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Category:Letter type:ULNRC
MONTHYEARULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ULNRC-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-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-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-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-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-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-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-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-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting 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 2024-06-26
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AmerenUE PO Box 620 Callaway Plant Fulton, MIO 65251 April 14, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-04969 wAmeren DOCKET NUMBER 50-483 UE CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
SUPPORTING INFORMATION AND FOLLOW-UP REQUEST REGARDING LICENSE AMENDMENT REQUEST OL-1228 FOR REVISION TO TECHNICAL SPECIFICATIONS 3.8.1, "AC SOURCES - OPERATING," AND 3.8.4, "DC SOURCES - OPERATING"
Reference:
I) AmerenUE Letter ULNRC-04837, "License Amendment Request OL-1228 - Revision to Technical Specification Surveillance Requirements 3.8.1 and 3.8.4," from D. Shafer (AmerenUE) to USNRC, dated June 6, 2003
- 2) USNRC Letter, "Request for Additional Information re: Technical Specifications 3.8.1 and 3.8.4 for Callaway, Diablo Canyon, Palo Verde, and Wolf Creek Plants," from J. Donohew (USNRC) to G. Randolph, AmerenUE; G. Rueger, Pacific Gas and Electric; G.
Overbeck, Arizona Public Service Company, and R. Muench, Wolf Creek Nuclear Operating Corporation; dated September 25, 2003.
- 3) AmerenUE Letter ULNRC-04909, "Response to Request for Additional Information Regarding License Amendment Request OL-1228 (Revision to Technical Specification Surveillance Requirements 3.8.1 and 3.8.4)," from K. Young (AmerenUE) to USNRC, dated December 19, 2003 Per Reference 1, Union Electric Company (AmerenUE) transmitted an application for amendment of Facility Operating License No. NPF-30 for the Callaway Plant. In that request AmerenUE proposed changes to Technical Specifications (TS) 3.8.1, "AC Sources - Operating," and TS 3.8.4, "DC Sources -
\oO a subsidiary ofAmeren Corporation
ULNRC-04969 April 14, 2004 Page 2 Operating," to allow surveillance testing of the emergency diesel generators (DGs) during MODES in which it is currently prohibited and to incorporate changes based on Industry/Technical Specification Task Force (TSTF) Standard Technical Specification change TSTF-283, Revision 3.
AmerenUE's application for amendment, along with similar applications from Wolf Creek Nuclear Operating Corporation, Arizona Public Service Company, and Pacific Gas and Electric Company, is currently under review by the NRC staff. Per Reference 2, the NRC transmitted a request for additional information regarding the proposed TS Changes, to which AmerenUE responded via Reference 3.
Subsequently, on February 4, 2004, two additional questions related to DG testing in MODES I and 2 with the DG connected to the offsite power supply were provided by electronic mail from the NRC Project Manager. Responses to those questions were provided electronically on February 24, 2004, wherein it was identified that the information requested was previously provided by References 1 and 3. Through further discussions with the NRC Project Manager it was requested by the NRC Electrical Engineering Section that Ameren UE provide, in the Bases of the Callaway Technical Specifications, administrative controls for DG testing in MODES I and 2 with the DG connected to the offsite power supply.
Based on these discussions, AmerenUE is providing in the Enclosure additional changes to the TS Bases for Surveillance Requirement (SR) 3.8.1.14 (i.e.,
the 24-hour DG endurance run) to include the requested administrative controls. The enclosed additional TS Bases changes are provided (for information only) to assist the staff in its review of the proposed changes. (The enclosed marked-up TS Bases page reflects the NRC-requested changes as well as those originally indicated in Reference I for the affected page.) As noted in Reference 1, revision of the TS Bases will be implemented pursuant to the TS Bases Control Program, TS 5.5.14, upon implementation of the license amendment.
Specifically, the information to be added to the TS Bases will state:
Administrative controls for performing this Surveillance in MODES 1 or 2 with the DG connected to an offsite circuit ensure or require that:
- a. Weather conditions are conducive for performing the Surveillance.
- b. The offsite power supply and switchyard conditions are conducive for performing the Surveillance, which includes ensuring that switchyard access is restricted and no elective maintenance within the switchyard is performed.
- c. No equipment or systems assumed to be available for supporting the performance of the Surveillance are removed from service.
ULNRC-04969 April 14, 2004 Page 3 In its license amendment application (Reference 1), AmerenUE proposed changes to the mode-restriction Notes associated with the applicable SRs under TS 3.8.1, as well as the applicable SRs under TS 3.8.4, i.e., SR 3.8.4.7 and SR 3.8.4.8.
The proposed changes to the Notes provide the flexibility for a partial performance of the surveillance during plant operation to reestablish OPERABILITY following corrective maintenance. Although application of the proposed changes in the Notes to SR 3.8.4.7 and SR 3.8.4.8 (in addition to the SRs of TS 3.8.1) is consistent with NRC-approved TSTF-283, NRC reviewers of AmerenUE's amendment application expressed some concerns regarding the changes proposed for SR 3.8.4.7 and SR 3.8.4.8. As a result, in Reference 3, AmerenUE indicated that the changes to those SRs should be processed separately (from the TS 3.8.1 SRs) based on the potentially additional time to resolve the concerns both generically and for AmerenUE. After further consideration, AmerenUE has decided to withdraw the proposed changes to SR 3.8.4.7 and SR 3.8.4.8. AmerenUE will consider pursuing additional changes depending on the generic resolution of the concerns associated with the changes to those SRs.
It should be noted that the supplemental information and changes provided by this letter do not impact the conclusions of the No Significant Hazards Consideration provided in Reference 1. In addition, there are no commitments associated with this submittal.
Please contact me or Dave Shafer at (314) 554-3104 for any questions you may have regarding this application.
Very truly yours, Keith D. Young Manager, Regulatory Affairs TBE/mlo Enclosure
ULNRC-04969 April 14, 2004 Page 4 cc: U.S. Nuclear Regulatory Commission (Original and 1 copy)
Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360
STATE OF MISSOURI )
) SS COUNTY OF CALLAWAY)
Keith D. Young, of lawful age, being first duly sworn upon oath says that he is Manager, Regulatory Affairs, for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By 4 W40" K D.Y g Manager, Regulatory Affairs SUBSCRIBED and sworn to before me this JŽ day of f)A2 j '2004.
TERRA E. COOK Notary Public - Notary Seal STATE OF MISSOURI Callaway County My Commission Expires May 13, 2006
ULNRC-04969 April 14, 2004 Enclosure
AC Sources - Operating B 3.8.1 BASES SURVEILLA!' ICE SR 3.8.1.14 REQUIREME !NTS (continued) Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(3), requires demonstration once per 18 months that the DGs can start and run continuously at full load capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the auto-connected design loads have increased above the continuous duty rating the load shall be increased to 110% of the continuous duty rating for 2 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the remainder of the time at a load equivalent to the continuous duty rating of the DG. The DG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for prelubricating and warmup, discussed in SR 3.8.1.2. and for gradual loading, discussed in SR 3.8.1.3, are applicable to this SR.
In order to ensure that the DG is tested under load conditions thatare as close to design conditions as possible, testing must be performed using a power factor of 2 0.8 and < 0.9. This power factor is chosen to be representative of the actual design basis inductive loading that the DG would experience. The load band is provided to avoid routine overloading of the DG. Routine overloading may result in more frequentteardown inspections in accordance with vendor recommendations in order to maintain DG OPERABILITY. The generator voltage and frequency is maintained within 4160 + 160 - 420 volts and 60 +/- 1.2 Hz during this test.
INSERT 6 The 18 month Frequency is consistent with the recommendations of
_Q RgulaorL~ide .10 upragah 2.a ( ,
si erain no n requiredSurveillance, nd is ctw This Surveillance is modified by`hFeeNotes. Note 1 states that momentary transients due to changing bus loads do not invalidate this test. Similarly, momentary powe factor tran ients above the row r factor ii vl p ot invalidate he tes u n a~o ea~ornIc, performance of this Surveilnecud cause perturbations to the electrical distribution systems thacol challenge co d sags at da s ours in the overloaded conditio eed not be performed, provided the auto-connected loads remain below he 6201 KVW continuous rating of the DG.
SR 3.8.1.15 This Surveillance demonstrates that the diesel engine can restart from a hot condition, such as subsequent to shutdown from normal (continued)
CALLAWAY PLANT B 3.8.1-22 Revision 0
ULNRC-04969 April 14, 2004 TS Bases Insert 6 (new)
Administrative controls for performing this Surveillance in MODES 1 or 2 with the DG connected to the offsite power supply ensure or require that:
- a. Weather conditions are conducive for performing the Surveillance.
- b. The offsite power supply and switchyard conditions are conducive for performing the Surveillance, which includes ensuring that switchyard access is restricted and no elective maintenance within the switchyard is performed.
- c. No equipment or systems assumed to be available for supporting the performance of the Surveillance are removed from service.