NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2

From kanterella
Jump to navigation Jump to search

License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2
ML20304A232
Person / Time
Site: Hatch, Vogtle, Farley  Southern Nuclear icon.png
Issue date: 10/30/2020
From: Gayheart C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-20-0949
Download: ML20304A232 (68)
v • d • e


Text

Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316 cagayhea@southernco.com October 30, 2020 10 CFR 50.90 Docket Nos.: 50-321 50-348 50-424 50-366 50-364 50-425 NL-20-0949 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant; Units 1 and 2 Edwin I. Hatch Nuclear Plant; Units 1 and 2 Vogtle Electric Generating Plant; Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position" Ladies and Gentlemen:

Pursuant to 10 CFR 50.90, Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Technical Specifications (TS) for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2, and Vogtle Electric Generating Plant (VEGP), Units 1 and 2.

SNC requests adoption of TSTF-541, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position," which is an approved change to the Standard Technical Specifications (STS), into the FNP Units 1 and 2, HNP Units 1 and 2, and VEGP Units 1 and 2 Technical Specifications (TS). The proposed amendment modifies certain TS Surveillance Requirements (SRs) by adding exceptions to consider the SR met when automatic valves or dampers are locked, sealed, or otherwise secured in the actuated position, in order to consider the SR met. Securing the automatic valve or damper in the actuated position may affect the operability of the system or any supported systems. The associated Limiting Condition for Operation (LCO) is met if the subject structure, system or component (SSC) remains operable (i.e., capable of performing its specified safety function).

The enclosure provides a description and assessment of the proposed changes. Attachments 1a, 1b, and 1c provide the existing TS pages marked up to show the proposed changes.

Attachments 2a, 2b, and 2c provide revised (clean) TS pages. Attachments 3a, 3b, and 3c provide existing TS Bases pages marked to show the proposed changes for information only.

SNC requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLIIP). Approval of the proposed amendment is requested by April 30, 2021. Once approved, the amendment shall be implemented within 90 days.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Alabama and Georgia Official.

U. S. Nuclear Regulatory Commission NL-20-0949 Page 2 This letter contains no NRC commitments. If you should have any questions regarding this submittal, please contact Jamie Coleman at 205.992.6611.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 30th day of October, 2020.

Respectfully submitted, Cheryl A. Gayheart Regulatory Affairs Director CAG/DSP/scm

Enclosure:

1. Description and Assessment Attachments: 1a. FNP Proposed Technical Specification Changes (Mark-Up) 1b. HNP Proposed Technical Specification Changes (Mark-Up) 1c. VEGP Proposed Technical Specification Changes (Mark-Up) 2a. FNP Revised Technical Specification Pages 2b. HNP Revised Technical Specification Pages 2c. VEGP Revised Technical Specification Pages 3a. FNP Proposed Technical Specification Bases Changes (Mark-Up) for Information Only 3b. HNP Proposed Technical Specification Bases Changes (Mark-Up) for Information Only 3c. VEGP Proposed Technical Specification Bases Changes (Mark-Up) for Information Only cc: Regional Administrator, Region ll NRR Project Manager - Farley, Hatch, Vogtle 1 & 2 Senior Resident Inspector - Farley, Hatch, Vogtle 1 & 2 Director, Alabama Office of Radiation Control Director, Environmental Protection Division - State of Georgia RType: CGA02.001

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position" Enclosure 1 Description and Assessment to NL-20-0949 Description and Assessment

1.0 DESCRIPTION

Southern Nuclear Operating Company (SNC) requests adoption of TSTF-541, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position," which is an approved change to the Standard Technical Specifications (STS), into the Joseph M.

Farley Nuclear Plant (FNP), Units 1 and 2, Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2, and Vogtle Electric Generating Plant (VEGP), Units 1 and 2 Technical Specifications (TS). The proposed amendment modifies the TS Surveillance Requirements (SRs) by adding exceptions to consider the SR met when automatic valves or dampers are locked, sealed, or otherwise secured in the actuated position, in order to consider the SR met. Securing the automatic valve or damper in the actuated position may affect the operability of the system or of any supported systems. The associated Limiting Condition for Operation (LCO) is met if the subject structure, system or component (SSC) remains operable (i.e., capable of performing its specified safety function). The following SRs are affected by the proposed change.

FNP Units 1 and 2 Technical Specification SRs TS 3.7.10, Control Room Emergency Filtration/Pressurization System (CREFS)

TS 3.7.12, Penetration Room Filtration (PRF) System HNP Units 1 and 2 Technical Specification SRs TS 3.5.1, [Emergency Core Cooling Systems] ECCS - Operating TS 3.5.2, Reactor Pressure Vessel (RPV) Water Inventory Control TS 3.5.3, [Reactor Core Isolation Cooling] RCIC System TS 3.6.4.3, Standby Gas Treatment (SGT) System TS 3.7.2, Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)

TS 3.7.4, Main Control Room Environmental Control (MCREC) System VEGP Units 1 and 2 Technical Specification SRs TS 3.7.10, Control Room Emergency Filtration System (CREFS) - Both Units Operating TS 3.7.13, Piping Penetration Area Filtration and Exhaust System (PPAFES)

While the proposed exceptions permit automatic valves and dampers that are locked, sealed, or otherwise secured in the actuated position to be excluded from the SR in order to consider the SR met, the proposed changes will not permit a system that is made inoperable by locking, sealing, or otherwise securing an automatic valve or damper in the actuated position to be considered operable. As stated in the FNP, HNP and VEGP SR 3.0.1 Bases, "Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the SRs."

2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation SNC has reviewed the safety evaluation for TSTF-541 provided to the Technical Specifications Task Force in a letter dated December 10, 2019. This review included a review of the NRC staffs evaluation, as well as the information provided in TSTF-541. As described herein, SNC has concluded that the justifications presented in TSTF-541 and the safety evaluation prepared by the NRC staff are applicable to FNP Units 1 and 2, HNP Units 1 and 2, and VEGP Units 1 E1-1 to NL-20-0949 Description and Assessment and 2, and justify this amendment for the incorporation of the changes to the FNP, HNP and VEGP TS.

SNC acknowledges that under the proposed change, the affected valves and dampers may be excluded from the SR when locked, sealed or otherwise secured in the actuated position.

However, if the safety analysis assumes movement from the actuated position following an event, or the system is rendered inoperable by locking, sealing, or otherwise securing the valve or damper in the actuated position, then the system cannot perform its specified safety function and is inoperable regardless of whether the SR is met.

SNC acknowledges for components for which the SR allowance can be utilized, the SR must be verified to have been met within its required Frequency after removing the valve or damper from the locked, sealed or otherwise secured status. If the SR exception is utilized to not test the actuation of a valve or damper and the specified Frequency of the SR is exceeded without testing the component, the SR must be performed on the component when it is returned to service in order to meet the SR.

2.2 Variations SNC is proposing the following variations from the TS changes described in TSTF-541 or the applicable parts of the NRC staffs safety evaluation:

VEGP Unit 1 and Unit 2 TS Variations The VEGP Unit 1 and Unit 2 TS utilize different numbering and titles than the STS on which TSTF-541 was based. The following table lists the differences. These differences are administrative and do not affect the applicability of TSTF-541 to the VEGP TS.

TSTF-541 SR TS Title Equivalent VEGP Equivalent VEGP TS SR Title SR 3.7.10.3 Control Room SR 3.7.10.4 Control Room Emergency Filtration Emergency Filtration System (CREFS) System (CREFS) -

Both Units Operating SR 3.7.14.3 Penetration Room SR 3.7.14.3 Piping Penetration Exhaust Air Cleanup Area Filtration and System (PREACS) Exhaust System (PPAFES)

The VEGP Unit 1 and Unit 2 TS contain requirements that differ from the STS on which TSTF-541 was based, but these differences do not affect the applicability of the TSTF-541 justification.

Specifically, VEGP Unit 1 and Unit 2 TS do not contain SRs equivalent to the following SRs affected by TSTF-541:

E1-2 to NL-20-0949 Description and Assessment

  • SR 3.7.14.5, Penetration Room Exhaust Air Cleanup System (PREACS)

The VEGP TS contain a Surveillance Frequency Control Program. Therefore, the Frequency for the affected SRs is In accordance with the Surveillance Frequency Control Program. This has no effect on the applicability of the proposed change.

FNP Unit 1 and Unit 2 TS Variations The FNP Unit 1 and Unit 2 TS utilize different numbering and titles than the STS on which TSTF-541 was based. The following table lists the differences. These differences are administrative and do not affect the applicability of TSTF-541 to the FNP TS.

TSTF-541 SR TS Title Equivalent FNP SR Equivalent FNP TS Title SR 3.7.10.3 Control Room SR 3.7.10.3 Control Room Emergency Filtration Emergency System (CREFS) Filtration/Pressurization System (CREFS)

SR 3.7.13.3 Fuel Building Air SR 3.7.12.4* Penetration Room Cleanup System Filtration (PRF) System (FBACS)

  • The function of the STS ECCS PREACS and STS PREACS are accomplished at FNP by the Penetration Room Filtration (PRF) system. However, this FNP system also provides filtration for the spent fuel storage pool in the event of a fuel handling accident and is required operable during fuel movement as well as modes 1-4. The STS FBACS TS requirements more closely match the FNP design and licensing basis and were used as the reference for the FNP PRF system in the conversion to the Improved Technical Specifications (ITS). Therefore, FNP Unit 1 and Unit 2 TS, SR 3.7.12.4, Verify each PRF train actuates and the normal spent fuel pool room ventilation system isolates on an actual or simulated actuation signal, contains additional requirements as compared to 3.7.13.3 from NUREG-1431 Revision 4 to reflect the plant design.

This variation does not affect the applicability of TSTF-541 to FNP SR 3.7.12.4.

The FNP Unit 1 and Unit 2 TS contain requirements that differ from the STS on which TSTF-541 was based, but these differences do not affect the applicability of the TSTF-541 justification.

Specifically, FNP Unit 1 and Unit 2 do not contain SRs equivalent to the following SRs affected by TSTF-541:

  • SR 3.7.14.3, Penetration Room Exhaust Air Cleanup System (PREACS)
  • SR 3.7.14.5, Penetration Room Exhaust Air Cleanup System (PREACS)

E1-3 to NL-20-0949 Description and Assessment The FNP TS contain a Surveillance Frequency Control Program. Therefore, the Frequency for the affected SRs is In accordance with the Surveillance Frequency Control Program. This has no effect on the applicability of the proposed change.

HNP Unit 1 and Unit 2 TS Variations The HNP Unit 1 and Unit 2 TS utilize different numbering than the STS on which TSTF-541 was based. Specifically, SR 3.7.2.6, "Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)," is numbered SR 3.7.2.3 in the HNP Unit 1 and Unit 2 TS.

The HNP Unit 1 and Unit 2 TS have incorporated TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control," which had not been incorporated into the standard TS on which TSTF-541 was based. The changes in TSTF-541 are equally applicable to new SR 3.5.2.7 added by TSTF-542. Therefore, the TSTF-541 allowance is added to this SR.

The HNP Unit 1 and Unit 2 TS contain requirements that differ from the STS on which TSTF-541 was based, but these differences do not affect the applicability of the TSTF-541 justification.

Specifically, HNP Unit 1 and Unit 2 TS do not have an SR equivalent to SR 3.6.4.3.4, to verify each SGT filter cooler bypass damper can be opened and the fan started, so the changes to SR 3.6.4.3.4 described in TSTF-541 are not applicable to the HNP Unit 1 and Unit 2 TS.

The HNP TS contain a Surveillance Frequency Control Program. Therefore, the Frequency for the affected SRs is In accordance with the Surveillance Frequency Control Program. This has no effect on the applicability of the proposed change.

2.3 Licensee Verifications SNC confirms that existing administrative processes, such as the Corrective Action Program, Operability Determination process, the maintenance, design control, configuration control, and operating procedures, etc., will be used to assess the operability of the system or of any supported systems when utilizing the SR allowances, which includes consideration of whether movement of the affected valves or dampers following an event is assumed in the safety analysis.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination SNC requests adoption of TSTF-541, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position," which is an approved change to the Standard Technical Specifications (STS), into the FNP Units 1 and 2, HNP Units 1 and 2, and VEGP Units 1 and 2 Technical Specifications (TS). The proposed amendment modifies the TS Surveillance Requirements (SRs) by adding exceptions to consider the SR met when automatic valves or dampers are locked, sealed, or otherwise secured in the actuated position, in order to consider the SR met. Securing the automatic valve or damper in the actuated position may affect the operability of the system or of any supported systems. The associated Limiting Condition for Operation (LCO) is met if the subject structure, system or component (SSC) remains operable (i.e., capable of performing its specified safety function).

E1-4 to NL-20-0949 Description and Assessment SNC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

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

Response: No The proposed change revises SRs by adding exceptions excluding from actuation and isolation time testing those valves and dampers that are locked, sealed or otherwise secured in the actuated position. The performance or lack of performance of SRs is not an initiator of any accident previously evaluated. As a result, the proposed change has no effect on the probability of any accident previously evaluated. The proposed change excludes performance of portions of certain SRs, but the SSC must still be capable of performing the safety functions assumed in the accident analysis. Otherwise, the SSC is inoperable, and the associated TS Actions are followed. As a result, the SSCs continue to perform their mitigating functions and the consequences of any accident previously evaluated are not affected.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

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

Response: No The proposed change revises SRs by adding exceptions excluding from actuation and isolation time testing those valves and dampers that are locked, sealed or otherwise secured in the actuated position. The proposed change will not change the design function or operability requirements of the affected SSCs. The SSC must still be capable of performing the safety functions assumed in the accident analysis or the SSC is inoperable, and the associated TS Actions are followed. The proposed change does not create any credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.

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 amendment involve a significant reduction in a margin of safety?

Response: No The proposed change revises SRs by adding exceptions excluding from actuation and isolation time testing those valves and dampers that are locked, sealed or otherwise secured in the actuated position. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis assumptions and acceptance criteria are not affected by this change.

E1-5 to NL-20-0949 Description and Assessment Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, SNC concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

3.2 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4. ENVIRONMENTAL CONSIDERATION 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 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.

E1-6

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 1a FNP Proposed Technical Specification Changes (Mark-Up)

CREFS 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.3 -----------------------------NOTE--------------------------------

In accordance Not required to be performed in MODES 5 and 6.

with the Surveillance Verify each CREFS train actuates on an actual or Frequency simulated actuation signal, except for dampers and Control Program valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in In accordance accordance with the Control Room Envelope with the Control Habitability Program. Room Envelope Habitability Program Farley Units 1 and 2 3.7.10-4 Amendment No. 216 - (Unit 1)

Amendment No. 213 - (Unit 2)

PRF 3.7.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two PRF trains inoperable E.1 Suspend movement of Immediately during movement of recently irradiated fuel recently irradiated fuel assemblies in the SFPR.

assemblies in the SFPR.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 ----------------------------NOTE----------------------------------

Only required to be met during movement of recently irradiated fuel assemblies in the SFPR.

Verify two PRF trains aligned to the SFPR. In accordance with the Surveillance Frequency Control Program SR 3.7.12.2 Operate each PRF train for 15 minutes in the In accordance with applicable mode of operation (post LOCA and/or the Surveillance refueling accident). Frequency Control Program SR 3.7.12.3 Perform required PRF filter testing in accordance with In accordance with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.12.4 Verify each PRF train actuates and the normal spent In accordance with fuel pool room ventilation system isolates on an the Surveillance actual or simulated actuation signal, except for Frequency Control dampers and valves that are locked, sealed, or Program otherwise secured in the actuated position.

SR 3.7.12.5 Verify one PRF train can maintain a pressure In accordance with

-0.125 inches water gauge with respect to adjacent the Surveillance areas during the post LOCA mode of operation at a Frequency Control flow rate 5500 cfm. Program SR 3.7.12.6 Verify one PRF train can maintain a slightly negative In accordance with pressure with respect to adjacent areas during the the Surveillance fuel handling accident mode of operation at a flow Frequency Control rate 5500 cfm. Program Farley Units 1 and 2 3.7.12-2 Amendment No. 223 (Unit 1)

Amendment No. 220 (Unit 2)

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 1b HNP Proposed Technical Specification Changes (Mark-Up)

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 -----------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI In accordance with pump can develop a flow rate 4250 gpm against the Surveillance a system head corresponding to reactor system Frequency Control pressure. Program SR 3.5.1.10 ----------------------------NOTE-------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with actuates on an actual or simulated automatic the Surveillance initiation signal, except for valves that are locked, Frequency Control sealed, or otherwise secured in the actuated Program position.

SR 3.5.1.11 ----------------------------NOTE-------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance with automatic initiation signal. the Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve relief mode actuator In accordance with strokes when manually actuated. the Surveillance Frequency Control Program HATCH UNIT 1 3.5-5 Amendment No. 266

RPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify, for the required ECCS injection/spray In accordance with subsystem, locations susceptible to gas the Surveillance accumulation are sufficiently filled with water. Frequency Control Program SR 3.5.2.5 ----------------------------NOTES-----------------------------

1. A Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system vent flowpaths opened under administrative control.

Verify for the required ECCS injection/spray In accordance with subsystem, each manual, power operated, and the Surveillance automatic valve in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.5.2.6 Operate the required ECCS injection/spray In accordance with subsystem through the recirculation line for 10 the Surveillance minutes. Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically In accordance with isolating a penetration flow path actuates to the the Surveillance isolation position on an actual or simulated Frequency Control isolation signal, except for valves that are locked, Program sealed, or otherwise secured in the actuated position.

SR 3.5.2.8 ---------------------------NOTE--------------------------------

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray In accordance with subsystem can be manually operated. the Surveillance Frequency Control Program HATCH UNIT 1 3.5-9 Amendment No. 290

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to In accordance with gas accumulation are sufficiently filled with water. the Surveillance Frequency Control Program SR 3.5.3.2 ----------------------------NOTE-------------------------------

Not required to be met for system vent flowpaths opened under administrative control.

Verify each RCIC System manual, power In accordance with operated, and automatic valve in the flow path, the Surveillance that is not locked, sealed, or otherwise secured in Frequency Control position, is in the correct position. Program SR 3.5.3.3 ----------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 1058 psig and In accordance with 920 psig, the RCIC pump can develop a flow the Surveillance Frequency Control rate 400 gpm against a system head Program corresponding to reactor pressure.

SR 3.5.3.4 ----------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the RCIC In accordance with the Surveillance pump can develop a flow rate 400 gpm against a Frequency Control system head corresponding to reactor pressure.

Program SR 3.5.3.5 ----------------------------NOTE-------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or In accordance with simulated automatic initiation signal, except for the Surveillance valves that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 1 3.5-11 Amendment No. 290

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two or more required SGT F.1 -----------NOTE-------------

subsystems inoperable LCO 3.0.3 is not during movement of applicable.

recently irradiated fuel --------------------------------

assemblies in the secondary containment. Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each required SGT subsystem for In accordance with 15 continuous minutes. the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.6.4.3.3 Verify each required SGT subsystem actuates on In accordance with an actual or simulated initiation signal, except for the Surveillance dampers that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 1 3.6-42 Amendment No. 301

PSW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in each PSW pump well of In accordance with the intake structure is 60.5 ft mean sea level the Surveillance (MSL). Frequency Control Program AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when water level is 61.7 ft MSL SR 3.7.2.2 ----------------------------NOTE-------------------------------

Isolation of flow to individual components or systems does not render PSW System inoperable.

Verify each PSW subsystem manual, power In accordance with operated, and automatic valve in the flow paths the Surveillance servicing safety related systems or components, Frequency Control that is not locked, sealed, or otherwise secured in Program position, is in the correct position.

SR 3.7.2.3 Verify each PSW subsystem actuates on an actual In accordance with or simulated initiation signal, except for valves that the Surveillance are locked, sealed, or otherwise secured in the Frequency Control actuated position. Program HATCH UNIT 1 3.7-5 Amendment No. 267

MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems -----------------NOTE-------------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel --------------------------------------------

assemblies in the secondary containment or F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS. assemblies in the secondary containment.

OR AND One or more MCREC subsystems inoperable due to an inoperable CRE F.2 Suspend CORE Immediately boundary during movement ALTERATIONS.

of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance with actual or simulated initiation signal, except for the Surveillance dampers and valves that are locked, sealed, or Frequency Control otherwise secured in the actuated position. Program (continued)

HATCH UNIT 1 3.7-10 Amendment No. 290

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 -----------------------------NOTE----------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI In accordance with pump can develop a flow rate 4250 gpm against the Surveillance a system head corresponding to reactor system Frequency Control pressure. Program SR 3.5.1.10 ----------------------------NOTE-----------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with actuates on an actual or simulated automatic the Surveillance initiation signal, except for valves that are locked, Frequency Control sealed, or otherwise secured in the actuated Program position.

SR 3.5.1.11 ----------------------------NOTE-------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance with automatic initiation signal. the Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve relief mode actuator In accordance with strokes when manually actuated. the Surveillance Frequency Control Program HATCH UNIT 2 3.5-5 Amendment No. 210-

RPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify, for the required ECCS injection/spray In accordance with subsystem, locations susceptible to gas the Surveillance accumulation are sufficiently filled with water. Frequency Control Program SR 3.5.2.5 --------------------------NOTES-------------------------------

1. A Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system vent flowpaths opened under administrative control.

Verify for the required ECCS injection/spray In accordance with subsystem, each manual, power operated, and the Surveillance automatic valve in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.5.2.6 Operate the required ECCS injection/spray In accordance with subsystem through the recirculation line for 10 the Surveillance minutes. Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically In accordance with isolating a penetration flow path actuates to the the Surveillance isolation position on an actual or simulated Frequency Control isolation signal, except for valves that are locked, Program sealed, or otherwise secured in the actuated position.

SR 3.5.2.8 ---------------------------NOTE-------------------------------

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray In accordance with subsystem can be manually operated. the Surveillance Frequency Control Program HATCH UNIT 2 3.5-10 Amendment No. 235

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 ----------------------------NOTE------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or In accordance with simulated automatic initiation signal, except for the Surveillance valves that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 2 3.5-13 Amendment No. 235

SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.3 Verify each required SGT subsystem actuates on In accordance with an actual or simulated initiation signal, except for the Surveillance dampers that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 2 3.6-42 Amendment No. 210

PSW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in each PSW pump well of In accordance with the intake structure is 60.5 ft mean sea level the Surveillance (MSL). Frequency Control Program AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when water level is 61.7 ft MSL SR 3.7.2.2 -----------------------------NOTE------------------------------

Isolation of flow to individual components or systems does not render PSW System inoperable.

Verify each PSW subsystem manual, power In accordance with operated, and automatic valve in the flow paths the Surveillance servicing safety related systems or components, Frequency Control that is not locked, sealed, or otherwise secured in Program position, is in the correct position.

SR 3.7.2.3 Verify each PSW subsystem actuates on an actual In accordance with or simulated initiation signal, except for valves that the Surveillance are locked, sealed, or otherwise secured in the Frequency Control actuated position. Program HATCH UNIT 2 3.7-5 Amendment No. 211

MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems ------------------NOTE------------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel --------------------------------------------

assemblies in the secondary containment or F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS. assemblies in the secondary containment.

OR AND One or more MCREC subsystems inoperable due F.2 Suspend CORE Immediately to an inoperable CRE ALTERATIONS.

boundary during movement of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance with actual or simulated initiation signal, except for the Surveillance dampers and valves that are locked, sealed, or Frequency Control otherwise secured in the actuated position. Program (continued)

HATCH UNIT 2 3.7-10 Amendment No. 235

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 1c VEGP Proposed Technical Specification Changes (Mark-Up)

CREFS - Both Units Operating 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Verify control room air temperature 85F. In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Operate each CREFS train for 15 continuous In accordance with minutes with the heater control circuit energized. the Surveillance Frequency Control Program SR 3.7.10.3 Perform required CREFS filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.10.4 Verify each CREFS train actuates (switches to In accordance with emergency mode) on an actual or simulated the Surveillance actuation signal, except for dampers and valves Frequency Control that are locked, sealed, or otherwise secured in Program the actuated position.

SR 3.7.10.5 Perform required CRE unfiltered air inleakage In accordance with testing in accordance with the Control Room the Control Room Envelope Habitability Program. Envelope Habitability Program Vogtle Units 1 and 2 3.7.10-5 Amendment No. 189 (Unit 1)

Amendment No. 172 (Unit 2)

PPAFES 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each PPAFES train for 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.13.2 Perform required PPAFES filter testing in In accordance with the accordance with the Ventilation Filter Testing VFTP Program (VFTP).

SR 3.7.13.3 Verify each PPAFES train actuates on an actual In accordance with the or simulated actuation signal, except for dampers Surveillance and valves that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program SR 3.7.13.4 Verify one PPAFES train can maintain a negative In accordance with the pressure 0.250 inches water gauge relative to Surveillance atmospheric pressure during the post accident Frequency Control mode of operation at a flow rate of Program 15,500 cfm 10%.

Vogtle Units 1 and 2 3.7.13-2 Amendment No. 179 - (Unit 1)

Amendment No. 160 -(Unit 2)

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 2a FNP Revised Technical Specification Pages

CREFS 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.3 -----------------------------NOTE--------------------------------

In accordance Not required to be performed in MODES 5 and 6.

with the Surveillance Verify each CREFS train actuates on an actual or Frequency simulated actuation signal, except for dampers and Control Program valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in In accordance accordance with the Control Room Envelope with the Control Habitability Program. Room Envelope Habitability Program Farley Units 1 and 2 3.7.10-4 Amendment No. (Unit 1)

Amendment No. (Unit 2)

PRF 3.7.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two PRF trains inoperable E.1 Suspend movement of Immediately during movement of recently irradiated fuel recently irradiated fuel assemblies in the SFPR.

assemblies in the SFPR.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 ----------------------------NOTE----------------------------------

Only required to be met during movement of recently irradiated fuel assemblies in the SFPR.

Verify two PRF trains aligned to the SFPR. In accordance with the Surveillance Frequency Control Program SR 3.7.12.2 Operate each PRF train for 15 minutes in the In accordance with applicable mode of operation (post LOCA and/or the Surveillance refueling accident). Frequency Control Program SR 3.7.12.3 Perform required PRF filter testing in accordance with In accordance with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.12.4 Verify each PRF train actuates and the normal spent In accordance with fuel pool room ventilation system isolates on an the Surveillance actual or simulated actuation signal, except for Frequency Control dampers and valves that are locked, sealed, or Program otherwise secured in the actuated position.

SR 3.7.12.5 Verify one PRF train can maintain a pressure In accordance with

-0.125 inches water gauge with respect to adjacent the Surveillance areas during the post LOCA mode of operation at a Frequency Control flow rate 5500 cfm. Program SR 3.7.12.6 Verify one PRF train can maintain a slightly negative In accordance with pressure with respect to adjacent areas during the the Surveillance fuel handling accident mode of operation at a flow Frequency Control rate 5500 cfm. Program Farley Units 1 and 2 3.7.12-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 2b HNP Revised Technical Specification Pages

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 -----------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI In accordance with pump can develop a flow rate 4250 gpm against the Surveillance a system head corresponding to reactor system Frequency Control pressure. Program SR 3.5.1.10 ----------------------------NOTE-------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with actuates on an actual or simulated automatic the Surveillance initiation signal, except for valves that are locked, Frequency Control sealed, or otherwise secured in the actuated Program position.

SR 3.5.1.11 ----------------------------NOTE-------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance with automatic initiation signal. the Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve relief mode actuator In accordance with strokes when manually actuated. the Surveillance Frequency Control Program HATCH UNIT 1 3.5-5 Amendment No.

RPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify, for the required ECCS injection/spray In accordance with subsystem, locations susceptible to gas the Surveillance accumulation are sufficiently filled with water. Frequency Control Program SR 3.5.2.5 ----------------------------NOTES-----------------------------

1. A Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system vent flowpaths opened under administrative control.

Verify for the required ECCS injection/spray In accordance with subsystem, each manual, power operated, and the Surveillance automatic valve in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.5.2.6 Operate the required ECCS injection/spray In accordance with subsystem through the recirculation line for 10 the Surveillance minutes. Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically In accordance with isolating a penetration flow path actuates to the the Surveillance isolation position on an actual or simulated Frequency Control isolation signal, except for valves that are locked, Program sealed, or otherwise secured in the actuated position.

SR 3.5.2.8 ---------------------------NOTE--------------------------------

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray In accordance with subsystem can be manually operated. the Surveillance Frequency Control Program HATCH UNIT 1 3.5-9 Amendment No.

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to In accordance with gas accumulation are sufficiently filled with water. the Surveillance Frequency Control Program SR 3.5.3.2 ----------------------------NOTE-------------------------------

Not required to be met for system vent flowpaths opened under administrative control.

Verify each RCIC System manual, power In accordance with operated, and automatic valve in the flow path, the Surveillance that is not locked, sealed, or otherwise secured in Frequency Control position, is in the correct position. Program SR 3.5.3.3 ----------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 1058 psig and In accordance with 920 psig, the RCIC pump can develop a flow the Surveillance Frequency Control rate 400 gpm against a system head Program corresponding to reactor pressure.

SR 3.5.3.4 ----------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the RCIC In accordance with the Surveillance pump can develop a flow rate 400 gpm against a Frequency Control system head corresponding to reactor pressure.

Program SR 3.5.3.5 ----------------------------NOTE-------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or In accordance with simulated automatic initiation signal, except for the Surveillance valves that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 1 3.5-11 Amendment No.

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two or more required SGT F.1 -----------NOTE-------------

subsystems inoperable LCO 3.0.3 is not during movement of applicable.

recently irradiated fuel --------------------------------

assemblies in the secondary containment. Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each required SGT subsystem for In accordance with 15 continuous minutes. the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.6.4.3.3 Verify each required SGT subsystem actuates on In accordance with an actual or simulated initiation signal, except for the Surveillance dampers that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 1 3.6-42 Amendment No.

PSW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in each PSW pump well of In accordance with the intake structure is 60.5 ft mean sea level the Surveillance (MSL). Frequency Control Program AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when water level is 61.7 ft MSL SR 3.7.2.2 ----------------------------NOTE-------------------------------

Isolation of flow to individual components or systems does not render PSW System inoperable.

Verify each PSW subsystem manual, power In accordance with operated, and automatic valve in the flow paths the Surveillance servicing safety related systems or components, Frequency Control that is not locked, sealed, or otherwise secured in Program position, is in the correct position.

SR 3.7.2.3 Verify each PSW subsystem actuates on an actual In accordance with or simulated initiation signal, except for valves that the Surveillance are locked, sealed, or otherwise secured in the Frequency Control actuated position. Program HATCH UNIT 1 3.7-5 Amendment No.

MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems -----------------NOTE-------------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel --------------------------------------------

assemblies in the secondary containment or F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS. assemblies in the secondary containment.

OR AND One or more MCREC subsystems inoperable due to an inoperable CRE F.2 Suspend CORE Immediately boundary during movement ALTERATIONS.

of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance with actual or simulated initiation signal, except for the Surveillance dampers and valves that are locked, sealed, or Frequency Control otherwise secured in the actuated position. Program (continued)

HATCH UNIT 1 3.7-10 Amendment No.

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 -----------------------------NOTE----------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI In accordance with pump can develop a flow rate 4250 gpm against the Surveillance a system head corresponding to reactor system Frequency Control pressure. Program SR 3.5.1.10 ----------------------------NOTE-----------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with actuates on an actual or simulated automatic the Surveillance initiation signal, except for valves that are locked, Frequency Control sealed, or otherwise secured in the actuated Program position.

SR 3.5.1.11 ----------------------------NOTE-------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance with automatic initiation signal. the Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve relief mode actuator In accordance with strokes when manually actuated. the Surveillance Frequency Control Program HATCH UNIT 2 3.5-5 Amendment No.

RPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify, for the required ECCS injection/spray In accordance with subsystem, locations susceptible to gas the Surveillance accumulation are sufficiently filled with water. Frequency Control Program SR 3.5.2.5 --------------------------NOTES-------------------------------

1. A Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system vent flowpaths opened under administrative control.

Verify for the required ECCS injection/spray In accordance with subsystem, each manual, power operated, and the Surveillance automatic valve in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.5.2.6 Operate the required ECCS injection/spray In accordance with subsystem through the recirculation line for 10 the Surveillance minutes. Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically In accordance with isolating a penetration flow path actuates to the the Surveillance isolation position on an actual or simulated Frequency Control isolation signal, except for valves that are locked, Program sealed, or otherwise secured in the actuated position.

SR 3.5.2.8 ---------------------------NOTE-------------------------------

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray In accordance with subsystem can be manually operated. the Surveillance Frequency Control Program HATCH UNIT 2 3.5-10 Amendment No.

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 ----------------------------NOTE------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or In accordance with simulated automatic initiation signal, except for the Surveillance valves that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 2 3.5-13 Amendment No.

SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.3 Verify each required SGT subsystem actuates on In accordance with an actual or simulated initiation signal, except for the Surveillance dampers that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program HATCH UNIT 2 3.6-42 Amendment No.

PSW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in each PSW pump well of In accordance with the intake structure is 60.5 ft mean sea level the Surveillance (MSL). Frequency Control Program AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when water level is 61.7 ft MSL SR 3.7.2.2 -----------------------------NOTE------------------------------

Isolation of flow to individual components or systems does not render PSW System inoperable.

Verify each PSW subsystem manual, power In accordance with operated, and automatic valve in the flow paths the Surveillance servicing safety related systems or components, Frequency Control that is not locked, sealed, or otherwise secured in Program position, is in the correct position.

SR 3.7.2.3 Verify each PSW subsystem actuates on an actual In accordance with or simulated initiation signal, except for valves that the Surveillance are locked, sealed, or otherwise secured in the Frequency Control actuated position. Program HATCH UNIT 2 3.7-5 Amendment No.

MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems ------------------NOTE------------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel --------------------------------------------

assemblies in the secondary containment or F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS. assemblies in the secondary containment.

OR AND One or more MCREC subsystems inoperable due F.2 Suspend CORE Immediately to an inoperable CRE ALTERATIONS.

boundary during movement of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance with actual or simulated initiation signal, except for the Surveillance dampers and valves that are locked, sealed, or Frequency Control otherwise secured in the actuated position. Program (continued)

HATCH UNIT 2 3.7-10 Amendment No.

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 2c VEGP Revised Technical Specification Pages

CREFS - Both Units Operating 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Verify control room air temperature 85F. In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Operate each CREFS train for 15 continuous In accordance with minutes with the heater control circuit energized. the Surveillance Frequency Control Program SR 3.7.10.3 Perform required CREFS filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

SR 3.7.10.4 Verify each CREFS train actuates (switches to In accordance with emergency mode) on an actual or simulated the Surveillance actuation signal, except for dampers and valves Frequency Control that are locked, sealed, or otherwise secured in Program the actuated position.

SR 3.7.10.5 Perform required CRE unfiltered air inleakage In accordance with testing in accordance with the Control Room the Control Room Envelope Habitability Program. Envelope Habitability Program Vogtle Units 1 and 2 3.7.10-5 Amendment No. (Unit 1)

Amendment No. (Unit 2)

PPAFES 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each PPAFES train for 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.13.2 Perform required PPAFES filter testing in In accordance with the accordance with the Ventilation Filter Testing VFTP Program (VFTP).

SR 3.7.13.3 Verify each PPAFES train actuates on an actual In accordance with the or simulated actuation signal, except for dampers Surveillance and valves that are locked, sealed, or otherwise Frequency Control secured in the actuated position. Program SR 3.7.13.4 Verify one PPAFES train can maintain a negative In accordance with the pressure 0.250 inches water gauge relative to Surveillance atmospheric pressure during the post accident Frequency Control mode of operation at a flow rate of Program 15,500 cfm 10%.

Vogtle Units 1 and 2 3.7.13-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 3a FNP Proposed Technical Specification Bases Changes (Mark-Up) for Information Only

CREFS B 3.7.10 BASES SURVEILLANCE SR 3.7.10.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. As the environment and normal operating conditions on this system are not severe, testing each train (CREFS and Pressurization) provides an adequate check of this system. The CREFS trains are initiated from the control room with flow through the HEPA and charcoal filters. Systems must be operated for 15 minutes to demonstrate the function of the system (Ref. 3).

Systems with heaters must be operated with the heaters energized.

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

SR 3.7.10.2 This SR verifies that the required CREFS testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The CREFS filter tests are in accordance with ASME N510-1989 (Ref. 4).

The VFTP includes testing the performance of the HEPA filter, charcoal adsorber efficiency, flow rate, and the physical properties of the activated charcoal. Specific test Frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.10.3 This SR verifies that each CREFS train starts and operates on an actual or simulated Safety Injection (SI) actuation signal. The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This SR is modified by a note which provides an exception to the requirement to meet this SR in MODES 5 and 6. This is acceptable since the automatic SI actuation function is not required in these MODES.

SR 3.7.10.4 (continued)

Farley Units 1 and 2 B 3.7.10-8 Revision 90

PRF B 3.7.12 BASES SURVEILLANCE SR 3.7.12.4 REQUIREMENTS (continued) This SR verifies that each PRF train starts and operates on an actual or simulated Phase B actuation signal. In addition, the normal spent fuel pool ventilation system must be verified to isolate on an actual or simulated spent fuel pool ventilation low differential pressure signal and on an actual or simulated spent fuel pool high radiation signal.

The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.12.5 This SR verifies the integrity of the ECCS pump rooms and penetration area boundary. The ability of the boundary to maintain negative pressure with respect to potentially uncontaminated adjacent areas is periodically tested to verify proper function of the PRF System. During the post-LOCA mode of operation, the PRF System is designed to maintain a slight negative pressure in the ECCS pump rooms and penetration area boundary, to prevent unfiltered LEAKAGE. The PRF System is designed to maintain -0.125 inches water gauge with respect to adjacent area pressure (as measured by the P between the PRF mechanical equipment room and the RHR Heat Exchanger Room) at a flow rate of 5,500 cfm.

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 Farley Units 1 and 2 B 3.7.12-8 Revision 73

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 3b HNP Proposed Technical Specification Bases Changes (Mark-Up) for Information Only

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.7, SR 3.5.1.8, and SR 3.5.1.9 (continued)

REQUIREMENTS steam flow for SR 3.5.1.8 is represented by at least two turbine bypass valves open, or 200 MWE from the main turbine generator; and for SR 3.5.1.9 adequate steam flow is represented by at least 1.25 turbine bypass valves open, or total steam flow 1E6 lb/hour.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure test has been satisfactorily completed and there is no indication or reason to believe that HPCI is inoperable. Therefore, SR 3.5.1.8 and SR 3.5.1.9 are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.

The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed is sufficient to achieve stable conditions for testing and provides a reasonable time to complete the SR.

The Frequency for SR 3.5.1.7 is consistent with the INSERVICE TESTING PROGRAM pump testing requirements. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.5.1.10 The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, CS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions. This SR also ensures that the HPCI System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the (continued)

HATCH UNIT 1 B 3.5-13 REVISION 92

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.10 (continued)

REQUIREMENTS system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlaps this Surveillance to provide complete testing of the assumed safety function.

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

This SR is modified by a Note that excludes vessel injection/spray during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

SR 3.5.1.11 The ADS designated S/RVs are required to actuate automatically upon receipt of specific initiation signals. A system functional test is performed to demonstrate that the mechanical portions of the ADS function (i.e., solenoids) operate as designed when initiated either by an actual or simulated initiation signal, causing proper actuation of all the required components. SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function.

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

This SR is modified by a Note that excludes valve actuation. This prevents an RPV pressure blowdown.

SR 3.5.1.12 The pneumatic actuator of each ADS valve is stroked to verify that the pilot disc rod lifts when the actuator strokes. Pilot rod lift is determined by measurement of rod travel. The total amount of lift of the pilot rod from the valve closed position to the open position shall meet criteria established by the S/RV supplier. SRs 3.5.1.11 and (continued)

HATCH UNIT 1 B 3.5-14 REVISION 87

RPV Water Inventory Control B 3.5.2 BASES SURVEILLANCE SR 3.5.2.5 (continued)

REQUIREMENTS This will ensure adequate core cooling if an inadvertent RPV draindown should occur.

The Surveillance is also modified by a Note 2 which exempts system vent flow paths opened under administrative control. The administrative control should be proceduralized and include stationing a dedicated individual who can rapidly close the system vent flow path if directed.

SR 3.5.2.6 Verifying that the required ECCS injection/spray subsystem can be manually started and operated for at least 10 minutes demonstrates that the subsystem is available to mitigate a draining event. Testing the ECCS injection/spray subsystem through the recirculation line is necessary to avoid overfilling the refueling cavity. The minimum operating time of 10 minutes was based on engineering judgement.

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

SR 3.5.2.7 Verifying that each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated RPV water level isolation signal is required to prevent RPV water inventory from dropping below that TAF should an unexpected draining event occur. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency.

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

(continued)

HATCH UNIT 1 B 3.5-24 REVISION 98

RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.3 and SR 3.5.3.4 (continued)

REQUIREMENTS Therefore, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.

The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed is sufficient to achieve stable conditions for testing and provides a reasonable time to complete the SR. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.5.3.5 The RCIC System is required to actuate automatically in order to verify its design function satisfactorily. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of the RCIC System will cause the system to operate as designed, including actuation of the system throughout its emergency operating sequence; that is, automatic pump startup and actuation of all automatic valves to their required positions. This test also ensures the RCIC System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps this Surveillance to provide complete testing of the assumed safety function.

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

This SR is modified by a Note that excludes vessel injection during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

(continued)

HATCH UNIT 1 B 3.5-32 REVISION 98

SGT System B 3.6.4.3 BASES (continued)

SURVEILLANCE SR 3.6.4.3.1 REQUIREMENTS Operating each required Unit 1 and Unit 2 SGT subsystem for 15 continuous minutes ensures that they 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.6.4.3.2 This SR verifies that the required Unit 1 and Unit 2 SGT filter testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.

SR 3.6.4.3.3 This SR verifies that each required Unit 1 and Unit 2 SGT subsystem starts on receipt of an actual or simulated initiation signal. The SR excludes automatic dampers that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic damper to the non-actuated position requires verification that the SR has been met within its required Frequency. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

HATCH UNIT 1 B 3.6-101 REVISION 105

PSW System and UHS B 3.7.2 BASES SURVEILLANCE SR 3.7.2.2 (continued)

REQUIREMENTS This SR is modified by a Note indicating that isolation of the PSW System to components or systems may render those components or systems inoperable, but does not affect the OPERABILITY of the PSW System. As such, when all PSW pumps, valves, and piping are OPERABLE, but a branch connection off the main header is isolated, the PSW System is still OPERABLE.

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

SR 3.7.2.3 This SR verifies that the automatic isolation valves of the PSW System will automatically switch to the safety or emergency position to provide cooling water exclusively to the safety related equipment during an accident event. This is demonstrated by the use of an actual or simulated initiation signal. This SR also verifies the automatic start capability (on a LOCA or LOSP signal) of one of the two PSW pumps in each subsystem. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency.

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

REFERENCES 1. FSAR, Section 10.7.

2. FSAR, Section 5.2.
3. Unit 2 FSAR, Chapter 15.
4. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States HATCH UNIT 1 B 3.7-13 REVISION 96

MCREC System B 3.7.4 BASES (continued)

SURVEILLANCE SR 3.7.4.1 REQUIREMENTS This SR verifies that a subsystem in a standby mode starts on demand and continues to operate. Standby systems should be checked periodically to ensure that they start and function properly.

As the environmental and normal operating conditions of this system are not severe, testing each subsystem once every 31 days provides an adequate check on this system. Since the MCREC System does not have heaters, each subsystem need only be operated for 15 minutes to demonstrate the function of the subsystem. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.4.2 This SR verifies that the required MCREC testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations).

Specific test Frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.4.3 This SR verifies that on an actual or simulated initiation signal, each MCREC subsystem starts and operates. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.7.1.4 overlaps this SR to provide complete testing of the safety function. The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured.

Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency.

This Surveillance can be performed with the reactor at power. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

HATCH UNIT 1 B 3.7-25 REVISION 87

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.7, SR 3.5.1.8, and SR 3.5.1.9 (continued)

REQUIREMENTS steam flow for SR 3.5.1.8 is represented by at least two turbine bypass valves open, or 200 MWE from the main turbine-generator; and for SR 3.5.1.9 adequate steam flow is represented by at least 1.25 turbine bypass valves open, or total steam flow 1E6 lb/hour.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure test has been satisfactorily completed and there is no indication or reason to believe that HPCI is inoperable. Therefore, SR 3.5.1.8 and SR 3.5.1.9 are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.

The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed is sufficient to achieve stable conditions for testing and provides a reasonable time to complete the SR.

The Frequency for SR 3.5.1.7 is consistent with the INSERVICE TESTING PROGRAM pump testing requirements. The Frequencies for SR 3.5.1.8 and SR 3.5.1.9 are based on operating experience, equipment reliability, and plant risk, and are controlled under the Surveillance Frequency Control Program.

SR 3.5.1.10 The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, CS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions. This SR also ensures that the HPCI System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary (continued)

HATCH UNIT 2 B 3.5-13 REVISION 103

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.10 (continued)

REQUIREMENTS for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlaps this Surveillance to provide complete testing of the assumed safety function.

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

This SR is modified by a Note that excludes vessel injection/spray during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

SR 3.5.1.11 The ADS designated S/RVs are required to actuate automatically upon receipt of specific initiation signals. A system functional test is performed to demonstrate that the mechanical portions of the ADS function (i.e., solenoids) operate as designed when initiated either by an actual or simulated initiation signal, causing proper actuation of all the required components. SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function.

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

This SR is modified by a Note that excludes valve actuation. This prevents an RPV pressure blowdown.

SR 3.5.1.12 The pneumatic actuator of each ADS valve is stroked to verify that the actuator shaft moves when the air operator module is pneumatically energized. This action confirms correct electrical and pneumatic connections between the electrical switch for the S/RV and its associated solenoid valve and, subsequently, the pneumatic operator. Successful confirmation of actuator shaft movement provides that this shaft will actuate the S/RV second stage disc. Confirmation that actuation of the second stage shaft (continued)

HATCH UNIT 2 B 3.5-14 REVISION 98

RPV Water Inventory Control B 3.5.2 BASES SURVEILLANCE SR 3.5.2.6 REQUIREMENTS (continued) Verifying that the required ECCS injection/spray subsystem can be manually started and operate for at least 10 minutes demonstrates that the subsystem is available to mitigate a draining event. Testing the ECCS injection/spray subsystem through the recirculation line is necessary to avoid overfilling the refueling cavity. The minimum operating time of 10 minutes was based on engineering judgement.

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

SR 3.5.2.7 Verifying that each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated RPV water level isolation signal is required to prevent RPV water inventory from dropping below the TAF should an unexpected draining event occur. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency.

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

SR 3.5.2.8 The required ECCS subsystem shall be capable of being manually operated. This Surveillance verifies that the required CS or LPCI subsystem (including the associated pump and valve(s)) can be manually operated to provide additional RPV Water Inventory, if needed.

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

(continued)

HATCH UNIT 2 B 3.5-25 REVISION 110

RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.5 REQUIREMENTS (continued) The RCIC System is required to actuate automatically in order to verify its design function satisfactorily. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of the RCIC System will cause the system to operate as designed, including actuation of the system throughout its emergency operating sequence; that is, automatic pump startup and actuation of all automatic valves to their required positions. This test also ensures the RCIC System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps this Surveillance to provide complete testing of the assumed safety function.

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

This SR is modified by a Note that excludes vessel injection during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 33.

2. FSAR, Section 5.5.6.
3. Memorandum from R.L. Baer (NRC) to V. Stello, Jr. (NRC),

"Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.

4. GE Report AES-41-0688, "Safety Evaluation for Relaxation of RCIC Performance Requirements for Plant Hatch Units 1 and 2," July 1988.

HATCH UNIT 2 B 3.5-33 REVISION 110

SGT System B 3.6.4.3 BASES SURVEILLANCE SR 3.6.4.3.3 REQUIREMENTS (continued) This SR verifies that each required Unit 1 and Unit 2 SGT subsystem starts on receipt of an actual or simulated initiation signal. The SR excludes automatic dampers that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic damper to the non-actuated position requires verification that the SR has been met within its required Frequency. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. This Surveillance can be performed with the reactor at power. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 41.

2. Unit 1 FSAR, Section 5.3.2.3.
3. Unit 2 FSAR, Section 6.2.4.
4. Unit 2 FSAR, Section 15.2.
5. Unit 2 FSAR, Section 15.3.
6. Technical Requirements Manual, Section 8.0.
7. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
8. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

HATCH UNIT 2 B 3.6-104 REVISION 117

PSW System and UHS B 3.7.2 BASES SURVEILLANCE SR 3.7.2.2 (continued)

REQUIREMENTS This SR is modified by a Note indicating that isolation of the PSW System to components or systems may render those components or systems inoperable, but does not affect the OPERABILITY of the PSW System. As such, when all PSW pumps, valves, and piping are OPERABLE, but a branch connection off the main header is isolated, the PSW System is still OPERABLE.

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

SR 3.7.2.3 This SR verifies that the automatic isolation valves of the PSW System will automatically switch to the safety or emergency position to provide cooling water exclusively to the safety related equipment during an accident event. This is demonstrated by the use of an actual or simulated initiation signal. This SR also verifies the automatic start capability (on a LOCA or LOSP signal) of one of the two PSW pumps in each subsystem. The SR excludes automatic valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to valves that are locked, sealed, or otherwise secured in the actuated position since the affected valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency.

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

REFERENCES 1. FSAR, Section 9.2.1.

2. FSAR, Chapter 6.
3. FSAR, Chapter 15.
4. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 2 B 3.7-13 REVISION 98

MCREC System B 3.7.4 BASES (continued)

SURVEILLANCE SR 3.7.4.1 REQUIREMENTS This SR verifies that a subsystem in a standby mode starts on demand and continues to operate. Standby systems should be checked periodically to ensure that they start and function properly.

As the environmental and normal operating conditions of this system are not severe, testing each subsystem once every 31 days provides an adequate check on this system. Since the MCREC System does not have heaters, each subsystem need only be operated for 15 minutes to demonstrate the function of the subsystem. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.4.2 This SR verifies that the required MCREC testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations).

Specific test Frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.4.3 This SR verifies that on an actual or simulated initiation signal, each MCREC subsystem starts and operates. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.7.1.4 overlaps this SR to provide complete testing of the safety function. The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency. This Surveillance can be performed with the reactor at power. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

HATCH UNIT 2 B 3.7-25 REVISION 98

Joseph M. Farley Nuclear Plant, Units 1 and 2 Edwin I. Hatch Nuclear Plant, Units 1 and 2 Vogtle Electric Generating Plant, Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position Attachment 3c VEGP Proposed Technical Specification Bases Changes (Mark-Up) for Information Only

CREFS Both Units Operating B 3.7.10 BASES SURVEILLANCE SR 3.7.10.2 (continued)

REQUIREMENTS Operations with the heater control circuit energized allows the heaters to operate as necessary to reduce the humidity in the ambient air and ensure excessive moisture (> 70% relative humidity) is removed from the adsorber and HEPA filters. Flow (FI-12191, FI-12192) through the HEPA filters and charcoal adsorbers is verified. Operation with the heater control circuit energized for 15 continuous minutes demonstrates OPERABILITY of the system. Periodic operation ensures that heater failure, blockage, fan or motor failure, or excessive vibration can be detected for corrective action. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.10.3 This SR verifies that the required CREFS testing is performed in accordance with the Ventilation Filter Testing Program (VFTP).

The CREFS filter tests are in accordance with Regulatory Guide 1.52 (Ref. 4). The VFTP includes testing the performance of the HEPA filter, charcoal adsorber efficiency, minimum flow rate, and the physical properties of the activated charcoal.

Specific test Frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.10.4 This SR verifies that each CREFS train starts and operates on an actual or simulated actuation signal. The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.10.5 (continued)

Vogtle Units 1 and 2 B 3.7.10-10 REVISION 49

PPAFES B 3.7.13 BASES (continued)

SURVEILLANCE SR 3.7.13.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. As the environmental and normal operating conditions on this system are not severe, testing each train once every month provides an adequate check on this system. Flow (FI-12629 and FI-12542) through the HEPA and charcoal filters is verified. Systems that do not take credit for humidity control (heaters) need only be operated for 15 minutes to demonstrate the function of the system. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.13.2 This SR verifies that the required PPAFES testing is performed in accordance with the Ventilation Filter Testing Program (VFTP).

The PPAFES filter tests are in accordance with Regulatory Guide 1.52 (Ref. 5). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.13.3 This SR verifies that each PPAFES starts and operates on an actual or simulated containment ventilation isolation signal. The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the non-actuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.7.13.4 (continued)

Vogtle Units 1 and 2 B 3.7.13-5 REVISION 38

Retrieved from "https://kanterella.com/w/index.php?title=NL-20-0949,_License_Amendment_Request_to_Revise,_Technical_Specifications_to_Adopt_TSTF-541,_Revision_2&oldid=3210406"