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| {{Adams | | {{Adams |
| | number = ML20203K280 | | | number = ML20248L634 |
| | issue date = 02/25/1998 | | | issue date = 03/18/1998 |
| | title = Discusses 980220 Meeting Re Three Apparent Violations Identified in Insp Repts 50-313/97-21 & 50-368/97-21.List of Attendees & Matls Used Encl | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/97-21 & 50-368/97-21.Actions Will Be Reviewed During Future Insp to Determine That Full Compliance Achieved & Maintained |
| | author name = Stetka T | | | author name = Stetka T |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
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| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-313-97-21, 50-368-97-21, EA-97-574, NUDOCS 9803050039 | | | document report number = 50-313-97-21, 50-368-97-21, NUDOCS 9803230335 |
| | | title reference date = 03-09-1998 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 69 | | | page count = 3 |
| }} | | }} |
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| {{#Wiki_filter:, _ _. . _ _ . . _ | | {{#Wiki_filter:,f + % UNITED STATES |
| . _ _ _ ._ _ _ _ _ _ _ . . . _
| | ; 3 # ,g NUCLEAR REGULATORY COMMISSION O j REGION IV D., 611 RYAN PLAZA DRIVE. SUITE 400 |
| . | | %, ,d,4 ARLINGTON, TEXAS 76011-8064 March 18,1998 C. Randy Hutchinson, Vice Presi' ont Operations Arkansas Nuclear One Entergy Operations, In S.R. 333 Russellville, Arkansas 72801-0967 SUBJECT: RESPONSE TO NRC INSPECTION REPORT 50-313/97-21; 50-368/97-21 Thank you for yc.ir letter of March 9,1998, in response to our February 6,1998, letter and Notice of Violation concerning an inadequate procedure and seven examples of design calculation discrepancies. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine |
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| Mp* * tog \ UNITED STATC
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| j ,i( j s NUCLEAR REGULATORY wMMISSION
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| ;- REGION tv o, < .[. T11 RYAN P( A2A DRIVE SUITE 400 Anuncion. texas non sou
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| %,**s ./ | |
| *** February 25, 1998 C. Randy Hutchinso.1, Vice President Operations
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| . Arkansas Nuclear One Entergy Operations, Inc.
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| 1448 S.R. 333 Russe:iville, Arkansas 728010967 SUBJECT: PREDECISIONAL ENFORCEMENT CONFERENCE (EA 97 574) TO DISCUSS NRC INSPECTION REPORT 50-313/97 21; 50-368/97-21
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| ==Dear Mr. Hutchinson:==
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| This refers to the meeting conducted in the Region IV office on February 20,1998. This meeting involved discussion of three apparent violations identified in NRC Inspection Report 50 313/97 21; 50-368/97 21. Enclosure 1 is the attendance list for this meeting and Enclosure 2 contains the licensee's presentation.
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| During the meeting, your staff discussed the causes for and corrective actions taken or planned to be taken regarding the failure to properly control activities related to the remnval of the borated water storage tank vacuum relief valve for testing on December 4,1996. Your staff also presented the engineering bases for concluding that the borated water storage tank was operable at all times during the sequence of events relevant to these issues.
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| In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be piaced in the NRC's Pchlic Document Room.
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| Should you have any questions conceming this matter, we will be pleased to discuss them with you.
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| Sincerely,
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| ) w~
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| I 7/swa Thomas F. Stetka, Acting Chief Engineering Branch Division of Reactor Safety Enclosures:
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| 1. Attendance List 2. Licensee Presei.'.ation /
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| [ I 9803050039 990225 PDR- ADOCK 05000313 lllll.l.llhh
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| Entergy Operations, Inc. 2-cc w/ enclosures:-
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| Executive Vice President -
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| & Chief Operating Officer.
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| Entergy Operations, Inc.
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| P.O. Box 31995 Jackson, Mississippi 39286-1995
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| ..
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| Vice President'
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| Operations Support '
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| Entergy Operations, Inc.
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| P.O. Box 31995 Jackson, Mississippi 30286 Manager, Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330
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| 'Rockvil'e, Maryland 20852
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| -
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| County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Winston & Strawn 1400 L Street, N.W.
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| Washington, D.C. 20005-3502 David D. Snellings, Jr., Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Mail Slot 30 Little Rock, Arkansas 72205-3867 Manager Rockville Nuclear Licensing Framatome Technologies
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| - 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852
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| O Entergy Operations, Inc. -3-E-Mail report to T. Frye (TJF)
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| E-Mail report to T. Hiltz (TGH)
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| E Mai! report to NRR Event Tracking Eystem (IPAS)
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| E Mail report to Document Control Desk (DOCE,ESK)
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| bec to DCD (IE42)
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| bec distrib, by RIV:
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| Regional Administrator Resident inspector DRS Director DRS Deputy Director DRP Director MIS System Branch Chief (DRD/C) RIV File Project Engineer (DRP/C) DRS-PS3 Branch Chief (DRP/TSS)
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| s DOCUMENT NAME: R:\._ANO\an721ms.mfr To receive copy of document, indicate in box:"C" = Copy without enclosures *E" = Copy with enclosures "h" = No copy RIV: SRI:EB pg l hC:EB . l l MFRunyan/Ri%r' TFStetkaW 024198 \ 026#98 OFFICIAL RECORD COPY l
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| E-MLil report to T. Hiltz (TGF1)
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| E Mali report to NRR Event Tracking System (IPAS)
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| E-Mail report to Document Control Desk (DOCDESK)
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| bec to DC"(IE42)
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| bec distrib, by RIV:
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| Regional Administrator Resident inspector DRS Director DRS Deputy Director DRP Director MIS System Branch Chief (DRP/C) RIV File Project Engineer (DRP/C) DRS-PSB Branch Chief (DRP/TSS)
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| DOCUMENT NAME: R:\,ANO\an721ms.mfr To receive copy of document, indicate in box:"C" = Copy without enclosures "E" = Copy wdh enclosures "N" = No copy RIV; SRI:EB gg, AC:EB _ _
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| MFRunyan/@S# TFStetkaW/
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| 024998 \ 02)/f98 OFFICIAL RECORD COPY alhO
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| . . - - - - .
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| i e 1
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| ENCLOSURE 1 ATTENDANCE LIST
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| PREDECISIONAL ENFORCEMENT CONFERENCE ATTENDANCE
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| LICENSEE / FACILITY Entergy Operations, inc1 Arkansas Nuclear One, Unit 1 DATEmME February 20,1998/1:00 p.m.
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| CONFERENCE NRC Region IV LOCATION Arlington, Texas
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| _
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| , EA NUMBER 97 574
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| LICENSEE REPRESENTATIVES _
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| ORGANIZATION TITLE l_ NAME (PLEASE PRINT)
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| .( , . . . . . . . . . . . . ......-. .. .
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| LICENSEE / FACILITY Ente;gy Operations, Inc / Arkansas Nuclear One Unit 1 DATE/ TIME February 20,1998! 1:00 p.m.
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| CONFERENCE NRC Region IV Office LOCATION Arlington, Texas EA NUMBER 97 574
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| __
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| NRC R_EPRESENTATIVES
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| | Thomas F. Stetka, Acting Chief Engineering Branch Division of Reactor Safety Docket Nos.: 50-313,50-368 License Nos.: DPR-51; NPF-6 ecutive Vice President |
| .
| | & Chief Operating Officer Entergy Operations, In P.O. Box 31995 l Jackson, Mississi;5pi 39286-1995 g 9803230335 980318 PDR ADOCK 05000313 G PDR |
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| | Entergy Operations, In ['bcc to DCD (lE01f bec distrib. by RIV: |
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| | Regional Administrator Resident inspector DRP Director MIS System Branch Chief (DRP/C) RIV File Project Engineer (DRP/C) DRS-PSB Branch Chief (DRP/TSS) |
| | | DRS AI 98-G-0023 DOCUMENT NAME: R:\_ANO\AN721AK.MFR To receive copy of document, Indicate in box:"C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV: SRI:EB 'JIV AC:EB MFRunyan/imb - TFStetkddir 034s/98 03/ /98 f OFFICIAL RECORD COPY ; |
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| _ _ _ .
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| AGENDA ^
| |
| Management Overview RANDY HUTCHINSON Vice President Operations, A?O Introduction DWIGHT MIMS
| |
| '
| |
| Director, Licensing
| |
| -
| |
| Chronology CHARLIE ZIMMERMAN l Plant Manager, Unit 1
| |
| ! Operability Assessment JERRY HOWELL Senior Engineer, MCS l Temporary Alteration Program JOE KOWALEWSKI ;
| |
|
| |
| Manager, System Engineering Uniti Non-outage Test Performance PETE DIETRICH !
| |
| Manager, Maintenance Unit 1 .
| |
| Enforcement Perspective DWIGHT MIMS
| |
| , Director, Licensing .
| |
| Closing Comments RANDY HUTCHINSON Vice President Operations, ANO
| |
| ~
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|
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| _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ .
| |
|
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| i[! ! :! i! ![1:;I !!II;l! f ;!!Ir !!!!!r!l
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| W H -
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| . R A E n s
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| H yn t
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| M de nid
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| E as Re r G P .
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|
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| INTRODUCTIOX -
| |
| Dwight Mims Director, Licensing
| |
| .
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| -
| |
|
| |
| .-4.- 4-aa. .=-4--+.4es m--w s e---s-,_u__s.m%.s. a mA hw _m s am.wm..-a4_-ee-*-.. .amm a 4a.ee e2.e.AA-=oam,
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| ; D
| | Entergy Operations, In Vice President Operations Support Entergy Operations, In P O. Box 31995 Jackson, Mississippi 39286 Manager, Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Winston & Strawn 1400 L Street, Washington, D.C. 20005-3502 David D. Snellings, Jr., Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Mail Slot 30 Little Rock, Arkansas 72205-3867 Manager Rockville Nuclear Licensing Framatome Technologies 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852 l |
| ,
| | . I m__________._______ _ |
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| APPAREXT VIOLATIONS
| |
| .
| |
| *
| |
| Failure to perform proper vacuum relief valve testing under the plant conditions as prescribed in the test procedure in accordance with 10CFR50, Appendix B, Criterion V, Instructions, .
| |
| Procedures and Drawings :
| |
| -
| |
| Failure to utilize the correct design control processes (temporary alterations) for the temporary cover configurations placed over the valve flange in accordance with 10CFR50, Appendix B, Criterion III, Design Control
| |
| *
| |
| Failure to perform. proper safety evaluations as described in 10CFR50.59, Changes, Tests and Experiments l
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| BORATED WATER STORAGE TAXK
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| t e
| |
| a
| |
| )
| |
| O (J o
| |
| n O W
| |
| ) r r r e e f o
| |
| d R
| |
| I k
| |
| a e
| |
| r t
| |
| e a
| |
| r d
| |
| r o
| |
| i w
| |
| e b o b v I B t jo e C 5 m
| |
| u u
| |
| c d n e ee ga invt t
| |
| r e
| |
| a 9 u
| |
| | |
| 1 (i ay vt mr "4 uo q e
| |
| yViteh v nk
| |
| -
| |
| r aS t
| |
| c ei t
| |
| os d a a n uP n
| |
| aDwNt I J
| |
| a - - - -
| |
| -
| |
| .
| |
| . . ' . i ,
| |
| J
| |
| | |
| - - - . - _ -
| |
| - -
| |
| .
| |
| | |
| L CHROXOLCGY December 3,1996
| |
| - Job order for PSV testing signed into control room
| |
| * Control Room Supervisor (CRS) and craft discussed need for " breathable" FME cover
| |
| * Craft and craft supervisor discussed need for
| |
| " breathable" FME cover
| |
| - PSV removed for testing i
| |
| - FME cover installed per surveillance test procedure :
| |
| requirement Plastic bag with slits installed to allow " breathing" .
| |
| .
| |
| .
| |
| g - -
| |
| % . .-..
| |
| | |
| . -
| |
| .
| |
| '
| |
| PLASTIC FME COVER Plastic bag loosely draped over flange
| |
| _p Plastic bag seam over pipe flange 2Verticalslits cut to allow BWS1 to breathe.
| |
| | |
| .
| |
| >
| |
| '
| |
| l i l
| |
| ;
| |
| -
| |
| c i i :
| |
| '
| |
| I i
| |
| t i
| |
| i I 1
| |
| '
| |
| i I
| |
| -
| |
| ) i j ( Bag taped
| |
| '
| |
| t
| |
| ;
| |
| To BWST 8" Schedule 10S pipe .
| |
| i
| |
| . .
| |
| | |
| __ . . . _ ..
| |
| e 1i
| |
| .
| |
| CHROXOLOGY
| |
| ~
| |
| *
| |
| December 4,1996
| |
| - Craft discovered crack in PSV flange late in day shift
| |
| * December 5,1996 .
| |
| '
| |
| -
| |
| ~ 1300 System Engineer observes crack and notes FME cover ,
| |
| -
| |
| Condition report initiated for PSV crack ~
| |
| - System Engineer begins operability determination and i conservatively directs a 1" gap FME cover be installed to replace plastic cover
| |
| ~ 18001" flanged gap FME cover installed
| |
| , ~ 2030 operability assessment completed for current configuration .
| |
| <
| |
| .'
| |
| i i
| |
| . _ - - _ _
| |
| . . - .
| |
| | |
| .
| |
| -
| |
| | |
| FLANGED GAP FME COVER Note: Install screen over open flange holes
| |
| "'
| |
| ~~ '
| |
| % All thread (4)
| |
| '
| |
| j,
| |
| ._m
| |
| , ,'~ Blind flange (1)
| |
| o_
| |
| Screen wrap on g \
| |
| Air gap
| |
| | |
| outside of flanges Nuts (16)
| |
| all around . -. , - :
| |
| !?
| |
| -
| |
| i l ; i + Existing valve flange t ri i::r .
| |
| - '
| |
| l -
| |
| 1 I I
| |
| n L Unattended Configuration for Vacuum Relief Valves Using 0.0386" to 0.2187" screen
| |
| ,
| |
| | |
| w
| |
| | |
| . _- - - . .. .-
| |
| .
| |
| .
| |
| | |
| CHROXOLOGY .
| |
| '
| |
| .
| |
| * December 5-12,1996
| |
| - Various departments discuss breathable FME cover as
| |
| ,
| |
| possibly superior to PSV
| |
| - Various departments consider need for temporary alteration
| |
| - Temporary alteration discussions concluded that procedure ;
| |
| ; provided adequate control ;
| |
| '
| |
| - Determined PSV weld repair unlikely and long lead time for new PSV -
| |
| - System Engineer modified FME cover to independently ,
| |
| l provide equivalent flow area io the PSV (i.e. 3" gap)
| |
| '
| |
| - Additionaljob order issued to increase gap and ,
| |
| conservatively provide dual signoffs t l
| |
| !
| |
| ,. , , - _ - _ . . -_ _ _
| |
| | |
| .
| |
| .
| |
| | |
| CHROXOLOGY
| |
| - January 22,1997 L - Self-assessment questions BWST PSV maintenance Condition report initiated
| |
| - Questioned acceptability of plastic FME cover
| |
| - Questioned use of surveillance test procedure in non-outage application
| |
| ! * BWST operable in current configuration (3" flanged gap cover)
| |
| * Past operability
| |
| - Determined operable based on slits in plastic FME cover
| |
| - ~
| |
| --
| |
| | |
| . -. -
| |
| .
| |
| 15 ,
| |
| CHROXOLOGY -
| |
| .
| |
| *
| |
| February 3,1997
| |
| '
| |
| - Condition report documents 4" vent not redundant to PSV
| |
| * Current configuration operable
| |
| - 3" flanged gap FME cover
| |
| * Past operability
| |
| - Determined operable with minor tank deformation
| |
| - Tank would not rupture
| |
| ,
| |
| ;
| |
| !
| |
| ____J
| |
| | |
| -
| |
| .
| |
| | |
| CHROXOLOGY
| |
| -
| |
| February 5,1997 <
| |
| - Temporary alteration documentation initiated.
| |
| | |
| * 4" vent line not redundant Surveillance test procedure not evaluated for non-outage mode '
| |
| * Desire to provide single documentation package Extended installation time
| |
| '
| |
| Differing opinions on whether FME cover was
| |
| .
| |
| : temporary alteration
| |
| :
| |
| !
| |
| -
| |
| February 18,1997 i
| |
| - Temporary alteration reviewed nnd. signed off
| |
| * No modifications required to 3" flanged gap configuration
| |
| - Installed December 12,1996
| |
| . . . .
| |
| | |
| . .. - - - . -
| |
| .
| |
| _
| |
| -
| |
| -i
| |
| :
| |
| -
| |
| _
| |
| -
| |
| .
| |
| CHROXOLOGY 7
| |
| ._
| |
| *
| |
| February / March 1997
| |
| -
| |
| .
| |
| - AE Design Basis Inspection team BWST questions answered
| |
| ~
| |
| October / December 1997
| |
| - Engineering Open Items Follow-up Inspection questioned
| |
| .
| |
| plastic FME cover past operability determination ,
| |
| ,
| |
| , - Performed analysis using bounding assumptions
| |
| { * Assumed plastic bag would not fail- only 4" vent Demonstrated BWST would not significantly deform and l l would perform design function
| |
| [ - Performed testing which showed plastic FME cover would i rupture before significant tank deformation
| |
| ]
| |
| , | |
| .
| |
| * Validated earlier engineeringjudgments/ evaluations t
| |
| i
| |
| | |
| - Conclusion !
| |
| i
| |
| .
| |
| ;
| |
| BWST remained operable in each configuration i
| |
| | |
| s . . _ . _ . . -. . .- . - _- _ _ _ . _ -- !
| |
| | |
| _
| |
| _ -
| |
| .
| |
| | |
| .
| |
| CHROXOLOGY
| |
| * Summary
| |
| - Controls satisfying procedural requirements of temporary alteration procedure should have been used to perform task
| |
| -
| |
| Inadequate review of test conversion resulted in inappropriate performance of task during operation
| |
| * Incorrect impact statement information made detection difficult
| |
| - Personnel on several occasions sought to improve a situation that they felt was already operable (i.e. recover margin),
| |
| -
| |
| focus was on safety and operability of a common mode component
| |
| ! - Conditions were self-identified
| |
| - Subsequent calculations and tests confirmed that BW5T
| |
| '
| |
| remained operable in each configuration
| |
| -
| |
| | |
| .6 ''Asa~
| |
| 0 '
| |
| I
| |
| : !
| |
| l
| |
| ~
| |
| .
| |
| .. ,
| |
| | |
| x
| |
| : M m m l
| |
| CO U 60
| |
| ! %
| |
| cn y .5 L =W a :
| |
| l W yw s
| |
| W .b I o g w
| |
| & *g C l -
| |
| C W H
| |
| H W d v u bb
| |
| % % og w *5 w r *
| |
| w a
| |
| | |
| -
| |
| | |
| .
| |
| nH
| |
| | |
| ,
| |
| l l
| |
| l
| |
| _ .._ , -
| |
| _ - . - _ . - _ . ._ _ .-_ _ _ . - . - . . , - - _ - . _ . - - . - - _ _ _ _ _ - . _ - _ - - _ . - - _ - . -,_ .._-- - .--_.. ___ _ -_ _ . _ _._ - - -
| |
| | |
| _-
| |
| .
| |
| -
| |
| | |
| -
| |
| OPERABILITY ASSESSMENT
| |
| * CR 1-96-0663 - December 5,1996 - PSV Flange Crack ,
| |
| - FME controls - i.e.1" gap plus 4" vent line
| |
| !
| |
| - Technical specification reviews
| |
| - BWST backleakage issues
| |
| * CR 1-97-0019 -January 22,1997 - Plastic FME Cover
| |
| * CR 1-97-0031 - February 3,1997 - Inadequacy of4" Vent / Single
| |
| '
| |
| Failure Concern
| |
| .
| |
| _-_
| |
| | |
| . - .
| |
| .
| |
| .
| |
| .
| |
| .
| |
| ;
| |
| | |
| ,
| |
| OPERABILITY ASSESSMENT
| |
| :
| |
| | |
| *
| |
| CR-1-96-0663 - December 5,1996 - PSV Flange Crack
| |
| .
| |
| - Operability addressed the adequacy of the PSV as well as other issues (Technical Specifications and BWST backleakage)
| |
| - The System Engineer understood that the basis for solely crediting the 4" overflow vent was not fully developed; therefore, he considered it prudent to re-establish a vent path equivalent to the vacuum breaker. Therefore,
| |
| .
| |
| calculations were performed to supportinstalladon of a i flanged 1" gap !
| |
| i
| |
| ,
| |
| _ _ _
| |
| i
| |
| | |
| - .
| |
| .
| |
| .
| |
| :
| |
| 22- t i
| |
| r
| |
| -
| |
| OPERABILITY ASSESSMEXT . i
| |
| , .
| |
| *
| |
| CR-1-97-0019 - January 22,1997 - Plastic FME Cover
| |
| | |
| ,
| |
| i !
| |
| ; - At this time, the 3" flanged gap had already been installed l based on additional calculations which established substantial margin. Therefore, no current operability t L concerns existed.
| |
| | |
| I
| |
| - System Engineer acknowledged that previous CRs did not ,
| |
| i explicitly address the p .t operability implications of the use
| |
| ; of the plastic bag FME cover.
| |
| | |
| j * Initial conclusions of indeterminate past operability were
| |
| [ revised based on confirmation that slits were made in the
| |
| : cover. t
| |
| :
| |
| ] - Design Engineers had concurrently concluded no past j operability concerns existed based on engineering judgment
| |
| '
| |
| that the bag would rupture during a rapid tank drawdown.
| |
| | |
| i i
| |
| ;
| |
| ! ,
| |
| I
| |
| _
| |
| - :_ __ _
| |
| | |
| - . .
| |
| p .
| |
| | |
| i a
| |
| ,
| |
| .
| |
| OPERABILITY ASSESSMENT ,
| |
| !
| |
| *
| |
| CR-1-97-0031 - February 3,1997 - Inadequacy of4" Vent / Single Failure Concern
| |
| -
| |
| - Standard engineering methods could not support capability of the 4 " vent line as redundant to the vacuum breaker line
| |
| ; - Single failure concerns which resulted in the condition :
| |
| report, were quickly resolved, i.e. PSV considered a passive component ,
| |
| - At this time, the 3" flanged gap cover provided an operable
| |
| !
| |
| configuration !
| |
| :
| |
| I
| |
| .
| |
| | |
| )
| |
| | |
| .
| |
| .
| |
| | |
| OPERABILITY ASSESSMEXT February 1997 follow-up questions
| |
| -
| |
| During the NRC AE Design Basis Inspection, additional detail supporting operability of the 1" flanged gap design was '
| |
| provided to address the effects of the wire screen. This was previously judged acceptable based on comparison with the screen on the PSV and a knowledge that margin existed in these calculations.
| |
| | |
| -
| |
| The re-assessment provided to the inspection team confirmed the validity of the previous engineering evaluation.
| |
| | |
| l
| |
| | |
| _
| |
| , . | |
| .
| |
| ~
| |
| .
| |
| | |
| .
| |
| OPERABILITY ASSESSMENT November 1997 follow-up inspection
| |
| -
| |
| During the NRC AE Design Basis Follow-up inspection, first l time questions were raised concerning adequacy of the original past operability determinations for the plastic bag FME. cover
| |
| -
| |
| ANO decided to perform additional efforts to respond to NRC questions (two approaches): '
| |
| - Testing to demonstrate fragility of the bag
| |
| - Analysis of tank effects assuming bag is not fragile, (i.e. does not rupture)
| |
| ..
| |
| | |
| --_------ - - _ _ _ _ - _ - _ . _ __. . _ _ _ _ _ _ . _ ._ . -- . _. _
| |
| _ .
| |
| 26 ,
| |
| ~
| |
| OPERABILITY ASSESSMEXT 1
| |
| ,
| |
| -
| |
| ,
| |
| November / December 1997 follow-up
| |
| -
| |
| Test results confirmed that the plastic bag would easily rupture under postulated conditions
| |
| *
| |
| Tank analyses determined that the overflow line by itself was ,
| |
| capable of venting the tank without tank breach or any .
| |
| significant damage
| |
| - Sealed 8" PSV mounting flange
| |
| *
| |
| Evaluated ECCS performance and was determined to be adequate '
| |
| i
| |
| !
| |
| -
| |
| t
| |
| | |
| .
| |
| .
| |
| "
| |
| OPERABILITY ASSESSMENT Operator impact
| |
| - Large Break LOCA Case 1 (expected)
| |
| - Full ECCS actuation (12,340 gpm)
| |
| '
| |
| - Plastic bag vents through slits
| |
| * No impact
| |
| - Plastic bag seals and quickly ruptures Momentary level indication perturbation
| |
| - Transparent to operators
| |
| . ,
| |
| - - . .
| |
| . - -
| |
| -
| |
| - - -. . . - - -
| |
| .-
| |
| | |
| . - _ ._. .
| |
| .
| |
| "
| |
| OPERABILITY ASSESSMENT Operator impact (Cont)
| |
| '
| |
| =
| |
| Large Break LOCA Case 2 (bounding) ;
| |
| - Full ECCS actuation (12,340 gpm)
| |
| - Plastic bag seals without bursting
| |
| - 4" vent limits tank vacuum to 2.7 psi
| |
| - Level error results in early manual transfer to reactor building sump suction (6' maximum) :
| |
| - Level indication rises as tank vents
| |
| - Operators dispatch HP personnel to monitor for BWST backleakage
| |
| - Calculations show adequate NPSH for ECCS pumps
| |
| !
| |
| L
| |
| | |
| i
| |
| | |
| _ _ .- . __ _ - _
| |
| .
| |
| "
| |
| .
| |
| OPERABILITY ASSESSMEXT Operator Impact (Cont)
| |
| ~
| |
| *
| |
| Additional conservatisms not considered
| |
| - Actual ECCS flows less than assumed result in smaller level error
| |
| - Reactor building sump suction transfer time results in 3-4 feet of additional BWST inventory injection not credited
| |
| ;
| |
| ,
| |
| | |
| 6 t
| |
| s
| |
| | |
| -
| |
| .
| |
| | |
| . OPERABILITY ASSESSMEXT Engineering judgment
| |
| -
| |
| Determining operability
| |
| - IE Manual 9900, Detailed Discussion ofSpecific Operability Issues SSC outside TS, engineering judgment must be used to determine safety significance
| |
| , * Decision based on best information available l .
| |
| l * Predicated on reasonable expectation that the SSC is operable May be based on analysis, test, partial test, experience with operating events, engineering judgment, or a combinaHon of factors
| |
| * Revise as appropriate
| |
| .
| |
| - - - -
| |
| --
| |
| -- -
| |
| .
| |
| --
| |
| -
| |
| ,
| |
| | |
| - - _ - -_ ._ -- _. __ _ _ _ _ _ _ - _ _ _ _ _ _ _ -. .
| |
| ..
| |
| . 31
| |
| .
| |
| OPERABILITY ASSESSMENT
| |
| . Engmeerma judgment (Cont)
| |
| *
| |
| NUREG 1022, Rev.1 - Event Reporting Guidelines 10CFR50.72 and
| |
| '5 0.73
| |
| - Engineering judgment
| |
| * "May include either a documented engineering analysis or a judgment by a technically qualified individual, depending on the complexity, seriousness, and nature of
| |
| . the event or condition"
| |
| '
| |
| -
| |
| " Staff considers that the use of engineering judgment implies a logical thought process that supports the judgment"
| |
| | |
| . . . . _ . . . - - . . - _ ._. -
| |
| . - -
| |
| ,
| |
| .
| |
| | |
| !
| |
| OPERABILITY ASSESSMENT
| |
| '
| |
| Conclusions
| |
| -
| |
| The original determination that the BWST was operable with t
| |
| -
| |
| the plastic bag installed was re-confirmed. The original efforts
| |
| : to support the engineering judgment determination were confirmed to be valid
| |
| -
| |
| The original tank evaluations in January and the additional tank analyses in November 1997 confirmed that no significant effects would have occurred even had the original premise been in error (i.e. even if the bag had not broken) ;
| |
| -
| |
| Use of engineering judgment was applied consistently in l accordance with regulatory guidance ,
| |
| !
| |
| ._ ..
| |
| | |
| . -. - - .
| |
| , _ _ _ _ . _ ---_ .. _
| |
| .
| |
| | |
| i
| |
| '
| |
| ,
| |
| TEMPORARY ALTERATIOX PROGRAM Joe Kowalewski Manager, Unit 1 System Engineering
| |
| | |
| . ._ _
| |
| .
| |
| | |
| '
| |
| | |
| TEMP ALT PROGRAM
| |
| !
| |
| *
| |
| Apparent violations
| |
| - Failure to perform 50.59 reviews for installation of FME covers
| |
| - Failure to utilize proper design controls for the installation-of FME covers
| |
| -
| |
| Temporary alteration program
| |
| - Temporary alteration procedure initiates both the design controls and 50.59 reviews
| |
| - Error made in application of temporary alteration decision
| |
| , | |
| criteria t
| |
| i
| |
| | |
| -- _ _ -
| |
| _. .
| |
| .
| |
| | |
| TEMP ALT PROGRAM
| |
| * Introduction
| |
| ,
| |
| - Temporary alteration program description
| |
| - Criteria for initiating temporary alteration controls
| |
| '
| |
| - Application of criteria to the BWST PSV removal
| |
| - Evaluation of temporary alteration program implementation
| |
| -- Planned corrective actions
| |
| | |
| .
| |
| '
| |
| ,
| |
| -
| |
| .
| |
| | |
| - . .
| |
| .
| |
| | |
| TEMP ALT PROGRAM
| |
| -
| |
| | |
| Program Description
| |
| *
| |
| Temporary alterations controlled by Procedure 1000.028
| |
| *
| |
| Two methods which initiate 50.59 review
| |
| - Procedures or work plans
| |
| .
| |
| ;
| |
| - Temporary alteration packages .
| |
| i
| |
| *
| |
| Both methods require:
| |
| l | |
| - Engineering review
| |
| - 50.59 review
| |
| .
| |
| ! - Independent verification .
| |
| *
| |
| INPO Good Practice used as reference for temporary alteration procedure development
| |
| :
| |
| :
| |
| | |
| - - _ -
| |
| - .
| |
| | |
| .
| |
| .
| |
| TEMP ALT PROGRAM
| |
| '
| |
| Criteria for temporary alteration controls
| |
| *
| |
| Addressed in Attachment 1 of temporary alteration procedure
| |
| *
| |
| Determine if maintenance controls adequate
| |
| - Affected structure / system / component (SSC) released by !
| |
| Operations to Maintenance
| |
| '
| |
| '
| |
| - Affected SSC in use by Operations
| |
| *
| |
| Determine if temporary alteration package required
| |
| - Activity controlled by existing procedure or work plan
| |
| - Activity a design change
| |
| .
| |
| --
| |
| - . . . .
| |
| __
| |
| .
| |
| .
| |
| .- - ,... .
| |
| ...; .
| |
| ,. _
| |
| | |
| . - . - - -
| |
| .
| |
| | |
| TEMP ALT PROGRAM . .
| |
| Application of the temporary alteration decision process to the BWST
| |
| .
| |
| | |
| PSV removal
| |
| -
| |
| Error occurred in evaluating criteria to determine if maintenance controls adequate '
| |
| - Was the SSC under the control of Maintenance (removed from .
| |
| service)-
| |
| - Was the SSC depended upon by Operations (function still '
| |
| required) .
| |
| *
| |
| Condition Report issued on February 5,1998 ,
| |
| I | |
| | |
| .
| |
| .
| |
| | |
| , TEMP ALT PROGRAM Application of the temporary alteration decision process to the BWST PSV removal (Cont)
| |
| * Affected component seen as the PSV
| |
| * Performance of maintenance on an operable and unisolated SSC unusual
| |
| * Venting function at PSV valve flange not seen as required for operability of BWST
| |
| * FME cover seen as normal maintenance activity
| |
| .~,
| |
| | |
| .. . - | |
| .
| |
| *
| |
| *
| |
| COXFIGURATION EXAMPLES NORMALOPERATION
| |
| .
| |
| ,
| |
| f
| |
| | |
| ,
| |
| | |
| .
| |
| *
| |
| COXFIGURATION EXAMPLES NORMALOPERATION h
| |
| /
| |
| < +
| |
| MAINTENANCE ; OPERABLE I
| |
| A
| |
| < -
| |
| +
| |
| /
| |
| ~
| |
| HOLDCARD l
| |
| .
| |
| Not a temporary alteration
| |
| . . .. .
| |
| ..
| |
| .
| |
| . .
| |
| . .
| |
| .
| |
| . .
| |
| .
| |
| .
| |
| ..
| |
| .. ..
| |
| ..
| |
| | |
| m , 4 ,.
| |
| _ m - _ e a p' O 4?
| |
| ~
| |
| COXFIGURATION EXAMPLES NORMALOPERATION A
| |
| <
| |
| +
| |
| MAINTENANCE OPERABLE
| |
| <
| |
| #
| |
| l l TEMPORARYALTERATION '
| |
| , | |
| | |
| -
| |
| f
| |
| | |
| BORATED WATER STORAGE TAXK Maint 4" Vent n
| |
| 8" flange U i
| |
| u a / :
| |
| U .
| |
| - -
| |
| _
| |
| y Operable-k (NO)
| |
| Drawing not to scale
| |
| . .
| |
| _
| |
| .
| |
| ..
| |
| _ _ _ _
| |
| | |
| _ _.
| |
| | |
| .
| |
| | |
| TEMP ALT PROGRAM Evaluation of temporary alteration program _
| |
| * Current plant configuration
| |
| - Walkdown of accessible areas of ANO l&2
| |
| '
| |
| .
| |
| * Minor deviations noted
| |
| - Six drains altered
| |
| - One pressure gauge removed
| |
| - Review of in-progress or delayed ANO l&2 JO's
| |
| * No undocumented temporary alterations noted ,
| |
| .
| |
| ,
| |
| . . . . . . . . . . . . . . . .
| |
| . . . . , . .
| |
| . , .
| |
| , . . . . .
| |
| i
| |
| ... .
| |
| . . . _ .
| |
| .
| |
| .......i
| |
| . . . . . . . . . . . .
| |
| . .-
| |
| _ . _ _ _ _ _ _ _ _ _
| |
| | |
| _
| |
| | |
| TEMP ALT PROGRAM Evaluation of temporary alteration' program (Cont).
| |
| | |
| * Condition reports
| |
| - Review of temporary alteration condition reports since 1994 Do not reflect similar condition
| |
| ,
| |
| * 1995 condition report on interconnecting systems has some similarities, but not the same causes
| |
| *
| |
| Independent assessments
| |
| - INPO " blue card" challenge, August 1996
| |
| .
| |
| * No undocumented temporary alterations identified
| |
| - System Engineering corporate assessment, October 199'7 Temporary alterations was a focus area No undocumented temporary alterations identified
| |
| .
| |
| t
| |
| '
| |
| -~
| |
| - . _ _ _ _ .
| |
| | |
| . . . - - _ _
| |
| .
| |
| .
| |
| -
| |
| .;
| |
| .
| |
| -
| |
| ;46 1
| |
| ~
| |
| .
| |
| TEMP ALT PROGRAM t
| |
| !
| |
| | |
| Evaluation of temporary alteration program (Cont)
| |
| *
| |
| Independent assessments (Cont)
| |
| - QA Surveillance, September 1997
| |
| >
| |
| a No undocumented temporary alterations identified- '
| |
| .
| |
| * Condition report issued to document administrative
| |
| ,
| |
| issues
| |
| -
| |
| ,
| |
| * Action initiated to benchmark industry {:
| |
| l-
| |
| !
| |
| -
| |
| ! ;
| |
| :.
| |
| a
| |
| . .
| |
| | |
| . _ _ .
| |
| %
| |
| | |
| TEMP ALT PROGRAM
| |
| .
| |
| *
| |
| Evaluation conclusions
| |
| ;
| |
| - Existing procedure is providing adequate controls of plant configuration
| |
| - Removal of BWST PSV involved an unusual condition
| |
| * Maintenance on operable system without isolation .
| |
| * Temporary alteration process does not provide adequate guidance for this situation
| |
| .
| |
| 'I
| |
| _ _ - _ _ ____...______ _ __ _ -____________________ :
| |
| | |
| . -
| |
| -
| |
| ( *
| |
| l- TEMP ALT PROGRAM Corrective Actions
| |
| -
| |
| Completed
| |
| - Finalized temporary alteration package on BWST
| |
| - Letter issued to plant personnel to heighten awareness of the potential for creating temporary alterations during maintenance and to clarify temporary alteration decision criteria '
| |
| *
| |
| In-Progress
| |
| - Appropriate training will be completed by March 13,1998
| |
| '
| |
| - Root cause analysis and comprehensive corrective action plan is scheduled for completion by March 5,1998
| |
| - Initial review of implementing documents for Operations and Maintenance is scheduled for completion by March 5, 1998
| |
| .
| |
| | |
| .
| |
| .
| |
| s
| |
| | |
| -
| |
| TEMP ALT PROGRAM
| |
| | |
| Corrective Actions (Cont)
| |
| -=
| |
| Planned Actions .
| |
| - Completion of industry benchmarking
| |
| '
| |
| - Changes to the temporary alteration procedure to provide clarification /
| |
| .
| |
| - Additional written gyldance for Maintenance Planners and Operations Liaisons
| |
| - Training of personnel on the procedure changes
| |
| _
| |
| | |
| . .. - - -
| |
| ---. _. .. .
| |
| ..
| |
| . 50
| |
| -
| |
| TEMP ALT PROGRAM Summary
| |
| *
| |
| Temporary alteration procedure initiates the design control and 50.59 review processes
| |
| *
| |
| The process implementing temporary alteration controls and 50.59 reviews is sound
| |
| *
| |
| Error made in application of temporary alteration decision criteria i
| |
| *
| |
| Procedure did not provide guidance addressing the unusual
| |
| '
| |
| situation of-maintenance performed on an operable and -
| |
| unisolated component -
| |
| *
| |
| Interim guidance issued and appropriate training will be performed f
| |
| ___ _ , __ _ _ _ . _ _ _ _ _ _ -
| |
| _ _ _ .
| |
| | |
| __ ~ -
| |
| -
| |
| | |
| XOX-OUTAGE TEST PERFORMAXCE
| |
| ~
| |
| ;
| |
| Pete Dietrich
| |
| '
| |
| Manager, Unit 1 Maintenance.
| |
| | |
| .
| |
| -- .
| |
| | |
| - --
| |
| | |
| ~
| |
| XOX-OLTAGE TEST PERFORMAXCE
| |
| = Statement of Apparent Violation
| |
| - Use of BWST PSV testing procedure during power operations was improper.. Paragraph 4.3.1 stated that inspection of the valve would be performed each refueling outage.-
| |
| * BWST PSV testing procedure (January 1995 version) referenced l IEB 80-05, Vacuum Condition ~Resulting in Damage to CVCS Holdup '
| |
| Tanks, but contained no description of reference
| |
| - Response to IEB 80-05 stated that PSV inspection will be scheduled during each refueling outage
| |
| - Response was not adequately reviewed when PSV testing moved to non-outage performance in January 1995
| |
| .
| |
| .
| |
| _ _ _ _ _
| |
| | |
| .
| |
| | |
| XOX-OLTAGE TEST PERFORMAXCE
| |
| .
| |
| '
| |
| - BWST PSV testing procedure l
| |
| - Procedure revision used on December 3,1996 listed response to IEB 80-05 in paragraph 4.3.1 as a commitment implemented in the document but did not provide description of commitment
| |
| - Revision approved July 21,1997 added specific wording in step 4.3.1 referenced in the violation as a result of commitment implementation improvements started in 1995
| |
| - Agree with violation but commitment not easily recognized I
| |
| - Conversion effort should have incorporated temporary
| |
| ;
| |
| alteration controls
| |
| .
| |
| . . . . _ . . . . . . , ,
| |
| . . , _ . . . . . . . . . . . . . , . , , , . . - . . . .
| |
| .
| |
| _ . . .
| |
| .
| |
| . . . . _
| |
| ..
| |
| .. . . . . . . . . . . . .
| |
| | |
| .
| |
| .v~
| |
| ~ '
| |
| -
| |
| -
| |
| | |
| .
| |
| -
| |
| -
| |
| XOX-OLTAGE TEST PERFORMAXCE i
| |
| ,
| |
| Cause-
| |
| *
| |
| Process for conversion of activities from outage to non-outage performance was not as encompassing as desired
| |
| '
| |
| Corrective Actions
| |
| *
| |
| Enhanced conversion process by adding cross-functional team review with specific review criteria for activities
| |
| *
| |
| Performing review of previously converted activities against specific review criteria
| |
| - Unrevie.wed activities placed on hold
| |
| *
| |
| Converted the performance of this activity back to outage
| |
| - _ -
| |
| - -
| |
| | |
| - _ _ _.
| |
| | |
| ,
| |
| -
| |
| | |
| L
| |
| .
| |
| XOX-OLTAGE TEST PERFORMANCE Issue l
| |
| * Deviated from the commitment requirement for testing the PSV !
| |
| '
| |
| during refueling outages Corrective Actions
| |
| -
| |
| Adjusted processes to ensure proper reviews on changes in activities which implement commitments
| |
| -
| |
| Procedure control process enhanced to ensure effects on commitment implementation are evaluated as part of procedure app val
| |
| -
| |
| Site procedures are under review for incorporation of appropriate references to commitments to ensure continued compliance
| |
| . _.
| |
| | |
| - _--
| |
| O
| |
| | |
| XOX-OUTAGE TEST PERFORMAXCE l
| |
| Issue. ,
| |
| * The ULD contained misleading information on the redundancy l
| |
| !
| |
| of the 4" vent line Corrective Actions
| |
| * ULD corrected
| |
| - Cause determined I - Open ULD discrepancies reviewed for ability to create a similar condition l
| |
| l l
| |
| .. - . . . . . . _ . . . .
| |
| .
| |
| ..... -
| |
| . .
| |
| ~-
| |
| .
| |
| ._.
| |
| | |
| __ . . .
| |
| _
| |
| .
| |
| | |
| .
| |
| XOX-OUTAGE TEST PERFORMAKCE Issue ,
| |
| * BWST PSV testing was performed non-outage in April 1995 Related Information
| |
| * Testing lasted approximately 10 hours
| |
| * Type of FME cover used cannot be determined
| |
| - Corrective actions same as for December 1996 performance l
| |
| i l
| |
| . . . .
| |
| . . _ . . . . .
| |
| . . . . . . . . . .
| |
| _ _ _
| |
| . . . . . . . . . . . . . . . . . . . .
| |
| _ ,
| |
| .
| |
| ...
| |
| _ . . _
| |
| | |
| , ---
| |
| , .
| |
| .
| |
| | |
| -
| |
| XON-OLTAGE TEST PERFORMAXCE
| |
| .
| |
| -
| |
| Summary
| |
| * BWST PSV test should not have been performed non-outage without commitment change and temporary alteration controls
| |
| "
| |
| - Recognition of commitment by individuals involved in the l
| |
| '
| |
| conversion and performance of the activity would not be obvious
| |
| '
| |
| * Problems were self-identified
| |
| * Corrective action plans to address issues are comprehensive and should prevent recurrence m. --w.--s--==-- %--- -- - - - -- - -am- -
| |
| _ _ _ _ _ _ _ _ _
| |
| | |
| -
| |
| . _ . .
| |
| .
| |
| .
| |
| | |
| EXFORCEMKNT PERSPECTIVE
| |
| ~
| |
| .
| |
| l i
| |
| Dwight Mims Director, Licensing
| |
| '
| |
| .
| |
| '
| |
| ' ' ' ' ' '
| |
| - . . . . - - -
| |
| _ _ _ _ _ _ _ , _ _ _
| |
| .._-.__.---....-7
| |
| | |
| .
| |
| | |
| APPARENT VIOLATION T-ALT /50.59 !
| |
| :
| |
| '
| |
| * Failure to utilize the correct design control processes (temporary alterations) for the temporary cover configurations placed over the PSV valve flange
| |
| * Failure to perform proper safety evaluations NOTE:
| |
| The failure to utilize the correct design control process and the
| |
| '
| |
| .
| |
| failure to perform a proper safety evaluation are consequential with each other and should be considered as one apparent violation l .
| |
| u _ _ _ _ _ _ _ _ _ _ _ . _ _ . . . _ = _ . . . _.
| |
| | |
| _
| |
| | |
| .
| |
| | |
| T-ALT /50.59 ISSLES Actual and Potential Safety Consequences
| |
| * BWST remained operable
| |
| - Would have performed intended safety function
| |
| - Operator response minimally affected by BWST level l indication l - System Engineer focused on operability and safety Conclusion
| |
| '
| |
| * Low actual or potential safety consequences I
| |
| | |
| .
| |
| | |
| T-ALT /50.59 ISSUS Regulatory Significance
| |
| - Self-identified
| |
| - ANO recognizes our regulatory responsibility as a licensee to perform engineering activities in accordance with established procedures
| |
| ! * ANO has shown commitment to taking comprehensive
| |
| '
| |
| corrective actions to address the root and contributing causes independent of any enforcement actions
| |
| * Condition not representative of overall ANO performance
| |
| - Not representative of overall engineering performance
| |
| - No major program breakdown
| |
| * Condition not repetitive
| |
| * Condition not willful
| |
| - Violations do not appear to have a common root cause Conclusion
| |
| * Low regulatory significance
| |
| -
| |
| -_
| |
| | |
| .
| |
| _
| |
| _
| |
| .
| |
| .
| |
| | |
| T-ALT /50.59 ISSUS Severity Level
| |
| * Failure to invoke temporary alteration requirements
| |
| - Procedure guidance insufficient j
| |
| * Precluded invoking the 50.59 process
| |
| - BWST remained operable, therefore, the condition had low actual or potential safety consequences
| |
| '
| |
| - Basis exists in Supplement I.D.3 to conclude that the issue is a Severity LevelIV violation -
| |
| * Failure to meet regulatory requirements that have more than minor safety significance
| |
| | |
| _
| |
| .
| |
| | |
| APPAREXT VIOLATION Non-outage test performance
| |
| * Failure to perform proper PSV valve testing under the plant conditions as prescribed in the test procedure I i
| |
| .
| |
| | |
| .
| |
| ,
| |
| _. o
| |
| ~ '
| |
| -
| |
| | |
| .
| |
| XOX-OLTAGE PERFORMAXCE s
| |
| Actual and Potential Safety Consequences
| |
| .
| |
| *
| |
| ~BWST remained operable -
| |
| Conclusion
| |
| -
| |
| Low actual or potential safety consequences
| |
| - Confirmed by test and calculation
| |
| .
| |
| | |
| .
| |
| .
| |
| .
| |
| XOX-OLTAGE PERFORMAXCE Regulatory Significance .
| |
| .
| |
| - Self-Identified ,
| |
| * ANO recognizes our regulatory responsibility as a licensee to perform maintenance in accordance with established procedures ANO has shown commitment to taking comprehensive
| |
| '
| |
| -
| |
| corrective actions to address the root and contributing causes independent of any enforcement actions
| |
| - Condition not representative of overall ANO performance
| |
| - Not representative of overall maintenance performance
| |
| '
| |
| f
| |
| - No major program breakdown
| |
| - Condition not repetitive
| |
| - Condition not willful
| |
| - Violations do not appear to have a common cause Conclusion
| |
| ,
| |
| = Low regulatory significance
| |
| -----
| |
| | |
| . . --
| |
| .
| |
| <
| |
| | |
| =
| |
| XOX-OETAGE PERFORMANCE Severity Level The failure to perform an adequate review of the PSV test procedure for non-outage performance did not cause the BWST to be inoperable; therefore, basis exists in Supplement I.D.3 to conclude that the condition is a Severity LevelIV violation I - Failure to meet regulatory requirements that have more than
| |
| '
| |
| minor safety significance or environmental significance
| |
| -
| |
| The performance of BWST PSV testing during non-outage
| |
| : conditions was a deviation from a commitment made in '
| |
| response to IEB 80-05
| |
| | |
| -
| |
| :
| |
| i l
| |
| t
| |
| !
| |
| _
| |
| | |
| .-
| |
| .
| |
| .
| |
| | |
| CLOSIXG COMMElNTS l
| |
| l Randy Hutchinson
| |
| .
| |
| Vice President, Operations
| |
| }} | | }} |
