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| | number = ML082750501 | | | number = ML082750501 |
| | issue date = 09/26/2008 | | | issue date = 09/26/2008 |
| | title = Catawba Nuclear Station, Units 1 and 2, Technical Specification Bases Changes | | | title = Technical Specification Bases Changes |
| | author name = Morris J R | | | author name = Morris J |
| | author affiliation = Duke Energy Carolinas, LLC | | | author affiliation = Duke Energy Carolinas, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Duke EnergyCarolinas JAMES R. MORRIS, VICE PRESIDENT' Duke Energy Carolinas, LLC Catawba Nuclear Station 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax September 26, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 | | {{#Wiki_filter:JAMES R. MORRIS, VICE PRESIDENT' Duke Energy Duke Energy Carolinas,LLC Catawba Nuclear Station Carolinas 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax September 26, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 |
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| ==Subject:== | | ==Subject:== |
| Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases. These Bases changes were made according to the provisions of 10CFR 50.59 and submitted on a frequency consistent with 10 CFR 50.71(e).Any questions regarding this information should be directed to Allison Jones-Young, Regulatory Compliance, at (803) 701-3051.I certify that I am a duly authorized officer of Duke Energy Corporation and that the information contained herein accurately represents changes made to the Technical Specification Bases since the. previous submittal. | | Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases. These Bases changes were made according to the provisions of 10CFR 50.59 and submitted on a frequency consistent with 10 CFR 50.71(e). |
| S Attachment AooJ www. duke-energy. | | Any questions regarding this information should be directed to Allison Jones-Young, Regulatory Compliance, at (803) 701-3051. |
| com U.S. Nuclear Regulatory Commission September 26, 2008 Page 2 Xc: L. A. Reyes U. S. Nuclear Regulatory Commission Regoinal Administrator, Region II Atlanta Federal Center 61 Forsyth St. SW, Suite23T85 Atlanta, GA 30303 J. F. Stang, Jr., NRR Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 A.T. Sabisch Senior Resident Inspector Catawba Nuclear Station U.S. Nuclear Regulatory Commission September 26, 2008 Page 3 bxc: w/o attachment NCMPA-1 NCEMC SREC PMPA w/attachment Electronic Licensing Library EC050 RGC File CN01RC Master File CN-801.01 CN04DM MSIVs B 3.7.2 BASES LCO This LCO requires that four MSIVs in the steam lines be OPERABLE.The MSIVs are considered OPERABLE when the isolation times are within limits, and they close on an isolation actuation signal.This LCO provides assurance that the MSIVs will perform their design safety function to mitigate the Consequences of accidents that could result in offsite exposures comparable to the 10 CFR 50.67 (Ref. 5) limits or the NRC staff approved licensing basis.APPLICABILITY The MSIVs must be OPERABLE in MODE 1, and in MODES 2 and 3 except when closed and de-activated, when there is significant mass and energy in the RCS and steam generators.
| | I certify that I am a duly authorized officer of Duke Energy Corporation and that the information contained herein accurately represents changes made to the Technical Specification Bases since the. previous submittal. |
| When the MSIVs are closed, they are already performing the safety function.In MODE 4, normally most of the MSIVs are closed, and the steam generator energy is low.In MODE 5or 6, the steam generators do not contain much energy because their temperature is below the boiling point of water; therefore, the MSIVs are not required for isolation of potential high energy secondary system pipe breaks in these MODES.-ACTIONS A.1 With one MSIV inoperable in MODE 1, action must be taken to restore OPERABLE status within 8 hours. Some repairs to the MSIV can be made with the unit hot. The 8 hour Completion Time is reasonable, considering the low probability of an accident occurring during this time period that would require a closure of the MSIVs.The 8 hour Completion Time is greater than that normally allowed for containment isolation valves because the MSIVs are valves that isolate a closed system penetrating containment. | | S Attachment AooJ www. duke-energy.com |
| These valves differ from other containment isolation valves in that the closed system provides an additional means for containment isolation. | | |
| B.1 If the MSIV cannot be restored to OPERABLE status within 8 hours, the unit must be placed in a MODE in which the LCO does not apply. To achieve .this status, the unit must be placed in MODE 2 within 6 hours and Condition C would be entered. The Completion Times are Catawba Units 1 and 2 B 3.7-2-3 Revision No. 1 MSIVs B 3.7.2 BASES ACTIONS (continued) reasonable, based on operating experience, to reach MODE 2 and to close the MSIVs in an orderly manner and without challenging unit systems.C.1 and C.2 Condition C is modified by a Note indicating that separate Condition entry is allowed for each MSIV.Since the MSIVs are required to be OPERABLE in MODES 2 and 3, the inoperable MSIVs may either be restored to OPERABLE status or closed.When closed, the MSIVs are already in the position required by the assumptions in the safety analysis.The 8 hour Completion Time is consistent with that allowed in Condition A.For inoperable MSIVs that cannot be restored to OPERABLE status within the specified Completion Time, but are closed, the inoperable MSIVs must be verified on a periodic basis to be closed. This is necessary to ensure that the assumptions in the safety analysis remain valid. The 7 day Completion Time is reasonable, based on engineering judgment, in view of MSIV status indications available in the control room, and other administrative controls, to ensure that these valves are in the closed position.D.1 and D.2 If the MSIVs cannot be restored to OPERABLE status or are not closed within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed at least in MODE 3 within 6 hours, and in MODE 4 within 12 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2 conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.2.1 REQUIREMENTS This SR verifies that the closure time of each MSIV is < 8.0 seconds on an actual or simulated actuation signal. The MSIV closure time is assumed in the accident and containment analyses. | | U.S. Nuclear Regulatory Commission September 26, 2008 Page 2 Xc: L. A. Reyes U. S. Nuclear Regulatory Commission Regoinal Administrator, Region II Atlanta Federal Center 61 Forsyth St. SW, Suite23T85 Atlanta, GA 30303 J. F. Stang, Jr., NRR Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 A.T. Sabisch Senior Resident Inspector Catawba Nuclear Station |
| This SR also Catawba Units 1 and 2 B 3.7.2-4 Revision No. I MSIVs B 3.7.2 BASES SURVEILLANCE REQUIREMENTS (continued) verifies the valve closure time is in accordance with the Inservice Testing Program. This SR is normally performed upon returning the unit to operation following a refueling outage. The MSIVs should not be tested at power, since even a part stroke exercise increases the risk of a valve closure when the unit is generating power. As the MSIVs are not tested at power, they are exempt from the ASME Code, Section XI (Ref. 6), requirements during operation in MODE 1 or 2. The Frequency is in accordance with the Inservice Testing Program.This test is conducted in MODE 3 with the unit at operating temperature and pressure, as discussed in Reference 6 exercising requirements. | | |
| This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR. This allows a delay of testing until MODE 3, to establish conditions consistent with those under which the acceptance criterion was generated. | | U.S. Nuclear Regulatory Commission September 26, 2008 Page 3 bxc: w/o attachment NCMPA-1 NCEMC SREC PMPA w/attachment Electronic Licensing Library EC050 RGC File CN01RC Master File CN-801.01 CN04DM |
| REFERENCES | | |
| : 1. UFSAR, Section 10.3.2. UFSAR, Section 6.2.3. UFSAR, Section 15.1.5.4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
| | MSIVs B 3.7.2 BASES LCO This LCO requires that four MSIVs in the steam lines be OPERABLE. |
| : 5. 10 CFR 50.67.6. ASME, Boiler and Pressure Vessel Code, Section Xl.Catawba Units 1 and 2 B 3.7.2-5 Revision No. 2 MFIVs, MFCVs, Associated Bypass Valves and Tempering Valves B 3.7.3 BASES ACTIONS (continued) judgment, in view of valve status indications available in the control room, and other administrative controls, to ensure that these valves are closed orisolated. | | The MSIVs are considered OPERABLE when the isolation times are within limits, and they close on an isolation actuation signal. |
| D.1 With the tempering valve inoperable or two inoperable valves in the same flow path, there may be no redundant system to operate automatically and perform the required safety function. | | This LCO provides assurance that the MSIVs will perform their design safety function to mitigate the Consequences of accidents that could result in offsite exposures comparable to the 10 CFR 50.67 (Ref. 5) limits or the NRC staff approved licensing basis. |
| The tempering valves have no other automatic isolation valves in series to provide isolation. | | APPLICABILITY The MSIVs must be OPERABLE in MODE 1, and in MODES 2 and 3 except when closed and de-activated, when there is significant mass and energy in the RCS and steam generators. When the MSIVs are closed, they are already performing the safety function. |
| Under these conditions, affected valves in each flow path must be restored to OPERABLE status, or the affected flow path isolated within 8 hours. This action returns the system to the condition where at least one valve in each flow path is performing the required safety function. | | In MODE 4, normally most of the MSIVs are closed, and the steam generator energy is low. |
| The 8 hour Completion Time is reasonable, based on operating experience, to complete the actions required to close the MFIV or MFCV, or otherwise isolate the affected flow path.E.1 and E.2 If the MFIV(s), MFCV(s), and the associated bypass valve(s) or the tempering valve(s) cannot be restored to OPERABLE status, or closed, or isolated within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within 12 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.3.1 REQUIREMENTS This SR verifies that the closure time .of each MFIV, MFCV, and associated bypass valves, and the tempering valve is <_ 12 seconds on an actual or simulated actuation signal. The MFIV and MFCV closure times are assumed in the accident and containment analyses. | | In MODE 5or 6, the steam generators do not contain much energy because their temperature is below the boiling point of water; therefore, the MSIVs are not required for isolation of potential high energy secondary system pipe breaks in these MODES.- |
| This SR also verifies the valve closure time is in accordance with the Inservice Testing Program. This SR is normally performed upon returning the unit to.operation following a refueling outage. These valves should not be tested at power since even apart stroke exercise increases the risk of a valve closure with the unit generating power. This is consistent with the Catawba Units 1 and 2 B B 3.7.3-5 Revision No. 1 MFIVs, MFCVs, Associated Bypass Valves and Tempering Valves B 3.7.3 BASES SURVEILLANCE REQUIREMENTS (continued) | | ACTIONS A.1 With one MSIV inoperable in MODE 1, action must be taken to restore OPERABLE status within 8 hours. Some repairs to the MSIV can be made with the unit hot. The 8 hour Completion Time is reasonable, considering the low probability of an accident occurring during this time period that would require a closure of the MSIVs. |
| ASME Code, Section XI (Ref. 3), quarterly stroke requirements during operation in MODES 1 and 2.The Frequency for this SR is in accordance with the Inservice Testing Program.REFERENCES 1.2.3.UFSAR, Section 10.4.7.10 CFR 50.36, Technical Specifications, (c)(2)(ii). | | The 8 hour Completion Time is greater than that normally allowed for containment isolation valves because the MSIVs are valves that isolate a closed system penetrating containment. These valves differ from other containment isolation valves in that the closed system provides an additional means for containment isolation. |
| ASME, Boiler and Pressure Vessel Code, Section XI.Catawba Units 1 and 2 B 3.7.3-6 Revision No. 1}} | | B.1 If the MSIV cannot be restored to OPERABLE status within 8 hours, the unit must be placed in a MODE in which the LCO does not apply. To achieve .this status, the unit must be placed in MODE 2 within 6 hours and Condition C would be entered. The Completion Times are Catawba Units 1 and 2 B 3.7-2-3 Revision No. 1 |
| | |
| | MSIVs B 3.7.2 BASES ACTIONS (continued) reasonable, based on operating experience, to reach MODE 2 and to close the MSIVs in an orderly manner and without challenging unit systems. |
| | C.1 and C.2 Condition C is modified by a Note indicating that separate Condition entry is allowed for each MSIV. |
| | Since the MSIVs are required to be OPERABLE in MODES 2 and 3, the inoperable MSIVs may either be restored to OPERABLE status or closed. |
| | When closed, the MSIVs are already in the position required by the assumptions in the safety analysis. |
| | The 8 hour Completion Time is consistent with that allowed in Condition A. |
| | For inoperable MSIVs that cannot be restored to OPERABLE status within the specified Completion Time, but are closed, the inoperable MSIVs must be verified on a periodic basis to be closed. This is necessary to ensure that the assumptions in the safety analysis remain valid. The 7 day Completion Time is reasonable, based on engineering judgment, in view of MSIV status indications available in the control room, and other administrative controls, to ensure that these valves are in the closed position. |
| | D.1 and D.2 If the MSIVs cannot be restored to OPERABLE status or are not closed within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed at least in MODE 3 within 6 hours, and in MODE 4 within 12 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2 conditions in an orderly manner and without challenging unit systems. |
| | SURVEILLANCE SR 3.7.2.1 REQUIREMENTS This SR verifies that the closure time of each MSIV is < 8.0 seconds on an actual or simulated actuation signal. The MSIV closure time is assumed in the accident and containment analyses. This SR also Catawba Units 1 and 2 B 3.7.2-4 Revision No. I |
| | |
| | MSIVs B 3.7.2 BASES SURVEILLANCE REQUIREMENTS (continued) verifies the valve closure time is in accordance with the Inservice Testing Program. This SR is normally performed upon returning the unit to operation following a refueling outage. The MSIVs should not be tested at power, since even a part stroke exercise increases the risk of a valve closure when the unit is generating power. As the MSIVs are not tested at power, they are exempt from the ASME Code, Section XI (Ref. 6), |
| | requirements during operation in MODE 1 or 2. The Frequency is in accordance with the Inservice Testing Program. |
| | This test is conducted in MODE 3 with the unit at operating temperature and pressure, as discussed in Reference 6 exercising requirements. This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR. This allows a delay of testing until MODE 3, to establish conditions consistent with those under which the acceptance criterion was generated. |
| | REFERENCES 1. UFSAR, Section 10.3. |
| | : 2. UFSAR, Section 6.2. |
| | : 3. UFSAR, Section 15.1.5. |
| | : 4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii). |
| | : 5. 10 CFR 50.67. |
| | : 6. ASME, Boiler and Pressure Vessel Code, Section Xl. |
| | Catawba Units 1 and 2 B 3.7.2-5 Revision No. 2 |
| | |
| | MFIVs, MFCVs, Associated Bypass Valves and Tempering Valves B 3.7.3 BASES ACTIONS (continued) judgment, in view of valve status indications available in the control room, and other administrative controls, to ensure that these valves are closed orisolated. |
| | D.1 With the tempering valve inoperable or two inoperable valves in the same flow path, there may be no redundant system to operate automatically and perform the required safety function. The tempering valves have no other automatic isolation valves in series to provide isolation. Under these conditions, affected valves in each flow path must be restored to OPERABLE status, or the affected flow path isolated within 8 hours. This action returns the system to the condition where at least one valve in each flow path is performing the required safety function. The 8 hour Completion Time is reasonable, based on operating experience, to complete the actions required to close the MFIV or MFCV, or otherwise isolate the affected flow path. |
| | E.1 and E.2 If the MFIV(s), MFCV(s), and the associated bypass valve(s) or the tempering valve(s) cannot be restored to OPERABLE status, or closed, or isolated within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within 12 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. |
| | SURVEILLANCE SR 3.7.3.1 REQUIREMENTS This SR verifies that the closure time .of each MFIV, MFCV, and associated bypass valves, and the tempering valve is <_12 seconds on an actual or simulated actuation signal. The MFIV and MFCV closure times are assumed in the accident and containment analyses. This SR also verifies the valve closure time is in accordance with the Inservice Testing Program. This SR is normally performed upon returning the unit to |
| | .operation following a refueling outage. These valves should not be tested at power since even apart stroke exercise increases the risk of a valve closure with the unit generating power. This is consistent with the Catawba Units 1 and 2 B 3.7.3-5 Revision No. 1 |
| | |
| | MFIVs, MFCVs, Associated Bypass Valves and Tempering Valves B 3.7.3 BASES SURVEILLANCE REQUIREMENTS (continued) |
| | ASME Code, Section XI (Ref. 3), quarterly stroke requirements during operation in MODES 1 and 2. |
| | The Frequency for this SR is in accordance with the Inservice Testing Program. |
| | REFERENCES 1. UFSAR, Section 10.4.7. |
| | : 2. 10 CFR 50.36, Technical Specifications, (c)(2)(ii). |
| | : 3. ASME, Boiler and Pressure Vessel Code, Section XI. |
| | Catawba Units 1 and 2 B 3.7.3-6 Revision No. 1}} |
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Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Technical Specification
MONTHYEARRA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies ML22186A0082022-06-21021 June 2022 SLC Revision to 16.9-22, TS Bases 3.7.7 RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-12-0404 December 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.2018-11-15015 November 2018 Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System. CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process CNS-16-046, Technical Specification Bases Changes, B 3.7 Plant Systems2016-06-14014 June 2016 Technical Specification Bases Changes, B 3.7 Plant Systems CNS-16-031, Technical Specification Bases Changes2016-04-26026 April 2016 Technical Specification Bases Changes CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016 Technical Specification Bases Changes CNS-15-098, Technical Specification Bases Changes2015-12-14014 December 2015 Technical Specification Bases Changes RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements2015-06-23023 June 2015 Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.142015-06-0202 June 2015 Submittal of Technical Specification Bases Changes 5.5.14 CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.2015-03-0909 March 2015 Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program. RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014 License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area CNS-14-079, Technical Specification Bases Changes2014-06-18018 June 2014 Technical Specification Bases Changes CNS-14-055, Technical Specification Bases Changes2014-05-0505 May 2014 Technical Specification Bases Changes CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications2014-03-10010 March 2014 Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.2014-02-17017 February 2014 Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System. ML13269A0772013-09-23023 September 2013 Submittal of Technical Specification Bases Changes ML13263A3732013-09-18018 September 2013 Technical Specification Bases Changes ML13109A0802013-04-17017 April 2013 Technical Specification Bases Changes ML12314A0152012-11-0606 November 2012 Technical Specification Bases Changes ML12153A3282012-05-31031 May 2012 Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method ML11335A1482011-11-29029 November 2011 Technical Specification Bases Changes ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML11171A0422011-06-15015 June 2011 Changes to Technical Specification Bases Pursuant to 10CFR 50.4 ML11138A3042011-05-10010 May 2011 Technical Specification Bases Changes, Pursuant to 1OCFR 50.4 ML1108907012011-03-24024 March 2011 Duke Energy Carolinas - Technical Specification Bases Changes ML1026500392010-09-16016 September 2010 License Amendment Request to Revise Technical Specification 5.3, Unit Staff Qualifications 2023-04-24
[Table view] Category:Bases Change
MONTHYEARRA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies ML22186A0082022-06-21021 June 2022 SLC Revision to 16.9-22, TS Bases 3.7.7 RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-12-0404 December 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.2018-11-15015 November 2018 Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System. CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process CNS-16-046, Technical Specification Bases Changes, B 3.7 Plant Systems2016-06-14014 June 2016 Technical Specification Bases Changes, B 3.7 Plant Systems CNS-16-031, Technical Specification Bases Changes2016-04-26026 April 2016 Technical Specification Bases Changes CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016 Technical Specification Bases Changes CNS-15-098, Technical Specification Bases Changes2015-12-14014 December 2015 Technical Specification Bases Changes ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements2015-06-23023 June 2015 Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.142015-06-0202 June 2015 Submittal of Technical Specification Bases Changes 5.5.14 CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.2015-03-0909 March 2015 Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program. RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014 License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area CNS-14-079, Technical Specification Bases Changes2014-06-18018 June 2014 Technical Specification Bases Changes CNS-14-055, Technical Specification Bases Changes2014-05-0505 May 2014 Technical Specification Bases Changes CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications2014-03-10010 March 2014 Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.2014-02-17017 February 2014 Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System. ML13269A0772013-09-23023 September 2013 Submittal of Technical Specification Bases Changes ML13263A3732013-09-18018 September 2013 Technical Specification Bases Changes ML13109A0802013-04-17017 April 2013 Technical Specification Bases Changes ML12314A0152012-11-0606 November 2012 Technical Specification Bases Changes ML11335A1482011-11-29029 November 2011 Technical Specification Bases Changes ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML11171A0422011-06-15015 June 2011 Changes to Technical Specification Bases Pursuant to 10CFR 50.4 ML11138A3042011-05-10010 May 2011 Technical Specification Bases Changes, Pursuant to 1OCFR 50.4 ML1108907012011-03-24024 March 2011 Duke Energy Carolinas - Technical Specification Bases Changes ML1019703652010-07-13013 July 2010 Submittal of Technical Specification Bases Changes ML0935600772009-12-15015 December 2009 Technical Specifications Revision Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity. ML0935005972009-12-14014 December 2009 Units 1 and 2 - License Amendment Request Applicable to Technical Specification 3.8.4, DC Sources-Operating ML0908503412009-03-23023 March 2009 Technical Specification Bases Changes ML0832605732008-11-12012 November 2008 Technical Specification Bases Changes ML0828800982008-10-0808 October 2008 Proposed Technical Specifications and Bases Amendment, TS and Bases Administrative Changes ML0827505012008-09-26026 September 2008 Technical Specification Bases Changes ML0814300052008-05-15015 May 2008 Technical Specification Bases Changes ML0812702282008-04-29029 April 2008 Technical Specification Bases Changes ML0731305512007-11-0707 November 2007 Transmittal of Technical Specification Bases Changes 2023-04-24
[Table view] |
Text
JAMES R. MORRIS, VICE PRESIDENT' Duke Energy Duke Energy Carolinas,LLC Catawba Nuclear Station Carolinas 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax September 26, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases. These Bases changes were made according to the provisions of 10CFR 50.59 and submitted on a frequency consistent with 10 CFR 50.71(e).
Any questions regarding this information should be directed to Allison Jones-Young, Regulatory Compliance, at (803) 701-3051.
I certify that I am a duly authorized officer of Duke Energy Corporation and that the information contained herein accurately represents changes made to the Technical Specification Bases since the. previous submittal.
S Attachment AooJ www. duke-energy.com
U.S. Nuclear Regulatory Commission September 26, 2008 Page 2 Xc: L. A. Reyes U. S. Nuclear Regulatory Commission Regoinal Administrator, Region II Atlanta Federal Center 61 Forsyth St. SW, Suite23T85 Atlanta, GA 30303 J. F. Stang, Jr., NRR Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 A.T. Sabisch Senior Resident Inspector Catawba Nuclear Station
U.S. Nuclear Regulatory Commission September 26, 2008 Page 3 bxc: w/o attachment NCMPA-1 NCEMC SREC PMPA w/attachment Electronic Licensing Library EC050 RGC File CN01RC Master File CN-801.01 CN04DM
MSIVs B 3.7.2 BASES LCO This LCO requires that four MSIVs in the steam lines be OPERABLE.
The MSIVs are considered OPERABLE when the isolation times are within limits, and they close on an isolation actuation signal.
This LCO provides assurance that the MSIVs will perform their design safety function to mitigate the Consequences of accidents that could result in offsite exposures comparable to the 10 CFR 50.67 (Ref. 5) limits or the NRC staff approved licensing basis.
APPLICABILITY The MSIVs must be OPERABLE in MODE 1, and in MODES 2 and 3 except when closed and de-activated, when there is significant mass and energy in the RCS and steam generators. When the MSIVs are closed, they are already performing the safety function.
In MODE 4, normally most of the MSIVs are closed, and the steam generator energy is low.
In MODE 5or 6, the steam generators do not contain much energy because their temperature is below the boiling point of water; therefore, the MSIVs are not required for isolation of potential high energy secondary system pipe breaks in these MODES.-
ACTIONS A.1 With one MSIV inoperable in MODE 1, action must be taken to restore OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Some repairs to the MSIV can be made with the unit hot. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is reasonable, considering the low probability of an accident occurring during this time period that would require a closure of the MSIVs.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is greater than that normally allowed for containment isolation valves because the MSIVs are valves that isolate a closed system penetrating containment. These valves differ from other containment isolation valves in that the closed system provides an additional means for containment isolation.
B.1 If the MSIV cannot be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the unit must be placed in a MODE in which the LCO does not apply. To achieve .this status, the unit must be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Condition C would be entered. The Completion Times are Catawba Units 1 and 2 B 3.7-2-3 Revision No. 1
MSIVs B 3.7.2 BASES ACTIONS (continued) reasonable, based on operating experience, to reach MODE 2 and to close the MSIVs in an orderly manner and without challenging unit systems.
C.1 and C.2 Condition C is modified by a Note indicating that separate Condition entry is allowed for each MSIV.
Since the MSIVs are required to be OPERABLE in MODES 2 and 3, the inoperable MSIVs may either be restored to OPERABLE status or closed.
When closed, the MSIVs are already in the position required by the assumptions in the safety analysis.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is consistent with that allowed in Condition A.
For inoperable MSIVs that cannot be restored to OPERABLE status within the specified Completion Time, but are closed, the inoperable MSIVs must be verified on a periodic basis to be closed. This is necessary to ensure that the assumptions in the safety analysis remain valid. The 7 day Completion Time is reasonable, based on engineering judgment, in view of MSIV status indications available in the control room, and other administrative controls, to ensure that these valves are in the closed position.
D.1 and D.2 If the MSIVs cannot be restored to OPERABLE status or are not closed within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed at least in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2 conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.2.1 REQUIREMENTS This SR verifies that the closure time of each MSIV is < 8.0 seconds on an actual or simulated actuation signal. The MSIV closure time is assumed in the accident and containment analyses. This SR also Catawba Units 1 and 2 B 3.7.2-4 Revision No. I
MSIVs B 3.7.2 BASES SURVEILLANCE REQUIREMENTS (continued) verifies the valve closure time is in accordance with the Inservice Testing Program. This SR is normally performed upon returning the unit to operation following a refueling outage. The MSIVs should not be tested at power, since even a part stroke exercise increases the risk of a valve closure when the unit is generating power. As the MSIVs are not tested at power, they are exempt from the ASME Code,Section XI (Ref. 6),
requirements during operation in MODE 1 or 2. The Frequency is in accordance with the Inservice Testing Program.
This test is conducted in MODE 3 with the unit at operating temperature and pressure, as discussed in Reference 6 exercising requirements. This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR. This allows a delay of testing until MODE 3, to establish conditions consistent with those under which the acceptance criterion was generated.
REFERENCES 1. UFSAR, Section 10.3.
- 2. UFSAR, Section 6.2.
- 3. UFSAR, Section 15.1.5.
- 4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 5. 10 CFR 50.67.
- 6. ASME, Boiler and Pressure Vessel Code, Section Xl.
Catawba Units 1 and 2 B 3.7.2-5 Revision No. 2
MFIVs, MFCVs, Associated Bypass Valves and Tempering Valves B 3.7.3 BASES ACTIONS (continued) judgment, in view of valve status indications available in the control room, and other administrative controls, to ensure that these valves are closed orisolated.
D.1 With the tempering valve inoperable or two inoperable valves in the same flow path, there may be no redundant system to operate automatically and perform the required safety function. The tempering valves have no other automatic isolation valves in series to provide isolation. Under these conditions, affected valves in each flow path must be restored to OPERABLE status, or the affected flow path isolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. This action returns the system to the condition where at least one valve in each flow path is performing the required safety function. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is reasonable, based on operating experience, to complete the actions required to close the MFIV or MFCV, or otherwise isolate the affected flow path.
E.1 and E.2 If the MFIV(s), MFCV(s), and the associated bypass valve(s) or the tempering valve(s) cannot be restored to OPERABLE status, or closed, or isolated within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.3.1 REQUIREMENTS This SR verifies that the closure time .of each MFIV, MFCV, and associated bypass valves, and the tempering valve is <_12 seconds on an actual or simulated actuation signal. The MFIV and MFCV closure times are assumed in the accident and containment analyses. This SR also verifies the valve closure time is in accordance with the Inservice Testing Program. This SR is normally performed upon returning the unit to
.operation following a refueling outage. These valves should not be tested at power since even apart stroke exercise increases the risk of a valve closure with the unit generating power. This is consistent with the Catawba Units 1 and 2 B 3.7.3-5 Revision No. 1
MFIVs, MFCVs, Associated Bypass Valves and Tempering Valves B 3.7.3 BASES SURVEILLANCE REQUIREMENTS (continued)
ASME Code,Section XI (Ref. 3), quarterly stroke requirements during operation in MODES 1 and 2.
The Frequency for this SR is in accordance with the Inservice Testing Program.
REFERENCES 1. UFSAR, Section 10.4.7.
- 2. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 3. ASME, Boiler and Pressure Vessel Code,Section XI.
Catawba Units 1 and 2 B 3.7.3-6 Revision No. 1