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MONTHYEARML0428703722004-09-17017 September 2004 Amerenue - Callaway Plant OL Amendment #1248 Replacement Steam Generators, Non-Proprietary, NSSS Systems Project stage: Request ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project2004-09-17017 September 2004 Technical Specification Revisions Associated with Steam Generator Replacement Project Project stage: Request ML0428603522004-09-17017 September 2004 Amerenue - Callaway Plant OL Amendment #1248 Replacement Steam Generators, Non-Proprietary Project stage: Request ML0429304812004-10-20020 October 2004 Notice of Forthcoming Meeting with Union Electric Company on the Callaway Plant Project stage: Meeting ML0430903882004-11-0404 November 2004 Docket No. 50-483 - Licensee'S Slides for Meeting Held on November 4, 2004, to Discuss Its Application on the Steam Generators Replacement in Fall 2005 (Tac No. MC4437) Project stage: Meeting ML0431703532004-11-10010 November 2004 Letter, Request for Additional Information from Public Disclosure, CAW-04-1868, TAC No. MC4437 Project stage: RAI ML0431302892004-11-17017 November 2004 Summary of Meeting with Union Electric Company for the Licensee to Present Its Application Dated September 17, 2004, to Replace the Steam Generators in the Fall of 2005 Project stage: Meeting ML0434301682004-12-20020 December 2004 RAI, Containment Integrity for the Steam Generator Replacement in the Fall of 2005 (TAC MC4437),12/20/04 Ltr to G. Randolph Project stage: RAI ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-02-11011 February 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Other ML0512206202005-05-0404 May 2005 Forthcoming Meeting with Union Electric Co. to Discuss Revision of TSTF-449 and Response to Questions on Replacement of Steam Generators to Be Installed in Fall 2005 Project stage: Meeting ML0511501022005-05-0404 May 2005 RAI, Steam Generator Replacement License Amendment Request, TAC MC4437 Project stage: RAI ML0514301542005-05-18018 May 2005 Enclosure - 05/18/05, Meeting Summary -Plots Referenced in Licensee'S Response to Question 46 Project stage: Meeting ULNRC-05145, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-05-26026 May 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ML0514601112005-06-0303 June 2005 Summary of Meeting with Callaway on 05/18/05 for the Licensee to Discuss Its Draft Response to the Request for Additional Information on Its Application Dated 09/17/2004. Project stage: Draft RAI ML0517803282005-06-17017 June 2005 Supplemental Technical Specification Revisions for the Steam Generator Replacement Project Project stage: Request ULNRC-05169, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-07-15015 July 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ULNRC-05178, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-07-29029 July 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ULNRC-05188, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-08-16016 August 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project2005-09-0606 September 2005 Supplemental Technical Specification Revisions for the Steam Generator Replacement Project Project stage: Request ML0524201542005-09-0707 September 2005 Withholding from Public Disclosure, Responses to NRC Request for Additional Information on WCAP-16265-P, Rev. 0, 'Callaway Replacement Steam Generator Program NSSS Licensing Report,' Dated February 2005 (CAW-05-1944) Project stage: RAI ML0524300462005-09-0707 September 2005 Withholding from Public Disclosure, Setpoint Methodology Portion of the Response to (NRC) Request for Additional Information, Questions 1 and 2 (CAW-05-1998) Project stage: RAI ML0524301332005-09-0707 September 2005 Callaway - Request for Withholding Information from Public Disclosure (CAW-05-2007) (Tac. MC4437) Project stage: Withholding Request Acceptance ML0527300832005-09-29029 September 2005 Technical Specifications, Amendment Regarding the Steam Generator Replacement Project Project stage: Acceptance Review ML0525700542005-09-29029 September 2005 License Amendment, Regarding the Steam Generator Replacement Project Project stage: Acceptance Review 2005-05-26
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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, MIO65251 July 29, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555 ULNRC-05178 Ladies and Gentlemen:
DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY CALLAWAY PLANT WAmeren TECHNICAL SPECIFICATION REVISIONS ASSOCIATED WITH THE STEAM GENERATOR REPLACEMENT PROJECT UE
References:
- 1. ULNRC-05056 dated September 17, 2004
- 2. ULNRC-05117 dated February 11, 2005
- 3. ULNRC-05145 dated May 26, 2005
- 4. ULNRC-05157 dated June 17, 2005
- 5. ULNRC-05159 dated June 17, 2005
- 6. ULNRC-05169 dated July 15, 2005
- 7. ULNRC-04158 dated December 3, 1999 In Reference 1 above AmerenUE transmitted an application for amendment to Facility Operating License Number NPF-30 for the Callaway Plant in support of the replacement steam generators to be installed during Refuel 14 (fall 2005). This letter provides additional information on three issues recently raised by the NRC staff during the review of that application.
In Reference 5 above AmerenUE responded to several requests for additional information (RAIs) from the NRC Reactor Systems Branch. The following discussion provides additional clarification and a new commitment regarding the responses to RAI Questions 11, 12, and 45.
RAI #11 In the response to Question 11 in Reference 5 it is stated that "the calculated values bound the maximum allowable PORV setpoints specified in the current Pressure Temperature Limits Report (PTLR); therefore, the PTLR is not being revised for the RSG project." The NRC staff would like to know the calculated values and maximum allowable PORV setpoints.
-(V(5 a subsidiary ofAmeren Corporation
ULNRC-05 178 July 29, 2005 Page 2 The statements made in Section 4.3.5 of Appendix A to Reference 1 and in the response to Question 11 in Reference 5 were predicated on an assumption by Westinghouse that AmerenUE would limit the operation of reactor coolant pumps (RCPs) below a reactor coolant system (RCS) temperature of 200'F such that a maximum of two (2) RCPs would be allowed to operate whenever the RCS temperature was
< 2000 F. AmerenUE has decided to implement Cold Overpressure Mitigation System (COMS) setpoints that have no RCP operation restrictions. These COMS setpoints are more limiting than their counterparts that have RCP operation restrictions, but will not present any undue burdens on plant operation. Since these COMS setpoints are more limiting than those currently presented in the PTLR, the PTLR will be revised and the COMS setpoints will be changed to implement the RSG project. The attachment to this letter shows the draft PTLR changes, which provide the new calculated values for RSG as well as the current maximum allowable PORV setpoints. The current COMS setpoints have not been revised since the initial PTLR submittal to NRC in Reference 7.
RAI #12 The NRC staff would like to know what computer methodology was used to perform the sensitivity discussed in the last paragraph of the response to Question 12 in Reference 5.
At the request of the NRC reviewer during the meeting held on May 18, 2005, Westinghouse performed an additional calculation based on the Loss of Load/Turbine Trip analysis in Section 6.3.4 of Appendix A to Reference 1 (which is the FSAR Chapter 15 deterministic-style analysis) crediting the second safety grade signal to demonstrate the adequacy of the installed primary safety valve (PSV) capacity in preventing over-pressurization of the RCS. The methodology, including the computer code used -
RETRAN, is identical to that of Section 6.3.4 of Appendix A. The difference in these analyses involves the high pressurizer pressure reactor trip function, credited as the first safety grade signal in the FSAR Chapter 15 deterministic-style analysis; that trip was conservatively ignored in the additional sensitivity discussed in the last paragraph of the response to Question 12 in Reference 5.
RAI #45 Regarding question 45, a telecon was held on July 26, 2005 between Westinghouse and the NRC to discuss NRC's concern about the impact of non-integer size breaks on the limiting small break loss of coolant (SBLOCA) peak clad temperature (PCT) analyses. Callaway was a participant on that telephone call. The NRC staff recently identified a potential issue related to the impact of non-integer size breaks on the limiting SBLOCA PCT analysis for another plant which is considering a power up-rate.
NRC approached Westinghouse to determine the extent of this issue on the analyses they have performed for other licensees. With respect to Callaway's amendment request for SG replacement (Reference 1 above), NRC has theorized that a break between the 3-inch analyzed small break case (which did not result in accumulator injection) and the 4-inch analyzed small break case (which did result in accumulator injection to stem the cladding
ULNRC-05178 July 29, 2005 Page 3 temperature rise) would result in a higher PCT value than reported for those analyzed cases. AmerenUE and Westinghouse believe this to be a generic industry issue.
New large break and small break LOCA analyses were performed in support of the Callaway steam generator replacement project. Callaway's reanalyses were performed by Westinghouse using NRC-approved methodologies. Large break LOCA analysis results demonstrate a limiting PCT of 1939'F (per the responses to questions 16 and 17 in Reference 5) and SBLOCA analysis results demonstrate a limiting PCT of 1043IF (for the 4-inch case in Table 6.2.2-5 of Appendix A to Reference 1). These results demonstrate that Callaway is large break limited with respect to PCT and has greater than 11 50'F margin to the 2200'F regulatory limit for SBLOCA. AmerenUE and Westinghouse have a high degree of confidence that this issue would not result in the PCT for SBLOCA becoming limiting or encroaching upon 2200'F.
The following commitment is submitted with the intent that its formal transmittal would allow NRC to proceed with completing the Safety Evaluation and issue the license amendment for the Callaway steam generator replacement project:
"In support of AmerenUE's license amendment request (Reference 1 above),
associated with the steam generator replacement project, AmerenUE has initiated a corrective action program item (CAR 200406948 Action 27) that will track this issue. Callaway staff will follow this generic industry issue and will assess non-integer intermediate breaks consistent with the generic resolution. AmerenUE will provide a status update and discuss the method of how this issue will be assessed in the next required 10 CFR 50.46 report."
References 2, 3, 4, and 6 above provided various RAI responses, supplemental Technical Specification changes, and additional RAI response clarification in support of this amendment request. Nothing in the information provided above invalidates the findings of the licensing evaluations contained in Attachment 1 of Reference 1. The requested approval date and implementation plans for this amendment application remain unchanged from Reference 1. If you have any further questions on this amendment application, please contact us.
Very truly yours, Timothy E. Herrmann Manager-Nuclear Engineering Services GGY/
Attachment - Draft PTLR Changes
ULNRC-05178 July 29, 2005 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 Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102
STATE OF MISSOURI )
) SSs COUNTY OF CALLAWAY)
Timothy E. Herrmann, of lawful age, being first duly sworn upon oath says that he is Manager, Nuclear Engineering Services, 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.
Timothy E. Herrmann Manager, Nuclear Engineering Services SUBSCRIBED and sworn to before me this Pith day of ,
9 2005.
I PAULkAA. JOHNSON Notary Public - Notary Seal STATE OF MISSOURI Callaway County My Commission Expires: July 31, 2007
51-5065107-00 Page 3 of 9 Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT CALLAWAY COMS MadmumAllowable PORV S61pclfls a 1ao 200 300 4 RCS Temperature (degree F)
. - High PORV $e~pnt - Low PO1W SetpoltI FIGURE2.2-1 Maxim AlowedPORVSetpointfor theColdOverpressure Mitigao System Callaway Plant 7 Revision3
51-5065107-00 Page 4 of 9 FIgure 14.9 PRESSURE AND TEMPERATURE LIMiTS REPORT TABLE 2.2-1 CALLAWAY PLANT COMS MA)XMUM ALLOWABLE PORV SETPOINTS AT 20 EFPY Maximum Allowable Function Generator Setpoo ts (Breakpoontsl Breakpoint Number mperature - High Setpoint Low Se m\
2 l _ 76 501 _ _ 471 l 3 _ _130- _ 525 495_
4 _ 170 -. M 505 5 _ 220 _ 520
_550 6 _ 245 __' 650 600 7 _ 270,,-_ 750 700 a __2f5_ 750 700 9 __420 2350 _ 2350D NOTE: Seipoints assurne fha( recor p\\ rrunigorTc0F and \ha t rprtor250 f Tmperatur - F 70 Setpoint High . Low 97Setpo nt /
RCS (°F) (psig) (psig) 70 496 466 80 496 466 90 496 466 ISO 527 497 230 758 512 250 750 597 270 750 597 280 750 597 350 2335 2185 Caliaway Plant Revision 3
I .
51-5065107-00 Page 6 of 9 CALLAWAY COMS Maximum Allowable PORV Setpolnts 2500 T. j i i7T7i f I 2000
&n cL
_0. 1500 +*+~-~+/-f&* I: 1!1, A.11l iI a
u) 1000 0
CL 500 . -1 i ;'
0 0 50 10O 15D 200 250 300 350 400 RCS Temperature (degree F)
-'High PORV Setpolnt - - - Low PORV Setpoint INSERT 2 FIGURE 14.9