ML18153C597

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LER 91-001-00:on 910307,block Valves Declared Inoperable Until Required Surveillance Testing Satisfactorily Complete. Caused by Personnel Error.Task Team Formed to Address Missed Surveillance & Other Recent Similiar events.W/910405 Ltr
ML18153C597
Person / Time
Site: Surry Dominion icon.png
Issue date: 04/05/1991
From: Kansler M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-193, LER-91-001-02, LER-91-1-2, NUDOCS 9104160505
Download: ML18153C597 (7)


Text

.ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM

! *.

  • e. *e *

\i' REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

  • .ACCESSION NBR: 9104160505. . DOC.DATE: . 91/.04/05 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

SUBJECT:

LER 91:....001-00:on 910307,block valves declared inoperable* I until required surveillance testing satisfactorily complete~

Caused by personnel error.Task team formed to address missed D f.iurveillance & other recent similiar events. W/9_10405 1 tr.

DISTRIBU'I'ION CODE: IE22T. COPIES .RECEIVED:LTR l_ ENCL _j_ SIZE:_.~-*-=-b_ _ __

s TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc .. I NOTES:lc:y NMSS/IMSB/PM. 05000281 A RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID.CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 p BUCKLEY,B 1 1 s

INTERNAL: ACNW 2 2 ACRS . 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP

  • 2 2 NRR/DET/ECMB 9H 1 1*

NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFBll 1 1 NRR/DLPQ/LPEBlO 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 ~ L B 8 D l * .. 1 1 NRR/DST/SRXB SE 1 1 .. 02 1 1 RES/DSIR/EIB .1 1 . G 2 FILE 01 1 1 EXTERNAL:* EG&G.BRYCE,J.H 3 3

  • L ST LOBBY WARD 1 1
  • NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT* *1 1 R NOTES: 1: . i. I D

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A D

D NOTE TO ALL "RIDS" RECIPIENTS:

s PLEASE HELP US TO REDUCE WASTE! CONTACT THE,DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED

.TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL 34

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\

Virginia Electric and Power Company Surry Power Station P. 0. Box 315 .

Surry, Virginia 23883 April 5, 1991 U; S. Nuclear Regulatory Commission Serial No.: 91-193 Document Control Desk* . *

  • License No.: DPR-37 Genthimen:

Pursuant to Surry Pow:er Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licen-see Event Report for Unit 2.

REPORT NUMBER 91-001-00 This report has been reviewed by the.Station Nuclear Safety and Operating Committee and will be.reviewed by the Corporate. Management Safety Review Committee.

Very truly yours, M. R. Kansler Station Manager

  • Enclosure cc: Regional Administrator Suite 2900 .

101 Marietta Street, NW Atlanta, Georgia 30323 910416050~ ~10405 F'[IR ADOCK 05000281 PDR

!=~

e NRC FORM 366 U.S. NUCLEAR R(.:GULATORY COMMISSION (6-89)

  • APPROVED 0MB NO. 3150-0104

- "EXPIRES: 4/30/92. .

ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE*RECORDS

  • AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 11) DOCKET NUMBER (2) PAGE (3)

TITLE (4)

Surry Power Station,_ Unit 2 01s101010'2 1811 I 1 OF nI c;

  • Failure to Demonstrate PORV Block Valves Operable.Due to 'Personnel Error EVENT DATE (5) LER N_UMBER (6) REPORT DATE (7)_ OTHER FACILITIES i"NVOLVED (Bl MONTH DAY YEAR W,R  : ] } SE~~i~I~AL &< ~~~~~~ MONTH DAY*. YEAR FACILITY NAMES DOCKET NUMBER(SI o I* 3 oI 7 9 1 911 - o Io I 1 -:- 01 o oI4 0 1s 9J 1 -0 1 5 r O I O I O.1 I I THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Ch*ck on* or moro of th* foliowing) (11) i--~---------.....-~---------r'---r-------,-----r----.------,--------t OPERATING MODE (Bl N 20.402(b) 20.405(1)(1 )(i) 20.405(c) 60.38(c)(1) i-60.73(1)(2Hiv) 60.7311ll2lM

- 73.71(b) 73.71(c) 1--- I--

20,406(1)(1 )(ii) 50.38(c)(2) 50.73(1)(2l(vll) OT.HER (Sp,Jcify in Abstr*ct I-- bt1low *nd in Text, NRC Form 20.406(1)(1 )(iii) X so.13(1J12uii (B) 60.73(1)(2Jlvlll)(A) 366A) 20.405(1)(1 )(Iv) 60,73(1)(2)(ii) 60.73(1)(2)Mli)(B)' .

..__ 1---

20.406111111M 50.73(1)(2)(iii) 60.73(1)(2)(x)

LICENSEE CONTACT FOR-THIS LER (121 NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station Manager 8 I OI 4 3 I 5 I 7 1- I 3 11 I 81 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC- MANUFAC-CAUSE SYSTEM COMPONEIH TURER TURER I I I I I .I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED n ~

SUBMISSION*

DATE 115)

YES (If yos, comp/er. E~PE"CTED SUBMISSION DA TEI NO I I I ABSTRAC'T'. (Limit to 1400 spacBJ, i.e.* approximately fiftst1n sing/e-spac~ typewritten lines). (16)

On March 7, 1991, at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, with Unit 2.at 87% power, it was discovered. - that the Pressurizer Power Operated Relief Valve (PORV) Blocking Valves (2-RC-MOV-2535 and 2-RC-MOV-2536)" had not been demonstrated operable at least once during the previous 92 days. This failure is a violation of

. Technical Specification 4.LB.2. The block valves were declared inoperable until the required surveillance testing was satisfactorily *accomplished. Since. the** PORVs-** remained operable throughout the period, the health and safety of. the.

public were not

  • affected. . The cause of the event was personnel error. A Task Team was formed to review this and similar events, and appropriate corrective* action is being taken. This event is being reported pursuant to 10CFR50.73(a)(2)(i)(B).

NRC Form 366 (6-89)

NRC l'ORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-89\ . .. APPROVED.OMB NO; 3150-0104 .

  • . EXPIRES: 4/30/92 . * .
  • ATED BURDEN PER RESPONSE TO COMPLY WTH THIS LIC:~NSEE EV. REPOR; (LER) .INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER 121 LER NUMBER (61 . PAGE (3)

Surry Power Stat;ion, ..Unit 2 o 1s Io Io Io I 21 s 11 911* - 010 11. - 010 012 OF 01-s TEXT (If more 8/MCS iu*quired, UIIO additiana/ NRC Fann a'6A '11/ (17) 1.0 m:scRIPTION OF THE EVENT On March 7, 1991, at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, with Unit 2 at 87% power, it was discovered that the Pressurizer Power . Operated

  • Relief
  • Valve (PORV) Block Valves, 2-RC-MOV~2535 and 2-RC-MOV-2536 [EIIS-ISV, AB] had not beeri demonstrated operable at least once during the previous 92 days. This failure is a
  • I I

violation of Technical Specification 4.1.B .2. The block valves I were declared inoperable, and a one-hour action statement was entered to restore operability or close the block valves and remove power m . accordance with Technical Specification 3.l.A.6.c. . At 1626, the appropriate surveillance testing was completed satisfactorily, the block valves wer~ declared operable, and the action statement was exited~

2. 0
  • fil.GNIFICANT SAFETY CONSEQUENCES AND IMPI,ICATIONS ..

The remotely operated block* valves are designed to provide*. a .

positive shut off capability should a PORV become inoperable.

The PORVs

  • remained operable throughout . this period; therefore, the health and safety of the public were not affected.

3.0 ~USE OF THE EVENT The event was caused

  • by personnel error. The Engineering Testing Department . is charged with the responsibility for preparation, coordination, and maintenance of the periodic test scheduling and tracking program for the
  • station.
  • Schedullng 1s accomplished by preparmg a master planning schedule for surveillance items for which a known frequency exists. This schedule covers testing coming* due during the following month and 1s distributed
  • to implementing _departments one to two weeks prior to the beginning of the. month. Also provided at this time are the individual scheduling data sheets for each NRC ""'1t> :wlA IS.S9l

NRC FORM 366A . . U.S. NUCLEAR REGULATORY COMMISSION 16-89) APPROVED 0MB NO. 3150-0104 . . .

EXPIRES: 4/30/92 . . . . . .

  • IMATED BURDEN PER RESPONSE TO COMPLY.WTH THIS .

LIC:ENSEE. EVIT REPORT (LER) . . INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION.WASHINGTON, DC 20555, AND TO I THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 11) DOCKET NUMBER (2) LER NUMBER 161 PAGE 131 VEAR ,*,*,*,*,*, SEQUENTIAL ,:,,:,:,:, REVISION

,:,:,:,:, NUMBER ..... NUMBER
  • Surry Power Station; Unit 2 o 1s Io Io Io I 21 s 11. 911 - o I 011 - 01 o o 13 oF o Is TEXT (N tn019 apactJ ia r9qui/ed, use odditiona/ NRC Form .BA'aJ 1171 .

sur-veillance test

  • which is to be performed.
  • Each scheduling sheet delineates the acceptable time window. during which the test: is to be .performed. After the test has been performed, the

_filk~d out sheet 1s attached to the completed test procedure and provides a means to feed back information to* the *Engi_neering Testing Department. This information

  • is used to update the sch,eduling and tracking program.

In this instance, a new PORV block valve surveillance pro,:;edure was prepared in December 1990. The - new procedure did n'ot appear on the January 1991 master. schedule because it was approved subsequent to the promulgation of the master planning schedule. The new procedure was not added to the January schedule. because of administrative error.

Normally, Engineering Testing also distributes a Daily Periodic Test Report - for surveillance tests with scheduled date,

  • fate date, and days late tabulated. This report is generated on a dail-~ basis for overdue surveillance tests and on a weekly
  • basis
  • for pending surveillance tests with an interval of quarterly or greater. Because of a management decision to change the permissible "grace period" during which a surveillance could be accomplished from +/-25% to * +25%/-0%, a maJor reprogrammrng .effort was taking place in the Engineering Testing Department. Because of this added
  • work load, the weekly reports were not issued from late December, 1990, until early February, 199L When the issuance of the weekly report was resum~d on February 12, 1991, it showed the PORV
  • block valve surveillance due on February 14. This notification faile~I to alert the department responsible for the test. The daily overdue report dated February 15, *1991 showed the test as one day overdue. Although the subsequent daily_ and weekly reports
  • showed the surveillance as overdue, no action was taken by the implementing department until March 7.

NRC Form 3liQA. C:G,-891

.e NRC.FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 16-89) - APPROVED 0MB NO. 3150-0104

  • EXPIRES: 4/30/92

. ESTIMATED BURDEN PER RESPONSE TO COMPLY .WTH THIS LICE:NSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 11) DOCKET NUMBER 12) LER NUMBER 16) PAGE 13)

Surry Power Station, Unit 2 o 1s Io Io Io 12 1s 11 9 11 - 01 o 11 - o 10 oI 4 oF o 1s TEXT '" mom apaCtJ i8 roquim, USII additional NRC Form 366A 'al 117) 4.0 nn1EDIATE CORRECTIVE ACTION(S}

The block valves were declared inoperable and a one-hour action statement was entered to restore operability or clos_e the block valves and remove power (re: Technical Specification 3.1.A.6.c). The appropriate surveillance testing was performed

  • satisfactorily, the block valves were declared operable, and the action statement was exited.

5.0 ADDITIONAL CORRECTIVE ACTION(S}

  • A task team was farmed to address this missed surveillance and other recent similar events at the station.

6.0 ACTIONS TO PREVENT RECURRENCE The task team's review found that current administration of the surveillance test program was adequate and complied with station administrative directives. The Team also found that certain improvements could be made, including increased supe:rvisory involvement, strengthened scheduling and tracking practices at the departmental level, and better communications between Engineering Testing and other departments. Accordingly, departments which perform surveillance testing will be required to review their internal administrative practices and take appropriate actions to strengthen their controls over the scheduling and tracking of surveillance testing. In addition, an administrative process which will provide prompt feedback to the Engineering Testing Department upon completion of surveillance testing will be evaluated.

lfflC t-ORM 366A : U.S. NUCLEA.R.REGULATORY COMMISSION (6-1!9) .

a APPROVED 0MB NO. 3160-0104 EXPIRES: 4/30/92 .

-ATED BURDEN .PER RESPONSE TO COMPLY WTH THIS UCIENSEE EV.

  • REPORT (LER) INFORMATION COLLECTION *REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION . AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20655, AND TO

.,I. THE PAPERWORK REDUCTION PROJECT *(3150-01041, OFFICE OF MANAGEMENT*AND BUDGET. WASHINGTON, DC 20503.

FACILITY NAME (11 DOCKET. N_UMBER (21 LER NUMBER (6) PAGE (3)

Surry Power Station, Unit 2 o 1s101010121 s11 911 _0*1011 _o 1o 01s oF 01s TEXT (ff mor9 .,,.. . ;,, f9qU/19d, UltHJddfflon,I_NRC.Form366A'a) (17)

  • 7. 0 ,SThfILAR *EVENTS LER 1-90--007-00: ,Fire Protection Dampers Surveillance Procedure Not Perfo;rmed *within Technical

.Specification Required Interval Due to Administrative Oversight*

LER 1.-89-034-00: Failure to Sample Service Water From Component Cooling Heat Exchanger Within Twelve Hours Due to Personnel Error LER 1-89"'018-00: Failure to Obtain the WGDT Sample Within Technical Specification Required 24-Hour Frequency Due to Personnel Error

8. 0 ADDITIONAL INFORMATION None.