ML19208A733

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LER 79-073/03L-0:on 790813,RHR Pump Breaker 2A Was Erroneously Racked Out,Making Both Loops of Sys Inoperable. Caused by Incorrect Prepration of Tag & tag-out Sheet by Control Operator.Personnel Instructed
ML19208A733
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 09/11/1979
From: Tollison A
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19208A727 List:
References
FOIA-81-159 LER-79-073-03L, LER-79-73-3L, NUDOCS 7909170382
Download: ML19208A733 (2)


Text

NHC FORM 366 U. 3 reUCLL AH HEGULATOR'e COMMISSION (7 77)

LICENSEE EVENT REPORT t

CONTROL BLOCK: l I

l l l l l lh b

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l0 l1l NlClB lE lP 2l@l0l0l-l0 0 0l 0 O ! - l O l O l@l 4LICENSE 7 8 9 LICENSEE CODE 14 15 LICENSE NUMbEH 26 2ti 1l111l1 TYPE JO

@lblCAT58 l l@

CON'T 0 1 S E 's60 l L @ l Ol Sl Ol -l 0l 3l 2l 4bd I @ 63

(_0 Bl il 3l 7l 9 hI 14 I l REPORT DATE l l 80 l@

7 8 61 COCKET NUV8E R EVENT DATE lb EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o 2 While atterneine to place the "B" loon o f PHPW nndor clonen,co rne min *on me n ebo 1 o a "2A" RIIRSW pump breaker was racked out by mistake, making both loops of RHRSW inoper- l o 4 able. The "2A" pump was out of op ration for approximately 15 minutes. The error wasj o s ldiscovered quickly af ter it occurred, as a result of the normal clearance process when l l 0 l61 the auxiliarv operator who hung the tag returned to the Control Room to sign the tag l

/

0 7 sheet and observed that it did not reflect the actual equipment cleared. l o 8 [ Technical Specification 3.7.1.1, 6.9.1.9c  !

7 8 9 80 SYSTE M CAUSE CAUSE COUP. VALVE CODE CODE SUBCODE COMPONENT CODE SU8 CODE SUBCODE lolol 8

l s H l @ L^J @ l ^ 1 @ l C l K 9 10 11 12 T l B l K l R lh l Flh y h 18 20 7 13 19 SEGLE NTI AL OCCU R RE NCE REPORT REVISION LER RO EVENT YEAR REPORT NO. CODE TYPE N O.

h REU RT 7l9l l-l l 0l 7l 3l l/l l0 l 3 l ] l-l l0

_ 21 22 23 24 26 27 N 2) Ju 31 32 AC I'IO N FUTURE EFFECT SHUT DOWN A TT ACHYENT N P R D-4 PRiVE COYP. COMPONENT TAKEN ACTION ON PL ANT YE1 HOD HOURS SUBVITTED FORMLuo. SU PP LI E R YANUFACTURER lx l@l xl@ l z l@ l36z l@ l 010101 lYl@ l Ul@ lAl@ cl0l8l0lg J3 34 3S 3/ 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i o lThe "2A" RHRSW pump was immediately racked in. The tag and the tag-out sheet had been l li li l l prepared incorrectly by the control operator in that "2A" pump was dostenated to be 1 i 7 racked out vice "2B" pump. The follOwing corrective action were or will be taken:

lilal 11) An immediate meeting and counselina session was held with the control onerator in- l 11 14i lvolved, the shift foreman, the acting operation supervisor, and the (CON'T) l 7 8 9 80 F ACILITY -

ME THOD OF STATUS  % POWE R OTHER STATUS Di SCOV E R Y OtSCOVERY DESCR<PTION 3, i s l E l@ l 0 l 5 l 4 @l NA l l A l@l Operator Surveillance l ACTIVITY Co TENT RELEASED OF RELE ASE AYOUNT OF ACTIVITY LOCATION OF RELE ASE N^ l N^

I i 168 9i LzJ @ 10l zi@

7 11 44 45 80 l

PERSONNEL E xPOSURES NUMBE R TYPE CESCRIPTION s i 7 l0l0l0l@lz @l NA l

PERSONNELINJU ES NUVBER DESCR PTION i a 8 9 l 0 l 0 l 0 l@l NA l 7 11 12 80 LOSS OF On DAMAGE TO FACILITY 43 TYPE DESCRIPTION 4'

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LLloJ8 9l z l@l NA 7 10 909170 W "

80 D e 2 o [,n ISStJE[hl NA ESCRIPTION l lllllllllllllj 7 8 9 10 68 69 80 5 NAME OF PRE PARER A. C. Tollison, Jr. ,., o m 919-457-9521 g

LER CONTINUATION - RO# 2-79-073 Facility: BSEP Unit No. 2 Event Date: 8-13-79 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS:

Operations & Maintenance Superin' endent. Subjects discussed were the sequence of events, the seriousness of such situations, potential consequences, require-ment for alertness, and actions to prevent reoccurance.

2) The plant Manager held a personal interview with the control operator involved and the shift foreman. In#this interview, he stressed the seriousness of events of this type, the reasons for management and regulatory concern, and the need to eliminate personnel errors to the maximum extent.
3) AOI-2, Operating Principles and Philosophy, will be reviewed by all operations personnel.
4) The clearance procedure is being revised to require that the tag-out sheets and tags for any clearance on a Technical Specification covered system be review-ed and approved by a licensed senior reactor operator prior to issuance. This review must be independent of the person filling out the cicarance.
5) The LER will be reviewed by all operations personnel as a reminder of problems created by a simple mistake.

II.Si$'k 183