ML20010J184
| ML20010J184 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/29/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010J142 | List: |
| References | |
| 50-302-81-11, NUDOCS 8109290676 | |
| Download: ML20010J184 (3) | |
Text
{{#Wiki_filter:. JUL 2 91981 APPENDIX A NOTICE OF VIOLATION Florida Powar Corporation Docket No. 50-302 Crystal River 3 License No. DPR-72 As a result of the inspection conducted on May 26 through June 26, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980), the following violations were identified. A. Technical Specification 6.8.1 requires written procedures to be established and implemented covering applicable activities recommended in Appendix "A" of Regulatory Guide 1.33. Regulatory Guide 1.33, Appendix A, Section H.2 requires written procedures for each surveillance test listed in the Technical Specification. Technical Specification 4.3.3.6, Table 4.3-7 requires a monthly channel check on the pressurizer power operated relief valve (PORV) and code safety valve position indicators. Contra y to the above, as of June 25, 1981, a procedure had not been approved and implemented, and monthly channel checking had not been performed on the PORV and code safety valve position indicators. This is a Severity Level V Violation (Supplement I.E.). B. Technical Specification 6.5.2.8 requires the Nuclear General Review Committee (NRCC) to review the following items: a. The safety evaluations for 1) changes to procedures, equipment or l systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR 50, to verify that such actions did not constitute an unreviewed safety question. b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR. c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59,10 CFR. d. Proposed changes in Technical Specifications or this Operating License. 0109290676 810922 PDR ADOCK 05000302 O PDR
JUL 2 91981 Florida Power Corporation 2 Docket No. 50-302/81-11' Notice of Violation License No. DPR-72 e. Violations of codes, ragulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance, f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety. g. Events requiring 24 hour written notification to the Commission. h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components. 1. Reports and meetings minutes of the Plant Review Committee. Contrary to the above, during the period of April 30, 1981 through May 13, 1981, the NGRU assigned individual NGRU members of one-man subcommittees to accomplish these reviews. The results of these one-man subcommittee reviews were then presented to the full NGRU in a summarized form consisting of titles of the items reviewed and lacking any details for committee review, therefore eliminating the review of item details by members with expertise in other disciplines. This is a Severity lavel V Violation (Supplement I.E.). C. Technical Specification 6.5 specifies the requirements for the review and audit function of the Plant Review Committee (PRC). Specific sections of the Specification require the following: Specification 6.5.1.3 requires all alternate members to the PRC to be-appointed on a temporary basis in writing by the PRC Chairman and that no more than two alternates serve as voting members at any one time; Specification 6.5.1.5 requires that a quorum of the PRC consist of the Chairman or his designated alternate and four members (two of whom may be alternates). Specification 6.5.1.6.e requires the PRC to review all violations of Technical Specifications, including those identified by internal audits or NRC inspections. Contrary to the 6bove, during the period October 14, 1980, through May 10, 1 1981, the following PRC meetings were conducted without a quorum and without designating alternates for the meeting in writing: 80-41, 80-47, 81-1, 81-2, 81-4 through c.1-8, and 81-18. 1
Florida Power Corporation 3 Docket No. 50-302/81-11 Notice of Violation License No. DPR-72 Contrary to the above, durinc the period June 1980, through May 1981, the PRC has not reviewed any fechnical Specification violations either ' identified through internal audits or through NRC Inspectors. This is a Severity Level V Violation (Supplement I.E.). Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged viola-tions; (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. Consideration may be given to extending your response time for good cause shown. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shal' be submitted under oath or affirmation. bb Date: .ve e =}}