Letter Sequence Approval |
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Results
Other: ML13303B031, ML13305A890, ML13310B024, ML13310B548, ML13310B550, ML13310B673, ML13316A805, ML13316A866, ML13316B055, ML20081B573, ML20133A063, ML20205H689, ML20207N580, ML20212R628
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MONTHYEARML13310B0241983-10-17017 October 1983
Informs of Organizational & Personnel Changes Resulting from Jan 1980 Centralization of Nuclear Engineering & Operations Dept.Revs to Tech Specs Being Prepared for Future Submittal
Project stage: Other
ML13305A5371984-03-0707 March 1984
Forwards Application for Amend 24 to License NPF-10 & Amend 10 to License NPF-15.Amends Revise Tech Spec 4.8.1.1.2.C Re Level of Insolubles in Diesel Fuel Oil & Section 6 Re Organizational Changes
Project stage: Request
ML20081B5641984-03-0707 March 1984
Application for Amend 10 to License NPF-15,revising Tech Spec 4.8.1.1.2.C to Determine Operability of Diesel Generator Should Diesel Fuel Oil Fail to Meet Test for Insolubles & Revising Section 6 Re Organization Changes
Project stage: Request
ML20081B5731984-03-0707 March 1984
Proposed Revs to Tech Spec 4.8.1.1.2.C to Determine Operability of Diesel Generator Should Diesel Fuel Oil Fail to Meet Test for Insolubles & Proposed Revs to Section 6 Re Organizational Changes
Project stage: Other
ML13310B5501984-07-17017 July 1984
Amend Application 122 to License DPR-13,revising Tech Specs to Add Requirements Re Administration & Use of Unit Staff Overtime,Per Generic Ltrs 82-12 & 82-16
Project stage: Other
ML13310B5481984-07-17017 July 1984
Forwards Amend Application 122 to License DPR-13,changing Tech Specs to Reflect Staff Overtime & Administrative Requirements,Per Generic Ltrs 82-12 & 82-16.Fee Encl
Project stage: Other
ML13310B5511984-07-17017 July 1984
Proposed Changes to Tech Spec Section 6.2.2, Administrative Controls, to Add Requirements Re Administration & Use of Staff Overtime
Project stage: Request
ML13310B6731984-09-0404 September 1984
Proposed Tech Spec Table 3.5.10-1 Re Radiation Instrument Alarm Setpoint & Figures 6.2.1.1,5.2-1 & 6.2-1 Re Offsite Organization
Project stage: Other
ML13310B6691984-09-0404 September 1984
Revised Application to Amend Licenses DPR-13,NPF-10 & NPF-15,changing Tech Specs Re Offsite Organization & Radiation Instrumentation Setpoint
Project stage: Request
ML13310B6781984-09-0505 September 1984
Forwards Addl Info Re Proposed Change 127 to Tech Spec Table 3.5.7-1,in Response to 840723 Request
Project stage: Request
ML13310B6811984-09-0505 September 1984
Revised Proposed Change 127 to Tech Spec Table 3.5.7-1
Project stage: Request
ML13330A4421984-09-0707 September 1984
Forwards Request for Addl Info Re Proposed Changes to Tech Specs Concerning Onsite Organization,Review Responsibilities & Control Room Command Function.Meeting Will Be Scheduled in Future
Project stage: RAI
ML13330A1671984-11-30030 November 1984
Rev 1 to Proposed Change 119 to Tech Specs,Revising Administrative Controls on Staff Working Hours by Job Classification
Project stage: Request
ML13330A4591984-11-30030 November 1984
Application for Amend to License DPR-13,consisting of Rev 1 to Proposed Change 119 to Tech Specs Re Administrative Controls on Working Hours of Staff Job Classifications,Per NUREG/CR-1764
Project stage: Request
ML13324A5301984-12-27027 December 1984
Summary of 841211 Meeting W/Util Re Proposed Tech Spec Changes on Administrative Controls.List of Attendees Encl
Project stage: Meeting
ML13316A8031985-03-0606 March 1985
Forwards Amend 88 to License DPR-13 & Safety Evaluation. Amend Adds Administrative Guidance & Requirements Re Assignment of Overtime to Personnel Performing safety-related Activities
Project stage: Approval
ML13316A8051985-03-0606 March 1985
Amend 88 to License DPR-13,adding Administrative Guidance & Requirements Re Assignment of Overtime to Personnel Performing safety-related Activities
Project stage: Other
ML13316A8081985-03-0606 March 1985
Safety Evaluation Supporting Amend 88 to License DPR-13
Project stage: Approval
ML13331A8031985-04-12012 April 1985
Forwards Responses to Questions Re Proposed Change 130 & Proposed Tech Spec Section 6.0, Administrative Controls. Onsite & Offsite Organization Charts Revised
Project stage: Request
ML13311A3851985-04-12012 April 1985
Rev 0 to Energy Balance Method Verification
Project stage: Request
ML20133A0631985-08-0202 August 1985
Proposed Tech Specs Extending Time Period for Submittal of Semiannual Radioactive Effluent Release Rept for 90 Days
Project stage: Other
ML13316A8691985-10-15015 October 1985
Safety Evaluation Supporting Amend 91 to License DPR-13
Project stage: Approval
ML13316A8661985-10-15015 October 1985
Amend 91 to License DPR-13,approving Tech Spec Revs Re Administrative Controls,Including Reporting Requirements,Min Shift Crew Composition & Offsite Organization
Project stage: Other
ML13316A8641985-10-15015 October 1985
Forwards Amend 91 to License DPR-13 & Safety Evaluation. Amend Approves Tech Spec Revs Re Administrative Controls, Including Reporting Requirements,Min Shift Crew Composition & Offsite Organization
Project stage: Approval
ML13305A8901986-06-30030 June 1986
Rev 2 to Chemistry Procedure SO123-III-6.6, Diesel Fuel Oil Specs & Testing Requirements
Project stage: Other
ML20206U7991986-09-30030 September 1986
Revised Proposed Tech Spec Change PCN 192,in Response to Generic Ltr 84-15 Concerning Cold Fast Start Testing.Addl Justification Also Encl,Per 860814 Meeting
Project stage: Meeting
ML20207N5801987-03-0909 March 1987
Notice of Withdrawal for License Amend Request NPF-10/15-75. Amend Proposed Revs to Licenses NPF-10 & NPF-15 Re Determination of Diesel Generator Operability When Fuel Oil Fails to Pass Test for Insolubles
Project stage: Other
ML20207N5331987-03-0909 March 1987
Forwards Notice of Withdrawal of License Amend Request NPF-10/15-75 Proposing Amends to Licenses NPF-10 & NPF-15. Withdrawn Amend Proposed Revs to Tech Spec 4.8.1.1.2.c & Was Superseded by Util 860317 Application
Project stage: Withdrawal
ML20212R6281987-04-0909 April 1987
Amends 59 & 48 to Licenses NPF-10 & NPF-15,respectively, Reducing Frequency of Emergency Diesel Generator (EDG) Fast Starts,Revising Diesel Fuel Oil Surveillance & Reducing Number of EDG Tests
Project stage: Other
ML20212R6481987-04-0909 April 1987
Safety Evaluation Supporting Amends 59 & 48 to Licenses NPF-10 & NPF-15,respectively
Project stage: Approval
ML13331A9591987-08-27027 August 1987
Forwards Amend Application 145 to License DPR-13,consisting of Proposed Change 176,requesting Rev of Tech Specs to Be Consistent W/Recent Util Organizational Changes & Conflicts in Tech Spec Reporting Requirements.Fee Paid
Project stage: Request
ML13316B8271987-08-27027 August 1987
Proposed Tech Specs,Reflecting Recent Util Organizational Changes,Recent 10CFR50 Correspondence Requirements & Conflicts in Tech Spec Reporting Requirements & Revising Section 6.0 Re Audit Requirements
Project stage: Other
ML13331A9631987-08-27027 August 1987
Amend Application 145 to License DPR-13,consisting of Proposed Change 176,modifying Tech Specs to Be Consistent W/ Util Organizational Changes & 10CFR50 Correspondence Requirements & Revising Audit Requirements
Project stage: Request
ML13331A2521988-04-0101 April 1988
Provides Rept on Conditions Identified During Inservice Insp of Steam Generator Tubing.Of Total of 7,425 inspected,169 Tubes Were Removed from Svc by Mechanical Plugging.Remedial Action Taken to Resolve Tube Degradation Appropriate
Project stage: Other
ML13330B2931988-04-15015 April 1988
Requests Submittal of Application for Amend to License DPR-13 for NRC Approval to Leave Tubes W/Defects Unplugged within 60 Days & Details Re Nonprogression of Intergranular Attacks within 30 Days,Per Util Feb-Mar 1988 Tube Insp
Project stage: Approval
ML13316B0551988-08-0303 August 1988
Amend 105 to License DPR-13,revising Tech Specs to Be Consistent W/Recent Util Organizational Changes & Recent 10CFR50 NRC Correspondence Requirements
Project stage: Other
ML13316B0561988-08-0303 August 1988
Safety Evaluation Supporting Amend 105 to License DPR-13
Project stage: Approval
ML13316B0521988-08-0303 August 1988
Forwards Amend 105 to License DPR-13 & Safety Evaluation. Amend Incorporates Recent Organizational Changes & Reflects Recent 10CFR50 NRC Correspondence Requirements.Changes Re Onsite & Offsite Organization Charts Not Included
Project stage: Approval
ML20205H6891988-10-18018 October 1988
Corrected Amends 68 & 57 to Licenses NPF-10 & NPF-15, Respectively,Deleting Onsite & Offsite Organization Charts & Revising Reporting Responsibility of Independent Safety Engineering Group & Nuclear Safety Group
Project stage: Other
ML13303B0311989-04-12012 April 1989
Advises That Proposed Change PCN-83 to Licenses NPF-10 & NPF-15,revising Section 6, Administrative Controls Withdrawn,In Response to Util Requests.Fr Notice of Withdrawal Will Be Prepared
Project stage: Other
ML13303B0911989-04-25025 April 1989
Forwards Notice of Withdrawal of 840307 Application for Amends to Licenses NPF-10 & NPF-15,revising Administrative Controls of Tech Specs to Reflect Changes in Util Organizational Structure
Project stage: Withdrawal
ML20245J6161989-04-25025 April 1989
Notice of Withdrawal of 840307 Application for Amends to Licenses NPF-10 & NPF-15,revising Tech Specs to Reflect Changes in Util Organizational Structure & to Incorporate New NRC Reporting Requirements
Project stage: Withdrawal
1985-08-02
[Table View] |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 105 TO FACILITY OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT NO. 1 DOCKET NO 50-206
1.0 INTRODUCTION
By letter dated August 27, 1987, Southern California Edison Company (SCE or the licensee) requested amendments to the Technical Specifications appended to Facility Operating License No. DPR-13 for the San Onofre Nuclear Generating Station Unit No. 1. The proposed amendments would revise the San Onofre Nuclear Generating Station Unit 1 Technical Specifications to be consistent with recent SCE organizational changes and recent 10 CFR Part 50 NRC correspondence requirements, resolve conflicts in the technical specification reporting requirements and revise Audit requirements.
2.0 EVALUATION A. The revised Section 6.2.2 deletes the Manager of Nuclear Generation Services and Deputy Station Manager approval for overtime deviation due to organizational changes. The revised Section 6.8.2 deletes the Manager of Nuclear Generation and Deputy Station Manager approval for programs and procedures, due to organizational changes. These changes are acceptable.
B. The change to Technical Specification Sections 3.5.8, 3.5.9, 3.18.3 and 3.19 reflects the deletion of reference to a portion of Section 6.0 that was deleted previously. This does not represent any significant change to the Technical Specification and, therefore, is acceptable.
C. The change to Technical Specification Sections 3.15.2, 3.15.3, 3.16.2, 3.16.3, 3.16.4, 3.17, 3.18.1 and 3.18.2 reflects the revision to the Special Reporting requirements and resolves the inconsistency with 10 CFR Part 50 requirements. In some cases, a Licensee Event Report (LER) is directed to be submitted by the technical specifications; however, the references are not appropriate since 10 CFR Part 50 contains criteria for submitting LERs. In addition, the Technical Specifications, in some instances, direct that the LER be replaced by a Special Report. The 10 CFR Part 50 requirements must be complied 8608240683 880803 PDR ADOCK 05000206 P
PNU
-2 with and it is not appropriate that exceptions be taken or they be superseded by technical specifications. This does not represent any significant change to the Technical Specifications and therefore is acceptable.
D. The change to Technical Specifications Sections 4.2.3 and, 4.16.E reflects the revision that replaces a reference to Section 6.6 with a reference to Section 6.9.2 and provides for consistency in the technical specification reference to Section 6.9.2 Special Report requirements. This does not represent any significant change to the Technical Specification and therefore is acceptable.
E. The change to Technical Specification Section 4.14F reflects the revision to replace a reference to subsection 6.10.2.k which has been deleted by a previous amendment with a reference to Section 6.10.2.
This does not represent any significant change to the Technical Specification and therefore is acceptable.
F. The change to Technical Specification Section 4.19 revises section 4.19b reference to Section 6.12 to Section 6.13. This numbering change resolves a conflict introduced by Amendment No. 91.
In addition, a minor format change for consistency with the standard Technical Specification format is also reflected. These changes do not represent any significant change to the Technical Specification and, therefore, are acceptable.
G. The change to Technical Specification Section 6.5.3.5 revises subsections 6.5.3.5.a, c and d by deleting the word "all".
This change is not intended to limit the scope of audits; it is intended, however, to allow audit personnel to perform audit on a schedule and to a level of detail required by current performance, commensurate with past experience and consistent with practices in other areas.
All provisions contained within the Technical Specifications and applicable license conditions are still subject to audits, however; the areas to be audited will be determined by the Nuclear Safety Group.
This does not represent any significant change to the Technical Specification and therefore, is acceptable.
H. The change to Technical Specification Sections 6.9.1.10, 6.9.2 and 6.16 reflect the revision of reporting requirements to make them consistent with 10 CFR 50.4 revisions. The reference to Distribution of Reports is not appropriate in the Technical Specification since 10 CFR Part 50 contains the criteria including distribution, number of copies, etc. for submitting NRC required reports. This does not represent any significant change to the Technical Specifications and therefore is acceptable.
In summary, the above changes are administrative in nature and are primarily necessary to resolve inconsistencies in the Technical Specifications.
The revision to the audit requirements section is not expected to reduce the audit effectiveness since the result is that problem areas will receive additional audit attention.
-3
3.0 ENVIRONMENTAL CONSIDERATION
These amendments relate to changes in recordkeeping, reporting, or admini strative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Charles M. Trammell Dated: August 3, 1988
