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| | number = ML071520229 | | | number = ML071520229 |
| | issue date = 05/31/2007 | | | issue date = 05/31/2007 |
| | title = Three Mile Island Unit 1, Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors. | | | title = Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors. |
| | author name = Cowan P B | | | author name = Cowan P |
| | author affiliation = AmerGen Energy Co, LLC | | | author affiliation = AmerGen Energy Co, LLC |
| | addressee name = | | | addressee name = |
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| | document type = Letter, Technical Specifications | | | document type = Letter, Technical Specifications |
| | page count = 7 | | | page count = 7 |
| | | project = |
| | | stage = Other |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:10 CFR 50.90 10 CFR 50.68 May 31, 2007 5928-07-20107 U S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No. DPR-50 NRC Docket No. 50-289 |
| | |
| | ==Subject:== |
| | Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors |
| | |
| | ==Reference:== |
| | AmerGen letter to USNRC, Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors, dated December 12, 2006 The referenced letter requested a change to the TMI Unit 1 Technical Specifications (TS) to relocate the reactor building refueling area and spent fuel storage area radiation monitor operability requirements to the Updated Final Safety Analysis Report (UFSAR) and plant procedures, since these radiation monitors do not meet the criteria for inclusion in the TS as presented in 10 CFR 50.36(c)(2)(ii). During subsequent discussions with the NRC staff the issue of compliance with 10 CFR 50.68(b) was discussed. Accordingly, Enclosure 1 provides a description of the TMI Unit 1 evaluation of current compliance with the Fuel Storage Area Radiation Monitoring requirements of 10 CFR 50.68(b). |
| | Regulatory commitments established by this submittal are identified in Enclosure 2. If any additional information is needed, please contact David J. Distel at (610) 765-5517. |
| | |
| | U.S. Nuclear Regulatory Commission May 31,2007 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 31st day of May, 2007. |
| | Respectfully, Pamela B. cowan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC |
| | |
| | ==Enclosures:== |
| | : 1) TMI Unit 1 Evaluation of Current Compliance with 10 CFR 50.68(b) |
| | : 2) List of Commitments cc: S. J. Collins, USNRC Administrator, Region I P. J. Bamford, USNRC Project Manager, TMI Unit 1 D. M. Kern, USNRC Senior Resident Inspector, TMl Unit 1 File No. 06041 |
| | |
| | ENCLOSURE 1 TMI Unit 1 Evaluation of Current Compliance with 10 CFR 50.68(b) |
| | |
| | Enclosure 1 Page 1 of 2 ENCLOSURE 1 TMI Unit 1 Evaluation of Current Compliance with 10 CFR 50.68(b) 10 CFR 50.68(b) Each licensee shall comply with the following requirements in lieu of maintaining a monitoring system capable of detecting a criticality as described in 10 CFR 70.24: |
| | (I) Plant procedures shall prohibit the handling and storage at any one time of more fuel assemblies than have been determined to be safely subcritical under the most adverse moderation conditions feasible by unborated water. |
| | TMI Unit 1 complies with this criterion. Fuel handling procedures are based on the design basis numbers of fuel assemblies assumed in analyses for the new fuel and spent fuel storage racks. |
| | (2) The estimated ratio of neutron production to neutron absorption and leakage (k-effective) of the fresh fuel in the fresh fuel storage racks shall be calculated assuming the racks are loaded with fuel of the maximum fuel assembly reactivity and flooded with unborated water and must not exceed 0.95, at a 95 percent probability, 95 percent confidence level. This evaluation need not be performed if administrative controls and/or design features prevent such flooding or if fresh fuel storage racks are not used. |
| | TMI Unit 1 complies with this criterion for fresh fuel stored in the new fuel storage racks. (This criterion is not applicable for fresh fuel subsequently stored in the spent fuel storage racks.) |
| | (3) If optimum moderation of fresh fuel in the fresh fuel storage racks occurs when the racks are assumed to be loaded with fuel of the maximum fuel assembly reactivity and filled with low-density hydrogenous fluid, the k-effective corresponding to this optimum moderation must not exceed 0.98, at a 95 percent probability, 95 percent confidence level. This evaluation need not be performed if administrative controls and/or design features prevent such moderation or if fresh fuel storage racks are not used. |
| | TMI Unit 1 complies with this criterion for fresh fuel stored in the new fuel storage racks. (This criterion is not applicable for fresh fuel subsequently stored in the spent fuel storage racks.) |
| | (4) If no credit for soluble boron is taken, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. If credit is taken for soluble boron, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with borated water, and the k-effective must remain below 1.0 (subcriticai), at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. |
| | TMI Unit 1 complies with the applicable criterion for the Spent Fuel Pool A Region 1 racks. The Spent Fuel Pool A Region 2 and the Spent Fuel Pool 6 racks have a Technical Specification limit placed on them based on the fuel assembly initial enrichment and burnup. In addition a boron requirement of 600 ppm must be maintained when moving fuel assemblies in either pool to meet the NRC maximum allowable reactivity value under the postulated accident conditions. |
| | |
| | Enclosure 1 Page 2 of 2 (5) The quantity of SNM, other than nuclear fuel stored onsite, is less than the quantity necessary for a critical mass. |
| | TMI Unit 1 complies with this criterion based on the SNM, other than nuclear fuel, currently stored at TMI Unit 1. |
| | (6) Radiation monitors are provided in storage and associated handling areas when fuel is present to detect excessive radiation levels and to initiate appropriate safety actions. |
| | Radiation monitors that meet General Design Criteria 63 are located in the fuel handling areas. |
| | These monitors are able to detect radiation levels caused by a fuel handling accident or spent fuel that is too close to the water surface. These monitors have alarms that allow personnel to take appropriate safety actions. Plant procedures require that either these radiation monitors or an equivalent portable monitor must be inservice in order to move fuel. |
| | (7) The maximum nominal U-235 enrichment of the fresh fuel assemblies is limited to five (5.0) percent by weight. |
| | TMI Unit 1 complies with this criterion. The TMI Unit 1 Technical Specifications contain this limit for fresh fuel in the new fuel storage vault and the spent fuel pool A storage racks, and contain a limit of 4.37 percent by weight for fuel stored in the spent fuel pool 8 storage racks. |
| | (8) The FSAR is amended no later than the next update which 9 50.71(e) of this part requires, indicating that the licensee has chosen to comply with 5 50.68(b). |
| | The TMI Unit 1 Updated Final Safety Analysis Report will be amended no later than the next update which 10 CFR 50.71 (e) requires, to indicate that TMI Unit 1 has chosen to comply with 10 CFR 50.68(b). |
| | |
| | ENCLOSURE 2 List of Commitments |
| | |
| | ==SUMMARY== |
| | OF AMERGEN COMMITMENTS The following table identifies regulatory commitments made in this document by AmerGen. (Any other actions discussed in the submittal represent intended or planned actions by AmerGen. They are described to the NRC for the NRCs information and are not regulatory commitments.) |
| | COMMITMENT TYPE COMMITMENT COMMIlTED DATE OR OUTAGE PROGRAMMATIC The TMI Unit 1 Updated Final Safety Analysis Report will be Update 19 amended no later than the next (Spring 2008) update which 10 CFR 50.71 (e) requires, to indicate that TMI Unit 1 has chosen to comply with}} |
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MONTHYEARML0635401682006-12-12012 December 2006 Technical Specification Change Request No. 333 - Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors Project stage: Other ML0715202292007-05-31031 May 2007 Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors. Project stage: Other ML0716300572007-06-12012 June 2007 Electronic Transmission, Draft Request for Additional Information Regarding the Relocation of the Refuel and Spent Fuel Pool Radiation Monitors from the Technical Specifications to Licensee Controlled Documents Project stage: Draft RAI ML0716404332007-07-0303 July 2007 RAI, Relocation of Refuel and Spent Fuel Pool Area Radiation Monitors Technical Specification Amendment Project stage: RAI ML0719203542007-07-11011 July 2007 Response to Request for Additional Information - Technical Specification Change Request No. 333: Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors Project stage: Response to RAI ML0723403482007-09-26026 September 2007 Issuance of Amendment 260 Regarding Relocation of Technical Specification Requirements for Refueling and Spent Fuel Pool Area Radiation Monitors Project stage: Approval ML0726904252007-09-26026 September 2007 Tech Spec Pages for Amendment 260 Regarding Relocation of Technical Specification Requirements for Refueling and Spent Fuel Pool Area Radiation Monitors Project stage: Other 2007-06-12
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Category:Letter
MONTHYEARML24038A0222024-02-0505 February 2024 Achp Letter on Section 106 Programmatic Agreement Participation IR 05000289/20230062024-01-29029 January 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006 ML23342A1242024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23325A1092024-01-0505 January 2024 Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 IR 05000320/20230032023-11-28028 November 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003 ML23243A9082023-08-29029 August 2023 Shpo Letter to TMI-2 Regarding Section 106 Activities IR 05000320/20230022023-08-17017 August 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23200A1882023-07-31031 July 2023 TMI-2 Correction Letter Amendment 67 ML23209A7632023-07-28028 July 2023 Letter from PA Shpo to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning ML23192A8272023-07-10010 July 2023 TMI-2 Solutions, LLC - Response to Shpo Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23167A0312023-06-28028 June 2023 Acceptance Review and Schedule for the Request for Exemption from a Requirement from 10 CFR 20, Appendix G, Section Iii.E, EPID L-2023-LLE-0016 ML23171B0222023-06-19019 June 2023 (TMI-2) - Notification Pursuant to 10 CFR 72.140(d) Regarding Application of Previously Approved TMI-2 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities ML23137A2822023-05-17017 May 2023 (TMI-2), Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 ML23026A3132023-05-0202 May 2023 Issuance of Exemption from 10 CFR 70.24 (EPID-L-2023-LLE-0003) ML23122A1842023-05-0101 May 2023 Shpo_Er_Summary_Letter ML23121A2492023-05-0101 May 2023 License Amendment Request, Historic and Cultural Resources Review, Response to Request for Additional Information ML23117A0012023-04-26026 April 2023 Commitment Revision Summary Report ML23027A0832023-04-24024 April 2023 Environmental Assessment/Finding of No Significant Impact - Request for Exemption from 10 CFR 70.24 ML23108A0802023-04-18018 April 2023 Annual Radiological Effluent Release Report ML23108A0822023-04-18018 April 2023 Annual Radiological Environmental Operating Report IR 05000320/20230012023-04-12012 April 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report No. 05000320/2023001 ML23102A0382023-04-10010 April 2023 Occupational Radiation Exposure Annual Report ML23108A2002023-04-10010 April 2023 CFR 20.2206(b) Personnel Radiation Exposure Report for 2022 ML23094A2582023-04-0606 April 2023 Letter to Sidney Hill, Chief, Onondaga Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0572023-04-0606 April 2023 Letter to Joanna Cain, President, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2362023-04-0606 April 2023 Letter to Carissa Speck, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2542023-04-0606 April 2023 Ltr J Bendremer Thpo Stockbridge-Munsee Community Band of Mohican Indians Re Initiation of Consultation Under Section 106 of the NHPA for Proposed License Amendment Request for TMI 2 ML23086C0652023-04-0606 April 2023 Ltr Larry Heady, Thpo, De. Tribe of Indian; Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI Nuclear Station, Unit 2 ML23093A0562023-04-0606 April 2023 Letter to Steve Minnick, Site Decommissioning Director, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2602023-04-0606 April 2023 Letter to William Tarrant, Seneca-Cayuga Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23094A2392023-04-0606 April 2023 Letter to Courtney Gerzetich, Thpo, Onedia Nation of Wisconsin, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0592023-04-0606 April 2023 Letter to Rebecca Countess, Chair, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 2024-02-05
[Table view] Category:Technical Specifications
MONTHYEARML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications ML22087A3942022-03-28028 March 2022 Supplemental Information Supporting License Amendment Request - Proposed Revision to License Conditions and Permanently Defueled Technical Specifications for Permanent Removal of Irradiated Fuel from the Spent Fuel Pool (ISFSI-Only Technica ML21118A0572021-04-13013 April 2021 Submittal of Changes to Technical Specifications Bases ML20352A3812020-12-18018 December 2020 TMI-2 License Transfer Conforming Amendment ML20261H9252020-12-0202 December 2020 Issuance of Amendment No. 299 for Unit 1 Permanently Defueled Emergency Plan and Emergency Action Level Scheme Changes ML19065A1142019-04-18018 April 2019 Issuance of Amendment No. 296 for Unit 1 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML19065A2172019-03-0606 March 2019 Supplement - License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML15225A1582015-10-0101 October 2015 Issuance of Amendment for Temporary Restoration of the Borated Water Storage Tank Cleanup and Recirculation Operation (TAC No. 6504) ML15090A5842015-07-28028 July 2015 Issuance of Amendments Technical Specifications to Modify Reactor Coolant System Pressure Isolation Check Valve Maximum Allowable Leakage Limits ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) TMI-15-072, Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts2015-06-10010 June 2015 Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts TMI-15-064, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2015-05-0707 May 2015 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process TMI-13-033, Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report2013-04-10010 April 2013 Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report TMI-12-169, Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements2013-02-0404 February 2013 Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements TMI-12-064, Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications2012-04-11011 April 2012 Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications TMI-11-171, Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications2012-01-20020 January 2012 Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications TMI-11-103, License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes2011-10-18018 October 2011 License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves2010-09-24024 September 2010 Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves ML1003204932010-03-11011 March 2010 License Amendment Technical Specification Changes Adopting TSTF-490-A, Revision 0, Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification ML0927104632009-10-22022 October 2009 Renewed Facility Operating License ML0927104012009-10-22022 October 2009 Issuance of Renewed Facility Operating License No. DPR-50 for Three Mile Island, Unit 1 TMI-09-082, Response to Request for Additional Information Related to License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical....2009-07-0202 July 2009 Response to Request for Additional Information Related to License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical.... ML0831201222008-11-0606 November 2008 License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification Using the Consolidated Line Item Improvement.. ML0828001742008-09-29029 September 2008 Technical Specification Change Request No. 342 Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods ML0827402962008-09-15015 September 2008 Supplement: Technical Specification Change Request for Technical Specification Change Request (Tscr) No. 86 Deletion of Technical Specification Sections 6.5, Review and Audit ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. ML0809101272008-04-16016 April 2008 Technical Specifications to Amendment ML0807700842008-03-14014 March 2008 Additional Information for Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0727100352007-09-27027 September 2007 Tech Spec Pages for Amendment 261 Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Generic Letter 2006-01 ML0726904252007-09-26026 September 2007 Tech Spec Pages for Amendment 260 Regarding Relocation of Technical Specification Requirements for Refueling and Spent Fuel Pool Area Radiation Monitors ML0725402542007-09-0404 September 2007 Additional Information - Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0718003192007-06-29029 June 2007 Tech Spec Pages for Amendment 259, One-Time Type a Test Interval Extension ML0715606022007-06-0505 June 2007 Response to Request for Additional Information Concerning Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension ML0715202332007-05-31031 May 2007 Response to Request for Additional Information - Technical Specification Change Request No. 331 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0715202292007-05-31031 May 2007 Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors. ML0712302682007-04-27027 April 2007 Submittal of Changes to Technical Specification Bases ML0708609682007-03-22022 March 2007 Technical Specification Change Request No. 335, Incorporating Revised Limit or the Variable Low Reactor Coolant System Pressure-Temperature Core Protection Safety Limit ML0628303312006-10-0606 October 2006 Response to Request for Additional Information, Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0626800402006-09-15015 September 2006 Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension ML0614202942006-05-15015 May 2006 Technical Specification Change Request No. 331 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0610100612006-04-0808 April 2006 Technical Specification Page Allowed Outage Time Extension from 7 Days to 10 Days for Emergency Diesel Generator EG-Y-1A ML0528702192005-10-13013 October 2005 Issuance of Amendment Elimination of Containment Equipment Hatch Closure Requirement During Refueling, Technical Specifications ML0522703622005-08-12012 August 2005 Tech Spec Pages for Amendment 256 Missed Surveillance Criteria Requirements and Addition of a Technical Specifications Bases Control Program ML0522304032005-08-10010 August 2005 Technical Specification Pages Extension of Reactor Trip System and Reactor Trip Device Functional Test Intervals ML0517506582005-06-17017 June 2005 Tech Spec Pages for Amendment - Monthly Operating Reports and Annual Occupational Radiation Reports 2023-01-27
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Text
10 CFR 50.90 10 CFR 50.68 May 31, 2007 5928-07-20107 U S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors
Reference:
AmerGen letter to USNRC, Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors, dated December 12, 2006 The referenced letter requested a change to the TMI Unit 1 Technical Specifications (TS) to relocate the reactor building refueling area and spent fuel storage area radiation monitor operability requirements to the Updated Final Safety Analysis Report (UFSAR) and plant procedures, since these radiation monitors do not meet the criteria for inclusion in the TS as presented in 10 CFR 50.36(c)(2)(ii). During subsequent discussions with the NRC staff the issue of compliance with 10 CFR 50.68(b) was discussed. Accordingly, Enclosure 1 provides a description of the TMI Unit 1 evaluation of current compliance with the Fuel Storage Area Radiation Monitoring requirements of 10 CFR 50.68(b).
Regulatory commitments established by this submittal are identified in Enclosure 2. If any additional information is needed, please contact David J. Distel at (610) 765-5517.
U.S. Nuclear Regulatory Commission May 31,2007 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 31st day of May, 2007.
Respectfully, Pamela B. cowan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC
Enclosures:
- 1) TMI Unit 1 Evaluation of Current Compliance with 10 CFR 50.68(b)
- 2) List of Commitments cc: S. J. Collins, USNRC Administrator, Region I P. J. Bamford, USNRC Project Manager, TMI Unit 1 D. M. Kern, USNRC Senior Resident Inspector, TMl Unit 1 File No. 06041
ENCLOSURE 1 TMI Unit 1 Evaluation of Current Compliance with 10 CFR 50.68(b)
Enclosure 1 Page 1 of 2 ENCLOSURE 1 TMI Unit 1 Evaluation of Current Compliance with 10 CFR 50.68(b) 10 CFR 50.68(b) Each licensee shall comply with the following requirements in lieu of maintaining a monitoring system capable of detecting a criticality as described in 10 CFR 70.24:
(I) Plant procedures shall prohibit the handling and storage at any one time of more fuel assemblies than have been determined to be safely subcritical under the most adverse moderation conditions feasible by unborated water.
TMI Unit 1 complies with this criterion. Fuel handling procedures are based on the design basis numbers of fuel assemblies assumed in analyses for the new fuel and spent fuel storage racks.
(2) The estimated ratio of neutron production to neutron absorption and leakage (k-effective) of the fresh fuel in the fresh fuel storage racks shall be calculated assuming the racks are loaded with fuel of the maximum fuel assembly reactivity and flooded with unborated water and must not exceed 0.95, at a 95 percent probability, 95 percent confidence level. This evaluation need not be performed if administrative controls and/or design features prevent such flooding or if fresh fuel storage racks are not used.
TMI Unit 1 complies with this criterion for fresh fuel stored in the new fuel storage racks. (This criterion is not applicable for fresh fuel subsequently stored in the spent fuel storage racks.)
(3) If optimum moderation of fresh fuel in the fresh fuel storage racks occurs when the racks are assumed to be loaded with fuel of the maximum fuel assembly reactivity and filled with low-density hydrogenous fluid, the k-effective corresponding to this optimum moderation must not exceed 0.98, at a 95 percent probability, 95 percent confidence level. This evaluation need not be performed if administrative controls and/or design features prevent such moderation or if fresh fuel storage racks are not used.
TMI Unit 1 complies with this criterion for fresh fuel stored in the new fuel storage racks. (This criterion is not applicable for fresh fuel subsequently stored in the spent fuel storage racks.)
(4) If no credit for soluble boron is taken, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. If credit is taken for soluble boron, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with borated water, and the k-effective must remain below 1.0 (subcriticai), at a 95 percent probability, 95 percent confidence level, if flooded with unborated water.
TMI Unit 1 complies with the applicable criterion for the Spent Fuel Pool A Region 1 racks. The Spent Fuel Pool A Region 2 and the Spent Fuel Pool 6 racks have a Technical Specification limit placed on them based on the fuel assembly initial enrichment and burnup. In addition a boron requirement of 600 ppm must be maintained when moving fuel assemblies in either pool to meet the NRC maximum allowable reactivity value under the postulated accident conditions.
Enclosure 1 Page 2 of 2 (5) The quantity of SNM, other than nuclear fuel stored onsite, is less than the quantity necessary for a critical mass.
TMI Unit 1 complies with this criterion based on the SNM, other than nuclear fuel, currently stored at TMI Unit 1.
(6) Radiation monitors are provided in storage and associated handling areas when fuel is present to detect excessive radiation levels and to initiate appropriate safety actions.
Radiation monitors that meet General Design Criteria 63 are located in the fuel handling areas.
These monitors are able to detect radiation levels caused by a fuel handling accident or spent fuel that is too close to the water surface. These monitors have alarms that allow personnel to take appropriate safety actions. Plant procedures require that either these radiation monitors or an equivalent portable monitor must be inservice in order to move fuel.
(7) The maximum nominal U-235 enrichment of the fresh fuel assemblies is limited to five (5.0) percent by weight.
TMI Unit 1 complies with this criterion. The TMI Unit 1 Technical Specifications contain this limit for fresh fuel in the new fuel storage vault and the spent fuel pool A storage racks, and contain a limit of 4.37 percent by weight for fuel stored in the spent fuel pool 8 storage racks.
(8) The FSAR is amended no later than the next update which 9 50.71(e) of this part requires, indicating that the licensee has chosen to comply with 5 50.68(b).
The TMI Unit 1 Updated Final Safety Analysis Report will be amended no later than the next update which 10 CFR 50.71 (e) requires, to indicate that TMI Unit 1 has chosen to comply with 10 CFR 50.68(b).
ENCLOSURE 2 List of Commitments
SUMMARY
OF AMERGEN COMMITMENTS The following table identifies regulatory commitments made in this document by AmerGen. (Any other actions discussed in the submittal represent intended or planned actions by AmerGen. They are described to the NRC for the NRCs information and are not regulatory commitments.)
COMMITMENT TYPE COMMITMENT COMMIlTED DATE OR OUTAGE PROGRAMMATIC The TMI Unit 1 Updated Final Safety Analysis Report will be Update 19 amended no later than the next (Spring 2008) update which 10 CFR 50.71 (e) requires, to indicate that TMI Unit 1 has chosen to comply with