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MONTHYEARML13123A0952013-05-0202 May 2013 10 CFR 50.55a Request: Proposed Alternative to ASME Section Xi Requirements for Leakage Testing of Reactor Pressure Vessel Head Flange Leakoff Lines (Relief Request 13R-14) Project stage: Request ULNRC-05990, Supplemental Information for 10 CFR 50.55a Request: Proposed Alternative to ASME Section XI Requirements for Leakage Testing of Reactor Pressure Vessel Head Flange Leakoff Lines (Relief Request I3R-14)2013-05-0606 May 2013 Supplemental Information for 10 CFR 50.55a Request: Proposed Alternative to ASME Section XI Requirements for Leakage Testing of Reactor Pressure Vessel Head Flange Leakoff Lines (Relief Request I3R-14) Project stage: Supplement ML13126A3202013-05-0707 May 2013 Summary of Telephone Conference, Verbal Authorization of Relief Request I3R-14. Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year ISI Interval. Project stage: Other ML13136A0592013-05-17017 May 2013 Request for Additional Information, Relief Request I3R-14, Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year Inservice Inspection Interval Project stage: RAI ULNRC-06012, Response to Request for Additional Information Regarding Relief Request 13R-14, Proposed Alternative to ASME Code, Section XI Requirements for Leakage Testing of Reactor Pressure Vessel Head Flange Leakoff Lines2013-07-0303 July 2013 Response to Request for Additional Information Regarding Relief Request 13R-14, Proposed Alternative to ASME Code, Section XI Requirements for Leakage Testing of Reactor Pressure Vessel Head Flange Leakoff Lines Project stage: Response to RAI ML13221A0912013-08-13013 August 2013 Relief Request I3R-14, Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year Inservice Inspection Interval Project stage: Other 2013-05-06
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Category:Letter type:ULNRC
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 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 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 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) 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 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 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 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) 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 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 . 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) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request 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 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request 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 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, 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 Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 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 Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
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WAmeren Callaway Plant MISSOURI July 3, 2013 ULNRC-060 12 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 10 CFR 50.55a Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, PROPOSED ALTERNATIVE TO ASME CODE, SECTION XI REQUIREMENTS FOR LEAKAGE TESTING OF REACTOR PRESSURE VESSEL HEAD FLANGE LEAKOFF LINES (TAC NO. MF1745)
References:
- 1) ULNRC-05986 dated May 2, 2013 (ADAMS Accession No. ML13123A095)
- 2) ULNRC-05990 dated May 6, 2013 (ADAMS Accession No. ML13126A304)
- 3) NRC Letter "Request for Additional Information Re: 13R-14, Proposed Alternative to ASME Code,Section XI Requirements for Leakage Testing of Reactor Pressure Vessel Head Flange LeakoffLines (TAC No. MF1745)," dated May 17, 2013 (ADAMS Accession No. ML13136A059)
Pursuant to 10 CFR 50.55a(a)(3)(ii), and by letter dated May 2, 2013 (Reference 1), as supplemented by letter dated May 6, 2013 (Reference 2), Union Electric Company (Ameren Missouri) proposed an alternative to Section XI, paragraph IWC-5221 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) for visual examination of reactor pressure vessel head flange leakofflines (Relief Request I3R-14). As compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, in lieu of the requirement to pressurize the subject leakoff lines to normal operating pressure prior to performing a VT -2 visual examination, Ameren Missouri proposed to use the pressure developed when the refueling cavity is filled to the normal refueling water level.
PO Box 620 Fulton, MO 65251 AmerenMissouri.com
ULNRC-060 12 July 3, 2013 Page 2 The NRC staff provided verbal authorization on May 6, 2013 for the proposed alternative described in Relief Request 13R-14 for the remainder of the third 10-year inservice inspection interval. By letter dated May 17, 2013 (Reference 3), the NRC staff transmitted a request for additional information (RAI) needed to complete its formal review.
Ameren Missouri's response to the RAI is provided in the attachment to this letter.
This letter and its attachment do not contain new commitments. None of the material presented herein is considered proprietary by Ameren Missouri.
Please contact me at 573-676-8719 or Jim Kovar at 314-225-1478 for any questions you may have regarding this response.
Sincerely, f) .A, V\\ ~
S.A.M~
Regulatory Affairs Manager JPK/nls
Attachment:
Response to Request For Additional Information (RAI) Regarding Relief Request 13R-14
ULNRC-060 12 July 3, 2013 Page 3 cc: Mr. Arthur T. Howell Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738
ULNRC-060 12 July 3, 2013 Page4 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:
A. C. Heflin F. M. Diya C. 0. Reasoner III L. H. Graessle S. A. Maglio T. B. Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)
Attachment to ULNRC-06012 Page 1 of3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RELIEF REQUEST I3R-14
Attachment to ULNRC-06012 Page 2 of3 Question #1 Please describe any incidents of significant reactor pressure vessel flange 0-ring leakage at Callaway Plant.
Callaway Response Callaway has no history of reactor pressure vessel flange 0-ring leakage.
Question #2 When there is leakage past the inner 0-ring and the valve on the inner 0-ring leakage line is closed, the line between the flange and the closed valve may be pressurized to the reactor operating pressure, 2235 pounds per square inch gauge.
- a. Please describe any plans for performing a VT-2 visual examination on the inner 0-ring line while it is pressurized to reactor operating pressure.
Callaway Response So long as leakage is within plant Technical Specification limits and there is no indication of leakage past the outer 0-ring, the plant is not required to shut down upon indication of leakage. The valves isolating the leak off lines are located outside the bioshield and can be accessed and operated while the plant is at power.
Control Room annunciator response procedure OTA-RK-00020 Addendum 58D, "RV Flange Leakoff Temperature High," directs the isolation of the inner 0-ring leakage line upon indication of leakage. This procedure is being revised to have Operations perform a visual examination for leakage of the accessible portions of the line 10 minutes after line isolation.
Additionally, an on-demand surveillance is being generated to perform a VT-2 examination on the accessible portion of the line after a minimum hold time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Accessible portions of the line include 2 feet of insulated line outside of the bioshield and 22 feet of uninsulated line that can be observed from the bioshield entrance.
- b. Please provide the length of the line that can be visually inspected.
Callaway Response 24 feet of the pressurized line is accessible for visual inspection.
- c. Please describe how much of the inspected length is insulated.
Callaway Response 2 feet of the pressurized line is insulated.
- d. Please provide the hold time after the line is pressurized before a VT-2 visual examination is performed.
Attachment to ULNRC-06012 Page 3 of3 Callaway Response OTA-RK-00020 is being revised to require a visual inspection of the accessible line no less than 10 minutes after the inner 0-ring leak off line is isolated and pressurized.
The on-demand surveillance for this line will require a four-hour hold time.
- e. Please describe any hardship associated with performing the examination (i.e., temperature, radiological dose, etc.).
Callaway Response Examining additional piping would involve entrance to the bioshield where elevated dose rates would be encountered.
- f. What would be the expected radiation field in the area being inspected during the time that the pressurized line could be examined? Please clarify the time needed to perform the VT-2 visual examination.
Callaway Response The pressurized portion of piping outside the bioshield is in a radiation field of approximately 5 mRemlhr. Of the pressurized piping inside the bioshield, 22 feet can be seen from the bioshield entrance with the examiner standing in a radiation field of 100 to 500 mRemlhr. To examine the remaining piping inside the bioshield, personnel would have to enter a radiation field of greater than 16 Remlhr and would have to maneuver in a congested area coming in close proximity to the cross-over loop piping.
The time needed to perform the VT-2 on the accessible portions of line would be less than five minutes. The time needed to examine the additional piping inside the bioshield would also be less than five minutes but would put the examiner in very close proximity to the cross-over loop piping.