Letter Sequence Approval |
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MONTHYEARML13329A4811984-10-17017 October 1984
Rev 0 to Health Physics Procedure SO1-VII-8.5.1, Process Control Program
Project stage: Other
ML13324A4721984-11-0202 November 1984
Forwards Rev 0 to Health Physics Procedure SO1-VII-8.5.1, Process Control Program. Applicable Documents Reviewed & Approved by NRC Listed
Project stage: Other
ML13324A5321984-12-27027 December 1984
Informs That Preliminary Review of Process Control Program (PCP) Completed.Pcp Acceptable for Use on Interim Basis. Interim Approval Continued Until Final Review of PCP Completed
Project stage: Approval
ML13324A6311985-04-22022 April 1985
Forwards Safety Evaluation Supporting Util Use of Process Control Program as Referenced in Tech Spec 6.16
Project stage: Approval
ML13324A6331985-04-22022 April 1985
Safety Evaluation Supporting Util Use of Process Control Program W/Tech Spec 6.16
Project stage: Approval
ML13309B5331985-05-0101 May 1985
Advises That Chem-Nuclear,Inc Replaced by Nuclear Packaging, Inc as Vendor of Wet Radwaste Treatment Svcs.Nuclear Packaging,Inc Will Dewater Wet Radwaste for Shipment,Per TP-02-NP.Approval Requested by 850601
Project stage: Other
ML13324A6651985-06-0303 June 1985
Special Rept Providing Status of Change in Radwaste Solidification Sys.Solid Radwaste Sys Contract w/Chem-Nuclear,Inc expired.Chem-Nuclear Replaced by Nuclear Packaging,Inc
Project stage: Other
ML13309B5481985-06-11011 June 1985
Grants Interim Authorization to Proceed W/Dewatering of Spent Resin Per Rev 0 to Nupac Operations & Maint Procedure OM-17 & Rev 1 to Health Physics Procedure SO23-VII-8.5.1. Review of Nuclear Packaging TP-02-NP Continuing
Project stage: Approval
ML13324A6931985-08-0909 August 1985
Requests Approval to Use Pacific Nuclear Svcs,Inc in Place of Chem-Nuclear Sys,Inc for Solidification & Encapsulation of Wet Radwaste.Nrc Approval Needed by 851101 Because Potential Burial Site Limitations Take Effect in 1986
Project stage: Other
1985-04-22
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Text
-~l REG,4
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YUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-206 PROCESS CONTROL PROGRAM
1.0 INTRODUCTION
On August 27, 1984 the staff issued Amendment No. 79 to the Provisional Operating License (DPR-13) for the San Onofre Nuclear Generating Station, Unit No. 1. The amendment incorporated the Radiological Effluent Tech nical Specifications (RETS) into the San Onofre 1 Technical Specifica tions (TS).
Section 6.16 of the TS referenced a Process Control Program (PCP) and prescribed the methods for changing it.
2.0 EVALUATION By letter dated November 2, 1984, Southern California Edison Company (SCE, licensee) provided copies of the PCP.
The staff has reviewed the PCP and found that it uses documented and approved methods that are consistent with current NRC guidelines (issued January 1982).
The PCP is therefore approved for use with San Onofre 1 Technical Specification 6.16.
The acceptability of this PCP is based on currently available guidelines, but a future revision should address compliance with 10 CFR Part 61 when revised guidance becomes available.
3.0 CONCLUSION
S The San Onofre 1 PCP is approved for use with San Onofre 1 Technical Specification 6.16.
4.0 ACKNOWLEDGEMENT W..Meinke prepared this Safety Evaluation.
Dated:
April 22, 1985.
8505060021 850422 PDR ADOCK 05000206 P
PDR
