ML20134B515: Difference between revisions

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{{Adams
#REDIRECT [[IR 05000506/2006005]]
| number = ML20134B515
| issue date = 07/30/1985
| title = Notice of Violation from Insp on 850506-0605
| author name =
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =
| addressee affiliation =
| docket = 05000327, 05000328
| license number =
| contact person =
| document report number = 50-327-85-17, 50-328-85-17, NUDOCS 8508150655
| package number = ML20134B511
| document type = NOTICE OF VIOLATION OF A REGULATION, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 3
}}
See also: [[see also::IR 05000506/2006005]]
 
=Text=
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                                                                                      ENCLOSURE 1
                                                                                  NOTICE OF VIOLATION
      Tennessee Valley Authority                                                                Docket Nos. 50-327 and 50-328
      Sequoyah Units 1 and 2                                                                    License Nos. DPR-77 and DPR-79
      The following violations were identified during an inspection conducted on
      May 6 - June 5,1985.                                              The Severity Levels were assigned in accordance with the
      NRC Enforcement Policy (10 CFR Part 2, Appendix C).
      -1.            Technical Specification 6.8.1 requires that written procedures be
                    established, covering safety related activities referenced in Appendix A of
                      Regulatory Guide 1.33, Revision 2, February 1978.
                    a.  DPS0-SMI-10G, " Relay Functional Tests for Diesel Generator Protective
                          Relays," and MI-10.1, " Diesel Generator Inspection," were established
                          to implement Technical Specification surveillance requirements.
                          Contrary to the above, adequate procedures were not established in that
                          DPS0-SMI-1DG did not specify Emergency Diesel Generator (EDG)
                          local-remote switch position in the EDG cubical nor in the control room
                          prior to the completion of paragraph 9.A(4)4.1 and did not require that
                          controlled test equipment be used in the performance of step 9.A(3),
                    b.  SQM-24, " Torque and Limit Switch Settings for Motor-0perated Valves,"
                          was established to comply with the above requirement for maintenance
                          procedures on safety related equipment.
                          Contrary to the above, SQM-24 did not incorporate the limit switch
                          adjustment technique identified in MI-11.2, " Motor Operated Valve                                                                  '
                          Adjustment Guidelines," which resulted in damage to two safety related
                          valves and a reactor trip.
                    c.  SI-484, " Periodic Calibration of Reactor Vessel Level Instrumentation
                          System (RVLIS) and RCS Wide Range Pressure Channels (P-403, P-406)
                          (Refueling Outage)," was established to implement post modification
                          testing requirements.
                          Contrary to the above, SI-484 was not adequately established for
                          configuration control in that the procedure did not include measures to                                                              !
                          assure that a sensing line common to RVLIS and Reactor Coolant System
                          pressure transmitter PT-68-66 was isolated so as to preclude actuation                                                              I
                          of a pressure interlock for the Residual Heat Removal (RHR) isolation                                                                l
                          valves. This deficiency resulted in the unanticipated isolation of the
                          RHR system due to a high pressure signal sensed by the transmitter
                          during RVLIS fill, vent, and pressurization,
                    g815065585073o                                            '
                    g    ADOCK 050C03p7,
                                                                        PDR
        __-____-_-_            __ - ___ _ ___ - _-----_- ______-__-___.                                  ._  __ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
 
l      .      ,
        . ..
    ,
  .  .
            Tennessee Valley Authority              2                Docket Nos. 50-327 e.1d 328
            Sequoyah Units 1 and 2                                    License Nos. DPR-77 and 79
                The above examples constitute a Severity Level IV Violation.      This violation
                applies to both units. (Supplement I).
            2.  Technical Specification 6.11 requires that procedures for personnel radia-
                tion protection shall be prepared consistent with the requirements of
                10 CFR 20 and shall be approved, maintained and adhered to for all opera-
                tions involving personnel radiation exposure. These requirements are
                implemented by procedure RCI-1, " Radiological Hygiene Program," which
                requires each employee to adhere to Health Physics procedures and protective
                measures.  One protective measure, Radiation Work Permit (RWP) 1-85-105,
                required a canvas hood be worn in addition to other protective clothing
                while conducting activities in the Unit 1 containment radiation area.
                Contrary to the above, RWP 1-85-105 requirements were not implemented in
                that an individual was observed conducting activities in the Unit I contain-
                ment without the prescribed canvas hood.
                This is a Severity Level V violation.      This violation applies to Unit 1
                only.  (Supplement IV).
            3.  Technical Specification 6.8.1 states that written procedures shall be
                established, implemented and maintained covering the procedures referenced
                in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Proce-
                dure MI-10.1 was established to implement requirements for Emergency Diesel
                Generator surveillance testing.    MI-10.1 paragraph 5.3.1.2.2.5 requires
                technicians to set up test equipment prior to diesel engine start and
                paragraph 5.3.1.2.4 requires the technician to verify receipt of the " Engine
                Running" annunciation at 850 rpm engine speed.
                Contrary to the above, as of May 21, 1985, MI-10.1 was not implemented in
                that technicians did not set up their test equipment prior to engine start
                and the technician erroneously recorded 850 rpm as the annunciation speed
                when the annunciation actually energized at about 875 rpm.
                                                                                                  .
                This is a Severity Level V violation.  This violation applies to both units.
                (Supplement I).
            4.  Technical Specification 6.8.1 requires that written procedures be
                implemented covering activities referenced in Appendix A of Regulatory
                Guide 1.33, Revision 2, February 1978.
                Contrary to the above, Workplan No.11188, which was established to install
                the battery racks and battery cells for vital bottery V, was not implemented
                in that installation of the intercell spacers for vital battery V was not
                completed in accordance with the vendor drawings for installation of the
                battery racks as required by the workplan.
                This is a Severity Level V violation.  This violation applies to both units.
                (Supplement I).
                                                                                                  b
 
/          .
      * ''
  . :.
          Tennessee Valley Authority                3              Docket Nos. 50-327 and 328
          Sequoyah Units 1 and 2                                  License Nos. OPR-77 and 79
          Pursuant to 10 CFR 2.201, you are required to submit to this office within .,
          days of the date of this Notice, a written statement or explanation in reply,
          including: (1) admission or denial of the alleged violations; (2) the reasons
          for the violations if admitted; (3) the corrective steps which have been taken
          and the results achieved; (4) corrective steps which will be taken to avoid
          further violations; and (5) the date when full compliance will be achieved.
          Security or safeguards information should be submitted as an enclosure to
          facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)
          or 10 CFR 73.21.
          Date:    JUL 3 01905
}}

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