Text

License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
	ML15103A656
Person / Time
Site:	Farley
Issue date:	04/13/2015
From:	Pierce C; Southern Co, Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-14-1531, TSTF-432-A, Rev 1, WCAP-16294
	Download: ML15103A656 (143)
	v • d • e

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 A

Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN COMPANY April 13, 2015 Docket Nos.: 50-348 NL-14-1531 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Units 1 and 2 License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294),

Using the Consolidated Line Item Improvement Process

Reference:

TSTF-432-A, Revision 1, "Change in Technical Specifications End States, WCAP-16294," dated November 29,2010.

Ladies and Gentlemen:

In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Technical Specifications (TS) for Farley Nuclear Plant (FNP), Units 1 and 2.

The proposed change would modify the Farley Technical Specifications to incorporate risk-informed requirements for selected Required Action end states. Specifically, the proposed change would permit a Required Action end state of Mode 4 rather than an end state of Mode 5.

The proposed changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Technical Change Traveler 432-A, Revision 1 (reference). provides the basis for the proposed changes, the requested confirmation of applicability, and plant-specific verifications. Enclosure 2 provides the existing Farley TS pages marked up to show the proposed changes. Enclosure 3 provides existing Farley TS Bases pages marked up to show the proposed changes. Enclosure 4 provides revised (clean-typed)

Farley TS pages.

SNC requests approval of the proposed license amendment by March 31,2016, with the amendment being implemented within 90 days of issuance of the amendment.

U.S. Nuclear Regulatory Commission NL-14-1531 Page2 This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.

Respectfully submitted, C. I{~

C. R. Pierce Regulatory Affairs Director CRP/JMC/

Sworn to and subs ribed before me this 13-JLday of 4r I./

I 12014.

Notary Public My commission expires: ~I Ii'

Enclosures:

1. Basis for Proposed Changes

2. Marked-Up Technical Specifications Pages

3. Marked-Up Technical Specifications Bases Pages

4. Clean-Typed Technical Specifications Pages cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley Mr. M.D. Meier, Vice President- Regulatory Affairs Mr. T. E. Tynan, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Mr. R. R. Martin, Regulatory Affairs Manager- Farley RTYPE: CFA04.054

U.S. Nuclear Regulatory Commission NL-14-1531 Page 3 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley Mr. K. E. Miller, Resident Inspector- Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer

Joseph M. Farley Nuclear Plant- Units 1 and 2 License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294),

Using the Consolidated Line Item Improvement Process Enclosure 1 Basis for Proposed Changes to NL-14-1531 Basis for Proposed Changes Basis for Proposed Changes 1.0 Description Southern Nuclear Operating Company, (SNC) requests an amendment to Operating Licenses for the Joseph M. Farley Nuclear Plant, Units 1 and 2, NPF-2 and NPF-8, respectively. The proposed change would modify the Farley Technical Specifications to incorporate risk-informed requirements for selected Required Action end states. The changes are consistent with Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler TSTF-432-A Revision 1, "Change in Technical Specifications End States (WCAP-16294) ." The availability of this TS improvement was announced in the Federal Register on May 11, 2012 (FR 77 27814) as part of the Consolidated Line Item Improvement Process (CLIIP) .

2.0 Assessment 2.1 Applicability of Published Safety Evaluation SNC has reviewed Westinghouse Topical Report (TR) WCAP-16294 (Reference 1), the Nuclear Regulatory Commission (NRC) safety evaluation for WCAP-16294 (Reference 2), TSTF-432-A, Revision 1 (Reference 3), and the associated NRC model safety evaluation (Reference 4). SNC has concluded that the technical bases described in the Westinghouse topical report and TSTF-432-A. Revision 1, as well as the associated safety evaluation prepared by the NRC staff are applicable to Farley Units 1 and 2 and support incorporation of this amendment request into the Farley Unit 1 and 2 Technical Specifications.

The TSTF-432 justification references Regulatory Guide (RG) 1.182. On November 27, 2012, the NRC published a Federal Register Notice stating that RG 1.182 has been withdrawn and the subject matter has been incorporated into RG 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." RG 1.160 endorses NUMARC 93 01, Revision 4A. dated April2011.

SNC assesses the risk of maintenance activities consistent with the guidance in RG 1.160. Therefore, the justification for adoption of TSTF-432 continues to be applicable.

2.2 Optional Changes and Variations SNC is proposing the following variations or deviations from the Westinghouse topical report, the TS changes described in the TSTF-432-A. Revision 1 , or the NRC staff's model safety evaluation published in the Federal Register on May 11, 2012 (77 FR 27814) as part of the CLIIP Notice of Availability. In some instances, the Technical Specification number and or title may be different between the generic Improved Standard Technical Specifications (ISTS)

(Reference 5) on which TSTF-432-A was based and the Farley Unit 1 and 2 specific TS; however, the justification for the proposed mode change remains directly applicable. Additionally, in some cases there may be content differences between the ISTS and Farley TS due to plant specific or historical reasons.

Table 1 provides a comparison of the Technical Specifications action E1 - 1 to NL-14-1531 Basis for Proposed Changes requirements in TSTF-432-A and the corresponding Farley Technical Specifications action requirements which are proposed for modification. These variations or deviations are discussed below:

1. ISTS TS 3.3.2. Engineered Safety Feature Actuation System Instrumentation. Condition K TS 3.3.2, Condition K applies to the Engineered Safety Feature Actuation System (ESFAS) Instrumentation safety feature for switchover from the refueling water storage tank (RWST) to the containment sump when RWST level is Low Low. Farley TS Table 3.3.2-1 does not include this function.

The changes described in TSTF-432-A, Revision 1 for ISTS TS 3.3.2, Condition K are therefore not adopted.

2. ISTS TS 3.3.8. Fuel Building Air Cleanup System Actuation Instrumentation.

Condition 0 ISTS TS 3.3.8, Condition 0 provides end state requirements for inoperability of the Fuel Building Air Cleanup System Actuation Instrumentation. The Farley TS do not include a corresponding specification for the Fuel Building Air Cleanup System Actuation Instrumentation. The changes described in TSTF-432-A, Revision 1 for ISTS TS 3.3.8, Condition 0 are therefore not adopted.

3. ISTS TS 3.4.15. Reactor Coolant System Leakage Detection Instrumentation. Condition E (Farley TS 3.4.15. Condition 0)

ISTS 3.4.15, Condition A provides requirements for the containment sump monitor leak detection instrumentation that is not included in the Farley TS.

Additionally, Farley TS 3.4.15 includes Conditions reflecting combinations of reactor coolant system leakage detection instrumentation inoperability (i.e.,

containment atmosphere particulate and gaseous radiation monitors, containment air cooler level monitor) that are not included in ISTS TS 3.4.15. The end state Completion Times for these additional Conditions are consistent with those evaluated in WCAP-16294, Revision 1, and provided in TSTF-432-A, Revision 1. The Completion Time for Required Action 0 .2 is revised to reflect these values.

4. ISTS TS 3.5.3. Emergency Core Cooling System - Shutdown.

Conditions A. B. C (Farley TS 3.5.3. Conditions A. B. C. 0)

Farley TS 3.5.3 includes an additional Condition (Condition B) for inoperability of an Emergency Core Cooling System (ECCS) centrifugal charging subsystem when 100% of the ECCS flow equivalent to a single ECCS train is available that is not included in ISTS TS 3.5.3. Farley TS 3.5.3, Condition 0 is also modified from ISTS TS 3.5.3, Condition C to reflect the additional Condition. The additional and modified Conditions in Farley TS 3.5.3 are plant-specific aspects of the licensing basis, and are not readily adaptable to the changes described in TSTF-432-A. Therefore, the TS and Bases changes identified in TSTF-432-A for ISTS 3.5.3 are not adopted.

E1- 2 to NL-14-1531 Basis for Proposed Changes

5. ISTS TS 3.6.6B. Containment Spray and Cooling Systems. Condition F ISTS TS 3.6.6B provides operability requirements for containment spray and cooling systems, where no credit is taken for iodine removal by the Containment Spray System. The Farley design credits containment spray for iodine removal in the event of a LOCA. The design also credits baskets of crystalline trisodium phosphate located inside containment for reduction of airborne iodine activity levels inside containment and retention of removed iodine in the containment sump following an accident. As a result, the changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.6B are not adopted.

6. ISTS TS 3.6.6C. Containment Spray System. Condition B The Farley design does not include an ice condenser. The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.6C are therefore not adopted.

7. ISTS TS 3.6.60. Quench Spray System. Condition B The Farley design does not include a Quench Spray System. The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.60 are therefore not adopted.

8. ISTS TS 3.6.6E. Recirculation Spray System. Condition B The Farley design does not include a Recirculation Spray System. The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.6E are therefore not adopted.

9. ISTS TS 3.6. 7. Spray Additive System. Condition B (Farley TS 3.5.6.

Recirculation Fluid pH Control System. Condition B)

ISTS TS 3.6.7 provides Conditions for inoperability of the Spray Additive System. The Farley design does not employ a Spray Additive System, and uses a recirculation fluid pH control system instead. The recirculation fluid pH control system consists of baskets of crystalline TSP that are located inside containment. The ISTS does not provide a model specification for recirculation fluid pH control systems that utilize TSP baskets, and it is therefore not specifically included in TSTF-432-A, Revision 1. However, end state Completion Times for recirculation fluid pH control systems that utilize TSP baskets are discussed in Section 3.1.15 of WCAP-16294, Revision 1. The Completion Time for Required Action B.2 of Farley TS 3.5.6 is revised to reflect the value evaluated in WCAP-16294, Revision 1.

10. ISTS TS 3.6.11. Iodine Cleanup System. Condition B The Farley design does not include an Iodine Cleanup System. The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.11 are therefore not adopted.

11. ISTS TS 3.6.12. Vacuum Relief Valves. Condition B The Farley design does not include a containment vacuum relief valves.

The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.12 are therefore not adopted.

E1- 3 to NL-14-1531 Basis for Proposed Changes

12. ISTS TS 3.6.13. Shield Building Air Cleanup System. Condition B The Farley design does not include a shield building air cleanup system .

The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.13 are therefore not adopted.

13. ISTS TS 3.6.14, Air Return System. Condition B The Farley design does not include an ice condenser air return system.

The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.13 are therefore not adopted.

14. ISTS TS 3.6.18, Containment Recirculation Drains. Condition C The Farley design does not include containment recirculation drains. The changes identified in TSTF-432-A, Revision 1 for ISTS TS 3.6.13 are therefore not adopted.

15. ISTS TS 3.7.8. Service Water System. Condition B (Farley TS 3.7.8.

Condition C)

Farley TS 3.7.8 includes an additional Condition for operability of the automatic Service Water System (SWS) isolation valve for the Turbine Building . The end state Completion Times for this additional Condition reflects a plant-specific attribute of the Farley SWS design, and is consistent with those evaluated in WCAP-16294, Revision 1, and provided in TSTF-432-A, Revision 1. The Completion Time for Required Action C.2 is revised to reflect these values.

16. ISTS TS 3.7.9. Ultimate Heat Sink. Condition C (Farley TS 3.7.9.

Condition El The structure and content of Farley TS 3.7.9 differs from that of ISTS TS 3.7.9. Farley TS 3.7.9 provides a singular Condition (Condition A) for ultimate heat sink (UHS) water level or temperature not within limits. The Completion Times for this Condition provide end state requirements, and there is not a separate Condition with end state requirements, as there is in the ISTS. The end state Completion Times for the additional UHS water level operability requirement reflect plant-specific attributes of the Farley UHS design, and are consistent with those evaluated in WCAP-16294, Revision 1, and provided in TSTF-432-A, Revision 1. The Completion Time for Required Action A.2 is revised to reflect these values.

E1-4 to NL-14-1531 Basis for Proposed Changes

17. ISTS TS 3.7.10. Control Room Emergency Filtration System. Condition C (Farley TS 3.7.10. Control Room . Condition C)

Farley TS 3.7.10, Condition C, provides an additional end state requirement when two Control Room Emergency Filtration System (CREFS) trains are inoperable for reasons other than inoperable control room boundary that is not provided in ISTS TS 3.7.10. With two CREFS trains inoperable under these conditions, ISTS TS 3.7.10 would require entry into LCO 3.0.3, which would then require that the unit be brought to MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , and MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months . Under these same conditions, with two CREFS trains inoperable, Farley TS 3.7.10, Condition C, allows 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to be in MODE 3, and 36 Hours to be in MODE 5. Adoption of the end state Completion Times for this additional requirement is consistent with those evaluated in WCAP-16294, Revision 1, and provided in TSTF-432-A, Revision 1. The Completion Time for Required Action C.2 is revised to reflect these values.

18. ISTS TS 3.7.12. ECCS Pump Room Exhaust Air Cleanup System.

Condition C (Farley TS 3.7.19. Engineered Safety Feature Room Coolers.

Condition B)

ISTS TS 3.7.12 provides requirements for ECCS pump room exhaust cleanup and cooling equipment. Farley TS 3.7.19 provides requirements for the ECCS pump room coolers, but does not include requirements for ECCS pump room exhaust cleanup equipment or the ECCS pump room ventilation boundary. As a result of this difference, ISTS TS 3.7.12 includes a Condition for ECCS pump room boundary inoperability that is not included in Farley TS 3.7.14. For Farley, the ECCS pump rooms are exhausted through the Penetration Room Filtration System, the requirements for which are provided in Farley TS 3.7.12. This difference does not affect the intent of TSTF-432-A, and the Completion Time for Required Action B.2 of Farley TS 3.7.19 is revised to reflect the value evaluated in WCAP-16294, Revision 1.

19. ISTS TS 3.7.13. Fuel Building Air Cleanup System. Condition C ISTS TS 3.7.13, Condition C provides end state requirements for inoperability of the Fuel Building Air Cleanup System. The Farley TS do not include a corresponding specification for the Fuel Building Air Cleanup System. The changes described in TSTF-432-A, Revision 1 for ISTS TS

3. 7.13, Condition B are therefore not adopted.

E1- 5 to NL-14-1531 Basis for Proposed Changes

20. ISTS TS 3.7.14. Penetration Room Exhaust Air Cleanup System .

Condition C (Farley TS 3.7.12. Penetration Room Filtration System.

Condition C)

ISTS TS 3.7.14, Condition C provides end state requirements for inoperability of the Penetration Room Exhaust Air Cleanup System. The corresponding Farley requirements are located in TS 3.7.12, Piping Room Filtration (PRF) System, Condition C. The Applicability for ISTS 3.7.14 is MODES 1, 2, 3, and 4. The Applicability for Farley TS 3.7.12, applies during movement of irradiated fuel assemblies in the spent fuel pool room (SFPR), in addition to theISTS requirements. This difference results in additional non-end state Conditions in the Farley TS for PRF System inoperability during irradiated fuel movement in the Spent Fuel Pool Room that do not appear in the ISTS.

Additionally, with two penetration room exhaust air cleanup systems inoperable, ISTS TS 3.7.14 would require entry into LCO 3.0.3, which would then require that the unit be brought to MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , and MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months . This condition is addressed in Farley TS 3.7.12, Condition C, which allows 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to be in MODE 3, and 36 Hours to be in MODE 5. Adoption of the end state Completion Times for this additional requirement is consistent with those evaluated in WCAP-16294, Revision 1, and provided in TSTF-432-A, Revision 1. The Completion Time for Required Action C.2 is revised to reflect these values.

21 . ISTS TS 3.8.1, AC Sources- Operating. Condition G (Farley TS 3.8.1.

Condition H)

Farley TS 3.8.1 includes an additional end state Condition, Condition F, that is not provided as a separate Condition in ISTS TS 3.8.1 . Condition F directs that the unit be brought to MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months when the Completion Times for Conditions related to emergency diesel generator operability are not met. Consistent with Condition Gin theISTS, Condition H of Farley TS 3.8.1 addresses all other inoperability conditions involving end state requirements forTS 3.8.1. The end state Completion Time for Condition C reflects the historical licensing basis for the Farley plant and is retained. This difference does not affect the intent of TSTF-432-A, and the Completion Time for Required Action H.2 of Farley TS 3.8.1 is revised to reflect the value evaluated in WCAP-16294, Revision 1.

22. ISTS TS 3.8.4. DC Sources- Operating . Condition D (Farley TS 3.8.4.

Condition C)

ISTS TS 3.8.4 provides requirements for the direct current (DC) electrical power distribution subsystems. The scope of Farley TS 3.8.4 is more limited than the ISTS, and provides requirements for the auxiliary building and service water intake structure DC vital bus electrical power distribution subsystems. As a result of this difference the structure and content of Farley TS 3.8.4 differs from that of ISTS TS 3.8.4. These differences do not affect the intent of TSTF-432-A, Revision 1 or the end state Completion Times evaluated in WCAP-16294, Revision 1. The Completion Time for Required Action C.2 is revised to reflect these values.

E1-6 to NL-14-1531 Basis for Proposed Changes

23. ISTS TS 3.8.9. Distribution Systems- Operating. Condition D (Farley TS 3.8.9, Condition D)

Farley TS 3.8.9 includes additional Conditions related to operability of the auxiliary building and service water intake structure DC vital bus electrical power distribution subsystems that are not included in ISTS TS 3.8.9.

These additional Conditions do not affect the intent of TSTF-432-A, Revision 1 or the end state Completion Times evaluated in WCAP-16294, Revision 1. The Completion Time for Required Action D.2 is revised to reflect these values.

3.0 Regulatory Analysis 3.1 No Significant Hazards Consideration Southern Nuclear Operating Company (SNC) has evaluated the proposed changes to the Technical Specifications (TS) using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration.

Description of Amendment Request: The proposed amendment would modify TS to risk-inform requirements regarding selected Required Action End States.

As required by 10 CFR 50.91 (a), the SNC analysis of the issue of no significant hazards consideration is presented below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change modifies the end state (e.g., mode or other specified condition) which the Required Actions specify must be entered if compliance with the Limiting Conditions for Operation (LCO) is not restored. The requested Technical Specifications (TS) permit an end state of Mode 4 rather than an end state of Mode 5 contained in the current TS. In some cases, other Conditions and Required Actions are revised to implement the proposed change. Required Actions are not an initiator of any accident previously evaluated. Therefore, the proposed change does not affect the probability of any accident previously evaluated. The affected systems continued to be required to be operable by the TS and the Completion Times specified in the TS to restore equipment to operable status or take other remedial Actions remain unchanged. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Tech Spec Required Action Endstates for Westinghouse NSSS PWRs," demonstrates that the proposed change does not significantly increase the consequences of any accident previously evaluated.

E1 -7 to NL-14-1531 Basis for Proposed Changes Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change modifies the end state (e.g., mode or other specified condition) which the Required Actions specify must be entered if compliance with the LCO is not restored. In some cases, other Conditions and Required Actions are revised to implement the proposed change. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the change does not impose any new requirements. The change does not alter assumptions made in the safety analysis.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No The proposed change modifies the end state (e.g., mode or other specified condition) which the Required Actions specify must be entered if compliance with the LCO is not restored. In some cases, other Conditions and Required Actions are revised to implement the proposed change. Remaining within the Applicability of the LCO is acceptable because WCAP-16294-NP-A demonstrates that the plant risk in MODE 4 is similar to or lower than MODE 5. As a result, no margin of safety is significantly affected.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

3.2 Applicable Regulatory Requirements/Criteria A description of the proposed TS change and its relationship to applicable regulatory requirements were published in the Model Safety Evaluation (SE) (NRC ADAMS Accession Number ML120200384). SNC has reviewed the NRC staffs model SE referenced in the CLIIP Notice of Availability and concluded that the regulatory evaluation section is applicable to Farley Units1 and 2.

E1-8 to NL-14-1531 Basis for Proposed Changes 4.0 Environmental Considerations The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, or would change an inspection or surveillance requirement.

However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b) , no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

5.0 References

1. WCAP-16294-NP-A, Revision 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," dated June, 2010 (NRC ADAMS Accession Number ML103430249).

2. Final Safety Evaluation for NEI Topical Report WCAP-16294-NP, Revision 0, "Risk-Informed Evaluation of Changes to Technical Specification Required Endstates for Westinghouse NSSS [Nuclear Steam Supply System] PWRS [Pressurized Water Reactors]," August 2005 (NRC ADAMS Accession Number ML100770146) 3 TSTF-432, Revision 1, "Change in Technical Specifications End States WCAP-16294" dated November 29, 2010 (NRC ADAMS Accession Number ML103360003).

4. Federal Register, 77 FR 27814, "Notice of Availability for TSTF-432, Revision 1, "Change in Technical Specifications End States (WCAP-16294)" Using the Consolidated Line Item Improvement Process, May 11,2012.

5. NUREG-1431, "Standard Technical Specifications Westinghouse Plants," Revision 3, March 2004.

E1-9 to NL-14-1531 Basis for Proposed Changes Table 1 - TSTF-432-A Technical Specifications and corresponding Farley Technical Specifications Required Actions TSTF-432-A Technical Specification Corresponding Farley Technical and Condition Specification and Condition 3.3.2-B: ESFAS Instrumentation 3.3.2-B: ESFAS Instrumentation 3.3.2-C: ESFAS Instrumentation 3.3.2-C: ESFAS Instrumentation 3.3.7-C: Control Room Emergency 3.3.7-C: Control Room Emergency Filtration System Actuation Filtration System Actuation Instrumentation Instrumentation 3.4.13-B: RCS Operational Leakage 3.4.13-B: RCS Operational Leakage 3.4.14-B: RCS Pressure Isolation 3.4.14-B: RCS Pressure Isolation Valve Leakage Valve Leakage 3.4.15-E: RCS Leakage Detection 3.4.15-D: RCS Leakage Detection Instrumentation Instrumentation 3.5.3-A: ECCS -- Shutdown 3.5.3-A: N/A- Changes not adopted 3.5.3-B: ECCS -- Shutdown 3.5.3-B: N/A- Changes not adopted 3.5.3-B: ECCS -- Shutdown 3.5.3-C: N/A- Changes not adopted 3.5.3-C: ECCS - Shutdown 3.5.3-D: N/A- Changes not adopted 3.5.4-C: Refueling Water Storage 3.5.4-C: Refueling Water Storage Tank Tank 3.6.6A-B: Containment Spray and 3.6.6-B: Containment Spray and Cooling Systems Cooling Systems 3.6.6A-E: Containment Spray and 3.6.6-E: Containment Spray and Cooling Systems Cooling Systems 3.6.7-B: Spray Additive System 3.5.6-B: ECCS Recirculation Fluid pH Control System 3.7.7-B: Component Cooling Water 3.7.7-B: Component Cooling Water System System 3.7.8-B: Service Water System 3.7.8-C: Service Water System 3.7.9-C: Ultimate Heat Sink 3.7.9-A: Ultimate Heat Sink 3.7.10-C: Control Room Emergency 3.7.10-C: Control Room Filtration System 3.7.11-B: Control Room Emergency 3.7.11-B: Control Room Air Air Temperature Control Conditioning System System 3.7.12-C: ECCS Pump Room Exhaust 3.7.19-B: Engineered Safety Feature Air Cleanup System Room Coolers 3.7.14-C: Penetration Room Exhaust 3.7.12-C: Penetration Room Filtration Air Cleanup System System 3.8.1-G: AC Sources - Operatii}Q 3.8.1-H: AC Sources - Operating 3.8.4-D: DC Sources- Operating 3.8.4-C: DC Sources -Operating 3.8.7-B: Inverters - Operating 3.8.7-B: Inverters- Operating 3.8.9-D: Distribution Systems - 3.8.9-D: Distribution Systems -

Operating Operating E1 -10

Joseph M. Farley Nuclear Plant- Units 1 and 2 License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294),

Using the Consolidated Line Item Improvement Process Enclosure 2 Marked-Up Technical Specifications Pages to NL-14-1531 Marked-Up Technical Specifications Pages Index of Affected Technical Specification Pages Affected Pages 3.3.2-1 3.3.2-2 3.3.7-2 3.4.13-1 3.4.14-2 3.4.15-3 3.5.4-1 3.5.6-1 3.6.6-1 3.6.6-2 3.7.7-1 3.7.8-2 3.7.9-1 3.7.10-2 3.7.11-1 3.7.12-1 3.7.19-1 3.8.1-5 3.8.4-1 3.8.7-2 3.8.9-2 to NL-14-1531 Marked-Up Technical Specifications Pages ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A. 1 Enter the Condition Immediately with one or more required referenced in channels or trains Table 3.3.2-1 for the inoperable. channel(s) or train(s) .

B. One channel or train B.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

OR B.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND 8.2.2 1'Be in MODE~ ~

L ~~;;;;~~~.T~;------

applicable when entering MODE4.

Farley Units 1 and 2 3.3.2-1 Amendment No. ~ (Unit 1)

Amendment No. lm:J (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. C.1 -------------NOTE-----------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

C.2.1 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

NOTE-------------

LCO 3.0.4.a is not AND applicable when entering MODE 4. t--+--C-.2--'.2~-Be in MODE ~

D. One channel inoperable. D.1 -------------N0 TE-----------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D.2.1 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months D.2.2 Be in MODE 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months Farley Units 1 and 2 3.3.2-2 Amendment No.I!Bm (Unit 1)

Amendment No. m::I(Unit 2) to NL-14-1531 Marked-Up Technical Specificatior

N0 TE--------------

CREFS Actuation Instrumentation LCO 3.0.4.a is not 3.3.7 applicable when entering MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place both CREFS trains Immediately in emergency recirculation mode.

C. Required Action and c.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND MODE~ ~s or B not met in MODE 1, 2, 3, or 4. C.2 Be in D. Required Action and D.1 Suspend CORE Immediately associated Completion ALTERATIONS.

Time for Condition A or B not met during AND movement of irradiated fuel assemblies or D.2 Suspend movement of Immediately during CORE irradiated fuel assemblies.

ALTERATIONS.

SURVEILLANCE REQUIREMENTS

NOTE-----------------------------------------------------------

Refer to Table 3.3.7-1 to determine which SRs apply for each CREFS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2 Perform COT. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.3.7-2 Amendment No. !lfffi1 (Unit 1)

Amendment No.CHH:B (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits within limits.

for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND MODE~ ~s met.

B.2 Be in OR Pressure boundary LEAKAGE exists.

OR 1 --------------N 0 TE--------------

LCO 3.0.4.a is not applicable when entering MODE4.

Primary to secondary LEAKAGE not within limit.

Farley Units 1 and 2 3.4.13-1 Amendment No. llBiil(Unit 1)

Amendment No. !JmJ(Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AMl A.2 Isolate the high 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressure portion of the affected system from the low

N0 TE-------------- pressure portion by LCO 3.0.4.a is not use of a second closed manual, applicable when enteri ng 1-

\

deactivated MODE 4.

automatic, or check valve.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AMl

~s met.

B.2 Be in MODE~

C. RHR System c.1 Place the affected valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months autoclosure or open in the closed position and permissive interlock maintain closed under function inoperable. administrative control.

Farley Units 1 and 2 3.4.14-2 Amendment No. l::ml (Unit 1)

Amendment No. lmJ (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages RCS Leakage Detection Instrumentation 3.4.15 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

NOTE-------------- AND LCO 3.0.4 .a is not applicable when entering MODE4. D.2 ~ ~

' Be in MODE . ~ s E. All required monitors E.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required In accordance with containment atmosphere radioactivity monitor. the Surveillance Frequency Control Program SR 3.4.15.2 Perform COT of the required containment In accordance with atmosphere radioactivity monitor. the Surveillance Frequency Control Program SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required In accordance with containment atmosphere radioactivity monitor. the Surveillance Frequency Control Program SR 3.4.15.4 Perform CHANNEL CALl BRATION of the required In accordance with containment air cooler condensate level monitor. the Surveillance Frequency Control Program Farley Units 1 and 2 3.4.15-3 Amendment Norml (Unit 1)

Amendment No. lml (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES-----------------------------------------------------------

1. RWST piping may be unisolated from non-safety related piping for s 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months under administrative controls to perform SR 3.5.4.3.*

2. RWST piping may be unisolated from non-safety related piping for s 30 days per fuel cycle under administrative controls for filtration or silica removal.*

CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.1 Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

OR --------------NOTE--------------

LCO 3.0.4.a is not RWST borated water applicable when entering B.

temperature not within limits.

RWST inoperable for B.1

\ MODE 4.

Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months c.

reasons other than Condition A.

Required Action and C.1

\ OPERABLE status.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 BeinMODE~ ~s

These Notes can only be applied during the next two fuel Cycles for each Unit.

These Notes cannot be used after Refueling Outages 1R26 (Spring 2015) and 2R24 (Spring 2016).

Farley Units 1 and 2 3.5.4-1 Amendment No. !!BHJ (Unit 1)

Amendment No. !iBID (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages ECCS Recirculation Fluid pH Control System 3.5.6 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 ECCS Recirculation Fluid pH Control System LCO 3.5.6 The ECCS Recirculation Fluid pH Control System shall be OPERABLE.

N0 TE --------------

APPLICABILITY: MODES 1, 2, 3, and 4. LCO 3.0.4.a is not I

applicable when entering MODE 4.

ACTIONS -------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME A. ECCS Recirculation Fluid A.1 Restore system to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pH Control System OPERABLE status.

inoperable.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 '¥Be in MODE~ ~

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.6.1 Perform a visual inspection of the ECCS In accordance with Recirculation Fluid pH Control System and verify the the Surveillance following: Frequency Control Program

a. Three (3) storage baskets are in place, and

b. Have maintained their integrity, and

c. Each basket is filled with trisodium phosphate compound such that the level is between the indicated fill marks on the baskets.

Farley Units 1 and 2 3.5.6-1 Amendment No. [!S5] (Unit 1)

Amendment No. [HHfl (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable. spray train to OPERABLE status. AND 10 days from discovery of failure to meet the LCO B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND

~einMODE~ ~s met.

B.2 C. One containment cooling C.1 Restore containment 7 days train inoperable. cooling train to OPERABLE status. AND 10 days from discovery of failure to meet the LCO I --------------N0 TE--------------

LCO 3.0.4.a is not applicable when entering MODE4.

Farley Units 1 and 2 3.6.6-1 Amendment No. r:mJ (Unit 1)

Amendment No. Em! (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages Containment Spray and Cooling Systems 3.6.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Two containment cooling D.1 Restore one containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trains inoperable. cooling train to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C or D AND j3e in MODE~ ~

not met.

I En:~:-~~~-~~:~*TE------------~~mediately E.2 F. Two containment spray trains inoperable. F.1 LCO 3.0.4.a is not

'--- ---iapplicable when entering Any combination of three MODE 4.

or more trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power In accordance with operated, and automatic valve in the flow path that is the Surveillance not locked, sealed, or otherwise secured in position is Frequency Control in the correct position. Program SR 3.6.6.2 Operate each required containment cooling train fan In accordance with unit for ~ 15 minutes. the Surveillance Frequency Control Program SR 3.6.6.3 Verify each containment cooling train cooling water In accordance with flow rate is~ 1600 gpm. the Surveillance Frequency Control Program Farley Units 1 and 2 3.6.6-2 Amendment No.llmiJ (Unit 1)

Amendment No.IIBf£) (Unit 2) to NL-1 4-1531 Marked-Up Technical Specifications Pages CCWSystem 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 ------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops- MODE 4,"

for residual heat removal loops made inoperable by ccw.

Restore CCW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND MODE~ ~s met.

B.2 1,Be in I --------------N0 TE --------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Farley Units 1 and 2 3.7.7-1 Amendment No. ffiHil (Unit 1)

Amendment No. lmJ (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages

N 0 T E--------------

LCO 3.0.4.a is not sws 3.7.8 applicable when entering ACTIONS CONDITION

\ MODE 4.

\ REQUIRED ACTION COMPLETION TIME C. Required Action and C. 1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or 8 AND einMODE~ ~

not met.

C.2 s SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 ------------------------------N0 T E--------------------------------

Isolation of SWS flow to individual components does not render the SWS inoperable.

Verify each accessible SWS manual, power In accordance with operated, and automatic valve in the flow path the Surveillance servicing safety related equipment, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.7.8.2 Verify each SWS automatic valve in the flow path that In accordance with is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the correct position on an actual Frequency Control or simulated actuation signal. Program SR 3.7.8.3 Verify each SWS pump starts automatically on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.7.8.4 Verify the integrity of the SWS buried piping by visual In accordance with inspection of the ground area. the Surveillance Frequency Control Program Farley Units 1 and 2 3.7.8-2 Amendment No.[!mi] (Unit 1)

Amendment No. l!fmJ (Unit 2) to NL-1 4-1531 Marked-Up Technical Specifications Pages UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS (Service Water Pond) shall be OPERABLE.

N 0 TE--------------

LCO 3.0.4.a is not APPLICABILITY: MODES 1, 2, 3, and 4.

applicable when entering ACTIONS CONDITION

\ MODE4.

\ REQUIRED ACTION COMPLETION TIME A. UHS water level or temperature not within the A.1

\~einMOD~ l48hol:lrsl ~

required limit(s). AND A.2 Be in MODE~ ISG l'iettFsiE:: ~

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is ~ 184 ft In accordance with mean sea level. the Surveillance Frequency Control Program SR 3.7.9.2 Verify water temperature of~ 95°F at the discharge In accordance with of the Service Water Pumps the Surveillance Frequency Control Program Farley Units 1 and 2 3.7.9-1 Amendment No. ll!5J (Unit 1)

Amendment No. ffimJ (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages Control Room 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or4.

C.2, Be in MODE~ ~ s OR --------------N0 TE --------------

LCO 3.0.4.a is not Two CREFS trains appl icable when entering inoperable in MODE 1, 2, MODE4.

3, or4. ------------------------------------

D. Required Action and D.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A not recirculation mode.

met during movement of OR irradiated fuel assemblies or during CORE ALTERATIONS. D.2.1 Suspend CORE Immediately ALTERATIONS.

AND D.2.2 Suspend movement of Immediately irradiated fuel assemblies.

Farley Units 1 and 2 3.7.10-2 Amendment No. llBBJ (Unit 1)

Amendment No. I!5BJ (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages CRAGS 3.7.11

3. 7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRAGS)

LCO 3.7.11 Two CRAGS trains shall be OPERABLE.

APPLICABILITY ..

MODES 1 2 3

an d 4 .

During movement of irradiated fuel assemblies,

NOTE--------------

During CORE ALTERATIONS. LCO 3.0.4.a is not applicable when entering ACTIONS CONDITION

\ \ REQUIRED ACTION MODE4.

COMPLETION TIME A.

B.

One CRAGS train inoperable.

Required Action and A.1 B.1

\~e Restore CRAGS train to OPERABLE status.

in MODE 3.

30 days 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND

~s met in MODE 1, 2, 3, or4. B.2 Be in MOD~4

c. Required Action and C.1 Place OPERABLE Immediately associated Completion CRAGS train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies or during CORE C.2.1 Suspend CORE Immediately ALTERATIONS. ALTERATIONS.

AND C.2.2 Suspend movement of Immediately irradiated fuel assemblies.

Farley Units 1 and 2 3.7.11-1 Amendment No. IIiSJ (Unit 1)

Amendment No. [Eff] (Unit 2) to NL-1 4-1 531 Marked-Up Technical Specifications Pages PRF 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Penetration Room Filtration (PRF) System LCO 3.7.12 Two PRF trains shall be OPERABLE.

NOTE -------------------------------------------

The PRF and Spent Fuel Pool Room (SFPR) boundaries may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, and 4 for post LOCA mode of operation, During movement of irradiated fuel assemblies in the SFPR for the fuel handling accident mode of operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One PRF train A.1 Restore PRF train to 7 days inoperable. OPERABLE status.

B. Two PRF trains B.1 Restore PRF boundary to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable in MODE 1, 2, OPERABLE status.

3, or 4 due to inoperable PRF boundary.

c. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND MOD~ ~s not met in MODE 1, 2, 3, or4. C.2 / Be in OR --------------N0 TE --------------

LCO 3.0.4.a is not Two PRF trains applicable when entering inoperable in MODE 1, 2, MODE 4.

3, or 4 for reasons other -------------------------------------

than Condition B.

D. Required Action and D.1 Place OPERABLE PRF Immediately associated Completion train in operation .

Time of Condition A not met during movement of OR irradiated fuel assemblies in the SFPR. D.2 Suspend movement of Immediately irradiated fuel assemblies in the SFPR.

Farley Units 1 and 2 3.7.12-1 Amendment No. ffiffl (Unit 1)

Amendment No. ~ (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages ESF Room Coolers 3.7.19 3.7 PLANT SYSTEMS 3.7.19 Engineered Safety Feature (ESF) Room Coolers LCO 3. 7.19 ESF Room Coolers shall be OPERABLE.

APPLICABILITY: When associated ESF equipment is required to be OPERABLE.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each ESF Room Cooler subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required ESF Room A.1 Restore the affected ESF Room 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Cooler subsystem Train Cooler subsystem Train to inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met. AND 8/einMODE~ ~

OR s

Two trains of the same ESF Room Cooler ~~~-~~~~.~~sT;~;------------

subsystem inoperable. applicable when entering MODE4.

Farley Units 1 and 2 3.7.19-1 Amendment No. [Hfi](Unit 1)

Amendment No.l:l69J(Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages AC Sources- Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. One automatic load G.1 Restore automatic load 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sequencer inoperable. sequencer to OPERABLE status.

H. Required Action and H.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, D, AND 1f!einMODE~ ~

or G not met.

I H.2 s I. Three or more required AC 1.1 Enter LCO 3.0.3. Immediately sources inoperable.

I -------------NOTE-------------

LCO 3.0.4.a is not applicable when entering MODE4.

Farley Units 1 and 2 3.8.1-5 Amendment No. r:ni'BJ (Unit 1)

Amendment No. lm](Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages DC Sources- Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources- Operating LCO 3.8.4 The Train A and Train B Auxiliary Building and Service Water Intake Structure (SWIS) DC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Auxiliary Building DC A.1 Restore the Auxiliary 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power subsystem Building DC electrical inoperable. power subsystem to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for 1B OPERABLE status. Auxiliary Building DC electrical power subsystem inoperable due to inoperable battery for cy_cle 19 only B. One Auxiliary Building DC B.1 Restore the battery 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power subsystem connection resistance to with battery connection within limit.

resistance not within limit.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND

~einMOD~ ~

not met.

C.2 s D. One required SWIS DC D.1 Restore the battery 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power connection resistance to subsystem battery within the limit.

connection resistance not within limit.

E. One required SWIS DC E.1 Declare the associated Immediately electrical power Service Water System subsystem inoperable. train inoperable.

OR --------------N0 TE--------------

Required Action and LCO 3.0.4.a is not associated Completion applicable when entering Time of Condition D not MODE4.

met. -------------------------------------

Farley Units 1 and 2 3.8.4-1 Amendment No. ffil!IJ (Unit 1)

Amendment No. lmJ (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages Inverters- Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.21f'e in MOD~ ~ r

N 0 TE --------------

SURVEILLANCE REQUIREMENTS I LCO 3.0.4.a is not applicable when entering MODE 4.

SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and In accordance with alignment to required AC vital buses. the Surveillance Frequency Control Program Farley Units 1 and 2 3.8.7-2 Amendment No.llB5J (Unit 1)

Amendment No. [!BE[] (Unit 2) to NL-14-1531 Marked-Up Technical Specifications Pages Distribution Systems- Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, 8, or AND MODE~ ~

C not met.

D.2 Be in s E. One Service Water Intake E.1 Declare the associated Immediately Structure (SWIS) DC Service Water train electrical power distribution inoperable.

subsystem inoperable.

F. Two trains with inoperable F.1 Enter LCO 3.0.3. Immediately distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, DC, and AC vital bus electrical power the Surveillance distribution subsystems. Frequency Control Program Farley Units 1 and 2 3.8.9-2 Amendment No.IJB5J (Unit 1)

Amendment No. l!BID (Unit 2)

Joseph M. Farley Nuclear Plant- Units 1 and 2 License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294) ,

Using the Consolidated Line Item Improvement Process Enclosure 3 Marked-Up Technical Specifications Bases Pages to NL-14-1531 Marked-Up Technical Specifications Bases Pages Index of Affected Technical Specification Bases Pages Affected Pages 83.3.2-33 83.3.2-34 83.3.2-48 83.3.7-5 83.3.7-8 83.4.13-4 83.4.13-6 83.4.14-4 83.4.14-8 83.4.15-5 83.4.15-6 83.4.15-7 83.5.4-5 83.5.4-6 83.5.6-4 83.5.6-5 83.6.6-6 83.6.6-7 83.6.6-8 83.6.6-11 83.7.7-3 83.7.7-5 83.7.8-3 83.7.8-5 83.7.9-2 83.7.9-3 83.7.10-6 83.7.10-8 83.7.11-3 83.7.11-4 83.7.12-4 83.7.12-7 83.7.19-5 83.7.19-6 83.8.1-15 83.8.1-29 83.8.4-6 83.8.4-11 83.8.7-4 83.8.9-8 83.8.9-9 o NL-14-1531 Marked-Up Technical Specifications Bases Pages SFAS Instrumentation B 3.3.2 BASES ACTIONS B.1. B.2.1 and B.2.2 (continued) must be placed in a MODE in which This is done by placing the unit in at least MODE 3 within an additional h 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months total time) and in MODE ithin an additional 1001 hours0.0116 days 0.278 hours 0.00166 weeks 3.808805e-4 months S hours total time). The allowabl Com letion Times are 4 reason e, based on operatin experience, to reach the required unit con 1t1ons from full power condit ns in an orderly manner and without challenging unit systems.

INSERT- BASES 3.3.2 C.1. C.2.1. and C.2.2 Condition B Condition C applies to the automatic actuation logic and actuation relays for the following functions:

Sl;

P-4 Interlock;

Containment Spray;

Phase A Isolation; and

Phase B Isolation .

This Condition is intended to address an inoperability of the actuation logic or relays associated with a given train which affects the integrated ESFAS response to an actuation signal. This Condition is applicable whenever more than one ESF system is affected by the inoperable train of logic or relays. However, if one or more inoperable actuation relay(s) in a train affect only a single ESF system, then the ACTIONS Condition of the LCO applicable to the affected ESF component or system should be entered and this Condition is not applicable.

This action addresses the train orientation of the SSPS and the master and slave relays. If one train is inoperable, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are allowed to restore the train to OPERABLE status. The 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowed for restoring the inoperable train to OPERABLE status is justified in Reference 11. The specified Completion Time is reasonable considering that there is another train OPERABLE, and the low probability of an event occurring during this interval. If the train cannot be restored to OPERABLE status, the unit must be (continued)

Farley Units 1 and 2 B 3.3.2-33 IRevtston 4e I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.3.2 Condition B Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 19). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 19, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8 .2.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to , and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Enclosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages ESFAS Instrumentation B 3.3.2 BASES ACTIONS placed in a MODE in which . This is done by placing the unit in at least MODE 3 within an additional 6 hoy~

(30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months total time) and in MODE ithin an additional ~ifuurs t.:::.J

..-.. :If~ hours total time) . The Completio :rimes are reasonable based 4

~ on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems .

INSERT- BASES 3.3.2 Condition C The Required Actions are modified by a Note that allows one train to be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing, provided the other train is OPERABLE. This allowance is based on the reliability analysis assumption of WCAP-10271-P-A (Ref. 10) that 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is the average time required to perform train surveillance.

D.1 D.2.1 and D.2.2 I I Condition D applies to :

Containment Pressure- High 1;

Pressurizer Pressure- Low;

Steam Line Pressure- Low;

Steam Line Differential Pressure-High;

Containment Pressure- High 2;

High Steam Flow in Two Steam Lines Coincident With Tav9 -Low Low; and

SG Water level-Low Low.

If one channel is inoperable, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months are allowed to restore the channel to OPERABLE status or to place it in the tripped condition .

Generally this Condition applies to functions that operate on two-out-of-three logic. Therefore, failure of one channel places the Function in a two-out-of-two configuration. One channel must be tripped to place the Function in a partial trip condition where one-out-of-two Logic will result in actuation. This configuration satisfies redundancy requirements. The 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed to restore the channel to OPERABLE status or to place it in the tripped condition is justified in Reference 11 .

(continued)

Farley Units 1 and 2 B 3.3.2-34 IReoisiot 1 46 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.3.2 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 19). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 19, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to , and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages ESFAS Instrumentation 8 3.3.2 BASES REFERENCES 3. FSAR, Chapter 15.

(continued)

4. Joseph M. Farley Nuclear Power Plant Unit 1 (2) Precautions, Limitations, and Setpoints U-266647 (U-280912) .

5. IEEE-279-1971.

6. WCAP 13751 , Rev. 1, Westinghouse Setpoint Methodology for Protection Systems Farley Nuclear Plant Units 1 and 2.

7. 10 CFR 50.49.

8. WCAP 13751 Rev. 0, Westinghouse Setpoint Methodology for Protection Systems SNOC Farley Nuclear Plant Units 1 and 2.

9. Joseph M. Farley Nuclear Power Plant Units 1 & 2 Precautions, Limitations, and Setpoints for Nuclear Steam Supply Systems, March 1978, U258631/U278997 Rev. 5.

10. WCAP-10271-P-A, Supplement 2, Rev. 1, "Updated Approved Version," June 1990.

11 . WCAP-14333-P-A, Revision 1, "Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times,"

October 1998.

12. Not used.

13. FSAR, Table 7.3-16.

14. WCAP-13632-P-A, Revision 2, "Elimination of Pressure Sensor Response Time Testing Requirements," Jan., 1996.

15. WCAP-14036-P-A, Revision 1, "Elimination of Periodic Protection Channel Response Time Tests," Oct. 1998.

16. NUREG-1218, April1988.

17. A-181007 Reactor Protection System FSD.

18. Westinghouse Functional Diagrams U-166231 thru U-166245.

~INSERT- Reference BASES 3.3.2 Farley Units 1 and 2 8 3.3.2-48 I Reoisi011 521 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.3.2 Reference

19. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

Enclosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages CREFS Actuation Instrumentation B 3.3.7 BASES ACTIONS A.1 (continued)

OPERABLE status, one CREFS train must be placed in the emergency recirculation mode of operation. This accomplishes the actuation instrumentation Function and places the unit in a conservative mode of operation.

B.1.1. B.1.2. and B.2 Condition B applies to the failure of two CREFS actuation trains, two required radiation monitor channels, or two manual initiation trains.

The first Required Action is to place one CREFS train in the emergency recirculation mode of operation immediately. This accomplishes the actuation instrumentation Function that may have been lost and places the unit in a conservative mode of operation.

The applicable Conditions and Required Actions of LCO 3. 7.10 must also be entered for the CREFS train made inoperable by the inoperable actuation instrumentation. In the case of inoperable radiation monitors, one train of CREFS must be declared inoperable and the applicable Condition of LCO 3. 7.1 0 entered. This ensures appropriate limits are placed upon train inoperability as discussed in the Bases for LCO 3.7.10.

Alternatively, both trains may be placed in the emergency recirculation mode. This ensures the CREFS function is performed even in the presence of a single failure.

C.1 and C.2 overall plant risk is reduced .

Condition C applies when the Required Action and associated Completion Time for Condition A or B have not been met and the u is in MODE 1, 2, 3, or 4. Condition C is only applicable to those CREFS functions in Table 3.3.7-1 required OPERABLE in MODES 1-4. The unit must be brought to a MODE in which ~t8~

INSERT- BASES 3.3.7 Ire1UIFeFFients are Aet appheable.l To achieve this status, t~~t must 112 1 be brought to MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 151 ithin urs.

Condition C The allowed Completion Times are reasonable, ba d on operating 4

experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

D.1 and D.2 Condition D applies when the Required Action and associated Completion Time for Condition A or B have not been met during CORE (continued)

Farley Units 1 and 2 B 3.3.7-5 IRevision 1e I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.3.7 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 1). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 1, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplan ned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-1 4-1531 Marked-Up Technical Specifications Bases Pages CREFS Actuation Instrumentation B 3.3.7 BASES SURVEILLANCE SR 3.3.7.5 REQUIREMENTS SR 3.3.7.5 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified in one of two ways. Actuation equipment that may be operated in the design mitigation MODE is either allowed to function or is placed in a condition where the relay contact operation can be verified without operation of the equipment. Actuation equipment that may not be operated in the design mitigation MODE is prevented from operation by the SLAVE RELAY TEST circuit. For this latter case, contact operation is verified by a continuity check of the circuit containing the slave relay. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.3.7.6 SR 3.3.7.6 is the performance of a TADOT. This test is a check of the Manual Actuation Functions. The test includes actuation of the end device (i.e., pump starts, valve cycles, etc.).

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The SR is modified by a Note that excludes verification of setpoints during the TADOT. The Functions tested have no setpoints associated with them.

SR 3.3.7.7 The CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES Farley Units 1 and 2 B 3.3.7-8 I Re\*isieA 591 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.3.7 Reference

1. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

Enclosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages RCS Operational LEAKAGE B 3.4.13 BASES APPLICABILITY In MODES 1, 2, 3, and 4, the potential for RCPB LEAKAGE is greatest when the RCS is pressurized .

In MODES 5 and 6, LEAKAGE limits are not required because the reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE.

LCO 3.4.14, "RCS Pressure Isolation Valve (PIV) Leakage," measures leakage through each individual PIV and can impact this LCO. Of the two PIVs in series in each isolated line, leakage measured through one PIV does not result in RCS LEAKAGE when the other is leak tight.

If both valves leak and result in a loss of mass from the RCS, the loss must be included in the allowable identified LEAKAGE.

ACTIONS Unidentified LEAKAGE or identified LEAKAGE in excess of the LCO limits must be reduced to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . This Completion Time allows time to verify leakage rates and either identify unidentified LEAKAGE or reduce LEAKAGE to within limits before the reactor must be shut down. This action is necessary to prevent further deterioration of the RCPB.

B.1 and B.2 If any pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within limit, or if unidentified or identified LEAKAGE cannot be reduced to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , the reactor must be brought to lower pressure conditions to reduce the severity of the LEAKAGE and its potential consequences. It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAG The reactor must be brought to MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE within hours. This action reduces the LEAKAGE and also reduces the fa ors that tend to degrade the pressure boundary.

12 The allowed ompletion Times are reasonable, based on operating experience, to reach the required plant conditions from full power con 1 10 in an orderly manner and without challenging plant systems.

In MOD the pressure stresses acting on the RCPB are much lower, and further deterioration is much less likely.

INSERT- BASES 3.4.13 Condition B Farley Units 1 and 2 B 3.4.13-4 I Revisio11 241 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.4.13 Condition 8 Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 6). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 6, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1 531 Marked-Up Technical Specifications Bases Pages RCS Operational LEAKAGE B 3.4.13 BASES SURVEILLANCE SR 3.4.13.2 REQUIREMENTS This SR verifies that primary to secondary LEAKAGE is less than or equal to 150 gpd through any one SG. Satisfying the primary to secondary LEAKAGE limit ensures that the operational LEAKAGE performance criterion in the Steam Generator Program is met. If this SR is not met, compliance with LCO 3.4.17, "Steam Generator Tube Integrity," should be evaluated. The 150 gpd limit is measured at room temperature as described in Reference 5. The operational LEAKAGE rate limit applies to LEAKAGE through any one SG. If it is not practical to assign the LEAKAGE to an individual SG, all the primary to secondary LEAKAGE should be conservatively assumed to be from one SG.

The Surveillance is modified by a Note which states that the Surveillance is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation . For RCS primary to secondary LEAKAGE determination, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows .

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. During normal operation the primary to secondary LEAKAGE is determined using continuous process radiation monitors or radiochemical grab sampling in accordance with EPRI guidelines.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 30.

2. Regulatory Guide 1.45, May 1973.

3. FSAR, Section 3.1.2.6, 5.2.7, 10.4, 11 .0, 12.0 and 15.0.

4. NEI 97-06, "Steam Generator Program Guidelines."

5. EPRI TR-104788, "Pressurized Water Reactor Primary-to-Secondary Leak Guidelines."

~INSERT- BASES 3.4.13 Reference Farley Units 1 and 2 B 3.4.13-6 I Reuision Szl o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.4.13 Reference

6. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages RCS PIV Leakage B 3.4.14 BASES ACTIONS A.1 and A.2 (continued)

The flow path must be isolated by two valves. Required Actions A.1 and A.2 are modified by a Note that the valves used for isolation must meet the same leakage requirements as the PIVs and must be within the RCPB or the high pressure portion of the system. However, the valves used to isolate the flow path (which are not PIVs) do not have to be pre-qualified by periodic testing. When Required Action A is entered and the flow path isolated, the valves will be verified at that time to meet the leakage requirements of SR 3.4.14.1 . This is accomplished using the methodology of SR 3.4.13.1 (RCS water inventory balance) with the leakage limits of SR 3.4.14.1 applied.

Required Action A.1 requires that the isolation with one valve must be performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Four hours provides time to reduce leakage in excess of the allowable limit and to isolate the affected system if leakage cannot be reduced. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time allows the actions and restricts the operation with leaking isolation valves.

Required Action A.2 specifies that the double isolation barrier of two valves be restored by closing some other valve qualified for isolation or restoring one leaking PIV. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time after exceeding the limit considers the time required to complete the Action and the low probability of a second valve failing during this time period.

B.1 and B.2 overall plant risk is reduced .

If leakage cann t be reduced, the system isolated, or the other Required Actio accomplished, the plant must be brought to a MODE in which . To achieve this he plant must be brought to MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and with' hours. This Action may reduce the leakage and also reduce e potential for a LOCA outside the containment. he 12 allowed Completion Times are reasonable based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. INSERT- BASES 3.4.14 Condition B The inoperability of the RHR autoclosure interlock renders the associated RHR suction isolation valves incapable of isolating in response to a high pressure condition. The inoperability of the RHR open permissive interlock renders the associated RHR suction (continued)

Farley Units 1 and 2 B 3.4.14-4 I RevisieA 0 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.4.14 Condition B Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 9). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 9, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8 .2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results , determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude , changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages RCS PIV Leakage B 3.4.14 BASES SURVEILLANCE SR 3.4.14.3 REQUIREMENTS (continued) Verifying that the RHR open permissive interlock is OPERABLE ensures that the RCS will not pressurize the RHR system beyond design of 600 psig. The open permissive interlock prevents opening the RHR System suction valves from the RCS when the RCS pressure is above the setpoint. The setpoint upper value ensures the RHR System design pressure will not be exceeded at the RHR pump discharge and was chosen taking into account instrument uncertainty and calibration tolerances. This value also provides assurance that the RHR System suction relief valves setpoint will not be exceeded.

The minimum value of the setpoint range is chosen based upon operational considerations (differential pressure) for the RCP seals and thus does not have a safety-related function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The SR is modified by a Note that provides an exception to the requirement to perform this surveillance when using the RHR System suction relief valves for cold overpressure protection in accordance with SR 3.4.12.3.

REFERENCES 1. 10 CFR 50.2.

2. 10 CFR 50.55a(c) .

3. 10 CFR 50, Appendix A, Section V, GDC 55 .

4. WASH-1400 (NUREG-75/014), Appendix V, October 1975.

5. NUREG-0677, May 1980.

6. Technical Requirement Manual (TRM) .

7. ASME , Boiler and Pressure Vessel Code,Section XI.

8. 10 CFR 50.55a(g) .

It:-.

\ !INSERT - BASES 3.4.14

! Reference Farley Units 1 and 2 B 3.4.14-8 l Reoision 52 I o NL-14* 1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.4.14 Reference

9. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages RCS Leakage Detection Instrumentation B 3.4.15 BASES ACTIONS B.1.11 B.1.21 and B.2 (continued)

With both the required gaseous containment atmosphere radioactivity monitoring instrumentation channel and the required containment air cooler condensate level monitoring instrumentation channel inoperable, alternative action is required. Either grab samples of the containment atmosphere must be taken and analyzed or water inventory balances, in accordance with SR 3.4.13.1, must be performed to provide alternate periodic information.

With a sample obtained and analyzed or water inventory balance performed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor may be operated for up to 30 days to allow restoration of at least one of the required containment monitors.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval provides periodic information that is adequate to detect leakage. The 30 day Completion Time recognizes at least one other form of leakage detection is available.

C.1 C.2.1 and C.2.2 I I With the required containment atmosphere particulate radioactivity monitor inoperable and the required containment air cooler condensate level monitor inoperable, the only means of detecting LEAKAGE is the required containment atmosphere gaseous radioactivity monitor. This Condition is applicable when the only OPERABLE monitor is the containment atmosphere gaseous radioactivity monitor. The containment atmosphere gaseous radioactivity monitor typically cannot detect a 1 gpm leak within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when the RCS activity is low. In addition, this configuration does not provide the required diverse means of leakage detection. Indirect methods of monitoring RCS leakage must be implemented. Grab samples of the containment atmosphere must be taken to provide alternate periodic information. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval is sufficient to detect increasing RCS leakage. The Required Action provides 7 days to restore another RCS leakage monitor to OPERABLE status to restore the intended leakage detection diversity. The 7 day Completion time ensures that the plant will not be operated in a degraded configuration for a lengthy time period.

D.1 and D.2 If a Required Action of Condition A, B, or C cannot be met, the plant must be brought to a MODE in which.J?F..:..;;...:~.;;.;.:..~.;:;.:..:.::..=..::..;:;.;;.....:...:..;:;..:....=..::.=L.:J overall plant risk is reduced .

(continued)

Farley Units 1 and 2 B 3.4 .15-5 IRevision ss l o NL-14-1531 Marked-Up Technical Specifications Bases Pages RCS Leakage Detection Instrumentation B 3.4.15 BASES INSERT- BASES 3.4.15 ACTIONS D.1 and D.2 (continu~ e Condition D 4 12 To achieve this status, the I nt mu t to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MOD within hours. he allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

With all required monitors inoperable, no automatic means of monitoring leakage are available, and immediate plant shutdown in accordance with LCO 3.0.3 is required.

SURVEILLANCE SR 3.4.15.1 REQUIREMENTS SR 3.4.15.1 requires the performance of a CHANNEL CHECK of the required containment atmosphere radioactivity monitor. The check gives reasonable confidence that the channel is operating properly.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

SR 3.4.15.2 SR 3.4.15.2 requires the performance of a COT on the required containment atmosphere radioactivity monitor. The test ensures that the monitor can perform its function in the desired manner. The test verifies the alarm setpoint and relative accuracy of the instrument string . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.4.15.3 and SR 3.4.15.4 These SRs require the performance of a CHANNEL CALIBRATION for each of the RCS leakage detection instrumentation channels. The calibration verities the accuracy of the instrument string, including the instruments located inside containment. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Farley Units 1 and 2 B 3.4.15-6 IRevisiOII ss l o NL-1 4-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.4.15 Condition D Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment*because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 4). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 4, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action D.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results , determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to , and the Note does not preclude , changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages RCS Leakage Detection Instrumentation B 3.4.15 BASES REFERENCES 1. 10 CFR 50, Appendix A, Section IV, GDC 30.

2. Regulatory Guide 1.45, Revision 0, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3. FSAR, Section 5.2.7.

~

Farley Units 1 and 2 B 3.4.15-7 IRevision SS I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.4.15 Reference 4 . WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs ," June 2010.

Enclosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages RWST B 3.5.4 BASES ACTIONS These administrative controls consist of (1) Stroking valve (continued) Q1(2)G31V010 open and then closed prior to circulating the RWST water through the Spent Fuel Pool Purification System (2) establishing a designated operator to control the valve and (3) establishing a preplanned communication method between the operator and Shift Supervisor. In this way, the flow path can be rapidly isolated in the event of a Reactor Trip or at the direction of the Shift Supervisor.

These Notes are to allow recirculation and sampling of the RWST through the Spent Fuel Pool Purification System for filtering as well as operation of the reverse osmosis system to remove silica. These Notes can only be applied during the next two fuel Cycles for each Unit. These Notes cannot be used after Refueling Outages 1R26 (Spring 2015) and 2R24 (Spring 2016).

With RWST boron concentration or borated water temperature not within limits, they must be returned to within limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Under these conditions neither the ECCS nor the Containment Spray System can perform its design function . Therefore, prompt action must be taken to restore the tank to OPERABLE condition . The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months limit to restore the RWST temperature or boron concentration to within limits was developed considering the time required to change either the boron concentration or temperature and the fact that the contents of the tank are still available for injection.

With the RWST inoperable for reasons other than Condition A (e.g.,

water volume), it must be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In this Condition, neither the ECCS nor the Containment Spray System can perform its design function . Therefore, prompt action must be taken to restore the tank to OPERABLE status or to place the plant in a MODE in which the RWST is not required . The short time limit of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to restore the RWST to OPERABLE status is based on this condition simultaneously affecting redundant trains .

C.1 and C.2 If the RWST cannot be returned to OPERABLE status within the overall plant risk is associated Completion Time, the plant must be brought to a MODE in reduced . whi . To achieve this status, the P~IJ~

be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE ~hin t.::J

~}-='t~ hours. he allowed Completion Times are reasonable, based on INSERT- BASES 3.5.4 Condition C Farley Units 1 and 2 B 3.5.4-5 I Re~ti!ion 541 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.5.4 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 2). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 2, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplan ned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages RWST B 3.5.4 BASES C.1 and C.2 (continued) operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.5.4.1 REQUIREMENTS The RWST borated water temperature should be verified to be above the minimum limit assumed in the accident analyses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

The SR is modified by a Note that eliminates the requirement to perform this Surveillance when ambient air temperature is within the operating limit of the RWST. With ambient air temperature within the limit, the RWST temperature should not exceed the limit.

SR 3.5.4.2 The RWST water volume should be verified to be above the required minimum level in order to ensure that a sufficient initial supply is available for injection and to support continued ECCS and Containment Spray System pump operation on recirculation . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

SR 3.5.4 .3 The boron concentration of the RWST should be verified to be within the required limits. This SR ensures that the reactor will remain subcritical following a LOCA. Further, it assures that the resulting sump pH will be maintained in an acceptable range so that boron precipitation in the core will not occur and the effect of chloride and caustic stress corrosion on mechanical systems and components will be minimized. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Chapter 6 and Chapter 15.

1 1NSERT- BASES 3.5.4 Reference Farley Units 1 and 2 B 3.5.4-6 I Revision 541 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.5.4 Reference

2. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages ECCS Recirculation Fluid pH Control System 8 3.5 .6 BASES APPLICABILITY In MODES 5, and 6, the probability and consequences of an event (continued) requiring the ECCS Recirculation Fluid pH Control System are reduced due to the pressure and temperature limitations in these MODES.

Thus, the ECCS Recirculation Fluid pH Control System is not required OPERABLE in MODES 5 and 6.

ACTIONS With the ECCS Recirculation Fluid pH Control System inoperable, the system must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The ability to adjust the recirculation fluid pH to the required range and the resulting iodine retention and corrosion protection may be reduced in this condition. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is based on the passive nature of the system design and the low probability of an event occurring during this time that would require the ECCS Recirculation Fluid pH Control System function.

B.1 and B.2 If the ECCS Recirculation Fluid pH C ntrol System cannot be restored to OPERABLE status within the req ed Com letion Time, the unit must be placed in a MODE in which . To ust be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in MOD within hours. The allowed Completion Time 4 of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is reas able, based on op ting experience, to reach MODE 3 from full power conditions in an orderly manner without challenging plant systems . The extende interval to reach MODE !51~

allows additional time for restoration of the system and is reasonable considering that the driving force for a rele e of radioactive material from the RCS is reduced in MODE 3. INSERT- BASES 3.5 .6 Condition B SURVEILLANCE SR 3.5.6.1 REQUIREMENTS In order to achieve the desired pH range of 7.5 to 10.5 in the post-LOCA recirculation solution a total of between 10,000 pounds (185 fe) and 12,900 pounds (215 fe) of TSP (or appropriate weights/volumes for equivalent compounds) is required. A visual inspection is performed to verify the structural integrity and content volume of the Farley Units 1 and 2 B 3.5.6-4 I ~evisi011 0 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.5.6 Condition 8 Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 3). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 3, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8 .2 is modified by a Note that states that LCO 3.0.4 .a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude , changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages ECCS Recirculation Fluid pH Control System 8 3.5.6 BASES SURVEILLANCE SR 3.5.6.1 (continued)

REQUIREMENTS three TSP storage baskets. The baskets are marked with a minimum and maximum fill level that corresponds to a total TSP volume of between 185 fe and 215 fe. The verification that the storage baskets contain the required amount of trisodium phosphate is accomplished by verifying that the TSP level is between the indicated fill marks on the baskets. The intent of the surveillance requirement is to verify containment of the TSP by visual inspection. Therefore, broken, crimped, or oxidized screen mesh is acceptable as long as the contents are contained . Also , lumps/caking is an analyzed condition .

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 6.2.

2. FSAR, Section 15.

~

V ! INSERT- BASES 3.5.6

!Reference Farley Units 1 and 2 8 3.5.6-5 IReuision 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.5.6 Reference

3. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Containment Spray and Cooling Systems B 3.6.6 BASES APPLICABILITY In MODES 1, 2, 3, and 4, a DBA could cause a release of radioactive material to containment and an increase in containment pressure and temperature requiring the operation of the containment spray trains and containment cooling trains.

In MODES 5 and 6, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES. Thus, the Containment Spray System and the Containment Cooling System are not required to be OPERABLE in MODES 5 and 6.

ACTIONS With one containment spray train inoperable, the inoperable containment spray train must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In this Condition, the remaining OPERABLE spray and cooling trains are adequate to perform the iodine removal and containment cooling functions. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time takes into account the redundant heat removal capability afforded by the Containment Spray System, reasonable time for repairs, and low probability of a DBA occurring during this period .

The 10 day portion of the Completion Time for Required Action A.1 is based upon engineering judgment. It takes into account the low probability of coincident entry into two Conditions in this Specification coupled with the low probability of an accident occurring during this time. Refer to Section 1.3, "Completion Times," for a more detailed discussion of the purpose of the "from discovery of failure to meet the LCO" portion of the Completion Time.

B.1 and B.2 If the inoperable containment spray t in cannot be restored to OPERABLE status within the require Completion Time, the plant must be brought to a MODE in whichl~e:l;~i=E~Etes:=flet=ai~f;l To 4

achieve this status, the pia 1 must be roug t to at east 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MOD withi ~ hours. The allowed Com letion Time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is rea nable, ba on operating 54 experience, to reach MODE 3 from full power c nditions in an orderly manner and without challenging plant systems. The extended interval INSERT - BASES 3.6.6 Condition B (continued)

Farley Units 1 and 2 B 3.6.6-6 I Revisior1 8 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.6.6 Condition B Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 7). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 7, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Containment Spray and Cooling Systems B 3.6.6 BASES ACTIONS 8.1 and 8.2 (continued) ~ 48 h ours to res tore ~

M~allows7eitieRal 4

to reach time fer attem tiRg resteratioR ofl the containment spray train ~ is reasonable when considering the driving force for a release radioactive material from the Reactor CoolantS stem is reduced in MODE 3.

to OPERABLE status in MODE 3. This C.1 With one of the required containment cooling trains inoperable, the inoperable required containment cooling train must be restored to OPERABLE status within 7 days. The components in this degraded condition provide iodine removal capabilities and are capable of providing at least 100% of the heat removal needs. The 7 day Completion Time was developed taking into account the redundant heat removal capabilities afforded by combinations of the Containment Spray System and Containment Cooling System and the low probability of DBA occurring during this period .

The 10 day portion of the Completion Time for Required Action C.1 is based upon engineering judgment. It takes into account the low probability of coincident entry into two Conditions in this Specification coupled with the low probability of an accident occurring during this time. Refer to Section 1.3 for a more detailed discussion of the purpose of the "from discovery of failure to meet the LCO" portion of the Completion Time.

With two required containment cooling trains inoperable, one of the required containment cooling trains must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The components in this degraded condition provide iodine removal capabilities and are capable of providing at least 100% of the heat removal needs after an accident. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time was developed taking into account the redundant heat removal capabilities afforded by combinations of the Containment Spray System and Containment Cooling System, the iodine removal function of the Containment Spray System, and the low probability of DBA occurring during this period.

(continued)

Farley Units 1 and 2 B 3.6.6-7 I Revisi011 8 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages Containment Spray and Cooling Systems B 3.6.6 BASES ACTIONS E.1 and E.2 overall plant risk is (continued) reduced .

If the Required Action and asso iated Completion Time of Condition C or D of this LCO are not met, t plant must be brought to a MODE in which . To achieve this status, the plao ust

~ ~ brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE ~ 1thin L:J ~ hours. The allowed Completion Times are reasonable, based on operating xperience, to reach the required plant conditions from full power con itions in an orderly manner and without challenging plant systems.

INSERT - BASES 3.6.6 ConditionE With two containment spray trains or any combination of three or more containment spray and cooling trains inoperable, the unit is in a condition outside the accident analysis. Therefore, LCO 3.0.3 must be entered immediately.

SURVEILLANCE SR 3.6.6.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, and automatic valves in the containment spray flow path provides assurance that the proper flow paths will exist for Containment Spray System operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these were verified to be in the correct position prior to locking, sealing, or securing. This SR does not require any testing or valve manipulation. Rather, it involves verification, through a system walkdown, that those valves outside containment (only check valves are inside containment) and capable of potentially being mispositioned are in the correct position .

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.6.6.2 Operating each required containment cooling train fan unit for 2: 15 minutes ensures that all trains are OPERABLE and that all associated controls are functioning properly. It also ensures that blockage, fan or motor failure, or excessive vibration can be detected for corrective action. The fans are started from the control room (unless already operating). The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

Farley Units 1 and 2 B 3.6.6-8 IRevisioR 52 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.6.6 Condition E Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 7). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth . As stated in Reference 7, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplan ned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action E.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to , and the Note does not preclude , changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Containment Spray and Cooling Systems B 3.6.6 BASES REFERENCES 5. FSAR, Section 15.

(continued)

6. ASME Code for Operation and Maintenance of Nuclear Power Plants.

INSERT- BASES 3.6.6 Reference Farley Units 1 and 2 B 3.6.6-11 IRevisi011 45 l o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.6.6 Reference

7. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages CCWSystem B 3.7.7 BASES APPLICABILITY In MODES 1, 2, 3, and 4, the CCW System is a normally operating system, which must be prepared to perform its post accident safety functions, primarily RCS heat removal, which is achieved by cooling the RHR heat exchanger.

In MODE 5 or 6, the OPERABILITY requirements of the CCW System are determined by the systems it supports.

ACTIONS Required Action A.1 is modified by a Note indicating that the applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," be entered if an inoperable CCW train results in an inoperable RHR loop. This note is only applicable in MODE 4. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components.

If one CCW train is inoperable, action must be taken to restore OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In this Condition , the remaining OPERABLE CCW train is adequate to perform the heat removal function. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable, based on the redundant capabilities afforded by the OPERABLE train, and the low probability of a DBA occurring during this period .

B.1 and B.2 overall plant risk is If the CCW train cannot be restored to OPERABLE status within the reduced . asso

ted Com letion Time, the unit must be placed in a MODE in which . To achieve this status, the ~nj~

f121-.-..., ~placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in MODE 15:J1Nithin 6 t...:...=J ~ hours. Jhe allowed Completion Times are reasonable, based on operating xperience, to reach the required unit conditions from full power con itions in an orderly manner and without challenging unit systems. INSERT- BASES 3.7.7 Condition B Farley Units 1 and 2 B 3.7.7-3 I Re~ision 0 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.7 Condition 8 Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 2) . In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 2, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages CCWSystem B 3.7.7 BASES SURVEILLANCE SR 3.7.7.3 REQUIREMENTS (continued) This SR verifies proper automatic operation of the CCW pumps on an actual or simulated actuation signal. The CCW System is a normally operating system that cannot be fully actuated as part of routine testing during normal operation. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 9.2.2.

~INSERT- BASES 3.7.7 Reference Farley Units 1 and 2 B 3.7.7-5 IRevision 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.7 Reference

2. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

Enclosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages sws B 3.7.8 BASES ACTIONS If one SWS train is inoperable, action must be taken to restore OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In this Condition, the remaining OPERABLE SWS train is adequate to perform the heat removal function. However, the overall reliability is reduced because a single failure in the OPERABLE SWS train could result in loss of SWS function. Required Action A.1 is modified by two Notes. The first Note indicates that the applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources- Operating," should be entered if an inoperable SWS train results in an inoperable emergency diesel generator. The second Note indicates that the applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," should be entered if an inoperable SWS train results in an inoperable decay heat removal train. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is based on the redundant capabilities afforded by the OPERABLE train, and the low probability of a DBA occurring during this time period.

With one automatic turbine building isolation valve inoperable in each SWS train, the inoperable valves must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . With the unit in this condition, the remaining OPERABLE SWS turbine building isolation valves in each train are adequate to perform the SWS non-essential load isolation function; however, the overall reliability of the function is reduced . The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is based on the fact that the remaining OPERABLE automatic turbine building isolation valves in each SWS train ensure the SWS trains remain fully capable of performing the required safety function and the low probability of an event occurring during this time period that would require the isolation function of these valves.

C.1 and C.2 overall plant risk is reduced .

If the SWS train cannot be restor d to OPERABLE status within the associated ComQ!etion Time, th unit must be placed in a MODE in whichlthe LCO dt)es not apply .1 o achieve this status, the unit must f12h. \ ~ placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in M~ ElDwithin

~ ~ hours. ~*

r.:lN""7:S::-::E::-:R::-:T::-_---:B::-A:-:S::-:E::-::S::-3=-.=-7.8 Condition C (continued)

Farley Units 1 and 2 B 3.7.8-3 l Revisio11 0 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.8 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 4) . In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 4, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to , and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are requ ired to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages sws 8 3.7.8 BASES SURVEILLANCE SR. 3.7.8.3 REQUIREMENTS (continued) This SR verifies proper automatic operation of the SWS pumps on an actual or simulated actuation signal. The SWS is a normally operating system that cannot be fully actuated as part of normal testing during normal operation. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.8.4 This SR requires a visual inspection be made of the ground area immediately surrounding the SWS buried piping. The performance of a visual inspection of the ground provides an indication of SWS piping integrity (leak tightness) by monitoring the surrounding ground for excessive moisture or erosion. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 9.2.1.

2. FSAR, Section 6.2.

3. FSAR, Section 5.1.

b

~INSERT- Reference BASES 3.7.8 Farley Units 1 and 2 8 3.7.8-5 l Revisi011 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.8 Reference

4. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

Enclosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages UHS B 3.7.9 BASES LCO The UHS is required to be OPERABLE and is considered OPERABLE if it contains a sufficient volume of water at or below the maximum temperature that would allow the SWS to operate for at least 30 days following the design basis LOCA without the loss of net positive suction head (NPSH) , and without exceeding the maximum design temperature of the equipment served by the SWS. To meet this condition, the UHS temperature should not exceed 95°F and the level should not fall below 184 ft mean sea level during normal unit operation.

APPLICABILITY In MODES 1, 2, 3, and 4, the UHS is required to support the OPERABILITY of the equipment serviced by the UHS and required to be OPERABLE in these MODES.

In MODE 5 or 6, the OPERABILITY requirements of the UHS are determined by the systems it supports.

ACTIONS A.1 and A.2 overall plant risk is reduced .

If the UHS water level or temperature are not with the re uired limits the unit must be placed in a MODE in which ~~~~~::!!§~

~ To achieve this status, the unit must be placed in at least INSERT - BASES 3.7.9 MODE ~ ithin ours and in MODE~ 'thin §ftj~ou '!:,....

Condition A 3 42 4 *~

The allowed ompletion imes are reasonab e, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.9.1 REQUIREMENTS This SR verifies that adequate long term (30 day) cooling can be maintained. The specified level also ensures that sufficient NPSH is available to operate the SWS pumps. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program . This SR verifies that the UHS water level is ~ 184 ft mean sea level.

(continued)

Farley Units 1 and 2 B 3.7.9-2 IRevisi011 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.9 Condition A Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 3) . In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 3, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action A.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages UHS B 3.7.9 BASES SURVEILLANCE SR 3.7.9.2 REQUIREMENTS (continued) This SR verifies that the SWS is available to cool the CCW System to at least its maximum design temperature with the maximum accident or normal design heat loads for 30 days following a Design Basis Accident. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This SR verifies that the water temperature at the discharge of the Service Water Pumps is 5 95°F.

REFERENCES 1. FSAR, Section 9.2.5.

2. Regulatory Guide 1.27.

~

Farley Units 1 and 2 B 3.7.9-3 IReoisi011 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.9 Reference

3. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Control Room I B 3.7.10 BASES ACTIONS C.1 and C.2 (continued) r.----:-:--:------:~----:---"~ ln MODE 1, 2, 3, or 4, if an inoperable CREFS train or CRE cannot be in which overall plant restored to OPERABLE status within the required Completion Time, risk is reduced . or if o CREFS trains are inoperable, the unit must be placed in a I MOD ~hat mini!!lizes aeeidenrrisk.l To achieve this status, the unit ..----f4l

~,be Pfacea m at feasf MOOE 3" within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE ~ L.......l L:..=.J withtitla61 hours. he allowed Completion Times are reasonable, based on operati experience, to reach the required unit conditions from full power con "tions in an orderly manner and without challenging unit syste s. INSERT- BASES 3.7.10 Condition C D.1. D.2.1. and D.2.2 During movement of irradiated fuel assemblies or during CORE ALTERATIONS, if an inoperable CREFS train cannot be restored to I OPERABLE status within the required Completion Time, action must be taken to immediately place the OPERABLE CREFS train in the emergency recirculation mode. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure would be readily detected.

An alternative to Required Action D.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes risk. This does not preclude the movement of fuel to a safe position .

E.1 and E.2 During movement of irradiated fuel assemblies or during CORE ALTERATIONS, if an inoperable CRE cannot be restored to OPERABLE status within the required Completion Time or with two CREFS trains inoperable, action must be taken to immediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes accident risk. This does not preclude the movement of fuel to a safe position.

Farley Units 1 and 2 B 3.7.10-6 I RevisieA 271 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.10 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 5). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 5, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Control Room B 3.7.10 BASES SURVEILLANCE SR 3.7.10.4 (continued)

REQUIREMENTS CRE would be entered but the Condition for an inoperable CREFS would not be entered . An inoperable CRE does not render the CREFS inoperable or vice versa. The frequency of 24 months on a STAGGERED TEST BASIS is adequate and has been shown to be acceptable by operating experience.

Any change in the components being tested by this SR will require reevaluation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program.

SR 3.7.10.5 This SR verifies the integrity of the CRE by requiring testing for control room in leakage. The details of the in leakage testing are contained in the CRIP.

REFERENCES 1. FSAR, Section 6.4.

2. FSAR, Chapter 15.

3. Regulatory Guide 1.52, Rev. 3.

4. ASME N510-1989.

~

Farley Units 1 and 2 B 3.7.10-8 l Revisio11 59l o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.10 Reference

5. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages CRAGS B 3.7.11 BASES ACTIONS B.1 and B.2 (continued)

C.1, C.2.1, and C.2.2 Condition B During movement of irradiated fuel, or during CORE ALTERATIONS ,

if the inoperable CRAGS train cannot be restored to OPERABLE status within the required Completion Time, the OPERABLE CRAGS train must be placed in operation immediately. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that active failures will be readily detected.

An alternative to Required Action C.1 is to immediately suspend activities that present a potential for releasing radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes accident risk. This does not preclude the movement of fuel to a safe position.

D.1 and D.2 During movement of irradiated fuel assemblies, or during CORE ALTERATIONS, with two CRAGS trains inoperable, action must be taken immediately to suspend activities that could result in a release of radioactivity that might require isolation of the control room . This places the unit in a condition that minimizes risk. This does not preclude the movement of fuel to a safe position .

If both CRAGS trains are inoperable in MODE 1, 2, 3, or 4, the control room CRAGS may not be capable of performing its intended function.

Therefore, LCO 3.0.3 must be entered immediately.

Farley Units 1 and 2 8 3.7.11-3 I Re'iiision 0 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.11 Condition 8 Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 2). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 2, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages CRAGS B 3.7.11 BASES SURVEILLANCE SR 3.7.11.1 REQUIREMENTS This SR verifies that the heat removal capability of the system is sufficient to remove the heat load assumed in the safety analyses in the control room . This SR consists of system testing. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 6.4.

~INSERT - BASES 3.7.11 Reference Farley Units 1 and 2 B 3.7.11-4 IRe*wisieR 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.11 Reference

2. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages PRF B 3.7.12 BASES ACTIONS (continued)

If the PRF system is inoperable due to a penetration room boundary being inoperable in MODE 1, 2, 3, or 4, the PRF trains cannot perform their intended functions. Actions must be taken to restore the PRF boundary within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . During the period the PRF boundary is inoperable, appropriate compensatory measures (consistent with the intent of GDC 19) should be utilized to protect control room operators from potential radiological hazards. Preplanned measures should be available to address these concerns for intentional and unintentional entry into the condition . The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time for the post LOCA mode of operation is reasonable based on the low probability of a DBA occurring during this time period, and the use of compensatory measures. It provides a reasonable time to diagnose, plan and possibly repair, and test most problems with the PRF boundary.

C.1 and C.2 overall plant risk is reduced .

In MODE 1, 2, 3, or 4, when Required Action A.1 or B.1 cannot e completed within the associated Completion Time, or when both RF trains are ino12erable, the unit must be placed in a MODE in whicti ~

lLGO eloes Aot applv.l To achieve this status, the unit must be placed in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MOD withi hours. The Completion Times are reasonable, bas on op ating exp ience, to reach the required unit conditions fro full po r condition in an orderly manner and without challengi g unit s stems.

4 12 ...,.,IN"""s=-=E=R=T:::-_-:B:::-:A,.&:S=E=s-=3-=.7:::--.-:

12,----,

D.1 and D.2 When Required Action A.1 cannot be completed within the required Completion Time, during movement of irradiated fuel assemblies in the spent fuel pool room, the OPERABLE PRF train must be started immediately or fuel movement suspended . This action ensures that the remaining train is OPERABLE, that no undetected failures preventing system operation will occur, and that any active failure will be readily detected.

If the system is not placed in operation, this action requires suspension of fuel movement, which precludes a fuel handling accident. This does not preclude the movement of fuel assemblies to a safe position .

(continued)

Farley Units 1 and 2 B 3.7.12-4 I~evlslon 2 I I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.12 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 7). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 7, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages PRF B 3.7.12 BASES SURVEILLANCE SR 3.7.12.5 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.12.6 During the fuel handling mode of operation, the PRF is designed to maintain a slightly negative pressure in the spent fuel pool room with respect to atmospheric pressure and surrounding areas at a flow rate of~ 5,500 cfm, to prevent unfiltered leakage. The slightly negative pressure is verified by using a non-rigorous method that yields some observable identification of the slightly negative pressure. Examples of non-rigorous methods are smoke sticks, hand held differential pressure indicators, or other measurement devices that do not provide for an absolute measurement. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 6.2.3.

2. FSAR, Section 9.4.2.

3. FSAR, Sections 15.4.1 and 15.4.5.

4. Regulatory Guide 1.25.

5. 10 CFR 100.

6. ASME N510-1989.

~INSERT- BASES 3.7.12

~Reference Farley Units 1 and 2 B 3.7.12-7 I Reuision Szl o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.12 Reference

7. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages ESF Room Coolers B 3.7.19 BASES ACTIONS A.1 (continued)

If one train of a required ESF Room Cooler subsystem is inoperable, action must be taken to restore the subsystem train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In this Condition, the remaining OPERABLE ESF Room Cooler subsystem train is adequate to perform the heat removal function for its associated ESF equipment.

B.1 and B.2 Condition B SURVEILLANCE SR 3.7.19.1 REQUIREMENTS Verifying the correct alignment for manual valves servicing safety-related equipment provides assurance that the proper flow paths exist for ESF Room Cooler operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since they are verified to be in the correct position prior to being locked, sealed, or secured. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned ,

such as check valves.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

Farley Units 1 and 2 B 3.7.19-5 I~evision ~2 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3. 7.19 Condition 8 Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 2). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 2, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages ESF Room Coolers B3.7.19 BASES SURVEILLANCE SR 3.7.19.2 REQUIREMENTS (continued) This SR verifies proper operation of the ESF Room Cooler fans on an actual or simulated actuation signal. Depending on the room cooler, this may be manual, high room temperature, an equipment running signal, or some combination. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Each Room Cooler Fan can be placed in Run mode locally. With the Room Cooler in the Run mode, all automatic functions are being met and the Room Cooler is considered OPERABLE.

REFERENCES 1. FSAR, Section 9.4.

~INSERT- BASES 3.7.19 Reference Farley Units 1 and 2 B 3.7.19-6 IRe~tision 52 1 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.7.19 Reference

2. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages AC Sources- Operating B 3.8.1 BASES ACTIONS (continued)

Condition F provides the default Required Actions for the Conditions which address two inoperable offsite circuits or two inoperable DG sets. If the inoperable AC Sources cannot be restored to OPERABLE status within the applicable Completion Time, Required Action F.1 specifies that the unit be placed in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Once shut down, the unit is in a more stable condition and the time allowed to remain in MODE 3 is ultimately limited by the Required Actions and Completion Times applicable to a single inoperable AC Source based on the time that an AC Source initially became inoperable. In addition, the Required Actions applicable to one inoperable DG set or offsite circuit would remain applicable until both inoperable DG sets or offsite circuits are restored to OPERABLE status or the unit is placed in a MODE in which the LCO does not apply (MODE 5) . The allowed Completion Times are reasonable to reach the required unit conditions from full power in an orderly manner and without challenging plant systems.

The sequencer(s) B1F, B2F, 81G, and B2G are an essential support system to both the offsite circuit and the DG associated with a given ESF bus. Furthermore, the sequencer is on the primary success path for most major AC electrically powered safety systems powered from the associated ESF bus. Therefore, loss of an ESF bus sequencer affects every major ESF system in the train. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time provides a period of time to correct the problem commensurate with the importance of maintaining sequencer OPERABILITY. This time period also ensures that the probability of an accident (requiring sequencer OPERABILITY) occurring during periods when the sequencer is inoperable is minimal.

H.1 and H.2 (continued)

Farley Units 1 and 2 8 3.8.1-15 I Re oision 0 l o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.8.1 Condition H Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 13). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 13, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action H.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages AC Sources- Operating B 3.8.1 BASES REFERENCES 6. Regulatory Guide 1.93, Rev. 0, December 1974.

(continued)

7. Generic Letter 84-15, "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability," July 2, 1984.

8. 10 CFR 50, Appendix A, GDC 18.

9. Regulatory Guide 1.108, Rev. 1, August 1977.

10. ASME, Boiler and Pressure Vessel Code,Section XI.

11. IEEE Standard 308-1971 .

12. NEMA MG1-1967.

~

' Z JINSERT - BASES 3.8.1

!Reference Farley Units 1 and 2 B 3.8.1-29 I Revision 0 I o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.8.1 Reference

13. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs ," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages DC Sources- Operating B 3.8.4 BASES ACTIONS B.1 and D.1 (continued)

Conditions B and D represent one Auxiliary Building or SWIS DC electrical power subsystem with connection resistance not within the specified limit. Consistent with the guidance in IEEE-450, connection resistance not within the limit is an indication that the affected battery requires attention to restore the resistance to within the limit but is not a basis on which to declare the battery inoperable. Therefore, the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time allowed to restore the battery connection resistance to within the required limit is a reasonable time considering that variations in connection resistance do not mean the battery is incapable of performing its required safety function, but is an indication that the battery requires maintenance.

C.1 and C.2 INSERT - BASES 3.8.4 Condition C If a required SWIS DC electrical power subsystem is inoperable or the connection resistance is not restored to within the limit and the associated Completion Time has expired, the Service Water System train supported by the affected SWIS DC electrical power subsystem must be declared inoperable. The capability of the affected SWIS DC electrical power subsystem to fully support the associated train of Service Water is not assured. Therefore, consistent with the definition of OPERABILITY, the associated train of Service Water must be declared inoperable immediately, thereby limiting operation in this condition to the Completion Time associated with the affected Service Water System train .

(continued)

Farley Units 1 and 2 B 3.8.4-6 !Revision zsll o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.8.4 Condition C Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 11 ). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 11 , the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action , there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action C.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components , consideration of the results , determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to , and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages DC Sources- Operating B 3.8.4 BASES (continued)

REFERENCES 1. 10 CFR 50, Appendix A, GDC 17.

2. Regulatory Guide 1.6, March 10, 1971 .

3. IEEE-308-1971 .

4. FSAR, Section 8.3.

5. None.

6. FSAR, Chapter 6.

7. FSAR, Chapter 15.

8. Regulatory Guide 1.93, December 1974.

9. IEEE-450-1980.

10. Regulatory Guide 1.32, February 1972.

~

\ TINSERT - BASES 3.8.4

!Reference Farley Units 1 and 2 B 3.8.4-11 IRevisiOI 1 2511 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.8.4 Reference 11 . WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs," June 2010.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Inverters- Operating B 3.8.7 BASES ACTIONS A.1 (continued) is powered from its constant voltage source, it is relying upon interruptible AC electrical power sources (offsite and onsite). The uninterruptible inverter source to the AC vital buses is the preferred source for powering instrumentation trip setpoint devices.

B.1 and B.2 If the in opera OPERABLE be brought to in whicH . To achieve this status, t t be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE within hours. The allowed Completion Times are reasonable, based on operating xperience, to reach the required unit conditions from full power con tions in an orderly manner and without challenging plant systems. INSERT- BASES 3.8.7 Condition B SURVEILLANCE SR 3.8.7.1 REQUIREMENTS This Surveillance verifies that the inverters are functioning properly with all required circuit breakers closed and AC vital buses energized from the inverter. The verification of proper voltage and frequency output ensures that the required power is readily available for the instrumentation of the RPS and ESFAS connected to the AC vital buses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Chapter 8.

2. FSAR, Chapter 6.

3. FSAR, Chapter 15.

~INSERT - BASES 3.8.7 Reference Farley Units 1 and 2 B 3.8.7-4 IRevisior 1 52 1

Endosure 3 o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.8. 7 Condition B Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 4). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 4, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action 8.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT - BASES 3.8.9 Condition D Remaining within the Applicability of the LCO is acceptable to accomplish short duration repairs to restore inoperable equipment because the plant risk in MODE 4 is similar to or lower than MODE 5 (Ref. 4). In MODE 4 the Steam Generators and Residual Heat Removal System are available to remove decay heat, which provides diversity and defense in depth. As stated in Reference 4, the steam turbine driven Auxiliary Feedwater Pump must be available to remain in MODE 4. Should Steam Generator cooling be lost while relying on this Required Action, there are preplanned actions to ensure long-term decay heat removal. Voluntary entry into MODE 5 may be made as it is also acceptable from a risk perspective.

Required Action D.2 is modified by a Note that states that LCO 3.0.4.a is not applicable when entering MODE 4. This Note prohibits the use of LCO 3.0.4.a to enter MODE 4 during startup with the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate. LCO 3.0.4 is not applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

o NL-14-1531 Marked-Up Technical Specifications Bases Pages Distribution Systems- Operating B 3.8.9 BASES ACTIONS (continued)

With two trains with inoperable distribution subsystems that result in a foss of safety function, adequate core cooling, containment OPERABILITY and other vital functions for DBA mitigation would be compromised, and immediate plant shutdown in accordance with LCO 3.0.3 is required.

SURVEILLANCE SR 3.8.9.1 REQUIREMENTS This Surveillance verifies that the required AC, DC, and AC vital bus electrical power distribution systems are functioning properly, with the correct circuit breaker alignment. The correct breaker alignment ensures the appropriate separation and independence of the electrical divisions is maintained, and the appropriate voltage is available to each required bus. The verification of proper voltage availability on the buses ensures that the required voltage is readily available for motive as well as control functions for critical system loads connected to these buses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Any change in the components being tested by this SR will require reevaluation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program .

REFERENCES 1. FSAR, Chapter 6.

2. FSAR, Chapter 15.

3. Regulatory Guide 1.93, December 1974.

~

'\. !INSERT - BASES 3.8 .9

!Reference F arfey Units 1 and 2 B 3.8.9-9 IRe~tision ss l o NL-14-1531 Marked-Up Technical Specifications Bases Pages INSERT- BASES 3.8.9 Reference

4. WCAP-16294-NP-A, Rev. 1, "Risk-Informed Evaluation of Changes to Technical Specification Required Action Endstates for Westinghouse NSSS PWRs ," June 2010.

Joseph M. Farley Nuclear Plant- Units 1 and 2 License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294),

Using the Consolidated Line Item Improvement Process Enclosure 4 Clean-Typed Technical Specifications Pages to NL-14-1531 Clean-Typed Technical Specifications Pages ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1 .

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more required referenced in channels or trains Table 3.3.2-1 for the inoperable. channel(s) or train(s).

B. One channel or train B.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

OR

. B.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE4. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months Farley Units 1 and 2 3.3.2-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

c. One train inoperable. C.1 -------------NOTE-----------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR C.2.1 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND C.2.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. One channel inoperable. D.1 -------------NOTE-----------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR D.2.1 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND D.2.2 Be in MODE 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months Farley Units 1 and 2 3.3.2-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages CREFS Actuation Instrumentation 3.3.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place both CREFS trains Immediately in emergency recirculation mode.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. C.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Required Action and D.1 Suspend CORE Immediately associated Completion ALTERATIONS.

Time for Condition A or B not met during AND movement of irradiated fuel assemblies or D.2 Suspend movement of Immediately during CORE irradiated fuel assemblies.

ALTERATIONS.

SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

Refer to Table 3.3.7-1 to determine which SRs apply for each CREFS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2 Perform COT. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.3.7-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A. 1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits within limits.

for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 ------------NOTE-----------

OR LCO 3.0.4.a is not applicable when entering Pressure boundary MODE4.

LEAKAGE exists. --------------------------------

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Primary to secondary LEAKAGE not within limit.

Farley Units 1 and 2 3.4.13-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND A.2 Isolate the high pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AND met.

B.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. RHR System C.1 Place the affected valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months autoclosure or open in the closed position and permissive interlock maintain closed under function inoperable. administrative control.

Farley Units 1 and 2 3.4.14-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages RCS Leakage Detection Instrumentation 3.4.15 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND D.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. All required monitors E.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required In accordance with containment atmosphere radioactivity monitor. the Surveillance Frequency Control Program SR 3.4.15.2 Perform COT of the required containment In accordance with atmosphere radioactivity monitor. the Surveillance Frequency Control Program SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required In accordance with containment atmosphere radioactivity monitor. the Surveillance Frequency Control Program SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required In accordance with containment air cooler condensate level monitor. the Surveillance Frequency Control Farley Units 1 and 2 3.4.15-3 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES-----------------------------------------------------------

1. RWST piping may be unisolated from non-safety related piping for ~ 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months under administrative controls to perform SR 3.5.4.3.*

2. RWST piping may be unisolated from non-safety related piping for ~ 30 days per fuel cycle under administrative controls for filtration or silica removal.*

CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.1 Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

OR RWST borated water temperature not within limits.

B. RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

These Notes can only be applied during the next two fuel Cycles for each Unit.

These Notes cannot be used after Refueling Outages 1R26 (Spring 2015) and 2R24 (Spring 2016).

Farley Units 1 and 2 3.5.4-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages RWST 3.5.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -----------------------------N 0 TE------------------------------

Only required to be performed when ambient air temperature is< 35°F.

Verify RWST borated water temperature is~ 35°F. In accordance with the Surveillance Frequency Control Program SR 3.5.4.2 Verify RWST borated water volume is~ 471,000 In accordance with gallons. the Surveillance Frequency Control Program SR 3.5.4.3 Verify RWST boron concentration is ~ 2300 ppm and In accordance with

~ 2500 ppm. the Surveillance Frequency Control Program Farley Units 1 and 2 3.5.4-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages ECCS Recirculation Fluid pH Control System 3.5.6 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 ECCS Recirculation Fluid pH Control System LCO 3.5.6 The ECCS Recirculation Fluid pH Control System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ECCS Recirculation Fluid A.1 Restore system to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pH Control System OPERABLE status.

inoperable.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE4. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.6.1 Perform a visual inspection of the ECCS In accordance with Recirculation Fluid pH Control System and verify the the Surveillance following: Frequency Control Program

a. Three (3) storage baskets are in place, and

b. Have maintained their integrity, and

c. Each basket is filled with trisodium phosphate compound such that the level is between the indicated fill marks on the baskets.

Farley Units 1 and 2 3.5.6-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable. spray train to OPERABLE status. AND 10 days from discovery of failure to meet the LCO B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE4. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months

c. One containment cooling C.1 Restore containment 7 days train inoperable. cooling train to OPERABLE status. AND 10 days from discovery of failure to meet the LCO Farley Units 1 and 2 3.6.6-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL 1531 Clean-Typed Technical Specifications Pages Containment Spray and Cooling Systems 3.6.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I

D. Two containment cooling D.1 Restore one containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trains inoperable. cooling train to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C or D AND not met.

E.2 ---------NOTE---------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. Two containment spray F.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power In accordance with operated, and automatic valve in the flow path that is the Surveillance not locked, sealed, or otherwise secured in position is Frequency Control in the correct position . Program SR 3.6.6.2 Operate each required containment cooling train fan In accordance with unit for 2:: 15 minutes. the Surveillance Frequency Control Program SR 3.6.6.3 Verify each containment cooling train cooling water In accordance with flow rate is 2:: 1600 gpm. the Surveillance Frequency Control Program Farley Units 1 and 2 3.6.6-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages CCWSystem 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A One CCW train A.1 ------------NOTE-------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4,"

for residual heat removal loops made inoperable by ccw.

Restore CCW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 ----------NOTE----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Farley Units 1 and 2 3.7.7-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages sws 3.7.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C. 2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 ------------------------------NOTE-------------------------------

Isolation of SWS flow to individual components does not render the SWS inoperable.

Verify each accessible SWS manual, power In accordance with operated, and automatic valve in the flow path the Surveillance servicing safety related equipment, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.7.8.2 Verify each SWS automatic valve in the flow path that In accordance with is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the correct position on an actual Frequency Control or simulated actuation signal. Program SR 3.7.8.3 Verify each SWS pump starts automatically on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.7.8.4 Verify the integrity of the SWS buried piping by visual In accordance with inspection of the ground area. the Surveillance Frequency Control Program Farley Units 1 and 2 3.7.8-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages UHS 3.7.9

3. 7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS (Service Water Pond) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS water level or A.1 Be in MODE 3. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months temperature not within the required limit(s). AND A. 2 -----------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE 4. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is ?:: 184 ft In accordance with mean sea level . the Surveillance Frequency Control Program SR 3.7.9.2 Verify water temperature of .:5 95°F at the discharge In accordance with of the Service Water Pumps the Surveillance Frequency Control Program Farley Units 1 and 2 3.7.9-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages Control Room 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or4.

C.2 ------------NOTE-----------

LCO 3.0.4.a is not OR applicable when entering MODE4.

Two CREFS trains inoperable in MODE 1, 2, 3, or 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Be in MODE4.

D. Required Action and D.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A not recirculation mode.

met during movement of OR irradiated fuel assemblies or during CORE ALTERATIONS. D.2.1 Suspend CORE Immediately ALTERATIONS.

AND D.2.2 Suspend movement of Immediately irradiated fuel assemblies.

Farley Units 1 and 2 3.7.10-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages CRAGS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRAGS)

LCO 3.7.11 Two CRAGS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies, During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAGS train A.1 Restore CRAGS train to 30 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or4. B.2 -----------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE4.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. Required Action and C.1 Place OPERABLE Immediately associated Completion CRAGS train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies or during CORE C.2.1 Suspend CORE Immediately ALTERATIONS. ALTERATIONS.

AND C.2.2 Suspend movement of Immediately irradiated fuel assemblies.

Farley Units 1 and 2 3.7.11-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages PRF 3.7.12 3.7 PLANT SYSTEMS

3. 7.12 Penetration Room Filtration (PRF) System LCO 3.7.12 Two PRF trains shall be OPERABLE.

NOTE ----------------------------------------

The PRF and Spent Fuel Pool Room (SFPR) boundaries may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, and 4 for post LOCA mode of operation, During movement of irradiated fuel assemblies in the SFPR for the fuel handling accident mode of operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One PRF train A.1 Restore PRF train to 7 days inoperable. OPERABLE status.

B. Two PRF trains B.1 Restore PRF boundary to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable in MODE 1, 2, OPERABLE status.

3, or 4 due to inoperable PRF boundary.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or4. C.2 -----------NOTE---------

LCO 3.0.4.a is not OR applicable when entering MODE4.

Two PRF trains --------------------------------

inoperable in MODE 1, 2, 3, or 4 for reasons other Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months than Condition B.

D. Required Action and D.1 Place OPERABLE PRF Immediately associated Completion train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies in the SFPR. D.2 Suspend movement of Immediately irradiated fuel assemblies in the SFPR.

Farley Units 1 and 2 3.7.12-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages ESF Room Coolers 3.7.19

3. 7 PLANT SYSTEMS 3.7.19 Engineered Safety Feature (ESF) Room Coolers LCO 3.7.19 ESF Room Coolers shall be OPERABLE.

APPLICABILITY: When associated ESF equipment is required to be OPERABLE.

ACTIONS

N0 TE-----------------------------------------------------------

Separate Condition entry is allowed for each ESF Room Cooler subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required ESF Room A.1 Restore the affected ESF 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Cooler subsystem Train Room Cooler subsystem inoperable. Train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met. AND OR B.2 ------------NOTE-----------

LCO 3.0.4.a is not Two trains of the same applicable when entering ESF Room Cooler MODE4.

subsystem inoperable.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Farley Units 1 and 2 3.7.19-1 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages AC Sources- Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. One automatic load G.1 Restore automatic load 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sequencer inoperable. sequencer to OPERABLE status.

H. Required Action and H.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, D, AND or G not met.

H.2 ------------N 0 TE-----------

LCO 3.0.4.a is not applicable when entering MODE 4 .

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I. Three or more required AC 1.1 Enter LCO 3.0.3. Immediately sources inoperable.

Farley Units 1 and 2 3.8.1-5 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages DC Sources- Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 The Train A and Train B Auxiliary Building and Service Water Intake Structure (SWIS) DC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Auxiliary Building DC A.1 Restore the Auxiliary 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power subsystem Building DC electrical inoperable. power subsystem to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for 1B OPERABLE status. Auxiliary Building DC electrical power subsystem inoperable due to inoperable battery for cycle 19 only B. One Auxiliary Building DC B.1 Restore the battery 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power subsystem connection resistance to with battery connection within limit.

resistance not within limit.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 ------------NOTE-----------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. One required SWIS DC D.1 Restore the battery 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power connection resistance to subsystem battery within the limit.

connection resistance not within limit.

Farley Units 1 and 2 3.8.4-1 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Enclosure 4 to NL-14-1531 Clean-Typed Technical Specifications Pages DC Sources- Operating 3.8.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One required SWIS DC E.1 Declare the associated Immediately electrical power subsystem Service Water System inoperable. train inoperable.

OR Required Action and associated Completion Time of Condition D not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is~ 127.8 Von float In accordance charge. with the Surveillance Frequency Control Program SR 3.8.4.2 Verify no visible corrosion at battery terminals and In accordance connectors. with the Surveillance Frequency Control Program Verify post-to-post battery connection resistance of each cell-to-cell and terminal connection is :::; 150 microhms for the Auxiliary Building batteries and

1500 microhms for the SWIS batteries.

SR 3.8.4.3 Verify battery cells, cell plates, and racks show no In accordance visual indication of physical damage or abnormal with the deterioration. Surveillance Frequency Control Program Farley Units 1 and 2 3.8.4-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages DC Sources- Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.4 Remove visible terminal corrosion, verify battery cell- In accordance with to-cell and terminal connections are coated with the Surveillance anti-corrosion material. Frequency Control Program SR 3.8.4.5 Verify post-to-post battery connection resistance of In accordance with each cell-to-cell and terminal connection is ~ 150 the Surveillance microhms for the Auxiliary Building batteries and Frequency Control

1500 microhms for the SWIS batteries Program SR 3.8.4.6 ---------------------------NOTE-----------------------------

This Surveillance may be performed in MODE 1, 2, 3, 4, 5, or 6 provided spare or redundant charger(s) placed in service are within surveillance frequency to maintain DC subsystem(s) OPERABLE.

Verify each required Auxiliary Building battery In accordance with charger supplies ~ 536 amps at ~ 125 V for ~ 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the Surveillance and each required SWIS battery charger supplies Frequency Control

~ 3 amps at~ 125 V for~ 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Program SR 3.8.4.7 ---------------------------NOTES---------------------------

1. The performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 once per 60 months.

2. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test at any time.

3. This Surveillance shall not be performed for the Auxiliary Building batteries in MODE 1, 2, 3, or4.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required the Surveillance emergency loads for the design load profile described Frequency Control in the Final Safety Analysis Report, Section 8.3.2, by Program subjecting the battery to a service test.

Farley Units 1 and 2 3.8.4-3 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages Inverters- Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

B. 2 ---------NOTE----------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and In accordance with alignment to required AC vital buses. the Surveillance Frequency Control Program Farley Units 1 and 2 3.8.7-2 Amendment No. (Unit 1)

Amendment No. (Unit 2) to NL-14-1531 Clean-Typed Technical Specifications Pages Distribution Systems- Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, or AND C not met.

D.2 --------NOTE---------- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE4.

E. One Service Water Intake E.1 Declare the associated Immediately Structure (SWIS) DC Service Water train electrical power distribution inoperable.

subsystem inoperable.

F. Two trains with inoperable F.1 Enter LCO 3.0.3. Immediately distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, DC, and AC vital bus electrical power the Surveillance distribution subsystems. Frequency Control Program Farley Units 1 and 2 3.8.9-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

v t e Letter Sequence Request
TAC:MF6118, Change in Technical Specifications End States - WCAP-16294 (Open)
Initiation Request Acceptance Administration Questions 18 August 2015 Answers Results Approval... Other:
MONTHYEAR2015-04-30 [Table View]

NL-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process

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NL-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process

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