ML18153A069

From kanterella
Jump to navigation Jump to search
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A069
Person / Time
Site: Surry Dominion icon.png
Issue date: 09/19/1996
From: Christian D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-489, LER-96-007, LER-96-7, NUDOCS 9609240390
Download: ML18153A069 (6)
v • d • e


Text

,,

  • 10CFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 September 20, 1996 U. S. Nuclear Regulatory Commission Serial No.: 96-489 Document Control Desk SPS:mdk Washington, D. C. 20555 Docket No.: 50-281 License No.: DPR-37

Dear Sirs:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.

REPORT NUMBER 50-280/50-281 /96-007-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.

Very truly yours, D. A. Christian Station Manager Enclosure pc: Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 R. A. Musser NRC Senior Resident Inspector Surry Power Station 9609240390 960919

oR ADOCK 05000280 PDR

NRC FORM366 (5-92)

  • U.S. NUCLEAR REGULATORY COMMISSION e

APPROVED BY 0MB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION

  • LICENSING EVENT REPORT (LER) AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) II PAGE(3)

SURRY POWER STATION, Unit 1 05000 - 280 1 OF 3 TITLE (4)

Fire Watch Patrol Inspection Frequenc, Exceeds One Hour EVENT DATE 5) LER NUMBER (6 REPORT DATE 71 OTHER FACILITIES INVOLVED 8)

MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NUMBER 05000-281 Surry Unit 2 08 21 96 96 -- 007 -- 00 09 19 96 FACILITY NAME DOCKET NUMBER 05000-OPERATING THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10 CFR:(Check one or more) (11)

MODE (9) N 20.402(b) 20.405(c) 50. 73(a)(2)(iv) 73.71 (c)

POWER 20.405(a)(1 )(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10)1 OOi 20.405(a)(1 )(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1 )(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in Abstract below and I-X 20.405(a)(1 )(iv) 50. 73(a)(2)(ii) 50.73(a)(2)(viii)(B) In Text, NRC Form 366A) 20.405(a)(1 )(v) 50. 73(a)(2)(iii) 50.73(a)(2)(X)

LICENSEE CONTACT FOR THIS LER (12)

NAME D. A. Christian, Station Manager I(804r357~31 1 84ing Area Code)

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13 SYSTEM

~

CAUSE COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (141 EXPECTED MONTH DAY YEAR I YES Of""" comDlete EXPECTED SUBMISSION DATE!

X I NO SUBMISSION DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On August 21, 1996, with Unit 1 and Unit 2 both at 100% power, fire watch patrols failed to complete fire detection zone inspections within the Technical Specifications required time period. With a fire detection panel inoperable, fire watch patrols were required to perform inspections of the affected fire detection zones "at least once per hour" in accordance with Technical Specification 3.21.B.1. The required fire detection zone inspections were performed however, the inspection period between some '

individual fire detection zones exceeded the allowed time period when a fire watch patrol was detained by Security after a security alarm was inadvertently activated.

Required fire suppression equipment remained operable. A fire has not occurred. The health and safety of the public were not affected by this event. This event was caused by inadvertent activation of a security alarm. To prevent recurrence, fire watch training is being changed to emphasize compliance with Security requirements and Technical Specifications fire watch requirements. This report is being made pursuant to 10CFR50. 73(a)(2)(i)(B), for any operation prohibited by Technical Specifications.

NRC FORM 366 (5-92)

NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3160--0104 (5-92) EXPIRES 6/31/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION LICENSING EVENT REPORT (LER) AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET. WASHINGTON, DC 20503.

FACILITY NAME 11 l DOCKET NUMBER 121 LER NUMBER (6) PAGE 131 YEAR SEQUENTIAL NUMBER REVISION NUMBER SURRY POWER STATION, Unit 1 05000-280 96 - 007 - 0 2 OF 3 TEXT (lf more apace ia required, use additional copies of NRC Form 366A) (17)

1.0 DESCRIPTION

OF THE EVENT At 1838 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />6.99359e-4 months <br /> on August 21, 1996 a fire detection panel [EIIS:IC] was declared inoperable. Fire watch patrols were initiated within one hour due to the inoperable fire detection panel, as required by Technical Specifications 3.21.B.1. Fire watch patrols were required to inspect the affected fire detection zones "at least once per hour while the fire detection panel was inoperable. Each fire detection zone inspection was performed while the fire detection panel was inoperable. However, one fire watch patrol was detained by Security when a security access alarm was inadvertently activated. The fire detection zone inspections were documented on Fire Watch Tour Documentation sheets. Required fire suppression equipment remained operable throughout this event. A fire did not occur.

A review of the Security Incident Report, Fire Watch Tour Documentation sheets, and personnel interviews, determined that a fire watch patrol had entered and inspected a fire detection zone and upon exiting the fire detection zone a security access alarm was inadvertently activated. The security access alarm occurred at 0029 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> when the fire watch patrol opened the door to exit the area prior to receiving positive egress indication on the security card reader. Security contacted the fire watch patrol using the Station intercommunication system. The fire watch patrol remained at the access door until a security officer arrived and investigated the incident as required by security procedures. The fire watch patrol was detained for approximately 13 minutes while the incident investigation was conducted. The fire watch patrol was advised by the security officer of the proper procedures and use of the security card reader. Following the security investigation, the fire watch patrol immediately proceeded to complete the-required inspections. However, as a result of being detained during the security incident, some fire detection zone inspections exceeded the Technical Specifications required frequency of "at least once per hour." Three fire detection zones were inspected 7 minutes late, two fire detection zones were inspected 11 minutes late, and three fire detection zones were inspected 13 minutes late. All other inspections were conducted in compliance with Technical Specifications and security requirements.

Although each required inspection was performed, some inspections exceeded the Technical Specifications required frequency of "at least once per hour." Therefore, this event is being reported in accordance with 10 CFR 50. 73(a)(2)(i)(B), for any operation prohibited by Technical Specifications.

r NRC FORM366 (5-92)

  • U.S. NUCLEAR REGULATORY COMMISSION
  • APPROVED BY 0MB NO. 3160-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION LICENSING EVENT REPORT (LER) AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR-REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 YEAR SEQUENTIAL NUMBER REVISION NUMBER SURRY POWER STATION, Unit 1 05000 -280 96 - 007 - 0 3 OF 3 TEXT (If more &pace is required, use additional copies of NRC Form 366A) (17) 2.0 SAFETY CONSEQUENCES AND IMPLICATIONS There are no safety consequences or implications associated with this event. The fire watch patrols were initiated within the Technical Specifications required time period of one hour. The fire detection zones requiring inspection were inspected by the fire watch patrols. The required number of inspections were performed. A fire did not occur. Fire watch personnel had received fire watch training prior to the event and remained qualified to detect, report, and extinguish fires. Fire watch personnel had been briefed regarding their duties, responsibilities, and assignments regarding fire detection zone inspections, prior to the event. Required fire suppression equipment remained operable throughout this event.

3.0 CAUSE This event was caused by inadvertent activation of a security alarm due to personnel error.

4.0 IMMEDIATE CORRECTIVE ACTIONS The Senior Reactor Operator instructed the fire watch personnel that fire detection zone inspections must be performed within Technical Specifications requirements and Security requirements. Fire watch personnel were also instructed to inform Security that they are performing the duties of a fire watch if a security alarm is activated during the performance of a fire watch patrol.

5.0 ADDITIONAL CORRECTION ACTION The fire detection panel was returned to service at 0555 hours0.00642 days <br />0.154 hours <br />9.176587e-4 weeks <br />2.111775e-4 months <br /> on August 22, 1996.

6.0 ACTIONS TO PREVENT RECURRENCE Fire watch training and associated lesson plans will be enhanced to emphasize compliance with the Technical Specifications requirements and Security requirements.

7.0 SIMILAR EVENTS There were no similar events identified.

8.0 ADDITIONAL INFORMATION None.

NRC FORM 386A (5-92)

t VIRGINIA POWER

  • LIAP-0003 ,

-REVISION 1 PAGE 30 OF 37

~

AITACHMENT 3 (Page 2 of 2)

LER Checklist LER Narrative (continued) Initials/Date Manufacturer and Model No. of each failed component ~,1 L &112b! f:-(y-Y?

Assessment of the safety significance and implications of the event pt[)£! 9-19+~

Description of corrective actions l:1!2.&J 9-if+t, Reference to previous similar events ,A.lo,11 ~

  • 1

/!17>1?-d f~f-7?

Status of unaffected unit (if applicable) '/3:rfX l~1 j 111-c-4~/ . 11AV/C- I E/f-7(,

Total accumulated ECCS actuations to date, per unit (if applicable) /1/0 r 11 fiff?!L-1 f'-/F r?,

IJpj)I, { di// e._.

LER Abstract and Narrative No typographical errors or misspelled words f.f_1ol('J- 0-1{--._,C{,

Statements of facts verified for accuracy, documented and contained in LER /.17:>/(- I Et f"-yV' permanent file.

LER Processing t NPRDS Reporter contacted J.5..;..9mponent fa,ilur_$s_ oymalfunctio 11721:1 f-tf-9~ I NPRDS reportability IV ofol t1111141er-r re--,- !ud.- -eVv<- 7 to determine Draft LER reviewed prior to distribution by Supervisor Licensing -41/Y.d ~lf-r6 LER distributed to the plant for comments f!l*{ifc I ~&--f?

Comments received and incorporated/resolved * ~ f-lf-Yb LER approved by SNSOC ( 9-1 'l-fb) 5/t/SOC. if-eg/,,Q If C/lt,,O(jt 3 *-!/,Of ~(/)/?f f~1t;--y6 LER signed by Station Manager 'f-I tf-96 /&0,C (l-1f-f'b p\"<'.,,,..._ k,."c1 I-.:

) .?MM.' f Date inserted on LER submittal letter and NRC Form 366, Item 7 (Report Date)

LER submitted to NRC

?-, f--Y 6 t4,17),.C:.. ; ;'-1 f-'P 6

___,I_ _

~u-L- ** LER copies transmitted to distribution _ __,!_ _

L LER package sent to Station Records _ __,!_ _

LER database has been updated /'1PK- I C/-tf-Y6 REVIEWER/DATE:

NOTE:* This completed form must be included in the LER package

  • LIAP-0003 REVISION!

PAGE 29 Of 3*;

.ATI'ACHNiENf J (Page 1 of 2)

LER Checklist Initials/Date LERData DR Number:-~- f_6_-4ff ,-- . L ef;)/L/ '7-/t.J-fh LER. Number: __-::-~ -d f ojf6.-Q{J 7-oC) ~ SlJ-;;;_ 9°//16-00 7-CJ 0 1

/if DJ?-! f-1 f-f7 LER Assigned to:~....r-::: ('.J.(~l:;¥-m a,,..-c 1~ * * . eYlJKL i--1H?

Letter Serial Number: £6-i?J (optional) f:(1)£/ 9-19--9,,h LER Abstract All the Form 366 Items except date of. s1,1brpiµal ar~ filled out . lt1 l>,L I f-if-9£,

5.;., b,n, l/e< I c/d:tff 1,ttlt<;z;-t( f,U.PtC--

Abstract less than 1400 characters, including spaces M7$d~a, Description of major occurrences flDJL! 9-tf-f'~

Component/system failures ~11 e_  ;,t,@?/~6 Description of corrective actions taken or planned t1-t'DJ;:__ I 9-/9-Y.,6 Assessment of the safety significance and implications of the event tHt? I y-/f~rJ, LER Narrative 10 CFR reponability requirement .or "OTHER" box chec.ked M D;L/ y-1 f-f'r;.,.

/0 CF(Z 50, 7 3 ( af:i.YO:. BJ Plant operating conditions prior to event kf1>4:-/ f-tf-Yb Structures/components/systems inoperable prior to event Af7)L! 9-tf-9?,

Dates and approximate times of occurrences faf'O,C- I f-19-90 Cause of each ceffll)oeeat failttreipn--el_e_rr_i=)_ llf~)L/ 9-!f-f ~

Failure mode/mechanism/effect of failed components tlll)/L I P-t?-7,6 EIIS component function identifiers/system names Mi),e_/ 9-;f-y~

A list affected items for multiple functional component failures /{otJL dfl:l?I P-tr-9?

Elapsed time of inoperability of failed train of safety systems M"pb I f--tf--96 Component/system failure/procedural err,PJ" discovery method

~11,u,1 evvcv- d,.scco JotJ~"o i ..... .r. /)

~ 11/ivtv\

Ji,11>K../ CJ-1f-9b1 Operator actions which affected course of events . r Mj)t;;L 9~1c;-'!~

Automatically or manually initiated ESF actuations NO'r1 L /t.,t[)!?-f f-1f--f6

Retrieved from "https://kanterella.com/w/index.php?title=ML18153A069&oldid=2403316"