Letter Sequence Other |
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TAC:55652, (Open) TAC:61468, (Open) TAC:65361, (Open) TAC:65374, (Open) TAC:65685, (Open) TAC:66006, (Open) TAC:66377, (Open) TAC:66415, (Open) TAC:66418, (Open) TAC:66419, (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML20096C682, ML20149J903, ML20149J964, ML20151X241, ML20209H917, ML20215L839, ML20216H604, ML20235W129, ML20236H021, ML20236X859, ML20237A688
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MONTHYEARML20096C6631984-08-27027 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 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 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 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 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 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 ML20215L8391987-05-0404 May 1987 Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d Project stage: Other 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 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 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 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 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 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 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 ML20235W1291987-10-0909 October 1987 Proposed Tech Specs,Allowing one-time Extension of 18 Month Emergency Diesel Generator Surveillance Interval Project stage: Other 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 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 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 ML20236N1671987-11-0707 November 1987 Discusses 871029 & 30 Fire Protection Meetings in Bethesda, MD Re Issues Which Have Arisen in Conjunction W/Licensee App R Reappraisal Effort,Including Status of Fire Protection on Plant Mods.List of Attendees Encl Project stage: Meeting 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 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 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 ML20149J9031988-02-10010 February 1988 Forwards Environ Assessment & Finding of No Significant Impact Re Util 871207 Application for Amend to License NPF-3 to Update 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 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 ML20148J7291988-03-21021 March 1988 Responds to NRC 880303 Request for Addl Info Re 870807 Application to Amend Tech Specs 3/4.3.2 & 3/4.6.3.Amend Re Proposed Removing Closure Time Requirements for Ten Valves Connected to Secondary Side of Steam Generators Project stage: Request ML20148J7151988-03-24024 March 1988 Forwards Request for Addl Info Re Proposed Tech Spec Change to Delete Safety Features Actuation Signal to Certain Valves Project stage: RAI ML20151X2411988-04-29029 April 1988 Forwards Discussion of & Proposed Revs to Tech Specs for Resolution of NRC Comments Concerning Deletion of Auxiliary Feedwater Pump Turbine Inlet Steam Pressure Interlock Operability Requirements,Per 880406 Telcon Project stage: Other ML20154A8061988-05-0202 May 1988 Provides Supplemental Info Re Application for Amend Re Removing Closure Time Requirements for Valves Connected to Secondary Side of Steam Generators Listed in Tech Spec Tables 3.3-5 & 3.6-2 Project stage: Supplement ML20154N9081988-09-23023 September 1988 Summary of 880721 Meeting/Util in Rockville,Md Re Licensee App R Reappraisal Efforts.List of Meeting Attendees & Viewgraphs Encl Project stage: Meeting 1987-05-04
[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 AmendsML20237A688 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
12/08/1987 |
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From: |
Shelton D TOLEDO EDISON CO. |
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To: |
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
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References |
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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) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207F4231999-06-0202 June 1999 Forwards Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504, IAW 10CFR50.4.NRC Evaluated Exercise Has Been Rescheduled for 991208,since NRC Did Not Evaluate 990504 Exercise ML20207E9561999-05-28028 May 1999 Forwards Update to NRC AL 98-03,re Estimated Info for Licensing Activities Through Sept 30,2000 ML20207E2521999-05-28028 May 1999 Forwards Rev 18,App A,Change 1 to Davis-Besse Nuclear Power Station,Unit 1,industrial Security Plan IAW Provisions of 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20207E7801999-05-21021 May 1999 Forwards Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capacity.Proprietary & non- Proprietary Version of Rev 2 to HI-981933 Re Cask Pit Rack Installation Project,Encl.Proprietary Info Withheld ML20206N0231999-05-0606 May 1999 Forwards License Renewal Applications for Davis-Besse Nuclear Power Station,Unit 1 for ML Klein,Cn Steenbergen & CS Strumsky.Without Encls ML20206D2421999-04-28028 April 1999 Forwards Combined Annual Radiological Environ Operating Rept & Radiological Effluent Release Rept for 1998. Rev 11, Change 1 to ODCM & 1998 Radiological Environ Monitoring Program Sample Analysis Results Also Encl PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl ML20206B8831999-04-17017 April 1999 Forwards 1634 Repts Re Results of Monitoring Provided to Individuals at Davis-Besse Nuclear Power Station During 1998,per 10CFR20.2206.Without Repts ML20205K5641999-04-0707 April 1999 Forwards Response to NRC 980415 RAI Re GL 96-06, Assurance of Equipment Operability & Ci During Design-Basis Accident Conditions. Rept FAI/98-126, Waterhammer Phenomena in Containment Air Cooler Swss, Encl ML20205K3871999-04-0707 April 1999 Forwards Copy of Application of Ceic,Oec,Ppc & Teco to FERC, Proposing to Transfer Jurisdictional Transmission Facilities of Firstenergy Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20205J1171999-03-29029 March 1999 Forwards Rev 1 to BAW-2325, Response to RAI Re RPV Integrity, Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rev Includes Corrected Values in Calculations PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) ML20205F5961999-03-27027 March 1999 Forwards Comments on Preliminary Accident Sequence Percursor (ASP) Analysis of 980624 Operational Event at Dbnps,Unit 1, as Transmitted by NRC Ltr ML20205D4791999-03-26026 March 1999 Forwards Rept Submitting Results of SG Tube ISI Conducted in Apr 1998.Rept Includes Description of Number & Extent of Tubes Inspected,Location & Percent wall-thickness Penetration for Each Indication of Imperfection ML20205L2031999-03-26026 March 1999 Submits Correction to Dose History of Tj Chambers.Dose Records During 1980-1997 Were Incorrectly Recorded Using Wrong Social Security Number.Nrc Form 5 Not Encl ML20205C7371999-03-25025 March 1999 Certifies That Dbnps,Unit 1,plant-referenced Simulator Continues to Meet Requirements of 10CFR55.45(b) for Simulator Facility Consisting Solely of plant-referenced Simulator.Acceptance Test Program & Test Schedule,Encl ML20205E3551999-03-19019 March 1999 Requests That Proposed Changes to TS 6.8.4.d.2 & TS 6.8.4.d.7 Be Withdrawn from LAR Previously Submitted to NRC ML20204J6361999-03-17017 March 1999 Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities PY-CEI-NRR-2375, Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage1999-03-15015 March 1999 Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage ML20204E6821999-03-12012 March 1999 Requests That Listed Changes Be Made to NRC Document Svc List for Davis-Besse Nuclear Power Station,Unit 1 1999-09-09
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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, j inspections and tests are planned which will require the revision 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 P ADOCK 05000346 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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