Letter Sequence Request |
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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
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
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
ML13310B3901984-05-0101 May 1984
Forwards Amend Application 117 to License DPR-13,consisting of Proposed Change 130,revising Tech Specs to Reflect Recent Organization Changes & Incorporating Revs Requested in Generic Ltr 83-43.Fee Encl
Project stage: Request
L-83-043, Amend Application 117 to License DPR-13,consisting of Proposed Change 130,revising Tech Specs to Reflect Recent Organization Changes & Incorporating Revs Requested in Generic Ltr 83-431984-05-0101 May 1984
Amend Application 117 to License DPR-13,consisting of Proposed Change 130,revising Tech Specs to Reflect Recent Organization Changes & Incorporating Revs Requested in Generic Ltr 83-43
Project stage: Request
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
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
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
ML13310B6341984-08-16016 August 1984
Application for Amend to License DPR-13,changing Tech Specs Re Max Reactor Coolant Activity,Leakage,Safety Injection Sys Hydraulic Valve Testing,Reactivity Anomalies & Miscellaneous Radioactive Matls Sources
Project stage: Request
ML13310B6371984-08-16016 August 1984
Proposed & Existing Tech Specs Re Max Reactor Coolant Activity,Leakage,Safety Injection Sys Hydraulic Valve Testing,Reactivity Anomalies & Miscellaneous Radioactive Matls Sources
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
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
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
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
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
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
ML13331A8181985-07-0101 July 1985
Revised Tech Spec Pages Delaying Implementation of 850412 Proposed Change 130 Revising Time Period for Submittal of Radioactive Effluent Release Rept from 60 to 90 Days
Project stage: Request
ML13331A8151985-07-0101 July 1985
Requests Delay in Implementation of Proposed Change 130 to Tech Specs,Revising Time Period for Submittal of Semiannual Radioactive Effluent Release Rept from 60 to 90 Days.Revised Tech Specs Encl
Project stage: Request
ML13331A8211985-07-31031 July 1985
Revised Tech Spec Section 6.15,allowing Major Changes to Radwaste Treatment Sys to Be Reported in Monthly Operating Rept
Project stage: Other
ML13331A8191985-07-31031 July 1985
Application to Amend License DPR-13,revising Tech Spec Section 6.15 to Allow Major Changes to Radwaste Treatment Sys to Be Reported in Monthly Operating Rept
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
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
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
ML13316A8691985-10-15015 October 1985
Safety Evaluation Supporting Amend 91 to License DPR-13
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
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
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
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
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
ML13316B0561988-08-0303 August 1988
Safety Evaluation Supporting Amend 105 to License DPR-13
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
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
1985-03-06
[Table View] |
Text
wM Southern California Edison Company P. 0. BOX BOO 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M.O. MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING (213) 572-1749 September 4, 1984 Director, Office of Nuclear Reactor Regulation Attention: D. G. Elsenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-206, 50-361 and 50-362 Revisions to Proposed Changes San Onofre Nuclear Generating Station Units 1, 2 and 3 By letters dated July 9, 1984 and May 1, 1984 we provided Proposed Change Nos. 125 and 130 to the San Onofre Unit 1 Technical Specifications.
Our letter of March 7, 1984 provided Proposed Changes NPF-10-83 and NPF-15-83 to the San Onofre Units 2 and 3 Technical Specifications. Recent changes to the offsite organization and a review of procedures necessary to implement a proposed San Onofre Unit 1 Technical Specification revision, have resulted in the need to further modify these proposed changes currently under your review.
A revision to Proposed Change No. 130 to the San Onofre Unit 1 Technical Specifications and Proposed Changes NPF-10-83 and NPF-15-83 to the San Onofre Units 2 and 3 Technical Specifications is required to reflect changes to the offsite portion of the organization responsible for San Onofre Nuclear Generating Station. The offsite organization in the proposed changes, shown in Enclosure 1, should be revised as shown in Enclosure 2. The Senior Vice President now has the Vice President and Site Manager, Nuclear Generation Site and the Vice President, Nuclear Engineering, Safety and Licensing also reporting to him. Proposed Change No. 130 to the San Onofre Unit 1 Technical Specifications should also be revised to show the San Onofre Unit 1 Project Manager now reporting to the Manager, Nuclear Generation Services in the Nuclear Generation Site Department.
A revision to Proposed Change No. 125 to the San Onofre Unit 1 Technical Specifications is required to provide an appropriate radiation instrumentation setpoint. The high range containment radiation monitors (R-1255, R-1257), as indicated in proposed Table 3.5.10-1 (Enclosure 3) have a proposed alarm setpoint of 1 R/hr. The alarm setpoint should be revised to be 10 R/hr (Enclosure 4).
This revision is required because 1 R/hr is the lowest end of the measurement capability of these monitors and the alarm setpoint cannot be reset after an alarm. The revision to 10 R/hr is acceptable because the purpose of these monitors is to monitor potential post-accident containment radiation which may exceed the range of the normal containment radiation monitors.
4 00 4
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Mr. D.
September 4, 1984 The revisions requested in this letter are administrative in nature and are made to update proposed changes currently under your review.
Therefore, a special Amendment Application for the requested revisions is not required.
If you have any questions regarding the above discussed information, please let me know.
Very truly yours, Enclosures cc:
- 3. B. Martin, Administrator, NRC Region V E. McKenna, NRR Project Manager H. Rood, NRC Project Manager A. E. Chaffee, USNRC Resident Inspector
ENCLOSURE 1
