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{{Adams
#REDIRECT [[IR 05000424/1987001]]
| number = ML20209E044
| issue date = 04/11/1987
| title = Insp Rept 50-424/87-01 on 870105-09 & 12-16.Violations Noted:Failure to Follow Procedure 00404 C by Signing Surveillance Task Sheets for Class 1E 18-month Battery Insp & Maint Indicating Acceptance Criteria Met
| author name = Shymlock M, Watson L
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =
| addressee affiliation =
| docket = 05000424
| license number =
| contact person =
| case reference number = TASK-1.C.2, TASK-TM
| document report number = 50-424-87-01, 50-424-87-1, IEIN-86-061, IEIN-86-61, NUDOCS 8704290419
| package number = ML20209E018
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 39
}}
See also: [[see also::IR 05000424/1987001]]
 
=Text=
{{#Wiki_filter:.
                    p2 Ric                                  UNITED STATES
                          oq'o                NUCLEAR REGULATORY COMMISSION
              2
                /    ~
                              g
                              o                                REGloN il
              5              $                  101 M ARIETTA STREET N.W., SUITE 2900
              *              8
                o                                        ATLANTA, GEORGIA 30323
                s,
                    .....
                            /
                  Report No.:        50-424/87-01
                  Licensee: Georgia Power Company
                                  P. O. Box 4545
                                  Atlanta, GA 30302
                  Docket No.: 50-424                                                      License No.: NPF-61
                  Facility Name: Vogtle 1
                  Inspection Conducted: January 5 - 9 and January 12 - 16, 1987
                  Inspector:            h OM
                                L. J./ Watson, Team Leader
                                                                                                        '/!87
                                                                                                  Dath Signed
                  Team Members:        B. R. Bonser
                                        M. S. Lesser
                                        A. R. Long
                                        P. B. Moore
                                        G. Nejfelt
l                                      T. J. O'Connor
'
                                        W. K. Poertner
                                        M. B. Shymlock
                                        C. L. Vanderneit
                  Approved By:                    WO
                                  M. B. ShymlocY, Chief
                                                                                              M8,887
                                                                                                Date Signed
                                    Operational Programs Section
                                    Division of Reactor Safety
                                                                SUMMARY
                  Scope:        This routine, announced inspection was conducted in the areas of
                  surveillance program administrative controls and implementation, maintenance
                  program administrative controls and implementation, Technical Specifications
                  applicability to as-built systems, control room activities and plant
                  procedures.        Corrective action for findings described in NRC Inspection
                  Reports 424/85-36, 424/86-60 and 424/86-117 were reviewed.
                  Results:      One violation was identified involving four examples of failure to
                  follow procedures. No deviations were identified.
                  8704290419 870417
                  PDR
                  O        ADOCK 05000424
                                            PDR
                                                                                                                        -.
  . - - - .                -                                .        -- _ -          - ._                -. .. . - .
 
  .. ..              _                                                                    _. _.                                                          -
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!
                                                              REPORT DETAILS
        1.    Persons Contacted
              Licensee Employees
;          #*P. D. Rice, Vice President, Project Engineering
'
            #*G. B. Bockhold, Jr., General Manager, Nuclear Operations
            #*T. Greene, Plant Manager
            #*E. M. Dannemiller II, Technical Assistant to General Manager, Nuclear
                Operations
            #*C. E. Belflower, QA Site Manager
            #*M. A. Griffis, Maintenance Superintendent
            #*J. F. D'Amico, Manager, Nuclear Safety and Compliance
            #*W. C. Gabbard, Senior Regulatory Specialist
            *C. E. Felton, Vogtle Coordinator, Nuclear Operations
            *L. F. Ray, Shift Supervisor
            *P. D. Rushton, Plant Training and Emergency Planning Manager
            #*W. E. Burns, Nuclear Licensing Manager
            #*R. M. Bellamy, Plant Support Manager
            *T. A. Seitz, Corporate Nuclear Office of Quality Assurance
            *J. E. Swartzwelder, Deputy Manager, Operations
            #*H. A. Jaynes, Maintenance Engineering Supervisor
            *A. L. Mosbaugh, Assistant Plant Support Manager
            *M. L. Hobbs, Instrument and Controls Superintendent
,
            *R. E. Conway, Senior Vice President and Project Director
'
            *J. A. Edwards, Senior Regulatory Specialist
            #*W. F. Kitchens, Manager, Operations
            #L. Russell, Operations Procedure Coordinator
            d*C. F. Meyer, Superintendent, Operations
              fA. Caudill, Superintendent, Operations
,
            #H. Varnadoe, Plant Engineering Supervisor
i
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              Other licensee employees contacted included engineers, technicians,
              operators, mechanics, and of fice personnel.
!              NRC Resident Inspectors
            *J. F. Rogge
            *R. J. Schepens
,          +*H. Livermore
j              * Attended exit interview on January 9, 1987
              # Attended exit interview on January 16, 1987
i
i
!
                      . . _ _ , _ _ , _ _ _ . , - , . . . _ _    ._ _ _ _ _ _ . _ _ _ .._      _ _ . _ _ _ _ . _ . _ - . _ __ _ , _ - _ . . , . . _ _ _ , ,
 
                                    J
                                        2
2. Exit Interview
  The inspection scope and findings were summarized on January 9 and 16,
  1987 with those persons indicated in paragraph 1 above.          The
  inspectors described the areas inspected and discussed in detail the
  inspection findings listed below.        No dissenting comments were
  received from the licensee.
  IFI Number    Status    Description / Reference Paragraph
  424/87-01-01  Open      VIOLATION - Failure to follow procedure for
                            1) confirmation of test results for vital battery
                            surveillance (paragraph 7.a.1), 2) QA hold point
                            review and Shift Supervisor approval to work MWO
                            (paragraph 7.b.1), 3) verification by maintenance
                            technicians that drawings and vendor manuals were
                            current revisions (paragraph 8.a), 4) review and
                            initialing operations logs (paragraph 10.b)
  424/87-01-02  Open      IFI - Review of provisions for determining that
                            acceptance criteria are met (paragraphs 7.a.8
                            and 12.11)
  424/87-01-03  Closed    IFI - Followup on adequacy of functional tests
                            and work instructions for maintenance (paragraphs
                            8.c and 12.jj)
  424/87-01-04  Open      IFI - Completion of QA review of DR on mounting
                            of radiation monitors (paragraphs 7.b.1 and
                            12.kk)
  424/87-01-05  Closed    IFI - Determination if temporary modifications
                            negated surveillance tests completed after
                            preoperational tests (paragraphs 9 and 12.11)
  424/87-01-06  Open      IFI - Miscellaneous Findings on Surveillance and
                            Maintenance Program Review (paragraphs 7.b.3 and
                            12.mm)
  424/87-01-07  Closed    IFI - Use of Master Setpoint Document (paragraphs
                            12.nand12.nn)
  424/86-117-01 Closed    IFI - Administrative controls for independent
                            verification of the restoration and testing of
                            plant equipment did not conform to the guidance
                            of NRC IE Notice 84-51 (paragraph 12.c)
  424/86-117-02 Closed    IFI - Venting followup items including high point
                            vents on AFW and procedure revisions for system
                            venting (paragraph 12.d)
 
  - - -                . -    -- _            .                                .
                                                            3
        424/86-117-03 Closed                  IFI - Procedure revisions to include adequate
                                              subcooling margin requirements (paragraph 12.e)
-
        424/86-117-04 Closed                  IFI - Correction of valve identification and
i                                              system lineup discrepancies (paragraph 12.f)
        424/86-117-05 Closed                  IFI - Correction of technical concerns in Unit
:                                            Operating Procedures (paragraph 12.g)
        424/86-117-07 Open                    IFI - Correction of discrepancies on labeling
                                              of valves and equipment (paragraph 12.h)
        424/86-117-09 Open                    IFI - Correction of discrepancies in RVLIS
                                              surveillance procedure and followup on vendor
                                              recommendations (paragraph 12.1)
        424/86-117-10 Closed                  IFI - Procedure revision to include check of
i                                              equipment actuation on Control Room ventilation
                                              start (paragraph 12.j)
        424/86-117-11 Closed                  IFI - Procedure prerequisites are general and not
                                              well understood by operators (paragraph 12.k)
        424/86-117-12 Closed                  IFI    -
                                                        Clarification of cleanliness levels
                                              (paragraph 12.1)
        424/86-117-13 Closed                  IFI - Review of events covered by Abnormal
                                              Operating Procedures (paragraph 12.m)
                                              IFI - Licensee to review annunciator response
*
        424/86-117-14 Closed
j                                              procedures for technical adequacy, walkdown
                                              ARPs and revise ARPs involving annunciators
,                                            on the main control board, as appropriate,
                                              prior to fuel load.      Remaining ARPs to be
                                              reviewed within 90 days (paragraph 12.n)
!
        424/86-117-15 Closed                  IFI - Resolution of ISI test data for CCW pump
                                              (paragraph 12.0)                                                      ,
        424/86-117-16 Closed                  IFI - Resolution of acceptance criteria for
                                              RHR differential pressure on recirc flow
                                              (paragraph 12.p)
        424/86-117-17 Closed                  IFI - Resolution of water hammer in NSCW ESF
                                              chillers (paragraph 12.q)
        424/86-117-18 Closed                  IFI - Review of implementation of the surveil-
                                              lance program administrative controls and
                                              tracking system (paragraph 12.r)
,
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          . _ . - . , - .  . .      . - - - .
                                                  ,-    . - - - . -      _ . -    - . _ - , . . _ _ , . . . . , ,
 
                                                                              .    . _ = = _ .        .
4
                                        4
    424/86-117-19 Closed    IFI - Review of test control and configura-
                            tion control for surveillances performed
                            prior to release to the Operations Department
                            (paragraph 12.s)
    424/86-117-20 Closed    IFI - Revise procedures to clarify use of
                            Staggered Test Basis for determining frequency
                            of test (paragraph 12.t)
    424/86-117-21 Closed    IFI - Review of the justification for the use
                            of pre-operational tests to meet surveillance
                            test requirements (paragraph 12.u)
    424/86-117-22 Closed    IFI - Corrective action to assure control of
4                          twelve hour surveillances (paragraph 12.v)
    424/86-117-23 Open      IFI - Resolution of various technical issues
                            in regard to surveillance procedure adequacy
                            (paragraph 12.w)
    424/86-117-24 Closed    IFI - Licensee to implement operational phase
                            corrective and preventive maintenance program
                            (paragraph 12.x)
    424/86-117-25 Closed    IFI - Resolution of Technical Specification
                            3/4.7.5  wording
                            the Ultimate    Heat in    regparagraph
                                                    Sink  (ard to availability 12.y)                of
    424/86-117-26 Closed    IFI - Corrective action for locking or system
                            lineup verification of boron injection flowpath
<                          valves (paragraph 12.z)
                                                                                                                    '
    424/86-117-27 Open      IFI - Followup on surveillance procedures
                            which have not been identified as complete
,                          on the Technical Specification / procedure
i                          cross reference tracking list and review of
                            completed      cross      reference            tracking              list
-
                            (paragraph 12.aa)
    424/86-117-28 Closed    IFI - Procedure revision for consistent defini-
                            tion of surveillance test completion date and
                            time (paragraph 12.cc)
    424/86-117-29 Closed    IFI - Review of implementation of special
                            triggering mechanisms to assure completion of
                            special  condition surveillances                      (paragraph
                            12.dd)
    424/86-117-30 Closed    IFI - Controls on location of BOP operator
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                            (paragraph 12.ee)
  _  . _ _ _ _ . . _ _____.          ._        _ __        _ _ _ _ _ . . _ .                        _.  . _ _ _ .
 
          _      ___          -                          _      .                              . - _
                                                                                  5
            424/86-117-31 Open                                      IFI - Verification of key control and access
                                                                    to plant equipment by operations staff (para-
                                                                    graph 12.ff)
            424/86-117-32 Closed                                    IFI - Revise TS and procedure for 18 month check
                                                                    of reactor trip breaker UV and shunt coil trip
                                                                    (paragraph 12 99)
            424/86-117-33 Open                                      IFI - Resolution of miscellaneous technical
                                                                    concerns on operating procedures (paragraph
                                                                    12.hh)
            424/86-60-10                                Closed    IFI - Adequacy of shift turnover procedures
                                                                    (paragraphs 10.b and 12.00)
            424/86-96-05                                Closed    IFI - Review of completed surveillance procedures
                                                                    (paragraph 12.bb)
            TMI It e T.C.2 Closed                                  Shift Relief and Turnover (paragraphs 6 and 10.b)
            Although proprietary material was reviewed during the inspection, no
            proprietary material is contained in this report.
        3.  Licensee Action on Previous Enforcement Matters
            This subject was not addressed in the inspection.
        4.  Unresolved Items
]
;            No unresolved items were identified during the inspection.
;
        5.  List of Abbreviations
i            ACCW(S)                Auxiliary Component Cooling Water System
            AFW                    Auxiliary Feedwater System
            A0P                    Abnormal Operating Procedure
            ARP                    Annunciator Response Procedure
            BIT                      Boron Injection Tank
            B0P                    Balance of Plant
            CBCS                    Containment Building Cooling System
            CCP                    Centrifugal Charging Pump
            CCW(S)                  Component Cooling Water System
            CSS                    Containment Spray System
            CVCS                    Chemical and Volume Control System
i'
            DR                      Deficiency Report
            ECCS                    Emergency Core Cooling System (s)
            EDG                    Emergency Diesel Generators
            E0P                      Emergency Operating Procedure
            EQ                      Environmental Qualification
            EQDP                    Environmental Qualification Data Package
            ESF                      Engineered Safety Feature
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  n,~,      . - -  . - - , - , - - - - - - , , - - - ,          ,    _
                                                                              , , - . . , , _ ,      . ,, , . , , - , , - . ,,-_-,-.g- ,-..,,,,-,-,,,,--,.m.-m--g. , , , , - ,,
 
  ..        -  _  -    .-_        _  -                    _.    _          - . . _
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                                            6
:
        F        Degrees Fahrenheit
        FSAR      Final Safety Analysis Report
        HFAS      High Flux at Shutdown
        HVAC      Heating, Ventilation and Air Conditioning
        HX        Heat Exchanger
        IEN      NRC Office of Inspection and Enforcement Notice
        IFI      Inspector Followup Item
        IST      Inservice Test
        LP        Lineup Procedure
        MDAFW(P) Motor Driven Auxiliary Feedwater (Pump)
        MLB      Monitor Light Board
        M0V      Motor Operated Valve
        MSIV      Main Steam Isolation Valve
        MWO      Maintenance Work Order
        MWPG      Maintenance Work Planning Group
        NLO      Non-Licensed Operator
        NPMIS    Nuclear Plant Maintenance Information System
        NRC      Nuclear Regulatory Commission
        NSAC      Nuclear Safety and Compliance Section
        NSCW      Nuclear Service Cooling Water System
        P&ID      Piping and Instrumentation Diagram
        PORV      Power Operated Relief Valve
        PRZR      Reactor Coolant System Pressurizer
        QA        Quality  Assurance
        RCS      Reactor Coolant System
        RER      Request for Engineering Evaluation
        RHR      Residual Heat Removal System
        R0        Reactor Operator
        RVLIS    Reactor Vessel Level Indication System
        RWST      Refueling Water Storage Tank
        SI        Safety Injection
        SIS      Safety Injection System
        SG        Steam Generator
        S0P      System Operating Procedure
        SS        Shift Supervisor
        SSMP      System Status Monitoring Panel
        STS      Standard Technical. Specifications
        TCP      Temporary Change to Procedure
        TDAFW(P) Turbine Driven Auxiliary Feedwater (Pump)
        TS        Technical Specification
        UOP      Unit Operating Procedure
        VCT      Volume Control Tank
    6. Review of TMI Items (TI 2515/65)
        (Closed) TMI Item I.C.2. Shift Relief and Turnover. The inspector                ,
        reviewed the implementation of the requirements of TMI Item I.C.2 and            i
        determined that the licensee had completed the actions necessary to meet        I
        these requirements. This review is documented fi paragraph 10.b of this          i
        report. TMI Item I.C.2 is closed.                                                ;
                                                                                        l
                                                                                        ,
 
                                        7
7. Surveillance Program and Procedure Review (42450B)
  During the inspection ending December 12, 1986, the inspectors had
  determined that the licensee had not yet fully implemented the surveil-
  lance program administrative controls except on a small number of systems
  which had been accepted by the Operations Department. This item had been
  identified as IFI 424/86-117-18. During this inspection, the inspectors
  reviewed the implementation of the surveillance program and a number of
  additional surveillance test packages.      Although several concerns and
  one example of a failure to follow procedure were identified; in general,
  the results of this review indicated that the surveillance program was
  adequately implemented.      The review conducted is documented below.    IFI
  424/86-117-18 is closed,
  a.  Review of Completed Surveillance Packages
        The inspectors reviewed completed active surveillance packages.      The
        surveillance reviews were performed to verify that specific controls
        were established and the surveillance system was working in accord-
        ance with procedure 00404-C, Surveillance Test Program. The
        inspectors reviewed the following:
        -
              System was readied by Operations before performance of the
              surveillance.
        -
              Prerequisites were completed and if not completed, adequate
              justification was provided for prerequisites which were
              marked not applicable.
        -
              All procedural steps were completed or marked appropriately.
        -
              Acceptance criteria were met and completed surveillances
              were included in the surveillance tracking system.
        -    Data packages supported the acceptance criteria.
        -    Task sheets were attached and completed in accordance with
              procedure 00404-C, Surveillance Test Program.
        -
              Appropriate reviews were completed as required.
        The surveillance packages reviewed were:
        SURV. TASK              TITLE                            COMPLETED DATE
        14225-101 Operations Weekly Surveillance Logs                1/14/87
        14235-102 On Site Power Distribution Operability              1/10/87
                    Verification
        14420-101 Solid State Protection System Train A              1/01/87
                    (B) Operability Test
 
                                8
  14420-102 Solid State Protection System Train A          1/10/87
            (B) Operability Test
  14423-106 Source Range NIS Analog Channel                1/14/87
            Operational Test
  14805-101 Residual Heat Removal Pump and Check            1/09/87
            Valve Inservice Test
  14811-101 Boric Acid Trant.fer Pumps and Discharge        1/08/87
            Check Valves Ir. service Test
  14850-102 Cold Shutdown Valve Inservice Test              1/08/87
  14890-1    Diesel Generctor Operability Test          Not recorded
  14895-101 ECCS Check Valve Refueling Inservice            9/27/86
  14896-101 ECCS Check Valve Cold Shutdown Inservice        9/22/86
  14980-111 Diesel Generator Operability Test              1/09/87
  14980-1    Diesel Generator Test                      Not recorded
            (Fuel Oil Sampling for Water)
  24342-1    Pressurizer Level Control F-121            Not recorded
            Channel Calibration
  24519-101 R. C. Pressure (Wide Range) Protection I      10/21/86
            P-405 ACOT and Channel Calibration
  24519-103  R. C. Pressure (Wide Range) Protection I      1/07/87
            P-405 ACOT and Channel Calibration
  24597-1    Containment Cooling Units 5, 6,            Not recorded
            7 & 8 - Condensate Detection L-17094
  24626-101 Containment Vent Effluent Air Particulate      1/08/87
            Monitor 1RE-2565A
  24681-101 Meteorological Station 10M Wind Direction      10/30/86
            Channel Calibration
  24684-C  Meteorological Station 60M Wind Speed        Not recorded
            Channel Calibration
  24688-101 Meteorological Station 10M Ambient and          9/12/86
            and 10-60M Delta Temperature Channel
            Calibration
  24737-101 Time History Accelerograph AXT-19903          12/04/86
  24737-102 Time History Accelerograph AXT-19903          12/04/86
  24739-101 Peak Acceleration AXR-19910                    1/02/87
  24806-101 Refueling Water Storage Tank Level L-990        1/15/86
            ACOT and Channel Calibration
  24840-101 Containment Pressure High Transmitters          1/02/87
            RTT Sensors PT-934
  28210-101 Main Steam Line Safety Valve Test              4/86
  thru 120
  28211-101 RHR Suction Relief Valve Test                  2/20/86
  28211-102 RHR Suction Relief Valve Test                  1/09/86
  28215-101 Safety Relief Valve IST 1 PSV-8010A            3/04/86
  28215-102 Safety Relief Valve IST 1 PSV-80108            2/27/86
  28215-103 Safety Relief Valve IST 1 PSV-8010C            3/05/86
  28290-101 Containment Spray Nozzle Flow Test                N/A
  28711-101 Diesel Fuel Oil Storage Tank Cleaning          9/08/85
  28711-102 Diesel Fuel Oil Storage Tank Cleaning          9/09/85
  28712-101 Diesel Fuel Oil Piping Pressure Test            3/23/84
  28820-C    Battery Charger Load Test                  Not recorded
l
                .                              .    _-
 
!                                9
l
  28905-C    Motor Operated Valve Thermal Overload          Not recorded
              and Bypass 18 Month Test
  28910-102 Class 1E 18 Mo. Battery Inspection                  12/08/86
              and Maintenance
  28912-102 Class IE Quarterly Battery Inspection                1/02/87
              and Maintenance
  54708-101 Containment Isolation and Containment              10/14/86
              Ventilation Isolation - Manual
              Initiation
  54820-101 Train "A" SI Pump Response Time Test                9/28/86
  54822-101 Train "B" SI Pump Response Time Test                9/28/86
  54825-101 Train "B" CCWP Response Time Test                    9/25/86
  The following items were identified during the inspection:
  (1) On procedures 28910-101,102,103, and 104, Class 1E 18-Month
      Battery Inspection and Maintenance, the inspector noted that
      the recorded data indicated that intercell resistance on
      rack to rack and tier to tier jumpers exceeded the Technical
      Specification requirement of 50 X 10-6 ohms. The Surveillance
      Task Sheets (STS), which listed the TS requirement as part of
      the acceptance criteria, had in each case been signed off as
      meeting acceptance criteria. The licensee was questioned about
      the signoffs.    The licensee stated that the engineer had signed
      off the step because the excess resistance was attributed to the
      cable length between the rack to rack and tier to tier jumpers.
      The inspector requested the evaluation of the cable resistance
      value. The licensee stated that an evaluation had not been
      performed. Since the cable resistance had not been determined
      and subtracted from the total resistance, the value of the cell
      to cell resistance was not known.
      Procedure 00404-C, Surveillance Test Program, Step 4.5.4.1,
      requires an independent reviewer to confirm that test results
      satisfy acceptance criteria.      The reviewer signed the STS
      indicating that the acceptance criteria were met.
      10 CFR 50, Appendix B, Criterion V, requires that activities
      affecting quality be accomplished in accordance with documented
      instructions, procedures, or drawings.      This requirement is
      implemented by Section 17.2, Operations Quality Assurance
      Program, of the FSAR. The failure to follow procedure 00404-C
      to confirm that test results met the acceptance criteria for
      the rack to rack and tier to tier jumpers on the vital batteries
      is identified as an example of violation 424/87-01-01.
                                                                          --
 
          . . .-                                    .      -
                                                  10
                    (2) On data sheet 2 of procedure 14423-106, Source Range NIS Analog
                        Channel Operational Test, performed on January 14, 1987, the
                        normal reading taken from the Neutron Level Drawer Meter
                        exceeded the upper limit values given on the data sheet. A
                        note on the data sheet directs the test performer to add the
                        pre-test indication on meter NI-101 to the upper limit values
                        for specific switch positions given on the data sheet.      This
                        would raise the upper limit.      Nowhere on the- data sheet,
                        however, is the reading on NI-101 documented.      This makes the
                        true upper limit unclear and makes it appear the procedure is
                        unsatisfactory when in fact it is satisfactory.      The licensee
                        agreed to change the procedure to include the reading on NI-101
                        on the data sheets.
                        No violations or deviations were identified.
                    (3) On procedure 14423-106, the High Flux at Shutdown (HFAS) set-
                        point was not checked. A note on the proceddre stated that the
  i                      HFAS setpoint would be set after two fuel bundles were loaded
t
                        in the reactor vessel.    The inspector questioned the licensee
                        on the triggering mechanism for establishirg the HFAS setpoint.
                        The licensee stated it was part of startup test procedure
                        #1-500-01, Initial Fuel Load Test Sequence.      The inspector
                        verified this and had no further comments.
1                        No violations or deviations were identified.
                    (4) On procedure 14895, ECCS Check Valve Refueling Inservice Test,
                        completed September 17, 1986, required flow rates which were
                        marked "LATER" had been changed to specific values without a
                        proper procedure revision.    This item had also been identified
                        by the licensee's QA audits and was being followed by QA.
                        No violations or deviations were identified.
                    (5) Procedure 14811, Boric Acid Transfer Pumps and Discharge Check
                        Valves Inservice Test, had been identified as not acceptable by
                        the IST group but NSAC was showing the surveillance to be
                        acceptable. This item was also identified in a QA audit and
                        was being followed by QA.
                        No violations or deviations were identified.
'
                    (6) The inspector questioned the absence of dates on a number of
                        Task Sheets attached to active surveillances. The licensee
                        provided verification that the problem was corrected and the
!                        surveillance tracking system was working as delineated in
                        procedure 00404-C, Surveillance Test Program.      The inspector
                        had no further questions.
                        No violations or deviations were identified.
l
    .- -
        .        ._ --                                                                    . _ _ _
 
                                  11
  (7) Surveillance procedure 14896-101, Revision 0, which was
        completed and reviewed by the licensee on January 12, 1987,
        was not revised in accordance with the outstanding TCP, No.
        14896-187-1.    The flow rate criterion on Data Sheet 1, for
        the emergency core cooling system (ECCS) check valve cold
        shutdown inservice test, was not changed from 3,000 gpm to
        3,788 gpm, as required by this TCP nor was another TCP
        written to change the flow rate criterion.
        No violations or deviations were identified.
  (8) The inspectors noted that items 1, 4, 5, and 7 raised questions
        about the reviews required to assure that acceptance criteria
        were met.  The review of the licensee's procedures to assure
        that adequate administrative controls exist for review of
        acceptance criteria and determination that the acceptance
        criteria are met is identified as inspector followup item
        424/87-01-02.
        No violations or deviations were identified.
b. Field Review of Surveillance Instructions
  The inspectors performed a field review of surveillance procedures
  by observation of surveillances in progress or by walkdown of
  procedures in the field. The following concerns were identified:
  (1) The inspector observed chemistry technicians dismantling a
        radiation monitor identified as 1RE-12444C. When the inspector
        asked to review the MWO under which the technicians were
        performing the work, they replied that they were dismantling
        the monitor via surveillance procedure 34223-C, Rev. 1, Channel
        Calibration of the Gaseous Effluent Monitors.      The inspector
        reviewed the procedure and associated attachments to determine
        if the procedure was being followed properly. The inspector
        determined that the technicians had not obtained the signature
        of the shift supervisor prior to performing work or the
        signature for review of QC holdpoints.
        The inspector noted that, step 5.1 of procedure 34223-C,
        Prerequisites, states, " Ensure a Quality Control (QC) represent-
        ative has signed the checklist indicating a QC review of the
        procedure for hold points. If hold points are indicated, notify
        QC prior to starting." Additionally, step 5.2 states, " Notify
        the Operations Shift Supervisor, or his designee, of the work
        to be performed and obtain his signature authorization."
        Neither of these signatures had been obtained. When the lead
        technician was questioned on these steps, the technician stated
        that verbal approval had been obtained from the Shift Supervisor
        to perform the work.
                                                                          - .
 
                            12
  10 CFR 50, Appendix B, Criterion V, requires, in part, that
  activities affecting quality be accomplished in accordance with
  documented procedures.      VEGP FSAR, section 17.2, Operations
  Quality Assurance Program, also requires that activities
  affecting quality be accomplished in accordance with documented
  procedures. The activities described above were not accom-
  plished in accordance with procedure 34223-C in that the
  signature of a QC representative had not been obtained for the
  hold point review, indicating that the review was not accom-
  plished, and the signature of the Shift Supervisor had not been
  obtained to authorize performance of the work. The inspector
  later verified that the Shift Supervisor had provided verbal
  approval. The failure to follow procedure 34223-C is identified
  as an example of violation 424/87-01-01.
  During the review, the inspector questioned whether or not the
  radiation monitor was seismically and/or environmentally quali-
  fied equipment and if provisions existed in the procedure to
  maintain these qualifications.    The inspector determined that
  Vogtle administrative procedure 00350-C, required that work
  performed on seismically or environmentally qualified equipment
  be done under the control of an MWO.    The inspector questioned
  the use of surveillance procedures to control removal and
  restoration of seismic and/or environmentally qualified
  equipment.    Resolution of this issue was identified as
  IFI 424/87-01-04.
  During subsequent inspections, the inspector was informed by
  the licensee that radiation monitor 1RE-12444C was seismically
  qualified and the technicians were not taking any special
  precautions to maintain the equipment qualification.        The
  licensee generated Deficiency Reports (DRs) 1-87-0203, on the
  disassembly of monitor RE-12444-C; and,1-82-0204, on detector
  removal and reinstallation for monitors RE-0020A and RE-00208.
  A Request for Engineering Review (RER) was written for problem
  resolution and MW0s were written to cover the remaining work.
  Regarding the concern of whether or not the EQ of the monitors
  was compromised by the routine disassembly and reassembly, the
  inspector reviewed the system description 9002-DRMS-002 to
  ascertain what is required to maintain EQ. The system descrip-
  tion indicates that no specific removal or replacement proce-
  dures are required. Nomal safety precautions and general shop
  techniques were adequate for this task. The portion of the
  monitor that could degrade the EQ of the monitor is never
  opened for these routine calibrations. Since these calibration
  activitics do not directly affect the seismically sensitive
  areas of the equipment, the original procedure was not clearly
  in violation of administrative procedure 00350-C, which requires
  MW0s to be written for work performed on seismic or environ-
  mentally qualified instrumentation.      However, the licensee
i
.
 
                            13
,
  stated that all procedures that affect radiation monitors that
  have seismic and/or environmental concerns are being reviewed
  and revised as deemed appropriate.
  Procedure 39350-C, Initial Calibration of Gaseous Process
  Monitors, was written to require an MWO for the removal or
  reinstallation of any components on radiation monitor RE-2562.
  This system is seismically qualified per FSAR Table 11.5.2-1.
  Other calibration procedures will be revised similarly in the
  near future to cover all of the monitors in this table.    The
  inspector was concerned that simply placing this caution in the
  calibration procedure would not guarantee that a technician
  would not start with the procedure for the removal of the
  detector; then use the procedure for the calibration and find
  out that an MWO was required to implement precautions so as not
  to jeopardize the EQ of the equipment.
  The inspector then reviewed the licensees EQ program in order to
  determine whether or not it provided adequate assurance that EQ
  is maintained. The inspector interviewed personnel from the
  Maintenance and Engineering departments as well as the Work
  Planning Group. The EQ program is implemented under procedure
  20009-C, Rev. 1.    The inspector found the procedure to be
  satisfactory.    Any equipment that must be EQ had an associated
  package of information called the Environmental Qualification
  Data Package (EQDP).    These EQDP's were numbered and controlled
'
  documents. Each package was divided into nine parts. The parts
  are:
  (a) EQDP equipment identification list
  (b) Environmental summary sheet
  (c) NUREG 0588 Checklist
  (d) Master listing - seismic
  (e) Seismic qualification and recorder data sheets
  (f) Calculations
  (g) Maintenance / replacement information
  (h) EQ design change signoff form
  (1) Miscellaneous information
  The inspector reviewed four EQDP's: Relief Valves; Radiation
  Monitors; Limitorque Valves; and Rosemount Transmitters. The
  inspector determined that the packages were comprehensive and
  found the information easily accessible.
                                                                    . .
 
                                                                                        _
                                    14
            The inspector reviewed three procedures to determine if the EQDP
            information had been implemented into these procedures. These
            procedures were: 22402-C, Rosemount Transmitter Removal and
'          Reinstallation; 28211-C, Relief Valve Test Procedure; and
            25240-C, General Bolted Flange Torquing Procedure. All of
            these procedures compared favorably with their respective EQDP.
            The inspector reviewed the licensee's Nuclear Plant Maintenance
            Information System (NPMIS) to observe how EQ equipment was
            flagged to prevent compromise of the EQ requirements. All
            equipment had a safety classification that was reviewed whenever
            an MWO was written against the equipment. In accordance with
            Regulatory Guide 1.60, Design Response Spectra for Seismic
            Design of Nuclear Power Plants, the licensee uses a project
            classification matrix (Table C13-1 from the VEGP Project
            Reference Manual) that delineates what safety classification
            code is used to designate safety related equipment and whether
            the equipment is EQ or not. All of the equipment with a safety
            classification that indicates either seismic or environmental
            qualification must be reviewed by QC. In addition, the Work
            Planning Group engineer and the Environmental Qualification
            Group engineer must both sign off on any EQ equipment that
            all proper reviews have been performed, the EQDP had been
            referenced, and the installation / replacement documents are
            accepta,ble.
            Finally, the inspector reviewed constructica documents to
            determine if the equipment had been installed correctly.        The
            most important aspect of the seismic qualification of the
            radiation monitors is the e, led upon which they are mounted
            during normal operation. All seismic modeling of the equipment
            was performed assuming that the sled was instaited the way that
            it was designed. The inspu, tor found that probNms had occurred
            with the installation of the sled.        These are detailed in
            Readiness Review finding M-13.    Correspondence from F. B. Marsh
            of Bechtel Western Power Division to J. A. Bailey of Southern
            Company Services discussed the specifics and stated that the
            deficiency was not reportable under the rules of 10CFR 50.55(e).
            A Deviation Report (DR) CD-9158 was generated on December 19,
            1987 to address and disposition the discrepant condition. The
            DR, which details the evaluation that determined the condition
            was ratisfactory, appeared adequate to the inspector. The DR
            had not been sent to QC for approval.
            Overall, the inspector found the licensee's EQ program to be
            satisfactory and in some aspects, exemplary. IFI 424/87-01-03
            will remain open pending review of the revisions of all radia-
            tion monitor procedures that affect those monitors listed in
            FSAR Table 11.5.2-1, and the closing out of CD-9158.
,
  __ _ _
          e  -      .- ,  -
                                                .  ,    _ _ . .      -r._    _ , , -
 
                                  15
    (2) Sections of procedure 24519-1, Rev. 2, Reactor Coolant Pressure
        (Wide Range) Protection I 1P-405 Analog Channel Operational
        Test and Channel Calibration, which apply to the analog channel
        operational test using the manual system, were observed. The
        operational test failed.    As-found readings fell outside the
        expected band.    Section 4.20, Summing Amplifier Card Field
        Calibration, of procedure 23300-C, Rev.1, Field Calibration
        Procedure, was performed and the appropriate sections of
        procedure 24519-1 were repeated.
        No violations or deviations were identified.
    (3) An inspection of portions of the field performance of procedure
        24634-1, CR Air Intake Process Radio Gas Monitor Analog Channel
        Operational Test & Channel Calibration, and procedure 24623-1,
        Containment Low Range Area Monitor Analog Channel Operation Test
        and Channel Calibration, was performed. The inspector had no
        comments.
        The inspector reviewed procedure 24183-1, Rev.1 Fuel Handling
        Building Effluent Radiogas Monitor, ARX-2533. The inspector
        noted an inconsistency betwcen the procedure and panel in that
        labeling for a connector was IAJ3 versus J3 on the panel. An
        LED which was unmarked on the remote / control box, did not light
        as indicated by the procedure.      No LED was provided on unit
        IRT-1005 as indicated in step 4.1.3.6.b.
        The inspector reviewed procedure 24756-1, Rev. 2, Steam
        Generator Level (Narrow Range) Protection Channel II, IL-553.
        The inspector noted that the location of equipment was
        determined using an out of date drawing due to the time required
        to pull new drawings.
        After this walkdown, the inspector encouraged the licensee to
        evaluate the distribution of drawings from Document Control.
        Requests for drawings by the inspector to the technicians, who
        were performing work in the plant, typically resulted in a
        50-minute wait in Document Control. The inspector was concerned
        that the opportunity to use obsolete information would be more
        likely if the people who needed the information consistently
        found obtaining new drawings difficult. Prompt distribution can
        greatly enhance compliance with drawing and document control
,
        requirements. During two surveillances, which were witnessed by
  I
        the inspector, technicians spent approximately 3 hours to find
        equipment that was either erroneously listed in the procedure
        (e.g., local indication for radiation area monitor) or moved in
        a modification (e.g., a steam generator level transmitter). The
'
        inspector asked the technicians in both instances, after a
        twenty-minute search, if it would be more expedient to check
        the drawings.    In both cases, the technicians thought the
        equipment would be located any moment and the time spent to
        obtain a drawing was unnecessary.
 
                                      16
  .
i
          '
            The inspector reviewed procedure 24634-1, Rer.1, Control Room
    i
            Air Intake (1RE-12116) Process Radio Gas Monitor. During the
            surveillance, remote control test box was removed. This item
            was identified to the licensee as part of IFI 424/87-01-06.
            The equipment was later determined to be used only for testing
      ,1    and did not affect the operation of the safety related monitor;
        '
            however, the Readout Control Box (RCB) was removed and used to
            perform calibrations on other monitors without any tracking,
            i.e., no MWO was issued. Deficiency Report 1-87-161 was written
            to document this occurrence and engineering report 87-0036
            was generated to perform an evaluation of the incident. The
            engineering report determined that the RCB is interchangeable on
            the monitors and there is no problem with using them in this
            manner. Still, the removal of the RCB does require a MW0 and
            the licensee showed the inspector a procedure that cautioned
            personnel performing this action with a RCB to generate a MW0.
            The procedure was a draft copy. Until the procedure is revised,
            this part of IFI 424/87-01-06 will remain open.
            The inspector also noted during plant walkdowns that an ambient
            temperature difference of 8 to 10 existed between the Control
            Building normal air conditioning room temperature gauge and the
            ESF air conditioning room temperature gauge,1-1539-TIC-13150
            and 1-TSH-13151.    The inspector requested the licensee to
            investigate if the instruments were operable. In a letter dated
            January 12, 1987, the licensee stated that an investigation had
            revealed that the instruments served separate functions, i.e.,
            monitored different rooms.      However, as a result of this
            finding, the inspector later determined that the licensee had
            written maintenance work order (MW0) 18700997 to correct the
            discrepancy between these instruments, since both instruments
            measured the same ambient room temperature. This is considered
            acceptable; however, the action did not correspond to the
            January 12, 1987 response. No followup is considered necessary
            for this item.
            Other concerns involving emergency lighting which was out in
            a stairwell, the failure of personnel to close fire doors
            and a question on the wire bend radius of cable at location
            A-1813-M3-027 were promptly answered or corrected by the
            licensee. The wire bend radius was determined to be within
            specification.    These concerns had also been identified as
            part of IFI 424/87-01-06. These concerns are considered closed.
            No violaticns or deviations were identified.
                                                                              !
                                                                            1
 
                                                                                  -      - _ - -
            -    .
                                              17
  8. Maintenance Program and Procedure Review (42451B, 357438)
    During previous inspections, reviews had been conducted of the administra-
    tive controls for plant maintenance, the technical adequacy of maintenance
    procedures and the implementation of the maintenance program. The review
    included an assessment of the corrective maintenance program; an assess-
    ment of the preventative maintenance program; a review of equipment
    control including the removal and restoration of equipment, equipment
    status tracking and functional testing requirements; verification of
    control of special processes, housekeeping and system cleanliness; and,
    document review and field verification of the implementation of the
    maintenance program.      The program had not been fully implemented under
    the operational quality assurance program at that time. Followup on the
    implementation of the program was identified as IFI 424/86-117-24.
    During this inspection, the inspectors reviewed procedure 00350-C,
    Maintenance Program, Rev. 5, dated December 3,1986. This procedure
    was the administrative procedure which governed maintenance activities
    during operation.      Additionally, the inspectors witnessed several
    maintenance activities in progress including the processing of mainte-
    nance work orders (MWO) in accordance with the requirements of 00350-C.
    The inspectors also reviewed completed work packages that were accom-
    plished under the operational QA program. The inspectors verified that
    the licensee had implemented its planned maintenance program. Based on
    the review, IFI 424/86-117-24 is closed.
    The field review consisted of observing 14 MW0s which addressed various
    aspects of plant maintenance. The inspector noted that MW0's, with one
    exception, were appropriately filled out and all MW0s reviewed addressed
    such areas as QC hold points and proper initial review by other depart-
    ments.    The inspector noted a number of cross outs which detracted from
    legibility. The inspector identified the following items:
    a.    The inspector determined that maintenance personnel had not verified
          that approved drawings, procedures and vendor manuals included in
          MW0s in use in the field were the current revision.                Procedures
          00103-C, Document Distribution and Control, and 00101-C, Drawing
          Control, required that drawings, procedures and vendor manuals be
          verified as current every seven days. These procedures also required
          that any documents which affected the revision to be noted on the
          affected working copy.          In addition, procedure 20050-C, MWPG Work
          Order Processing, requires that working copy documents be verified
          current prior to their issuance to the field; and, procedure 20407-C,
          Maintenance Conduct of Operations, states that it is the responsi-
          bility of the user to ensure that only current, approved working copy
          documents are used.          The maintenance personnel observed by the
          inspector had failed to perform the seven day review for drawings on
          MW0s 18700429,18700453 and 18624440 and for vendor manuals on MW0
          18624165.
l
i
!                        --
                                  . - .        _ _ _      _ ,_-        - - _ .    _ .._ - _ ._
 
          .                                    ._.
  l'
                                            18
            10 CFR 50, Appendix B, Criterion V, requires that activities
            affecting quality be accomplished in accordance with documented
            instructions, procedures or drawings.        The failure to follow
            procedures 00101-C, 00103-C and 20407-C is identified as an
            example of violation 424/87-01-01.
            During the week of January 12, 1987, the inspector determined that
            the drawings and vendor manuals included in the MW0s reviewed were
            the latest revisions. The Maintenance Department issued a memorandum
            to all maintenance department supervisors and foremen requiring them
            to review all work packages in their possession to assure that all
            working copy documents are the latest revision.
            Deficiency Report (DR) 1-87-0185 was written by the licensee to
            document the finding. The licensee stated that the Quality Assurance
            Department will perform random audits of the maintenance program.
            Additionally, the licensee will consider incorporating into the
,          appropriate Maintenance Department procedure the requirement that
            foremen and supervisors verify weekly that working copy documents are
'
            the latest revision.
      b.  Paragraphs 4.1.2.c through e of 00350-C, stated that MW0s were not
            required for certain activities which do not involve safety-related,
            seismic or environmentally qualified equipment. The inspector
            interviewed members of the Maintenance Work Planning Group concerning
            the process used in making this determination and documentation of
            the review. The MWPG stated that equipment addressed by paragraphs
            c, d, and e of 00350-C was contained in the Nuclear Plant Management
            Information System (NPMIS) which delineates all of the pertinent
            information on the safety-related, seismic and environmental qualifi-
            cation classifications of equipment. If the foreman is in doubt, an
            MWO is submitted which will be reviewed for procedural applicability.
            Additionally, paragraph d, which addresses labeling, was being
            performed under operations procedure 10016-C, Equipment Labeling
            Guidelines.
            No violations or deviations were identified.
      c.  The inspector noted that MW0 18624097 did not have a functional
            test assigned in block 32 as required by procedure 00350-C. During
            review of other maintenance work orders the inspectors noted that
            MW0s appeared weak in the area of functional testing. This item is
            of particular concern in light of the number of findings identified
            by the Quality Assurance Department related to the failure to assign
            functional testing to MW0s. These findings are documented in audit
            reports No. OP15/TP02-86/20, #045-II, July 12 thru August 5,1986;
            No. OP15-86/45, November 17 thru December 5, 1986; and No. OP15-87/03,
            January 6 thru 11,1987.      The inspectors identified this item as IFI
            424/87-01-03.
i
1
    -            _    ,                        --  -  ,            .-.    - . - - , . - - . .
 
                                                              _ _ _ _                      _    _ __    _      _ _ _ _ _ _ _ _ _ _ _ _
  .
                                                19
            The inspector reviewed the corrective action for this item during
            the week of January 12, 1987. In response to the item, the licensee
            had issued procedure 20051-C, Maintenance Work Order Functional
            Tests, to provide guidelines for proper functional test assignments.
            The licensee also plans to revise the MWO processing procedure to
            assign the functional testing requirements after the work has been
            accomplished. In addition, the licensee established a review team
            assigned the task of assessing the quality of the MW0s being issued
            by the Maintenance Work Planning Group and returning to the MWPG
            those MW0s lacking sufficient direction or adequate functional
            testing. The work conducted under MWO 18624097 was complete and
            awaiting the assignment of the appropriate functional testing. The
            inspector determined that the licensee had implemented procedures
            which provided adequate direction and review to ensure that MWO
            instructions are sufficiently detailed and are assigned the appropri-
            ate functional testing.        IFI 424/87-01-03 is closed. The IFI number
            will remain assigned to the item to allow tracking of the finding.
            No violations or deviations were identified.
    9. Review of Aaministrative Controls for Temporary Modifications (424518)
      During the inspection, the inspector noted that there were numerous
      temporary modifications installed in the plant. The inspectors determined
      that the licensee had a mechanism to review temporary modifications and
      their effect on system operability once the system was formally turned
      over to operations. However, the licensee was performing surveillances on
      systems that had temporary modifications installed.                                Therefore, the
      validity of the surveillance could be affected for surveillance tests
      completed after preoperational testing and prior to establishing configu-
      ration control by Operations.          This concern was identified as Inspector
      Followup Item 424/87-01-05.
      During the week of January 12, 1987, the inspection team conducted a
      review of the licensee's procedures.          Procedure 00350-C, Maintenance
      Program, addressed the removal of temporary modifications to ensure
      that proper documentation was provided and that the functional testing,
      including assessment of its impact on surveillances, was performed.
      Procedure 00307-C, Temporary Modifications, addressed the methods utilized
      to ensure that temporary modifications are properly identified, docu-
,
      mented, controlled and evaluated.
      While under the jurisdiction of the Start Up Manual, Procedures SUM-10,
      Temporary Modification Control, and SUM-22, Maintenance Work Orders,
,
      adequately addressed the subject of temporary modifications including the
'
      assessment of its impact on surveillance tests.
        .-                            _ --                .          _ _ - - . . . - - -                . . .                        -
 
                                                                    __  _ _.  __ .
                                          20
    The aforementioned maintenance and temporary modification procedures
    ensure that work / temporary modifications performed on a system will verify
    that surveillances are active and document that components / systems are
    functioning properly and capable of performing their intended safety
    function. Temporary modifications which were in place during pre-
    operational testing which was utilized to satisfy surveillance require-
    ments were adequately addressed by the constraints imposed by Section 4.4
    of procedure 00404-C, Surveillance Test Program.          Under the pre-
    operational test program, the test supervisor was responsible for
    reviewing the temporary modification log for items which may preclude
    completion of the test or invalidate the test results upon completion.
    Specifically, paragraph 4.4.6.1 required that " documentation for the
    completed procedure or work activity shall be carefully reviewed to ensure
    that satisfaction of the surveillance requirements is clearly documented
    and that the conditions during the period of the test are the same as
    would be experienced during the operational phase surveillance test
    procedure. Discrepancies shall be noted in the comments section of the
    documentation check list."
    As a further area of discussion, it should be noted that test / surveil-
    lance procedures contain steps which require the introduction of
    modifications which place the system / component into a configuration such
    that the test / surveillance procedure attains the required objective. The
    introduction of such modifications is reviewed with the development of the
    procedure. The inspector feels that all concerns regarding temporary
    modifications have been addressed and therefore inspector followup item
    424/87-01-05 is closed. The inspector followup item number will remain
    assigned to the item to allow tracking of the item.
    No violations or deviations were identified.
10. Control Room Activities Review (424508)
    a.    The inspector reviewed control room administrative procedures and
          verified documentation maintained in the control room to assure
          the documentation was being maintained in accordance with procedures.
          Documents reviewed were:
          Reactor Operator & Shift Supervisor Logs
          LC0 Log                                                                  i
                                                                                    !
          Standing Orders
          Jumper & Lifted Wire Clearance Log
          Operations Reading Book
          Disabled Aanunciator Log
          The inspector also checked 12 hour Technical Specification valve
          position verification requirements applicable to the ECCS subsystems.    ,
          These verifications were being performed properly. The inspector had      l
          no comments.
                                                                                    l
                                                                                    1
                                                                                    !
 
                                                                                  - - _ _
                                                                                          l
                                                                                          ,
                                    21
      It was noted previously that numerous administrative controls
      established for the management of those plant and control room
      activities conducted under the direction of licensed operatcrs
      were not implemented.    These findings were documented in NRC
      Inspection Report 424/86-117.    However, during this inspection
      the inspectors noted a marked improvement in this area. The
      administrative controls were implemented and review of record,
      logs and checklists indicated thorough input and current status.
      The inspector had no further comments in this area.
      No violations or deviations were identified.
    b. (Closed)    Inspector Followup Item 424/86-60-10 (TMI Action Item
      I.C.2). Shift Relief and Turnover. The inspector reviewed procedure
      10004-C, Shift Relief, Rev. 3, and the shift turnover process to
      ensure adequate controls were in place to provide for a complete
      shift turncver and the meeting of TMI action item I.C.2 requirements.
      The inspector's review included observation of control room activity,
      review of logkeeping and log review, and a review of all procedures
      governing shift turnover.
      The inspector noted that adequate controls appeared to be in place
      to maintain access to the control room in an orderly manner. The
      operators also appeared to display a professional manner and surveil-
      lance of the control boards appeared to be adequate.
      The Reactor Operator (RO), Balance Of Plant (80P), and Non-Licensed
      Operators (NLO) utilize rounds sheets to log and record plant
      parameters. The inspector reviewed the rounds sheets of the R0, B0P,
      and the NL0s. These sheets appeared to be properly completed and to
      adequately meet the part of TMI action item I.C.2 which requires that
      the licensee provide assurance that plant parameters were within
      allowable limits. The rounds sheets of the NL0s are reviewed by the
      R0, B0P, and Shift Supervisor (SS) to ensure knowledge of plant
      parameters not indicated in the control room. The rounds sheets of
      the R0 and the B0P are also reviewed by the SS. The inspector
      determined that these reviews appeared to be taking place and that
      the operators in the control room were cognizant of the status of the
      plant.
      While reviewing the narrative logs, the inspector noted on
      January 15, 1987, that the SS log had no initialed review by
      the day shift SS for the previous night's log entries.        When
      questioned as to the apparent lack of a review, the SS told the
      inspector that he did not review the previous night's logs and that
      he was not required to review his own logs by procedure because
      the verbal turnover from the off-going SS was adequate. The
      inspector showed the SS where procedure 10004-C, Revision 3, Shift
      Relief, required the on-coming operator to review and initial the
._.                                            -.                          - - . ,
 
                                        22
          narrative logs completed since the last shift worked by that operator
          or for the preceding 5 days, whichever is less. The SS stated that
          he was referring to direction received from procedure 10001-C,
          Revision 3, Logkeeping, however, when he showed the procedure to
          the inspector he noted that he was incorrect and that he was also
          required to review his narrative logs by this procedure.
        The failure to review and initial the Shif t Supervisor narrative
          logs is a failure to follow approved plant procedures in accordance
        with 10 CFR 50, Appendix B, Criterion V. This item is identified as
          an example of violation 424/87-01-01.
          During the review of procedure 10004-C the inspector identified a
          discrepancy between the procedure and the On Shift Operations
          Supervisor (0505), R0, and B0P checklists. These checklists are
          provided in procedures 11870-C,11872-C, and 11869-C, respectively.
          The procedures require each on-coming OSOS, R0, and 80P to review the
          following logs in addition to the rounds sheets and narrative logs:
          Special Conditions Surveillance Log, Clearance Log, Lif ted Wire Log,
          and Temporary Modifications Log. The OSOS, R0, and 80P checklists
        were missing the appropriate check blocks for each of the above logs.
          This was brought to the attention of the licensee and the checkshetts
        were modified to reflect the intent of the procedure.
          The TMI action item also required implementation of a system to
          evaluate the effectiveness of the shift relief turnover procedure.
          Step 3.12 of procedure 10004-C states that the 050S shall make an
          evaluation of shift relief and turnover at least semiannually.        The
          results of this evaluation were to be forwarded to the Operations
        Manager for disposition. Although the statement contained in the
          licensee's procedure directed the Operations Superintendent to
          perform an evaluation, the procedure provided no instructions on how
          the evaluation was to be performed. The inspector discussed this
          item with the licensee and the licensee issued a revision to the
          Non-Technical Specification Activities sheet.      Prior to the revision
          the sheet merely restated the step in the procedure and provided no
          further direction.    The revision provides direction to the OSOS by
          listing several specific items to be addressed during the evaluation.
          This revision appeared to satisfy the final requirement of the TMI
          action item. TMI Action Item I.C.2 and IFI 424/86-60-10 are closed.
11. Inspection and Enforcement Notice Review (92701)
    The inspector reviewed the licensee's response to IE Notice 86-61,
    Failure of Auxiliary Feedwater Manual Isolation Valve.        The inspector    l
    discussed the notice with the licensee and determined that the preventive
    maintenance requirements for manual isolation valves were determined on a
    case-by-case basis during the formulation of the PM program. Based or
    this review this item is closed.
 
                                                                          _ . - _ _ - _ - _ _ - _ _ _ _ _ _
                                        23
12. Inspector Followup Items (92701)
    a.  (Closed) Inspector Followup Item 424/85-36-02.      Evaluation of
        Operational Event Reports. The IFI involved a concern that the
        licensee tended to address items programmatically rather than
        technically. The applicant had committed to reopen and reevaluate IE
        Information Notice 85-23 and reevaluate preoperational testing
        associated with differential pressure transmitters. The inspector
        reviewed a March 14, 1986 memorandum from Ron Bone, GPC to Bob Lide,
        GPC which provided the technical evaluation of the preoperational and
        startup testing of the differential pressure transmitters and an
        evaluation of IE Information Notice 85-23. The inspector did not
        identify any concerns with the licensee's disposition of the evalua-
        tion findings.    In addition, the inspector reviewed five additional
        IE Information Notice evaluations and identified no concerns. This
        item is considered closed.
    b.  (Closed) Inspector Followup Item 424/85-36-03. Performance of Safety
        Evaluations and Duties and Responsibilities of Plant Review Board.
        The IFI concerned the lack of procedural requirements to submit
        safety evaluations for unreviewed safety questions and Technical
        Specification changec to the Plant Review Board for review. The
        inspector reviewed a revised copy of 00051-C, Review and Approval of
        Procedures, which added this requirement. This item is closed.
    c.  (Closed) Inspector Followup Item 424/86-117-01.        Independent
        Verification. The inspector reviewed procedure 00308-C and deter-
        mined that the licensee had met the NRC g'aidance in regard to
        independent verification. The inspector verified that independent
        verification was being performed in accordance with procedure
        00308-6, Independent Verification Policy. The inspector observed the
        performance of a Boric Acid Transfer Pump tag-out and checked a
        co.'pleted RHR system lineup. This item is considered closed.
    d.  (Closed) Inspector Followup Item 424/86-117-02. Lack of Vents on
        AFW Piping at Apparent System High Points. The inspectors had noted
        in a system walkdown of the Auxiliary Feedwater System that there
        were no high point vents on the AFW side of the first check valve
        between the AFW system and the main feedwater bypass line for stecm
        generators 1 and 4. The inspectors were concerned that any back-
        leakage and subsequent steam formation of main feedwater through
        those check valves would become trapped in the highpoints and could
        result in water hammer upon AFW initiation. There were no provisions
        within the procedure, 13610-1, to monitor these highpoints for                                      l
        1eakage and steam formation, nor to take action, upon detection of                                  ,
        steam formation, to resolve water hanner concerns. The inspector                                    !
        reviewed the analysis performed by the licensee for backleakage into                                )
        the AFW system and determined that the present design and monitoring
        procedures provide adequate assurance that backleakage will not occur                                l
        or result in waterhammer in the AFW system. This item is closed.                                    -
                                                                                                              l
                                                                                                              l
                                                                                                              1
                                                                                                            -
 
                                                                                                                  . - _ _ _ _ - _ _ _
                _.  _
                                                    24
            e. (Closed) Inspector Followup Item 424/86-117-03. Precautions on
                Maintaining Subcooling Margin.                    Item a was closed in Inspection
                Report 424/86-117. In regard to Item b, which concerned A0P 18009-1,
                Steam Generator Tube Leak, the inspector had determined that Step 5,
                " Response Not Obtained", required the reduction of RCS temperature
                from 557 F to 500 F prior to isolation of the faulted SG if the
                faulted S/G was not immediately identified. The procedure then
                required the subsequent identification and isolation of the faulted
                S/G and RCS depressurization to 25-50 psig greater than the faulted
                S/G pressure. Under these conditions, RCS subcooling margin would be
                approximately 5 F, which is substantially less than the 28 F sub-
                cooling margin parameter delineated in procedure 19200-1, F-0,
                Critical Safety Function Status Trees, for assuring adequate core
                cooling in the Emergency Operating Procedure Network.                            In addition,
                no instructions were given to isolate the cold leg accumulators at
                950 psig.
                The inspector reviewed the revision of the procedure that had been
                reviewed and approved by the Plant Review Board.                            (The revision was
                handwritten at the time of the review.)                    Prior to the steps that
                depressurized the RCS to 25-50 psig of the faulted S/G, the licensee
i
                had inserted the following steps: "If pressurizer pressure lowers to
                less than 1000 psi, accumulators should be isolated." and, "During
                cooldown, maintain at least 50 F RCS subcooling." These changes
                adequately addressed the problems described above and Item b of IFI
                424/86-117-03 is closed.
            f. (Closed) Inspector Followup Item 424/86-117-04. Correction of Valve
                Identification and Lineup Discrepancies. Each item identified in IFI
                424/86-117-04 is addressed separately below.
                Item a.    NSCW valve 1-1202-X4-205, shown to be on the return line
l              of the train "A" reactor cavity cooling coil, was listed on the
                alignment checklist of procedure 11150-1, Rev.1, but was not on
                the P&ID, nor was it found in the system during a system walkdown.
                The licensee provided the inspector a Temporary Change to Procedure
                (TCP) form number 11150-1-87-2, generated and approved on January 8,
                1987, which corrected the checklist. The TCP required final approval
                by the Plant Review Board by January 22, 1987.                              Item a of IFI
                424/86-117-04 is closed.
                Item b.    A vent valve on the NSCW system on the outlet from the
                lube oil cooler for the centrifugal charging pumps on train A was
                not on the valve lineup verification list of procedure 11150-1,
                Rev. O. This discrepancy had been corrected on Rev.1 of this
                procedure.    Item b of IFI 424/86-117-04 is closed.                                                                  l
                                                                                                                                      l
                ltem c.  This item was closed in Inspection Report 424/86-117.                                                      .
                                                                                                                                      1
!              Item d.  This item was closed in Inspection Report 424/86-117.                                                      I
                                                                                                                                      !
  .-- - -, -        .            _
                                      -    , . _ .    . - . . _          - - _ . , - -- -              - - - _ - - ,
 
                                  25
  Item e. The CS system alignment procedure, 11115-1, and the CS
  system P&ID, drawing 1X4DB131, did not agree. The CS drawing
  contained two valves, X-40 and X-127, on a flushing line downstream
  of the B train CS pump that were not included in the alignment
  procedure.    The valves were verified to exist during the CS system
  walkdown.    The drawing indicated that the valves were both normally
  closed.    Also, in the same flushing connection, the CS alignment
  procedure showed valve U4-012 closed. The CS P&ID showed the valve
  locked open. The inspector reviewed procedure 11115-1 and determined
  that the licensee had corrected the discrepancies.      Item e of IFI
  424/86-117-04 is closed.
  Iten f.    The IFI concerned the removal of a reference to a obsolete
  controller from a procedure. No followup review was considered
  necessary.
  Item g. The inspector noted that CTB Cooling Unit Outlet Dampers
  were required to be locked open per Containment Heat Removal System
  drawing 1X4DB212.      Procedure 13120-1 did not include the locking
  requirement and the locking method. The inspector determined that
  the licensee had corrected the discrepancy. Item g of 424/86-117-04
  is closed.
g. (Closed) Inspector Followup Item 424/86-117-05. Discrepancies in
  Unit Operating Procedures. Each item identified in IFI 424/86-117-05
  is addressed separately below.
  Item a.    Item a was closed in Inspection Report 424/86-117.
  Item b.    Item b was closed in Inspection Report 424/86-117.
  Item c. Procedure 12006-1, step 2.2.5, paraphrased a Technical
  Specification requirement. The paraphrase was incorrect. The step
  should have read "... and at least one loop in operation with the
  reactor trip breakers open." The inspectors verified that 12006-1
  had been corrected. Item c of IFI 424/86-117-05 is closed.
  Item d.    Procedure 12006-1, Section C4.1, Preparation for Continuing
  Unit Cooldown, required action be taken to accivate protection
  against cold overpressurization. Only one method of cold over-
  pressure protection was addressed, the use of PORVs. The procedure
  also should have addressed the two other mear of cold overpressure
  protection and a mechanism to declare which method was providing
  protection. The procedure should have addressed the implementation
  of the TS :urveillance requirement on the RHR relief valves which
  must be completed prior to taking credit for the RHR reliefs.      The
  inspector verified that procedure 12006-1 had been changed.    Item d
  of IFI 424/86-117-05 is closed.
                                                                          l
                                                                          .
                                                  -
                                                      g -
 
                        . -.                        .                                                                                          .
;
                                                                                          26
                                    Item e.            Procedure 12005-1 did not include a requirement in the
i
                                    Limitations section to refer to TS 3.4.1.2.                            The inspector verified
                                    that procedure 12005-1 had been changed.                          Item e of IFI 424/86-117-05
;
                                    is closed.
                                    Item f. Procedure 12006-1 did not include a precaution to assure
                                    that when the reactor is in the source range, positive reactivity
                                    additions will only be made by one controlled method at a time.
                                    The inspector verified that 12006-1 had been changed. Item f of
                                    IFI 424/86-117-05 is closed.
j                                h. (0 pen) Inspector Followup Item 424/86-117-07.                                    Discrepancies in
                                    Equipment Labeling. Each item identified in IFI 424/86-117-07 is
;
                                    addressed separately below.
i                                  Item a.            Name tags were missing from RHR valves HV-8701B and
                                    1205-027.            The licensee stated that one of these tags had been
                                    replaced and the other had been ordered. These valves will be
                                    examined during a subsequent inspection to assure that these actions
l                                  are taken. Item a of IFI 424/86-117-07 is open.
l                                  Item b. The inspector determined that the B train controller at
                                    the remote shutdown panel was still labeled as 4. Item b of IFI
                                    424/86-117-07 remains open.
                                    Item c. The TDAFW panel SG level gauge was not labeled wide range or
                                    narrow range. The procedure did not indicate the range. An AFW to
                                    SG bypass flow gauge was not labeled with engineering units. The
                                    inspector verified that the SG level gauge had been labeled. The
                                    bypass flow gauge had not been labeled. Item c of IFI 424/86-117-07
                                    remains open.
                                    Item d.          Item d was closed in Inspection Report 424/86-117.
                                    Item e.          Item e was closed in Inspection Report 424/86-117.
                                    Item f.            The inspector had noted that engineering units were not
                                    displayed on strip chart recorder scales for main steam temperature
                                    and other recorders. The inspector subsequently reviewed labeling
                                    of main control board strip chart recorders for engineering units.
'
                                    Although the main steam temperature had been correctly labeled by
                                    the licensee, other recorders still had no units.                                    Item f of IFI
1                                  424/86-117-07 remains open.
                                    Item g. The inspector noted that remote handwheels in the CVCS
                                    system including BIT valves and charging crossover were not labeled.
                                    The applicant stated that handwheels had been installed recently and
                                    labeling was planned but had not been completed. The inspector
,
                                    conducted a tour of the auxiliary building levels containing the CVCS
.
                                    system and noted a greatly improved level of labeling for the remote
i
                                    manual valve operators, however, the inspector noted several remote
  <
    <-,--,.-----.,,,--m-      ,-    ----.-w.,, ,-p.m,        w      w -.----w.,-n..-,.m--    . - , ,-    -,,-,..,,--,n        ,,-y . ,,--,.--m-e-,- yme --
 
                                  27
    manual valve operators in the waste gas disposal area which lacked
    tags. The licensee stated that final efforts were being completed in
    assuring the adequacy of valve labeling. No additional followup is
    considered necessary. Item g of IFI 424/86-117-07 is closed.
    Item h.    The CS alignment procedure, 11115-1, lists two sets of
    120V AC CS MOV space heater breakers. A check of the 120V AC breaker
<
    panels (IAYD1 and 18YD1) identified the breakers as being labeled
    " spares."    The applicant is determining if these breakers are
    utilized for the M0V space breakers.    Item h of IFI 424/86-117-07
    remains open.
  i. (0 pen) Inspector Followup Item 424/86-117-09. Review of Reactor
    Vessel Level Indication System. Four concerns were identified during
    the review of RVLIS involving procedure nomenclature, instrumentation
    references in procedure 14228-1, a vendor recommendation for a
    control room annunciator that had not been provided, and a vendor
    recommendation for periodic checks of locally indicating null meters.
    The inspector was provided a Daily Schedule Control Sheet which
    indicated that the null meters would be checked by Operations
    quarterly. It is noted that the RVLIS will be tested when the
    reactor coolant system is at system operating pressure during startup
    testing. The inspector will review the reuining items and the
    results of the RVLIS testing after startup.      IFI 424/86-117-09
    remains open.
  j. (Closed) Inspector Followup Item 424/86-117-10. Procedure Revision
    to Include Check of Equipment Actuation on Control Room Ventilation
    Start. The inspector reviewed procedure 13301-1, which had been
    revised in Rev.1 to include steps that verify that the outside air
    supply dampers close on manual actuation of Control Room Toxic Gas
    Isolation. IFI 424/86-117-10 is closed.
  k. (Closed) Inspector Followup Item 424/86-117-11.        Adequacy of
    Procedure Prerequisites. The inspectors had identified that scme
    of the prerequisites in S0Ps and surveillance procedures were too
    general. Interviews with licensee personnel indicated that it was
    not clear to them what was required to be verified to satisfy
    selected prerequisites. By letter dated January 14, 1987, the
    licensee committed to implement additional controls of prerequisites
    until the procedures were reviewed and modified to clarify prerequi-
    sites. The licensee stated that standing order 1-87-04 had been
    issued to Operations to require that prior to initial use of any
    procedure being used in the control room the Shift Supervisor and
    operator will review the prerequisites / initial conditions section
    to ensure clarity and understanding of the required conditions. The
    order contains provisions to upgrade prerequisites by submitting
    comments / changes via an attachment to the letter.    Based on this
    commitment, IFI 424/86-117-11 is closed.
 
                                  .            .        _  -.      ._.  _ _ _ _ _
                                      28
,
  f
    1. (Closed) Inspector Followup Item 424/86-117-12. Clarification of
      Cleanliness Levels. The IFI involved clarification of the cleanli-
'
      ness zone designations in Section 4.1.d of procedure 00254-C, Plant
      Housekeeping and Cleanliness Control, to ensure that all open RCS
:    components, as well as the refueling cavity, would be classified as
      Level II. The licensee revised the Level II cleanliness requirements
      in 00254-C, Section 5.4, to specifically include any system that
      could allow contaminates to reach the RCS. This revision meets the
      intent of the IFI and IFI 424/86-117-12 is closed,
i
!  m. (Closed) Inspector Followup Item 424/86-117-13. General Review
i    of Abnormal Operating Procedures. Topics from Regulatory Guide
      1.33, Revision 2, February 1978, were verified to have procedures
      established. The following contingencies were implemented by the
      procedures listed below:
l                                                    Procedure Revision
                            Event                      Number    Number
      Loss of Condenser Vacuum                    - 18011-1      1
                                                      18023-1    1
      Loss of Containment Integrity              - 17005-1      2
:      Loss of Feedwater                          - 17009-1      0
                                                      18016-1    1
>
      Conditions Requiring Emerg. Boration        - 17010-1      3
                                                      18007-1    1
      Fuel Cladding Failure                      - 17005-1      2
                                                      18006-1    1
      High Activity in Coolant or Offgas          - 17100-1      2
,                                                    17213-1    0
                                                      18009-1    2
      Pressure Control Malfunction                - 18011-1      1
      Plant Fires                                - 17103-C      0
,                                                    18038-1    2
i      Abnormal Releases of Radioactivity          - 18009-1      2
:
j      Based on this review, procedural implementation of Regulatory
'
      Guide 1.33 is adequate and IFI 424/86-117-13 is closed.
    n. (Closed) Inspector Followup Item 424/86-117-14. Annunciator Response
      Procedure (ARP) Discrepancies. The inspector reviewed the licensee's
      commitment to conduct a review of ARP's to determine the adequacy of
      initial operator actions, the accuracy of window labelling, and the
      overall adequacy of each procedure.      The inspector reviewed Main
      Control Board (MCB) ARP's (panels 1 through 20) and concluded that a
      thorough review had been performed on these procedures and the
      procedures accurately reflected the annunciator windows and provided
      sufficient initial operator action.    The inspector also reviewed
,
      several of the review packagos for the annunciator panels, particu-
'
      larly those on the MCB. All of the reviews appeared to be comprehen-
      sive and competent. Although the ARP's for the annunciators that are
(
 
                                                          .-
                                                  29
                                                                                      !
        not on the MCB have not all been revised as yet; the reviews that
        were completed were adequate and the licensee program for completion
        of the reviews was determined to be adequate.      Therefore, IFI
        424/86-117-14 is closed.
        During the review of the corrective action for IFI 424/86-117-14,
        the inspector detennined that the ARPs referenced a Master Setpoint
        Document in lieu of giving an actual setpoint for certain annunciator
        alarms. Interviews with several operators indicated that they did
        not know where to find this document. In addition, personnel in the
        Operations Department were not sure as to the exact form or location
        of this document. Followup on the licensee's actions to establish
        the document or to replace the references to the document in the
        ARP's with the actual setpoint was identified as IFI 424/87-01-07.
        This IFI was subsequently reviewed during this inspection and the
        inspector determined that the licensee had taken corrective action
        for the IFI. This review is documented under paragraph 12.nn for IFI
        424/87-01-07 in this report.
    o. (Closed) Inspector Followup Item 424/86-117-15. Acceptability of
        Baseline IST Data for Section XI ASME Pump Testing. This item
        concerned baseline data obtained on four of six Component Cooling
        Water (CCW) pumps which was below the data obtained during preopera-
        tional testing.    The inspector requested engineering justification
        for the operability of these pumps prior to fuel load. The inspector
        discussed with the licensee the ASME Section XI code, the licensee's
        ISI program, the inherent error in the measuring equipment, and the
        configuration of the preoperational test versus that of the ISI test.
        Pump curves from the manufacturer were compared with the preopera-
        tional data and the baseline data. The licensee provided adequate
        justification as to the operability of the CCW pumps in question.
,      IFI 424/86-117-15 is closed.
    p. (Closed) Inspector Followup Item 424/86-117-16. Technical Specifica-
        tion on the Discharge Flow of the RHR Pump. The inspector had
        determined that the discharge pressure on the recirculation flow of
        RHR pump B was equal to 180 psid. TS 4.2.5.f required the discharge
,
        pressure to be 1180 psid. The licensee had stated that a TS revision
        had been requested to change the value to be 1165 psid. The inspec-
        tor subsequently reviewed the TS revision whIch incorporated the
-
        change. IFI 424/86-117-16 is closed,
    q. (Closed) Inspector Followup Item 424/86-117-17. Resolution of Water
        Hanner in NSCW. The item concerned the waterhammer that had occurred
        on the NSCW system during the Loss of Offsite Power test. The
        licensee's analysis, which concluded that the waterhammer did not
        impair the operability of the system, was reviewed and found to be
        acceptable. IFI 424/86-117-17 is closed.
                      -
  .-                      -
                              .-_- - -. - -- - - -                  . . . - -    --
            _
                                                                                .
                                                                -            .
 
                                                                                            :
                                            30
        r.  (Closed) Inspector Followup Item 424/86-117-18. Implementation of
              Surveillance Program.    During the inspection ending December 12,
              1986, the inspectors had determined that the licensee had not yet
              fully implemented the surveillance program administrative controls
              except on a small number of systems which had been accepted by the
              Operations Department.      During this inspection, the inspectors
              reviewed the implementation of the surveillance program and a number
              of additional surveillance test packages. Although several concerns
              were identified and one example of a failure to follow procedure was
              identified; in general, the results of this review indicated that the
              surveillance program was adequately implemented.        The review is
              documented in paragraph 7 of this report.      IFI 424/86-117-18 is
              closed.
        s.  (Closed) Inspector Followup Item 424/86-117-19.        Review of Test
              Control and Implementation of Configuration Control during
              Performance of Surveillance Testing.    The inspectors had determined
              that in some surveillances performed during the preoperational
              testing, the prerequisites were not always satisfied prior to
              beginning the test. It was not clear in the cases reviewed whether
              or not credit would be taken for the test. The inspectors reviewed a
              number of completed surveillance packages and observed additional
              performances of surveillance testing. No additional instances of
              failure to satisfy prerequisites or establish system configuration
              were noted.    The inspector rereviewed the performance of the MDAFW
              surveillance procedure,14807, and determined that the system had
              been retested. Additional information on the review of the surveil-
              lance program is provided in paragraph 7. IFI 424/86-117-19 is
              closed,
          t. (Closed) Inspector Followup Item 424/86-117-20.      Revise Procedures to
              Clarify Use of Staggered Test Basis for Determining Frequency of
              Test. The inspector had determined that although the Surveillance
              Test Coordinator was correctly tracking surveillances required on a
              staggered test basis, the test frequencies specified in certain
              surveillance procedures did not mention the requirement for stagger-
              ing the tests.    The inspector determined that procedure 00404-C,
              Surveillance Test Program, has been revised to include the TS
              definition of staggered test basis.      The inspector reviewed the
              deficient procedures identified and determined that the surveillance
              procedures had been revised to specify that the tests are to be
              performed on a staggered test basis where appropriate.              IFI
              424/86-117-20 is closed.
        u.  (Closed) Inspector Followup Item 424/86-117-21.          Review of
              Justifications for Use of Preoperational Tests to Meet TS
              Surveillance Requirements.        The inspectors reviewed the
              preoperational test data used to take credit for the 18 month
              surveillance tests of the emergency diesel generators (EDG) and
              the battery chargers.    The inspectors reviewed the pre-op tests
              with the engineers responsible for the EDGs and the battery
- _ _ . ._      _                      _            _          _          , . _
                                                                                        . __
 
                                                    31
                chargers. The review included a step by step table-top walkthrough
                uf the effected surveillances with a comparison of the pre-op data
                used to take credit for required data in the surveillances.                        In both
                cases the inspectors determined that the pre-op data appeared to be a
                valid substitute for the data required for the surveillance and that
                the licensee did an adequate job in the justification of the use of
                the pre-op data. The inspector discussed the controls with the
                licensee which will be utilized for assuring that startup tests are
                appropriately evaluated if the tests are to be used in lieu of
                surveillance tests. The inspector determined that the licensee made
                significant improvements in the evaluation of the use of other tests
                in lieu of surveillance tests and took steps to assure that surveil-
                lance tests were performed in those cases where other tests did not
                satisfy the surveillance test requirements.          The inspector had no
                additional questions. IFI 424/86-117-21 is closed.
          v.    (Closed) Inspector Followup Item 424/86-117-22. Corrective Action to
                Assure Control of Twelve Hour Surveillances. The inspector reviewed
                procedure 14000-1, Rev. 3, Operations Shift and Daily Surveillance
                Logs, which now specify that surveillances be performed within
                two hours of each shift. Procedure 10000-C, Rev. 3, Conduct of
                Operations, had been revised to require that the On Shift Operations
                Supervisor or the Shift Supervi::or ensure that procedure 14000-1
                be performed within the first two hours of each shift.                  IFI
                424/86-117-22 is closed.
          w.    (0 pen) Inspector Followup Item 424/86-117-23.            Miscellaneous
                Technical Issues Identified in Review of Surveillance Program.
                This IFI included examples of various technical concerns identified
                during the review of surveillance procedures and/or surveillance
                program implementation. Each concern is identified separately below
                by the paragraph number in Inspection Report 424/86-117.
                Paragraph 7.c.          Procedure 14721-1 required SI pumps to be operated
                during the test; however, there was no provision to open and rack out
                the motor supply breakers upon test completion. TS 4.5.3.2 requires
                the motor supply breakers to be open while in Modes 4, 5 and 6. The
                inspector was shown a draft revision to the procedure which included
                adequate steps. The procedure additionally specified that maximum
                allowed flow was 650 gpm although TS 4.5.2.h.2.b allows up to 660
                gpm. Although the requirement was conservative, it was inconsistent
                with other requirements in the procedure. The same draft revision
                also corrected the allowable flew to 660 gpm. Procedure 14460-1 did
                not require venting through valve 1-1204-X4-827, SI Pump Miniflow                                                    I
                Vent Valve. TS 4.5.2.b.1 requires the venting of ECCS pump discharge                                                !
                piping high points at least once per 31 days. The applicant stated
                that a Temporary Change Procedure (TCP) would be initiated. The
                procedure additionally referred to the A SI pump as 1. The inspector                                                I
                verified that the procedure was corrected. Procedure 14000-1 did not                                                l
                specify that the surveillances on page 17 were to be performed in                                                    !
                modes 1 or 2 only. The inspector verified that the procedure was
                                    v
                                      .vr
_ _ _ _ _  ___        _____ _ ____        _                                      . _ _ _ . _ _ . _ _  _ _ _ _ _ _ _ _ _ _ _ _ _
 
                              32
corrected. The correction of minor comments on procedures 54821-1,
which referenced a deleted TS table, and 55016-1, which contained a
typographical error in a TS reference, was verified. The comments on
the surveillance procedures for the safety injection system in IFI
424/86-117-23 are considered closed.
Paragraph 7.e. A review of procedure 00404-C, Surveillance Test
Program, Rev. 2, dated December 3, 1986; 00405-C, Commitment
Identification, Tracking, and Implementation, Rev. 3, dated
October 22, 1986; and 00051-C, Procedures Review and Approval,
Rev. 5, dated December 1,1986 indicated that the mechanisms to
govern changes to procedures which implement technical specification
commitments and changes to technical specification commitments which
are implemented in procedures were in place. The aforementioned
procedures will ensure that if changes occur, the changes will be
reflected in the surveillance task cross reference report and the
master surveillance report.      It should be noted that procedure
14935-1, Rev. I draft, which prompted this concern, was approved. A
review of the associated paper work revealed that the individual
responsible for the commitment review failed to identify the deletion
of a commitment.    The appropriate corrections were made when the
error was identified to the reviewer. This part of IFI 424/85-117-23
is closed.
A review of procedure 14721-1, ECCS Subsystem Flow Balance Test,
Rev.1, dated January 2,1987, discloses a revision which changes
the applicability of the procedure to modes 1, 2, 3 and 4.      This
is consistent with TS 4.5.2 and 4.5.3.1.          This part of IFI
424/86-117-23 is closed.
Paragraph 7.f. Section 6.0, Acceptance Criteria, in both revisions
of procedure 14806-1 did not include observation of proper lubricant
level or check of calibration due dates. Section 8.0 of draft Rev.1
did not include the date of the applicable edition of ASME B&PV code,
Section XI. The inspector verified that these items had been
corrected. These comments are considered closed. Procedure 54701-1:
(1) did not meet the requirements of TS 4.8.4.2.b, (2) failed to
require the opening and locking of valve 1-1206-U6-029 after comple-
tion of the test, (3) did not include a step to unlock and close
valve 1-1204-U6-018, and (4) did not include independent verification
of the position of 1-1206-U6-018.      The inspector verified that
the licensee had corrected these items.        This portion of IFI
424/86-117-23 is closed.
Paragraph 7.g. The valve numbers in TS 3/4.6.1.7 were incorrect.
Valves HV-2624 A and B, 4 inch isolation valves in the Containment
Building Post LOCA Exhaust system; and, HV-2627 A and B and HV-2629 A
and B, containment purge and exhaust isolation valves, were not
included in the statement of the LCO. The valve numbers in surveil-
lance requirement 4.6.1.7.1 were not all 24-inch containment purge
 
                                  33
  and exhaust isolation valves as indicated. HV-2624 A and 8 were 4
  inch Containment Building Post LOCA Exhaust isolation valves.
  HV-26268 and HV-26-288 were 14-inch Containment Building mini-purge
  supply and exhaust isolation valves. The inspector verified that the
  numbers in the TS were corrected. This portion of IFI 424/86-117-23
  is closed.
  Paragraph 7.h.    The reference to paragraph 7.h in Inspection
  Report 424/86-117 was a typographical error. Coments in this
  section were evaluated and no followup was considered necessary.
  Paragraph 7.i. While witnessing the MDAFWP testing, the inspector
  noted in procedure 14807 that no step was included in the system
  restoration to place handswitch HS5131A back into automatic. The
  system restoration section of procedure 14807, Rev.1, now includes a
  step to place handswitch HS5131A back into automatic at the conclu-
  sion of the MDAFW surveillance test, and to independently verify this
  step. This portion of IFI 424/86-117-23 is closed.
  Paragraph 7.J. The inspector noted that the physics curve book
  had not been completed.      During a subsequent inspection, the
  inspector determined that the physics curve book was near completion.
  The majority of the reactivity data, which had been extracted from
  WCAP-11338 and reformatted, had been provided to Reactor Engineering
  for review. This portion of IFI 424/86-117-23 will remain open until
  completion of the curve book is reviewed.
x. (Closed) Inspector Followup Item 424/86-117-24. Implementation
  of the Operational Phase Corrective and Preventive Maintenance
  Program. This item is closed as discussed in paragraph 8 of this
  report,
y. (Closed) Inspector Followup Item 424/86-117-25. Ultimate Heat Sink
  Technical Specification Clarification.    A revision was to be made to
  the ultimate heat sink TS to clarify the wording, remove ambiguities,
  and modify a surveillance so that it could be realistically met. The
  inspector determined that the changes had been approved and would be
  included in the TS. IFI 424/86-117-25 is closed.
z. (Closed) Inspector Followup Item 424/86-117-26. Verification of
  Position of BIT Isolation Valves.    A review of procedure 11006-1,
  Chemical and Volume Control System Alignment for Start-up and Normal
  Operation, Rev. 3, dated December 29, 1986, contains a revision which
  calls for the verification of BIT isolation valves 1-HV 9803 A & B
  in the open position with the Limitorque handwheel lon ed. This
  revision satisfies TS requirement 4.5.2.b.2 by designating these
  valves, which are in the ECCS flow path, as locked valves, thereby
  excluding them from the 31 day correct position verification. The
  inspector field verified that the appropriate locks were installed.
  IFI 424/86-117-26 is closed.
 
                                  34
aa. (0 pen) Inspector Followup Items 424/86-117-27. TS / Surveillance
    Procedure Cross Reference List and Surveillance Procedure Completion.
    Some procedures referenced in the TS / surveillance procedure cross
    reference list had not been written and/or had not been identified in
    the cross reference list. Procedure 53002-C was shown in the cross
    reference list for BOL moderator temperature coefficient surveillance
    (TS 4.1.1.3.a) but the licensee did not plan to use the procedure for
    the initial startup test and it had not been written. This procedure
    will be an integrated low power physics testing procedure to be used
    for reloads. The inspectors confirmed that the procedure to be used
    was adequate to meet the surveillance requirements. The TS cross
    reference list did not show which startup tests are used to satisfy
    surveillance requirements. Startup testing will be observed in
    future inspections.
    The inspectors reviewed a portion of the cross reference list to
    confirm that procedures required for Mode 6 had been identified
    and completed.    The inspectors provided several minor comments to
    the licensee for resolution, but determined that the cross reference
    list was adequate for startup.      IFI 424/86-117-27 will remain open
    pending further review of the status of procedures required for power
    operation.    IFI 424/86-96-05, which involved the review of the
    completion of procedures required to meet TS surveillances, is
    closely related to IFI 424/86-117-27.      Based on the review of the
    surveillance program documented in paragraph 7 and the followup to be
    conducted to close IFI 424/86-117-27, IFI 424/86-96-05 is closed.
bb. (Closed) Inspector Followup Item 424/86-96-05. Review of Surveil-
    lance Procedure Completion. This item is closed as documented in
    paragraph 12.aa.
cc. (Closed) Inspector Followup Item 424/86-117-28.    Procedure Revision
    for Consistent Definition of Surveillance Test Completion Date and
    Time. Administrative surveillance tracking procedure 00404-C, was
    revised by Revision 4 to correct a discrepancy between Section 2.5
    and its surveillance task sheet completion instructions, note 20,
    concerning the surveillance official completion date and time. A
    surveillance test is now consistently considered complete only after
    the test results have been reviewed. Therefore, IFI 424/86-117-28 is
    closed.
dd. (Closed) Inspector Followup Item 424/86-117-29. Review of Special
    Condition Surveillance Test Triggering Mechanisms. The inspector
    reviewed documentation to determine whether or not the applicant has
    adequate triggering mechanisms to ensure certain special condition
    surveillances are performed. A computer printout listing all special
    condition surveillances for mode 6 and all modes was reviewed. The
    list contained approximately 112 surveillance requirements, the
    department responsible for triggering, the department responsible for
 
.
.
                                      35
      completion, and the applicable procedures. The inspector audited 20
      surveillance requirements to determine that adequate steps or
'
      precautions had been inserted into the appropriate procedure to
      trigger the required surveillance test.
      In all but one case either an adequate procedure existed, a Temporary
      Change Procedure (TCP) had been generated, or a revision was in the
      approval process which the inspector reviewed. The inspector noted
      one case where inadequate triggering mechanisms existed. Procedure
      17034-1 did not contain a requirement to verify 125V battery opera-
      bility after battery discharge or overcharge within 7 days as
      required by TS 4.8.2.2. Although procedure 17034-1 had been desig-
      nated to have the triggering mechanisms for the maintenance
      department to perform the surveillance, the revision had not been
      done. This was pointed out to the licensee. A TCP was immediately
      processed. The inspector reviewed the TCP and found that the change
      incorporated the appropriate triggering mechanisms.
!    The inspector reviewed methods and procedures for departments to
;    keep track of special condition surveillances.      Draft procedure
      50045-C, Engineering Special Condition Surveillances, was reviewed.
      The procedure included a log for keeping track of active surveil-
,
      lances. Discussions with responsible personnel indicated that the
      draft copy reviewed by the inspector was not finalized for approval
      and that additional EFPD sensitive surveillances, which were not
      requirements for fuel load, were to be incorporated into the
      procedure.  The inspector reviewed chemistry procedures 31045-C, Rev.
4
      4, Chemistry Logkeeping, Filing, and Record Storage; and, 30040-C,
      Rev. 1, Reporting Chemistry Data to Operations Department. The
      procedures were adequate to track surveillances in the Laboratory
      Logbook. Special condition surveillances for the Instrumentation and
i      Control Section were primarily associated with instrument calibra-
      tions after a seismic event and one associated with RCS pressure
      calibration after refueling. The following procedures were reviewed:
      18036-C, Rev.0, Seismic Event; 50022-C, Rev. 3, Seismic Event Plan;
      55039-C, Rev. O, Seismic Monitoring Instrument System; 12000-1,
      Rev.1, Refueling Recovery. Items will be tracked through Operations
      as equipment is placed inoperable. The Maintenance Department
      triggered all of their special condition surveillances through the
,
      planning and work order programs and did not have a log to keep
      track of active surveillances; however, procedure 20051-C, Rev. O,
      Maintenance Work Order Functional Tests, itemized surveillances to
      be triggered after certain maintenance items.      This was deemed
      adequate. IFI 424/86-117-29 is closed.
  ee. (Closed) Inspector Followup Item 424/86-117-30.      Control on the
      Location of the B0P Operator. The inspector reviewed procedure
      10000-C, Rev. 3, which had been revised to state that the balance
      of plant operator normally remains in the control room.        IFI
      424/86-117-30 is closed.
4
 
                                                                                l
                                                                                l
                                                                                l
                                                                                !
                                          36
    ff. (0 pen) Inspector Followup Item 424/86-117-31. Key Control . On
          December 11, 1986, during the walk through of the reactor coolant
          pump loop 1F-416 procedure, 24790-1, the inspector had observed
          that the technician needed to go to the shif t clerk's office three
          times to obtain the keys needed to open the reactor solid state
          protection system (SSPS) cabinets to perform the surveillance
          procedure.    In a letter dated January 13, 1987, which referenced a
          memorandum dated January 8, 1987, the licensee stated that the
  ,
          control of keys to all panels and cabinets which require operator
;
          access would be reviewed and validated. The memorandum stated that a
          new key control cabinet had been added, that an up-to-date list of
          keys had been completed and that the cabinet keys would be validated
          by February 6, 1987. By memorandum dated January 15, 1987, a copy of
          which was provided to the inspectors, the licensee stated that the
          cabinet key controls would be in place by February 21, 1987. The
          inspectors agreed that this date was acceptable. The memorandum also
,
          stated in regard to locked doors inside the power block, that these
          doors would routinely be left unlocked, except vital area doors,
~
          remote shutdown panel doors, essential 4160V AC switchgear room
          doors and high radiation area doors.      Due to the types of locks
          on some of the interior doors, the licensee stated that certain
          locks would have to replaced to allow the doors to be left unlocked.
.
          The licensee stated that the locks would be replaced by April 1,
l        1987.  IFI 424/86-117-31 will remain open until these actions are
          verified.
    gg.    (Closed) Inspector Followup Item 424/86-117-32. Technical Specifica-
          tion Change to Reflect 18 Month Surveillance of Under Voltage and
          Shunt Trip Coils on Reactor Trip Breaker. The final TS draft did not
          specify testing of the reactor trip breaker undervoltage (UV) and
          shunt coils. Generic letter 83-28 required this testing to be
          performed with an 18 month frequency, as a minimum.      The inspector
          verified that procedure 14701-1, Rev. 3, had been changed tn
          incorporate these items to test the reactor trip breakers unde -
          voltage and shunt trip. IFI 424/86-117-32 is closed.
    hh.    (0 pen) Inspector Followup Item 424/86-117-33.      Miscellaneous
          Technical Issues Identified in Review of Operations Procedures.
          This IFI included examples of various technical concerns identified
,        during the review of operations procedures. Each concern is identi-
          fied separately below by the paragraph number in Inspection Report
          424/86-117.
i        Paragraph 6.b.6. Two alarm panels were not displayed above the
          CCW operating switches in the control room as required by 18020-1
          and ARP 17002-1.      The inspector verified that the licensee had
          taken action to correct these discrepancies.      This portion of IFI
          424/86-117-33 is closed.
i
i
!
 
r
                                                                                                                                              37
                                                                                                            Paragraph 6.b.7.      In procedure 18003-1 the following coments were
                                                                                                            made.    In step 4.1.2.9, which repeats a reactor coolant pump start
                                                                                                            sequence, no reference was made to the reactor coolant pump restart
                                                                                                            limitations identified by precautions 2.2.11.2 and 2.2.11.3.        The
                                                                                                            seal injection flow shown on Figure 1 showed six to eight gpm,
                                                                                                            whereas item 2.2.6 specified 8 to 13 gpm. The flow logic in the
                                                                                                            decision tree depicted in Figure 1 failed at both the " check No. 2
                                                                                                            seal leakoff flow" block and at the " check injection and bearing
                                                                                                            temperature" block since neither block provided a logical exit from
                                                                                                            the block. The inspector verified that procedure 18004-1, Rev. 2,
                                                                                                            corrected the:e items. This portion of IFI 424/86-117-33 is closed.
                                                                                                            Paragraph 6.b.9.      The inspector had identified concerns in that
                                                                                                            procedure 13610-1 did not contain provisions for monitoring and
                                                                                                            responding to adverse bearing oil temperatures for all three AFW
                                                                                                            pumps and did not implement provisions for positioning and aligning
                                                                                                            the turbine driven AFW pump overspeed test switch (HS-15130) and
                                                                                                            speed control potentiometer. During a walkdown of the AFW system,
                                                                                                            the inspectors noted that the turbine driven pump gland seal leakage
                                                                                                            was approximately 3 to 5 times greater than that of the motor driven
                                                                                                            pumps and appeared to be excessive. The licensee acknowledged the
                                                                                                            concern.    Procedure 11882-1, Outside Areas Round Sheets, did not
                                                                                                            provide for a general inspection of the north Main Steam and
                                                                                                            Feedwater valve room, the motor driven pump A pump room or the
                                                                                                            turbine driven pump pump room. Also there are no items to check for
                                                                                                            adequate pump gland seal leakage and adequate gland seal leakage
                                                                                                            drainage from the gland seal leakage reservoir. The inspector
                                                                                                            verified that all of the issues had been satisfactorily addressed by
                                                                                                            the licensee except one. Gland seal leakage from the turbine driven
                                                                                                            AFW purrp has not been dispositioned yet.      IFI 424/86-117-33 remains
                                                                                                            open to follow the corrective action on the gland seal leakage.
                                                                                                            Paragraph 6.b.10.      Steps 2.2.1 and 2.2.2 in CS system procedure
                                                                                                            13115-1 which addresses TS limits did not include Mode 4 in the
                                                                                                            applicable modes as required by TSs.      The inspector verified that
                                                                                                            the procedure had been revised.          This portion of IFI
                                                                                                            424/86-117-33 is closed.
                                                                                                            Paragraph 6.b.11. Steps 2.2.1 and 2.2.2 in procedure 13120-1 did
                                                                                                            not list the applicable TS modes. The inspector verified that the
                                                                                                            procedure was revised. This portion of IFI 424/86-117-33 is closed.
                                                                                                            Paragraph 6.c.      The concern involved limiting excessive overtime
                                                                                                            for personnel performing safety related functions. Limiting exces-
                                                                                                            sive overtime is addressed by TMI Action Item I.A.1.3. Procedure                                  l
                                                                                                            00005-C, Rev. 2, Overtime Authorization, now includes the requirement                              I
                                                                                                            of TS 6.2.2.e that overtime should not be routinely scheduled for                                  l
                                                                                                            personnel responsible for performing safety-related functions.
                                                                                                            Procedure 10000-C, which applies to Operations personnel, also
                                                                                                            had been revised to state that overtime should not be routinely
                                                                                                            scheduled. This portion of IFI 424/86-117-33 is closed.                                            l
                                                                                                                                                                                                                l
                                                                                                                                                                                                                <
w ____ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _                                                                      _  _ _ _ _ _ _ _ _ _ _ _ _ _
 
                                                                            .
r            ._
                                    38
  ii. (0 pen) Inspector Followup Item 424/87-01-02. Acceptance Criteria
      Reviews. The IFI involved the review of the licensee's procedures
      to assure that adequate administrative controls exist for review of
      acceptance criteria and determination that the acceptance criteria
      are met. This item is discussed in paragraph 7.a.8 of this report.
  jj. (Closed) Inspector Followup Item 424/87-01-03. Implementation of
      Controls to Assure Adequate MW0s and Assignment of Appropriate
      Functional Testing. The inspector had determined that a MWO did
      not designate the functional testing to be performed. In addition,
      the inspector noted that QA audits indicated recurring problems in
      the adequacy of MWO instructions and designation of functional tests.
      The inspector reviewed the corrective action taken by the licensee.
      This review is described in paragraph 8.c. of this report.      IFI
      424/87-01-03 is closed.
  kk. (0 pen) Inspector Followup Item 424/87-01-04.  Resolution of Concerns
      on the Seismic and Environmental Qualification (EQ) of Radiation
      Monitors. This IFI is discussed in paragraph 7.b.1 of this report.
  11. (Closed) Inspector Followup Item 424/87-01-05. Review of Temporary
      Modifications. This IFI is closed as discussed in paragraph 9. The
      IFI number will remain assigned to allow tracking of the item.
  mm. (0 pen) Inspector Followup Item 424/87-01-06. Miscellaneous Findings
      on Surveillance and Maintenance Procedure Implementation. The
      concerns, which are discussed in paragraph 7.b.3 of this report
      included equipment mislabeling and an inadequate lighting safety
      concern.  The items were determined to be isolated cases and have
      been corrected by the licensee. After obtaining additional informa-
      tion from the licensee, the fire doors and a wire radius bend concern
      were determined not to be issues. Therefore, with the exception of
      one item, discussed in paragraph 7.b.3, IFI 424/87-01-06 is closed,
  nn. (Closed) Inspector Followup Item 424/87-01-07.      Reference of
      Nonexistent Setpoint Document in Control Room ARP's. Control Room
      ARP's were found to reference a Master Setpoint Document that was
      used in lieu of giving the actual setpoint.    No one in either the
      Control Room or the operations department could produce or describe
      the document.    The licensee provided revised procedures for the
      following ARPs that had previously been noted as deficient.      The
      procedures no longer referenced the Master Setpoint Document. The
      procedures reviewed were 17001-1, Rev. 5; 17013-1, Rev. 3; 17014-1,
      Rev. 3; 17015-1, Rev. 2; 17016-1, Rev. 2; 17017-1, Rev.1; and,
      17020-1, Rev. 3. The inspector found that the revised procedures
      were incorporated into the control room copies.      The inspector
      determined that the ARP's in the control room no longer referenced
      the document. IFI 424/87-01-07 is considered closed.
  oo. (Closed) Inspector Followup Item 424/86-60-10. Shift Relief and
      Turnover. The item is discussed in paragraph 10.b.
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