Letter Sequence Other |
|---|
TAC:55652, (Approved, Closed) TAC:61468, (Approved, Closed) TAC:65361, (Open) TAC:65374, (Approved, Closed) TAC:65685, (Open) TAC:66006, (Approved, Closed) TAC:66377, (Approved, Closed) TAC:66415, (Approved, Closed) TAC:66418, (Approved, Closed) TAC:66419, (Approved, Closed) |
|
MONTHYEARML19322C6631979-02-0202 February 1979 Forwards Memo Announcing Radical Change in Ofc of Executive Legal Director Activities Re OL Amend Applications Project stage: Other ML19322C6651979-02-0202 February 1979 Discusses Revised Procedure for Ofc of Executive Legal Director Involvement in Processing OL Amend Applications. Review of Safety Evaluations & Eias Re Proposed OL Amends Will Be Discontinued as of 790215 Project stage: Approval ML20096C6401984-08-27027 August 1984 Forwards Application to Amend License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys Project stage: Request ML20096C6631984-08-27027 August 1984 Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys.Fee Paid Project stage: Request ML20096C6821984-08-27027 August 1984 Proposed Tech Specs Reflecting Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys Project stage: Other ML20101N4281984-12-11011 December 1984 Amend 79 to License NPF-3,changing Tech Spec Table 3.6-2 Re Containment Isolation Valve to Allow for Modified Steam Generator Blowdown & Drain Sys Project stage: Other ML20101N4481984-12-11011 December 1984 Safety Evaluation Supporting Amend 79 to License NPF-3 Project stage: Approval ML20140D1451986-01-22022 January 1986 Forwards Application for Amend to License NPF-3,changing Tech Specs Clarifying Station Review Board Duties & Responsibilities.Separate Amend Application Being Prepared to Address Addl Administrative Changes.Fee Paid Project stage: Request ML20140D1741986-01-22022 January 1986 Application for Amend to License NPF-3,changing Tech Specs to Clarify Station Review Board Duties & Responsibilities Project stage: Request ML20140D1911986-01-22022 January 1986 Proposed Tech Specs,Clarifying Station Review Board Duties & Responsibilities Project stage: Other ML17346B2411986-10-20020 October 1986 Proposed Tech Specs Requiring 18-month Insp of Diesel Generator Be Performed During Next Unit 3 Refueling Outage Project stage: Other L-86-433, Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Specs to Require That 18-month Insp of Each Diesel Generator Be Performed During Next Unit 3 Refueling Outage. Fee Paid1986-10-20020 October 1986 Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Specs to Require That 18-month Insp of Each Diesel Generator Be Performed During Next Unit 3 Refueling Outage. Fee Paid Project stage: Request ML17347A1531986-11-10010 November 1986 Amend 120 to License DPR-31 & Amend 114 to DPR-41,revising Tech Spec 4.8.1.c.1 to Permit one-time Deferral of Insp of Both Diesel Generators Until Unit 3 Outage in Mar 1987 Project stage: Other B12414, Application for Amend to License NPF-49,extending 18-month Surveillance Testing Requirements for Diesel Generator Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2,on one-time Basis1987-01-30030 January 1987 Application for Amend to License NPF-49,extending 18-month Surveillance Testing Requirements for Diesel Generator Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2,on one-time Basis Project stage: Request ML20209H9171987-01-31031 January 1987 Proposed Tech Specs,Extending Diesel Generator 18-month Surveillance Requirements Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2 on one-time Basis Project stage: Other B12448, Submits Addl Info Re 870130 Application for Amend to License NPF-49,revising Tech Specs to Extend Diesel Generator 18-month Surveillance Testing Requirements,Per 870224 Telcon1987-03-0606 March 1987 Submits Addl Info Re 870130 Application for Amend to License NPF-49,revising Tech Specs to Extend Diesel Generator 18-month Surveillance Testing Requirements,Per 870224 Telcon Project stage: Request ML20215K3801987-05-0404 May 1987 Requests Reissuance of Table 3.6-2, Containment Isolation Valves of Tech Spec 3/4.6.3,correcting Typos in 840911 Application to Amend License NPF-3 Project stage: Request ML20215L8391987-05-0404 May 1987 Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d Project stage: Other ML20215L8351987-05-0404 May 1987 Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d Re Auxiliary Feedwater Sys as Result of 850609 Loss of Feedwater Event. Supporting Documentation Encl Project stage: Request ML20215L8141987-05-0404 May 1987 Forwards Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d to Reflect Mods to Steam Line Piping to Auxiliary Feed Pump Turbine Following 850609 Loss of Feedwater Event.Fee Paid Project stage: Request ML20214K7551987-05-20020 May 1987 Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection to Implement Guidance of Generic Ltr 86-10 & to Transfer Fire Protection Program to Updated SAR Project stage: Request ML20214K7241987-05-20020 May 1987 Forwards Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection to Assist in Transfer of Fire Protection Program to Updated Sar,Per Generic Ltr 86-10.Fee Paid Project stage: Request ML20214K7721987-05-20020 May 1987 Proposed Changes to Tech Specs Re Fire Protection to Assist in Transfer of Fire Protection Program to Updated Sar,Per Generic Ltr 86-10.Safety Evaluation & Significant Hazards Consideration Encl Project stage: Request ML20216H6041987-06-25025 June 1987 Advises That Based on B&W Analytical Studies for Primary Sys Blowdown Using RELAP5,use of Blowdown Valves Not Practicable for Feed & Bleed,Per 851204 Commitment.Listed Proposed Mods Will Be Implemented to Enhance Makeup Sys Project stage: Other ML20237G2591987-08-0707 August 1987 Proposed Tech Specs,Removing All Safety Features Actuation Sys Response Times & Containment Isolation Time Requirements from Valves on Secondary Side of Steam Generators Project stage: Other ML20237F8171987-08-0707 August 1987 Application for Amend to License NPF-3,removing All Safety Features Actuation Sys Response Times & Containment Isolation Time Requirements in Tech Specs 3/4.3.2 & 3/4.6.3 Project stage: Request ML20237F8041987-08-0707 August 1987 Forwards Application for Amend to License NPF-3,removing Safety Features Actuation Sys Response Times & Containment Isolation Time Requirements from Valves on Secondary Side of Steam Generators.Fee Paid Project stage: Request ML20237K8441987-08-28028 August 1987 Requests That Revised Tech Spec 6.5.1.6,submitted w/870122 License Amend Request,Reflects Station Review Board Responsibility to Review safety-related Aspects of Proposed Procedures,Mods,Tests & Experiments,Per NUREG-0103,Rev 4 Project stage: Other ML20150B9711987-09-11011 September 1987 Discusses Plant Organizational Changes.Meeting W/E Butcher & Bryan Should Be Set Up Project stage: Meeting ML20235W1271987-10-0909 October 1987 Application for Amend to License NPF-3,revising Tech Specs to Allow one-time Extension of 18 Month Surveillance Interval for Insp & Operability Testing of Emergency Diesel Generators Project stage: Request ML20235W1121987-10-0909 October 1987 Forwards Application for Amend to License NPF-3.Amend Revises Tech Specs to Allow one-time Extension in 18 Month Surveillance Interval for Insp & Operability Testing of Emergency Diesel Generators.Fee Paid Project stage: Request ML20235W1291987-10-0909 October 1987 Proposed Tech Specs,Allowing one-time Extension of 18 Month Emergency Diesel Generator Surveillance Interval Project stage: Other ML20236H0211987-10-27027 October 1987 Proposed Tech Specs,Changing Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods Project stage: Other ML20236G9801987-10-27027 October 1987 Application for Amend to License NPF-3,revising Tech Spec Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods.Fee Paid Project stage: Request ML20236X8331987-12-0707 December 1987 Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection Project stage: Request ML20236X8591987-12-0707 December 1987 Proposed Tech Specs Re Fire Protection Project stage: Other ML20236X8221987-12-0707 December 1987 Forwards Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection Per Generic Ltr 86-10 Project stage: Request ML20237B0401987-12-0808 December 1987 Safety Evaluation Supporting Amend 105 to License NPF-3 Project stage: Approval ML20237B0271987-12-0808 December 1987 Amend 105 to License NPF-3,revising Tech Specs to Extend Due Dates for Performing Tests & Insps Required by Surveillance Requirement by Correctly Referring to Safety Features Actuation Sys Test Signal Project stage: Other ML20237A6881987-12-0808 December 1987 Informs of Changes Necessary to Support Fifth Refueling Outage in Feb 1988.Key Amend Requests Placed Into 1 of 3 Listed Categories.Nrc Should Allocate Necessary Resources to Provide Timely Support for Review & Issuance of Amends Project stage: Other ML20236Y3421987-12-0808 December 1987 Forwards Application for Amend to License NPF-3,revising Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 Re Containment Sys & Containment Leakage.Fee Paid Project stage: Request ML20238E5701987-12-28028 December 1987 Provides Clarification to 860122 Application for Amend to License NPF-3 Re Station Review Board Responsibilities,Per 871127 & 1202 Telcons W/Aw Deagazio & Staff,Respectively, Revising Tech Specs 6.5.1.6(b) & 6.5.3.1(a),(b),(d) & (E) Project stage: Supplement ML20149J9641988-02-10010 February 1988 Environ Assessment & Finding of No Significant Impact Based on Util 871207 Application for Amend to License NPF-3, Updating Tech Specs to Reflect Current Plant Design,Testing & Compensatory Measures Re Fire Protection Features Project stage: Other ML20149J0571988-02-17017 February 1988 Provides Addl Clarification of License Amend Request Submitted on 860122 Involving Proposed Tech Spec 6.5.3.1(c). Clarified Administrative Control Will Require Technical Reviews on Each Mod Affecting Nuclear Safety Project stage: Other ML20150B0321988-03-0707 March 1988 Forwards Application for Amend to License NPF-3 Changing Tech Spec Section 4.6.1.2.a to Allow Third Type a Test & 10-yr Inservice Insps to Be Uncoupled & Performed in Separate Refueling Outages.Fee Paid Project stage: Request ML20150C4731988-03-0909 March 1988 Notice of Denial of Amend to License NPF-3 Re Deleting Requirement in Tech Spec 6.5.1.6.e Concerning Station Review Board Responsibility to Investigate & Rept Tech Spec Violations Project stage: Other ML20150C4621988-03-0909 March 1988 Safety Evaluation Supporting Amend 109 to License NPF-3 Project stage: Approval ML20150C4511988-03-0909 March 1988 Amend 109 to License NPF-3,revising Responsibilities & Authority of Station Review Board & Adding Section to Technical Review & Control Project stage: Other ML20150B9671988-03-11011 March 1988 Requests That Encl 870911 Memo from J Scinto Be Included in Docket Files.Memo Relates to 870122 Application for Amend to License NPF-3 Re Organization Changes Project stage: Other ML20148B1781988-03-14014 March 1988 Amend 110 to License NPF-3,revising Tech Specs to Permit Extension of Range of RCS Pressure Instrument on Auxiliary Shutdown Panel to 3,000 Psig from 2,500 Psig & Tech Spec 3.3.3.5,Table 3.3-9,Item 3 Project stage: Other 1987-12-08
[Table View] |
Informs of Changes Necessary to Support Fifth Refueling Outage in Feb 1988.Key Amend Requests Placed Into 1 of 3 Listed Categories.Nrc Should Allocate Necessary Resources to Provide Timely Support for Review & Issuance of Amends| ML20237A688 |
| Person / Time |
|---|
| Site: |
Davis Besse  |
|---|
| Issue date: |
12/08/1987 |
|---|
| From: |
Shelton D TOLEDO EDISON CO. |
|---|
| To: |
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
|---|
| References |
|---|
| 1435, TAC-55652, TAC-61468, TAC-65361, TAC-65374, TAC-65685, TAC-66006, TAC-66377, TAC-66415, TAC-66418, TAC-66419, NUDOCS 8712150174 |
| Download: ML20237A688 (7) |
|
Text
.
e(
-'R TDLEDO
%smEDISON DONALO C. SHELTON Vos Preedent-Near l419} 249 2399 Docket No. 50-346 License No. NPF-3 Serial No. 1435 l
December 8, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Subject:
Request for NRC Staff Action on License Amendment Requests Gentlemen:
I The Davis-Besse Nuclear Power Station Unit No. 1 is presently scheduled to commence its fifth refueling outage (5RFO) in February, 1988.
In addition to the refueling activities, significant modifications, inspections and tests are planned which will require the revision j
of a license condition and certain Operating License Appendix A, Technical Specifications. The purpose of this letter is to alert j
the NRC Staff as to the changes necessary in supporting the SRF0, and the Technical Specifications changes presently under NRC Staff l
review which have significant impact on plant operation. To avoid adverse impact on scheduled activities, Toledo Edison requests that the NRC Staff allocate the necessary resources to provide timely support for the review and issuance of these Davis-Besse license amendments.
Toledo Edison has reviewed its submitted and planned-to-be submitted r
license amendment requests. Key amendment requests have been placed into one of three categories:
A) " Required" License Condition, Technical Specification and Bases changes for the SRF0, B) " Desired" Technical Specification and Bases changes for the SRF0, and C), "Significant" Technical Specification and Bases changes pending within the NRC. Attachments 1 through 3 identify the specific Technical Specification change requests within these categories.
Categories A (required changes) and B (desired changes) each provide a brief description of the change, the Technical Specification or license condition affected and the planned submittal date or the actual submittal date. At present, Toledo Edison has identified l
8712150174 871208 PDR ADOCK 05000346 P
PDR j \\.
1 THE TOLEDO EDISDN COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 l'
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l Docket No. 50-346 License No. NPF-3 Serial No. 1435 Page 2 eleven Category A (required) changes.
The majority of these requests are in support of plant modification commitments previously made to the NRC, Accordingly, NRC Staff action is required for Toledo Edison to complete those commitments.
Eight Category B (desired) changes have been identified. Category B contains those changes related to the SRF0 for which issuance is prudent from a regulatory or cost savings standpoint.
For example, one change request, when approved, will provide for closure of NRC Inspection Report Open Item 84-29-02.
Another would allow a significant cost savings through the elimination of unnecessary i
surveillance walkdowns if the change is approved by the NRC prior to the SRF0. The Category A and B change requests presently under 4
preparation are tentatively planned to be submitted to the NRC by the l
dates shown in the attachments.
Category C identifies three Technical Specification change requests previously submitted to the NRC for which Toledo Edison requests expeditious action. The first request (Serial No. 1377) l submitted in May 1987, concerns the deletion of a surveillance i
requirement which is no longer necessary to demonstrate operability l
as a result of system modifications. This unnecessary surveillance requirement places a burden on plant personnel with no increase in plant safety.
l The second request (Serial No. 1235), submitted in January 1986, concerns the Station Review Board (SRB) responsibilities and performance of technical reviews. This request, similar to that previously approved by the NRC Staff for the Virgil C. Summer Plant (NUREG-0932), will provide for more effective and efficient use of the SRB.
This request has been under NRC review for over 21 months.
Toledo Edison requests that the NRC Staff expeditiously complete its review and issue the requested change.
The third Category C request (Serial No. 1430) concerns a one-time l
interval extension for performing certain surveillance requirements for the emergency diesel generators. NRC issuance of the requested Technical Specification change is required prior to December 10, 1987 to avoid an unscheduled shutdown of the plant.
S
i l
Docket No. 50-346 License No. NPF-3 Serial No. 1435 Page 3 i
Toledo Edison believes it has identified the Technical Specification and license condition changes required for the SRFO. However, additional changes may be identified as the SRF0 approaches and as activities during that outage are completed. Should additional changes be identified, they will be prepared and submitted as expeditiously as practical.
Very truly y urs, D
- bah cc:
A. B. Davis, Reg 1onal Administrator DB-1 NRC Resident Inspector l
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