ONS-2018-013, Technical Specification Bases Changes: Difference between revisions
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Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Numbers 50-269, 50-270, and 50-287 Technical Specification Bases Changes Carrie T. Dunton Director, Site Support Oconee Nuclear Station Duke Energy ON01VP / 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3477 | Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Numbers 50-269, 50-270, and 50-287 Technical Specification Bases Changes Carrie T. Dunton Director, Site Support Oconee Nuclear Station Duke Energy ON01VP / 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3477 | ||
: f. 864.873.4208 Carrie.dunton@duke-energy.com The attached changes to the Oconee Nuclear Station TS Bases were processed in accordance with the provisions of Technical Specification 5.5.15, "Technical Specifications (TS) Bases Control Program." Any questions regarding this information should be directed to Chris Wasik, Oconee Regulatory Affairs Manager, at (864) 873-5789. | : f. 864.873.4208 Carrie.dunton@duke-energy.com The attached changes to the Oconee Nuclear Station TS Bases were processed in accordance with the provisions of Technical Specification 5.5.15, "Technical Specifications (TS) Bases Control Program." Any questions regarding this information should be directed to Chris Wasik, Oconee Regulatory Affairs Manager, at (864) 873-5789. | ||
* Sincerely, (a~~ Director, Site Support Oconee Nuclear Station Attachments www.duke-energy.com U. S. Nuclear Regulatory Commission February 22, 2018 Page 2 cc: Ms. Catherine Haney Administrator, Region II U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Cente_r Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Ms. Audrey Klett, Project Manager (ONS) (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-08B1A Rockville, MD 20852-2738 Mr. Eddy L. Crowe Senior Resident Inspector Oconee Nuclear Station ONS-2018-013 February 22, 2018 Attachments TSB List of Effective Pages (LOEPs), Rev. 018 TSIB Limiting Condition for Operation (LCO) Applicability, Rev. 001 TSB Spent Fuel Pool Boron Concentration, Rev. 002 TSl3 Dry Spent Fuel Storage Cask Loading and Unloading, Rev. 001 TSl3 AC Sources -Operating, Rev. 003 LOEP 1-4 TSB3.0 1-18 TSB3.7.12 1-3 TSB3.7.18 1-4 TSB 3.8.1 1 -26 www.duke-energy.com OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER IMPLEMENTATION DATE TOC 000 09/03/14 B 2.1.1 001 06/08/17 B 2.1.2 000 02/06/14 B 3.0 001 08/23/17 B 3.1.1 000 05/16/12 B 3.1.2 000 05/16/12 B 3.1.3 000 06/02/99 B 3.1.4 000 07/23/12 B 3.1.5 000 05/16/12 B 3.1.6 000 07/23/12 B 3.1.7 000 07/23/12 B 3.1.8 000 05/16/12 B 3.2.l 000 05/16/12 B 3.2.2 000 05/16/12 B 3.2.3 000 05/16/12 B 3.3.1 003 01/17/17 B 3.3.2 000 12/14/04 B 3.3.3 000 12/10/14 B 3.3.4 000 12/10/14 B 3.3.5 000 12/10/14 B 3.3.6 000 12/10/14 B 3.3.7 000 12/10/14 B 3.3.8 000 05/16/12 B 3.3.9 000 05/16/12 B 3.3.10 000 05/16/12 B 3.3.11 001 01/17/17 B 3.3.12 000 05/16/12 Oconee Nuclear Station LOEP I Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DATE B 3.3.13 000 05/16/12 B 3.3.14 001 01/17/17 B 3.3.15 000 05/16/12 B 3.3.16 000 05/16/12 B 3.3.17 000 05/16/12 B 3.3.18 000 05/16/12 B 3.3.19 000 05/16/12 B 3.3.20 000 05/16/12 B 3.3.21 000 05/16/12 B 3.3.22 000 05/16/12 B 3.3.23 000 05/16/12 B 3.3.24 000 09/26/01 B 3.3.25 000 11/05/03 B 3.3.26 000 11/05/03 B 3.3.27 000 12/10/14 B 3.3.28 000 05/16/12 B 3.4.1 000 05/16/12 B 3.4.2 000 12/16/98 B 3.4.3 001 01/17/17 B 3.4.4 001 07/14/16 B 3.4.5 000 05/16/12 B 3.4.6 001 04/18/17 lB 3.4.7 001 04/18/17 B 3.4.8 001 04/18/17 B 3.4.9 000 05/16/12 B3.4.10 001 09/21/15 B3.4.11 000 10/12/12 B 3.4.12 000 06/13/14 Oconee Nuclear Station LOEP2 Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DATE B3.4.13 001 01/17/17 B 3.4.14 001 09/21/15 B 3.4.15 001 11/24/15 B 3.4.16 001 08/23/16 B 3.5.1 000 05/16/12 B 3.5.2 003 04/18/17 B 3.5.3 003 04/18/17 B 3.5.4 000 05/16/12 B 3.6.1 001 01/17/17 B 3.6.2 001 01/17/17 B 3.6.3 000 05/16/12 B 3.6.4 000 05/16/12 B 3.6.5 002 04/18/17 B 3.7.1 002 01/17/17 B 3.7.2 000 11/13/12 B 3.7.3 001 09/21/15 B 3.7.4 002 01/17/17 B 3.7.5 001 09/21/15 B 3.7.6 000 05/16/12 B 3.7.7 000 12/10/14 B 3.7.8 000 05/16/12 B 3.7.9 000 08/28/14 B 3.7.10 003 01/17/17 lB 3.7.1 Oa 001 01/17/17 B 3.7.11 000 05/16/12 B 3.7.12 002 08/09/17 B 3.7.13 000 08/19/10 B 3.7.14 000 05/16/12 Oconee Nuclear Station LOEP3 Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DA TE B 3.7.15 000 10/24/07 B 3.7.16 001 05/18/17 B 3.7.17 001 01/17/17 B 3.7.18 001 08/09/17 B 3.7.19 001 03/10/16 B 3.8.1 003 01/03/18 B 3.8.2 000 04/07/11 B 3.8.3 001 01/17/17 B 3.8.4 000 12/18/07 B 3.8.5 000 05/16/12 B 3.8.6 000 05/16/12 B 3.8.7 000 05/16/12 B 3.8.8 001 01/17/17 B 3.8.9 001 01/17/17 B 3.9.1 000 05/16/12 B 3.9.2 000 05/16/12 B 3.9.3 001 01/17/17 B 3.9.4 002 04/18/17 B 3.9.5 001 04/18/17 B 3.9.6 000 05/16/12 B 3.9.7 000 05/16/12 B 3.9.8 000 06/25/14 B 3.10.1 001 01/17/17 B 3.10.2 000 11/05/14 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation elates for revisions in effect prior to this change. Oconee Nuclear Station LOEP4 Revision O 18. | * Sincerely, (a~~ Director, Site Support Oconee Nuclear Station Attachments www.duke-energy.com U. S. Nuclear Regulatory Commission February 22, 2018 Page 2 cc: Ms. Catherine Haney Administrator, Region II U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Cente_r Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Ms. Audrey Klett, Project Manager (ONS) (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-08B1A Rockville, MD 20852-2738 Mr. Eddy L. Crowe Senior Resident Inspector Oconee Nuclear Station ONS-2018-013 February 22, 2018 Attachments TSB List of Effective Pages (LOEPs), Rev. 018 TSIB Limiting Condition for Operation (LCO) Applicability, Rev. 001 TSB Spent Fuel Pool Boron Concentration, Rev. 002 TSl3 Dry Spent Fuel Storage Cask Loading and Unloading, Rev. 001 TSl3 AC Sources -Operating, Rev. 003 LOEP 1-4 TSB3.0 1-18 TSB3.7.12 1-3 TSB3.7.18 1-4 TSB 3.8.1 1 -26 www.duke-energy.com OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER IMPLEMENTATION DATE TOC 000 09/03/14 B 2.1.1 001 06/08/17 B 2.1.2 000 02/06/14 B 3.0 001 08/23/17 B 3.1.1 000 05/16/12 B 3.1.2 000 05/16/12 B 3.1.3 000 06/02/99 B 3.1.4 000 07/23/12 B 3.1.5 000 05/16/12 B 3.1.6 000 07/23/12 B 3.1.7 000 07/23/12 B 3.1.8 000 05/16/12 B 3.2.l 000 05/16/12 B 3.2.2 000 05/16/12 B 3.2.3 000 05/16/12 B 3.3.1 003 01/17/17 B 3.3.2 000 12/14/04 B 3.3.3 000 12/10/14 B 3.3.4 000 12/10/14 B 3.3.5 000 12/10/14 B 3.3.6 000 12/10/14 B 3.3.7 000 12/10/14 B 3.3.8 000 05/16/12 B 3.3.9 000 05/16/12 B 3.3.10 000 05/16/12 B 3.3.11 001 01/17/17 B 3.3.12 000 05/16/12 Oconee Nuclear Station LOEP I Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DATE B 3.3.13 000 05/16/12 B 3.3.14 001 01/17/17 B 3.3.15 000 05/16/12 B 3.3.16 000 05/16/12 B 3.3.17 000 05/16/12 B 3.3.18 000 05/16/12 B 3.3.19 000 05/16/12 B 3.3.20 000 05/16/12 B 3.3.21 000 05/16/12 B 3.3.22 000 05/16/12 B 3.3.23 000 05/16/12 B 3.3.24 000 09/26/01 B 3.3.25 000 11/05/03 B 3.3.26 000 11/05/03 B 3.3.27 000 12/10/14 B 3.3.28 000 05/16/12 B 3.4.1 000 05/16/12 B 3.4.2 000 12/16/98 B 3.4.3 001 01/17/17 B 3.4.4 001 07/14/16 B 3.4.5 000 05/16/12 B 3.4.6 001 04/18/17 lB 3.4.7 001 04/18/17 B 3.4.8 001 04/18/17 B 3.4.9 000 05/16/12 B3.4.10 001 09/21/15 B3.4.11 000 10/12/12 B 3.4.12 000 06/13/14 Oconee Nuclear Station LOEP2 Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DATE B3.4.13 001 01/17/17 B 3.4.14 001 09/21/15 B 3.4.15 001 11/24/15 B 3.4.16 001 08/23/16 B 3.5.1 000 05/16/12 B 3.5.2 003 04/18/17 B 3.5.3 003 04/18/17 B 3.5.4 000 05/16/12 B 3.6.1 001 01/17/17 B 3.6.2 001 01/17/17 B 3.6.3 000 05/16/12 B 3.6.4 000 05/16/12 B 3.6.5 002 04/18/17 B 3.7.1 002 01/17/17 B 3.7.2 000 11/13/12 B 3.7.3 001 09/21/15 B 3.7.4 002 01/17/17 B 3.7.5 001 09/21/15 B 3.7.6 000 05/16/12 B 3.7.7 000 12/10/14 B 3.7.8 000 05/16/12 B 3.7.9 000 08/28/14 B 3.7.10 003 01/17/17 lB 3.7.1 Oa 001 01/17/17 B 3.7.11 000 05/16/12 B 3.7.12 002 08/09/17 B 3.7.13 000 08/19/10 B 3.7.14 000 05/16/12 Oconee Nuclear Station LOEP3 Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DA TE B 3.7.15 000 10/24/07 B 3.7.16 001 05/18/17 B 3.7.17 001 01/17/17 B 3.7.18 001 08/09/17 B 3.7.19 001 03/10/16 B 3.8.1 003 01/03/18 B 3.8.2 000 04/07/11 B 3.8.3 001 01/17/17 B 3.8.4 000 12/18/07 B 3.8.5 000 05/16/12 B 3.8.6 000 05/16/12 B 3.8.7 000 05/16/12 B 3.8.8 001 01/17/17 B 3.8.9 001 01/17/17 B 3.9.1 000 05/16/12 B 3.9.2 000 05/16/12 B 3.9.3 001 01/17/17 B 3.9.4 002 04/18/17 B 3.9.5 001 04/18/17 B 3.9.6 000 05/16/12 B 3.9.7 000 05/16/12 B 3.9.8 000 06/25/14 B 3.10.1 001 01/17/17 B 3.10.2 000 11/05/14 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation elates for revisions in effect prior to this change. Oconee Nuclear Station LOEP4 Revision O 18. | ||
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This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. If at the end of 1 hour, corrective measures which would allow exiting LCO 3.0.3 are not complete, but there is reasonable assurance that corrective measures will be completed in time to still allow for an orderly unit shutdown, commencing a load decrease may be delayed until that time. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is OPERABLE. | This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. If at the end of 1 hour, corrective measures which would allow exiting LCO 3.0.3 are not complete, but there is reasonable assurance that corrective measures will be completed in time to still allow for an orderly unit shutdown, commencing a load decrease may be delayed until that time. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is OPERABLE. | ||
This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Specification applies. The use and interpretation of specified times to complete the actions of | This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Specification applies. The use and interpretation of specified times to complete the actions of | ||
* LCO 3.0.3 are consistent with the discussion of Section 1.3, Completion Times. A unit shutdown required in accordance with LCO 3.0.3 may be terminated and LCO 3.0.3 exited if any of the following occurs: a. The LCO is now met. b. A Condition exists for which the Required Actions have now been performed. | * LCO 3.0.3 are consistent with the discussion of Section 1.3, Completion Times. A unit shutdown required in accordance with LCO 3.0.3 may be terminated and LCO 3.0.3 exited if any of the following occurs: a. The LCO is now met. b. A Condition exists for which the Required Actions have now been performed. | ||
: c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time LCO 3.0.3 is exited. OCONEE UNITS 1, 2, & 3 B 3.0-3 Rev.001 I r ---BASES LCO 3.0.3 (continued) | : c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time LCO 3.0.3 is exited. OCONEE UNITS 1, 2, & 3 B 3.0-3 Rev.001 I r ---BASES LCO 3.0.3 (continued) | ||
LCO 3.0.4 LCO Applicability B 3.0 The time limits of LCO 3.0.3 allow 37 hours for the unit to be in MODE 5 when a shutdown is required during MODE 1 operation. | LCO 3.0.4 LCO Applicability B 3.0 The time limits of LCO 3.0.3 allow 37 hours for the unit to be in MODE 5 when a shutdown is required during MODE 1 operation. | ||
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However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO. OCONEE UNITS 1, 2, & 3 B 3.0-5 Rev.001 I BASES (continued) | However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO. OCONEE UNITS 1, 2, & 3 B 3.0-5 Rev.001 I BASES (continued) | ||
LCO 3.0.5 LCO 3.0.6 LCO Applicability B 3.0 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Required Action(s)) | LCO 3.0.5 LCO 3.0.6 LCO Applicability B 3.0 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Required Action(s)) | ||
to allow the performance of required testing to demonstrate: | to allow the performance of required testing to demonstrate: | ||
: a. The OPERABILITY of the equipment being returned to service; or b. The OPERABILITY of other equipment. | : a. The OPERABILITY of the equipment being returned to service; or b. The OPERABILITY of other equipment. | ||
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. | The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. | ||
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LCO Applicability B 3.0 declared inoperable if determined to be inoperable as a result of the support system inoperability. | LCO Applicability B 3.0 declared inoperable if determined to be inoperable as a result of the support system inoperability. | ||
However, it is not necessary to enter into the supported systems' Conditions and Required Actions unless directed to do so by the support system's Required Actions. The potential confusion and inconsistency of requirements related to the entry into multiple support and supported systems' LCOs' Conditions and Required Actions are eliminated by providing all the actions that are necessary to ensure the unit is maintained in a safe condition in the support system's Required Actions. However, there are instances where a support system's Required Action may either direct a supported system to be declared inoperable or direct entry into Conditions and Required Actions for the supported system. This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's Required Action directs a supported system to be declared inoperable or directs entry in Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2. Specification 5.5.16, "Safety Function Determination Program (SFDP)," ensures loss of safety function is detected and appropriate actions are taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. The SFDP implements the requirements of LCO 3.0.6. Cross train checks to identify a loss of safety function for those support systems that support multiple and redundant safety systems are required. | However, it is not necessary to enter into the supported systems' Conditions and Required Actions unless directed to do so by the support system's Required Actions. The potential confusion and inconsistency of requirements related to the entry into multiple support and supported systems' LCOs' Conditions and Required Actions are eliminated by providing all the actions that are necessary to ensure the unit is maintained in a safe condition in the support system's Required Actions. However, there are instances where a support system's Required Action may either direct a supported system to be declared inoperable or direct entry into Conditions and Required Actions for the supported system. This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's Required Action directs a supported system to be declared inoperable or directs entry in Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2. Specification 5.5.16, "Safety Function Determination Program (SFDP)," ensures loss of safety function is detected and appropriate actions are taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. The SFDP implements the requirements of LCO 3.0.6. Cross train checks to identify a loss of safety function for those support systems that support multiple and redundant safety systems are required. | ||
The cross train check verifies that the supported systems of the remaining OPERABLE support systems are OPERABLE, thereby ensuring safety function is retained. | The cross train check verifies that the supported systems of the remaining OPERABLE support systems are OPERABLE, thereby ensuring safety function is retained. | ||
: a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or (EXAMPLE B3.06-1) b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or (EXAMPLE B3.06-2) c. A required system redundant to support system(s)for the supported systems (a) and (b) above is also inoperable. (EXAMPLE B3.06-3) OCONEE UNITS 1, 2, & 3 B 3.0-7 Rev. 001 I BASES LCO 3.0.6 (continued) | : a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or (EXAMPLE B3.06-1) b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or (EXAMPLE B3.06-2) c. A required system redundant to support system(s)for the supported systems (a) and (b) above is also inoperable. (EXAMPLE B3.06-3) OCONEE UNITS 1, 2, & 3 B 3.0-7 Rev. 001 I BASES LCO 3.0.6 (continued) | ||
System 2 System 1 System 3 EXAMPLE 83.06-1 LCO Applicability B 3.0 If System 2 of Train A is inoperable, and System 5 of Train B is inoperable, a loss of safety function exists in supported System 5. EXAMPLE 83.06-2 If System 2 of Train A is inoperable, and System 11 of Train B is inoperable, a loss of safety function exists in System 11 which is in turn supported by System 5. EXAMPLE 83.06-3 If System 2 of Train A is inoperable, and System 1 of Train B is inoperable, a loss of safety function exists in Systems 2, 4, 5, 8, 9, 10 and 11. If this evaluation determines that a loss of safety function exists, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. EXAMPLES TRAINA TRAIN B ~~ma ~~ma System 4 System 4 System 9 System 9 System 2 ~~m10 ~~Wm10 System 5 System 5 System 11 System 11 System 1 ~~m12 ~~Wm12 System 6 System 6 System 13 System 13 System 3 ~~m14 ~ymm14 System 7 System 7 System 15 System 15 OCONEE UNITS 1, 2, & 3 B 3.0-8 Rev.001 I BASES (continued) | System 2 System 1 System 3 EXAMPLE 83.06-1 LCO Applicability B 3.0 If System 2 of Train A is inoperable, and System 5 of Train B is inoperable, a loss of safety function exists in supported System 5. EXAMPLE 83.06-2 If System 2 of Train A is inoperable, and System 11 of Train B is inoperable, a loss of safety function exists in System 11 which is in turn supported by System 5. EXAMPLE 83.06-3 If System 2 of Train A is inoperable, and System 1 of Train B is inoperable, a loss of safety function exists in Systems 2, 4, 5, 8, 9, 10 and 11. If this evaluation determines that a loss of safety function exists, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. EXAMPLES TRAINA TRAIN B ~~ma ~~ma System 4 System 4 System 9 System 9 System 2 ~~m10 ~~Wm10 System 5 System 5 System 11 System 11 System 1 ~~m12 ~~Wm12 System 6 System 6 System 13 System 13 System 3 ~~m14 ~ymm14 System 7 System 7 System 15 System 15 OCONEE UNITS 1, 2, & 3 B 3.0-8 Rev.001 I BASES (continued) | ||
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The DSC burnup requirements are provided in LCO 3.7.18. The minimum SFP boron concentration of 2220 ppm (per SR 3.7.12.1) allows sufficient time to detect and mitigate all credible boron dilution scenarios, well before the SFP boron concentration drops to 430 ppm. The minimum 2220 ppm boron is available for all accident conditions evaluated in the SFP rack and DSC criticality analyses, per the double contingency principle (Ref. 4 ). APPLICABLE Reference 3 discusses several criticality accident conditions that should SAFETY ANALYSES be considered in SFP storage rack criticality analyses. | The DSC burnup requirements are provided in LCO 3.7.18. The minimum SFP boron concentration of 2220 ppm (per SR 3.7.12.1) allows sufficient time to detect and mitigate all credible boron dilution scenarios, well before the SFP boron concentration drops to 430 ppm. The minimum 2220 ppm boron is available for all accident conditions evaluated in the SFP rack and DSC criticality analyses, per the double contingency principle (Ref. 4 ). APPLICABLE Reference 3 discusses several criticality accident conditions that should SAFETY ANALYSES be considered in SFP storage rack criticality analyses. | ||
Applicable accidents for the Oconee SFP storage racks include: 1) drop of a fuel assembly on top of the SFP storage rack; 2) drop of a fuel assembly outside of the storage rack modules; 3) abnormal SFP water temperatures outside the normal temperature range; 4) the misloading of a fuel assembly in a storage cell for which restrictions on location, enrichment, burnup, or post-irradiation cooling time are not satisfied; and 5) the drop of a heavy load (transfer cask) onto the SFP storage racks (NUREG-0612). | Applicable accidents for the Oconee SFP storage racks include: 1) drop of a fuel assembly on top of the SFP storage rack; 2) drop of a fuel assembly outside of the storage rack modules; 3) abnormal SFP water temperatures outside the normal temperature range; 4) the misloading of a fuel assembly in a storage cell for which restrictions on location, enrichment, burnup, or post-irradiation cooling time are not satisfied; and 5) the drop of a heavy load (transfer cask) onto the SFP storage racks (NUREG-0612). | ||
Of these SFP storage rack accidents, the heavy load. drop event requires the largest amount of soluble boron (almost 2200 ppm) to maintain SFP keff 0.95. OCONEE UNITS 1, 2, & 3 B 3.7.12-1 Rev.002 J BASES Spent Fuel Pool Boron Concentration B 3.7.12 APPLICABLE The accident scenarios (Ref. 3) that are valid for the loading/unloading SAH:TY ANALYSES of a NU HOMS@ -24P/24PHB DSC include:* | Of these SFP storage rack accidents, the heavy load. drop event requires the largest amount of soluble boron (almost 2200 ppm) to maintain SFP keff 0.95. OCONEE UNITS 1, 2, & 3 B 3.7.12-1 Rev.002 J BASES Spent Fuel Pool Boron Concentration B 3.7.12 APPLICABLE The accident scenarios (Ref. 3) that are valid for the loading/unloading SAH:TY ANALYSES of a NU HOMS@ -24P/24PHB DSC include:* | ||
: 1) drop of a fuel assembly (continued) on top of the DSC storage cells; 2) drop of a fuel assembly immediately outside of the transfer cask containing the DSC; 3) abnormal SFP water temperatures beyond the normal temperature range; and 4) the misloading of a fresh 5.0 wt % U-235 fuel assembly in one of the DSC storage cells. Of these DSC accidents, the misload event requires the largest amount of soluble boron (630 ppm) to achieve a system kett 0.95. LCO APPLICABILITY ACTIONS Note that it is plausible to consider a loss of normal SFP cooling accident occurring in conjunction with a boron dilution event in the Oconee SFPs. In this unlikely scenario, with SFP water temperatures up to 212°F, the largest concentration of soluble boron required to maintain system kett 0.95 is 500 ppm (for the SFP storage racks). This amount of soluble boron is still much less than that remaining after the worst-case credible dilution event (825 ppm). Therefore, maintaining the SFP boron concentration 2220 ppm per SR 3. 7 .12.1 ensures that kett 0.95 for any accident conditions in the SFP storage rack or NUHOMS@ -24P/24PHB DSC. This minimum boron concentration limit includes allowance for analytical, mechanical, and instrument measurement uncertainties. | : 1) drop of a fuel assembly (continued) on top of the DSC storage cells; 2) drop of a fuel assembly immediately outside of the transfer cask containing the DSC; 3) abnormal SFP water temperatures beyond the normal temperature range; and 4) the misloading of a fresh 5.0 wt % U-235 fuel assembly in one of the DSC storage cells. Of these DSC accidents, the misload event requires the largest amount of soluble boron (630 ppm) to achieve a system kett 0.95. LCO APPLICABILITY ACTIONS Note that it is plausible to consider a loss of normal SFP cooling accident occurring in conjunction with a boron dilution event in the Oconee SFPs. In this unlikely scenario, with SFP water temperatures up to 212°F, the largest concentration of soluble boron required to maintain system kett 0.95 is 500 ppm (for the SFP storage racks). This amount of soluble boron is still much less than that remaining after the worst-case credible dilution event (825 ppm). Therefore, maintaining the SFP boron concentration 2220 ppm per SR 3. 7 .12.1 ensures that kett 0.95 for any accident conditions in the SFP storage rack or NUHOMS@ -24P/24PHB DSC. This minimum boron concentration limit includes allowance for analytical, mechanical, and instrument measurement uncertainties. | ||
The concentration of dissolved boron in the SFP satisfies Criterion 2 of 10 CFR 50.36 (Ref. 5). The minimum concentration of dissolved boron in the SFP (2220 ppm) preserves the assumptions used in the analyses of the potential accident scenarios described above. The minimum boron concentration ensures that the system kettfor the SFP storage rack or the NUHOMS@ -24P/24PHB DSC will remain below 0.95 for all credible criticality accident scenarios and boron dilution events. This LCO applies whenever fuel assemblies are stored in the SFP storage racks, or whenever fuel assemblies are being loaded into a NU HOMS@ -24P/24PHB DSC in the SFP. This LCO applies only to spent fuel storage casks loaded under the ISFSI site-specific license. Site-specific storage casks are contained in Horizontal Storage Modules (HSMs) Nos. 1 through 40. A.1 and A.2 The Required Actions are modified by a Note indicating that LCO 3.0.3 does not apply. OCONEE UNITS 1, 2, & 3 B 3.7.12-2 Rev. 002 I BASES ACTIONS A.1 and A.2 (continued) | The concentration of dissolved boron in the SFP satisfies Criterion 2 of 10 CFR 50.36 (Ref. 5). The minimum concentration of dissolved boron in the SFP (2220 ppm) preserves the assumptions used in the analyses of the potential accident scenarios described above. The minimum boron concentration ensures that the system kettfor the SFP storage rack or the NUHOMS@ -24P/24PHB DSC will remain below 0.95 for all credible criticality accident scenarios and boron dilution events. This LCO applies whenever fuel assemblies are stored in the SFP storage racks, or whenever fuel assemblies are being loaded into a NU HOMS@ -24P/24PHB DSC in the SFP. This LCO applies only to spent fuel storage casks loaded under the ISFSI site-specific license. Site-specific storage casks are contained in Horizontal Storage Modules (HSMs) Nos. 1 through 40. A.1 and A.2 The Required Actions are modified by a Note indicating that LCO 3.0.3 does not apply. OCONEE UNITS 1, 2, & 3 B 3.7.12-2 Rev. 002 I BASES ACTIONS A.1 and A.2 (continued) | ||
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This does not preclude movement of a fuel assembly to a safe position. | This does not preclude movement of a fuel assembly to a safe position. | ||
Immediate action is also required to initiate action to restore the SFP boron concentration to within limits. SURVEILLANCE SR 3.7.12.1 REQUIREMENTS REFERENCES This SR verifies that the concentration of boron in the SFP is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed. | Immediate action is also required to initiate action to restore the SFP boron concentration to within limits. SURVEILLANCE SR 3.7.12.1 REQUIREMENTS REFERENCES This SR verifies that the concentration of boron in the SFP is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed. | ||
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. The COLR revision process assures that the minimum boron concentration specified in the COLR bounds the limit specified by this SR. 1. 10 CFR 50.68(b). | The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. The COLR revision process assures that the minimum boron concentration specified in the COLR bounds the limit specified by this SR. 1. 10 CFR 50.68(b). | ||
: 2. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants," ANSI/ANS-57.2-1983, October 7, 1983. 3. Nuclear Regulatory Commission, Memorandum to Timothy Collins from Laurence Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants," August 19, 1998. 4. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A). 5. 10 CFR 50.36. OCONEE UNITS 1, 2, & 3 B 3.7.12-3, Rev. 002 I Dry Spent Fuel Cask Loading and Unloading 83.7.18 B 3. 7 PLANT SYSTEMS B 3.7.18 Dry Spent Fuel Storage Cask Loading and Unloading BASES ================================ | : 2. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants," ANSI/ANS-57.2-1983, October 7, 1983. 3. Nuclear Regulatory Commission, Memorandum to Timothy Collins from Laurence Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants," August 19, 1998. 4. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A). 5. 10 CFR 50.36. OCONEE UNITS 1, 2, & 3 B 3.7.12-3, Rev. 002 I Dry Spent Fuel Cask Loading and Unloading 83.7.18 B 3. 7 PLANT SYSTEMS B 3.7.18 Dry Spent Fuel Storage Cask Loading and Unloading BASES ================================ | ||
BACKGROUND Fuel loading and unloading operations for the NUHOMS@-24P and NUHOMS@-24PHB dry storage canisters (DSCs) take place in the cask pit area of the spent fuel pool. The cask pit is adjacent to the spent fuel storage racks in each of the Oconee spent fuel pools, and is open to the rest of the spent fuel pool at all times. The NUHOMS@-24P and NUHOMS@-24PHB DSCs contain storage cells for 24 fuel assemblies. | BACKGROUND Fuel loading and unloading operations for the NUHOMS@-24P and NUHOMS@-24PHB dry storage canisters (DSCs) take place in the cask pit area of the spent fuel pool. The cask pit is adjacent to the spent fuel storage racks in each of the Oconee spent fuel pools, and is open to the rest of the spent fuel pool at all times. The NUHOMS@-24P and NUHOMS@-24PHB DSCs contain storage cells for 24 fuel assemblies. | ||
Eligible B&W 15x15 fuel assemblies (Mk82-88, Mk89, and Mk810) with initial enrichments s 5.0 wt % U-235 may be stored in the NUHOMS@-24P or NUHOMS@-24PHB DSC, as long as the fuel assemblies meet the minimum burnup and cooling time requirements specified in Table 3.7.18-1. | Eligible B&W 15x15 fuel assemblies (Mk82-88, Mk89, and Mk810) with initial enrichments s 5.0 wt % U-235 may be stored in the NUHOMS@-24P or NUHOMS@-24PHB DSC, as long as the fuel assemblies meet the minimum burnup and cooling time requirements specified in Table 3.7.18-1. | ||
For normal conditions in the spent fuel pool, the NUHOMS@-24P and NUHOMS@-24PHB DSCs have been analyzed using credit for soluble boron as allowed in Reference | For normal conditions in the spent fuel pool, the NUHOMS@-24P and NUHOMS@-24PHB DSCs have been analyzed using credit for soluble boron as allowed in Reference | ||
: 1. This ensures that the system multiplication factor, kett, is~ 0.95 as recommended in ANSI/ANS-57.2-1983 (Ref. 2) and NRC guidance (Ref. 3). The DSC is analyzed to allow loading/unloading of eligible fuel assemblies while maintaining kett~ 0.95, including uncertainties, tolerances, biases, and credit for 430 ppm soluble boron. Note that the criticality analysis accounts for a maximum as-built enrichment tolerance of 0.05 wt % U-235. For example, for a specified maximum design enrichment of 5.00 wt % U-235, an as-built enrichment up to 5.05 weight percent is acceptable. | : 1. This ensures that the system multiplication factor, kett, is~ 0.95 as recommended in ANSI/ANS-57.2-1983 (Ref. 2) and NRC guidance (Ref. 3). The DSC is analyzed to allow loading/unloading of eligible fuel assemblies while maintaining kett~ 0.95, including uncertainties, tolerances, biases, and credit for 430 ppm soluble boron. Note that the criticality analysis accounts for a maximum as-built enrichment tolerance of 0.05 wt % U-235. For example, for a specified maximum design enrichment of 5.00 wt % U-235, an as-built enrichment up to 5.05 weight percent is acceptable. | ||
The 430 ppm soluble boron credit must provide sufficient subcritical margin to maintain the DSC kett 0.95. In addition, sub-criticality of the DSC (kett < 1.0) must be assured on a 95/95 basis, without the presence of any soluble boron in the spent fuel pool. The dual kett criteria identified in the above paragraph are satisfied for fuel assemblies meeting the minimum burnup and post-irradiation cooling time requirements specified in Table 3. 7.18-1. Reactivity reduction with cooling time is primarily attributable to Pu-241 decay and Gd-155 buildup (via Eu-155 decay). Specification 4.4.1 c. requires that the DSC kett be~ 0.95 when flooded with water borated to 430 ppm. A spent fuel pool boron dilution analysis has been performed that confirms that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 kett OCOI\IEE UNITS 1, 2, & 3 B 3.7.18-1 Rev. 001 BASES BACl<GROUND (continued) | The 430 ppm soluble boron credit must provide sufficient subcritical margin to maintain the DSC kett 0.95. In addition, sub-criticality of the DSC (kett < 1.0) must be assured on a 95/95 basis, without the presence of any soluble boron in the spent fuel pool. The dual kett criteria identified in the above paragraph are satisfied for fuel assemblies meeting the minimum burnup and post-irradiation cooling time requirements specified in Table 3. 7.18-1. Reactivity reduction with cooling time is primarily attributable to Pu-241 decay and Gd-155 buildup (via Eu-155 decay). Specification 4.4.1 c. requires that the DSC kett be~ 0.95 when flooded with water borated to 430 ppm. A spent fuel pool boron dilution analysis has been performed that confirms that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 kett OCOI\IEE UNITS 1, 2, & 3 B 3.7.18-1 Rev. 001 BASES BACl<GROUND (continued) | ||
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The spent fuel pool boron dilution analysis concluded that an unplanned or inadvertent event which could result in the dilution of the spent fuel pool boron concentration to 430 ppm is not a credible event. | The spent fuel pool boron dilution analysis concluded that an unplanned or inadvertent event which could result in the dilution of the spent fuel pool boron concentration to 430 ppm is not a credible event. | ||
* APPLICABLE Several accident conditions (Ref. 3) are considered that could result SAFETY ANALYSES in an increase in system kett for a DSC being loaded or unloaded in the spent fuel pool. These accident conditions include the drop of a fuel assembly on top of the DSC storage cells, the drop of a fuel assembly just outside the transfer cask 9ontaining the DSC, a higher than normal spent fuel pool water temperature, and the misleading of a fresh 5.0 wt % U-235 assembly in one of the DSC storage cells. For an occurrence of these postulated accidents, the double contingency principle discussed in ANSI N-16.1-1975 and the April 1978 NRC letter (Ref. 4) can be applied. This double contingency principle does not require assuming two unlikely, independent, concurrent events to ensure protection against a criticality accident. | * APPLICABLE Several accident conditions (Ref. 3) are considered that could result SAFETY ANALYSES in an increase in system kett for a DSC being loaded or unloaded in the spent fuel pool. These accident conditions include the drop of a fuel assembly on top of the DSC storage cells, the drop of a fuel assembly just outside the transfer cask 9ontaining the DSC, a higher than normal spent fuel pool water temperature, and the misleading of a fresh 5.0 wt % U-235 assembly in one of the DSC storage cells. For an occurrence of these postulated accidents, the double contingency principle discussed in ANSI N-16.1-1975 and the April 1978 NRC letter (Ref. 4) can be applied. This double contingency principle does not require assuming two unlikely, independent, concurrent events to ensure protection against a criticality accident. | ||
Thus, for these postulated accident conditions, the presence of additional soluble boron in the spent fuel pool water (above the 430 ppm required to maintain kett 0.95 under normal DSC loading/unloading conditions) can be assumed as a realistic initial condition since not assuming its presence would be a second unlikely event. Calculations were performed to determine the amount of soluble boron required to offset the highest reactivity increase associated with these postulated accidents, in order to maintain kett .'.::. 0.95. It was found that a spent fuel pool boron concentration of 630 ppm was sufficient to maintain kett 0.95 for the worst-case postulated criticality-related accident (the fresh fuel assembly misloaded in a DSC storage cell). Specification | Thus, for these postulated accident conditions, the presence of additional soluble boron in the spent fuel pool water (above the 430 ppm required to maintain kett 0.95 under normal DSC loading/unloading conditions) can be assumed as a realistic initial condition since not assuming its presence would be a second unlikely event. Calculations were performed to determine the amount of soluble boron required to offset the highest reactivity increase associated with these postulated accidents, in order to maintain kett .'.::. 0.95. It was found that a spent fuel pool boron concentration of 630 ppm was sufficient to maintain kett 0.95 for the worst-case postulated criticality-related accident (the fresh fuel assembly misloaded in a DSC storage cell). Specification | ||
: 3. 7.12 ensures the spent fuel pool contains adequate dissolved boron to compensate for the increased reactivity caused by these postulated accidents. | : 3. 7.12 ensures the spent fuel pool contains adequate dissolved boron to compensate for the increased reactivity caused by these postulated accidents. | ||
For normal storage conditions, Specification 4.3.1 c. requires that the spent fuel rack kett be~ 0.95 when flooded with water borated to 430 ppm. A spent fuel pool boron dilution analysis was performed which confirmed that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 kett design basis is exceeded. | For normal storage conditions, Specification 4.3.1 c. requires that the spent fuel rack kett be~ 0.95 when flooded with water borated to 430 ppm. A spent fuel pool boron dilution analysis was performed which confirmed that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 kett design basis is exceeded. | ||
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When the configuration of fuel assemblies loaded in the NUHOMS@-24P or NUHOMS@-24PHB DSC is not in accordance with the LCO, immediate action must be taken to make the necessary fuel assembly movement(s) to bring the configuration into compliance with the LCO. SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment, burn up, and post-irradiation cooling time of the fuel assembly to be loaded into or removed from the NUHOMS@-24P or NUHOMS@-24PHB DSC is in accordance with Table 3.7.18-1. | When the configuration of fuel assemblies loaded in the NUHOMS@-24P or NUHOMS@-24PHB DSC is not in accordance with the LCO, immediate action must be taken to make the necessary fuel assembly movement(s) to bring the configuration into compliance with the LCO. SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment, burn up, and post-irradiation cooling time of the fuel assembly to be loaded into or removed from the NUHOMS@-24P or NUHOMS@-24PHB DSC is in accordance with Table 3.7.18-1. | ||
OCONEE UNITS 1, 2, & 3 B 3.7.18-3 Rev. 001 BASES ( continued) | OCONEE UNITS 1, 2, & 3 B 3.7.18-3 Rev. 001 BASES ( continued) | ||
REFERENCES Dry Spent Fuel Cask Loading and Unloading 83.7.18 1. 10 CFR 50.68(b)(4) | REFERENCES Dry Spent Fuel Cask Loading and Unloading 83.7.18 1. 10 CFR 50.68(b)(4) | ||
: 2. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants," ANSI/ANS-57.2-1983, October 7, 1983. 3. Nuclear Regulatory Commission, Memorandum to Timothy Collins from Laurence Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants," August 19, 1998. 4. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A). 5. 10 CFR 50.36 OCONEE UNITS 1, 2, & 3 8 3.7.18-4 Rev. 001 AC Sources -Operating B 3.8.1 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.1 AC Sources -Operating BASES ================================== | : 2. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants," ANSI/ANS-57.2-1983, October 7, 1983. 3. Nuclear Regulatory Commission, Memorandum to Timothy Collins from Laurence Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants," August 19, 1998. 4. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A). 5. 10 CFR 50.36 OCONEE UNITS 1, 2, & 3 8 3.7.18-4 Rev. 001 AC Sources -Operating B 3.8.1 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.1 AC Sources -Operating BASES ================================== | ||
BACKGROUND The AC Power System consists of the offsite power sources (preferred power) and the onsite standby power sources, Keowee Hydro Units (KHU). This system is designed to supply the required Engineered Safeguards (ES) loads of one unit and safe shutdown loads of the other two units and is so arranged that no single failure can disable enough loads to jeopardize plant safety. The design of the AC Power System provides independence and redundancy to ensure an available source of power to the ES systems (Ref. 1). The KHU turbine generators are powered through a common penstock by water taken from Lake Keowee. The use of a common penstock is justified on the basis of past hydro plant experience of the licensee (since 1919) which indicates that the cumulative need to dewater the penstock can be expected to be limited to about one day a year, principally for inspection, plus perhaps four days every tenth year. The preferred power source is provided from offsite power to the red or yellow bus in the 230 kV switchyard to the units startup transformer and the E breakers. | BACKGROUND The AC Power System consists of the offsite power sources (preferred power) and the onsite standby power sources, Keowee Hydro Units (KHU). This system is designed to supply the required Engineered Safeguards (ES) loads of one unit and safe shutdown loads of the other two units and is so arranged that no single failure can disable enough loads to jeopardize plant safety. The design of the AC Power System provides independence and redundancy to ensure an available source of power to the ES systems (Ref. 1). The KHU turbine generators are powered through a common penstock by water taken from Lake Keowee. The use of a common penstock is justified on the basis of past hydro plant experience of the licensee (since 1919) which indicates that the cumulative need to dewater the penstock can be expected to be limited to about one day a year, principally for inspection, plus perhaps four days every tenth year. The preferred power source is provided from offsite power to the red or yellow bus in the 230 kV switchyard to the units startup transformer and the E breakers. | ||
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Operable offsite sources are required to be "physically independent" (separate towers) prior to entering the 230 kV switchyard. | Operable offsite sources are required to be "physically independent" (separate towers) prior to entering the 230 kV switchyard. | ||
Once the 230 kV lines enter the switchyard, an electrical pathway must exist through OPERABLE power circuit breakers (PCBs) and disconnects such that both sources are available to energize the Unit's startup transformer either automatically or with operator action. Once within the boundary of the switchyard, the electrical pathway may be the same for both independent offsite sources. In addition, at least one E breaker must be available to automatically supply power to a main feeder bus from the energized startup transformer. | Once the 230 kV lines enter the switchyard, an electrical pathway must exist through OPERABLE power circuit breakers (PCBs) and disconnects such that both sources are available to energize the Unit's startup transformer either automatically or with operator action. Once within the boundary of the switchyard, the electrical pathway may be the same for both independent offsite sources. In addition, at least one E breaker must be available to automatically supply power to a main feeder bus from the energized startup transformer. | ||
The voltage provided to the startup transformer by the two independent offsite sources must be sufficient to ensure ES equipment will operate. Two of the following offsite sources are required: | The voltage provided to the startup transformer by the two independent offsite sources must be sufficient to ensure ES equipment will operate. Two of the following offsite sources are required: | ||
: 1) Jocassee (from Jocassee) | : 1) Jocassee (from Jocassee) | ||
Black or White, 2) Dacus (from North Greenville) | Black or White, 2) Dacus (from North Greenville) | ||
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LCO (continued) | LCO (continued) | ||
An OPERABLE KHU and its required overhead emergency power path must be capable of automatically supplying power from the KHU through the KHU main step-up transformer, the 230 kV yellow bus, the Unit startup transformer and both E breakers to both main feeder buses. At least one channel of switchyard isolation (by actuation from degraded grid voltage protection) is required to be OPERABLE to isolate the 230 kV switchyard yellow bus. If closed, each N breaker must be capable of opening using either of its associated breaker trip circuits. | An OPERABLE KHU and its required overhead emergency power path must be capable of automatically supplying power from the KHU through the KHU main step-up transformer, the 230 kV yellow bus, the Unit startup transformer and both E breakers to both main feeder buses. At least one channel of switchyard isolation (by actuation from degraded grid voltage protection) is required to be OPERABLE to isolate the 230 kV switchyard yellow bus. If closed, each N breaker must be capable of opening using either of its associated breaker trip circuits. | ||
KPF-9 (for KHU1) and KPF-10 (for KHU2) must remain open since there is no engineering analysis that ensures that the associated KHU can power both PSW and Engineered Safeguards (ES) system loads should an event occur (with the breaker closed). Either of the following combinations provides an acceptable KHU and required overhead emergency power path: Keowee Hydro Unit Keowee Hydro Unit 1A) Keowee Unit 1 generator, 1 B) Keowee Unit 2 generator, 2A) Keowee ACB 1 (enabled by 28) Keowee ACB 2 (enabled by one channel of Switchyard one channel of Switchyard Isolate Complete), Isolate Complete), 3A) Keowee auxiliary transformer | KPF-9 (for KHU1) and KPF-10 (for KHU2) must remain open since there is no engineering analysis that ensures that the associated KHU can power both PSW and Engineered Safeguards (ES) system loads should an event occur (with the breaker closed). Either of the following combinations provides an acceptable KHU and required overhead emergency power path: Keowee Hydro Unit Keowee Hydro Unit 1A) Keowee Unit 1 generator, 1 B) Keowee Unit 2 generator, 2A) Keowee ACB 1 (enabled by 28) Keowee ACB 2 (enabled by one channel of Switchyard one channel of Switchyard Isolate Complete), Isolate Complete), 3A) Keowee auxiliary transformer | ||
: 38) Keowee auxiliary transformer 1X, Keowee ACB 5, Keowee 2X, Keowee ACB 6, Keowee Load Center 1X, Load Center 2X, 4A) Keowee MCC 1 XA, 48) Keowee MCC 2XA, SA) Keowee Battery #1, Charger SB) Keowee Battery #2, Charger #1 or Standby Charger, and #2 or Standby Charger, and Distribution Center 1 DA, Distribution Center 2DA, 6A) ACB-1 to ACB-3 interlock, 68) ACB-2 to ACB-4 interlock, 7 A) Keowee Unit 1 Voltage and 78) Keowee Unit 2 Voltage and Frequency out of tolerance Frequency out of tolerance (OOT) logic (OOT) logic 8) Keowee reservoir level~ 775 feet above sea level, BA) KPF-9 is OPEN with closing 88) KPF-10 is OPEN with closing spring discharged, spring discharged, Overhead Emergency Power Path 9) Keowee main step-up transformer, 10) PCB 9 (enabled by one channel of Switchyard Isolate Complete), 11) The 230kV switchyard yellow bus capable of being isolated by one channel of Switchyard Isolate, 12) A unit startup transformer and associated yellow bus PCB (CT-1 / PCB 18, CT-2 / PCB 27, CT-3 / PCB 30), 13) Both E breakers. | : 38) Keowee auxiliary transformer 1X, Keowee ACB 5, Keowee 2X, Keowee ACB 6, Keowee Load Center 1X, Load Center 2X, 4A) Keowee MCC 1 XA, 48) Keowee MCC 2XA, SA) Keowee Battery #1, Charger SB) Keowee Battery #2, Charger #1 or Standby Charger, and #2 or Standby Charger, and Distribution Center 1 DA, Distribution Center 2DA, 6A) ACB-1 to ACB-3 interlock, 68) ACB-2 to ACB-4 interlock, 7 A) Keowee Unit 1 Voltage and 78) Keowee Unit 2 Voltage and Frequency out of tolerance Frequency out of tolerance (OOT) logic (OOT) logic 8) Keowee reservoir level~ 775 feet above sea level, BA) KPF-9 is OPEN with closing 88) KPF-10 is OPEN with closing spring discharged, spring discharged, Overhead Emergency Power Path 9) Keowee main step-up transformer, 10) PCB 9 (enabled by one channel of Switchyard Isolate Complete), 11) The 230kV switchyard yellow bus capable of being isolated by one channel of Switchyard Isolate, 12) A unit startup transformer and associated yellow bus PCB (CT-1 / PCB 18, CT-2 / PCB 27, CT-3 / PCB 30), 13) Both E breakers. | ||
OCONEE UNITS 1, 2, & 3 B 3.8.1-4 Rev.003 BASES AC Sources -Operating B 3.8.1 , ________________________________ | OCONEE UNITS 1, 2, & 3 B 3.8.1-4 Rev.003 BASES AC Sources -Operating B 3.8.1 , ________________________________ | ||
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The limits are automatically maintained by Keowee control systems. A nominal time of 60 seconds following the Emergency Start signal is sufficient time to begin monitoring steady state operation. | The limits are automatically maintained by Keowee control systems. A nominal time of 60 seconds following the Emergency Start signal is sufficient time to begin monitoring steady state operation. | ||
Since the only available loads of adequate magnitude for simulating an accident is the grid, subsequent loading on the grid is required to verify the KHU's ability to assume rapid loading under accident conditions. | Since the only available loads of adequate magnitude for simulating an accident is the grid, subsequent loading on the grid is required to verify the KHU's ability to assume rapid loading under accident conditions. | ||
Sequential block loads are not available to fully test this feature. This is the reason for the requirement to load the KHUs at the maximum practical rate. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.10 A battery service test is a special test of the battery capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length should correspond to the design duty cycle requirements as specified in Reference | Sequential block loads are not available to fully test this feature. This is the reason for the requirement to load the KHUs at the maximum practical rate. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.10 A battery service test is a special test of the battery capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length should correspond to the design duty cycle requirements as specified in Reference | ||
: 4. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. OCONEE UNITS 1, 2, & 3 B 3.8.1-23 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ---------------------------------- | : 4. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. OCONEE UNITS 1, 2, & 3 B 3.8.1-23 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ---------------------------------- | ||
SURVEILLANCE REQUIREMENTS (continued) | SURVEILLANCE REQUIREMENTS (continued) |
Revision as of 21:00, 25 April 2019
ML18060A080 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 02/22/2018 |
From: | Dunton C T Duke Energy Carolinas |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
ONS-2018-013 | |
Download: ML18060A080 (58) | |
Text
'1_~DUKE ElNERGY ONS-2018-013 February 22, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Numbers 50-269, 50-270, and 50-287 Technical Specification Bases Changes Carrie T. Dunton Director, Site Support Oconee Nuclear Station Duke Energy ON01VP / 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3477
- f. 864.873.4208 Carrie.dunton@duke-energy.com The attached changes to the Oconee Nuclear Station TS Bases were processed in accordance with the provisions of Technical Specification 5.5.15, "Technical Specifications (TS) Bases Control Program." Any questions regarding this information should be directed to Chris Wasik, Oconee Regulatory Affairs Manager, at (864) 873-5789.
- Sincerely, (a~~ Director, Site Support Oconee Nuclear Station Attachments www.duke-energy.com U. S. Nuclear Regulatory Commission February 22, 2018 Page 2 cc: Ms. Catherine Haney Administrator, Region II U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Cente_r Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Ms. Audrey Klett, Project Manager (ONS) (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-08B1A Rockville, MD 20852-2738 Mr. Eddy L. Crowe Senior Resident Inspector Oconee Nuclear Station ONS-2018-013 February 22, 2018 Attachments TSB List of Effective Pages (LOEPs), Rev. 018 TSIB Limiting Condition for Operation (LCO) Applicability, Rev. 001 TSB Spent Fuel Pool Boron Concentration, Rev. 002 TSl3 Dry Spent Fuel Storage Cask Loading and Unloading, Rev. 001 TSl3 AC Sources -Operating, Rev. 003 LOEP 1-4 TSB3.0 1-18 TSB3.7.12 1-3 TSB3.7.18 1-4 TSB 3.8.1 1 -26 www.duke-energy.com OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER IMPLEMENTATION DATE TOC 000 09/03/14 B 2.1.1 001 06/08/17 B 2.1.2 000 02/06/14 B 3.0 001 08/23/17 B 3.1.1 000 05/16/12 B 3.1.2 000 05/16/12 B 3.1.3 000 06/02/99 B 3.1.4 000 07/23/12 B 3.1.5 000 05/16/12 B 3.1.6 000 07/23/12 B 3.1.7 000 07/23/12 B 3.1.8 000 05/16/12 B 3.2.l 000 05/16/12 B 3.2.2 000 05/16/12 B 3.2.3 000 05/16/12 B 3.3.1 003 01/17/17 B 3.3.2 000 12/14/04 B 3.3.3 000 12/10/14 B 3.3.4 000 12/10/14 B 3.3.5 000 12/10/14 B 3.3.6 000 12/10/14 B 3.3.7 000 12/10/14 B 3.3.8 000 05/16/12 B 3.3.9 000 05/16/12 B 3.3.10 000 05/16/12 B 3.3.11 001 01/17/17 B 3.3.12 000 05/16/12 Oconee Nuclear Station LOEP I Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DATE B 3.3.13 000 05/16/12 B 3.3.14 001 01/17/17 B 3.3.15 000 05/16/12 B 3.3.16 000 05/16/12 B 3.3.17 000 05/16/12 B 3.3.18 000 05/16/12 B 3.3.19 000 05/16/12 B 3.3.20 000 05/16/12 B 3.3.21 000 05/16/12 B 3.3.22 000 05/16/12 B 3.3.23 000 05/16/12 B 3.3.24 000 09/26/01 B 3.3.25 000 11/05/03 B 3.3.26 000 11/05/03 B 3.3.27 000 12/10/14 B 3.3.28 000 05/16/12 B 3.4.1 000 05/16/12 B 3.4.2 000 12/16/98 B 3.4.3 001 01/17/17 B 3.4.4 001 07/14/16 B 3.4.5 000 05/16/12 B 3.4.6 001 04/18/17 lB 3.4.7 001 04/18/17 B 3.4.8 001 04/18/17 B 3.4.9 000 05/16/12 B3.4.10 001 09/21/15 B3.4.11 000 10/12/12 B 3.4.12 000 06/13/14 Oconee Nuclear Station LOEP2 Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DATE B3.4.13 001 01/17/17 B 3.4.14 001 09/21/15 B 3.4.15 001 11/24/15 B 3.4.16 001 08/23/16 B 3.5.1 000 05/16/12 B 3.5.2 003 04/18/17 B 3.5.3 003 04/18/17 B 3.5.4 000 05/16/12 B 3.6.1 001 01/17/17 B 3.6.2 001 01/17/17 B 3.6.3 000 05/16/12 B 3.6.4 000 05/16/12 B 3.6.5 002 04/18/17 B 3.7.1 002 01/17/17 B 3.7.2 000 11/13/12 B 3.7.3 001 09/21/15 B 3.7.4 002 01/17/17 B 3.7.5 001 09/21/15 B 3.7.6 000 05/16/12 B 3.7.7 000 12/10/14 B 3.7.8 000 05/16/12 B 3.7.9 000 08/28/14 B 3.7.10 003 01/17/17 lB 3.7.1 Oa 001 01/17/17 B 3.7.11 000 05/16/12 B 3.7.12 002 08/09/17 B 3.7.13 000 08/19/10 B 3.7.14 000 05/16/12 Oconee Nuclear Station LOEP3 Revision O 18 OCONEE NUCLEAR STATION TECHNICAL SPECIFICATIONS-BASES REVISED 01/03/2018 LIST OF EFFECTIVE PAGES SECTION/PAGES REVISION NUMBER BASES REVISION DA TE B 3.7.15 000 10/24/07 B 3.7.16 001 05/18/17 B 3.7.17 001 01/17/17 B 3.7.18 001 08/09/17 B 3.7.19 001 03/10/16 B 3.8.1 003 01/03/18 B 3.8.2 000 04/07/11 B 3.8.3 001 01/17/17 B 3.8.4 000 12/18/07 B 3.8.5 000 05/16/12 B 3.8.6 000 05/16/12 B 3.8.7 000 05/16/12 B 3.8.8 001 01/17/17 B 3.8.9 001 01/17/17 B 3.9.1 000 05/16/12 B 3.9.2 000 05/16/12 B 3.9.3 001 01/17/17 B 3.9.4 002 04/18/17 B 3.9.5 001 04/18/17 B 3.9.6 000 05/16/12 B 3.9.7 000 05/16/12 B 3.9.8 000 06/25/14 B 3.10.1 001 01/17/17 B 3.10.2 000 11/05/14 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation elates for revisions in effect prior to this change. Oconee Nuclear Station LOEP4 Revision O 18.
LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCOs LCO 3.0.1 LCO 3.0.2 LCO 3.0.1 through LCO 3.0.9 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated. LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Specification).
LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes ttiat: a. Completion of the Required Actions within .the specified Completion Times constitutes compliance with a Specification; and b. Completion of the Required Actions is not required when an LCO is met within the specified Completion Time, unless otherwise specified.
There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS.)
The second type of Required Action specifies the remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation.
OCONEE UNITS 1, 2, & 3 B 3.0-1 Rev.001 I BASES LCO 3.0.2 ( continued)
LCO 3.0.3 LCO Applicability 8 3.0 Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specification.
The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The individual LCO's ACTIONS specify the Required Actions where this is the case. An example of this is in LCO 3.4.3, "RCS Pressure and Temperature (PIT) Limits." The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally.
Reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems.
Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience.
Additionally, if intentional entry into ACTIONS would result in redundant equipment being inoperable, alternatives should be used instead. Doing so limits the time both subsystems/trains of a safety function are inoperable and limits the time conditions exist which may result in LCO 3.0.3 being entered. Individual Specifications may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed.
When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another Specification becomes applicable.
In this case, the Completion Times of the associated Required Actions would apply from the point in time that the new Specification becomes applicable and the ACTIONS Condition(s) are entered. LCO 3.0.3 establishes the actions that must be implemented when an LCO is not met and: a. An associated Required Action and Completion Time is not met and no other Condition applies; or b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly OCONEE UNITS 1, 2, & 3 8 3.0-2 Rev. 001 I BASES LCO 3.0.3 (continued)
LCO Applicability B 3.0 corresponds to the actual condition of the unit. Sometimes, possible combinations of Conditions are such that entering LCO 3.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that LCO 3.0.3 be entered immediately.
This Specification delineates the time limits for placing the unit in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the LCO and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.
Upon entering LCO 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in unit operation.
This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. If at the end of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, corrective measures which would allow exiting LCO 3.0.3 are not complete, but there is reasonable assurance that corrective measures will be completed in time to still allow for an orderly unit shutdown, commencing a load decrease may be delayed until that time. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is OPERABLE.
This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Specification applies. The use and interpretation of specified times to complete the actions of
- LCO 3.0.3 are consistent with the discussion of Section 1.3, Completion Times. A unit shutdown required in accordance with LCO 3.0.3 may be terminated and LCO 3.0.3 exited if any of the following occurs: a. The LCO is now met. b. A Condition exists for which the Required Actions have now been performed.
- c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time LCO 3.0.3 is exited. OCONEE UNITS 1, 2, & 3 B 3.0-3 Rev.001 I r ---BASES LCO 3.0.3 (continued)
LCO 3.0.4 LCO Applicability B 3.0 The time limits of LCO 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the unit to be in MODE 5 when a shutdown is required during MODE 1 operation.
If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE is reached in less time than allowed, however, the total allowable time to reach MODE 5, or other applicable MODE, is not reduced. For example, if MODE 3 is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowed for reaching MODE 4 is the next 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, because the total time for reaching MODE 4 is not reduced from the allowable limit of 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. Therefore, if remedial measures are completed that would permit a return to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed. In MODES 1, 2, 3, and 4, LCO 3.0.3 provides actions for Conditions not covered in other Specifications.
The requirements of LCO 3.0.3 do not apply in MODES 5 and 6 because the unit is already in the most restrictive Condition required by LCO 3.0.3. The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, 3, or 4) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken. Exceptions to LCO 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with LCO 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit. An example of this is in LCO 3.7.11, "Spent Fuel Pool Water Level." LCO 3.7.11 has an Applicability of "During movement of irradiated fuel assemblies in the spent fuel pool." Therefore, this LCO can be applicable in any or all MODES. If the LCO and the Required Actions of LCO 3.7.11 are not met while in MODE 1, 2, 3, or 4, there is no safety benefit to be gained by placing the unit in a shutdown condition.
The Required Action of LCO 3. 7.11 of "Suspend movement of irradiated fuel assemblies in spent fuel pool" is the appropriate Required Action to complete in lieu of the actions of LCO 3.0.3. These exceptions are addressed in the individual Specifications.
LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist: a. Unit conditions are such that the requirements of the LCO would not be met in the Applicability desired to be entered; and b. Continued noncompliance with the LCO requirements, if the Applicability were entered, would result in the unit being required to OCONEE UNITS 1, 2, & 3 B 3.0-4 Rev.001 I BASES LCO 3.0.4 (continued)
LCO Applicability B 3.0 exit the Applicability desired to be entered to comply with the Required Actions. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation.
This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.
Exceptions to LCO 3.0.4 are stated in the individual Specifications.
The exceptions allows entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time. Exceptions may apply to all the ACTIONS or to a specific Required Action of a Specification.
LCO 3.0.4 is only applicable when entering MODE 4 from MODE 5, MODE 3 from MODE 4, MODE 2 from MODE 3, or MODE 1 from MODE 2. Furthermore, LCO 3.0.4 is applicable when entering any other specified condition in the Applicability associated with operating in MODES 1, 2, 3, or 4. The requirements of LCO 3.0.4 do not apply in MODES 5 and 6, or in other specified conditions of the Applicability (unless in MODES 1, 2, 3, or 4) because the ACTIONS of individual Specifications sufficiently define the remedial mea*sures to be taken. Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, changing MODES or other specified conditions while in an ACTIONS Condition, in compliance with LCO 3.0.4 or where an exception to LCO 3.0.4 is stated, is not a violation of SR 3.0.1 or SR 3.0.4 for those Surveillances that do not have to be performed due to the associated inoperable equipment.
However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO. OCONEE UNITS 1, 2, & 3 B 3.0-5 Rev.001 I BASES (continued)
LCO 3.0.5 LCO 3.0.6 LCO Applicability B 3.0 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Required Action(s))
to allow the performance of required testing to demonstrate:
- a. The OPERABILITY of the equipment being returned to service; or b. The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY.
This Specification does not provide time to perform any other preventive or corrective maintenance.
An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with a Required Action, and must be reopened to perform the required testing. An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system. LCO 3.0.6 establishes an exception to LCO 3.0.2 for support systems that have an LCO specified in the Technical Specifications (TS). This exception is provided because LCO 3.0.2 would require that the Conditions and Required Actions of the associated inoperable supported system LCO be entered solely due to the inoperability of the support system. This exception is justified because the actions that are required to ensure the unit is maintained in a safe condition are specified in the support system LCO's Required Actions. These Required Actions may include entering the supported system's Conditions and Required Actions or may specify other Required Actions. When a support system is inoperable and there is an LCO specified for it in the TS, the supported system(s) are required to be OCONEE UNITS 1, 2, & 3 B 3.0-6 Rev.001 I BASES LCO 3.0.6 (continued)
LCO Applicability B 3.0 declared inoperable if determined to be inoperable as a result of the support system inoperability.
However, it is not necessary to enter into the supported systems' Conditions and Required Actions unless directed to do so by the support system's Required Actions. The potential confusion and inconsistency of requirements related to the entry into multiple support and supported systems' LCOs' Conditions and Required Actions are eliminated by providing all the actions that are necessary to ensure the unit is maintained in a safe condition in the support system's Required Actions. However, there are instances where a support system's Required Action may either direct a supported system to be declared inoperable or direct entry into Conditions and Required Actions for the supported system. This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's Required Action directs a supported system to be declared inoperable or directs entry in Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2. Specification 5.5.16, "Safety Function Determination Program (SFDP)," ensures loss of safety function is detected and appropriate actions are taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. The SFDP implements the requirements of LCO 3.0.6. Cross train checks to identify a loss of safety function for those support systems that support multiple and redundant safety systems are required.
The cross train check verifies that the supported systems of the remaining OPERABLE support systems are OPERABLE, thereby ensuring safety function is retained.
- a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or (EXAMPLE B3.06-1) b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or (EXAMPLE B3.06-2) c. A required system redundant to support system(s)for the supported systems (a) and (b) above is also inoperable. (EXAMPLE B3.06-3) OCONEE UNITS 1, 2, & 3 B 3.0-7 Rev. 001 I BASES LCO 3.0.6 (continued)
System 2 System 1 System 3 EXAMPLE 83.06-1 LCO Applicability B 3.0 If System 2 of Train A is inoperable, and System 5 of Train B is inoperable, a loss of safety function exists in supported System 5. EXAMPLE 83.06-2 If System 2 of Train A is inoperable, and System 11 of Train B is inoperable, a loss of safety function exists in System 11 which is in turn supported by System 5. EXAMPLE 83.06-3 If System 2 of Train A is inoperable, and System 1 of Train B is inoperable, a loss of safety function exists in Systems 2, 4, 5, 8, 9, 10 and 11. If this evaluation determines that a loss of safety function exists, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. EXAMPLES TRAINA TRAIN B ~~ma ~~ma System 4 System 4 System 9 System 9 System 2 ~~m10 ~~Wm10 System 5 System 5 System 11 System 11 System 1 ~~m12 ~~Wm12 System 6 System 6 System 13 System 13 System 3 ~~m14 ~ymm14 System 7 System 7 System 15 System 15 OCONEE UNITS 1, 2, & 3 B 3.0-8 Rev.001 I BASES (continued)
LCO 3.0.7 LCO 3.0.8 LCO Applicability B 3.0 There are certain special tests and operations required to be performed at various times over the life of the unit. These special tests and operations are necessary to demonstrate select unit performance characteristics, to perform special maintenance activities, and to perform special evolutions.
Test Exception LCO 3.1.8 allows specified Technical Specification (TS) requirements to be changed to permit performances of these special tests and operations, which otherwise could not be performed if required to comply with the requirements of these TS. Unless otherwise specified, all the other TS requirements remain unchanged.
This will ensure all appropriate requirements of the MODE or other specified condition not directly associated with or required to be changed to perform the special test or operation will remain in effect. The Applicability of a Test Exception LCO represents a condition not necessarily in compliance with the normal requirements of the TS. Compliance with Test Exception LCOs is optional.
A special operation may be performed either under the provisions of the appropriate Test Exception LCO or under the other applicable TS requirements.
If it is desired to perform the special operation under the provisions of the Test Exception LCO, the requirements of the Test Exception LCO shall be followed.
LCO 3.0.8 establishes conditions under which systems are considered to remain capable of performing their intended safety function when associated snubbers are not capable of providing their associated support function(s).
This LCO states that the supported system is not considered to be inoperable solely due to one or more snubbers not capable of performing their associated support function(s).
This is appropriate because a limited length of time is allowed for maintenance, testing, or repair of one or more snubbers not capable of performing their associated support function(s) and appropriate compensatory measures are specified in the snubber requirements, which are located outside of the Technical Specifications (TS) under licensee control. The snubber requirements do not meet the criteria in 10 CFR 50.36(c)(2)(ii), and, as such, are appropriate for control by the licensee.
If the allowed time expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's LCO(s) must be declared not met and the Conditions and Required Actions entered in accordance with LCO 3.0.2. LCO 3.0.8.a applies when one or more snubbers are not capable of providing their associated support function(s) to a single train of a multiple train or to a single train system. LCO 3.0.8.a allows 72 OCONEE UNITS 1, 2, & 3 B 3.0-9 Rev. 001 I BASES LCO 3.0.8 ( continued)
LCO 3.0.9 LCO Applicability B 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to restore the snubber(s) before declaring the supported system inoperable.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function and due to the availability of the redundant train of the supported system. LCO 3.0.8.b applies when one or more snubbers are not capable of providing their associated support function(s) to more than one train of a multiple train system. LCO 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the supported system inoperable.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function.
LCO 3.0.8 requires that risk be assessed and managed. Industry and NRC guidance on the implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of _LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train is properly controlled, and emergent issues are properly addressed.
The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.
LCO 3.0.9 establishes conditions under which systems described in the Technical Specifications are considered to remain OPERABLE when required barriers are not capable of providing their related support function (s). Barriers are doors, walls, floor plugs, curs, hatches, installed structures or components, or other devices, not explicitly described in Technical Specifications, that support the performance of the safety function of systems described in the Technical Specifications.
This LCO states that the supported system is not considered to be inoperable solely due to required barriers not capable of performing their related support function(s) under the described conditions.
LCO 3.0.9 allows 30 days before declaring the supported system(s) inoperable and the LCO(s) associated with the supported system(s) not met. A maximum time is placed on each use of this allowance to ensure that as required barriers are found or are otherwise made unavailable, they are restored.
However, the allowable duration may be less than the specified maximum time based on the risk assessment.
OCONEE UNITS 1, 2, & 3 B 3.0-10 Rev.001 I BASES LCO 3.0.9 ( continued)
LCO Applicability B 3.0 If the allowed time expires and the barriers are unable to perform their related support function(s), the supported system's LCO(s) must be declared not met and the Conditions and Required Actions entered in accordance with LCO 3.0.2. This provision does not apply to barriers which support ventilation systems or to fire barriers.
The Technical Specifications for ventilation systems provide specific Conditions for inoperable barriers.
Fire barriers are addressed by other regulatory requirements and associated plant programs.
This provision does not apply to barriers which are not required to support system OPERABILITY
.(see NRC Regulatory Issue Summary 200_1-09, "Control of Hazard (;3arriers," dated April 2, 2001. The provisions of LCO 3.0.9 are justified because of the low risk associated with required barriers not being capable of performing their related support function.
This provision is based on consideration of the following initiating event categories:
- Loss of coolant accidents,
- Feedwater line breaks,
- External flooding,
- Turbine missile ejection, and
- Tornado or high wind The risk impact of the barriers which cannot perform their related support function(s) must be addressed pursuant to the risk assessment and management provision of the Maintenance Rule, 10 CFR 50.65 (a)(4), and the associated implementation guidance, Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." Regulatory guide 1.160 endorses the guidance in Section 11 of NUMARC 93-01, Revision 4A, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." This guidance provides for the consideration of dynamic plant configuration issues, emergent conditions, and other aspects pertinent to plant operation with the barriers unable to perform their related support function(s).
These considerations may result in risk management and other compensatory actions being required during the period that barriers are unable to perform their related support function(s).
LCO 3.0.9 may be applied to one or more trains or subsystems of a system supported by barriers that cannot provide their related support function(s), provided that risk is assessed and managed (including consideration of the effects on Large Early Release and from external events). If applied concurrently to more than one train or subsystem of a multiple train or subsystem supported system, the barriers supporting OCONEE UNITS 1, 2, & 3 B 3.0-11 Rev.001 I BASES LCO 3.0.9 ( continued)
LCO Applicability B 3.0 each of these trains or subsystems must provide their related support function(s) for different categories of initiating events. For example, LCO 3.0.9 may be applied for up to 30 days for more than one train of a multiple train supported system if the affected barrier for one train protects against internal flooding and the affected barrier for the other train protects against tornado missiles.
In this example, the affected barrier may be the same physical barrier but serve different protection functions for each train. If during the time that LCO 3.0.9 is being used, the required OPERABLE train or subsystem becomes inoperable, it must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, the train(s) or subsystem(s) supported by barriers that cannot perform their related support function(s) must be declared inoperable and the associated LCOs declared not met. This 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period provides time to respond to emergent conditions that would otherwise likely lead to entry into LCO 3.0.3 and a rapid plant shutdown, which is not justified given the low probability of an initiating event which would require the barrier(s) not capable of performing their related support function(s).
During this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, the plant risk associated with the existing conditions is assessed and managed in accordance with 10 CFR 50.65(a)(4).
OCONEE UNITS 1, 2, & 3 B 3.0-12 Rev. 001 I SR Applicability B 3.0 B :3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated. SR. 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO. Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the SRs; or b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified.
The SRs associated with an Exception LCO are only applicable when the Exception LCO is used as an allowable exception to the requirements of a Specification.
Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR. In this case, the unplanned event may be credited as fulfilling the performance of the SR. This allowance includes those SRs whose performance is normally precluded in a given MODE or other specified condition.
Surveillances, including Surveillances invoked by Required Actions, do not have to be performed on inoperable equipment because the ACTIONS OCONEE UNITS 1, 2, & 3 B 3.0-13 Rev. 001 I BASES SR 3.0.1 (continued)
SR 3.0.2 SR Applicability B 3.0 define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status. Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE.
This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established.
In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function.
This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
Some example of this process are: a. Emergency feedwater (EFW) pump turbine maintenance during refueling that requires testing at steam pressures
> 300 psi. However, if other appropriate testing is satisfactorily completed, the EFW System can be considered OPERABLE.
This allows startup and other necessary testing to proceed while the plant reaches the steam pressure required to perform the EFW pump testing. b. High Pressure Injection (HPI) maintenance during shutdown that requires system functional tests at a specified pressure.
Provided other appropriate testing is satisfactorily completed, startup can proceed with HPI considered OPERABLE.
This allows operation to reach the specified pressure to complete the necessary post maintenance testing. SR3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per. .. " interval.
SR 3.0.2 permits a 25% extension of the interval specified in the Frequency.
This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).
OCONEE UNITS 1, 2, & 3 B 3.0-14 Rev.001 I BASES SR 3.0.2 (continued)
SR 3.0.3 SR Applicability B 3.0 The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency.
This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications.
The requirements of regulations take precedence over the TS. An example of where SR 3.0.2 does not apply is in the Containment Leakage Rate Testing Program. This program establishes testing requirements and Frequencies in accordance with the requirements of regulations.
The TS cannot in and of themselves extend a test interval specified in the regulations.
As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per ... "basis. The 25% extension applies to each performance after the initial performance.
The initial performance of the Required Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner. The provisions of SR 3.0.2 are not inte11ded to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.
SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency.
A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met. This delay period provides an adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.
OCONEE UNITS 1, 2, & 3 B 3.0-15 Rev. 001 I BASES SR 3.0.3 (continued)
SR Applicability B 3.0 The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.
When a Surveillance with a Frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading, or in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance.
However, since there is not a time interval specified, the missed Surveillance should be performed at the first reasonable opportunity.
SR 3.0.3 provides a time limit for, and allowances for the performance of, Surveillances that become applicable as a consequence of MODE changes imposed by Required Actions. Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence.
Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals.
While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified Frequency is provided to perform the missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity.
The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the Surveillance as well as any plant configuration changes required or shutting the plant down to perform the Surveillance) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the Surveillance.
This risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.182, 'Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants.' This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown.
The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide. The risk evaluation may use quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component.
OCONEE UNITS 1, 2, & 3 B 3.0-16 Rev. 001 I BASES SH 3.0.3 ( continued)
SR 3.0.4 SR Applicability B 3.0 Missed Surveillances for important components should be analyzed quantitatively.
If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed Surveillances will be placed in the licensee's Corrective Action Program. If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon the failure of the Surveillance.
Satisfactory completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1. SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.
This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and compqnents ensure safe operation of the unit. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
However, in certain circumstances, failure to meet an SR will not result in SR 3.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1, which states that surveillances do not have to be performed on inoperable equipment.
When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability.
However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. OCONEE UNITS 1, 2, & 3 B 3.0-17 Rev. 001 I BASES SR 3.0.4 (continued)
SR Applicability B 3.0 The provisions of SR 3.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.
The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary.
The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance.
A Surveillance that could not be performed until after entering the LCO Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.
SR 3.0.4 is only applicable when entering MODE 4 from MODE 5, MODE 3 from MODE 4, MODE 2 from MODE 3, or MODE 1 from MODE 2. Furthermore, SR 3.0.4 is applicable when entering any other specified condition in the Applicability associated with operation in MODES 1, 2, 3, or 4. The requirements of SR 3.0.4 do not apply in MODES 5 and 6, or in other specified conditions of the Applicability (unless in MODES 1, 2, 3, or 4) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken. OCONEE UNITS 1, 2, & 3 B 3.0-18 Rev. 001 I Spent Fuel Pool Boron Concentration B 3.7.12 B 3.7 PLANT SYSTEMS B 3.7.12 Spent Fuel Pool Boron Concentration BASES ================================
BACKGROUND Each Oconee spent fuel pool (SFP) contains racks for fuel assembly storage and a cask pit area for loading assemblies into a NUHOMS@ -24P/24PHB dry storage canister (DSC). Criticality analyses have been performed for both SFP rack storage and DSC loading/unloading operations, in accordance with the regulation (Ref. 1) and the guidance in References 2 and 3. The SFP and DSC criticality analyses each take credit for 430 ppm soluble boron during normal conditions, in order to achieve system keff 0.95. This partial soluble boron credit is included in TS 4.3.1 c. (SFP storage racks) and 4.4.1 c. (DSC). The SFP storage rack criticality analysis yields fuel assembly storage configuration requirements and associated minimum burnup values (as a function of initial U-235 enrichment), which are specified in LCO 3. 7.13. The DSC criticality evaluation establishes minimum burnup requirements for the loading of fuel assemblies into a NU HOMS@ -24P/24PHB DSC without location restrictions.
The DSC burnup requirements are provided in LCO 3.7.18. The minimum SFP boron concentration of 2220 ppm (per SR 3.7.12.1) allows sufficient time to detect and mitigate all credible boron dilution scenarios, well before the SFP boron concentration drops to 430 ppm. The minimum 2220 ppm boron is available for all accident conditions evaluated in the SFP rack and DSC criticality analyses, per the double contingency principle (Ref. 4 ). APPLICABLE Reference 3 discusses several criticality accident conditions that should SAFETY ANALYSES be considered in SFP storage rack criticality analyses.
Applicable accidents for the Oconee SFP storage racks include: 1) drop of a fuel assembly on top of the SFP storage rack; 2) drop of a fuel assembly outside of the storage rack modules; 3) abnormal SFP water temperatures outside the normal temperature range; 4) the misloading of a fuel assembly in a storage cell for which restrictions on location, enrichment, burnup, or post-irradiation cooling time are not satisfied; and 5) the drop of a heavy load (transfer cask) onto the SFP storage racks (NUREG-0612).
Of these SFP storage rack accidents, the heavy load. drop event requires the largest amount of soluble boron (almost 2200 ppm) to maintain SFP keff 0.95. OCONEE UNITS 1, 2, & 3 B 3.7.12-1 Rev.002 J BASES Spent Fuel Pool Boron Concentration B 3.7.12 APPLICABLE The accident scenarios (Ref. 3) that are valid for the loading/unloading SAH:TY ANALYSES of a NU HOMS@ -24P/24PHB DSC include:*
- 1) drop of a fuel assembly (continued) on top of the DSC storage cells; 2) drop of a fuel assembly immediately outside of the transfer cask containing the DSC; 3) abnormal SFP water temperatures beyond the normal temperature range; and 4) the misloading of a fresh 5.0 wt % U-235 fuel assembly in one of the DSC storage cells. Of these DSC accidents, the misload event requires the largest amount of soluble boron (630 ppm) to achieve a system kett 0.95. LCO APPLICABILITY ACTIONS Note that it is plausible to consider a loss of normal SFP cooling accident occurring in conjunction with a boron dilution event in the Oconee SFPs. In this unlikely scenario, with SFP water temperatures up to 212°F, the largest concentration of soluble boron required to maintain system kett 0.95 is 500 ppm (for the SFP storage racks). This amount of soluble boron is still much less than that remaining after the worst-case credible dilution event (825 ppm). Therefore, maintaining the SFP boron concentration 2220 ppm per SR 3. 7 .12.1 ensures that kett 0.95 for any accident conditions in the SFP storage rack or NUHOMS@ -24P/24PHB DSC. This minimum boron concentration limit includes allowance for analytical, mechanical, and instrument measurement uncertainties.
The concentration of dissolved boron in the SFP satisfies Criterion 2 of 10 CFR 50.36 (Ref. 5). The minimum concentration of dissolved boron in the SFP (2220 ppm) preserves the assumptions used in the analyses of the potential accident scenarios described above. The minimum boron concentration ensures that the system kettfor the SFP storage rack or the NUHOMS@ -24P/24PHB DSC will remain below 0.95 for all credible criticality accident scenarios and boron dilution events. This LCO applies whenever fuel assemblies are stored in the SFP storage racks, or whenever fuel assemblies are being loaded into a NU HOMS@ -24P/24PHB DSC in the SFP. This LCO applies only to spent fuel storage casks loaded under the ISFSI site-specific license. Site-specific storage casks are contained in Horizontal Storage Modules (HSMs) Nos. 1 through 40. A.1 and A.2 The Required Actions are modified by a Note indicating that LCO 3.0.3 does not apply. OCONEE UNITS 1, 2, & 3 B 3.7.12-2 Rev. 002 I BASES ACTIONS A.1 and A.2 (continued)
Spent Fuel Pool Boron Concentration 83.7.12 If moving irradiated fuel assemblies while in MODE 5 or 6, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation.
Therefore, inability to suspend movement of fuel assemblies is not a sufficient reason to require a reactor shutdown.
When the concentration of boron in the SFP is less than required, immediate action must be taken to preclude the occurrence of an accident or to mitigate the consequences' of an accident in progress.
This is achieved by immediately suspending the movement of the fuel assemblies.
This does not preclude movement of a fuel assembly to a safe position.
Immediate action is also required to initiate action to restore the SFP boron concentration to within limits. SURVEILLANCE SR 3.7.12.1 REQUIREMENTS REFERENCES This SR verifies that the concentration of boron in the SFP is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. The COLR revision process assures that the minimum boron concentration specified in the COLR bounds the limit specified by this SR. 1. 10 CFR 50.68(b).
- 2. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants," ANSI/ANS-57.2-1983, October 7, 1983. 3. Nuclear Regulatory Commission, Memorandum to Timothy Collins from Laurence Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants," August 19, 1998. 4. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A). 5. 10 CFR 50.36. OCONEE UNITS 1, 2, & 3 B 3.7.12-3, Rev. 002 I Dry Spent Fuel Cask Loading and Unloading 83.7.18 B 3. 7 PLANT SYSTEMS B 3.7.18 Dry Spent Fuel Storage Cask Loading and Unloading BASES ================================
BACKGROUND Fuel loading and unloading operations for the NUHOMS@-24P and NUHOMS@-24PHB dry storage canisters (DSCs) take place in the cask pit area of the spent fuel pool. The cask pit is adjacent to the spent fuel storage racks in each of the Oconee spent fuel pools, and is open to the rest of the spent fuel pool at all times. The NUHOMS@-24P and NUHOMS@-24PHB DSCs contain storage cells for 24 fuel assemblies.
Eligible B&W 15x15 fuel assemblies (Mk82-88, Mk89, and Mk810) with initial enrichments s 5.0 wt % U-235 may be stored in the NUHOMS@-24P or NUHOMS@-24PHB DSC, as long as the fuel assemblies meet the minimum burnup and cooling time requirements specified in Table 3.7.18-1.
For normal conditions in the spent fuel pool, the NUHOMS@-24P and NUHOMS@-24PHB DSCs have been analyzed using credit for soluble boron as allowed in Reference
- 1. This ensures that the system multiplication factor, kett, is~ 0.95 as recommended in ANSI/ANS-57.2-1983 (Ref. 2) and NRC guidance (Ref. 3). The DSC is analyzed to allow loading/unloading of eligible fuel assemblies while maintaining kett~ 0.95, including uncertainties, tolerances, biases, and credit for 430 ppm soluble boron. Note that the criticality analysis accounts for a maximum as-built enrichment tolerance of 0.05 wt % U-235. For example, for a specified maximum design enrichment of 5.00 wt % U-235, an as-built enrichment up to 5.05 weight percent is acceptable.
The 430 ppm soluble boron credit must provide sufficient subcritical margin to maintain the DSC kett 0.95. In addition, sub-criticality of the DSC (kett < 1.0) must be assured on a 95/95 basis, without the presence of any soluble boron in the spent fuel pool. The dual kett criteria identified in the above paragraph are satisfied for fuel assemblies meeting the minimum burnup and post-irradiation cooling time requirements specified in Table 3. 7.18-1. Reactivity reduction with cooling time is primarily attributable to Pu-241 decay and Gd-155 buildup (via Eu-155 decay). Specification 4.4.1 c. requires that the DSC kett be~ 0.95 when flooded with water borated to 430 ppm. A spent fuel pool boron dilution analysis has been performed that confirms that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 kett OCOI\IEE UNITS 1, 2, & 3 B 3.7.18-1 Rev. 001 BASES BACl<GROUND (continued)
Dry Spent Fuel Cask Loading and Unloading B 3.7.18 design basis is exceeded.
The spent fuel pool boron dilution analysis concluded that an unplanned or inadvertent event which could result in the dilution of the spent fuel pool boron concentration to 430 ppm is not a credible event.
- APPLICABLE Several accident conditions (Ref. 3) are considered that could result SAFETY ANALYSES in an increase in system kett for a DSC being loaded or unloaded in the spent fuel pool. These accident conditions include the drop of a fuel assembly on top of the DSC storage cells, the drop of a fuel assembly just outside the transfer cask 9ontaining the DSC, a higher than normal spent fuel pool water temperature, and the misleading of a fresh 5.0 wt % U-235 assembly in one of the DSC storage cells. For an occurrence of these postulated accidents, the double contingency principle discussed in ANSI N-16.1-1975 and the April 1978 NRC letter (Ref. 4) can be applied. This double contingency principle does not require assuming two unlikely, independent, concurrent events to ensure protection against a criticality accident.
Thus, for these postulated accident conditions, the presence of additional soluble boron in the spent fuel pool water (above the 430 ppm required to maintain kett 0.95 under normal DSC loading/unloading conditions) can be assumed as a realistic initial condition since not assuming its presence would be a second unlikely event. Calculations were performed to determine the amount of soluble boron required to offset the highest reactivity increase associated with these postulated accidents, in order to maintain kett .'.::. 0.95. It was found that a spent fuel pool boron concentration of 630 ppm was sufficient to maintain kett 0.95 for the worst-case postulated criticality-related accident (the fresh fuel assembly misloaded in a DSC storage cell). Specification
- 3. 7.12 ensures the spent fuel pool contains adequate dissolved boron to compensate for the increased reactivity caused by these postulated accidents.
For normal storage conditions, Specification 4.3.1 c. requires that the spent fuel rack kett be~ 0.95 when flooded with water borated to 430 ppm. A spent fuel pool boron dilution analysis was performed which confirmed that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 kett design basis is exceeded.
The spent fuel pool boron dilution analysis concluded that an unplanned or inadvertent event which could result in the dilution of the spent fuel pool boron concentration to 430 ppm is not a credible event. OCONEE UNITS 1, 2, & 3 B 3.7.18-2 Rev. 001 Dry Spent Fuel Cask Loading and Unloading . B 3.7.18 BASES APPLICABLE The configuration of fuel assemblies in the DSC and the concentration of SAFETY ANALYSIS dissolved boron in the spent fuel pool satisfy Criterion 2 of 10 CFR 50.36 (continued) (Ref. 5) LCO APPLICABILITY ACTIONS The keff of the dry spent fuel storage cask (NUHOMS@-24P or NUHOMS@-24PHB DSC), during loading and unloading operations in the spent fuel pool, will always remain _:s 0.95, assuming the spent fuel pool is flooded with water borated to at least 430 ppm, and that each loaded fuel assembly meets the initial enrichment, burnup, and post-irradiation cooling time of Table 3.7.18-1.
This LCO applies whenever any fuel assembly is in a dry spent fuel storage cask located in the spent fuel pool. This LCO applies only to spent fuel storage casks loaded under the ISFSI site-specific license. Site-specific storage casks are contained in Horizontal Storage Modules (HSMs) Nos. 1 through 40. Required Action A.1 is modified by a Note indicating that LCO 3.0.3 does not apply. If moving fuel assemblies while in MODE 5 or 6, LCO 3.0.3 would not specify any action. If moving fuel assemblies while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation.
Therefore, in either case, inability to move fuel assemblies is not sufficient reason to require a reactor shutdown.
When the configuration of fuel assemblies loaded in the NUHOMS@-24P or NUHOMS@-24PHB DSC is not in accordance with the LCO, immediate action must be taken to make the necessary fuel assembly movement(s) to bring the configuration into compliance with the LCO. SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment, burn up, and post-irradiation cooling time of the fuel assembly to be loaded into or removed from the NUHOMS@-24P or NUHOMS@-24PHB DSC is in accordance with Table 3.7.18-1.
OCONEE UNITS 1, 2, & 3 B 3.7.18-3 Rev. 001 BASES ( continued)
REFERENCES Dry Spent Fuel Cask Loading and Unloading 83.7.18 1. 10 CFR 50.68(b)(4)
- 2. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants," ANSI/ANS-57.2-1983, October 7, 1983. 3. Nuclear Regulatory Commission, Memorandum to Timothy Collins from Laurence Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants," August 19, 1998. 4. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A). 5. 10 CFR 50.36 OCONEE UNITS 1, 2, & 3 8 3.7.18-4 Rev. 001 AC Sources -Operating B 3.8.1 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.1 AC Sources -Operating BASES ==================================
BACKGROUND The AC Power System consists of the offsite power sources (preferred power) and the onsite standby power sources, Keowee Hydro Units (KHU). This system is designed to supply the required Engineered Safeguards (ES) loads of one unit and safe shutdown loads of the other two units and is so arranged that no single failure can disable enough loads to jeopardize plant safety. The design of the AC Power System provides independence and redundancy to ensure an available source of power to the ES systems (Ref. 1). The KHU turbine generators are powered through a common penstock by water taken from Lake Keowee. The use of a common penstock is justified on the basis of past hydro plant experience of the licensee (since 1919) which indicates that the cumulative need to dewater the penstock can be expected to be limited to about one day a year, principally for inspection, plus perhaps four days every tenth year. The preferred power source is provided from offsite power to the red or yellow bus in the 230 kV switchyard to the units startup transformer and the E breakers.
The 230 kV switchyard is electrically connected to the 525 kV switchyard via the autobank transformer.
Emergency power is provided using two emergency power paths, an overhead path and an underground path. The underground emergency power path is from one KHU through the underground feeder circuit, transformer CT-4, the CT-4 incoming breakers (SK breakers), standby bus and the standby breakers (S breakers).
The standby buses may also receive offsite power from the 100 kV transmission system through transformer CT-5 and the CT-5 incoming breakers (SL breakers).
The overhead emergency power path is from the other KHU through the startup transformer and the startup incoming breakers (E breakers).
In addition to supplying emergency power for Oconee, the KHUs provide peaking power to the generation system. During periods of commercial power generation, the KHUs are operated within the acceptable region of the KHU operating restrictions.
This ensures that the KHUs are able to perform their emergency power functions from an initial condition of commercial power generation.
The KHU operating restrictions for commercial power generation are contained in UFSAR Chapter 16, (Ref. 2). The standby buses can also OCONEE UNITS 1, 2, & 3 B 3.8.1-1 Rev. 003 I ( '
BASES BACKGROUND (continued)
APPLICABLE SAFETY ANALYSIS LCO AC Sources -Operating B 3.8.1 receive power from a combustion turbine generator at the Lee Steam Station through a dedicated 100 kV transmission line, transformer CT-5, and both SL breakers.
The 100 kV transmission line can be supplied from a Lee combustion turbine (LCT) and electrically separated from the system grid and offsite loads. The minimum capacity available from any of the multiple sources of AC power is 22.4MVA (limited by CT-4 and CT-5 transformer capacities).
The initial conditions of design basis transient and accident analyses in the UFSAR Chapter 6 (Ref. 4) and Chapter 15 (Ref. 5) assume ES systems are OPERABLE.
The AC power system is designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ES systems so that the fuel, reactor coolant system, and containment design limits are not exceeded.
Consistent with the accident analysis assumptions of a loss of offsite power (LOOP) and a single failure of one onsite emergency power path, two onsite emergency power sources are required to be OPERABLE.
AC Sources -Operating are part of the primary success path and function to mitigate an accident or transient that presents a challenge to the integrity of a fission product barrier. As such, AC Sources -Operating satisfies the requirements of Criterion 3 of 1 O CFR 50.36 (Ref. 3). Two sources on separate towers connected to the 230 kV switchyard to a unit startup transformer and one main feeder bus are required to be OPERABLE.
Two KHUs with one capable of automatically providing power through the underground emergency power path to both main feeder buses and the other capable of automatically providing power through the overhead emergency power path to both main feeder buses are required to be OPERABLE.
The Keowee Reservoir level is required to be~ 775 feet above sea level to support OPERABILITY of the KHUs. The zone overlap protection circuitry is required to be OPERABLE when the overhead electrical disconnects for the KHU associated with the underground power path are closed to provide single failure protection for the KHUs. The zone overlap protection circuitry includes the step-up transformer lockout, the underground KHU lockout, the Keowee emergency start signal, and the underground breaker for the overhead KHU to ensure the zone overlap protection circuitry logic is OPERABLE.
OCONEE UNITS 1, 2, & 3 B 3.8.1-2 Rev.003 BASES AC Sources -Operating B 3.8.1 ----------------------------------
LCO (continued)
Operable offsite sources are required to be "physically independent" (separate towers) prior to entering the 230 kV switchyard.
Once the 230 kV lines enter the switchyard, an electrical pathway must exist through OPERABLE power circuit breakers (PCBs) and disconnects such that both sources are available to energize the Unit's startup transformer either automatically or with operator action. Once within the boundary of the switchyard, the electrical pathway may be the same for both independent offsite sources. In addition, at least one E breaker must be available to automatically supply power to a main feeder bus from the energized startup transformer.
The voltage provided to the startup transformer by the two independent offsite sources must be sufficient to ensure ES equipment will operate. Two of the following offsite sources are required:
- 1) Jocassee (from Jocassee)
Black or White, 2) Dacus (from North Greenville)
Black or White, 3) Oconee (from Central) Black or White, 4) Calhoun (from Central) Black or White, 5) Autobank transformer fed from either the Asbury (from Newport), Norcross (from Georgia Power), or Katoma (from Jocassee) 525 kV line. An OPERABLE KHU and its required emergency power path are required to be able to provide sufficient power within specified limits of voltage and frequency within 23 seconds after an emergency start initiate signal and includes its required emergency power path, required instrumentation, controls, auxiliary and DC power, cooling and seal water, lubrication and other auxiliary equipment necessary to perform its safety function.
Two emergency power paths are available.
One emergency power path consists of an underground circuit while the other emergency power pathway uses an overhead circuit through the 230 kV switchyard.
OCONEE UNITS 1, 2, & 3 B 3.8.1-3 -Rev.003 I BASES ------------------------------------------, AC Sources -Operating B 3.8.1 ---------------------------------
LCO (continued)
An OPERABLE KHU and its required overhead emergency power path must be capable of automatically supplying power from the KHU through the KHU main step-up transformer, the 230 kV yellow bus, the Unit startup transformer and both E breakers to both main feeder buses. At least one channel of switchyard isolation (by actuation from degraded grid voltage protection) is required to be OPERABLE to isolate the 230 kV switchyard yellow bus. If closed, each N breaker must be capable of opening using either of its associated breaker trip circuits.
KPF-9 (for KHU1) and KPF-10 (for KHU2) must remain open since there is no engineering analysis that ensures that the associated KHU can power both PSW and Engineered Safeguards (ES) system loads should an event occur (with the breaker closed). Either of the following combinations provides an acceptable KHU and required overhead emergency power path: Keowee Hydro Unit Keowee Hydro Unit 1A) Keowee Unit 1 generator, 1 B) Keowee Unit 2 generator, 2A) Keowee ACB 1 (enabled by 28) Keowee ACB 2 (enabled by one channel of Switchyard one channel of Switchyard Isolate Complete), Isolate Complete), 3A) Keowee auxiliary transformer
- 38) Keowee auxiliary transformer 1X, Keowee ACB 5, Keowee 2X, Keowee ACB 6, Keowee Load Center 1X, Load Center 2X, 4A) Keowee MCC 1 XA, 48) Keowee MCC 2XA, SA) Keowee Battery #1, Charger SB) Keowee Battery #2, Charger #1 or Standby Charger, and #2 or Standby Charger, and Distribution Center 1 DA, Distribution Center 2DA, 6A) ACB-1 to ACB-3 interlock, 68) ACB-2 to ACB-4 interlock, 7 A) Keowee Unit 1 Voltage and 78) Keowee Unit 2 Voltage and Frequency out of tolerance Frequency out of tolerance (OOT) logic (OOT) logic 8) Keowee reservoir level~ 775 feet above sea level, BA) KPF-9 is OPEN with closing 88) KPF-10 is OPEN with closing spring discharged, spring discharged, Overhead Emergency Power Path 9) Keowee main step-up transformer, 10) PCB 9 (enabled by one channel of Switchyard Isolate Complete), 11) The 230kV switchyard yellow bus capable of being isolated by one channel of Switchyard Isolate, 12) A unit startup transformer and associated yellow bus PCB (CT-1 / PCB 18, CT-2 / PCB 27, CT-3 / PCB 30), 13) Both E breakers.
OCONEE UNITS 1, 2, & 3 B 3.8.1-4 Rev.003 BASES AC Sources -Operating B 3.8.1 , ________________________________
_ LCO (continued)
An OPERABLE KHU and its required underground emergency power path must be capable of automatically supplying power from the KHU through the underground feeder, transformer CT-4, both standby buses, and both Unit S breakers to both main feeder buses. If closed, each N breaker and each SL breaker must be capable of opening using either of its associated breaker trip circuits.
KPF-9 (for KHU1) and KPF-10 (for KHU2) must remain open since there is no engineering analysis that ensures that the associated KHU can power both PSW and Engineered Safeguards (ES) system loads should an event occur (with the breaker closed). Either of the following combinations provides an acceptable KHU and required underground emergency power path: Keowee Hydro Unit Keowee Hydro Unit 1A) Keowee Unit 1 generator, 1 B) Keowee Unit 2 generator, 2A) Keowee ACB 3, 28) Keowee ACB 4, 3A.1) Keowee auxiliary 3B.1) Keowee auxiliary transformer CX, Keowee transformer CX, Keowee ACB 7, Keowee Load ACB 8, Keowee Load Center 1 X, Center 2X, 3A.2) One Oconee Unit 1 S 38.2) One Oconee Unit 1 S breaker capable of breaker capable of feeding switchgear 1 TC, feeding switchgear 1 TC, 3A.3) Switchgear 1TC capable 3B.3) Switchgear 1TC capable of feeding Keowee of feeding Keowee auxiliary transformer CX, auxiliary transformer CX, 4A) Keowee MCC 1 XA, 48) Keowee MCC 2XA, SA) Keowee Battery #1, 58) Keowee Battery #2, Charger #1 or Standby Charger #2 or Standby Charger, and Distribution Charger, and Distribution Center 1 DA, Center 2DA, 6A) ACB-1 to ACB-3 interlock, 68) ACB-2 to ACB-4 interlock, 7 A) Keowee Unit 1 Voltage 78) Keowee Unit 2 Voltage and Frequency OOT logic and Frequency OOT logic 8) Keowee reservoir level~ 775 feet above sea level, SA) KPF-9 is OPEN with closing 88) KPF-10 is OPEN with closing spring discharged, spring discharged, Underground Emergency Power Path 9) The underground feeder, 10) Transformer CT-4, 11) Both SK breakers, 12) Both standby buses, 13) Both S breakers, and 14) ACB-3 to ACB-4 interlock.
OCONEE UNITS 1, 2, & 3 B 3.8.1-5 Rev. 003 BASES LCO (continued)
APPLICABILITY ACTIONS AC Sources -Operating B 3.8.1 This LCO is modified by three Notes. Note 1 indicates that a unit startup transformer may be shared with a unit in MODES 5 and 6. Note 2 indicates that the requirements of Specification 5.5.18, "KHU Commercial Power Generation Testing Program," shall be met for commercial KHU power generation.
Note 3 indicates that the requirements of Specification 5.5.19, "Lee Combustion Turbine Testing Program," shall be met when a Lee Combustion Turbine (LCT) is used to comply with Required Actions. The AC power sources are required to be OPERABLE in MODES 1, 2, 3, and 4 to ensure that: a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of accidents and transients, and b. Adequate core cooling is provided, and containment OPERABILITY and other vital functions are maintained in the event of a postulated accident.
AC source requirements during MODE 5 and 6 are covered in LCO 3.8.2, AC Sources-Shutdown.
The ACTIONS are modified by a Note. The Note excludes the MODE change restriction of LCO 3.0.4 when both standby buses are energized from an LCT via an isolated power path to comply with Required Actions. This exception allow entry into an applicable MODE while relying on the ACTIONS even though the ACTIONS may eventually require a unit shutdown.
This exception is acceptable due to the additional capabilities afforded when both standby buses are energized from an LCT via an isolated power path.
- A.1, A.2, A.3.1, and A.3.2 In the event a startup transformer becomes inoperable, it effectively causes the emergency overhead power path and both of the offsite sources to be inoperable.
A KHU and its required underground power path remain available to ensure safe shutdown of the unit in the event of a transient or accident without a single failure. OCONEE UNITS 1, 2, & 3 B 3.8.1-6 Rev. 003 BASES ACTIONS A.1, A.2, A.3.1, and A.3.2 (continued)
AC Sources -Operating B 3.8.1 Operation niay continue provided the KHU and its required underground emergency power path are tested using SR 3.8.1.3 within one hour if not performed in the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This Required Action provides assurance that no undetected failures have occurred in the KHU and its required underground emergency power path. Since Required Action A.1 only specifies "perform," a failure of SR 3.8.1.3 acceptance criteria does not result in a Required Action not met. However, if the KHU and its required underground emergency path fails SR 3.8.1.3, both emergency power paths and both required offsite circuits are inoperable, and Condition I for both KHUs and their required emergency power paths inoperable for reasons other than Condition G and H is entered concurrent with Condition A. If available, another Unit's startup transformer should be aligned to supply power to the affected Unit's auxiliaries so that offsite power sources and the KHU and its required overhead emergency power path will also be available if needed. Although this alignment restores the availability of the offsite sources and the KHU and its required overhead emergency power path, the shared startup transformer's capacity and voltage adequacy could be challenged under certain OBA conditions.
The shared alignment is acceptable because the preferred mode of Unit shutdown is with reactor coolant pumps providing forced circulation and due to the low likelihood of an event challenging the capacity of the shared transformer during a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period to bring a Unit to MODE 5. Required Action A.3.1 requires that the unit startup transformer be restored to OPERABLE status and normal startup bus alignment in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or Required Action 3.2 requires designating one unit sharing the startup transformer, to be shutdown.
For example, if Unit 1 and 2 are operating and CT-2 becomes inoperable, Unit 2 may align CT-1 to be available to the Unit 2 main feeder buses and continue operating for up to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. At that time, if CT-2 has not been restored to OPERABLE status, one Unit must be "designated" to be shutdown.
The designated Unit must be shut down per ACTION B. Note that with one Unit in MODES 1, 2, 3 or 4 and another Unit in a condition other than MODES 1, 2, 3, or 4, the units may share a startup transformer indefinitely provided that the loads on the unit not in MODES 1, 2, 3 or 4 are maintained within acceptable limits. For example, if Unit 1 is in MODE 5 and CT-2 becomes inoperable, Unit 2 may align CT-1 to the Unit 2 main feeder buses and continue operation indefinitely.
OCONEE UNITS 1, 2, & 3 B 3.8.1-7 Rev. 003 I BASES AC Sources -Operating B 3.8.1 , _________________________________
_ ACTIONS (continued)
B.1 and B.2 When a unit is designated to be shutdown due to sharing a unit startup transformer per Required Action A.3.2, the unit must be brought to a MODE in which the LCO does not apply, since the shared unit startup transformer's capacity could be challenged under certain DBA conditions.
To achieve this status, the unit must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 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. C.1, C.2.1, C.2.2.1, C.2.2.2, C.2.2.3, C.2.2.4, and C.2.2.5 With the KHU or its required overhead emergency power path inoperable due to reasons other than an inoperable startup transformer (Condition A), sufficient AC power sources remain available to ensure safe shutdown of the unit in the event of a transient or accident.
Operation may continue if the OPERABILITY of the remaining KHU and its required underground emergency power path is determined by performing SR 3.8.1.3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if not performed in the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and once every 7 days thereafter.
This demonstration assures the remaining emergency power path is not inoperable due to a common cause or other failure. Testing on a 7 day Frequency is acceptable since both standby buses must be energized from an LCT via an isolated power path when in Condition C for > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. When the standby buses are energized by an LCT via an isolated power path, the likelihood that the OPERABLE KHU and its required underground emergency power path will be required is decreased.
Since Required Action C.1 only specifies "perform," a failure of SR 3.8.1.3 acceptance criteria does not result in a Required Action not met. SR 3.8.1.3 is only required to be performed when the KHU associated with the underground emergency power path is OPERABLE.
If the KHU and its required underground emergency path fails SR 3.8.1.3, both KHUs and their required emergency power paths are inoperable, and Condition I (Both KHUs or their required emergency power paths inoperable for reasons other than Condition G or H) is entered concurrent with Condition C. OCONEE UNITS 1, 2, & 3 B 3.8.1-8 Rev. 003 I BASES ACTIONS AC Sources -Operating B 3.8.1 C.1, C.2.1, C.2.2.1, C.2.2.2, C.2.2.3, C.2.2.4, and C.2.2.5 (continued)
If the inoperable KHU or its required overhead emergency power path are not restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as required by Required Action C.2.1, a controlled shutdown must be initiated as required by the Required Actions for Condition M unless the extended Completion Times of Required Action C.2.2.5 are applicable.
The second Completion Time for Required Action C.2.1 establishes a limit on the maximum time allowed for a KHU to be inoperable during any single contiguous occurrence of having a KHU inoperable.
If Condition C is entered as a result of switching an inoperable KHU from the underground to the overhead emergency power path, it may have been inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This could lead to a total of 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> since the initial failure of the KHU. The second Completion Time allows for an exception to the normal "time zero" for beginning the allowed time "clock." This will result in establishing the "time zero" at the time the KHU become inoperable, instead of at the time Condition C was entered. The extended Completion Times of Required Action C.2.2.5 apply when the KHU or its required overhead emergency power path is inoperable due to an inoperable Keowee main step-up transformer, an inoperable KHU (if not used for that KHU in the previous 3 years), or a KHU made inoperable to perform generator stator replacement work. In order to use the extended Completion Times, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of entering Condition C both standby buses must be energized from an LCT (Required Action C.2.2.1 ), KHU generation to the grid except for testing must be suspended (Required Action C.2.2.2), the remaining KHU and its required underground emergency power path and both required offsite sources must be verified OPERABLE, the LCOs indicated in Required Action C.2.2.3 must be verified to be met, and alternate power source capability must be verified by performing SR 3.8.1.16.
Required Action C.2.2.5 permits maintenance and repair of a Keowee main step-up transformer which requires longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Transformer replacement is rare but is time extensive.
A 28 day Completion Time is permitted by Required Action C.2.2.5 to restore the KHU and its overhead power path to OPERABLE status when inoperable due to an inoperable Keowee main step-up transformer.
This allows a reasonable period of time for transformer replacement.
Required Action C:2.2.5 also permits maintenance and repair of a KHU which requires longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The primary long term maintenance items are expected to be hydro turbine runner and discharge ring welding OCONEE UNITS 1, 2, & 3 B 3.8.1-9 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
ACTIONS C.1, C.2.1, C.2.2.1, C.2.2.2, C.2.2.3, C.2.2.4, and C.2.2.5 (continued) repairs which are estimated to be necessary every six to eight years. Also, generator thrust and guide bearing replacements are necessary.
Other items which manifest as failures are expected to be rare and may be performed during the permitted maintenance periods. The 45-day Completion Time of Required Action C.2.2.5 is allowed to be applied cumulatively over a rolling three year period for each KHU. This Completion Time is 45 days from discovery of initial inoperability of the KHU. This effectively limits the time the KHU can be inoperable to 45 days from discovery of initial inoperability rather than 45 days from entry into Condition C and precludes any additional time that may be gained as a result of switching an inoperable KHU from the underground to the overhead emergency power path. The Completion Time is modified by three notes. Note 1 indicates that the Completion Time is cumulative per a rolling 3-year time period for each KHU. For example, if KHU-1 is inoperable for 15 days, the 45-day Completion Time for KHU-1 is reduced to 30 days for the rolling 3-year time period containing the 15 day inoperability.
This requires a review of entries for the previous 3 years to determine the remaining time allowed in the 45-day Completion Time. If the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time of C.2.1 is not exceeded, the 45-day Completion is not applicable and is not reduced. Notes 2 and 3 indicate the Completion Time is not applicable during generator stator replacement work or until one year after the KHU is declared OPERABLE following generator stator replacement work. Note 2 is added to avoid using up the 45-day Completion Time concurrent with the 55-day Completion Time and preserves some time to perform emergent maintenance work should the need arise. Note 3 is added to require a one year waiting period prior to use for planned work. The temporary 55-day Completion Time of Required Action C.2.2.5 is allowed for each KHU to perform generator stator replacement work. The 55-day Completion Time is modified by three notes that provide conditions for using the extended outage. Note 1 indicates that no discretionary maintenance or testing is allowed on the Standby Shutdown Facility (SSF), Protected Service Water (PSW), Emergency Feedwater (EFW), and essential alternating current (AC) Power Systems. Note 2 indicates that the 55-day Completion Time is only applicable one time for each KHU due to generator stator replacement work and expires on September 30, 2021: Note 3 indicates that it is only applicable if the SSF, PSW and EFW are administratively verified OPERABLE prior to entering the extended Completion Time. This increases the probability, even in the unlikely event of an additional failure, that the risk significant systems will function as required to support their safety function.
Required Actions C.2.2.1, C.2.2.2, C.2.2.3, and C.2.2.4 must be met in order to allow the longer restoration times of Required Action C.2.2.5. OCONEE UNITS 1, 2, & 3 B 3.8.1-10 Rev.003 BASES AC Sources -Operating B 3.8.1 ----------------------------------
ACTIONS C.1, C.2.1, C.2.2.1, C.2.2.2, C.2.2.3, C.2.2.4, and C.2.2.5 (continued)
Required Action C.2.2.1 requires that both standby buses be energized using an LCT through the 100 kV transmission circuit. With this arrangement (100 kV transmission circuit electrically separated from the system grid and all offsite loads), a high degree of reliability for the emergency power system is provided.
In this configuration, the LCT is serving as a second emergency power source, however, since the 100 kV transmission circuit is vulnerable to severe weather a time limit is imposed. The second Completion Time of Required Action C.2.2.1 permits the standby buses to be re-energized by an LCT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event this source is subsequently lost. Required Action C.2.2.2 requires suspension of KHU generation to the grid except for testing. The restriction reduces the number of possible failures which could cause loss of the underground emergency power path. Required Action C.2.2.3 requires verifying by administrative means that the remaining KHU and its required underground emergency power path and both required offsite sources are OPERABLE.
This provides additional assurance that offsite power will be available.
In addition, this assures that the KHU and its required underground emergency power path are available.
Required Action C.2.2.3 also requires verifying by administrative means that the requirements of the following LCOs are met: LCO 3.8.3, "DC Sources -Operating;" LCO 3.8.6, "Vital Inverters
-Operating;" LCO 3.8.8, "Distribution Systems -Operating;" LCO 3.3.17, "EPSL Automatic Transfer Function;" LCO 3.3.18, "EPSL Voltage Sensing Circuits;" LCO 3.3.19, "EPSL 230 kV Switchyard DGVP;" and LCO 3.3.21, "EPSL Keowee Emergency Start Function." This increases the probability, even in the unlikely event of an additional failure, that the DC power system and the 120 VAC Vital Instrumentation power panelboards will function as required to support EPSL, power will not be lost to ES equipment, and EPSL will function as required.
OCONEE UNITS 1, 2, & 3 B 3.8.1-11 Rev.003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
ACTIONS C.1, C.2.1, C.2.2.1, C.2.2.2, C.2.2.3, C.2.2.4, and C.2.2.5 (continued)
Verifying by administrative means allows a check of logs or other information to determine the OPERABILITY status of required equipment in place of requiring unique performance of Surveillance Requirements.
If the AC Source is subsequently determined inoperable, or an LCO stated in Required Action C.2.2.3 is subsequently determined not met, continued operation up to a maximum of four hours is allowed by ACTION L. Required Action C.2.2.3 is modified by a note indicating that it is not applicable to the remaining KHU and its required underground emergency power path or LCO 3.3.21 when in Condition H to perform generator stator replacement work. This note is needed to allow entry into the 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> dual unit outage to reassemble the refurbished KHU and return it to functional condition, as well as perform balance runs and shots, post modification testing, and a commissioning run prior to declaring the refurbished KHU operable.
Without this note, entry into Condition L would be required allowing only 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> to restore the KHU and its required underground path and only 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore compliance with LCO 3.3.21. Required Action C.2.2.4 requires verifying alternate power source capability by performing SR 3.8.1.16.
This confirms that entry into Condition C is due only to an inoperable main step-up transformer or an inoperable KHU, as applicable.
If SR 3.8.1.16 is subsequently determined not m1;:it, continued operation up to a maximum of four hours is allowed by ACTION L. D.1, D.2 and D.3 With the KHU or its required underground emergency power path inoperable, sufficient AC power sources remain available to ensure safe shutdown of the unit in the event of a transient or accident.
Operation may continue for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the remaining KHU and its required overhead emergency power path are tested using SR 3.8.1.4 within one hour if not performed in the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. SR 3.8.1.4 is only required to be performed when the KHU associated with the overhead emergency power path is OPERABLE.
This Required Action provides assurance that no undetected failures have occurred in the overhead emergency power path. Since Required Action D.1 only specifies "perform," a failure of SR 3.8.1.4 acceptance criteria does not result in a Required Action not met. However, if the KHU and its required overhead emergency path fails SR 3.8.1.4, both KHUs and their required emergency power paths are inoperable, and Condition I for both KHUs and their emergency power paths inoperable for reasons other than Condition G or H is entered concurrent with Condition D. This OCONEE UNITS 1, 2, & 3 B 3.8.1-12 Rev.003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
ACTIONS D.1, D.2 and D.3 (continued) demonstration is to assure that the remaining emergency power path is not inoperable due to a common cause or due to an undetected failure. For outages of the KHU and its required underground emergency power path in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an LCT (using the 100 kV transmission circuit electrically separated from the grid and offsite loads) must energize a standby bus prior to the outage exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This ensures the availability of a power source on the standby buses when the KHU and its required underground emergency power path are out of service in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The second Completion Time of Required Action D.2 permits the standby buses to be re-energized by an LCT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event this source is subsequently lost. The second Completion Time for Required Action D.3 establishes a limit on the maximum time allowed for a KHU to be inoperable during any single contiguous occurrence of having a KHU inoperable.
If Condition D is entered as a result of switching an inoperable KHU from the overhead to the underground emergency power path, it may have been inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This could lead to a total of 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> since the initial failure of the KHU. The second Completion Time allows for an exception to the normal "time zero" for beginning the allowed time "clock." This will result in establishing the "time zero" at the time the KHU become inoperable, instead of at the time Condition D was entered. E.1 and E.2 If the Required Action and associated Completion Time for Required Action D.2 are not met, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for one Oconee unit and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for other Oconee unit(s) and to MODE 5 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 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 plant systems. F.1 and F.2 With the zone overlap protection circuitry inoperable when the overhead electrical disconnects for the.KHU associated with the underground power path are closed, the zone overlap protection circuitry must be restored to OPERABLE status or the overhead electrical disconnects must be opened within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this Condition, both KHUs and their required emergency power paths are OPERABLE, however a single failure could result in the loss of both KHUs. OCONEE UNITS 1, 2, & 3 B 3.8.1-13 Rev. 003 I BASES AC Sources -Operating B 3.8.1 *----------------------------------
ACTIONS (continued)
With both emergency power paths inoperable due to an E breaker and S breaker inoperable on the same main feeder bus, one breaker must be restored to OPERABLE status. In this Condition, both emergency power paths can still provide power to the remaining main feeder bus. H.1 and H.2 With both KHUs or their required emergency power paths inoperable for planned maintenance or test with both standby buses energized from an LCT via an isolated power path, the KHU must be restored to OPERABLE status within 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />. Operation with both KHUs and their required power paths inoperable is permitted for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> provided that both standby buses are energized using an LCT through the 100 kV transmission circuit and the requirements of the Note to the Condition are met. The Note to the Condition indicates that it may only be entered when both offsite sources are verified by administrative means to be OPERABLE and the requirements of the following LCOs are verified by administrative means to be met: LCO 3.8.3, "DC Sources -Operating;" LCO 3.8.6, "Vital Inverters
-Operating;" LCO 3.8.8, "Distribution Systems -Operating;" LCO 3.3.17, "EPSL Automatic Transfer Function;" LCO 3.3.18, "EPSL Voltage Sensing Circuits;" and LCO 3.3.19, "EPSL 230 kV Switchyard DGVP." This increases the probability, even in the unlikely event of an additional . failure, that the DC power system and the 120 VAC Vital Instrumentation power panelboards will function as required to support EPSL, power will not be lost to ES equipment, and EPSL will function as required.
OCONEE UNITS 1, 2, & 3 B 3.8.1-14 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
ACTIONS H.1 and H.2 (continued)
Verifying by administrative means allows a check of logs or other information to determine the OPERABILITY status of required equipment in place of requiring unique performance of Surveillance Requirements.
If the AC Source is subsequently determined inoperable, or an LCO stated in the Note to Condition H is subsequently determined not met, continued operation up to a maximum of four hours is allowed by ACTION L. With both standby buses energized from an LCT via an isolated power path (100 kV transmission circuit electrically separated from the system grid and all offsite loads), a high degree of reliability for the emergency power system is provided.
In this configuration, the LCT is serving as the Oconee emergency power source, however, since the Oconee Units are vulnerable to a single failure of the 100 kV transmission circuit a time limit of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> is imposed. Required Action H.1 permits the standby buses to be re-energized by an LCT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event this source is subsequently lost. The second Completion Time of Required Action H.2 limits the amount of time two KHUs can be inoperable during the 45-day Completion Time of Required Action C.2.2.5 to a cumulative 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> over a rolling 3-year period. This requires a review of entries for the previous 3 years to determine the remaining time allowed in the 240-hour Completion Time. This limits the dual KHU outage time when using the 45-day Completion Time of Required Action C.2.2.5 on a cumulative basis over a 3-year time period. If both emergency power paths are restored, unrestricted operation may continue.
If only one power path is restored, operation may continue per ACTIONS C or D. 1.1, 1.2, and 1.3 With both KHUs or their required emergency power paths inoperable for reasons other than Conditions G and H, insufficient standby AC power sources are available to supply the minimum required ES functions.
In this Condition, the offsite power system is the only source of AC power available for this level of degradation.
The risk associated with continued operation for one hour without an emergency power source is considered acceptable due to the low likelihood of a LOOP during this time period, and because of the potential for grid instability caused by the simultaneous shutdown of all three units. This instability would increase the probability of a total loss of AC power. Operation with both KHUs or their required power paths inoperable is permitted for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> provided that Required Actions 1.1 and 1.2 are met. Required Action 1.1 requires that both standby buses be energized using an LCT via an isolated power OCONEE UNITS 1, 2, & 3 B3.8.1-15 Rev.003 BASES AC Sources -Operating B 3.8.1 ----------------------------------
ACTIONS 1.1, 1.2, and 1.3 (continued) path. With this arrangement (100 kV transmission circuit electrically separated from the system grid and all offsite loads), a high degree of reliability for the emergency power system is provided.
In this configuration, the LCT is serving as the Oconee emergency power source, however, since the Oconee Units are vulnerable to a single failure of the 100 kV transmission circuit a time limit of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is imposed. The second Completion Time of Required Action 1.1 permits the standby buses to be re-energized by an LCT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event this source is subsequently lost. Required Action 1.2 requires that the OPERABILITY status of both offsite sources be determined by administrative means and that the OPERABILITY status of equipment required by the following LCOs be determined by administrative means: LCO 3.8.3, "DC Sources -Operating;" LCO 3.8.6, "Vital Inverters
-Operating;" LCO 3.8.8, "Distribution Systems -Operating;" LCO 3.3.17, "EPSL Automatic Transfer Function;" LCO 3.3.18, "EPSL Voltage Sensing Circuits;" and LCO 3.3.19, "EPSL 230 kV Switchyard DGVP." This increases the probability, even in the unlikely event of an additional failure, that the DC power system and the 120 VAC Vital Instrumentation power panelboards will function as required to support EPSL, power will not be lost to ES equipment, and EPSL will function as required.
Determining by administrative means allows a check of logs or other information to determine the OPERABILITY status of required equipment in place of requiring unique performance of Surveillance Requirements.
If the AC Source is initially or subsequently determined inoperable, or an LCO stated in Required Action 1.2 is initially or subsequently determined not met, continued operation up to a maximum of four hours is allowed by ACTION L. If both emergency power paths are restored, unrestricted operation may continue.
If only one power path is restored, operation may continue per ACTIONS C or D. OCONEE UNITS 1, 2, & 3 B 3.8.1-16 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ---------------------------------
ACTIONS (continued)
J.1, J.2, and J.3 With one or both required offsite sources inoperable for reasons other than Condition A, sufficient AC power sources are available to supply necessary loads in the event of a OBA. However, since the AC power system is degraded below the Technical Specification requirements, a time limit on continued operation is imposed. With only one of the required offsite sources OPERABLE, the likelihood of a LOOP is increased such that the Required Actions for all required offsite circuits inoperable are conservatively followed.
The risk associated with continued operation for one hour without a required offsite AC source is considered acceptable due to the low likelihood of a LOOP during this time period, and because of the potential for grid instability caused by the simultaneous shutdown of all three units. Operation with one or both required offsite sources inoperable is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided that Required Actions J.1 and J.2 are met. Required Action J.1 requires that both standby buses be energized using an LCT via an isolated power path. With this arrangement (100 kV transmission circuit electrically separated from the system grid and all offsite loads), a high degree of reliability for the emergency power system is provided.
In this configuration, the LCT is serving as an emergency power source, however, since the Oconee units are vulnerable to a single failure of the 100 kV transmission circuit a time limit is imposed. The second Completion Time of Required Action J.1 permits the standby buses to be re-energlzed by an LCT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event this source is subsequently lost. Required Action J.2 requires that the OPERABILITY status of both KHUs and their required emergency power paths be determined by administrative means and that the OPERABILITY status of equipment required by the following LCOs be determined by administrative means: LCO 3.8.3, "DC Sources -Operating;" LCO 3.8.6, "Vital Inverters
-Operating;" LCO 3.8.8, "Distribution Systems -Operating;" LCO 3.3.17, "EPSL Automatic Transfer Function;" LCO 3.3.18, "EPSL Voltage Sensing Circuits;" LCO 3.3.19, "EPSL 230 kV Switchyard DGVP," and LCO 3.3.21, "EPSL Keowee Emergency Start Function." OCONEE UNITS 1, 2, & 3 B 3.8.1-17 Rev. 003 I r -BASES ACTIONS J.1, J.2, and J.3 (continued)
AC Sources -Operating B 3.8.1 This increases the probability, even in the unlikely event of an additional failure, that the DC power system and the 120 VAC Vital Instrumentation power panelboards will function as required to support EPSL, power will not be lost to ES equipment, and EPSL will function as required.
Determining by administrative means allows a check of logs or other information to determine the OPERABILITY status of required equipment in place of requiring unique performance of Surveillance Requirements.
If the AC Source is initially or subsequently determined inoperable, or an LCO stated in Required Action J.2 is initially or subsequently determined not met, continued operation up to a maximum of four hours is allowed by ACTION L. The two trip circuits for each closed N and SL breakers are required to ensure both breakers will open. An N breaker trip circuit encompasses those portions of the breaker control circuits necessary to trip the associated N breaker from the output of the 2 out of 3 logic matrix formed by the auxiliary transformer's undervoltage sensing circuits up to and including an individual trip coil for the associated N breaker. The undervoltage sensing channels for the auxiliary transformer are addressed in LCO 3.3.18, "Emergency Power Switching Logic (EPSL) Voltage Sensing Circuits." An SL breaker trip circuit encompasses those portions of the breaker control circuits necessary to trip the SL breaker from the output of both 2 out of 3 logic matrices formed by each standby bus's undervoltage sensing circuits up to and including an individual trip coil for the associated SL breaker. The undervoltage sensing channels for the CT-5 transformer are addressed in LCO 3.3.18, "Emergency Power Switching Logic (EPSL) Voltage Sensing Circuits." With one trip circuit inoperable a single failure could cause an N or SL breaker to not open. This could prevent the transfer to other available sources. Therefore, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to repair the trip circuit or open the breaker (opening the breaker results in exiting the Condition).
The Completion Time is based on engineering judgement taking into consideration the time required to complete the required action and the availability of the remaining trip circuit. A Note modifies the Condition, indicating that separate Condition Entry is permitted for each breaker. Thus, Completion Times are tracked separately for the N1, N2, SL 1, and SL2 breaker. OCONEE UNITS 1, 2, & 3 83.8.1-18 Rev. 003 I BASES AC Sources -Operating B 3.8.1 *----------------------------------
ACTIONS (continued)
SURVEILLANCE REQUIREMENTS L.1, L.2, and L.3 With an AC Source inoperable or LCO not met, as stated in Note for Condition H entry; or with an AC Source inoperable or LCO not met, as stated in Required Action C.2.2.3 when in Condition C for > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or with an AC Source inoperable or LCO not met, as stated in Required Action 1.2 or J.2 when in Conditions I or J for> 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; or with SR 3.8.1.16 not met, Required Action L.1, L.2 and L.3 requires restoration within four hours. Condition L is modified by a Note indicating that separate Condition entry is permitted for each inoperable AC Source, and LCO or SR not met. The Required Action is modified by a Note that allows the remaining OPERABLE KHU and its required emergency power path to be made inoperable if required to restore both KHUs and their required emergency power paths to OPERABLE status. This note is necessary since certain actions such as dewatering the penstock may be necessary to restore the inoperable KHU although these actions would also cause both KHUs to be inoperable.
The purpose of this Required Action is to restrict the allowed outage time for an inoperable AC Source or equipment required by an LCO when in Conditions C, H, I or J. For Conditions I and J when the LCOs stated are initially not met, the maximum Completion Time is four hours or the remaining Completion Time allowed by the stated LCO, whichever is shorte~
- M.1 and M.2 If a Required Action and associated Completion Time for Condition C, F, G, H, I, J, Kor Lare not met; or if a Required Action and associated Completion Time are not met for Required Action D.1 or D.3, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 5 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 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. SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are OCONEE UNITS 1, 2, & 3 B 3.8.1-19 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
SURVEILLANCE REQUIREMENTS SR 3.8.1.1 (continued) connected to their power source, and that appropriate separation of offsite sources is maintained.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.2 This SR verifies adequate battery voltage when the KHU batteries are on float charge. This SR is performed to verify KHU battery OPERABILITY.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.3 This SR verifies the availability of the KHU associated with the underground emergency power path to start automatically and energize the underground power path. Utilization of either the auto-start or emergency start sequence assures the control function OPERABILITY by verifying proper speed control and voltage. Power path verification is included to demonstrate breaker OPERABILITY from the KHU onto the standby buses. This is accomplished by closing the Keowee Feeder Breakers (SK) to energize each deenergized standby bus. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.4 This surveillance verifies the availability of the KHU associated with the overhead emergency power path. Utilization of either the auto-start or emergency start sequence assures the control function OPERABILITY by verifying proper speed control and voltage. The ability to supply the overhead emergency power path is satisfied by demonstrating the ability to synchronize (automatically or manually) the KHU with the grid system. If an automatic start of the KHU is performed and a manual synchronization is desired, the KHU will need to be shutdown and started in manual to allow a manual synchronization of the KHU. The SR also requires that the underground power path be energized after removing the KHU from the overhead emergency power path. This surveillance can be satisfied by first demonstrating the ability of the KHU OCONEE UNITS 1, 2, & 3 B 3.8.1-20 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
SURVEILLANCE REQUIREMENTS SR 3.8.1.4 (continued) associated with the underground emergency path to energize the underground path then synchronizing the KHU to the overhead emergency power path. The SR is modified by a Note indicating that the requirement to energize the underground emergency power path is not applicable when the overhead disconnects are open for the KHU associated with the underground emergency power path or 2) when complying with Required Action D.1. The latter exception is necessary since Required Action D.1 continues to be applicable when both KHUs are inoperable.
\ The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.5 This surveillance verifies OPERABILITY of the trip functions of each closed SL and each closed N breaker. Neither of these breakers have any automatic close functions; therefore, only the trip coils require verification.
Cycling of each breaker demonstrates functional OPERABILITY and the coil monitor circuits verify the integrity of each trip coil. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. This SR modified by a Note that states it is not required to be performed for an SL breaker when its standby bus is energized from a LCT via an isolated power path. This is necessary since the standby buses are required to be energized from a LCT by several Required Actions of Specification 3.8.1 and the breakers must remain closed to energize the standby buses from a LCT. SR 3.8.1.6 Infrequently used source breakers are cycled to ensure OPERABILITY.
The Standby breakers are to be cycled one breaker at a time to prevent inadvertent interconnection of two units through the standby bus breakers.
Cycling the startup breakers verifies OPERABILITY of the breakers and associated interlock circuitry between the normal and startup breakers.
This circuitry provides an automatic, smooth, and safe transfer of auxiliaries in both directions between sources. The Surveillance Frequency is based on operating experience, equipment OCONEE UNITS 1, 2, & 3 B 3.8.1-21 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
SURVEILLANCE REOUIREMENTS SR 3.8.1.6 (continued) reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. This SR is modified by a Note which states the SR is not required to be performed for an S breaker when its standby bus is energized from a LCT via an isolated power path. This is necessary since the standby buses are required to be energized from a LCT by several Required Actions of Specification 3.8.1 and cycling the S breakers connects the standby buses with the main feeder buses which are energized from another source. SR 3.8.1.7 The KHU tie breakers to the underground path, ACB3 and ACB4, are interlocked to prevent cross-connection of the KHU generators.
The safety analysis utilizes two independent power paths for accommodating single failures in applicable accidents.
Connection of both generators to the underground path compromises the redundancy of the emergency power paths. Installed test logic is used to verify a circuit to the close coil on one underground ACB does not exist with the other underground ACB closed. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.8 Each KHU tie breaker to the underground emergency power path and tie breaker to the overhead emergency path, are. interlocked to prevent the unit associated with the underground circuit from automatically connecting to the overhead emergency power path. The safety analysis utilizes two independent power paths for accommodating single failures in applicable accidents.
Connection of both generators to the overhead emergency power path compromises the redundancy of the emergency power paths. Temporary test instrumentation is used to verify a circuit to the close coil on the overhead ACB does not exist with the Underground ACB closed. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. OCONEE UNITS 1, 2, & 3 B 3.8.1-22 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.9 This surveillance verifies the KHUs' response time to an Emergency Start signal (normally performed using a pushbutton in the control room) to ensure ES equipment will have adequate power for accident mitigation.
UFSAR Section 6.3.3.3 (Ref. 6) establishes the 23 second time requirement for each KHU to achieve rated frequency and voltage based on the assumption that an engineered safeguards actuation in one unit occurs simultaneously with a loss of offsite power to all three units. Emergency start without a design basis event or minimal load such as unit shutdown could conceivably cause the KHU to experience overshoot or over-frequency.
This surveillance also verifies the KHU's steady-state frequency is 59.4 Hz and ::. 61.8 Hz. These limits were established to ensure key mechanical systems and equipment have adequate frequency for accident mitigation.
The limits are automatically maintained by Keowee control systems. A nominal time of 60 seconds following the Emergency Start signal is sufficient time to begin monitoring steady state operation.
Since the only available loads of adequate magnitude for simulating an accident is the grid, subsequent loading on the grid is required to verify the KHU's ability to assume rapid loading under accident conditions.
Sequential block loads are not available to fully test this feature. This is the reason for the requirement to load the KHUs at the maximum practical rate. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.10 A battery service test is a special test of the battery capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length should correspond to the design duty cycle requirements as specified in Reference
- 4. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. OCONEE UNITS 1, 2, & 3 B 3.8.1-23 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.11 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.12 Verification of cell to cell connection cleanliness, tightness, and proper coating with anti-corrosion grease provides an indication of any abnormal condition, and assures continued OPERABILITY of the battery. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.8.1.13 The KHU underground ACBs have a control feature which will automatically close the KHU, that is pre-selected to the overhead path, into the underground path upon an electrical fault in the zone overlap region of the protective relaying.
This circuitry prevents an electrical fault in the zone overlap region of the protective relaying from locking out both emergency power paths during dual KHU grid generation.
In order to ensure this circuitry is OPERABLE, an electrical fault is simulated in the zone overlap region and the associated underground ACBs are verified to operate correctly.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. This SR is modified by a Note indicating the SR is only applicable when the overhead disconnects to the underground KHU are closed. When the overhead disconnects to the underground KHU are open, the circuitry preventing the zone overlap protective lockout of both KHUs is not needed. SR 3.8.1.14 This surveillance verifies OPERABILITY of the trip functions of the SL and N breakers.
This SR verifies each trip circuit of each breaker OCONEE UNITS 1, 2, & 3 B 3.8.1-24 Rev. 003 I BASES AC Sources -Operating B 3.8.1 ----------------------------------
SUHVEILLANCE REOUIREMENTS (continued)
SR 3.8.1.14 (continued) independently opens each breaker. Neither of these breakers have any automatic close functions; therefore, only the trip circuits require verification.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. The SR is modified by a Note indicating that the SR is not required for an SL breaker when its standby bus is energized by a LCT via an isolated power path. This is necessary since the standby buses are required to be energized from a LCT by several Required Actions of Specification 3.8.1 and the breakers must remain closed to energize the standby buses from a LCT. SR 3.8.1.15 This surveillance verifies proper operation of the 230 kV switchyard circuit breakers upon an actual or simulated actuation of the Switchyard Isolation circuitry.
This test causes an actual switchyard isolation (byactuation of degraded grid voltage protection) and alignment of KHUs to the overhead and underground emergency power paths. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. The effect of this SR is not significant because the generator red bus tie breakers and feeders from the Oconee 230 kV switchyard red bus to the system grid remain closed. Either Switchyard Isolation Channel causes full system realignment, which involves a complete switchyard realignment.
To avoid excessive switchyard circuit breaker cycling, realignment and KHU emergency start functions, this SR need be performed only once each SR interval.
SR 3.8.1.16 This SR verifies by administrative means that one KHU provides an alternate manual AC power source capability by manual or automatic KHU start with manual synchronize, or breaker closure, to energize its non-required emergency power path. That is, when the KHU to the overhead emergency power path is inoperable, the SR verifies by administrative means that the overhead emergency power path is OPERABLE.
When the overhead emergency power path is inoperable, the SR verifies by administrative means that the KHU associated with the overhead emergency power path is OPERABLE.
OCONEE UNITS 1, 2, & 3 B 3.8.1-25 Rev. 003 I r I ' BASES AC Sources -Operating B 3.8.1 *----------------------------------
SURVEILLANCE REOUIREMENTS REFERENCES SR 3.8.1.16 (continued)
This SR is modified by a Note indicating that the SR is only applicable when complying with Required Action C.2.2.4. SR 3.8.1.17 This SR verifies the Keowee Voltage and Frequency out of tolerance logic trips arid blocks closure of the appropriate overhead or underground power path breakers on an out of tolerance trip signal. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. There are three over voltage relays, three under voltage relays, and three over/under frequency relays per KHU with each relay actuating an auxiliary relay used to provide two out of three logic. These relays monitor generator output voltage and if two phases are above/below setpoint, prevent the power path breakers from closing or if closed, provide a trip signal which is applied after a time delay, to open the power path breakers.
Testing demonstrates that relays actuate at preset values, that timers time out and that two under voltage relays, two over voltage relays, or two over/under frequency relays will actuate the logic channel. This ensures that the power path breakers will not close and if closed, will trip after a preset time delay that becomes effective when the KHU first reaches the required frequency and voltage band. 1. UFSAR, Section 3.1.39 2. UFSAR, Chapter 16 3. 10 CFR 50.36 4. UFSAR, Chapter 6 5. UFSAR, Chapter 15 6. UFSAR, Section 6.3.3.3 OCONEE UNITS 1, 2, & 3 B 3.8.1-26 Rev.003 I