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MONTHYEARML1011602662010-06-0101 June 2010 University of Missouri at Columbia - Request for Additional Information License Renewal, Safety Analysis Report, 45-Day Response Questions Project stage: RAI ML1008800852010-07-21021 July 2010 Fleet - Acceptance Review Implementation of Emergency Action Level Schemes Developed from NEI 99-01m Rev. 5 Project stage: Acceptance Review ML1021505302010-07-29029 July 2010 Attachment to Draft RAIs -Exelon EAL Upgrade Project Project stage: Draft RAI ML1021505272010-07-29029 July 2010 Draft NRC RAI Dresden and Quad - Emergency Action Levels Based on NEI 99-01 Rev 5 Project stage: Draft RAI ML1023804012010-08-24024 August 2010 Request for Exemption from Physical Security Requirements Project stage: Request ML1029400142010-10-17017 October 2010 Supplement to Request for Exemption from Physical Security Requirements Project stage: Supplement ML1029206912010-10-17017 October 2010 Supplement to Request for Exemption from Physical Security Requirements Project stage: Supplement ML1032105082010-11-16016 November 2010 Units 1 & 2 - Electronic Transmission, Draft Request for Additional Information Regarding Request to Implement Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Project stage: Draft RAI ML1031203322010-12-14014 December 2010 Emergency Action Level Scheme Change to NEI 99-01; Revision 5 Project stage: Other ML1034101262010-12-28028 December 2010 Request for Additional Information Implementation of Emergency Action Level Schemes Developed from NEI 99-01, Revision 5 Project stage: RAI ML1036305532011-01-0606 January 2011 Summary of Meeting (Teleconference) with Exelon to Discuss RAI Regarding the Implementation of an Emergency Action Level Scheme Based on NEI 99-01, Rev. 5 Project stage: RAI ML1116500972011-06-30030 June 2011 Fleet - Approval of Change from Emergency Action Level Scheme Based on NEI 99-01, Revision 4, to NEI 99-01, Revision 5 Project stage: Other ML1131301972011-11-10010 November 2011 University of Missouri, Columbia - Approval for Request of Additional Time to Respond to NRC Request for Additional Information License Renewal (Tac No. ME3034) Project stage: RAI 2010-07-21
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Category:Memoranda
MONTHYEARML23324A4332024-01-23023 January 2024 10/16-17/2023 Summary of Routine NRC Site Visit at the Oyster Creek Nuclear Generating Station to Discuss License Termination Plans and Other Technical Topics ML22308A2392022-11-0808 November 2022 Documentation of Approval for Longer Review Period for Limerick Digital Instrumentation and Control License Amendment Requests Acceptance Review ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21277A2472021-11-0505 November 2021 Notification of Significant Licensing Action - Proposed Issuance of Order Approving the Transfer of Licenses for Which a Hearing Has Been Requested - Exelon Generation Company, LLC; Et. Al ML20150A3252020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Oyster Creek ISFSI ML19295G4922019-10-24024 October 2019 Summary of the October 3, 2019, Public Meeting Near the Oyster Creek Nuclear Generating Station Regarding the Establishment and Operation of Community Advisory Boards ML18205A5502018-08-0606 August 2018 Memorandum to File - Public Feedback to 7/17/18 Public Meeting in Forked River, Nj, to Receive Public Comments on Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate ML18138A3442018-05-22022 May 2018 2018 Limerick Summary of Public Meeting and Attendance List ML18102A1072018-04-18018 April 2018 Annual Assessment Meeting Summary 2018 ML17151A2702017-05-31031 May 2017 Annual Assess Meeting Summary and Attendees ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17132A2242017-05-10010 May 2017 May 25, 2017, Oyster Creek Nuclear Generating Station Public Meeting Notice ML17075A0172017-03-16016 March 2017 Meeting Summary Memorandum - Regulatory Conference March 9, 2017 ML17037B8502017-02-0606 February 2017 08/21/1975 Notice of Meeting with Architect Engineers of Mark II Owners to Discuss Load Combinations and Analytical Techniques for Determining Stresses in Mechanical Components and Structures of Mark II Containments ML16344A2192016-12-12012 December 2016 Safety Evaluation for Limerick, Units 1 and 2, Proposed License Amendment to Revise the Technical Specifications to Address the High-Pressure Coolant Injection Operability Requirement Under Low Reactor Pressure Conditions ML16221A6152016-08-19019 August 2016 Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC Regarding a Presubmittal Physical Security Plan Change for Decommissioning at the Oyster Creek Nuclear Generating Station ML16221A6122016-08-0808 August 2016 Draft Request for Additional Information ML16221A6712016-08-0808 August 2016 Draft Request for Additional Information ML16174A2982016-06-22022 June 2016 Draft Request for Additional Information ML16166A0862016-06-14014 June 2016 Draft Request for Additional Information ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16085A0252016-03-24024 March 2016 Draft Request for Additional Information ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML16035A0362016-02-0505 February 2016 February 3, 2016, Summary of Closed Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Regarding Security Plan Change for the Oyster Creek Nuclear Generating Station ML16015A1402016-01-27027 January 2016 Forthcoming Closed Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding a Physical Security Plan Change for the Oyster Creek Nuclear Generating Station ML15239A4622015-08-28028 August 2015 54p PSP Rev 13 Close-out Letter 8-27-15 ML15202A3782015-07-21021 July 2015 Draft Request for Additional Information ML15028A4502015-01-27027 January 2015 LG-15-014 Verification of Readiness for Supplemental Inspection at Limerick Generating Station ML15035A1122015-01-10010 January 2015 LTR-15-0061 Lewis Cuthbert, President, Alliance for a Clean Environment, ACE, Letter Lessons Learned from Fukushima Related to Limerick Nuclear Plant ML14267A0762014-09-23023 September 2014 Acknowledgement Letter: B. Shank and C. Shank Regarding Limerick Nuclear Power Plant ML14247A6482014-09-10010 September 2014 Supplemental Safety Evaluation Report ML14220A5122014-09-0303 September 2014 Summary - Site Visit Regarding Physical Security License Amendment Request for Oyster Creek Nuclear Generating Station ML14190A9442014-08-11011 August 2014 Forwarding of Supplement 1 to the Safety Evaluation Report Related to the License Renewal of Limerick Generating Station, Units 1 and 2, Docket Numbers 50-352 and 50-353, to the Advisory Committee on Reactor Safeguards ML14210A5762014-07-29029 July 2014 Draft Request for Additional Information (Tac Nos. MF3198 and MF3199) ML14202A5182014-07-21021 July 2014 Draft Request for Additional Information (Tac Nos. MF3085 and MF3086) ML14055A5322014-03-11011 March 2014 Summary of Telephone Conference Call Held on January 30, 2014. Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Requests for Additional Information Pertaining to the Limerick Generating Station, ML14066A0972014-03-0707 March 2014 Draft Request for Additional Information ML14030A0942014-01-29029 January 2014 Draft Request for Additional Information (TAC Nos. MF1399 and MF1400) ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13199A5092013-09-18018 September 2013 Transmittal of Final Oyster Creek Nuclear Station Accident Sequence Precursor Analysis ML13240A2952013-09-10010 September 2013 Notice of Forthcoming Closed Meeting with the Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding a Pre-Submittal Physical Security License Amendment Request for Oyster Creek Nuclear Generating Station ML13190A3522013-07-10010 July 2013 Notice of Forthcoming Teleconference with Exelon Generation Company, LLC ML13156A0902013-06-26026 June 2013 Dseis Meeting Summary ML13109A5392013-05-0303 May 2013 5/23/2013 - Meeting Notice: Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Limerick Generating Station, Units 1 and 2 ML12348A6962012-12-17017 December 2012 1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans ML1227704332012-10-0101 October 2012 Minutes of the ACRS Plant License Renewal Subcommittee Meeting on September 5, 2012 (Open) ML12139A0612012-06-25025 June 2012 Summary of Telephone Conference Call Held on May 16, 2012, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Requests for Additional Information Pertaining to the Limerick Generating Station, Lice ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML1210403072012-04-12012 April 2012 Draft Request for Additional Information 2024-01-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24284A2032024-10-16016 October 2024 Enclosure 2 Revised Pending Request for Additional Information ML24284A1962024-10-16016 October 2024 Enclosure 1 Revised Request for Supplemental Information ML24274A2372024-10-0707 October 2024 – Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications ML24269A0462024-10-0404 October 2024 Cover Letter for Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Acceptance Review Request for Additional Information ML24269A0492024-10-0404 October 2024 Enclosure 1, Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Request for Supplemental Information ML24199A1842024-07-15015 July 2024 RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24150A0242024-05-29029 May 2024 Notification of Commercial Grade Dedication Inspection (05000352/2024012 and 05000353/2024012) and Request for Information ML24079A2922024-03-21021 March 2024 Draft Request for Additional Information Regarding Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) - Non-Proprietary ML23276B4642023-10-0303 October 2023 NRR E-mail Capture - NRC Request for Additional Information Limerick TSTF-477 LAR ML23269A0522023-09-26026 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000352/2023010 and 05000353/2023010 ML23208A1942023-07-27027 July 2023 NRR E-mail Capture - Limerick Generating Station - Audit Plan for TSTF-477 LAR Review (L-2022-LLA-0174) ML23202A0682023-07-21021 July 2023 NRR E-mail Capture - NRC Request for Additional Information Re. TSTF-477 LAR ML23201A1262023-07-18018 July 2023 Additional RAIs for Limerick Generation Station, Units 1 and 2 - LAR and Exemption Request for Digital I&C Installation Support ML23173A0632023-06-20020 June 2023 RAIs for Limerick Generation Station, Units 1 and 2 - LAR and Exemption Request for Digital I&C Installation Support ML22320A1132022-11-21021 November 2022 Generation Station, Units 1 and 2 - Supplemental Information Needed for Acceptance of Digital Instrumentation and Controls License Amendment Requests ML22172A0752022-06-17017 June 2022 Response: Review and Feedback on Draft Limerick Digital License Amendment Request (L-2020-LRM-0041) ML22136A0032022-05-13013 May 2022 NRR E-mail Capture - NRC Request for Additional Information - Limerick License Amendment Request (L-2021-LLA-0042) ML22124A2862022-05-0404 May 2022 Information Needed to Provide Substantive Feedback on Human Factors Engineering Supporting the Planned Limerick Digital I&C License Amendment Request ML22103A2542022-04-19019 April 2022 Draft Request for Additional Information ML22089A1172022-03-30030 March 2022 Additional Comments and Questions on Constellations March 31st Presentation ML22045A4822022-02-14014 February 2022 Notification of Conduct of a Fire Protection Team Inspection ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21099A0442021-04-0808 April 2021 Enclosure - Request for Additional Information Related to Request for Approval of Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Only Emergency Plan Holtec Decommissioning International, LLC ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21048A3402021-02-11011 February 2021 Request for Information for Relief Request I4R-24 Associated with Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations ML21015A1852021-01-15015 January 2021 Temporary Instruction 2515/194 Inspection Documentation Request ML20335A3102020-11-30030 November 2020 RAI November 2020 Part 73 FOF Exemption Request ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20297A2382020-10-22022 October 2020 Fleet DQAP RAIs - Enclosure ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20156A2992020-06-0404 June 2020 RAI for RR to Use Inservice Testing Program Safety Relief Valve Testing ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20149K7012020-05-28028 May 2020 Request for Additional Information for License Amendment Request to Use Inservice Testing Program Safety Relief Valve Testing ML20134H8732020-05-12012 May 2020 E-mail - Request for Additional Information: Oyster Creek Request for Temporary Exemption from Part 73, Appendix B Requirements ML20098C4342020-04-0606 April 2020 Draft Request for Additional Information - Limerick Generating Station, Unit 1 - Emergency LAR to Increase Allowable MSIV Leakage ML19344A0332019-12-10010 December 2019 Request for Additional Information License Amendment Request to Adopt TSTF-505, Revision 2 Risk Informed Completion Times Exelon Generation Company Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 ML19344A0242019-12-0909 December 2019 Request for Additional Information (RAI) - Limerick Units 1 and 2: TSTF-505, Use of Risk Informed Completion Times (Ricts) for Actions to Be Taken When Limiting Conditions for Operation (Lcos) Are Not Met ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19263D2142019-09-20020 September 2019 Hdi PSDAR Environmental RAI Enclosure (002) ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19192A0312019-07-10010 July 2019 NRR E-mail Capture - LIMERICK-REQUEST for Additional Information: Risk Informed Completion Times TSTF-505, Revison 2, Provide RISK-INFORMED Completion Times - RITSTF Initiative 4B ML19168A0882019-06-17017 June 2019 Letter to R. W. Libra Alternative Request Pertaining to Dry Shielded Canisters Equipped with Boral Neutron Absorber Plates - Supplemental Information Needed (W/Enclosursi) ML19158A2772019-05-28028 May 2019 NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS ML19025A1172019-01-24024 January 2019 NRR E-mail Capture - for Your Action - RAI for Oyster Creek EP Exemption (Change to Adiabatic Heat-Up Calculation) 2024-07-15
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Text
November 16, 2010 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION AND LIMERICK GENERATING STATION, UNITS 1 AND 2 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO IMPLEMENT EMERGENCY ACTION LEVEL SCHEME CHANGE TO NEI 99-01, REVISION 5 (TAC NOS.
ME3037, ME3038, AND, ME3039)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on November 17, 2010 to Mr. Richard Gropp, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with Exelon in order to clarify the request dated December 22, 2009 (Agencywide Documents Access and Management System Accession No. ML100050503), to incorporate EALs. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed.
Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket Nos. 50-352, 50-353, and 50-219
Enclosure:
As stated
ML103210508 *Via E-mail OFFICE LPLI-2/PM LPLI-2/PM LPLIII-2/PM NSIR/ORLOB/BC NAME GEMiller* PBamford EBrown JAnderson*
DATE 11/17/10 11/17/10 11/17/10 11/16/10 DRAFT REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION, UNITS 1 AND 2 OYSTER CREEK NUCLEAR GENERATING STATION EMERGENCY ACTION LEVEL SCHEME CHANGE TO NEI 99-01, REVISION 5 DOCKET NOS. 50-352, 50-353, AND 50-219 By letter dated December 22, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100050503), Exelon Generation Company (Exelon) submitted a request for Nuclear Regulatory Commission (NRC) review and approval of revisions to the Emergency Plan (EP) Emergency Action Levels (EALs) for the subject plants. The proposed EP changes would incorporate EALs based on the NRC-endorsed methodology in Nuclear Energy Institute (NEI) 99-01, Revision 5, Methodology for Development of Emergency Action Levels, dated February 22, 2008 (ADAMS Accession No. ML080450149). To complete its review, the Nuclear Regulatory Commission (NRC) staff requests responses to the following request for additional information1. Please note that the majority of the questions request a justification for a deviation from the wording in NEI 99-01, Revision 5. When responding to these questions, you may propose to revise the wording in accordance with the endorsed guidance in lieu of providing the requested justification.
- 1. Please provide the missing Emergency Action Level (EAL) Basis Document pages (Oyster Creek, 3-8 through 3-26; Limerick 3-9 through 3-29), or provide justification as to why it has not been included with your submittal.
- 2. The paragraph from Section 3.1 that begins with EALs are for unplanned events differs from the standard EAL scheme (Section 3.9) of the endorsed guidance - Revision 5 to Nuclear Energy Institute (NEI) 99-01. Specifically, a statement that EALs are for unplanned events was introduced. Additionally, the statement regarding the potential for planned or unplanned evolutions to result in an EAL threshold being exceeded was omitted, while the statement that this these dont result in an EAL declaration was retained. Please provide a justification for the changes in wording.
- 3. Sections 3.9 Emergency Action Levels, 3.10 Treatment of Multiple Events and Classification Level Upgrading, and 3.11 Emergency Classification Level Downgrading, from the endorsed EAL guidance contain important information necessary to understand the intent of the guidance. Please provide justification as to why the information has not been incorporated.
1 Questions 9 and 11 are applicable only to Oyster Creek Enclosure
- 4. The following definitions are intended to be site-specific so as to prevent confusion with classification, as indicated in endorsed guidance. Please provide the site-specific definitions rather than the generic definition provided in the approved development guidance:
- 5. Please provide the definition for Independent Spent Fuel Storage Installation (ISFSI) as this is a term used with the site-specific EAL document and is defined in Revision 5 to NEI 99-01, which the submittal is based upon. Additionally, as discussed in RAI 4, please ensure that this definition contains site specific information in addition to what is included in the standard wording.
- 6. The proposed definition of Civil Disturbance includes a minimum number of 5 participants. In the development of NEI 99-01, Revision 5, the specific number of people required to constitute a civil disturbance was removed, recognizing that number of persons involved is not as important as the activities they are involved in. Please provide a justification for defining a minimum number of participants.
- 7. For EAL RS1, the following paragraph from the endorsed guidance is not considered to be developmental and is annotated improperly in the endorsed EAL development guidance. This information provides insight into why this EAL was chosen versus others and may be germane to subsequent revisions to the EALs under 10 CFR 50.54(q).
Please justify its omission from the EAL scheme:
While these failures are addressed by other Initiating Conditions (IC), this IC provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or methodology.
- 8. For EAL RG1, the following paragraph from the approved guidance is not considered to be developmental and is annotated improperly in the endorsed EAL development guidance. This information provides insight into why this EAL was chosen versus others and may be germane to subsequent revisions to the EALs under 10 CFR 50.54(q).
Please justify its omission from the EAL scheme:
While these failures are addressed by other ICs, this IC provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or methodology.
- 9. (Oyster Creek Only) For EAL RS1, the technical basis information for EAL #1 states, Amp readings for the Main Stack RAGEMS HRM instrument are read on Panel 1R (MCR) or locally. EALs are required to be based upon information readily available to Main Control Room (MCR) personnel. As such, local indications do not suffice to ensure timely EAL classification. Please revise to remove or locally from the technical basis for this EAL, or provide further justification ensuring the ability to classify in a timely manner.
- 10. For EALs RA1 and RU1, the IC states, Radiological Effluent Technical Specifications/ODCM [Offsite Dose Calculation Manual]. Please verify that the wording aligns with the title of the facilities document.
- 11. (Oyster Creek Only) For EAL RU2, please explain how the EAL #2 threshold, or valid upscale reading, can suffice for this EAL. Criteria in endorsed guidance (Section 3.8, 2nd paragraph) states, For those conditions that are easily measurable and instrumented, the boundary is likely to be the EAL (observable by plant staff, instrument reading, alarm setpoint, etc) that indicates entry into a particular emergency classification level. Please explain how the time it takes to determine if an upscale reading is based upon instrument failure or based upon a saturated radiation element can be acceptable for timely EAL classification, or remove the statement or valid upscale reading.
- 12. The endorsed guidance for EAL AA3 (equivalent to RA3 for Oyster Creek and Limerick)
Directs declaration of an alert upon detection of dose rate greater than 15 mR/hr in any of areas listed in a site specific table. For the proposed RA3, the wording of Dose rate
> 15 mR/hr in areas requiring continuous occupancy (Table R3) to maintain plant safety functions is ambiguous as to whether an elevated dose rate in any or all of the locations in the table requires declaration of the EAL. Additionally, since the Central Alarm Station is the primary location for control of security related functions, it is unclear why the Secondary Alarm Station has been added to Table R3. The original intent of this list was to include the primary locations for accomplishing a function. Please justify the wording of the EAL threshold and contents of Table R3.
- 13. For EAL RU3, this EAL corresponds to SU4 in endorsed guidance, which specifically has this EAL as part of the Systems Malfunction Category, not as part of the Abnormal Rad Levels/Radiological Effluent Category. Using an appropriate category is important to ensure timely classification. Please provide a justification as to why you have categorized Fuel Clad degradation in the Abnormal Rad Levels/Radiological Effluent Category versus Systems Malfunction Category.
- 14. Please justify why the Fission Product Barrier Matrix Table has not been included.
- 15. For Fission Barrier threshold RC2.C, please explain the inclusion of Indications of RCS leakage in the drywell. While the basis statement indicates that this is to discriminate between an actual loss of RCS barrier and shine from failed Fuel Clad with an intact RCS barrier, it is unclear how this determination will be made. Additionally, it is unclear how making this determination will be done in a timely manner. Please provide a
justification for allowing this discriminating factor and for how indications of RCS leakage can be identified in a timely manner.
- 16. For EALs MU2, MU3, MU4, MU5, MU8, MU9, MU10, MA2, MA5, MA8, MS8, and MG8, the endorsed guidance has these EALs in their own unique table (and category) and with their own unique IC designation, for EALs applicable in Cold/Refuel Operating Modes. Please provide a justification for this deviation.
- 17. For EAL MU7, the endorsed guidance for this EAL states, However, a relief valve that operates and fails to close per design should be considered applicable to this IC if the relief valve cannot be isolated. The submittal states, Relief valve operation should be excluded from this EAL. Please justify why the remainder of the detailed information related to relief valve operation is not included with this EAL.
- 18. For EAL MU8, please justify why the entire paragraph related to relief valve operation is not included with this EAL.
- 19. For EAL MU10, the list of communication options for offsite communications must be limited to communication systems that can readily perform required notifications for licensee event classification and protective action recommendations to State and local response agencies, as well as the NRC. Please provide documentation that supports the conclusion that the stated list of offsite communication systems can perform as expected.
- 20. For EAL HU3 (EAL #2), the proposed wording includes the addition of the words, resulting in damage to permanent structure or equipment directly associated with plant operations. Please justify the inclusion of this caveat into the EAL, including how timely declaration of the EAL is possible if verification of damage is required prior to declaration. Additionally, HA3 uses the EAL defined term VISIBLE DAMAGE, while HU3 uses damage. Please clarify the difference in these two terms and explain why the EAL defined term was not used in HU3.
- 21. For EAL HA4:
- a. The endorsed EAL development guidance (EAL HU1, #5) states, Site specific occurrences affecting the protected area. In addition, the basis section of the endorsed guidance states, This EAL addresses other site specific phenomena (such as hurricane, flood, or seiche) that can also be precursors of more serious events. Please provide documentation to support your apparent conclusion that no additional hazards are applicable to your site.
- b. The submittal states, The phrase in plant is meant to include buildings and structures associated with plant operations and to rule out buildings or structures such as warehouses, administrative buildings or bullet resistant enclosures (BRE), which would not be a precursor of potential degradation of level of safety. This statement is not in the endorsed guidance and the staff cannot determine if this statement is acceptable for use as the submittal did not clearly state why this was needed, nor did the submittal
document the impact this statement has on timely EAL classification. Provide additional justification for the deviation.
- 22. For EAL HU4, the submittal states, The phrase in plant is meant to include buildings and structures associated with plant operations and to rule out buildings or structures such as warehouses, administrative buildings or bullet resistant enclosures (BRE), which would not be a precursor of potential degradation of level of safety. This statement is not in the endorsed guidance and the staff cannot determine if this statement is acceptable for use as the submittal did not clearly state why this was needed, nor did the submittal document the impact this statement has on timely EAL classification. Provide additional justification for the deviation.
- 23. For EAL HA5, the submittal contained deviations without sufficient justification to reach a conclusion as to their acceptability. Please provide additional justification for the following deviations to support that they do not negatively impact the timeless of EAL classification:
- a. The 3rd paragraph added, A precautionary area evacuation for the purpose of atmospheric testing does not warrant declaration until test results are obtained.
However, declaration should not be delayed for atmospheric testing after an inadvertent actuation of installed Cardox fire suppression systems, or for gas releases that result in personnel ill effects from exposure.
- b. The submittal deleted the 2nd and 3rd paragraphs from the approved EAL guidance which state:
Declaration should not be delayed for confirmation from atmospheric testing if the atmosphere poses an immediate threat to life and health or an immediate threat of severe exposure to gases. This could be based upon documented analysis, indication of personal ill effects from exposure, or operating experience with the hazards.
If the equipment in the stated area was already inoperable, or out of service, before the event occurred, then this EAL should not be declared as it will have no adverse impact on the ability of the plant to safely operate or safely shutdown beyond that already allowed by Technical Specifications at the time of the event.
- 24. For EAL HU5, the 4th paragraph in the submittal added, A precautionary area evacuation for the purpose of atmospheric testing does not warrant declaration until test results are obtained. However, declaration should not be delayed for atmospheric testing after an inadvertent actuation of installed Cardox fire suppression systems, or for gas releases that result in personnel ill effects from exposure. Please provide additional justification to support the conclusion waiting for test results would not impact the timeliness of an EAL declaration.
- 25. For EAL HU7, the endorsed guidance has this ISFSI-specific EAL as a stand-alone EAL.
Your submittal proposes to incorporate this EAL into one of the pre-existing categories.
Please justify this deviation. This justification for deviation from the endorsed guidance should address why the Hazards Category was chosen and why the use of this category will not cause an unnecessary delay in classification (i.e., explain why the Abnormal Radiation category is not more appropriate).