ML20045B931

From kanterella
Jump to navigation Jump to search
LER 93-013-00:on 930514,fire Watch Was Not Performed within Time Frame Required by Tech Specs Due to Inadequate Supervision by Fire Protection Foreman.Fire Watch Patrol reestablished.W/930610 Ltr
ML20045B931
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 06/10/1993
From: Bajraszewski J, Fenech R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-013, LER-93-13, NUDOCS 9306210281
Download: ML20045B931 (7)
v • d • e


Text

- _ _ = --. . _-

A Tenner.see vaney Authonty. Post OfSce Box 2000. Soddy-Daisy, Tennessee 3737'J 2000 s

Robert A. Fenech

%c.e Premdent. Sequoyah NutJear Plant June 10, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - DOCKET NOS. 50-327 AND 50-328 - FACILITY OPERATING LICENSES DPR-77 AND DPR LICENSEE EVENT REPORT (LER) 50-327/93013 The enclosed LER provides details concerning a failure to perform a fire watch within the timeframe required by technical specifications.

This event is being reported in accordance with 10 CFR 50.73(a)(2)(1)(B) as an operation prohibited by technical specifications.

Sincerely,

f. J eA-.

Robert A. Fenech Enclosure ec: See page 2 170LC6 ,

93062102B1'.93061O E

/' }

{DR ADOCK 0500 7 f -

[l

1

]'

U.S. Nuclear Regulatory Commission Page 2 June 10, 1993 cc (Enclosure):

INPO Records Center ,

Institute of Nuclear Power Operatiens 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission a One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator -i U.S. Nuclear Regulatory Commission ;j Region II ,

101 Marietta Street, NW, Suite 2900 l Atlanta, Georgia 30323-2711 L i

l i

s -

NRC f orm 366 U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EV G T REPORT (LER)

FACILITY NAML (1) lDOCKETNUMBER(2)lPAGE(3)

_Srnvoyahl(vclearJ1rtt_130!!LJait 1 101S}DISj0J3_j2_lLill0fLDLs TITLE (4) la ihre_t o _ferlo rsa _Eirelaith_W Lt ttindhe_li tnefrawrRe q uitrLby_lesh nical_S nes.ilica t inn s

_EVLRLyAL{51_1 _.LEJL14UMBIRJb) l REPORT DATE (7).I OIMELEAC11111ESJNY01yLL(B) l l l l l5EQUENTIALl l REVISION l l l l FACILITY NAMES .lDOCKETNUMBER(S) tdt 11BLDALl1EAL}XEALl I NUtjDER l lNUMQERlHONTHl_pALlYEARl Seaunyah. Unit 2 1Dj$jAjalDj3J2]L ;

I I I Li LI I I 1 I l ,

.s L51J i lla lJ L9 L3 L LLLL IJJJ _0_ LLlalJ LL10_L2 L31 Js1510J01DL L L OPERATING l lTHIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS Of 10 CFR $:

H0DE I LJcheck_snt_nt more of thelo11nwino)(11)

[91 ljiLl20.402(b) l_l20.405(c) l_l50.73(a)(2)(iv) Ll73.71(b)

POWER l l__l20.405(a)(1)(1) l_l50.36(c)(1) l_l50.73(a)(2)(v) l_l73.71(c)

LEVEL l l_l20.405(a)(1)(ii) Ll50.36(c)(2) l_l50.73(a)(2)(vii) Ll0THER(Specifyin

__L10 LL OLD L01_ l 20. 405 ( a ) ( 1 ) ( i i i ) l xx 150. 73 ( a ) ( 2 ) ( i ) l_l50.73(a)(2)(viii )( A) l Abstract below and in l_l20.405(a)(1)(iv) l_l50.73(a)(2)(li) Ll50.73(a)(2)(viii)(B)l Text, NRC form 366A)

__ _ _ _ L 12D M 3La)(1)fv) I 159213(11(211111) l ISD2 Diam 2)(x) I

_ ._ _ LIELt!SELCDIUACLEOR_It!!LLERll2 )

NAME l TEEEft!QNE NUMBER lAREACODEl

.1Jej rmewstimCowlicatelisensina 1 6 1_Ll 5 I 8 1 4 1 3 1 - l 7 1 1_ l 4 1 9

___. ._ .__CDMPLETLDNLLINEl0R_EAEtLEQLPONDiLfAILURLDf1CEIDERJ1LTELS_REPORLi]3) l l l l REPORTABLE l l l l l l REPORTABLE l c Au st i sts u nIDMPfuRILl tW1UI ADMRERjj QJLPFaSJ IEAUSElHntttLcDMefLNEt(LINABULASIURERl TO NPRp1_l i I I I I I I I I 1 I

._ L L _LLLL_LLI I I L i 1 I .I I I I I I I I I I i l i I I I I I I I I El LLL1 1 ! !1  ! I I  ! I I 1 11 I I I LJ l SUPELEMEDIALREEDR_LEXEEC1ED P (14) l EXPECTED lt!QtJHjil DAY l YEAL

_ l__ l SUBMISSION l l l

_._J J E S jlLy e n_c owle EnlXEECl ELSUSMLS S 10tLRA ILL_j jj _t40 I DAIE_115LLI I 1_J l ABSTRACT (Limit to 1400 spaces, i.e., approximately fif teen single-space typewritten lines) (16)

On May 14, 1993, at 1315 Eastern daylight time, it was discovered that a fire watch patrol was not performed within the timeframe required by technical specifications. The fire watch patrol had been established in the diesel generator (D/G) building as a compensatory measure for a breached fire door. The fire watch evacuated the D/G building when a fire panel alarm sounded. The fire watch mistakenly believed that th3 alarm was the carbon dioxide actuation / evacuation alarm. The fire panel alarm was in response to smoke from welding that was in progress in the shop area of a different site building. The alarm was reset in five minutes; however, approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minuten elapsed before the fire watch returned to duty. The cause of the late performance of the fire watch patrol was inadequate supervision of the fire watch j individual by the fire protection foreman. The fire watch patrol was subsequently reestablished. Personnel involved were counseled on their responsibilities concerning the SQN Fire Protection Program. l NPC f orm 366(f>-89)

NRC f*orm 366A U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92

, LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) lDOCKETNUMBER(2)l LER NUMDEE_(6) I l PAGE (3) l l l l$EQUENTIALl l REVISION l l l l l '

Sequoyah Nuclear Plant (SQN), Unit 1 l lYEAR l l NUMBER l l nut 1Q d l l l l ID15]DlDlDILlLILlLl3_l l 0 l 1 1 3 l--I o I O I OL2101LaLs._

TEXT (If more space is required, use additional NRC form 366A's) (17)

I. PIANT CONDITIONS Unit I was defueled and Unit 2 was in Mode 5, cold shutdown for a forced outage.

II. DESCRIPTION OF EVENTS A. Ev_ent <

On May 14, 1993, at 1315 Eastern daylight time (EDT), it was discovered that a fire watch patrol was not performed within the timeframe required by technical specifications (TSs). A fire watch patrol had been established in the diesel generator (D/G) building (EIIS Code NB) as a compensatory measure for a breached fire door. The fire watch evacuated the D/G building when a fire panel alarm (EIIS Code IC) in the D/G building sounded. The fire watch mistakenly believed that the alarm was the carbon dioxide (EIIS Code LW) '

actuation / evacuation alarm. The fire panel alarm was in response to smoke from welding that was in progress in the shop area of a different site building. The alarm was reset in five minutes; however, approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes elapsed before it was determined that the fire watch had not returned to duty. The fire watch patrol was subsequently reestablished.

B. In9perable_StrmtuteL_ComponentL_0LEystems That Contributed _to_the Event None.

C. Dal.csand_AppInximate Tintes of Major Occurrentes May 11, 1993 A D/G building fire door was breached by an electrical at 1200 EDT cable that was routed through the doorway. A fire watch was established at the breached door.

May 14, 1993 The fire panel in the D/G building alarmed for a fire zone in at 1055 EDT a different building. The fire watch evacuated the D/G building and the fire foreman was notified of the fire watch ,

leaving the post. Fire Operations personnel responded to the alarm.

May 14, 1993 It was determined that the alarm was in response to smoke from at 1100 EDT welding that was in progress in the shop area of a different '

site building.

l t

i NRC form 366(6-89) 1 l

NRC Tbrm 366A U.S. tdUCLEAR REGULATORY COMMISSION Approved OMf1 No. 3150-0104-(6-89) Expires 4/30/92 LIEENSEE EVENT REPORT (LER)

TEXT C0tfi1NUATION FACIllTY NAME (1) lDOCKETNUMBER(2) l LER NVlE1] Lift) l l PAGE (3) l l l l SEQUENTIAL l l REVISION l. l l l l Sequoyah Nuclear Plant (SQN), Unit 1 l 11fARI l _f M 1R l l tMULl l l l l loisjalalalti;L171913 !-I o LLLL1--I o ! o LOL3]DLLoui_

1 EXT (!f more space is required, use additional NRC form 366A's) (17)

May 14, 1993 The alarm was silenced; the fire foreman verified that the at 1105 EDT alarm was clear and informed Site Security that personnel could reenter the D/G building.

May 14, 1993 The labor foreman proceeded to the D/G building and observed at 1315 EDT that the fire watch was outside of the building. The fire foreman was notified and the fire watch returned to duty.

May 17, 1993 The cable was removed f rom the doorway, the fire door breach

  • at 1545 EDT was removed, and the fire watch patrol was discontinued.

D. O t henSy.siem s_nLEe con daryluntuon s_Alf.ectell None.

E. Method _plDiECREery A labor foreman observed that the fire watch was outside of the D/G building, away from the assigned duty station.

F. Opgrator_hcLigna No operator actions were required.

G. Salety_Sy1LRnLEcaponses The fire detection system alarin functioned as designed. A build-up of smoke from ongoing work activities in the Modifications shop area initiated the alarm on the D/G building fire panel and in the main control room on the main control panel.

III. CAUSE OF THE EVENT A. Jmedialc_Cause The immediate cause was that the fire watch did not return to the duty location after the fire panel alarm had been cleared. The fire watch did not l exhibit a questioning attitude by remaining outside of the D/G building for  !

over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> without contacting the foreman or Fire Operations personnel.

l l

NRC Form 366(6-89) l

NRC form 366A U.S. NUCLEAR REGULATORY COMMISSION Approvod OMB Wo. 3150-0104 (6-89) Expires 4/30/92 t!CEN3EE EVENT REPORT (LER)

TEXT CONTINUATION rACILITY NAME (1) lDOCKETNUMBER(2)} LER. NV@fRJ1_j l PAGE (3) l l l l SEQUENTIAL l l REVISION l l l l l Sequoyah Nuclear Plant (SQH), Unit 1 l lyEARl I NU@f.R l I NU$fjLJ l l l l 10151010j0311LILl213 l-l 0 I L131-1 OJ 0101310rl 01 s TEXT (If more space is required, use additional NRC rorm 366A's) (17)

B. RnoLEause The root cause of the late fire watch performance was inadequate supervision of the fire watch by the responsible fire foreman. The fire foreman was notified when the fire watch patrol left the duty station and was aware that the fire watch patrol was impacted by the alarm and evacuation of the D/G' building. The fire foreman notified Site Security personnel that the D/G building alarm was cleared and personnel could reenter. The fire foreman failed to ensure resumption of the fire watch patrol within the required timeframe.

C. ContIlbuting_fattnra A contributing cause to the event was that the fire watch did not recognize.

the difference between the fire panel alarm and the carbon dioxide evacuation / actuation alarm. As a result, the fire watch evacuated the D/G building, mistakenly believing that the fire panel alarm was the carbon dioxide evacuation / actuation alarm.

1 V. ANALYSIS OF THE EVENT The fire watch patrol was in place as a result of a fire door br tach, in accordance with TS Limiting Condition for Operation 3.7.12. The breach consisted of an electrical cable routed through the doorway. The electrical cable did not interfere with closure of the sliding fire door. The breached fire door is located between the 1A and 2A D/G 480-volt board rooms. Both A-train D/Gs were out of service. Fire loads on either side of the fire door were low and the fire detection and protection systems were operable and capable of performing their functions. Therefore, there was no adverse consequences to plant personnel or to ,

the public as a result of this event.

V. CORRECTIVE ACTIONS A. Jmmediate_Correctivn_ Actions The fire watch patrol was reestablished. l B. Action _to_ImenLRe_currence A meeting was conducted by the Fire Protection Manager with the fire foremen to ensure that each individual understood their responsibilities for ensuring that TS compensatory fire watches are established as described in the Fire Protection Plan.

l Personnel involved were counseled on their responsibilities concerning the SQN Fire Protection Program. Specific training was provided to the fire watch on the differences between a fire panel alarm and a carbon dioxide alarm. ,

NRC Form 366(6-89) i

i NRC Porm 366A U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92

, LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILI1Y NAME (1) lDOCKETNUMBER(2) 1 (fjLINMJ.ER (6) l l PAGLL3.)

l l l l SEQUENTIAL l l REVISION l l l l l-Sequoyah Nuclear Plant ($QN), Unit 1 l }YEARl l NUMBER l I NUMB M l l l l loistslain1312171913 l l 01 1 13 l-l 01 0 1 01 Sl0FI 01 5_

TEXT (If more space is required, use additional NRC form 366A's) (17)

A revision to fire watch training is in process to include training on fire alarms, including fire panel trouble buzzers, fire panel alarms, and carbon dioxide alarms to expand on and reinforce general employee training that currently provides carbon dioxide alarm training.

VI ADDITIONAL INFORMATION A. Eail.esLfompnnents 1

None.

B. FIRYinus_Similar_Ey_eata A review of previous events identified one LER (LER 50-327/91014) that was a result of inadequate administrative control of fire watch personnel. In that event, a fire watch was released from the patrol by the labor shop without reestablishing a roving patrol f rom the Fire Operations group. The corrective action established one organization responsible for managing fire watch patrols. This was accomplished by making the Operations, Fire Protection unit fire foreman responsible for fire watch personnel. That action would not have prevented the event described by this LER that resulted from inadequate supervision of the fire watch by the fire foreman.

VII. COMMIIMENTS None.

l l

NRC form 366(6-89) l 1

Retrieved from "https://kanterella.com/w/index.php?title=ML20045B931&oldid=2556969"