Letter Sequence Meeting |
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TAC:MD6398, Increase Flexibility in Mode Restraints, Addition of LCO 3.0.8, Inoperability of Snubbers, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec, Changes to Reflect Revision of 10 CFR 50.55A, Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Correct Example 1.4-1, Containment Structural Integrity, TSTF-28, Correct LCO 3.0.6 Bases, Add Restriction for Lowest LOOP Tave During Mode 2 Physics Testing (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement
Results
Other: L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0, L-08-241, Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs, L-08-338, Copy of Improved Technical Specifications (ITS), L-08-378, Implementation of Improved Technical Specification Amendment No. 279, ML073531253, ML081350505, ML082000451, ML082270661, ML082270662, ML082270663, ML082270664, ML082270665, ML082270666, ML082270667, ML082270669, ML082270670, ML082600577, ML082840099, ML082900630, ML082900882, ML082910125
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MONTHYEARML0725600462007-09-11011 September 2007 9/11/2007-Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) - 9/11/2007 NRC Meeting Slides Project stage: Meeting ML0725600562007-09-12012 September 2007 9/12/2007 Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) 9/12/2007 NRC Meeting Slides Project stage: Meeting ML0729001172007-11-0707 November 2007 09/12/2007 - Meeting Summary with Fenco to Discuss Licensee'S ITS Conversion License Amendment Request for Davis-Besse Project stage: Meeting ML0735312532008-02-0404 February 2008 Improved Technical Specification Conversion Project stage: Other ML0814804652008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 5, (Revision 1), Section 3.0 - LCO and SR Applicability Project stage: Request ML0801400252008-05-16016 May 2008 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Opportunity for a Hearing (Tac Nos. MD6319-MD3622, MD6324-MD6333, MD6398-MD6403, MD6644-MD6649, and MD6684) Project stage: Acceptance Review L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.02008-05-16016 May 2008 Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0 Project stage: Other L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD63982008-05-16016 May 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398 Project stage: Supplement ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features Project stage: Request ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems Project stage: Request ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) Project stage: Request ML0814804672008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits Project stage: Request ML0814804662008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems Project stage: Request ML0826005772008-05-30030 May 2008 Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website Project stage: Other ML0813505052008-06-17017 June 2008 Improved Technical Specifications Conversion Milestone Schedule Project stage: Other ML0815705882008-06-18018 June 2008 Request for Additional Information Related to Improved Technical Specifications Conversion Project stage: RAI ML0816503642008-06-20020 June 2008 RAI Related to Improved Technical Specifications Conversion Project stage: RAI L-08-221, Response to Request for Additional Information Related to Improved Technical Specifications Conversion2008-07-23023 July 2008 Response to Request for Additional Information Related to Improved Technical Specifications Conversion Project stage: Response to RAI ML0822706582008-08-0707 August 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications to Improved Technical Specifications - Volumes 1, 2, 3, 4, 8, 10, 12, 13, 14, and 16 Project stage: Supplement L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations2008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations Project stage: Request ML0822706612008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 1, Revision 1, Application of Selection Criteria to the Dbnps Technical Specifications Project stage: Other ML0822706622008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 2, Revision 1, Generic Determination of No Significant Hazards Consideration and Environmental Assessment Project stage: Other ML0822706672008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 16, Revision 1, ITS Chapter 5.0, Administrative Controls Project stage: Other ML0822706702008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 13, Revision 1, ITS Section 3.8, Electrical Power Systems Project stage: Other ML0822706692008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 12, Revision 1, ITS Section 3.7, Plant Systems Project stage: Other ML0822706662008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 10, Revision 1, ITS Section 3.5, Emergency Core Cooling Systems Project stage: Other ML0822706652008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 8, Revision 1, Section 3.3 - Instrumentation Project stage: Other ML0822706642008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 4, Revision 1, ITS Chapter 2.0, Safety Limits Project stage: Other ML0822706632008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request Volume 3, Revision 1, ITS Chapter 1.0, Use and Application Project stage: Other L-08-241, Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs2008-08-26026 August 2008 Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs Project stage: Other L-08-224, Response to Request for Additional Information License Amendment Request to Convert Current Technical Specifications (CTS) to Improved Technical Specifications (Its), and Copy of Two Questions from NRC and Davis-Besse Its.2008-09-0303 September 2008 Response to Request for Additional Information License Amendment Request to Convert Current Technical Specifications (CTS) to Improved Technical Specifications (Its), and Copy of Two Questions from NRC and Davis-Besse Its. Project stage: Response to RAI ML0824903002008-10-0202 October 2008 ITSB Draft R, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902622008-10-0202 October 2008 Draft Safety Evaluation for Conversion to ITS with Beyond Scope Issues, (TAC MD Project stage: Draft Approval ML0824902712008-10-0202 October 2008 List of Acronyms to Davis Besse Draft Amend. ITS Conversion Project stage: Draft Other ML0824902752008-10-0202 October 2008 Draft a, Attachment to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902802008-10-0202 October 2008 ITSB Draft La, to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902892008-10-0202 October 2008 ITSB Draft L, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0824902952008-10-0202 October 2008 ITSB Draft M, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues Project stage: Draft Other ML0828400992008-10-0808 October 2008 Assessment -Davis-Besse Nuclear Power Station, Unit No. 1 - Environmental Assessment and Finding of No Significant Impact for the Proposed Conversion to the Improved Technical Specifications (TAC 6398) Project stage: Other ML0820004512008-10-0808 October 2008 Environmental Assessment and Finding of No Significant Impact for the Proposed Conversion to the Improved Technical Specifications Project stage: Other L-08-338, Copy of Improved Technical Specifications (ITS)2008-10-21021 October 2008 Copy of Improved Technical Specifications (ITS) Project stage: Other ML0829006832008-11-20020 November 2008 Table A-DOC Attachment - Administrative Changes - to Davis-Besse Amend. ITS with Beyond Scope Issues Project stage: Acceptance Review ML0829007802008-11-20020 November 2008 ITSB L-Less Restrictive Changes - Attachment to Davis-Besse Amendment Beyond Scope Issues Project stage: Acceptance Review ML0829008822008-11-20020 November 2008 ITSB LA-Removed Details - Attachment to Davis-Besse Beyond Scope Issues Project stage: Other ML0829006302008-11-20020 November 2008 List of Acronyms to Davis-Besse Amend. Re; ITS with Beyond Scope Issues Project stage: Other ML0829101252008-11-20020 November 2008 ITSB R-Relocated Specifications - to Davis Besse Amendment Beyond Scope Issues Project stage: Other ML0829101122008-11-20020 November 2008 ITSB M - More Restrictive Changes - to Davis Besse Amendment Beyond Scope Issues Project stage: Acceptance Review ML0829006002008-11-20020 November 2008 Issuance of Amendment 279 for the Conversion to the Improved TSs with Beyond Scope Issues Project stage: Approval L-08-378, Implementation of Improved Technical Specification Amendment No. 2792008-12-16016 December 2008 Implementation of Improved Technical Specification Amendment No. 279 Project stage: Other 2008-02-04
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24248A2112024-09-0303 September 2024 2023 Davis-Besse End-of-Cycle Meeting Presentation ML22222A1102022-07-21021 July 2022 KM Session Final ML22178A1952022-06-27027 June 2022 2021 Davis Besse Nuclear Power Station End-of-Cycle Meeting Presentation ML22028A3922022-02-0101 February 2022 Licensee Regulatory Conference Presentation ML22028A3972022-02-0101 February 2022 NRC Regulatory Conference Presentation ML21176A1992021-06-25025 June 2021 Slideshow Presentation for 2020 End -of-Cycle Public Meeting for Davis-Besse and Perry ML20210M0712020-07-27027 July 2020 Combined End-of-Cycle 2019 Public Meeting Slide Presentation ML19249D0212019-09-0606 September 2019 End-of-Cycle Summary Handout (2018) ML18310A3802018-11-0808 November 2018 Pre-Submittal Meeting Davis-Besse Nuclear Power Station (DB) Post-Shutdown Emergency Plan (PSEP) License Amendment Request ML18180A1962018-06-29029 June 2018 Slides for Davis Besse 2017 EOC Open House ML17229B3382017-08-17017 August 2017 Presentation for 2016 Davis-Besse EOC Open House ML16174A3152016-06-21021 June 2016 Annual Assessment Meeting Open House June 21, 2016 ML15156A6962015-06-11011 June 2015 Annual Assessment Meeting Open House Handout ML14224A1112014-08-25025 August 2014 Safety Culture Presentation for Brazil, U.S. Workshop on Safety and Security Culture - August 25, 2014 ML14218A0542014-08-0707 August 2014 Handout Davis-Besse EOC Mtg ML14050A4002014-02-20020 February 2014 NRC Presentation for Davis-Besse Steam Generator Replacement Webinar ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13294A5972013-10-21021 October 2013 FENOC Presentation Slides for Public Meeting September 24, 2013 ML13157A0642013-06-0606 June 2013 June 11, 2013 NRC Presentation ML13159A0092013-06-0404 June 2013 Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12227A4172012-08-15015 August 2012 NRC End-Of-Cycle Assessment 2011 Meeting Presentation ML12221A2642012-08-0909 August 2012 NRC Public Meeting NRC Presentation 8/9/12 ML12221A2682012-08-0909 August 2012 FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML1206901712012-02-29029 February 2012 Slides and View Graphs - Boric Acid Corrosion Testing Program: Industry Perspective ML12200A2402012-02-23023 February 2012 Presentation Slides on Davis-Besse Shield Building Crack ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12004A0102012-01-0404 January 2012 Public Meeting NRC Slides ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML1117209902011-06-15015 June 2011 Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station. ML1021501112010-07-29029 July 2010 NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting ML1021501182010-07-29029 July 2010 Licensee Slides for Davis-Besse Annual Assessment Meeting L-02-002, G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse2010-04-15015 April 2010 G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse ML0920202972009-07-15015 July 2009 NRC Slides from EOC Meeting ML0920202872009-07-15015 July 2009 Meeting Slides, NRC Annual Assessment Meeting Davis-Besse Nuclear Power Station ML0725600562007-09-12012 September 2007 9/12/2007 Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) 9/12/2007 NRC Meeting Slides ML0725600462007-09-11011 September 2007 9/11/2007-Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) - 9/11/2007 NRC Meeting Slides ML0722201892007-08-0808 August 2007 NRC EOC Public Meeting Slides ML0717905962007-06-27027 June 2007 Slides from Public Meeting Between NRC and FENOC Regarding Response to May 14, 2007, Demand for Information ML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts ML0706502022007-01-23023 January 2007 Slides to Summary of Pre-Application Meeting with FENOC Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML0632003672006-12-11011 December 2006 Slides, Improved Technical Specification Conversion from Category 1 Pre-submittal Meeting with Fenco to Discuss Davis-Besse's' Proposed Conversion to Improved Technical Specifications ML0612404142006-05-0202 May 2006 NRC Annual Assessment Meeting ML0601801602006-01-18018 January 2006 Industry Safety Culture Presentation for January 18, 2006 Public Meeting ML0603002272006-01-10010 January 2006 Multi-Regional NRC Public Meeting Licensee (FENOC) Slide Presentation ML0802205572005-09-12012 September 2005 NRC Commissioners Briefing by Firstenergy Nuclear Operating Co ML0525604472005-08-17017 August 2005 B&W Owners Group Reactor Vessel Working Group Summary of the Plans of the B&Wog Reactor Vessel Integrity Program 2024-09-03
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24248A2112024-09-0303 September 2024 2023 Davis-Besse End-of-Cycle Meeting Presentation ML23152A2022023-06-0101 June 2023 2022 Davis-Besse End-of-Cycle Meeting Presentation ML22222A1102022-07-21021 July 2022 KM Session Final ML22178A1952022-06-27027 June 2022 2021 Davis Besse Nuclear Power Station End-of-Cycle Meeting Presentation ML22028A3922022-02-0101 February 2022 Licensee Regulatory Conference Presentation ML22028A3972022-02-0101 February 2022 NRC Regulatory Conference Presentation ML21176A1992021-06-25025 June 2021 Slideshow Presentation for 2020 End -of-Cycle Public Meeting for Davis-Besse and Perry ML20210M0712020-07-27027 July 2020 Combined End-of-Cycle 2019 Public Meeting Slide Presentation ML19249D0212019-09-0606 September 2019 End-of-Cycle Summary Handout (2018) ML18310A3802018-11-0808 November 2018 Pre-Submittal Meeting Davis-Besse Nuclear Power Station (DB) Post-Shutdown Emergency Plan (PSEP) License Amendment Request ML18180A1962018-06-29029 June 2018 Slides for Davis Besse 2017 EOC Open House ML17229B3382017-08-17017 August 2017 Presentation for 2016 Davis-Besse EOC Open House ML16174A3152016-06-21021 June 2016 Annual Assessment Meeting Open House June 21, 2016 ML16117A1822016-04-22022 April 2016 Industry Slides for the Spring 2016 Conference Call Regarding the Steam Generator Tube Inservice Inspections ML15156A6962015-06-11011 June 2015 Annual Assessment Meeting Open House Handout ML14224A1112014-08-25025 August 2014 Safety Culture Presentation for Brazil, U.S. Workshop on Safety and Security Culture - August 25, 2014 ML14218A0542014-08-0707 August 2014 Handout Davis-Besse EOC Mtg ML14050A4002014-02-20020 February 2014 NRC Presentation for Davis-Besse Steam Generator Replacement Webinar ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13294A5972013-10-21021 October 2013 FENOC Presentation Slides for Public Meeting September 24, 2013 ML13220A0632013-08-30030 August 2013 Dsd ED2013 3267 Presentation, Primary Water Stress Corrosion Cracking Tests and Metallurgical Analyses of Davis-Besse Control Rod Drive Mechanism Nozzle #4. ML13157A0642013-06-0606 June 2013 June 11, 2013 NRC Presentation ML13159A0092013-06-0404 June 2013 Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting ML13078A2492013-03-20020 March 2013 Project Overview-Public Mtg 3-20-13 Non Proprietary ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12227A4172012-08-15015 August 2012 NRC End-Of-Cycle Assessment 2011 Meeting Presentation ML12221A2682012-08-0909 August 2012 FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12 ML12221A2642012-08-0909 August 2012 NRC Public Meeting NRC Presentation 8/9/12 ML12138A0732012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 5 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML1206901712012-02-29029 February 2012 Slides and View Graphs - Boric Acid Corrosion Testing Program: Industry Perspective ML12200A2402012-02-23023 February 2012 Presentation Slides on Davis-Besse Shield Building Crack ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML1200501462012-01-0505 January 2012 Public Meeting FENOC Slides ML12004A0102012-01-0404 January 2012 Public Meeting NRC Slides ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML11221A3012011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 16 Davis-Besse Loss of All Feedwater ML1117303602011-06-21021 June 2011 FENOC Licensee Slides for 6-21-11 All FENOC Meeting ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML1117209902011-06-15015 June 2011 Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station. ML1032103472010-11-16016 November 2010 FENOC 11/16/10 Public Meeting Presentation Slides ML1025103462010-09-0909 September 2010 SIT Exit Meeting Presentation Slides ML1021501182010-07-29029 July 2010 Licensee Slides for Davis-Besse Annual Assessment Meeting ML1021501112010-07-29029 July 2010 NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting ML1015400332010-06-0303 June 2010 Licensee Slides for June 3, 2010 Public Meeting Presentation ML1015400342010-06-0303 June 2010 NRC Slides for June 3, 2010 Public Meeting Presentation ML1009102662010-03-31031 March 2010 Slides FENOC and NRC Senior Management Briefing, 3-31-10 ML0920202872009-07-15015 July 2009 Meeting Slides, NRC Annual Assessment Meeting Davis-Besse Nuclear Power Station ML0920202972009-07-15015 July 2009 NRC Slides from EOC Meeting 2024-09-03
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Text
(7t2-( G-)
FirstEnergy Nuclear Operating Co. (FENOC)
Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS)
(LAR No. 06-0003; August 3, 2007)
September 11 - 12, 2007 9:00 AM "-4:00 PM U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike, Room O-04B6 Rockville, Maryland
Agenda (Day 2 of 2,- Revised)
,, Day 2
- Review select portions of draft NRC office instruction LIC-601 ("Technical Specification Conversion Accelerated Review") guidance
- Just-in-time training & issuance of passwords for NRC staff to submit questions to on-line Q&A database to facilitate accelerated review
- Opportunity for public comment
- Adjourn 9/12/2007 2
LIC-601 Review LIC-601 Development Continues and Will Incorporate Lessons-Learned During the Davis-Besse ITS Conversion Today We'll Review Sample Excerpts from Several LIC-601 References Important to Detailed Review & On-Line Q&A 1#'All LIC-601 References (with hyperlinks &
ML's) Have Been Replicated in the DBNPS ITS Cony. Workbook - "LIC-601 Refs" Tab 9/12/2007 3
Some Important Q&A Process Refs 10 CFR § 2.108 Denial of 10 CFR § 50.36, Technical application for failure to supply Specifications information 58 FR 29132 Final Policy COM-203, Informal Statement on Technical Interfacing and Exchange of Specifications Improvements ...
Information with Licensees and July 22, 1993 Applicants, Rev 1 10 CFR § 50.90 Application LIC-101, License Amendment For Amendment of License or Review Procedures, Rev 3 (Rev Construction Permit 4 Pending) , 10 CFR § 50.92 Issuance of
, LIC-202, Managing Plant- Amendment Specific Backfits ..., Rev 1 NRC Administrative Letter 96-MD-8.4, NRC Program for 04 -Efficient Adoption of Management of Plant-Specific Improved Standard Backfitting ... Technical Specifications, October, 1996 RIS-2000-06, Consolidated Line Item Improvement Process for , NEI 96-06, Improved Technical Adopting Standard Technical Specifications Conversion Specifications Changes ... Guidance, August, 1996 9/12/2007 4
10 CFR § 2.108 (NRR)... may deny an application if an applicant fails to respond to a request for additional information within thirty (30) days from the date of the request, or within such other time as may be specified 9/12/2007
COM-203 Informal Interfacing and Exchange of Information with Licensees and Applicants Regulations require that all license applications, requests for amendments and associated correspondence be submitted in writing or by authorized electronic submission (Electronic Information Exchange (EIE) or CD-ROM)
It is NRC policy to make all correspondence used to support decision making an officialagency record and to make it publicly available by placing a copy into ADAMS,, unless exempted..
In formation informallyexchanged with licensees or applicants, and used in decision making, must be properly documented to ensure public disclosure and allow public participation in the decision making process.
9/12/2007 6 6
COM-203 Outgoing correspondence from NRR cannot be considered an official agency issuance unless it has received appropriate review and concurrence and is signed by a person authorized by NRR Office Instruction ADM-200, "Delegation of Signature Authority."
Staff members should refrain from stepping out of the role of the regulator and into the role of advisor. E.g.,
- Detailed input on the technical content would not be appropriate.
- Also, staff members should refrain from providing comments or advice that would give more of an advantage to one licensee or applicant than to any other.
Comments on the scope of discussion needed for decision making, the need to address regulatory or industry guidelines, or editorial and formatting suggestions that would facilitate staff review, would be acceptable.
9/12/2007 7
LiC-1 01 The SE provides the technical, safety, and legal basis for the NRC's disposition of a license amendment request.
The SE should provide sufficient information to explain the staff's rationale to someone unfamiliar with the licensee's request.
The SE includes a brief description of the proposed change, the regulatory requirements related to the issue, and an evaluation that explains why the staff's disposition of the request satisfies the regulatory requirements.
Given that the SE serves as the record of the staff's disposition of a license amendment request, the information relied upon in the SE must be docketed correspondence 9/12/2007 8
LIC-1 01 Requests for additional information (RAIs) serve the purpose of enabling the staff to obtain all relevant information needed to make a decision on a licensing
.action request that is fully informed, technically correct, and legally defensible, RAIs are necessary when the information was not included in the initial submittal, is not contained in any other docketed correspondence, or cannot reasonably be inferred from the information available to the staff.
RAIs should be directly related to the applicable requirements related to the amendment application, and consistent with the applicable codes, standards, regulatory guides, and/or the applicable Standard Review Plan sections.
RAIs should not be used as general information requests or as a means to encourage commitments from licensees.
9/12/2007 9
LIC-202 The Backfit Rule, 10 CFR 50.109... requires that the NRC justify each backfit with either a regulatory analysis or a documented evaluation If ... staff determines that a ... backfit that is necessary to bring a facility into compliance ...,
or ... necessary to ensure ... adequate protection to the public health and safety, or ..., (then)...
staff should, within 2 weeks of determination.
provide ... a documented evaluation...
The position that constitutes the potential backfit should not be communicated to the licensee until the issue has been resolved and approved by the ADRO.
9/12/2007 10
MD-8.4 Backfitting is the process by which NRC decides whether to impose new or revised regulatory requir ements or staff positions on NRC-licensed nuclear power reactors
., Backfitting is an inherent part of the regulatory process and is expected to occur. However, it is to be implemented only after a formal and systematic review to ensure that the proposed changes are properly justified and suitably defined.
9/12/2007 11
RIS-2000-06 The NRC staff reviews the changes to the STS proposed by the TSTF (referred to as TSTF changes) and will accept, modify, or reject them.
Once TSTF changes are accepted, they are considered to be part of the STS.
Individual licensees may propose to adopt the TSTF changes during a conversion to the STS or as a separate license amendment application.
9/12/2007 12
10 CFR 50.36 (a) Each applicant ...shall include...
proposed technical specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications... shall also be included...
(b) ...The technical specifications will be derived from the analyses and evaluation included in the safety analysis report...
9/12/2007 13
58 FR 29132 The purpose of Technical Specifications is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety by identifying those features that are of controlling importance to safety and establishing on them certain conditions of operation which cannot be changed without prior Commission approval 9/12/2007 14 1
58 FR 29132 The Commission encourages licensees to use the improved STS as the basis for plant-specific Technical Specifications. During ... conversions, the nonvoluntary addition of new requirements from the improved STS to individual plant Technical Specifications will be evaluated in accordance with the Commission regulations on backfitting (10 CFR 50.109) unless the staff suggested additional changes are needed to make the licensee requested changes acceptable from the standpoint of adequate protection or compliance with NRC regulations, in which case § 50.109 does not apply and the request may be denied without the additional items 9/12/2007 15
58 FR 29132 When licensees submit amendment requests ... , they should identify the location of and controls for the technical and administrative requirements of the relocated requirements, The NRC staff will carefully review these submittals to ensure the accountability and the acceptability of controls for each relocated requirement.
9/12/2007 16 1
50.90 T Whenever a holder of a license ...
desires to amend the license...
application ...must be filed ... fully describing the changes desired, and following as far as applicable, the form prescribed for original applications.
9/12/2007 17
50.92 (a) In determining whether an amendment to a license ... will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses ... to the extent applicable and appropriate.
9/12/2007 18
Adm Ltr 96-04 The NRC continues to believe that total adoption of the improved STS will substantially improve the efficiency of the regulatory process, and ensure that licensee and NRC resources are applied to significant safety matters The major objective of converting from plant-specific technical specifications to the improved STS is to achieve as much consistency in the license requirements as possible, to the extent that the plant-specific design basis can conform with the related typical plant design reflected in the improved STS.
9/12/2007 19
NEI 96-06 Si.gnificant discussion and disposition of philosophical and technical issues between the industry and the NRC occurred during the development of the ISTS. Therefore, a high threshold should be satisfied for deviating from the ISTS in the ITS.
Language and justifiedon a format preferences, unless lant-specific basis, should be avoided. This is especially true of Sections 1.0 and 3.0. This high threshold is used to preserve the standardization of the use and meaning of the requirements for the industry and the NRC.
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NEI 96-06 The licensee may decide not to adopt certain ISTS provisions because conformance with the ISTS would constitute an unwarranted backfit to existing license requirements.
For these changes, the NRC may consider whether plant-specific provisions affect the completeness of the ISTS, and determine if a backfit evaluation is warranted.
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Just-in-time training & issuance of passwords
...for NRC staff to submit questions to on-line Q&A database to facilitate accelerated review and request-for-additional-information (RIA) processes
Any Further Discussion or Questions from Staff?
From Licensee?
Opportunity for Public Comment Thank You For Your Participation Any Further Comments or Questions?
Adjourn