ML19327B545

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LER 89-011-00:on 890925,discovered That Tech Spec 4.6.3.1.a Surveillance Requirement Re Containment Air Lock Outer Door Not Done.Caused by Personnel Error.Individuals Involved Counseled Re Importance of Subj requirements.W/891025 Ltr
ML19327B545
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 10/25/1989
From: Hairston Q, Dennis Morey
ALABAMA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-011, LER-89-11, NUDOCS 8911010193
Download: ML19327B545 (4)


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Alat:ma Power Company 7- 40 inverness C:n' r Parkmy

.' Post Office Box 1295 Birmingham, Alabama 35201 Telephone 205 058 5581 W. G. Hairston, Ill Senior V6ce President Nuclear Operations AlabamaPower thesouthernelectrer tem October 25, 1989 10CFR5[.73 Docket No. 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Dear Sir:

Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report No. LER 89-011-00 Joseph M. Farley Nuclear Plant, Unit 2, Licensee Event Report No. LER 89-011-00 is being submitted in accordance sith 10CFR50.73.

If you have any questions, please advise. $

Respectfully submitted, s

&.h, he' l W. G. Hairston,.III

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VGH III/JARimd 8.44 l l

L Enclosure cci Mr. S. D. Ebneter Mr. G. F. Maxwell

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i 8911010193 991025 l PDR ADOCK 05000364 L S PDC l 4 l

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9 ACsLITY NAMI tip DOC 8LET NUMetR m PAM G Joseph M. Farley - Unit 2 ols1o]olol3l6 4 1 i jorl 0 13 I TITLt set Surveillance Not Performed On Containment Air Lock Due To Personnel Error EVtNT DAf t W LtR NUMet h 141 R$ PORT DAf t 471 OTHER S ACILitMS INVOLVED (Gl H t MONTH DAY YtAR 8 ACILIT v h AME9 ')OCILET NUMBERi$1 MONTH DAY YtAR YEAR 4,A L 0151010101 l 1_

nlo ds no n! o n l 1l1 n!r 1l0 ?ls Rlo 0 1 5 1 0 10 1 0 1 I I OPE Re:TiteO THIS REPORT 18 SUDMITTt0 PURSUANT TO THE RLOUIREMENTS 0710 CFR $ (Chece oas or more of the foneer'arl HH I* 70 402161 20 406tel to.73teH2 Heel 73.71161 t '4 l R to 4051elt1Hil to atleHH to.tateH2Het ?3.714el H06 01 010 0 .Os wiH Hei

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$AMt TELEPHONE NUMBER ARE A COD 4 D. N. Morey, General Manager-Nuclear Plant 21 015 81_9191- 1 51 11 516 JONDLEf t ONE LINE FOR E ACH COMPONENT F AILURE OtsCRitED IN THit REPORT H3e CALJE SYsitM COMPONENT "'j'glC' "('n0"p','jg'I CAust sysTIM COMPONENT "$%$C.

nP O PR 1 I I I I I I I t i I l i 1 I I I I I I I I I I I i 1 1 SUPPLEMENT 4.L REPORT EXPkt:f D Het MONTH DAY Y'

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SUOMISSION Yt$ (19 ret tamo,een EXPICTED SVOMI55 TON DA TE) NO l l l Ass,RAci<t,-,Misme,u.,i.. .,,ew,,,, ,e ,.e.ue,,,, , ,,,..,Hei At 0300 on 9-25-89, it was discovered that the Technical Specification 4.6.1.3.a surveillance requirement to demonstrate operability of the containment air lock outer door had not been performed as required

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following multiple containment entries. The first containment entry I occurred at 1346 on 9-20-89 and multiple containment entries ensued.

This event was caused by personnel error in that shift supervisory personnel failed to schedule FNP-2-STP-15.0 (Containment Air Lock Door Seal Operability Test) to be performed when the conditions requiring its performance occurred. In addition, the daily Shift Foremen review of the surveillance schedule failed to identify the plant conditions as requiring performance of STP-15.0.

' dividuals involved have been counseled regarding their

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esponsibilities and the importance of identifying conditional surveillance requirements. Administrative controls vill be strengthened to assist supervisory personnel in recognizing the need for performing STP-15.0 when the conditions varrant. Additionally, Operations on-shift personnel vill be briefed on the lessons learned and the importance of thorough review of surveillance schedules.

l hC Form See (649)

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DF MANAGEMENT AND SUDGET, WASHINGTON.DC 20603.

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Plant and System Identification: I Vestinghouse - Pressurized Vate:: 'teac tor Energy Industry Identification System codes are identified in the text as [XX].

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Summary of Event At 0300 on 9-25-89, it was discovered that ths Technical Specificatisn 4.6.1.3.a surveillance requirement to demonstrate operability of the containment [NH] air {

lock outer door had not been performed as required following multiple containment entrics. The first containment entry occurred at 1346 on 9-20-89 cnd multiple containment entries ensued.

Description of Event A containment entry was made at 1346 on 9-20-89 for containment inspection.

Multiple containment entries vcre necessary to perform work identified during the initial containment entry. FNP-2-STP-15.0 (Containment Air Lock Door Seal ,

Operability Test) is listed in the surveillance schedule as a conditional surveillance procedure to be used for demonstrating operability of the ,

containment air lock outer door. Technical Specification 4.6.1.3.a requires the containment air lock to be demonstrated operable at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when multiple entries are required.

s At 0300 on 9-25-89, while the Shift Supervisor and Shift Foreman were discussing requirements for unit startup, it was discovered that FNP-2-STP-15.0 had not been performed as required. Upon discovery of the missed surveillance, l

FNP-2-STP-15.0 was performed immediately. The surveillnnee test passed, indicating that the outer door was operable.

Cause of Event

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, This event was caused by personnel error in that shift supervisory personnel l failed to schedule S1P-15.0 to be performed when the conditions requiring its l performance occurred. In addition, the daily Shift Foremen review of the

surveillance schedule failed to identify the plant conditionn as requiring performance of STP-15.0.

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NRC Fonn 30BA M91

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!P,Wti"JJi* tat!h",#2inWE& t"?.'c? l OF MANAGEMENT AND $UDGET,WA$NINGTON, DC 70603 ,

9 ACILITY NAME tu DOCKtT NUMDimL2) Lin WUMetR (Si PA01 (3) l n'a -

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Farlev Nedear Plant - Unit 2 TEXT M mme mese a mesesar, use asWeenaf h4C Form WW 1171 0 l5 l0 l0 l0 l 3 l 614 d9 -

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I Reportability Analysis and Safety Assessment i

This event is reportable as a condition prohibited by the plant's Technical .

Specifications. '

This event had no significant impact on plant safety. The containment air lock remained operable even though the required surveillance was not performed. ,

t There was no effect on the health and safety of the public. i corrective Action Individuals involved have been counseled regarding their responsibilities and the importance of identifying conditional surveillance requirements.

Administrative controls vill be strengthened to assist tapervisory personnel in recognizing the need for performing STP-15.0 when the conditions warrant.

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Additionally, Operations on-shift personnel vill be br.tefed on the lessons learned and the importance of thorough review of surveillance schedules.

Additional Information No similar LERs have been submitted by Farley Nuclear Plant.

No component failures occurred during this event.

l This event v ald not have been more severe if it had occurred under different operating couditions.

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  • EAC Foca 30BA 6689)

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