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| | issue date = 11/05/2012 | | | issue date = 11/05/2012 |
| | title = Withdrawal of an Amendment Request | | | title = Withdrawal of an Amendment Request |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Heflin A C | | | addressee name = Heflin A |
| | addressee affiliation = Union Electric Co | | | addressee affiliation = Union Electric Co |
| | docket = 05000483 | | | docket = 05000483 |
| | license number = NPF-030 | | | license number = NPF-030 |
| | contact person = Lyon C F | | | contact person = Lyon C |
| | case reference number = TAC ME6645 | | | case reference number = TAC ME6645 |
| | document type = Letter, Federal Register Notice | | | document type = Letter, Federal Register Notice |
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| ==Dear Mr. Heflin:== | | ==Dear Mr. Heflin:== |
| By letter dated June 30, 2011 (Agencywide Documents Access and Management System (ADAMS Accession No. ML 111820367). | | By letter dated June 30, 2011 (Agencywide Documents Access and Management System (ADAMS Accession No. ML111820367). |
| you applied for an amendment to the Callaway Plant, Facility Operating License No. NPF-30. The proposed change would have modified the facility Technical Specifications (TSs) pertaining to TS 3.6.6, "Containment Spray and Cooling Systems." Specifically, the amendment would have revised Surveillance Requirement 3.6.6.3 for verifying the minimum required containment cooling train cooling water flow rate. By letter dated September 10, 2012 (ADAMS Accession No. ML 12255A040), you provided a response to the U.S. Nuclear Regulatory Commission (NRC) staff's request for additional information dated August 9,2012 (ADAMS Accession No. ML 12220A211). | | you applied for an amendment to the Callaway Plant, Facility Operating License No. NPF-30. The proposed change would have modified the facility Technical Specifications (TSs) pertaining to TS 3.6.6, "Containment Spray and Cooling Systems." Specifically, the amendment would have revised Surveillance Requirement 3.6.6.3 for verifying the minimum required containment cooling train cooling water flow rate. By letter dated September 10, 2012 (ADAMS Accession No. ML12255A040), you provided a response to the U.S. Nuclear Regulatory Commission (NRC) staff's request for additional information dated August 9,2012 (ADAMS Accession No. ML12220A211). |
| Subsequently, by letter dated October 26,2012 (ADAMS Accession No. ML 12305A202), you withdrew the amendment request. For your future information, based on its review of your request, the NRC staff's preliminary conclusion was that you did not provide sufficient information for the staff to conclude that you were using an acceptable methodology with acceptable design inputs and assumptions, or that the proposed changes complied with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.36(c)(3), "Surveillance requirements." Specific comments from the NRC staffs review to date are provided below: While heat exchanger fouling factor is a significant contributor to determining the required cooling water flow, the licensee is determining fouling factor by visual inspection as opposed to using the Final Safety Analysis Report specified value of 0.002, which conservatively bounds expected fouling factors that should be controlled by regular cleaning and/or testing. In response to the NRC staff's request for the methodology, design inputs, and assumptions used for determining the proposed new "within limits" flow as the proposed acceptance criteria for required cooling water flow, the licensee stated it uses PROTO-HX and its service water flow balancing procedure. | | Subsequently, by letter dated October 26,2012 (ADAMS Accession No. ML12305A202), you withdrew the amendment request. For your future information, based on its review of your request, the NRC staff's preliminary conclusion was that you did not provide sufficient information for the staff to conclude that you were using an acceptable methodology with acceptable design inputs and assumptions, or that the proposed changes complied with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.36(c)(3), "Surveillance requirements." Specific comments from the NRC staffs review to date are provided below: While heat exchanger fouling factor is a significant contributor to determining the required cooling water flow, the licensee is determining fouling factor by visual inspection as opposed to using the Final Safety Analysis Report specified value of 0.002, which conservatively bounds expected fouling factors that should be controlled by regular cleaning and/or testing. In response to the NRC staff's request for the methodology, design inputs, and assumptions used for determining the proposed new "within limits" flow as the proposed acceptance criteria for required cooling water flow, the licensee stated it uses PROTO-HX and its service water flow balancing procedure. |
| It appears that the licensee is plugging tubes and placing whole coils out of service (quantity not specified) and visibly determining fouling factors as input to predict cooling water flow rate that would be satisfactory for removing 70.7 MBtu/hr, and using several calculations to make the A. -2 determinations. | | It appears that the licensee is plugging tubes and placing whole coils out of service (quantity not specified) and visibly determining fouling factors as input to predict cooling water flow rate that would be satisfactory for removing 70.7 MBtu/hr, and using several calculations to make the A. -2 determinations. |
| When requested to list design input and methodology for the basis of the current specified TS limit of ">2200 gpm" and the proposed "within limits," the licensee listed the inputs from only design calculation 07-44. The licensee did not provide all of the assumptions, design inputs and various methodologies of the various calculations used. When requested to list the differences in the design assumptions, design inputs and methodology between the current analysis for "> 2200 gpm" and "within limits," the licensee provided a general statement with no limits to the number of tubes to be plugged or coils to be taken out of service. Based on the lack of information provided and the proposed visual determination of fouling factor and the licensee's inability to test the cooler at design conditions, the NRC staff does not have assurance that the licensee will qetermine a new cooling water flow rate without reducing or eliminating safety margin of the containment cooling heat exchangers. The licensee's design basis calculation 07-044 is titled, "Containment Cooler Performance as a Function of Tube Side Differential Pressure." It appears that the licensee is taking entire coils out of service and plugging tubes while apparently using cooling water differential pressure as measured locally at each heat exchanger to define cooler performance. | | When requested to list design input and methodology for the basis of the current specified TS limit of ">2200 gpm" and the proposed "within limits," the licensee listed the inputs from only design calculation 07-44. The licensee did not provide all of the assumptions, design inputs and various methodologies of the various calculations used. When requested to list the differences in the design assumptions, design inputs and methodology between the current analysis for "> 2200 gpm" and "within limits," the licensee provided a general statement with no limits to the number of tubes to be plugged or coils to be taken out of service. Based on the lack of information provided and the proposed visual determination of fouling factor and the licensee's inability to test the cooler at design conditions, the NRC staff does not have assurance that the licensee will qetermine a new cooling water flow rate without reducing or eliminating safety margin of the containment cooling heat exchangers. The licensee's design basis calculation 07-044 is titled, "Containment Cooler Performance as a Function of Tube Side Differential Pressure." It appears that the licensee is taking entire coils out of service and plugging tubes while apparently using cooling water differential pressure as measured locally at each heat exchanger to define cooler performance. |
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| 301-415-2296; e-mail: Fred. Lyon@nrc.gov. | | 301-415-2296; e-mail: Fred. Lyon@nrc.gov. |
| SUPPLEMENTARY INFORMATION: | | SUPPLEMENTARY INFORMATION: |
| The U.S. Nuclear Regulatory Commission (NRC or the Commission) has granted the request of Union Electric Co. (the licensee) to withdraw its application dated June 30, 2011 (ADAMS Accession No. ML 111820367), as supplemented by letter dated September 10, 2012 (ADAMS Accession No. ML 1225A040), for proposed amendment to Facility Operating License No. NPF-30 for the Callaway Plant, Unit No.1, located in Callaway County, Missouri. | | The U.S. Nuclear Regulatory Commission (NRC or the Commission) has granted the request of Union Electric Co. (the licensee) to withdraw its application dated June 30, 2011 (ADAMS Accession No. ML111820367), as supplemented by letter dated September 10, 2012 (ADAMS Accession No. ML 1225A040), for proposed amendment to Facility Operating License No. NPF-30 for the Callaway Plant, Unit No.1, located in Callaway County, Missouri. |
| The proposed amendment would have revised Technical Specification (TS) 3.6.6, "Containment Spray and Cooling Systems." Specifically, the amendment would have revised Surveillance Requirement (SR) 3.6.6.3 for verifying the minimum required containment cooling train cooling water flow rate. Rather than require verifying each containment cooling train has a cooling water flow rate greater than or equal to 2200 gallons per minute, TS SR 3.6.6.3 would have been revised to require verification that the flow rate is capable of being "within limits" for achieving the heat removal rate assumed in the Callaway Plant safety analyses. | | The proposed amendment would have revised Technical Specification (TS) 3.6.6, "Containment Spray and Cooling Systems." Specifically, the amendment would have revised Surveillance Requirement (SR) 3.6.6.3 for verifying the minimum required containment cooling train cooling water flow rate. Rather than require verifying each containment cooling train has a cooling water flow rate greater than or equal to 2200 gallons per minute, TS SR 3.6.6.3 would have been revised to require verification that the flow rate is capable of being "within limits" for achieving the heat removal rate assumed in the Callaway Plant safety analyses. |
| -The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on November 1, 2011 (76 FR 67491). However, by letter dated October 26, 2012 (ADAMS Accession No. ML 12305A202), the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated June 30,2011, the supplement dated September 10,2012, and the licensee's letter dated October 26, 2012, which withdrew the application for license amendment. | | -The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on November 1, 2011 (76 FR 67491). However, by letter dated October 26, 2012 (ADAMS Accession No. ML12305A202), the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated June 30,2011, the supplement dated September 10,2012, and the licensee's letter dated October 26, 2012, which withdrew the application for license amendment. |
| Dated at Rockville, Maryland, this 5th day of November 2012. For the Nuclear Regulatory Commission. | | Dated at Rockville, Maryland, this 5th day of November 2012. For the Nuclear Regulatory Commission. |
| Carl F. Lyon, Project Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor A. Heflin -The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication. | | Carl F. Lyon, Project Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor A. Heflin -The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication. |
Letter Sequence Withdrawal |
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MONTHYEARULNRC-05804, Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025)2011-06-30030 June 2011 Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025) Project stage: Request ML1121505412011-08-0303 August 2011 Acceptance Review E-mail, License Amendment Request to Revise Technical Specification 3.6.6, Containment Spray and Cooling Systems, Project stage: Acceptance Review ML12220A2112012-08-0909 August 2012 Request for Additional Information, License Amendment Request to Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems Project stage: RAI ULNRC-05904, Response to Request for Additional Information Pertaining to Revision of Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, LDCN 09-00252012-09-10010 September 2012 Response to Request for Additional Information Pertaining to Revision of Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, LDCN 09-0025 Project stage: Response to RAI ML12305A1952012-11-0505 November 2012 FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems Project stage: Withdrawal ML12305A1942012-11-0505 November 2012 Withdrawal of an Amendment Request Project stage: Withdrawal NRC-2012-0275, FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems2012-11-0505 November 2012 FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems Project stage: Withdrawal 2012-11-05
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Category:Letter
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 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 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 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) 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 ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System 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 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications 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) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 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 ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 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 ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure 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 ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) 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 IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a 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) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 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 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) 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 . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage 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) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
[Table view] Category:Federal Register Notice
MONTHYEARML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter ML23297A2552023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - FRN ML23234A1542023-10-11011 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (FRN) ML22220A1292022-10-25025 October 2022 Exemptions from the Requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.46, 10 CFR 50 Appendix a General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (FRN) ML22182A4062022-08-23023 August 2022 FRN - Environmental Assessment & Finding of No Significant Impact Requests for Amendment & Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (EPID L-2021-LLA-0059 & L-2021-LLE-0021) ML22182A4112022-08-23023 August 2022 Letter - Environmental Assessment & Finding of No Significant Impact Requests for Amendment & Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (EPID L-2021-LLA-0059 & L-2021-LLE-00021) ML21028A0122021-02-18018 February 2021 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for January 2021 ML20335A0902020-12-21021 December 2020 Federal Register Notice - November 2020 COVID-19 Exemptions ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20246G5702020-10-16016 October 2020 Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections ML20190A0822020-07-20020 July 2020 FRN - Notice of Consideration of Issuance of Amendment to RFOL, Proposed Nshcd, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information ML20190A0812020-07-15015 July 2020 Letter - Notice of Consideration of Issuance of Amendment to RFOL, Proposed Nshcd, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML19140A4562019-05-28028 May 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 06/04/2019 NRC-2016-0273, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 20172016-12-21021 December 2016 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 2017 ML16355A2612016-12-21021 December 2016 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 2017 ML16061A3012016-03-0202 March 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 ML15148A3762015-06-0101 June 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 ML15022A6532015-01-26026 January 2015 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 3, 2015 ML14252A6432014-11-0505 November 2014 FRN-Notice of Availability of the Final Plant-Specific Supplement 51 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Callaway Plant, Unit 1 ML14056A4182014-02-26026 February 2014 Correction ML14043A5362014-02-12012 February 2014 (FRN) Notice of Availability of the Draft Plant-Specific Supplement 51 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Callaway Plant, Unit 1 ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit NRC-2012-0275, FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems2012-11-0505 November 2012 FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems ML12305A1952012-11-0505 November 2012 FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems ML12305A1942012-11-0505 November 2012 Withdrawal of an Amendment Request ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12024A2542012-02-16016 February 2012 Notice of Opportunity for Hearing, Regarding Renewal of Facility Operating License No. NPF-30 for an Additional 20-year Period, Federal Register Notice ML12040A2152012-02-14014 February 2012 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for Callaway Plant, Unit 1 ML12024A2622012-02-14014 February 2012 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Application from Union Electric Company, for Renewal of the Operating License for Callaway Plant, Unit 1 ML11343A0872011-12-23023 December 2011 Notice of Receipt and Availability of Application for Renewal of Callaway Plant, Unit 1 - Federal Register Notice ML11343A0602011-12-23023 December 2011 Receipt and Availability of the License Renewal Application for the Callaway Plant, Unit 1 NRC-2011-0276, Notice of Receipt and Availability of Application for Renewal of Callaway Plant, Unit 1 - Federal Register Notice2011-12-23023 December 2011 Notice of Receipt and Availability of Application for Renewal of Callaway Plant, Unit 1 - Federal Register Notice NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 20112011-12-15015 December 2011 Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 ML11349A0052011-12-15015 December 2011 Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 ML1132502102011-11-22022 November 2011 Individual Notice of Consideration of Issuance of Amendment to Add New Surveillance Requirement 3.3.8.6 to Technical Specification 3.3.8, Emergency Exhaust System (EES) Actuation Instrumentation ML1132502002011-11-22022 November 2011 Letter, Individual Notice of Consideration of Issuance of Amendment to Add New Surveillance Requirement 3.3.8.6 to Technical Specification 3.3.8, Emergency Exhaust System (EES) Actuation Instrumentation. NRC-2011-0205, FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/112011-08-25025 August 2011 FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11 ML11237A0072011-08-25025 August 2011 FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11 ML1122302752011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML1033303052010-12-28028 December 2010 Frn:General Notice. Ameren Missouri Combined License Application for Callaway Plant Unit 2 Environmental Assessment and Finding of No Significant Impact ML1009103092010-04-0707 April 2010 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing (Exigent Circumstances) (Tac No. ME3595) ML1009103222010-04-0707 April 2010 Exigent 14-day Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for Function 6.g in TS Table 3.3.2-1 NRC-2010-0151, Exigent 14-day Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for Function 6.g in TS Table 3.3.2-12010-04-0707 April 2010 Exigent 14-day Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for Function 6.g in TS Table 3.3.2-1 ML0905800142009-02-26026 February 2009 Sholly Report for Fr Publication Date March 10th 2009 ML0835102082008-12-18018 December 2008 Withdrawal Federal Register Notice License Amendment Request to Revise Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs), and Add New TS 3.7.19, Secondary System Isolation Valves (Ssivs) ML0834700412008-12-16016 December 2008 Individual Notice of Consideration of Issuance of Amendment, Proposed No Significant Hazards Consideration Change in Plant Modification Dates for Replacement of Essential Service Water Train B Carbon Steel Piping 2023-11-06
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 November 5, 2012 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton. MO 65251 CALLAWAY PLANT, UNIT 1 -WITHDRAWAL OF AN AMENDMENT REQUEST (TAC NO. ME6645)
Dear Mr. Heflin:
By letter dated June 30, 2011 (Agencywide Documents Access and Management System (ADAMS Accession No. ML111820367).
you applied for an amendment to the Callaway Plant, Facility Operating License No. NPF-30. The proposed change would have modified the facility Technical Specifications (TSs) pertaining to TS 3.6.6, "Containment Spray and Cooling Systems." Specifically, the amendment would have revised Surveillance Requirement 3.6.6.3 for verifying the minimum required containment cooling train cooling water flow rate. By letter dated September 10, 2012 (ADAMS Accession No. ML12255A040), you provided a response to the U.S. Nuclear Regulatory Commission (NRC) staff's request for additional information dated August 9,2012 (ADAMS Accession No. ML12220A211).
Subsequently, by letter dated October 26,2012 (ADAMS Accession No. ML12305A202), you withdrew the amendment request. For your future information, based on its review of your request, the NRC staff's preliminary conclusion was that you did not provide sufficient information for the staff to conclude that you were using an acceptable methodology with acceptable design inputs and assumptions, or that the proposed changes complied with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.36(c)(3), "Surveillance requirements." Specific comments from the NRC staffs review to date are provided below: While heat exchanger fouling factor is a significant contributor to determining the required cooling water flow, the licensee is determining fouling factor by visual inspection as opposed to using the Final Safety Analysis Report specified value of 0.002, which conservatively bounds expected fouling factors that should be controlled by regular cleaning and/or testing. In response to the NRC staff's request for the methodology, design inputs, and assumptions used for determining the proposed new "within limits" flow as the proposed acceptance criteria for required cooling water flow, the licensee stated it uses PROTO-HX and its service water flow balancing procedure.
It appears that the licensee is plugging tubes and placing whole coils out of service (quantity not specified) and visibly determining fouling factors as input to predict cooling water flow rate that would be satisfactory for removing 70.7 MBtu/hr, and using several calculations to make the A. -2 determinations.
When requested to list design input and methodology for the basis of the current specified TS limit of ">2200 gpm" and the proposed "within limits," the licensee listed the inputs from only design calculation 07-44. The licensee did not provide all of the assumptions, design inputs and various methodologies of the various calculations used. When requested to list the differences in the design assumptions, design inputs and methodology between the current analysis for "> 2200 gpm" and "within limits," the licensee provided a general statement with no limits to the number of tubes to be plugged or coils to be taken out of service. Based on the lack of information provided and the proposed visual determination of fouling factor and the licensee's inability to test the cooler at design conditions, the NRC staff does not have assurance that the licensee will qetermine a new cooling water flow rate without reducing or eliminating safety margin of the containment cooling heat exchangers. The licensee's design basis calculation 07-044 is titled, "Containment Cooler Performance as a Function of Tube Side Differential Pressure." It appears that the licensee is taking entire coils out of service and plugging tubes while apparently using cooling water differential pressure as measured locally at each heat exchanger to define cooler performance.
This appears to be contrary to the NRC's answer to question 6 of Section III of Generic Letter (GL) 89-13, Supplement 1, "Service Water Problems Affecting Safety-Related Equipment," dated April 4, 1990 (ADAMS Accession No. ML0341140185). Although the coolers are in constant use during plant operation, the licensee appears to assume an air-side fouling factor of zero, which is non-conservative. With entire coils taken out of service and some tubes plugged, the licensee did not provide information on how it proposed to account for sections of air flow ineffectiveness, and how all this relates to the proposed new cooling water flow limit of "within limits." The NRC staff requested that the licensee describe the GL 89-13 program for the containment cooling heat exchangers and any changes needed as a result of the proposed changes. The licensee stated that its procedure, EDP-ZZ-01112, will not be affected by the proposed changes. No specific information was provided to explain the statement that the GL 89-13 program with respect to the containment cooling heat exchangers will not be affected. Based on the information provided, the NRC staff was unable to conclude that the proposed change to the surveillance requirement (Le., moving the TS value to a licensee-controlled document), would assure that the necessary quality of systems and components is maintained, that facility operation will be within safe limits, and that the limiting conditions for operation will be met. Therefore, the staff was unable to conclude that the proposed changes met the requirements of 10 CFR 50.36(c)(3).
A. Heflin -The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.
If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
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NUCLEAR REGULATORY Docket No. 50-483; NRC-20VY Callaway Plant, Unit Application for Amendment to Facility Operating AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment application; withdrawal.
ADDRESSES:
Please refer to Docket ID <NRC-20YY-XXXX>
when contacting the NRC about the availability of information regarding this document.
You may access information related to this document, which the NRC possesses and are publicly available, using any of the following methods:
301-492-3668; e-mail: CaroI.Galiagher@nrc.gov.
- NRC's Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select "ADAMS Public Documents" and then select "Begin Web-based ADAMS Search." For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or bye-mail to pdr.resource@nrc.gov.
The ADAMS accession number for each document referenced in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced.
w 2 w
- NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room 01-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Carl F. Lyon, Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555; telephone:
301-415-2296; e-mail: Fred. Lyon@nrc.gov.
SUPPLEMENTARY INFORMATION:
The U.S. Nuclear Regulatory Commission (NRC or the Commission) has granted the request of Union Electric Co. (the licensee) to withdraw its application dated June 30, 2011 (ADAMS Accession No. ML111820367), as supplemented by letter dated September 10, 2012 (ADAMS Accession No. ML 1225A040), for proposed amendment to Facility Operating License No. NPF-30 for the Callaway Plant, Unit No.1, located in Callaway County, Missouri.
The proposed amendment would have revised Technical Specification (TS) 3.6.6, "Containment Spray and Cooling Systems." Specifically, the amendment would have revised Surveillance Requirement (SR) 3.6.6.3 for verifying the minimum required containment cooling train cooling water flow rate. Rather than require verifying each containment cooling train has a cooling water flow rate greater than or equal to 2200 gallons per minute, TS SR 3.6.6.3 would have been revised to require verification that the flow rate is capable of being "within limits" for achieving the heat removal rate assumed in the Callaway Plant safety analyses.
-The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on November 1, 2011 (76 FR 67491). However, by letter dated October 26, 2012 (ADAMS Accession No. ML12305A202), the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated June 30,2011, the supplement dated September 10,2012, and the licensee's letter dated October 26, 2012, which withdrew the application for license amendment.
Dated at Rockville, Maryland, this 5th day of November 2012. For the Nuclear Regulatory Commission.
Carl F. Lyon, Project Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor A. Heflin -The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.
If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.
Sincerely, IRA! Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
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