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Category:Letter type:TMI
MONTHYEARTMI-23-018, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation TMI-23-013, Radiological Emergency Plan Document Revision2023-05-30030 May 2023 Radiological Emergency Plan Document Revision TMI-23-009, Submittal of Changes to Technical Specifications Bases2023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases TMI-23-004, Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 12023-03-21021 March 2023 Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 1 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan TMI-23-002, Radiological Emergency Plan Document Revision2023-02-23023 February 2023 Radiological Emergency Plan Document Revision TMI-22-028, Radiological Emergency Plan Document Revisions2022-09-27027 September 2022 Radiological Emergency Plan Document Revisions TMI-22-016, 2021 Annual Radiological Effluent Release Report2022-04-25025 April 2022 2021 Annual Radiological Effluent Release Report TMI-22-017, 2021 Annual Radiological Environmental Operating Report2022-04-25025 April 2022 2021 Annual Radiological Environmental Operating Report TMI-22-018, 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20212022-04-19019 April 2022 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2021 TMI-22-015, Submittal of Changes to Technical Specifications Bases2022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases TMI-22-009, Registration of Use of Casks to Store Spent Fuel2022-03-0909 March 2022 Registration of Use of Casks to Store Spent Fuel TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 TMI-22-004, Registration of Use of Casks to Store Spent Fuel2022-02-0606 February 2022 Registration of Use of Casks to Store Spent Fuel TMI-21-027, Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-08-30030 August 2021 Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme TMI-21-024, 90-Day Notification Prior to First Storage of Spent Fuel2021-06-15015 June 2021 90-Day Notification Prior to First Storage of Spent Fuel TMI-21-025, Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities2021-06-15015 June 2021 Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities TMI-21-026, Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation2021-06-15015 June 2021 Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation TMI-21-018, License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan2021-04-29029 April 2021 License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan TMI-21-019, Submittal of 2020 Annual Radiological Environmental Operating Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Environmental Operating Report TMI-21-017, Submittal of 2020 Annual Radiological Effluent Release Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Effluent Release Report TMI-21-021, (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20202021-04-27027 April 2021 (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2020 TMI-21-009, License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-03-0404 March 2021 License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme TMI-20-027, Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License2020-10-0909 October 2020 Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License TMI-20-026, Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation2020-09-15015 September 2020 Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation TMI-20-025, Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report2020-07-16016 July 2020 Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report TMI-20-021, Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative2020-07-0808 July 2020 Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative TMI-20-015, 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report2020-04-30030 April 2020 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report TMI-20-016, 2019 Annual Radiological Environmental Operating Report2020-04-30030 April 2020 2019 Annual Radiological Environmental Operating Report TMI-20-017, 2019 Annual Radiological Effluent Release Report2020-04-30030 April 2020 2019 Annual Radiological Effluent Release Report TMI-20-012, Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases2020-04-13013 April 2020 Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases TMI-20-002, Annual Notification of Property Insurance Coverage2020-03-25025 March 2020 Annual Notification of Property Insurance Coverage TMI-20-006, Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7)2020-03-0202 March 2020 Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7) TMI-19-112, Application for Order Approving License Transfer and Conforming License Amendments2019-11-12012 November 2019 Application for Order Approving License Transfer and Conforming License Amendments TMI-19-097, License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-10-31031 October 2019 License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements TMI-18-100, Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition2018-10-29029 October 2018 Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition TMI-18-088, Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report2018-08-21021 August 2018 Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report TMI-18-024, Biennial 10 CFR 50.59 and Pdms SAR Report2018-04-24024 April 2018 Biennial 10 CFR 50.59 and Pdms SAR Report TMI-18-044, Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 292018-03-29029 March 2018 Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 29 TMI-18-004, Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 22018-03-16016 March 2018 Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 2 TMI-18-017, Annual Report2018-02-12012 February 2018 Annual Report TMI-17-093, Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 252017-08-18018 August 2017 Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 25 TMI-17-060, Request for Approval of Certified Fuel Handler Training Program2017-07-10010 July 2017 Request for Approval of Certified Fuel Handler Training Program TMI-17-051, Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 20132017-05-16016 May 2017 Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013 TMI-17-035, Submittal of Changes to Technical Specifications Bases2017-04-13013 April 2017 Submittal of Changes to Technical Specifications Bases TMI-17-034, Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04)2017-03-31031 March 2017 Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04) TMI-17-006, Decommissioning Funding Status Report2017-03-24024 March 2017 Decommissioning Funding Status Report TMI-16-097, Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 172016-10-20020 October 2016 Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 17 TMI-16-082, Notice of Transfer of Transmission Asset2016-09-15015 September 2016 Notice of Transfer of Transmission Asset TMI-16-091, Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-22016-09-0808 September 2016 Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-2 2023-05-30
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10 CFR 50.55a TMI-10-102 October 13, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Submittal of Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (lSI) Interval Attached for your review is a relief request associated with the third Inservice Inspection (lSI) interval for Three Mile Island Nuclear Station (TMI), Unit 1. TMI, Unit 1 is requesting relief from Table IWB-2500-1, Examination Category B-O, Item Number B14.10, which requires volumetric or surface examination of the pressure retaining Control Rod Drive (CRD) butt welds in 10% of the peripheral CRD housings. The third interval of the TMI, Unit 1 lSI program complies with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 1995 Edition, 1996 Addenda. We request your approval by October 13, 2011.
There are no regulatory commitments in this letter.
If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Respectfully, Pamela B. Cowan Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Relief Request RR-10-01 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI USNRC Project Manager, TMI
ATTACHMENT Relief Request RR-10-01
Relief Request RR-10-01 for Alternative Control Rod Drive Housing Examinations in Accordance with 10 CFR 50.55a(a)(3)(i)
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- 1. ASME Code Component(s) Affected Code Class: 1
Reference:
Table IWB-2500-1 Examination Category: B-O Item Number: B14.10
Description:
Selection of Control Rod Drive (CRD) housing welds for examination Component Number: Various
2. Applicable Code Edition and Addenda
The Inservice Inspection (lSI) program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 1995 Edition, 1996 Addenda.
3. Applicable Code Requirement
Table IWB-2500-1, Examination Category B-O, Item Number B14.10 requires volumetric or surface examination of the pressure retaining CRD butt welds in 10% of the peripheral CRD housings.
4. Reason for Request
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative will provide an acceptable level of quality and safety.
TMI, Unit 1 has sixty-nine (69) CRD locations which have four butt welds each (shown in Figure RR-10-01.1 - welds "A", "B", "C", and "0"). Twenty-four (24) of these CRD locations are categorized as "peripheral" per Examination Category B-O. Ten percent of the peripheral CRD housings equates to an examination of three (3) CRD locations. Peripheral housing welds with the "0" designator in Figure RR-10-01.1 are accessible for NDE examination through access ports in the reactor vessel closure head service structure and are not applicable to this relief request. CRD housing welds with an "A", "B", or "C" designator as shown in Figure RR-1 0-01.1 are only accessible for examination when a CRD is removed from the reactor vessel closure head. As shown in Figure RR-10-01.2, the "Service Structure" surrounding the CRDs causes interferences that result in the peripheral CRD housing welds being inaccessible for examination unless the CRD is removed to gain access.
Literal compliance with Table IWB-2500-1, Examination Category B-O requires that only welds on the peripheral CRD locations can be credited for meeting the code requirements.
It is believed that the intent of this requirement was to provide greater flexibility in meeting the code by requiring examination of the peripheral locations as compared to the inner locations. Typically, examination of welds on non-peripheral CRD locations is limited due to access restrictions. However, the code did not account for some plants, such as TMI, Unit 1, that have a Service Structure that makes examination of the peripheral CRD locations more difficult.
Relief Request RR-10-01 for Alternative Control Rod Drive Housing Examinations in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 2 of 6)
Over the course of a ten-year lSI interval, a small population of CROs (though often not peripheral in location) are removed for various purposes which allows an opportunity to perform examinations. At this time, no peripheral CROs are expected to be removed during the upcoming outage (Fall 2011). The Fall 2011 outage is the last outage in the third lSI interval.
During the third interval in the first period (2001), six (6) CROs not in the periphery were examined and no indications were identified. There were no examination limitations reported for these welds. A review of lSI data for examinations of welds "A", "B", and "c" completed since 1986 identified no degradation. Visual examination of the flange region of all CROs is completed using remote video each outage to assure there is no leakage from the mechanical joint. Small leakage from the welds above the flange that might not be evident during the normal Section XI VT-2 examination pressure tests would likely be observed during the flange video examinations.
The cost for removal and reinstallation of three peripheral CROs in order to meet the literal compliance with this code requirement is estimated to be greater than $80,000. The estimated dose for removing and re-installing three control rod drive mechanisms to perform the inspection is greater than 1.3 Rem.
A review of the operating conditions between the interior and peripheral CRO locations shows that the difference in operating temperatures is not significant.
The motor tube (RCS pressure boundary) weldments (welds "A", "B", and "C") are located above an internal thermal barrier which results in the welds being at a lower operating temperature as shown in Figure RR-10-01.3. The thermal barrier restricts the thermal circulation of hot, primary coolant and acts as an insulator between the reactor vessel and the drive. The maximum steady state operating temperature for the internal components above the thermal barrier is 470°F. Welds "A" and "B" are located slightly above the internal rotor assembly (further away from the top of the reactor vessel head) so their operating temperature is slightly lower. Additionally, an external water cooled stator-water jacket assembly is installed over the motor tube region of welds "A" and "B" for all 69 drives which leads to a relatively consistent temperature. Weld "c" is located approximately 165" above weld "B" and is the coolest of the three welds based on the lack of flow and distance from the RV closure head.
Accordingly, an examination sample of welds from interior drive locations is essentially equivalent to a sample of welds from the peripheral drive locations and will adequately represent the condition of the Examination Category B-O welds.
- 5. Proposed Alternative and Basis for Use As a proposed alternative, TMI Unit 1 will credit the examinations of the "A", "B", and "c" designator welds on three non-peripheral (3) CRO housings, performed in the first period of the third interval. The examinations performed met the requirements of Table IWB-2500-1 Examination Category B-O for NOE methods, area examined, and acceptance.
Relief Request RR-10-01 for Alternative Control Rod Drive Housing Examinations in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 3 of 6)
Examination of the CRO housing welds on any of the 69 CRO locations provides an equivalent level of quality and safety.
TMI, Unit 1 will complete the examination of the "0" designator welds shown in Figure RR-10-01.1 on three (3) peripheral CRO housings in accordance with Table IWB-2500-1 requirements.
TMI, Unit 1 will perform an ASME Section XI, Category B-O examination of the "A", "B",
and "c" welds on at least one peripheral CRO housing during the first period of the fourth lSI interval and complete the remaining examinations during the interval as required by ASME Section XI. As an alternative to the first period examination, TMI, Unit 1 may replace the current population of CROs with new CROs during the first period of the fourth lSI interval and complete the subsequent fourth lSI interval examinations in accordance with ASME Section XI.
- 6. Duration of Proposed Alternative Relief is requested for the third ten-year lSI interval for TMI, Unit 1. The third ten-year interval began on April 20, 2001.
- 7. Precedents (Optional)
None.
Relief Request RR-10-01 for Alternative Control Rod Drive Housing Examinations in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 4 of 6)
FIGURE RR-10-01.1 CRD Housing Weld Locations (Excerpt from TMI drawing 1D-ISI-RC-011 )
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Relief Request RR-10-01 for Alternative Control Rod Drive Housing Examinations in Accordance with 10 CFR 50.55a(a)(3)(1)
(Page 5 of 6)
Approximate elevation of welds A and B Removed CRD Location and RV Head Penetration Top Flange Typical Non-Peripheral CRD Locations FIGURE RR-10-01.2 CRD Housings and Weld Locations Photograph from Top of Service Structure Looking Down
Relief Request RR-10-01 for Alternative Control Rod Drive Housing Examinations in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 6 of 6)
FIGURE RR-10-01.3 CRD Schematic and Materials SA 182 F304 Or SA-479 TP-304 Stator-Water Jacket Assembly Thermal Barrier I Assembly SA-508 Class 2 I I Reactor Vessel SA-312 SA-182 F304 TP-304 Head Nozzle Flange ERNiCr-3