ML19317G815
| ML19317G815 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G810 | List: |
| References | |
| NUDOCS 8004010643 | |
| Download: ML19317G815 (3) | |
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s UNITED STATES flUCLEAR REGULATORY CO T.* *."!SS IO N WASHINGTON. D.
C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION-SUPPORTING AMENDMENT NO. 2 TO FACILITY LICENSE NO. DPR-54 CHANGE NO. 2 TO TECHNICAL SPECIFICATIONS i
SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION, UNIT 1 DOCKET NO. 50-312 Introduction By 1ctters dated December 12, 1974 and October 3, 1975, Sacramento Municipal Utility District proposed changes to the Technical Specifications appended to Facility Operating License No. DPR-54, for the Rancho Seco Nucicar Generating Station, Unit 1.
The proposed changes involve changes to the administrative controls including changes to the reporting requirements.
Discussion The proposed changes would be administrative in nature and would affect the conduct of operation. The proposed changes are intende( to provide uniform license requirements. Areas covered by the proposed uniform specifications include licensee staffing qualifications and management procedures involved with operating the reactor, reporting requirements, abnormal occurrence definition change, and a respiratory protection program.
Members of the facility staff should meet the requirements set forth in Guide 1.8, " Personnel Selection and Training" which endorses proposed ANSI N18.1, which was subsequently issued as ANSI N18.1-1971. Provisions for independent review of facility operations should be in accord with Guide 1.33, " Quality Assurance Program Requirements" which endorses proposed standard ANS 3.2, which was subsequently issued as ANSI 18.7-1972.
In Section 208 o'f the Energy Reorganization Act of 1974 " abnormal occurrence" is defined as an unscheduled incident or event which the Commission determines is significant from the standpoint of public health or safety. The term " abnormal occurrence" is reserved for usage by NRC.-
Regulatory Guide 1.16, " Reporting of Operating Information -
Appendix A Technical Specifications," Revision 4, enumerates required 1
9 04 01 EY3
reports consistent with Section 208..The proposed change to required reports identifies the reports required of all-licensees not already identified by the regulations and those unique to this facility. The proposal would formalize present reporting and would delete any reports no longer needed for assessment of safety related activities.
In add.ition, a ' radiation protection program delineates use of respiratory equipment in the event personnel are to be exposed to concentrations in excess of Part 20 concentrations. A requirement also has been added for pressurizer level instrumentation operability during reactor operation.
Evaluation The new guidance for reporting operating information does not identify any event as an " abnormal occurrence." The proposed reporting require,
ments also delete reporting of information no longer required and duplication of reported information. The standardization of required reports and desired format for the information will permit more rapid recognition of potential prob 1 cms.
Identifying minimum acceptabic qualifications for facility personnel should assure capabic performance from the facility staff. - Other administrative requirements also restated by the specifications assure uniformity and conformance to the desired features in the review, staffing, and procedures.
Incorporating the currently accepted respiratory protection program at this time assures that a consistent method of using respira-tory equipment is immediately availabic whenever needed. Similar changes are being approved fgr all power reactor licensees, so all licensees will have the same requirements presented in a uniform manner.
In addition to revising the administrative controls, we have made several editorial modifications and added a requirement for pressurizer level instrumentation during reactor operation. 'These changes, which were made at the licensee's request, provide consistency and add a restriction which did not previously exist They are therefore acceptable.
During our review of the proposed changes, we found that certain modi-fications to the proposal were necessary to have conformance with the desired regulatory position. These changes were discussed with the
-licensee's staff and have been incorporated into the proposal.
We have concluded that the proposal as modified improves the licensee's program for evaluating plant performance and the reporting of the operating information needed by the Commission to assess safety related activities and is acceptable. The facility staff qualifications and training program' conform to Regulatory Guide 1.8 and_ therefore are acceptable.
The administrative procedures and facility review and audit are, consistent with Regulatory Guide 1.33 and are acceptable. The modified reporting program is consistent with thespidance provided by Regulatory Guide 1.16, 'IReporting of Operating Information - Appendix A Technical Specifications," Revision 4.
The administrative controls are consistent with requirements being incorporated in Technical Specifications for new licensed facilities.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the change.does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: CEC. 3 1 1975
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