ML20081E379

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Proposed Tech Specs Re Periodic Review of Station Procedures
ML20081E379
Person / Time
Site: Pilgrim
Issue date: 10/31/1983
From:
BOSTON EDISON CO.
To:
Shared Package
ML20081E250 List:
References
NUDOCS 8311020060
Download: ML20081E379 (2)


Text

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b. Reports of reviews encompassed by Section 6.5.B.7 e, f, g and h above, shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear,with a copy to the Station Manager within 21 days following the completion of the review.
c. Audit reports encompassed by Section 6.5.B.8 above shall be forwarded to the Senior Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURENCE ACTION The following actions shall be taken in the event of a reportable occurrence:

A. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

B. Each Reportable Occurrence Report'submilt'ad to the Commission shall be reviewed by the ORC and submitted to the NSRAC Chairman and the Station Manager.

6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

A. The provisions of 10 CFR 50.36(c) (1) (i) shall be complied with immediately.

B. The Safety Limit Violation shall be reported to the Commission, the Station Manager, and to the NSRAC Chairman immediately.

C. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the ORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

D. The Safety Limit Violation Report shall be submitted to the Commission, the NSRAC Chairman, and the Station Manager within 14 days of the violation.

6.8 PROCEDURES A. Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and '

recommendations of Section 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in 6.8.B and 6.8.C below.

B. Each procedure of 6.8.A above, and changes thereto, shall be reviewed by the ORC and approved by the ORC Chairman prior to implementation.

These procedures shalt be reviewed periodically as set forth in administrative procedures.

8311020060 831031 PDR ADOCK 05000293 - 216 -

P PDR Amendment No. 30, M , 69

b. Reports of reviews encompassed by Section 6.5.B.7 e, f, g and h above, shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear,with a copy to the Station Manager within 21 days following the completion of the review.
; c. Audit reports encompassed by Section 6.5.B.8 above shall be forwarded to the Senior Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURENCE ACTION The following actions shall be taken in the event of a reportable occurrence:

A. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

B. Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the ORC and submitted to the NSRAC Chainnan and the Station Manager.

1 6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

A. The provisions of 10 CFR 50.36(c) (1) (i) shall be complied with immediately.

B. The Safety Limit Violation shall be reported to the Commission, the Station Manager, and to the NSRAC Chairman immediately.

C. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the ORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

D. The Safety Limit Violation Report shall be submitted to the Commission, the NSRAC Chairman, and the Station Manager within 14 days of the violation.

6.8 PROCEDURES A. Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in 6.8.B and 6.8.C below.

B. Each procedure of 6.8.A above, and changes thereto, shall be reviewed by the ORC and approved by the ORC Chairman prior to implementation.

These procedures shall be reviewed periodically as set forth in administrative procedures.

8311020060 831031 PDR ADDCK 05000293 - 216 -

P PDR

' Amendment No. 30, M , M

NOTE: ORC review and approval of procedures for vendors / contractors, who have a QA Program approved by Boston Edison Company, is not required for work performed at the vendor / contractor facility.

C. Temporary changes to procedures of 6.8. A above may be made provided:

1. The intent of the original procedure is not altered.
2. The change is approved by two members of 'the plant management staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
3. The change is documented, reviewed subsequently by the ORC, and approved by the ORC Chairman within 7 days of implementation.

D. Written procedures to implement the Fire Protection Program shall be established, implemented and maintained.

6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.

A. Routine Reports

1. Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., in-itial criticality, completion of startup test program, and resump-tion or commencement of commerical power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

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