs: 88-026, 88-024, 88-0}0,88-006, 88-002,86-021, & 85-019.

Unit 2 LERs: 88-020, 88-012,88-007, 88-003,86-019 & 85-009.

8.0 Manufacturer/Model Number(s)

Magnetics Inc./Project #K9391, K9392.

NIIC , _

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