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{{Adams
#REDIRECT [[IR 05000458/1986020]]
| number = ML20213E539
| issue date = 11/05/1986
| title = Ack Receipt of 860829 & 1017 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/86-20
| author name = Gagliardo J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name = Cahill W
| addressee affiliation = GULF STATES UTILITIES CO.
| docket = 05000458
| license number =
| contact person =
| document report number = NUDOCS 8611130209
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 2
}}
See also: [[see also::IR 05000458/1986020]]
 
=Text=
{{#Wiki_filter:,  .
                                        NOV  5 1986
  In Reply Refer To:
  Docket: 50-458/86-20
  Gulf States Utilities
  . ATTN: William J. Cahill, Jr.
            Senior Vice President
            River Bend Nuclear Group
  P.-0. Box 220
  St. Francisville, Louisiana      70775
  Gentlemen:
        Thank you for your letters, dateo August 29, 1986, and October 17, 1986,
  in response to our letters, dated July 30, 1986, and September 16, 1986. We
  have no further questions at this time and will review your corrective action
  during a future inspectio'n.
                                              Sincerely,
                                                -cornai nma dy:
                                                # 1. r_ H A t. L*
                                              J. E. Gagliardo, Chief
                                              Reactor Projects Branch
  cc:
  Gulf States Utilities
  ATTN:    J. E. Booker, Manager-
                Engineering, Nuclear
                Fuels & Licensing
  P. O. Box 2951
  Beaumont, Texas      77704
                                            '
  Louisiana State University,
      Government Documents Department
  Louisiana Radiation Control Program Director
  bcc:    (see next page)
      '                      iV
        1
    C      /(              C RPB
  JPJpu on:cs          /kJEGagliardo                                            g
    11/g/86              Wil/ /86                                                D\
                                                                            4      y
                                                                                    s  \
                      8611130209 861105
                      PDR    ADOCK 05000458
                      G                PDR
                                                                                        1
 
, .
  Gulf States Utilities        -2-
  bec to DMB (IE01)
  bcc distrib. by RIV:
  RPB                  DRSP
  Resident Inspector    R. D. Martin, RA
  Section Chief (RPB/A) D. Weiss, LFMB (AR-2015)
  MIS System            RSB
  RSTS Operator        R&SPB
  RIV File
 
    ' '
.
                                                                                                                          0
  s.
            GULF STATES                          UTELETIES COMPANY ,
                      river BEND STATION      Post OFFICE BOX 220    $7 FR ANCISVlLLE. louts 4ANA 70775
                                          AREA CODE 504      635 6094    346 8651
                                                                                                August 29, 1986
                                                                                                RBG-        24275
                                                                                                File Nos. G9.5, G15.4.1
        Mr. Robert D. Martin, Regional Adntinistrator
        U.S. Nuclear Regulatory Commission
        Region IV                                                                                                                          t
                                                                                                        _.
                                                                                                                g,.    ,
        611 Ryan Plaza Drive, Suite 1000                                                                      j 1:, y tf. t :
        Arlington, TX 76011
                                                                                                        ,
                                                                                                                                  '
                                                                                                        '
                                                                                                              i                            j
        Dear Mr. Martin:                                                                                          SEP - 41986      ', _
                                                                                                                                      :
                                                                                                          "
                                                                                                                                      dO;
                                        River Bend Station - Unit 1                                          -
                                              Refer to: Regicn IV                                                                        -
                                    Docket No. 50-458/ Report 86-20
              This letter is in response to the Notice of Violation
        contained in NRC Inspection Report No. 50-458/86-20.                                                                  The
        inspection was performed by Messrs. D. D. Chamberlain and W. B.
        Jones during the period May 1 through June 15, 1986, of
        activities authorized by NRC Operating License NPF-47 for River
        Bend Station Unit No. 1.
                                                                                    .
              Gulf States Utilities Company's (GSU) response to the Notice
        of Violation 8620-01 and                            8620-02 is provided in the enclosed
        attachment. This completes                        GSU's response to the Notice of
        Violation.
                                                                                              Sincerely,
                                                                                                                            .
                                                                                              W. J. Cahill, Jr.
                                                                                              Senior Vice President
                                                                                              River Bend Nuclear Group
              GP 6?S
        WJC/ ERG /RRS/kn
        Attachment
                                                  ,    ,
                                        t,t                ^
                    -
                            ,/ ri ,
                                      l L k' cs O )
                    {)D V l I  .f
TL-ut(8to
 
. .
                                UNITED STATES OF AMERICA
                            BUCIAAR REGUIATORY Ct3 MISSION
                                                                        -
                        .
    STATE OF IRISIAEA                      5
    FARISE OF UEST FELICIANA                l                              .
    In the Matter of                        $          Docket Boe. 50-458
    CULF STATES UTILITIES CtBIFARY          I
          (River Bend Station,
                                  *
          Unit 1)                                                                .
                                        AFFID&VIT
          W. J.  Cahill,  Jr.,  beins duly sworn, states that he is a Senior
    Vice President of Gulf States Utilities Company        that he is authorized
    on the part of said Company to sign and file with the Nuclear Regulatory
    Commission the documents attached heretos and that all such documents
    are true and correct to the best of his knowledge, information and belief.
                                            W.    Cahill, Jr. //
                                                                      .-
          Subscribed and sworn to before me, a Notary Public in and for the
    State and Parish above named, this /7 day of dead ,19&.                          l
                                                        l          r
                                                tt o                      /%
                                              anW.Middlebloops                      I
                                              otary Public in and for
                                            West Feliciana Parish,
                                            Louisiana                                l
                                                                                    l
    My Conunission is for Life.                                                    l
                                                                                    1
                                                                      -
      _
                                                                                    i
 
                                  . _  .            _.                  .    _ _ _ .        ._  _  . _ _ _ _                  __ . . , .
              .              .
      .
                                                              ATTACHMENT
                                                                                                            .
                                          Response to Notice of Violation 50-458/8620-01
{
                                                                Level IV
                                FAILURE TO FOLLOW ADMINISTRATIVE PROCEDURES FOR ISSUANCE OF
                                TEMPORARY CHANGE NOTICES (TCN's)
                                REFERENCE:
                                Notice of Violation      -
                                                              Letter        to W. J. Cahill, Jr. from J. E.
                                Gagliardo dated July 30, 1986.
;
'
                                REASON FOR THE VIOLATION
l                              During an NRC inspection conducted on May 1 through June 15,
                                1986,    the    inspectors    identified              a  failure  to            follow
:                              Administrative procedures. As a result of personnel oversight,
,                              I&C Maintenance Technicians failed to comply with the procedural
                                requirements      of    Administrative                Procedure    (ADM)-0003,
;                              " Development, Control and Use of Procedures" when initiating
i                              Temporary Change Notice No. 86-0581 for procedure STP-051-4210.
                                This    resulted in an official work copy of the procedure
,
                                containing duplicate page numbers with different Temporary Change
:                              Notice (TCN) Numbers on each page.
i
)                              CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS' ACHIEVED
;                              On April 10, 1986, prior to the NRC inspection, Memorandum No.
:                              PAS-86-141 was issued identifying procedures with two or more
                                TCN's    having duplicate pages with different changes.
'
                                                                                                                              The
;
                                memorandum identified the deficiencies with STP-051-4210 and
j                              requested that the faulty TCN's be corrected.
i                              In response to Memorandum No. PAS-86-141, Procedure STP-051-4210,                                            .
l                              Revision 2, was submitted for revision on April 20, 1986 to                                                  !
l                              incorporate the outstanding TCN's and eliminate the duplicate
                                pages. Revision 3 of STP-051-4210 was approved and issued on
                                July 30, 1986.
                                CORRECTIVE STEPS WILL BE TAKEN TO AVOID FURTHER VIOLATIONS
                                The I&C Procedure Coordinator reviewed the TCN deficiencies with
i
                                the. responsible individuals and instrucLad the individuals to
'
                                comply with the requirements of ADM-0003 when initiating future
                                TCN's.
                                Memorandum No. PIC-M-86-116 was issued on July 9, 1986 requesting
                                that TCN's issued by the I&C Maintenance Department be routed
l                              through the I&C Procedure Coordinator prior to obtaining the
,
                                Shift Supervisor's signature. The IEC Procedure Coordinator is
i                              responsible for reviewing TCN's being issued to assure compliance
l                              with ADM-0003 and evaluates the necessity of the TCN. The
;
  . - _ _ . _ _ , . _ _ . . .                      _ _-    _    ___.____                                      _ _ _ - _ _ _
 
                                              .                . ,                - --                        . - -          - .      -
  e
  f  .      .
    .
                                                          ATTACHMENT (Cont'd)
              routing of the TCN through the I&C Procedure coordinator will be
              discontinued when the number of                                    TCN's    being                  issued            is
              significantly reduced.
]              To prevent recurrence of similar violations, ADM-0003 was revised
'
              on 8/6/86 to clarify procedural instructions for issuing a TCN to
              a page that has been previously changed by a TCN.
              DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED
                                                        '
              STP-051-4210                      was reviied on July 30, 1986 to incorporate the
*
              outstanding TCN's and eliminate the duplicate pages.
;
              River Bend Station is currently in compliance.
;
                                        e
!                                                                                        +
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!
!
I
i
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I
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!
        -. .      . . . - - - - - - - . - . -                      - - - . - . -          - . . . - - - _ . - - - . . - . . _ . -    _.
 
    -        -    .  .  _ - .        -
<
  ,
      . .
e
                                                                    Page 3
                                        ATTACHMENT (Cont'd)
                      Response to Notice of Violation 50-458/9620-02
                                            Level.IV
<
          FAILURE TO CONTROL ACTIVITIES AFFECTING QUALITY
          REASON FOR THE VIOLATION
          A walkdown of the "C" Residual Heat Removal (RHR) system by NRC
          inspectors identified the following differences between actual
*
          system configurations and controlling instructions, procedures,
          and    drawings:        1)  five pipe caps, shown as installed on
          Engineering, Piping and Instrument Drawing PID-27-C were not.
          installed, 2)          valve E12*MOVF064C, which was shown closed on
          Engineering, Piping and Instrument Drawing PID-27-7C was open, 3)
          valve E12*VF063C was not locked, although Engineering, Piping and
          Instrument Drawing PID-4-3C showed this valve to be locked, 4)
          differences were found between Engineering, Piping and Instrument
          Drawing PID-27-7C and System Operating Procedure, SOP-0031, as to
          which valves were locked in position.
          Item 1
          Investigaticns to determine the reason that the pipe caps are
          missing, although shown installed on Engineering, Piping and
          Instrument Drawing, PID-27-7C, are indeterminate.
          Item 2
          The minimum flow valve E12*VF064C was placed in the open
          position, per the SOP-0031, however, PID-27-7C showed this valve
          to be closed.
          Item 3
          Operations personnel had previour,1y performed an audit of locked
          valves on the RHR system and determined valve E12*VF063C was
          verified to be closed, but no lock was installed on the valve
          because it was approximately twenty feet above the floor and
          considered inaccessible.
          Item 4
          Operations was aware of the differences between the two existing
          system drawing types and the SOP's and was in the process of
          correcting this situation by revisions to the PID's and the
          SOP's. The cause of these discrepancies was determined to be the
          lack of configuration management programs to ensure procedure
          updates on the issuance of changes to drawings and drawing
          updates to reflect commitments to lock specific valves.
 
              . .            - - .      _. _    _        -    -    .  .-          .  --    .  -                __ . - . -
i
        ,
          e *  .
!
      .
                                                                                            Page 4
;
                    CORRECTIVE STEP WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED
                    The five missing pipe caps that are shown on PID-27-C have been
                    replaced.
                    Since valve E12*MOVF064C was in the proper position in accordance
                    with SOP-0031 it will be left in this position (i.e., open to
                    allow minimum flow).
i
                    Valve E12*VF063C has been locked as shown on PID-4-3C.
                    Operations has revised the RHR SOP to agree with existing FID's.
!
                    CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS
:
                    Nuclear Equipment Operators on rounds will take notice of missing
.
                    pipe cape and r? place them. A supply of caps has been placed in
l                  the Control Room for this purpose. Additionally, Local Leak Rate
!                  Testing        (LLRT)      Procedures will include a step to ensure
i                  replacement of caps which are removed for LLRT.                    Nuclear Plant-
l                  Engineering (NuPE), along with Stone & Webster (S&W) is in the
                    process of determining which valve caps are required for a system
j
                    to meet its intended design.
                    PID's will be revised to indicate valve position for a normal
                    mode of operation, and Station Operation Manual (SOM) procedures
;                  will govern actual valve position.
1                                                                              .
                    A new procedure,                Operation Section Procedure OSP-0014, which
                    directly addresses the control of locked valves has been issued
i                  by the River Bend Operations Department.
J
'
                    A review of all PID's versus SOPS has been conducted. Changes to
i
                    the procedures have been issued to- agree with the PID's.                                      A
                    review of the PID's is being performed by NuPE to determine which
!                  valves should be locked and which should be left unlocked.                        NuPE
l^                  will also develop a procedure which will delineate the locked
                    valve regulation requirements. Included in this review will be
,                  the necessary changes of PID's to match these requirements. Upon
                    completion, it is expected this will decrease the number of
                    valves required to be locked.
j                  Adequate        configuration          management    control    procedures are
;
                    currently in place. All changes to locked valve status will be-
                    followed by updates to the SOP's via these controls,
i
i                  DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED
l                  The additional procedural controls ensuring replacement of pipe
t
                    caps in Local Leak Rate Testing Procedures will be completed by
;
                    October 30, 1986.
d
1
!
  - - -          -    -                      .                  -          -    -_                - - . _ - - -
 
                                                    .
    . .  ,
  o
                                    ATTACHMENT (Cont'd)
            Valve E12*VF063C has    been verified to be locked at the time of
            this response.
            Procedures being devel5 ped by NuPE for determining locked valve
            regulation requirements will be completed by November 30, 1986.
        ,    The;PID changes brought about by NuPE's reviews will be completed
            iby December 31, 1986.
                                                        .
                        E
1
-
 
,.    .    . . _ - - - - _ - - - - - _
      e * .
                                                                                                                                1;h
  '
                            GULF STATES                              UTILETIES COMPANY
                                                                                                                                  eg
                                            RIVER BEND STAYtON    POST OFFICE 80x 220    St FRANCISvtLLE. LOutslANA 70776
                                                              ARE A CODE 604    635 6094    346-8651
                                                                                                                October 17, 1986
                                                                                                                RBG-        24583
                                                                                                                File Nos. G9.5, G15.4.1
                  Mr. Robert D. Martin, Regional Administrator
                  U.S. Nuclear Regulatory Commission
                  Region IV
                  611 Ryan Plaza Drive, Suite 1000
                  Arlington, TX 76011
                  Dear Mr. Martin:
                                                            River Bend Station - Unit 1
                                                                  Refer to: Region IV
                                                        Docket No. 50-458/ Report 86-20
                                  This letter is in supplemental response to the Notice of
                  Violation contained in NRC Inspection Report No.                                                                50-458/86-20.
                  The inspection was performed by Messrs. D. D. Chamberlain and W.
                  B. Jones during the period May 1 through June 15, 1986, of
                  activities authorized by NRC Operating License NPF-47 for River
                  Bend Station Unit No. 1.
'
                                  Gulf States Utilities Company's (GSU) supplemental response
                  to                the  Notice of Violation 8620-02,                                        " Failure          to Control
                  Activities Affecting Quality", is provided in the enclosed
                  attachment.                    This completes GSU's response to the Notice of
                  Violation.
                                                                                                                Sincerely,
                                                                                                                            ,
                                                                                                                W. J. Cahill, Jr.
                                                                                                                Senior Vice President
                                                                                                                River Bend Nuclear Group
                                                                                                                                                  .
                  Attachment                                                                        .
                                                          ,      t  ~i} f                                        @
                                          g~t
                                          <
                                          U
                                                              ,w>                                          )
                                                                                                                  OCT 231986
                                                        Mc    -,;                                    -
                                                                                                        .
                                                                                                              . . . _ _
                                                                                                                                      D
                                                                                                                                        .      3
                                                                                                                      .. . . . . .
  g g 59        6                                                                                                                            Yo
 
        .
      .  .
,
*                                              UNITED STATES OF AMERICA
                                            BUCLEAR EEGULATORY CCESEISSION
                                        -
                                                                                                                                    ,
              STATE OF IAUISIAEA                                    5
              FARISE OF WEST FELICIAEA                              5
              In the Matter of                                      I                    Docket Bos. 50-458
              GULF STATES UTILITIES C(EEFANY                        $
                    (River Bend Station,
                    Unit 1)                                                                                                                          .
                                                                AFFID&VIT
                    W. J.  Cahill,        Jr.,  being duly sworn, states that he is a Senior
              Vice President of Gulf States U' 111 ties Company: that he is authorized
              on the part of said Company to sign and file with the Nuclear Regulatory
              Commission the documents attached heretos and that all such documents
              are true and correct to the best of his knowledge, information and belief.
                                                                    W. J Cahill, Jr.
                                                                                                                                      ..
                    Subscribed and sworn to before me, a Notary Public in and for the
              State and Parish above named, this /8              ,
                                                                        day of                  #MM , 19ffe,.
                                                                Q              9//] L U L L /,
                                                                                                                                          -
                                                                L    L.,. ,
                                                                    Joan W. Middlebrooks
                                                                    Notary Public in and for
                                                                    West Feliciana Parish,
                                                                    Louisiana
              My Commission is for Life.
_. .      .    --          - _ - - -          - - . _ _ . .-              . . - . _ . _ - _ _ . _ . - - . - . . _ - - _ _ _ _ . -        . - _ _ .
 
    . .    .
  ,
  .
                                                            ATTACHMENT
                                          Response to Notice of Violation 50-458/8620-02
                                                              Level IV
              FAILURE TO CONTROL ACTIVITIES AFFECTING QUALITY
              REFERENCE
              Notice of Violation - Letter to W.                                                J.          Cahill,      Jr.  from  J.  E.
              Gagliardo dated July 30, 1986.
              Request for supplemental information - Letter to W. J. Cahill,
              Jr. from J. E. Gagliardo dated September 16, 1986.
              REASON FOR THE VIOLATION
              A walkdown of the "C" Residual Heat Removal (RHR) system by NRC
              inspectors identified the following differences between actual
              system configurations and controlling instructions, procedures,
i
              and              drawings:          1)  five pipe caps,                                          shown as installed on
:            Engineering, Piping and Instrument Drawing (PID)-27-C were not
              installed,                      2) valve E12*MOVF064C, which was shown closed on
            PID-27-7C was open, 3) valve E12*VF063C was not locked, although
              PID-4-3C showed this valve to be locked, 4) differences were
              found between PID-27-7C                        and                    System                        Operating  Procedure,
              (SOP)-0031, as to which valves were locked in position.
              Item 1
              Investigations to determine the reason that the pipe caps are
            missing, although shown installed on PID-27-7C are indeterminate.
                                                                                                                                                      .
              Item 2
              The minimum flow valve E12*VF064C was placed in the open
            position, per the SOP-0031, however, PID-27-7C showed this valve
              to be closed.
4
              Item 3
            Operations personnel had previously performed an audit of locked
            valves on the RHR system and determined valve E12*VF063C was
            verified to be closed, but no lock was installed on the valve
            because it was approximately twenty feet above the floor and                                                                            *
            considered inaccessible.
              Item 4
            Operations was aware of the differences between the two existing
              system drawing types and the SOP's and was in the process of
              correcting this situation by revisions to the PID's and the
              SOP's. The cause of these discrepancies was determined to be the
    ~ _ . -      _ _ _ _ _ _ _ _ _ _ _ _ _                    _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ - _ . . _ . _ _ ,                          _ _ _ _ .
 
                                                                                                                        ..
      . . .
    ,
    t
                                                      ATTACHMENT (cont'd.)                Page 2
            lack of configuration management programs to ensure procedure
            updates on the issuance of changes to drawings and drawing
            updates to reflect commitments to lock specific valves.
,
            CORRECTIVE STEP WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED
4
            The five missing pipe' caps that are shown on PID-27-C                        have                  been
            replaced.
            Since valve E12*MOVF064C was in the proper position in accordance
            with SOP-0031 it will be left in this position (i.e., open to
            allow minimum flow).
I          Valve E12*VF063C has been locked as shown on PID-4-3C.
            Operations has revised the RHR SOP to agree with existing PID's.
            CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS
            Nuclear Equipment Operators on rounds will take notice of missing
            pipe caps and replace them. A supply of caps has been placed in
            the Control Room for this purpose.                          Local Leak Rate Testing
            (LLRT) Procedures include a step to ensure replacement of caps
          which are removed for LLRT. GSU Design Engineering, along with
            Stone & Webster (S&W) is in the process of determining which pipe
            caps are required for a system to meet its intended design.
          A new procedure, Operation Section Procedure (OSP) -0014, " Control
          of Locked Valves and Devices", which directly controls locked
          valves and other devices required to be locked has been issued by
'
            the Operations Department.
          GSU Design Engineering has initiated two Modification Requests
            (MR's),          Nos.  86-1587 and 86-1588, to add notes to the PID's
          concerning valve position and pipe caps. A note will be added to
            PID's stating that valve positions shown on the PID's are for the
l
          normal mode of operation and are for information only. The valve
          positions indicated by the PID's are not to be used for actual
          valve lineups.                Station Operation Manual (SOM) procedures will
          govern actual valve position.                          Another note on the PID's will
          state that pipe caps are not required for system operability.
          Any exceptions to this note will be identified on the PID.                                                  .
I
          A review of PID's against Flow Diagrams (FSK's) and Loop Diagrams
          by S&W began in January                          1986.    This      review  identified
;          discrepancies in these drawings. MR's were initiated to resolve
,
            these discrepancies in accordance with existing design control
:          procedures.              This initial review has been completed, however, all
l          MR's have not been closed. Ninety-Five (95) MR's were identified
4
I
  _.      . _ _ _ _ _ . _ _ _        _      . _ , , _ _        __        _ _ _ _ _ . _ , _ _ _ _ . , . - . . -          -
 
                                                .- -      -      . _.  -_ -
      . ..
    ,
t
t
!
!                                              ATTACHMENT (cont'd.)                Page 3
f
                that affect PID's. Design Engineering will conduct a survey of a
                  10% sample of safety related PID's to verify the effectiveness of
                the S&W review.            If additional discrepancies are identified, an
                MR is processed in accordance with NuPE-AA-0054, " Guidelines and
                Instructions for Processing Modification Requests".
                PID's will be reviewed and revised to include locked open and
i                locked closed designations for those valves which must be locked
                because of regulatory requirements. A list of locked valves will
                be generated and a Design Engineering procedure developed to
,
                control this list and to delineate the requirements for locking
"
                valves. Upon completion, this procedure will be forwarded to
;                Operations for implementation under OSP-0014.
!
                The            criteria  will divide locked valves into two groups:
                regulatory required locked valves and administrative required
                  locked valves.          Regulatory required locked valves are those
                valves that must be locked in accordance with                      regulatory
                requirements.          Administrative required locked valves are those
;                which, at the discretion of the River Bend Operations Department,
                must be locked for safety considerations or other administrative
                reasons.
:                Overall, it is anticipated that this review process and the
                establishment of the locked valve criteria will reduce the number
                of required locked valves.
i
                A review of PID's versus SOP's has been conducted.              Changes to
;                the procedure have been issued to agree with the PID's. Adequate
-
                configuration management control procedures are currently in
,
                place, and changes to locked valve status will be followed by
"
                updates to the SOP's via these controls.
;                DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED
                The procedural controls ensuring replacement of              pipe  caps        in l
i
                Local Leak Rate Testing Procedures are in place.
                Valve E12*VF063C          has    been verified to be locked at the time of
                this response.
                MR's issued to correct discrepancies between PID's and FSK's
l                Loop Diagrams will be completed by December 31, 1986.                          andl
I                The review of PID's with respect to locked valve criteria and the
  .
                procedures controlling these locked valves will be completed by
!
                November 30, 1986.
1
i
  i
!--.    . . - . - - _ - - _ -                - - _ - . -                    -        - - - -
 
                                                    . _ _ - .
    . , s
  .
  .
                                  ATTACHMENT (cont'd.)              Page 4
          MR  86-1587 concerning pipe caps on PID's and MR 86-1588
          concerning valve position will be completed by December 31, 1986.
          The Design Engineering survey of safety  related  PID's  will be
          completed by December 1, 1986.
>
l
!,
i
i
l
l
t
l                                                                            -
,
i
,
;
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