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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-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24019A0742024-01-19019 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 ML23256A1502023-09-11011 September 2023 Request for Additional Information Requests - Comanche Peak - Set 4 ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - 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 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 ML23167A0232023-06-14014 June 2023 Request for Additional Information (RAI) for the Review of the Comanche Peak Initial License Renewal Application (Lra), Set 1 ML23145A2322023-05-25025 May 2023 LRA - Request for Confirmation of Information - Set 2 ML23143A1372023-05-23023 May 2023 LRA - Request for Confirmation of Information - Set 1 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 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 ML22179A3032022-06-28028 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 ML16015A0032016-01-14014 January 2016 NRR E-mail Capture - Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 ML15345A0112015-12-16016 December 2015 Request for Additional Information, License Amendment Request, Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML15317A1582015-11-13013 November 2015 Request for Additional Information Email, Relief Request B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval ML15317A1482015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-9 for Reactor Pressure Vessel Outlet Nozzle Safe End to Piping Welds, Second 10-year Inservice Inspection Interval ML15317A1502015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-3 for Reactor Coolant System Pipe to Pipe Flange Weld, Second 10-year Inservice Inspection Interval 2024-01-19
[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