CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)
| ML23031A247 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah  |
| Issue date: | 01/31/2023 |
| From: | Jim Barstow Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| CNL-22-037 | |
| Download: ML23031A247 (1) | |
Text
1101 Market Street, Chattanooga, Tennessee 37402 CNL-22-037 January 31, 2023 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Power Plant Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Dockets 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 328
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Sequoyah Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-541-A, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position" (BFN TS-533) (SQN-TS-20-07)
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Tennessee Valley Authority (TVA) is submitting a request for an amendment to the Technical Specifications (TS) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, and Sequoyah Nuclear Plant (SQN), Units 1 and 2.
TVA requests adoption of Technical Specification Task Force (TSTF)-541-A Revision 2, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position," which is an approved change to the Standard Technical Specifications, into the BFN Units 1, 2, and 3, and SQN Units 1 and 2 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.
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 is met if the subject structure, system, or component remains operable (i.e., capable of performing its specified safety function).
The enclosure provides a description and assessment of the proposed changes. .1 provides the existing BFN TS pages marked up to show the proposed changes. .2 provides the existing SQN TS pages marked up to show the proposed changes. .1 provides the existing BFN TS pages retyped to show the proposed changes.
U.S. Nuclear Regulatory Commission CNL-22-037 Page 2 January 31, 2023 .2 provides the existing SQN TS pages retyped to show the proposed changes. .1 provides the BFN Unit 1 Bases markups to show the proposed changes (the BFN Unit 2 and 3 TS Bases are identical with respect to this change). Attachment 3.2 provides the SQN Unit 1 TS Bases markups to show the proposed changes (the SQN Unit 2 TS Bases are identical with respect to this change). The Bases pages are provided for information only.
TVA requests that the amendment be reviewed under the Consolidated Line Item Improvement Process. Approval of the proposed amendment is requested within six months of completion of the NRCs acceptance review. Once approved, the amendment shall be implemented within 60 days.
There are no new regulatory commitments made in this submittal.
In accordance with 10 CFR 50.91(b)(1), a copy of this application, with attachments, is being provided to the Alabama State Department of Public Health and the Tennessee Department of Environment and Conservation.
If you should have any questions regarding this submittal, please contact Stuart L. Rymer, Senior Manager, Fleet Licensing, at slrymer@tva.gov.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 31st day of January 2023.
Respectfully, Digitally signed by Rearden, Pamela S Date: 2023.01.31 14:41:38 -05'00' James Barstow Vice President, Nuclear Regulatory Affairs and Support Services
Enclosure:
Description and Assessment cc: (with Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant State Health Officer, Alabama State Department of Public Health Director, Division of Radiological Health - Tennessee Department of Environment and Conservation
Enclosure Description and Assessment
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Sequoyah Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-541-A, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position" (BFN TS-533) (SQN-TS-20-07)
Table of Contents 1.0 DESCRIPTION................................................................................................................... 2
2.0 ASSESSMENT................................................................................................................... 2
2.1 Applicability of Safety Evaluation .................................................................................... 2
2.2 Variations ........................................................................................................................ 3
2.3 Licensee Verifications ..................................................................................................... 5
3.0 REGULATORY ANALYSIS ................................................................................................ 5
3.1 No Significant Hazards Consideration Determination .................................................... 5
3.2 Conclusion ...................................................................................................................... 6
4.0 ENVIRONMENTAL CONSIDERATION ............................................................................. 6
ATTACHMENTS 1.1 Proposed TS Changes (Mark-Ups) for BFN Units 1, 2, and 3 1.2 Proposed TS Changes (Mark-Ups) for SQN Units 1 and 2 2.1 Proposed TS Changes (Final Retyped) for BFN Units 1, 2 and 3 2.2 Proposed TS Changes (Final Retyped) for SQN Units 1 and 2 3.1 Proposed TS Bases Page Changes (Mark-Ups) for BFN Unit 1 (For Information Only) 3.2 Proposed TS Bases Page Changes (Mark-Ups) for SQN Unit 1 (For Information Only)
CNL-22-037 E1 of 6
Enclosure
1.0 DESCRIPTION
Tennessee Valley Authority (TVA) requests adoption of Technical Specification Task Force (TSTF)-541-A, "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 Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, and Sequoyah Nuclear Plant (SQN) 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 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.
x BFN SR 3.5.1.9, Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.
x BFN SR 3.5.3.5, Verify the RCIC System actuates on an actual or simulated automatic initiation signal.
x BFN SR 3.6.4.3.3, Verify each SGT subsystem actuates on an actual or simulated initiation signal.
x BFN SR 3.7.3.3, Verify each CREV subsystem actuates on an actual or simulated initiation signal.
x SQN SR 3.6.10.3, Verify each EGTS Air Cleanup Subsystem train actuates on an actual or simulated actuation signal.
x SQN SR 3.6.10.4, Verify each EGTS Air Cleanup Subsystem filter cooling bypass valve can be operated.
x SQN SR 3.7.10.4, Verify each CREVS train actuates on an actual or simulated actuation signal.
x SQN SR 3.7.12.3, Verify each ABGTS train actuates on an actual or simulated actuation signal.
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 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 TVA has reviewed the safety evaluation for TSTF-541-A provided to the Technical Specification Task Force in a letter dated December 10, 2019. This review included a review of the Nuclear Regulatory Commission (NRC) staffs evaluation, as well as the information provided in TSTF-541. As described herein, TVA has concluded that the justifications presented in TSTF-541 and the safety evaluation prepared by the NRC staff are applicable to BFN Units 1, 2, and 3, and SQN Units 1 and 2 and justify this amendment for the incorporation of the changes to the BFN and SQN TS.
CNL-22-037 E2 of 6
Enclosure TVA 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.
TVA 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 2.2.1 BFN Variations TVA is proposing the following variations from the TS changes described in TSTF-541-A or the applicable parts of the NRC staffs safety evaluation:
The BFN TS utilize different numbering and titles from the STS on which TSTF-541-A was based. The following table lists the differences. These differences are administrative and do not affect the applicability of TSTF-541-A to the BFN TS.
TSTF-541-A SR Title BFN SR Title SR 3.5.1.10 Emergency Core SR 3.5.1.9 ECCS - Operating Cooling System (ECCS) - Operating SR 3.7.4.3 Main Control Room SR 3.7.3.3 Control Room Emergency Environmental Control Ventilation (CREV)
(MCREC) System System The BFN TS contain requirements that differ from the STS on which TSTF-541-A was based, but these differences do not affect the applicability of the TSTF-541-A justification. Specifically, the BFN TS does not contain SRs equivalent to the following SRs affected by TSTF-541-A.
x SR 3.6.4.3.4, [Verify each SGT filter bypass damper can be opened and the fan started.]
x SR 3.7.2.6, [Verify each [PSW] subsystem actuates on an actual or simulated initiation signal.]
The BFN 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.
CNL-22-037 E3 of 6
Enclosure 2.2.2 SQN Variations TVA is proposing the following variations from the TS changes described in TSTF-541-A or the applicable parts of the NRC staffs safety evaluation.
The SQN TS utilize different numbering and titles from the STS on which TSTF-541-A was based. The following table lists the differences. These differences are administrative and do not affect the applicability of TSTF-541-A to the SQN TS.
TSTF-541-A SR Title SQN SR Title SR 3.6.13.3 Shield Building Air SR 3.6.10.3 Emergency Gas Cleanup System Treatment System (SBACS) (EGTS) Air Cleanup Subsystem SR 3.6.13.4 SBACS SR 3.6.10.4 EGTS Air Cleanup Subsystem SR 3.7.10.3 Control Room SR 3.7.10.4 Control Room Emergency Emergency Filtration Ventilation System System (CREFS) (CREVS)
SR 3.7.14.3 Penetration Room SR 3.7.12.3 Auxiliary Building Gas Exhaust Air Cleanup Treatment System System (PREACS) (ABGTS)
The SQN TS contains an SR similar to those that are affected by TSTF-541-A, but that does not appear in the traveler. NUREG-1431 SR 3.6.13.4 states, "Verify each SBACS filter bypass damper can be opened." TSTF-541-A modified SR 3.6.13.4 by appending, "except for dampers that are locked, sealed, or otherwise secured in the open position." The equivalent SR in the SQN TS is SR 3.6.10.4, which states, "Verify each EGTS Air Cleanup Subsystem filter cooling bypass valve can be operated." SQN SR 3.6.10.4 is revised by appending, "except for valves that are locked, sealed, or otherwise secured in the actuated position." This distinction between a damper and valve is immaterial to the intent of TSTF-541-A. Therefore, this is considered to be an administrative variation from TSTF-541-A.
The SQN TS contain requirements that differ from the STS on which TSTF-541-A was based, but these differences do not affect the applicability of the TSTF-541-A justification. Specifically, the SQN TS does not contain SRs equivalent to the following SRs affected by TSTF-541-A.
x SR 3.6.11.3, Verify each ICS train actuates on an actual or simulated signal.
x SR 3.6.11.4, Verify each ICS filter bypass damper can be opened.
x SR 3.7.12.3, Verify each ECCS PREACS train actuates on an actual or simulated signal.
x SR 3.7.12.5, Verify each ECCS PREACS filter bypass damper can be closed.
x SR 3.7.13.3, Verify each FBACS train actuates on an actual or simulated signal.
x SR 3.7.13.5, Verify each FBACS filter bypass damper can be closed.
x SR 3.7.14.5, Verify each PREACS filter bypass damper can be closed.
The SQN 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.
CNL-22-037 E4 of 6
Enclosure 2.3 Licensee Verifications TVA 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 TVA requests adoption of TSTF-541-A, "Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position," which is an approved change to the Standard Technical Specifications, into the BFN Unit 1, 2, and 3, and SQN Units 1 and 2 TS.
The proposed amendment modifies the TS 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 is met if the subject structure, system, or component remains operable (i.e., capable of performing its specified safety function).
TVA has evaluated whether or not a significant hazards consideration is involved with the proposed amendments 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 consequence 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 CNL-22-037 E5 of 6
Enclosure 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.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, TVA 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.
4.0 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 maybe 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.
CNL-22-037 E6 of 6
Attachment 1.1 Proposed TS Changes (Mark-Ups) for BFN Units 1, 2, and 3 (12 pages)
CNL-22-037
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SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for t 15 In accordance continuous minutes with heaters operating. with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).
SR 3.6.4.3.3 Verify each SGT subsystem actuates on an In accordance actual or simulated initiation signal. with the Surveillance
, except for dampers and valves that Frequency are locked, sealed, or otherwise Control Program secured in the actuated position SR 3.6.4.3.4 Verify the SGT decay heat discharge In accordance dampers are in the correct position. with the Surveillance Frequency Control Program BFN-UNIT 3 3.6-54 Amendment No. 215, 284, 000
CREV System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for t 15 In accordance continuous minutes with the heaters with the operating. Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREV filter testing in In accordance accordance with the VFTP. with the VFTP SR 3.7.3.3 Verify each CREV subsystem actuates on an In accordance actual or simulated initiation signal. with the Surveillance
, except for dampers and valves that Frequency are locked, sealed, or otherwise secured in the actuated position Control Program SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program BFN-UNIT 3 3.7-12 Amendment No. 215, 261, 267, 284,
Attachment 1.2 Proposed TS Changes (Mark-Ups) for SQN Units 1 and 2 (6 pages)
CNL-22-037
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Attachment 2.1 Proposed TS Changes (Final Retyped) for BFN Units 1, 2, and 3 (12 pages)
CNL-22-037
ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.7 --------------------------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 1040 and In accordance 950 psig, the HPCI pump can develop a with the flow rate 5000 gpm against a system head Surveillance corresponding to reactor pressure. Frequency Control Program SR 3.5.1.8 --------------------------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 In accordance HPCI pump can develop a flow rate 5000 with the gpm against a system head corresponding to Surveillance reactor pressure. Frequency Control Program SR 3.5.1.9 --------------------------NOTE-------------------------
Vessel injection/spray may be excluded.
Verify each ECCS injection/spray subsystem In accordance actuates on an actual or simulated automatic with the initiation signal, except for dampers and Surveillance valves that are locked, sealed, or otherwise Frequency secured in the actuated position. Control Program (continued)
BFN-UNIT 1 3.5-6 Amendment No. 234, 263, 269, 315, ___
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 In accordance or simulated automatic initiation signal, except with the for dampers and valves that are locked, Surveillance sealed, or otherwise secured in the actuated Frequency position. Control Program BFN-UNIT 1 3.5-14 Amendment No. 234, 263, 315, ___
SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 In accordance continuous minutes with heaters operating. with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).
SR 3.6.4.3.3 Verify each SGT subsystem actuates on an In accordance actual or simulated initiation signal, except for with the dampers and valves that are locked, sealed, Surveillance or otherwise secured in the actuated position. Frequency Control Program SR 3.6.4.3.4 Verify the SGT decay heat discharge In accordance dampers are in the correct position. with the Surveillance Frequency Control Program BFN-UNIT 1 3.6-54 Amendment No. 235, 300, 315, ___
CREV System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for 15 In accordance continuous minutes with the heaters with the operating. Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREV filter testing in In accordance accordance with the VFTP. with the VFTP SR 3.7.3.3 Verify each CREV subsystem actuates on an In accordance actual or simulated initiation signal, except for with the dampers and valves that are locked, sealed, Surveillance or otherwise secured in the actuated position. Frequency Control Program SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program BFN-UNIT 1 3.7-11 Amendment 235, 275, 282, 300, 315, ___
ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.7 --------------------------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 1040 and In accordance 950 psig, the HPCI pump can develop a with the flow rate 5000 gpm against a system head Surveillance corresponding to reactor pressure. Frequency Control Program SR 3.5.1.8 --------------------------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 In accordance HPCI pump can develop a flow rate 5000 with the gpm against a system head corresponding to Surveillance reactor pressure. Frequency Control Program SR 3.5.1.9 --------------------------NOTE-------------------------
Vessel injection/spray may be excluded.
Verify each ECCS injection/spray subsystem In accordance actuates on an actual or simulated automatic with the initiation signal, except for dampers and Surveillance valves that are locked, sealed, or otherwise Frequency secured in the actuated position. Control Program (continued)
BFN-UNIT 2 3.5-6 Amendment No. 255, 338, ___
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 In accordance or simulated automatic initiation signal, except with the for dampers and valves that are locked, Surveillance sealed, or otherwise secured in the actuated Frequency position. Control Program BFN-UNIT 2 3.5-14 Amendment No. 255, 338, ___
SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 In accordance continuous minutes with heaters operating. with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).
SR 3.6.4.3.3 Verify each SGT subsystem actuates on an In accordance actual or simulated initiation signal, except for with the dampers and valves that are locked, sealed, Surveillance or otherwise secured in the actuated position. Frequency Control Program SR 3.6.4.3.4 Verify the SGT decay heat discharge In accordance dampers are in the correct position. with the Surveillance Frequency Control Program BFN-UNIT 2 3.6-54 Amendment No. 255, 324, 338, ___
CREV System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for 15 In accordance continuous minutes with the heaters with the operating. Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREV filter testing in In accordance accordance with the VFTP. with the VFTP SR 3.7.3.3 Verify each CREV subsystem actuates on an In accordance actual or simulated initiation signal, except for with the dampers and valves that are locked, sealed, Surveillance or otherwise secured in the actuated position. Frequency Control Program SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program BFN-UNIT 2 3.7-12 Amendment No. 255, 302, 308, 324, 338, ___
ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.7 --------------------------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 1040 and In accordance 950 psig, the HPCI pump can develop a with the flow rate 5000 gpm against a system head Surveillance corresponding to reactor pressure. Frequency Control Program SR 3.5.1.8 --------------------------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 In accordance HPCI pump can develop a flow rate 5000 with the gpm against a system head corresponding to Surveillance reactor pressure. Frequency Control Program SR 3.5.1.9 --------------------------NOTE-------------------------
Vessel injection/spray may be excluded.
Verify each ECCS injection/spray subsystem In accordance actuates on an actual or simulated automatic with the initiation signal, except for dampers and Surveillance valves that are locked, sealed, or otherwise Frequency secured in the actuated position. Control Program (continued)
BFN-UNIT 3 3.5-6 Amendment No. 215, 298, ___
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 In accordance or simulated automatic initiation signal, except with the for dampers and valves that are locked, Surveillance sealed, or otherwise secured in the actuated Frequency position. Control Program BFN-UNIT 3 3.5-14 Amendment No. 215, 298, ___
SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 In accordance continuous minutes with heaters operating. with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).
SR 3.6.4.3.3 Verify each SGT subsystem actuates on an In accordance actual or simulated initiation signal, except for with the dampers and valves that are locked, sealed, Surveillance or otherwise secured in the actuated position. Frequency Control Program SR 3.6.4.3.4 Verify the SGT decay heat discharge In accordance dampers are in the correct position. with the Surveillance Frequency Control Program BFN-UNIT 3 3.6-54 Amendment No. 215, 284, 298, ___
CREV System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for 15 In accordance continuous minutes with the heaters with the operating. Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREV filter testing in In accordance accordance with the VFTP. with the VFTP SR 3.7.3.3 Verify each CREV subsystem actuates on an In accordance actual or simulated initiation signal, except for with the dampers and valves that are locked, sealed, Surveillance or otherwise secured in the actuated position. Frequency Control Program SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program BFN-UNIT 3 3.7-12 Amendment No. 215, 261, 267, 284, 298, ___
Attachment 2.2 Proposed TS Changes (Final Retyped) for SQN Units 1 and 2 (6 pages)
CNL-22-037
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Attachment 3.1 Proposed TS Bases Page Changes (Mark-Ups) for BFN Unit 1 (For Information Only)
(4 pages)
CNL-22-037
ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.9 REQUIREMENTS (continued) 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 The SR excludes automatic automatic initiation logic of HPCI, CS, and LPCI will cause the dampers and valves that are locked, systems or subsystems to operate as designed, including sealed, or otherwise secured in the actuation of the system throughout its emergency operating actuated position. The SR does not sequence, automatic pump startup and actuation of all apply to dampers or valves that are automatic valves to their required positions. This SR also locked, sealed, or otherwise ensures that the HPCI System will automatically restart on an secured in the actuated position since the affected dampers or RPV low-low water level (Level 2) signal received subsequent to valves were verified to be in the an RPV high water level (Level 8) trip and that the suction is actuated position prior to being automatically transferred from the CST to the suppression pool.
locked, sealed, or otherwise The LOGIC SYSTEM FUNCTIONAL TEST performed in secured. Placing an automatic valve LCO 3.3.5.1 overlaps this Surveillance to provide complete or damper in a locked, sealed, or testing of the assumed safety function.
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 The Surveillance Frequency is controlled under the Surveillance to be repositioned to the non- Frequency Control Program.
actuated position to support the accident analysis. Restoration of an This SR is modified by a Note that excludes vessel automatic valve or damper to the non-actuated position requires injection/spray during the Surveillance. Since all active verification that the SR has been components are testable and full flow can be demonstrated by met within its required Frequency. recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.
(continued)
BFN-UNIT 1 B 3.5-18 Revision 0, 43, 123 March 22, 2020
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 perform 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 The SR excludes automatic cause the system to operate as designed, including actuation of dampers and valves that are locked, the system throughout its emergency operating sequence; that sealed, or otherwise secured in the is, automatic pump startup and actuation of all automatic valves actuated position. The SR does not to their required positions. This test also ensures the RCIC apply to dampers or valves that are locked, sealed, or otherwise System will automatically restart on an RPV low-low water level secured in the actuated position (Level 2) signal received subsequent to an RPV high water level since the affected dampers or (Level 8) trip. The LOGIC SYSTEM FUNCTIONAL TEST valves were verified to be in the performed in LCO 3.3.5.3 overlaps this Surveillance to provide actuated position prior to being complete testing of the assumed safety function.
locked, sealed, or otherwise secured. Placing an automatic valve The Surveillance Frequency is controlled under the Surveillance or damper in a locked, sealed, or otherwise secured position requires Frequency Control Program.
an assessment of the operability of the system or any supported This SR is modified by a Note that excludes vessel injection systems, including whether it is during the Surveillance. Since all active components are necessary for the valve or damper testable and full flow can be demonstrated by recirculation to be repositioned to the non- through the test line, coolant injection into the RPV is not actuated position to support the accident analysis. Restoration of an required during the Surveillance.
automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency.
(continued)
BFN-UNIT 1 B 3.5-37 Revision 0, 43, 123, 125 January 26, 2022
SGT System B 3.6.4.3 BASES SURVEILLANCE SR 3.6.4.3.3 REQUIREMENTS (continued) This SR verifies that each SGT subsystem starts on receipt of The SR excludes automatic an actual or simulated initiation signal. The Surveillance dampers and valves that are locked, Frequency is controlled under the Surveillance Frequency sealed, or otherwise secured in the Control Program.
actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise SR 3.6.4.3.4 secured in the actuated position since the affected dampers or valves were verified to be in the This SR verifies that the SGT decay heat discharge dampers actuated position prior to being are in the correct position. This ensures that the decay heat locked, sealed, or otherwise removal mode of SGT System operation is available. The secured. Placing an automatic valve Surveillance Frequency is controlled under the Surveillance or damper in a locked, sealed, or Frequency Control Program.
otherwise secured position requires an assessment of the operability of the system or any supported REFERENCES systems, including whether it is 1. 10 CFR 50, Appendix A, GDC 41.
necessary for the valve or damper to be repositioned to the non- 2. FSAR, Section 5.3.3.7.
actuated position to support the accident analysis. Restoration of an 3. FSAR, Section 14.6.
automatic valve or damper to the non-actuated position requires verification that the SR has been
- 4. NRC No.93-102, "Final Policy Statement on Technical met within its required Frequency. Specification Improvements," July 23, 1993.
BFN-UNIT 1 B 3.6-121 Revision 123 Amendment No. 235 March 22, 2020
CREV System B 3.7.3 BASES SURVEILLANCE SR 3.7.3.3 REQUIREMENTS (continued) This SR verifies that on an actual or simulated initiation signal, The SR excludes automatic each CREV subsystem starts and operates. This SR includes dampers and valves that are locked, verification that dampers necessary for proper CREV operation sealed, or otherwise secured in the function as required. The LOGIC SYSTEM FUNCTIONAL actuated position. The SR does not TEST in SR 3.3.7.1.4 and SR 3.3.7.1.6 overlaps this SR to apply to dampers or valves that are provide complete testing of the safety function. The locked, sealed, or otherwise Surveillance Frequency is controlled under the Surveillance secured in the actuated position since the affected dampers or Frequency Control Program.
valves were verified to be in the actuated position prior to being SR 3.7.3.4 locked, sealed, or otherwise secured. Placing an automatic valve This SR verifies the OPERABILITY of the CRE boundary by or damper in a locked, sealed, or testing for unfiltered air inleakage past the CRE boundary and otherwise secured position requires into the CRE. The details of the testing are specified in the an assessment of the operability of the system or any supported Control Room Envelope Habitability Program.
systems, including whether it is necessary for the valve or damper The CRE is considered habitable when the radiological dose to to be repositioned to the non- CRE occupants calculated in the licensing basis analyses of actuated position to support the DBA consequences is no more that 5 REM TEDE and the CRE accident analysis. Restoration of an occupants are protected from hazardous chemicals and smoke.
automatic valve or damper to the There is no automatic CREV actuation for hazardous chemical non-actuated position requires verification that the SR has been releases or smoke and there are no Surveillance Requirements met within its required Frequency. to verify the OPERABILITY in cases of hazardous chemicals or smoke. This SR verifies that the unfiltered air inleakage into the CRE is no greater than the flow rate assumed in the licensing basis analysis of DBA consequences. When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered. Required Action B.3 allows time to restore the CRE boundary to OPERABLE status provided mitigating actions can ensure that the CRE remains within the licensing basis habitability limits for occupants following an accident.
Compensatory measures are discussed in Regulatory Guide 1.196, Section C.2.7.3, (Ref. 6) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 7).
These compensatory measures may also be used as mitigating actions as required by Required Action B.2. Temporary analytical methods may also be used as compensatory BFN-UNIT 1 B 3.7-25 Revision 123 Amendment No. 235, 275 March 22, 2020
Attachment 3.2 Proposed TS Bases Page Changes (Mark-Ups) for SQN Unit 1 (For Information Only)
(3 pages)
CNL-22-037
EGTS Air Cleanup Subsystem B 3.6.10 BASES SURVEILLANCE REQUIREMENTS (continued)
The SR excludes automatic dampers and valves that are locked, SR 3.6.10.2 sealed, or otherwise secured in the actuated position. The SR does not This SR verifies that the required EGTS Air Cleanup Subsystem filter apply to dampers or valves that are testing is performed in accordance with the Ventilation Filter Testing locked, sealed, or otherwise Program (VFTP). The VFTP includes testing HEPA filter performance, secured in the actuated position charcoal adsorber efficiency, minimum system flow rate, and the physical since the affected dampers or properties of the activated charcoal (general use and following specific valves were verified to be in the operations). Specific test frequencies and additional information are actuated position prior to being discussed in detail in the VFTP.
locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or SR 3.6.10.3 otherwise secured position requires an assessment of the operability of the system or any supported The automatic startup ensures that each EGTS Air Cleanup Subsystem systems, including whether it is train responds properly.
necessary for the valve or damper to be repositioned to the non- The Surveillance Frequency is controlled under the Surveillance actuated position to support the Frequency Control Program.
accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires SR 3.6.10.4 verification that the SR has been met within its required Frequency. The EGTS Air Cleanup Subsystem filter cooling bypass valves are tested to verify OPERABILITY. The ability to cool the filters and adsorbers in an The SR excludes automatic valves inactive air cleanup unit is accomplished with two crossover flow ducts that are locked, sealed, or otherwise that draw a small stream of air from the active air cleanup unit through the secured in the actuated position. inactive air cleanup unit. The valves in the inactive train automatically The SR does not apply to valves receive a signal to open. The capability to manually open the suction that are locked, sealed, or otherwise valve for the inactive train and align to the affected unit is provided in the secured in the actuated position main control room to complete the flow path through the inactive unit.
since the affected valves were verified to be in the actuated The Surveillance Frequency is controlled under the Surveillance position prior to being locked, Frequency Control Program.
sealed, or otherwise secured.
Placing an automatic valve in a locked, sealed, or otherwise SR 3.6.10.5 secured position requires an assessment of the operability of the The proper functioning of the fans, dampers, filters, adsorbers, etc., as a system or any supported systems, system is verified by the ability of each train to produce the required including whether it is necessary for system flow rate.
the valve to be repositioned to the non-actuated position to support the The Surveillance Frequency is controlled under the Surveillance accident analysis. Restoration of an Frequency Control Program.
automatic valve to the non-actuated position requires verification that the SR has been met within its required Frequency.
SEQUOYAH - UNIT 1 B 3.6.10-4 Revision 45
CREVS B 3.7.10 BASES SURVEILLANCE REQUIREMENTS (continued)
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.7.10.3 This SR verifies that the required CREVS testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The The SR excludes automatic VFTP includes testing the performance of the HEPA filter, charcoal dampers and valves that are adsorber efficiency, minimum flow rate, and the physical properties of the locked, sealed, or otherwise activated charcoal. Specific test Frequencies and additional information secured in the actuated position. are discussed in detail in the VFTP.
The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated SR 3.7.10.4 position since the affected dampers or valves were verified to be in the This SR verifies that each CREVS train starts automatically, diverts its actuated position prior to being locked, sealed, or otherwise inlet flow through the HEPA filters and charcoal adsorbers, and operates secured. Placing an automatic valve on an actual or simulated (i.e., safety injection signal or a high radiation or damper in a locked, sealed, or signal from the air intake stream) actuation signal.
otherwise secured position requires an assessment of the operability of The Surveillance Frequency is controlled under the Surveillance the system or any supported Frequency Control Program.
systems, including whether it is necessary for the valve or damper to be repositioned to the non- SR 3.7.10.5 actuated position to support the accident analysis. Restoration of an This SR verifies the OPERABILITY of the CRE boundary by testing for automatic valve or damper to the unfiltered air inleakage past the CRE boundary and into the CRE. The non-actuated position requires details of the testing are specified in the Control Room Envelope verification that the SR has been Habitability Program.
met within its required Frequency.
The CRE is considered habitable when the radiological dose to CRE occupants calculated in the licensing basis analyses of DBA consequences is no more than 5 rem whole body or its equivalent to any part of the body and the CRE occupants are protected from hazardous chemicals and smoke. This SR verifies that the unfiltered air inleakage into the CRE is no greater than the flow rate assumed in the licensing basis analyses of DBA consequences. When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered.
Required Action B.3 allows time to restore the CRE boundary to OPERABLE status provided mitigating actions can ensure that the CRE remains within the licensing basis habitability limits for the occupants following an accident. Compensatory measures are discussed in Regulatory Guide 1.196, Section C.2.7.3, (Ref. 6) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 7). These SEQUOYAH - UNIT 1 B 3.7.10-7 Revision 45
ABGTS B 3.7.12 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.7.12.2 This SR verifies that the required ABGTS testing is performed in The SR excludes automatic accordance with the Ventilation Filter Testing Program (VFTP). The dampers and valves that are VFTP includes testing HEPA filter performance, charcoal adsorber locked, sealed, or otherwise efficiency, minimum system flow rate, and the physical properties of the secured in the actuated position. activated charcoal (general use and following specific operations).
The SR does not apply to Specific test frequencies and additional information are discussed in dampers or valves that are detail in the VFTP.
locked, sealed, or otherwise secured in the actuated position since the affected dampers or SR 3.7.12.3 valves were verified to be in the actuated position prior to being locked, sealed, or This SR verifies that each ABGTS train starts and operates on an actual otherwise secured. Placing an or simulated actuation signal. The SR is modified by two Notes that automatic valve or damper in a specify when verification of ABGTS actuation for each actuation signal is locked, sealed, or otherwise required to be met. ABGTS actuation on a Containment Phase A secured position requires an isolation signal is required to be met in MODES 1, 2, 3 and 4. ABGTS assessment of the operability of actuation on fuel storage pool area high radiation signal is required to be the system or any supported met during movement of irradiated fuel assemblies and with fuel stored in systems, including whether it is the spent fuel pool.
necessary for the valve or damper to be repositioned to the The Surveillance Frequency is controlled under the Surveillance non-actuated position to support Frequency Control Program.
the accident analysis. Restoration of an automatic valve or damper to the non-actuated position SR 3.7.12.4 requires verification that the SR has been met within its required This SR verifies the integrity of the auxiliary building enclosure (i.e., spent Frequency. fuel storage area and the ESF pump rooms). The ability of the auxiliary building to maintain negative pressure with respect to potentially uncontaminated adjacent areas is periodically tested to verify proper function of the ABGTS. During the post accident mode of operation, the ABGTS is designed to maintain a slight negative pressure in the auxiliary building, to prevent unfiltered LEAKAGE. The ABGTS is designed to maintain a pressure -0.25 inches water gauge with respect to atmospheric pressure at a flow rate 8,100 and 9,900 cfm to the auxiliary building.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SEQUOYAH - UNIT 1 B 3.7.12-5 Revision 45