|
---|
Category:Letter
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 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 ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
[Table view] Category:Safety Evaluation
MONTHYEARML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML22361A0702023-02-24024 February 2023 Issuance of Amendment No. 231 for Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ML23019A1752023-01-30030 January 2023 Issuance of Amendment No. 230 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22301A0072022-12-0202 December 2022 Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2 ML22220A1302022-10-21021 October 2022 Exemptions from the Requirements of 10 CFR 50.46 and 10 CFR Part 50 Appendix a, General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (Cover Letter) ML22220A1322022-10-21021 October 2022 Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach ML22053A2832022-04-0707 April 2022 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML21344A0052021-12-29029 December 2021 Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML21053A1262021-03-24024 March 2021 Issuance of Amendment No. 225 to Revise Technical Specification Administrative Control 5.3.1 to Remove Details Specified for the Qualification of Certain Positions within the Unit Staff ML20218A4102020-11-0303 November 2020 Issuance of Amendment No. 224 Performance Based Method Alternative for Thermal Insulation Material ML20246G5702020-10-16016 October 2020 Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections ML20230A3872020-08-31031 August 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20216A6812020-08-0606 August 2020 Operating Quality Assurance Manual Change Revision 34B (EPID L-2020-LLQ-0004 (COVID-19)) ML20141L7452020-06-0808 June 2020 Operating Quality Assurance Manual Change Revision 34A ML20107H9782020-04-20020 April 2020 COVID-19 Relief Request CC-01 Containment Tendon Inspection ML19283C4812019-12-0606 December 2019 Issuance of Amendment No. 221 Main Turbine Control Slave Relay Testing ML19158A2902019-07-30030 July 2019 Issuance of Amendment No. 220 Regarding Emergency Action Level Scheme Changes ML19073A0012019-04-18018 April 2019 Issuance of Amendment No. 219 to Add New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System ML19079A1482019-04-0101 April 2019 Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051 ML18313A0692018-11-26026 November 2018 Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping ML18124A0262018-05-30030 May 2018 Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection ML17262A7002017-10-0303 October 2017 Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval ML17254A1202017-09-25025 September 2017 Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval ML17236A0822017-09-15015 September 2017 Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr), ML17170A3202017-06-20020 June 2017 Safety Evaluation Input - for Ameren Missouri Request to Amend Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report - ML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML17010A3322017-02-0202 February 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16223A7122016-08-30030 August 2016 Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval ML16089A1672016-04-0101 April 2016 Review and Approval of Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 14-05A, Revision 1 ML16055A4642016-03-17017 March 2016 Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737) ML16020A5162016-02-29029 February 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 2.1.1.1 and TS 5.6.5, to Remove Uncertainties from Departure from Nucleate Boiling Ratio Safety Limit and Adopt WCAP-14565-P-A Methodology ML15324A1142016-02-0202 February 2016 Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML16027A1582016-01-29029 January 2016 Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval ML15328A0592016-01-28028 January 2016 Issuance of Amendment No. 214, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15258A5102015-10-28028 October 2015 Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15251A4932015-10-0707 October 2015 Issuance of Amendment No. 212, Request to Upgrade the Emergency Action Level Scheme by Adopting Nuclear Energy Institute NEI 99-01, Revision 6 ML15064A1252015-05-12012 May 2015 Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval ML15064A0282015-03-31031 March 2015 Issuance of Amendment No. 211, Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML15035A1482015-02-10010 February 2015 Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval ML14350B2392015-01-20020 January 2015 Issuance of Amendment No. 210, Revise Technical Specification LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4-6 ML14234A4512014-09-0404 September 2014 Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval ML14178A7692014-07-15015 July 2014 Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval ML14175A3902014-07-0101 July 2014 Issuance of Amendment No. 209, Adoption of Technical Specification Task Force Change Traveler TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using CLIIP ML14027A0572014-01-29029 January 2014 Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval 2024-01-18
[Table view] |
Text
November 8, 2006 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - REVISION OF EMERGENCY ACTION LEVELS IN RADIOLOGICAL EMERGENCY RESPONSE PLAN (TAC NO. MD3192)
Dear Mr. Naslund:
By letter dated October 3, 2006 (ULNRC-05336), as supplemented by letter dated October 24, 2006 (ULNRC-05339), Union Electric Company (UEC) requested approval of a change to Emergency Action Levels (EALs) 3I and 3J of the Radiological Emergency Response Plan for the Callaway Plant, Unit 1 (Callaway). The changes to the EALs will prevent unnecessary declarations of Unusual Events and Alerts at Callaway; however, because UEC considered the changes a reduction in plan effectiveness, the Commission was requested, in accordance with paragraph 50.54(q) of Part 50, Domestic Licensing of Production and Utilization Facilities, of Title 10 of the Code of Federal Regulations (10 CFR 50.54(q)) to approve the changes.
As discussed in the enclosed safety evaluation, the Commission concludes that the above proposed EAL changes meet the standards of 10 CFR 50.47(b) and the requirements of Section IV.B of Appendix E to 10 CFR Part 50, and are, therefore, acceptable.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Safety Evaluation cc w/encl: See next page
ML062980278 OFFICE NRR/LPL4/PM NRR/LPL4/LA NSIR/LRB/BC OGC-NLO w/changes NRR/LPL4/BC NAME JDonohew LFeizollahi EWeiss BPoole DTerao DATE 11/8/06 11/8/06 10/16/06 11/8/06 11/8/06 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO CHANGES TO RADIOLOGICAL EMERGENCY RESPONSE PLAN UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By application dated October 3, 2006 (Reference 1), as supplemented by letter dated October 24, 2006 (Reference 2) (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML062850223 and ML063050140, respectively), the Union Electric Company (the licensee) requested changes to the emergency action levels (EALs) for the Plant Radiological Emergency Response Plan (RERP) for the Callaway Plant, Unit 1 (Callaway). The licensees proposed changes would revise the following EALs:
! Group 3 - EAL I: This EAL is being revised to conform to Nuclear Energy Institute (NEI) 99-01 Revision 4 EAL HU3, Release of Toxic or Flammable Gases Deemed Detrimental to Normal Operation of the Plant.
! Group 3 - EAL J: This EAL is being revised to conform to NEI 99-01 Revision 4 EAL HA3, Release of Toxic or Flammable Gases Within or Contiguous to a Vital Area Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or Establish or Maintain Safe Shutdown.
2.0 REGULATORY EVALUATION
2.1 Regulations Paragraph (a)(1) to Section 50.47, Emergency Plans, of Part 50, Domestic Licensing of Production and Utilization Facilities, to Title 10 of the Code of Federal Regulations (10 CFR 50.47(a)(1)) states that no initial operating license for a nuclear power reactor will be issued unless a finding is made by the Nuclear Regulatory Commission (NRC) that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Section 50.47 also establishes standards that must be met by the onsite and offsite emergency response plans for NRC staff to make a finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. One of these standards, 50.47(b)(4), requires that emergency plans include a standard emergency classification and action level scheme.
Section IV.B to Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, of 10 CFR Part 50 provides, among other things, that emergency plans are to include EALs to be used as criteria for determining the need for notification and participation of local and State agencies, the Commission, and other Federal agencies, and EALs to be used for determining when and what type of protective measures should be considered within and outside the site boundary (i.e., onsite and offsite) to protect health and safety. EALs are to be based on in-plant conditions and instrumentation, and on onsite and offsite monitoring.Section IV.B of Appendix E provides that initial EALs shall be discussed and agreed on by the applicant and State and local governmental authorities and be approved by the NRC. EALs are to be reviewed annually thereafter with State and local governmental authorities. In addition,Section IV.B of Appendix E requires that an EAL revision shall be approved by the NRC before implementation if it involves the following:
- 1. Changing from one EAL scheme to another EAL scheme (e.g., a scheme based on NUREG-0654/FEMA-REP-1 to a scheme based on NUMARC/NESP-007 or NEI 99-01),
- 2. Proposal of an alternate method for complying with the regulations, or
- 3. The EAL revision decreases the effectiveness of the emergency plan.
2.2 Guidance Revision 4 to Regulatory Guide (RG) 1.101, issued in July 2003, endorses the guidance contained in NEI 99-01, Methodology for Development of Emergency Action Levels (Revision 4, January 2003), as acceptable to the NRC staff as an alternative method to that described in the following guidance for developing EALs required in Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4):
- Appendix 1 to NUREG-0654/FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (November 1980), and
- Nuclear Utilities Management Council (NUMARC) NESP-007, Methodology for Development of Emergency Action Levels (Revision 2, January 1992).
Regulatory Issue Summary (RIS) 2003-18, Use of NEI 99-01, Methodology for Development of Emergency Action Levels, dated October 8, 2003, (as well as Supplements 1 and 2 thereto, dated July 13, 2004, and December 12, 2005, respectively), provides guidance for developing or changing a standard emergency classification and action level scheme. In addition, this RIS provided recommendations to assist licensees, consistent with Section IV.B to Appendix E of Part 50, in determining whether to seek prior NRC approval of deviations from the new guidance.
3.0 TECHNICAL EVALUATION
The licensee evaluated the proposed revisions to the Callaway RERP EALs and determined that the revisions would constitute a decrease in the effectiveness of the RERP. As such, it
submitted the proposed EAL changes to the NRC (Reference 1) for approval prior to implementation as required under Section IV.B to Appendix E of Part 50 and 10 CFR 50.54(q).
The licensees application is consistent with the guidance set forth in RIS 2003-01.
The following evaluation by the NRC staff is based on the proposed revision to the EALs in the licensees application and supplemental letter (Reference 2), which responded to the NRCs request for additional information.
Callaway utilizes an EAL scheme based upon NESP-007, Methodology for Development of Emergency Action Levels (Revision 2, January 1992).
The Group 3 EAL I, Release of Toxic or Flammable Gases Deemed Detrimental to Normal Operation of the Plant, is being revised by the licensee to conform to NEI 99-01 (Revision 4),
EAL HU3. This EAL is conservative because, as stated by the licensee, the EAL initiating condition for release of toxic or flammable gases is reached at a lower initiating level than that set forth in NEI 99-01, Revision 4, which in effect directs the licensee to declare an emergency event sooner than is necessary or required during normal plant operations involving toxic or flammable gases. Because this conservatism is not required by the regulations and requires the licensee to declare events sooner than is necessary, the licensee is seeking relief by requesting a change to remove the conservatism and have the EAL conform to the wording set forth in NEI 99-01 (Revision 4), which was endorsed by NRC in RG 1.101, Revision 4.
The Group 3 EAL J, Release of Toxic or Flammable Gases Within or Contiguous to a Vital Area Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or Establish or Maintain Safe Shutdown, is being revised to conform to NEI 99-01 (Revision 4),
EAL HA3. This EAL is conservative because, as stated by the licensee and discussed above, the EAL initiating condition for release of toxic or flammable gases is reached at a lower initiating level than that set forth in NEI 99-01, Revision 4, which in effect directs the licensee to declare an emergency event sooner than is necessary or required during normal plant operations involving toxic or flammable gases. Because this conservatism is not required by the regulations and requires the licensee to declare events sooner than is necessary, the licensee is seeking relief by requesting a change to conform to the wording set forth in NEI 99-01 (Revision 4), which, as stated above, was endorsed by NRC.
Based on the above discussion, the NRC staff concludes that the proposed changes only remove conservatisms in the existing EALs to adopt EALs that are consistent with NEI 99-01 (Revision 4), which has been endorsed by NRC.
4.0 CONCLUSION
The NRC staff performed a review of the proposed changes to the Callaway EALs described in Reference 1, as supplemented by Reference 2, and determined they are consistent with the guidance of NEI 99-01, Revision 4, which has been endorsed by NRC. As such, the NRC staff concludes that the proposed EAL changes meet the requirements of 10 CFR 50.47(b) and Section IV.B of Appendix E to 10 CFR Part 50 and are, therefore, acceptable.
5.0 REFERENCES
- 1. Letter Number ULNRC-05336 from Union Electric Company to the NRC, Emergency Preparedness, dated October 3, 2006, licensees application (ADAMS Accession No. ML062850223).
- 2. Letter Number ULNRC-05339 from Union Electric Company, Emergency Preparedness EAL Revision, dated October 24, 2006, response to request for additional information (ADAMS Accession No. ML063050140).
- 3. Nuclear Utilities Management Council (NUMARC) document, entitled NESP-007, Methodology for Development of Emergency Action Levels, Revision 2, dated January 1992 (ADAMS Accession No. ML041120174).
- 4. NEI 99-01, Methodology for Development of Emergency Action Levels, Revision 4, dated January 2003 (ADAMS Accession No. ML041470143).
- 5. Emergency Planning and Preparedness for Nuclear Power Reactors, Regulatory Guide 1.101, Revision 4 (ADAMS Accession No. ML032020276).
Principal Contributor: Don Johnson Date: November 8, 2006
Callaway Plant, Unit 1 cc:
Professional Nuclear Consulting, Inc. Mr. Dan I. Bolef, President 19041 Raines Drive Kay Drey, Representative Derwood, MD 20855 Board of Directors Coalition for the Environment John ONeill, Esq. 6267 Delmar Boulevard Pillsbury Winthrop Shaw Pittman LLP University City, MO 63130 2300 N. Street, N.W.
Washington, D.C. 20037 Mr. Lee Fritz, Presiding Commissioner Callaway County Court House Mr. Keith A. Mills, Supervising Engineer 10 East Fifth Street Regional Regulatory Affairs/Safety Analysis Fulton, MO 65151 AmerenUE P.O. Box 620 Mr. David E. Shafer Fulton, MO 65251 Superintendent, Licensing Regulatory Affairs U.S. Nuclear Regulatory Commission AmerenUE Resident Inspector Office P.O. Box 66149, MC 470 8201 NRC Road St. Louis, MO 63166-6149 Steedman, MO 65077-1302 Manager, Regulatory Affairs Mr. Les H. Kanuckel AmerenUE Manager, Quality Assurance P.O. Box 620 AmerenUE Fulton, MO 65251 P.O. Box 620 Fulton, MO 65251 Mr. Keith G. Henke, Planner Division of Community and Public Health Missouri Public Service Commission Office of Emergency Coordination Governor Office Building 930 Wildwood P.O. Box 570 200 Madison Street Jefferson City, MO 65102 Jefferson City, MO 65102-0360 Certrec Corporation Regional Administrator, Region IV 4200 South Hulen, Suite 630 U.S. Nuclear Regulatory Commission Fort Worth, TX 76109 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Director, Missouri State Emergency Management Agency Mr. H. Floyd Gilzow P.O. Box 116 Deputy Director for Policy Jefferson City, MO 65102-0116 Missouri Department of Natural Resources P. O. Box 176 Jefferson City, MO 65102-0176 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839