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MONTHYEARCP-200900751, Supplement to the Proposed Emergency Plan Change to Implement NEI 99-01, Revision 5, Emergency Action Levels (Eals)2009-05-28028 May 2009 Supplement to the Proposed Emergency Plan Change to Implement NEI 99-01, Revision 5, Emergency Action Levels (Eals) Project stage: Request ML0916903952009-06-18018 June 2009 Acceptance Review Email, Emergency Plan Changes to Implement Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for the Development of Emergency Action Levels Project stage: Acceptance Review NEI 09-01, Acceptance Review Email, Emergency Plan Changes to Implement Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for the Development of Emergency Action Levels (TAC Nos. ME1304 and ME1305)2009-06-18018 June 2009 Acceptance Review Email, Emergency Plan Changes to Implement Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for the Development of Emergency Action Levels (TAC Nos. ME1304 and ME1305) Project stage: Acceptance Review ML0934804552009-12-23023 December 2009 Request for Additional Information, Emergency Plan Changes to Implement Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for the Development of Emergency Action Levels Project stage: RAI ML1008501152010-05-17017 May 2010 Emergency Plan Changes to Implement Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for the Development of Emergency Action Levels Project stage: Other 2009-05-28
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Category:Letter
MONTHYEARCP-202400424, (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0)2024-11-0404 November 2024 (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0) IR 05000445/20240032024-10-30030 October 2024 Integrated Inspection Report 05000445/2024003 and 05000446/2024003 IR 05000445/20244042024-10-23023 October 2024 Security Baseline Inspection Report 05000445/2024404 and 05000446/2024404 (Public) IR 07200074/20244012024-10-10010 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200074/2024401 Public 05000445/LER-2024-002-01, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-10-0303 October 2024 Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions 05000446/LER-2024-001-01, Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-09-30030 September 2024 Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24031A6322024-09-11011 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24228A2252024-08-22022 August 2024 Relief to Use Later Code Edition for Inservice Inspection Program ML24179A0772024-08-20020 August 2024 Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants 05000445/LER-1924-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator 05000446/LER-2024-001, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications 05000445/LER-2024-001, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma 2024-09-30
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24204A0022024-07-18018 July 2024 NRR E-mail Capture - Request for Additional Information Comanche Peak Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24052A0122024-02-16016 February 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications ML24036A0122024-02-0202 February 2024 NRR E-mail Capture - Comanche Peak - Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24033A2642024-02-0202 February 2024 NRR E-mail Capture - Comanche Peak - Revised Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24019A0742024-01-19019 January 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24018A1072024-01-18018 January 2024 – Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23256A1502023-09-11011 September 2023 Request for Additional Information Requests - Comanche Peak - Set 4 ML23213A2162023-08-0202 August 2023 Vistra Operations Company, LLC Notification of License Renewal Inspection and Request for Information ML23188A0452023-07-0707 July 2023 Request for Additional Information Requests - Comanche Peak - Set 3 ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23181A0212023-06-29029 June 2023 Request for Additional Information Requests - Comanche Peak - Set 2 ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 ML23167A0232023-06-14014 June 2023 Request for Additional Information (RAI) for the Review of the Comanche Peak Initial License Renewal Application (Lra), Set 1 ML23167A0222023-06-14014 June 2023 Email: Request for Additional Information (RAI) Letter for the Review of the Comanche Peak Initial License Renewal Application, Set 1 ML23145A2322023-05-25025 May 2023 LRA - Request for Confirmation of Information - Set 2 ML23132A2542023-05-23023 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action LAR to Adopt 10 CFR 50.69,Risk-Informed Categorization & Treatment of Structures,Systems & Components for Nuclear Power Reactors EPID L-2023-LLA-0057 ML23143A1372023-05-23023 May 2023 LRA - Request for Confirmation of Information - Set 1 ML23068A0562023-05-0909 May 2023 Request for Additional Information - Comanche Peak License Renewal Application Environmental Review ML23068A0732023-04-13013 April 2023 Requests for Confirmation of Information for the Environmental Review of the Comanche Peak Nuclear Power Plant, Units 1 and 2, Licensed Renewal Application (EPID Number: L-2022-LNE-0004) (Docket Numbers 50-445 and 50-446) ML23103A4682023-04-11011 April 2023 NRR E-mail Capture - Comanche Peak – Request for Additional Information - License Amendment Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23086B9852023-03-27027 March 2023 NRR E-mail Capture - Comanche Peak – Draft Request for Additional Information - Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23010A1442023-01-0909 January 2023 Inservice Inspection Request for Information ML22325A2742022-11-21021 November 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22318A3102022-11-10010 November 2022 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22230B1092022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22220A1942022-08-0808 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Draft Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing IR 05000445/20224012022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000445/2022401; 05000446/2022401 ML22083A0262022-03-23023 March 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2 ML21286A7912021-10-13013 October 2021 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF-577 Revision 1 ML21253A2242021-09-0909 September 2021 Request for Information Occupational Radiation Safety Inspection (71124.01, 71124.02, and 71151) from 10/18-22/2021 ML21253A2332021-09-0909 September 2021 Request for Information: Comanche Peak Nuclear Power Plant, Units 1 and 2 (05000445 and 05000446); Occupation Radiation Safety (71124.01, 71124.02, 7511) ML21245A3072021-09-0202 September 2021 Request for Information ML21245A307 ML21166A3382021-06-22022 June 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action LAR to Adopt TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML21165A1022021-06-13013 June 2021 Pi&R; Request for Information ML21103A3982021-04-13013 April 2021 CP Security Inspection Information Request 2021403 ML20225A0932020-08-12012 August 2020 Notification of Inspection 05000445/2020004 and 05000446/2020004 and Request for Information ML20105A1072020-04-13013 April 2020 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Exigent Amendment Request for One Time Change to Unit 2 Steam Generator Inspection Frequency ML20104A0022020-04-11011 April 2020 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - Proposed Alternative to ASME OM Code for Deferral of Snubber Testing (SNB-1) and Visual Examinations (SNB-2) ML20045E3512020-02-13013 February 2020 Information Request February 13, 2020 Notification of Inspection and Request for Information Comanche Peak Unit 2 NRC Inspection Report 05000446/2020002 ML19346B3812019-12-11011 December 2019 NRR E-mail Capture - Comanche Peak RAIs - Quality Assurance Program Reduction in Commitment ML19319A5432019-11-14014 November 2019 NRR E-mail Capture - Draft Comanche Peak RAIs - Quality Assurance Program Reduction in Commitment ML19058A3592019-02-27027 February 2019 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 - Final Request for Additional Information Concerning License Amendment Request to Revise the Emergency Plan IR 05000445/20170072018-02-0808 February 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000445/2017007 and 05000446/2017007) ML17276B8622017-10-0303 October 2017 Notification of NRC Design Bases Assurance Inspection (Programs)(05000445/2017007 and 05000446/2017007) and Initial Request for Information ML17087A2032017-03-28028 March 2017 NRR E-mail Capture - Comanche Peak, Unit 2 - Final Request for Additional Information Regarding Request No. 2B3-1 ML17066A2372017-03-0707 March 2017 Notification of NRC Triennial Fire Protection Baseline Inspection (05000445/2017008 and 05000446/2017008) and Request for Information ML17048A4172017-02-17017 February 2017 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment... ML16034A1962016-02-0808 February 2016 Independent Spent Fuel Storage Installation - Request for Additional Information, Application for Order Approving Transfer of Facility Operating Licenses and Conforming Amendment 2024-07-18
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 23, 2009 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043 SUB..IECT: COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED EMERGENCY PLAN CHANGES TO IMPLEMENT NUCLEAR ENERGY INSTITUTE (NEI) 99-01, REVISION 5, METHODOLOGY FOR THE EMERGENCY ACTION LEVELS (TAC NOS. ME1304 AND ME1305)
Dear Mr. Flores:
By letter dated May 12, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091390820), as supplemented by letter dated May 28, 2009 (ADAMS Accession No. ML091550030), Luminant Generation Company LLC (the licensee) submitted the proposed changes to the emergency plan to implement Nuclear Energy Institute (NEI) 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2, for U.S. Nuclear Regulatory Commission (NRC) approval.
The NRC staff has reviewed the information provided by the licensee and determined that additional information is needed in order to complete the review. A draft copy of the request for additional information (RAI) was forwarded to Mr. Jim Barnette of your staff on November 24, 2009, via e-mail. The licensee had discussions with the NRC staff on December 11, 2009, to ensure mutual understanding of the RAI. Mr. Barnette agreed to provide the final response by January 29, 2010.
R. Flores - 2 If you have any questions, please contact me at 301-415-3016 or via e-mail at balwant.singal@nrc.gov.
Sincerely, b~\L0o.-.1 t.-8,~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION PROPOSED CHANGES TO EMERGENCY PLAN LUMINANT GENERATION COMPANY LLC COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By letter dated May 12, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091390820), as supplemented by letter dated May 28, 2009 (ADAMS Accession No. ML091550030), Luminant Generation Company LLC (the licensee) submitted the proposed changes to the emergency plan to implement Nuclear Energy Institute (NEI) 99-01, Revision 5 (ADAMS Accession No. ML080450149), "Methodology for Development of Emergency Action Levels," for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2, for U.S. Nuclear Regulatory Commission (NRC) approval.
The NRC staff has reviewed the information provided by the licensee and determined that the additional information identified in the following table is needed in order to complete its review.
It was agreed that the licensee will provide the additional information being requested by January 29, 2010.
TABLE IDENTIFYING THE REQUEST FOR ADDITIONAL INFORMATION (RAI) FOR CPSES, UNITS 1 AND 2
~,<t#*f EAL Que$tion It is expected that licensees adhere to endorsed guidance, particularly for Initiating Conditions and Definitions, with no differences or deviations other than those related to a licensee's particular design. This is to ensure regulatory stability of the Emergency Action Level (EAL) scheme.
This also ensures that, as stated in Title 10 of the Code of Federal Regulations, (10 CFR), Paragraph 50.47(b)(4), licensees implement "A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters .... "
GENERIC While the NRC staff is not enforcing strict verbatim compliance with the endorsed guidance, where applicable, the NRC staff will be pointing out areas where it expects the endorsed guidance to be used to ensure implementation of a standard scheme. This is primarily based upon industry and NRC staff experience with issues related to a particular EAL.
While formatting is usually not technically relevant to the NRC staffs review of EALs, when inconsistent formatting may result in potential misunderstanding, an RAI will be developed to correct the formatting or to obtain additional information in support of the deviation.
Enclosure
-2
...... ;,U
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EAL Question
- 1. Off-scale high or low thresholds are usually not within the calibrated range of instrumentation. Please confirm that all stated values, setpoints, and indications provided are within the calibrated range of the applicable instrumentation.
1 GENERAL 2. Sections 3.9,3.10, and 3.11 from the endorsed guidance contain important information necessary to understand the intent of the guidance as well as NRC staff expectations. Please indicate whether these sections will be incorporated into the document or fully document the technical basis for why it cannot be incorporated.
While no specific section in NEI 99-01, Revision 5, documents the purpose of the EAL Technical Bases Document (EAL TBD), however, it can be implied from statements made in NEI 99-01, Revision 5, Sections 4.2, 5.1, and particularly 2 SECT 1.0 Section 5.3. Please indicate whether the purpose statement in Section 1.0 of the EAL TBD for CPSES, Units 1 and 2 will be revised, to align with NEI 99-01, Revision 5, to state the purpose of the EAL TBD, or provide justification of why this is not necessary.
Generally, the industry implementation method has been for a HOT [hot conditions] EAL Wallboard and a COLD [cold conditions] EAL Wallboard.
Please explain how having three EAL Wallboards is more effective than two EAL 3 SECT 2.6 Wallboards and will not cause a situation whereby an Emergency Response Organization decision-maker neglects the ANY Operating Mode EAL Wallboard when reviewing the applicable HOT/COLD EAL Wallboard, or vice versa.
The NRC staff requests that ADAMS Accession No. ML080450149 be used to reference I\lEI 99-01, Revision 5, to ensure that the multiple draft copies of this 4 SECT 3.0 document that are in ADAMS are not inadvertently referenced. Please revise Section 3.0 to reference this ADAMS accession number.
It is expected that definitions are verbatim from the endorsed guidance, with the exception of terms specifically defined by the licensee, to ensure implementation of a standard emergency classification and action level scheme.
Please provide the following:
- 1. Please define the term PROJECTILE as worded in the endorsed guidance, 5 SECT 4.0 or provide adequate justification supporting the deviation.
- 2. As noted above, please provide the site-specific definition for VITAL AREA rather then the generic wording used in the endorsed guidance.
- 3. Add the word "energized" to the definition of EXPLOSION or provide adequate justification to support the deviation.
-3
,\
RAI# EAL Question RU1.1
- 1. [RU 1, RA1] Please provide documentation to support that the values "2 x RU1.2 HIGH ALARM and 200 x HIGH ALARM" are within the calibrated range of the applicable instrumentation.
RA1.1
- 2. Table R-1 appears to be formatted incorrectly. Please verify that the listed 6 RA1.2 values for u-RE-2325 thru u-RE-2328 are as stated. It appears that the RA1.3 values listed in the table may be only applicable to u-RE-2325.
RS1 3. All the values that should be "IJCi" state "IJC" instead. Please correct these typographical errors or provide justification to support the deviation.
RG1 Please explain why the value for X-RE-5570 A&B is only 10x the UE value 7 RA1.1 instead of 100x. Please correct the discrepancy or provide adequate justification for the deviation.
RA1.1 The RU 1 set of EALs incorporate language that is derived from the endorsed 8 RA1.2 guidance; however, the RA1 set of EALs do not. Please incorporate the endorsed language or provide justification to support the deviation.
RA1.3 RS1 Please confirm that the resolution of the instrumentation used for these EALs 9
RG1 can accurately indicate the stated values.
RS1.3 Please restore the note related to timing as stated in the endorsed guidance, or 10 RG1.3 provide justification to support why it is not applicable.
HU2.1 RA2.3 CU1.2 CU2.2 If using the same Initiating Condition (IC) numbering base (RA2.1, RA2.3, etc.),
11 then the IC title is expected to be the same. Please indicate whether the CU2.3 endorsed guidance will be followed or provide justification for the deviation.
SS1.2 SU4.2
-4
.)
RAI# EAti Question
- 1. Please explain why "station blackout" is not part of the EAL, as endorsed.
Please indicate whether the endorsed wording will be incorporated or justify the deviation.
12 CU1.1 2. The plant-specific basis information on page 89 of EAL TBD for CPSES, Units 1 and 2, does not include language to support the expectation that this EAL be declared, if the EAL is expected to continue beyond the time allowed. Please clarify.
Please confirm that the instrumentation to be used for the 10 psig value is 13 CA3.1 capable of reading this value (i.e., within the resolution and calibrated range).
- 1. Please explain why the Engineering Notification System (ENS) is not listed in Tables C-2 and S-2 as a viable option for onsite and offsite communications.
- 2. The plant-specific description for CU4.1 states the FAX transmissions are CU4.1 included. FAX transmissions are not actually a method that is considered 14 SU4.2 reasonably viable nor is it a method CPSES, Units 1 and 2, chose to list in Tables C-2 and S-2. Please indicate whether the discrepancy will be corrected or justify the deviation.
- 3. The plant-specific information is not consistent for these two EALs. Please explain the inconsistency.
The plant-specific basis information states "later." Please include information for 15 EU1.1 review or change the basis to "none."
HU1.1 Please confirm that the stated alarms and indicators are available in the Control 16 Room, or, if not, justify the effect these alarms and indicators have on the timing HA1.1 of this EAL.
This EAL on page 160 of the EAL TBD for CPSES, Units 1 and 2, should 17 HU1.3 actually be numbered HU1.4. Please correct the discrepancy or justify why the EAL scheme has two HU1.3 EALs.
Please explain why "startup" is not an operating mode listed for this EAL or 18 SA2.1 justify the deviation.
Please provide documentation to support the values chosen for 1-131 and 19 SU5.1 XE-133 specific activity and, in addition, confirm that CPSES, Units 1 and 2, do not have an activity threshold over a certain site-specific duration.
-5 RAitt****. SAL Question Please provide additional documentation to support what was reviewed, and Fission what was considered, for the "Other Site Specific Indications" from the endorsed 20 Product guidance (line 7 for all barriers). Please indicate the extent to which a Barrier Matrix reasonable effort has been made to determine a site-specific indicator of a loss or potential loss of any fission barrier.
R. Flores -2 If you have any questions, please contact me at 301-415-3016 or via e-mail at balwant.singal@nrc.gov.
Sincerely, IRA!
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNsirDprDdep Resource RidsNrrPMComanchePeak Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource DJohnson, NSIRIDDEP/ONRB/ORLT ADAMS Accession No.: ML093480455 RAI Received via e-mail dated November 13 , 2009 OFFICE NRR/LPL4/PM NRR/LPL4/LA NSIR/ORLOB NRR/LPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt JAnderson* MMarkley BSingal DATE 12/23/09 12/16/09 11/13/09 12/23/09 12/23/09 OFFICIAL AGENCY RECORD