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{{Adams
#REDIRECT [[IR 05000621/2007020]]
| number = ML20134J342
| issue date = 08/14/1985
| title = Notice of Violation from Insp on 850621-0720
| author name =
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =
| addressee affiliation =
| docket = 05000369, 05000370
| license number =
| contact person =
| document report number = 50-369-85-23, 50-370-85-24, NUDOCS 8508290252
| package number = ML20134J339
| document type = NOTICE OF VIOLATION OF A REGULATION, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 2
}}
See also: [[see also::IR 05000621/2007020]]
 
=Text=
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                                                  ENCLOSURE 1
                                              NOTICE OF VIOLATION
            Duke Power Company                                    Docket Nos. 50-369 and 50-370
            McGuire Nuclear Station                              License Nos. NPF-9 and NPF-17
            The following violations were identified during an inspection conducted on
            June 21 - July 20, 1985. The Severity Levels _were assigned in accordance with
            the NRC Enforcement Policy (10 CFR Part 2, Appendix C).
            1.  Technical Specification (TS) 4.9.2 requires, for mode 6 operation, that each
                source range neutron flux monitor be demonstrated operable by the
                performance of an analog channel operational test within 8 hours prior to
                initial core alterations and at least once per 7 days.
                TS 4.0.4 declares that entry into an operational mode shall not be made
                unless the surveillance requirement associated with the limiting condition
                for operation have been performed within the ste.ted surveillance interval.
                Contrary to the above,
                a.    On May 1,1985, Unit 1 entered mode 6 without performing an analog
                      channel operation test on the source range monitors within the previous  '
                      seven days,
                b.    On May 6,1985, Unit 1 core alterations were begun without performing
                      an analog channel operational test on the source range monitors within
                      the previous eight hours.
                This is a Severity Level IV violation (Supplement I).
            2.  Technical Specification 6.8.1.a requires that current written approved
                procedures be established, implemented and maintained covering tnose
                surveillance tests required by Technical Specifications.        Implicit in the
                provisions of these requirements is the requirement that the procedures
                embody sufficient detail to facilitate the successful accomplishment of the
                task.
                Contrary to the above:
                a.    On July 12, 1985, during the performance of a manual reactor trip
                      surveillance test, the applicable procedure, PT-2-A-4600-56, Manual
                      Reactor Trip Functional Test, was not followed in that the feedwater
                        isolation reset switches were not depressed while tripping reactor trip
                      breaker as required. This resulted in an inadvertent feedwater
                        isolation.
          8508290252 850814 9
            DR ADOCK 050
 
  . . . ,
,,*        .
          Duke Power Company                          2        Docket Nos. 50-369 and 50-370
          McGuire Nuclear Station                              License Nos. NPF-9 and NPF-17
                b.    On July 12, 1985, during the performance of test PT-0-A-4601-08A, Solid
                      State Protection System Train A, the procedure was inadequate in detail
                      in that it did not specify the deactivation of the P-4 permissive prior
                      to closing the reactor trip breaker. This resulted in an inadvertent
                    -feedwater isolation.
                c..  On May 6,1985, a shift supervisor erroneously signed step 6.5 on
                      Enclosure 13.1 of' Unit 1 procedure MP-1-A-7150-41, Control Rod Drive
                      Shaft Latching and Unlatching, which stated that applicable surveil-
                      lance requirements of TS 3.9.2 has been met. The surveillance had not
                      been performed. This in turn led to a mode change without completing
                      prerequisites required by TS 4.0.4
                This is a Severity Level IV violation (Supplement I).
          3.    10 CFR 50, Appendix B, Criteria XVI as implemented by Duke Power Company
                Topical Report, Quality Assurance Program Duke-1-A, Amendment 7,              ,
                Section -17.2.16 requires that conditions adverse to quality be promptly      l
                identified and corrected.
                                                                                              l
                                                                                              ,
                Contrary to the above, on May 22, 1985, a QC inspector discovered a
                violation of the electrical separation of certain Unit 2 safety related
                cable yet no corrective action was taken until May 28, 1985.
                This is a Severity Level IV violation (Supplement I).
          Pursuant to 10 CFR 2.201, you are required to submit to this office within 30
          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.
                      AUG 141985
          Date:
                              _ _ _ _ __ _- -
}}

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