Text

Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance.
	ML21337A227
Person / Time
Site:	Browns Ferry
Issue date:	12/03/2021
From:	Polickoski J; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CNL-21-002
	Download: ML21337A227 (175)
	v • d • e

{{#Wiki_filter:1101 Market Street, Chattanooga, Tennessee 37402 CNL-21-002 December 3, 2021 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Browns Ferry Nuclear 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

Subject:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program, and Rescind Surveillance Requirement Changes (BFN TS-536)

Reference:

Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 (EPID L-2020-LLA-0058), dated April 8, 2021 (ML21041A489) In accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 10 CFR 50.90, Tennessee Valley Authority (TVA) is submitting for Nuclear Regulatory Commission (NRC) approval, a request for an amendment to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. TVA requests adoption of Technical Specification Task Force (TSTF) Traveler TSTF-205-A, Revision 3, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. TSTF-205-A revises the NUREG-1433 standard technical specifications (STS) definitions of Channel Calibration, Channel Functional Test (CFT), and Logic System Functional Test. TSTF-563-A further revises the definitions of Channel Calibration and CFT (which with TSTF-205-A incorporated, permits performance by means of any series of sequential, overlapping, or total channel steps) to allow the required frequency for testing the components or devices in each step to be determined in accordance with the Technical Specifications (TS) surveillance frequency control program (SFCP).

U.S. Nuclear Regulatory Commission CNL-21-002 Page 2 December 3, 2021 Additionally, as approved in License Amendments 315, 338, and 298 (Reference), TVA consolidated 18 Surveillance Requirements (SR) that were rendered redundant by having the common Frequency of In accordance with the Surveillance Frequency Control Program. With the implementation of these license amendments, the magnitude of necessary BFN document changes was not recognized, as well as the increased potential for human error. Accordingly, this License Amendment Request (LAR) proposes the rescission of these consolidations. The Enclosure to this letter provides a description and assessment of the proposed change. Attachments 1.1, 1.2, and 1.3 provide the existing BFN Unit 1, 2, and 3 TS pages marked up to show the proposed changes. Attachments 2.1, 2.2, and 2.3 provide revised (re-typed) BFN TS pages. Attachment 3 provides the revised BFN Unit 1 TS Bases changes associated with TSTF-205-A and the SR rescissions, for information only (for purposes of this LAR, the BFN Units 1, 2, and 3 TS Bases are nearly identical). TVA has determined that there are no significant hazards consideration associated with the proposed change and that the license amendment qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and enclosures to the Alabama State Department of Public Health. Approval of the proposed license amendment is requested within 12 months of the date of this letter with implementation within 30 days following NRC approval. There are no new regulatory commitments made in this letter. Please address any questions regarding this submittal to Kimberly Hulvey, Senior Manager, Fleet Licensing, at 423-751-3275. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3rd day of December 2021. Respectfully, James T. Polickoski Director, Nuclear Regulatory Affairs

Enclosure:

Description and Assessment of the Proposed Change cc: NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health

CNL-21-002 Enclosure Description and Assessment of the Proposed Change for Browns Ferry Nuclear Units 1, 2, and 3

CNL-21-002 E-1 of 6 Enclosure Description and Assessment of the Proposed Change

Subject:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program, and Rescind Surveillance Requirement Changes (BFN TS-536) Table of Contents

1.0 DESCRIPTION

..................................................................................................................... 2

2.0 ASSESSMENT

..................................................................................................................... 2 2.1 Applicability of Safety Evaluation.................................................................................. 2 2.2 Optional Changes and Variations................................................................................. 3 2.3 Rescission of SR Consolidations.................................................................................. 3

3.0 REGULATORY ANALYSIS

.................................................................................................. 4 3.1 No Significant Hazards Consideration Analysis........................................................... 4 3.2 Conclusion.................................................................................................................... 6 4.0 ENVIRONMENTAL EVALUATION....................................................................................... 6

5.0 REFERENCES

..................................................................................................................... 6 Attachments 1.1 Proposed TS Changes (Markups) for BFN Unit 1 1.2 Proposed TS Changes (Markups) for BFN Unit 2 1.3 Proposed TS Changes (Markups) for BFN Unit 3 2.1 Proposed TS Changes (Final typed) for BFN Unit 1 2.2 Proposed TS Changes (Final typed) for BFN Unit 2 2.2 Proposed TS Changes (Final typed) for BFN Unit 3 3 Proposed TS Bases Changes (Markups for information only) for BFN Unit 1

Enclosure Description and Assessment of the Proposed Change CNL-21-002 E-2 of 6

1.0 DESCRIPTION

Tennessee Valley Authority (TVA) requests adoption of Technical Specification Task Force (TSTF) Traveler TSTF-205-A, Revision 3, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program into the Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 technical specifications (TS). TSTF-205-A revises the NUREG-1433 standard technical specifications (STS) definitions of Channel Calibration, Channel Functional Test (CFT), and Logic System Functional Test (LSFT). TSTF-563-A further revises the definitions of Channel Calibration and CFT (which with TSTF-205-A incorporated, permits performance by means of any series of sequential, overlapping, or total channel steps) to allow the required frequency for testing the components or devices in each step to be determined in accordance with the TS surveillance frequency control program (SFCP). Additionally, in Reference 1, TVA proposed consolidating 18 Surveillance Requirements (SR) that were rendered redundant by having the common Frequency of In accordance with the Surveillance Frequency Control Program. In Reference 2, the Nuclear Regulatory Commission provided approval with the issuance of License Amendments 315, 338, and 298. With the implementation of these license amendments, the magnitude of necessary BFN document changes were not recognized, as well as the increased potential for human error. Accordingly, this License Amendment Request (LAR) proposes the rescission of these consolidations.

2.0 ASSESSMENT

2.1 Applicability of Safety Evaluation TVA has reviewed the safety evaluation for TSTF-563 provided to the Technical Specifications Task Force in a letter dated December 4, 2018. This review included a review of the Nuclear Regulatory Commission (NRC) staffs evaluation, as well as the information provided in TSTF-563. As described herein, TVA has concluded that the justifications presented in TSTF-563 and the safety evaluation prepared by the NRC staff are applicable to BFN Units 1, 2, and 3 and justify this amendment for the incorporation of the changes to the BFN Unit 1, 2, and 3 TS. TSTF-205-A does not have an associated NRC staff evaluation. However, TVA has reviewed the traveler, and has determined that the changes provided in TSTF-205-A are applicable to BFN. An SFCP was incorporated into the BFN Unit 1, 2, and 3 Technical Specifications (TS) with the issuance of Reference 2.

Enclosure Description and Assessment of the Proposed Change CNL-21-002 E-3 of 6 2.2 Optional Changes and Variations TVA is not proposing any variations from the TS changes described in the TSTF-563-A or the applicable parts of the NRC staffs safety evaluation dated December 4, 2018. Similarly, TVA is not proposing any variations from the TS changes described in TSTF-205-A. However, TSTF-205-A provides clarifying TS Bases language for all CFT SRs that only a single contact change of state is required to provide relay verification. The following differences are noted: x BFN has several different CFT SR numbers than the analogous STS SR numbers. x BFN had CFTs that pertain to different instrument functions than STS. x STS has several CFT SRs that BFN does not have. x BFN adjusted the inserted wording to remove reference to refueling interval because the frequency is governed by the SFCP. These are considered to be administrative variations. 2.3 Rescission of SR Consolidations In Reference 1, TVA proposed the following SR consolidations in TS Section 3. These consolidations had been made because they now had the common Frequency In accordance with the Surveillance Frequency Control Program, and therefore appeared identical on the TS pages. - SR 3.3.1.1.4 (retained), 3.3.1.1.8 (deleted), and 3.3.1.1.12 (deleted): Perform CHANNEL FUNCTIONAL TEST - SR 3.3.1.2.1 (retained) and 3.3.1.2.3 (deleted): Perform CHANNEL CHECK - SR 3.3.5.1.3 (retained), 3.3.5.1.4 (deleted), and 3.3.5.1.5 (deleted): Perform CHANNEL CALIBRATION - SR 3.3.7.1.3 (retained) and 3.3.7.1.5 (deleted): Perform CHANNEL CALIBRATION - SR 3.3.7.1.4 (retained) and 3.3.7.1.6 (deleted): Perform LOGIC SYSTEM FUNCTIONAL TEST - SR 3.3.8.1.1 (retained) and 3.3.8.1.2 (deleted): Perform CHANNEL CALIBRATION. Similarly, SR 3.3.3.1.3 (Perform CHANNEL CALIBRATION of the Reactor Pressure Functions) was revised to read: Perform CHANNEL CALIBRATION, and SR 3.3.3.1.4 (Perform CHANNEL CALIBRATION for each required post-accident monitoring instrumentation channel except for the Reactor Pressure Function) was deleted. Lastly, SR 3.3.3.2.2 (Perform CHANNEL CALIBRATION for the Suppression Pool Water Level Function) was revised to read: Perform CHANNEL CALIBRATION, and SR 3.3.3.2.3 (Perform CHANNEL CALIBRATION for each required instrumentation channel except for the Suppression Pool Water Level Function) was deleted. While these changes were intended to simplify the TS and improved consistency with the ITS Writers Guide, the magnitude of BFN documents (e.g., Surveillance Instructions and Maintenance Plans) that would require revision was not recognized. Moreover, it was also not recognized that these consolidations would produce an error-likely situation because instrument

Enclosure Description and Assessment of the Proposed Change CNL-21-002 E-4 of 6 functions with different frequencies were tracked under the same SR number within the SFCP. Therefore, TVA proposes to restore the above SR consolidations to their prior status, albeit with Frequencies In accordance with the Surveillance Frequency Control Program. Although this is viewed as an administrative change, TVA has reviewed the SRs and associated Instrument Functions that are being restored and judge them to be eligible for application of the SFCP, consistent with the model safety evaluation contained in Federal Register Notice 74 FR 31996, which announced the availability of TSTF-425.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Analysis TVA requests adoption of TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program, into the TS of BFN, Units 1, 2, and 3. TSTF-205-A revises the NUREG-1433 STS definitions of Channel Calibration, CFT, and LSFT. TSTF-563-A further revises the definitions of Channel Calibration and CFT (which with TSTF-205-A incorporated, permits performance by means of any series of sequential, overlapping, or total channel steps) to allow the required frequency for testing the components or devices in each step to be determined in accordance with the TS SFCP. Additionally, this license amendment request restores the numbering of certain Surveillance Requirements that had been consolidated under License Amendments 315, 338, and 298 for BFN Units 1, 2, and 3, respectively. TVA 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 Regarding TSTF-205-A, the definitions of Channel Calibration, CFT, and LSFT specified in the TS provide basic information regarding what the test involves, the components involved in the test, and general information regarding how the test is to be performed. Regarding TSTF-563-A, the proposed change revises the TS definitions of Channel Calibration and CFT to allow the frequency for testing the components or devices in each step to be determined in accordance with the TS SFCP. All components in the channel continue to be tested. The frequency at which a channel test is performed is not an initiator of any accident previously evaluated, so the probability of an accident is not affected by the proposed change. The channels surveilled in accordance with the affected definitions continue to be required to be operable and the acceptance criteria of the surveillances are unchanged. As a result, any mitigating functions assumed in the accident analysis will continue to be performed. Rescission of the SR consolidations are administrative changes. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Enclosure Description and Assessment of the Proposed Change CNL-21-002 E-5 of 6

2.

Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated? Response: No Regarding TSTF-205-A, the proposed revisions to the definitions of Channel Calibration, CFT, and LSFT specified in the TS do not involve a change to the design or operation of any plant structure, system, or component (SSC). As a result, the plant will continue to be operated in the same manner. Regarding TSTF-563-A, the proposed change revises the TS definitions of Channel Calibration and CFT to allow the frequency for testing the components or devices in each step to be determined in accordance with the TS SFCP. The design function or operation of the components involved are not affected and there is no physical alteration of the plant (i.e., no new or different type of equipment will be installed). No credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases are introduced. The changes do not alter assumptions made in the safety analysis. The proposed changes are consistent with the safety analysis assumptions. Rescission of the SR consolidations are administrative changes. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Does the proposed amendment involve a significant reduction in a margin of safety? Response: No Regarding TSTF-205-A, the affected definitions involve testing of instrumentation used in the mitigation of accidents to ensure that the instrumentation will perform as assumed in the safety analyses. The proposed revisions of the definitions of Channel Calibration, CFT, and LSFT will not change their meaning or intent. Regarding TSTF-563-A, the proposed change revises the TS definitions of Channel Calibration and CFT to allow the frequency for testing the components or devices in each step to be determined in accordance with the TS SFCP. The SFCP assures sufficient safety margins are maintained, and that design, operation, surveillance methods, and acceptance criteria specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plants' licensing basis. The proposed change does not adversely affect existing plant safety margins, or the reliability of the equipment assumed to operate in the safety analysis. As such, there are no changes being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety as a result of the proposed change. Margins of safety are unaffected by method of determining surveillance test intervals under an NRC-approved licensee-controlled program. Rescission of the SR consolidations are administrative changes. 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.

Enclosure Description and Assessment of the Proposed Change CNL-21-002 E-6 of 6 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 NRC 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 EVALUATION The proposed license amendment 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.

5.0 REFERENCES

1. Letter from TVA to NRC, CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516), dated March 27, 2020 (ML20087P262)

2. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment Nos 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 (EPID L-2020-LLA-0058), dated April 8, 2021 (ML21041A489)

.1 CNL-21-002 Proposed Technical Specification Changes (Markups) for BFN Unit 1 (22 total pages) Note - The red markups pertain to TSTF-205-A. The green markups pertain to TSTF-563-A. The blue markups pertain to the SR rescissions.

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PAM Instrumentation 3.3.3.1 BFN-UNIT 1 3.3-25 Amendment No. 234, 253, 263, SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK for each required PAM instrumentation channel. In accordance with the Surveillance Frequency Control Program SR 3.3.3.1.2 (Deleted). SR 3.3.3.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program of the Reactor Pressure Functions SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for each required PAM instrumentation channel except for the Reactor Pressure Function. In accordance with the Surveillance Frequency Control Program

Backup Control System 3.3.3.2 BFN-UNIT 1 3.3-28 Amendment No. 234, 263, SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and transfer switch is capable of performing the intended function. In accordance with the Surveillance Frequency Control Program SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for HDFKUHTXLUHGLQVWUXPHQWDWLRQFKDQQHO. In accordance with the Surveillance Frequency Control Program the Suppression Pool Water Level Function SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each required instrumentation channel except for the Suppression Pool Water Level Function In accordance with the Surveillance Frequency Control Program HDFK UHTXLUHG LQVWUXPHQWDWLRQ FKDQQHO

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-41 Amendment No. 234, 263, SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 (Deleted) SR 3.3.5.1.5 (Deleted) SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (Deleted) (Deleted) Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-42 Amendment No. 234, 257, Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3 4(b) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4(b) B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4(b) 2 per trip system C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 435 psig and d 465 psig d. Core Spray Pump Discharge Flow - Low (Bypass) 1,2,3 2 1 per subsystem E SR 3.3.5.1.2 SR 3.3.5.1.3 t 1647 gpm and d 2910 gpm e. Core Spray Pump Start - Time Delay Relay Pumps A,B,C,D (with diesel power) 1,2,3 4 1 per pump C SR 3.3.5.1.3 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 6 seconds and d 8 seconds (continued) D Deleted E Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating." (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5 SR 3.3.5.1.4 SR 3 3 5 1 3

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-43 Amendment No. 234, 257, Table 3.3.5.1-1 (page 2 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System (continued) e. Core Spray Pump Start - Time Delay Relay (continued) Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 18 seconds and d 24 seconds 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4 B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4 C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 435 psig and d 465 psig (continued) D 'HOHWHG. E Deleted. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5 SR 3 3 5 1 3 SR 3.3.5.1.4

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-44 Amendment No. 234, 250, 257, Table 3.3.5.1-1 (page 3 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System (continued) d. Reactor Steam Dome Pressure - Low (Recirculation Discharge Valve Permissive)(e) 1(c),2(c), 3(c) 4 C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 215 psig and d 245 psig e. Reactor Vessel Water Level - Level 0 1,2,3 2 1 per subsystem B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 312 5/16 inches above vessel zero f. Low Pressure Coolant Injection Pump Start - Time Delay Relay Pump A,B,C,D (with diesel power) 1,2,3 4 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 18 seconds and d 24 seconds (continued) (a) Deleted. (c) With associated recirculation pump discharge valve open. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3.3.5.1.4 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5

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ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-46 Amendment No. 234, 257, 258, Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. ADS Trip System A (continued) b. Drywell Pressure - High(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Automatic Depressurization System Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.3 SR 3.3.5.1.6 d 115 seconds d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)(e) 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 528 inches above vessel zero e. Core Spray Pump Discharge Pressure - High 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig f. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1, 2(d), 3(d) 2 G SR 3.3.5.1.3 SR 3.3.5.1.6 d 322 seconds 5. ADS Trip System B a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1. SR 3.3.5.1. SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1. SR 3.3.5.1.6 d 2.5 psig (continued) (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 SR 3 3 5 1 SR 3.3.5.1.5 Relocate to next page

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CREV System Instrumentation 3.3.7.1 BFN-UNIT 1 3.3-68 Amendment No. 234, 263, SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREV initiation capability. 3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours provided the downscale trip of the inoperable channel is placed in the trip condition. SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. For each entry, add Frequency "In accordance with the Surveillance Frequency Control Program" Add these two new rows. SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

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LOP Instrumentation 3.3.8.1 BFN-UNIT 1 3.3-73 Amendment No. 235, SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function. SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 'HOHWHG SR 3.3.8.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program 'HOHWHG Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

LOP Instrumentation 3.3.8.1 BFN-UNIT 1 3.3-74 Amendment No. 234, Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS PER BOARD SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage) a. Board Undervoltage 2 SR 3.3.8.1. SR 3.3.8.1.3 Reset at t 2813 V and d 2927 V b. Diesel Start Initiation Time Delay 2 SR 3.3.8.1. SR 3.3.8.1.3 t 1.4 seconds and d 1.6 seconds 2. 4.16 kV Shutdown Board Undervoltage (Degraded Voltage) a. Board Undervoltage 3 SR 3.3.8.1.1 SR 3.3.8.1.3 t 3900 V and d 3940 V b.1 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 0.2 seconds and d 0.4 seconds b.2 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 3 seconds and d 5 seconds b.3 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 5.15 seconds and d 8.65 seconds b.4 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 0.9 seconds and d 1.7 seconds 3. 4.16 kV Shutdown Board Undervoltage (Unbalanced Voltage Relay) 3 SR 3.3.8.1. SR 3.3.8.1.3 1.5V at 3 seconds (Permissive Alarm) 3.4V at 8.65 seconds (Lo) 20V at 3.5 seconds (High) SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3.3.8.1.2 .2 CNL-21-002 Proposed Technical Specification Changes (Markups) for BFN Unit 2 (22 total pages) Note - The red markups pertain to TSTF-205-A. The green markups pertain to TSTF-563-A. The blue markups pertain to the SR rescissions.

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ECCS Instrumentation 3.3.5.1 BFN-UNIT 3.3-4 Amendment No. 2, 000 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 (Deleted) SR 3.3.5.1.5 (Deleted) SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (Deleted) (Deleted) Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-43 Amendment No. 253, 296, 000 Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3, 4(b) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4(b) B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4(b) 2 per trip system C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 435 psig and d 465 psig d. Core Spray Pump Discharge Flow - Low (Bypass) 1,2,3, 2 1 per subsystem E SR 3.3.5.1.2 SR 3.3.5.1.3 t 1647 gpm and d 2910 gpm e. Core Spray Pump Start - Time Delay Relay Pumps A,B,C,D (with diesel power) 1,2,3, 4 1 per pump C SR 3.3.5.1.3 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump A (with normal power) 1,2,3, 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3, 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 6 seconds and d 8 seconds (continued) D (Deleted) E Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating." (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5 SR 3 3 5 1 3 SR 3.3.5.1.4

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-44 Amendment No. 253, 296, 000 Table 3.3.5.1-1 (page 2 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System (continued) e. Core Spray Pump Start - Time Delay Relay (continued) Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3, 1 C SR 3.3.5.1.3 SR 3.3.5.1.6 t 18 seconds and d 24 seconds 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3, 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4 B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4 C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 435 psig and d 465 psig (continued) (a) Deleted. (b) Deleted. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5 SR 3 3 5 1 3 SR 3.3.5.1.4

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CREV System Instrumentation 3.3.7.1 BFN-UNIT 3.3-6 Amendment No. 2, 000 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREV initiation capability. 3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours provided the downscale trip of the inoperable channel is placed in the trip condition. SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. Add these two new rows. For each entry, add Frequency "In accordance with the Surveillance Frequency Control Program"

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LOP Instrumentation 3.3.8.1 BFN-UNIT 2 3.3-75 Amendment No. 253, Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS PER BOARD SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage) a. Board Undervoltage 2 SR 3.3.8.1. SR 3.3.8.1.3 Reset at t 2813 V and d 2927 V b. Diesel Start Initiation Time Delay 2 SR 3.3.8.1. SR 3.3.8.1.3 t 1.4 seconds and d 1.6 seconds 2. 4.16 kV Shutdown Board Undervoltage (Degraded Voltage) a. Board Undervoltage 3 SR 3.3.8.1.1 SR 3.3.8.1.3 t 3900 V and d 3940 V b.1 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 0.2 seconds and d 0.4 seconds b.2 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 3 seconds and d 5 seconds b.3 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 5.15 seconds and d 8.65 seconds b.4 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 0.9 seconds and d 1.7 seconds 3. 4.16 kV Shutdown Board Undervoltage (Unbalanced Voltage Relay) 3 SR 3.3.8.1. SR 3.3.8.1.3 1.5V at 3 seconds (Permissive Alarm) 3.4V at 8.65 seconds (Lo) 20V at 3.5 seconds (High) SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3.3.8.1.2 .3 CNL-21-002 Proposed Technical Specification Changes (Markups) for BFN Unit 3 (22 total pages) Note - The red markups pertain to TSTF-205-A. The green markups pertain to TSTF-563-A. The blue markups pertain to the SR rescissions.

all devices in the channel required for channel OPERABILITY and , and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step

of all devices in the channel required for channel OPERABILITY , and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step

required for OPERABILITY

RPS Instrumentation 3.3.1.1 BFN-UNIT 3 3.3-5 Amendment No. 213, 000 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program. SR 3.3.1.1.5 Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap. Prior to withdrawing SRMs from the fully inserted position SR 3.3.1.1.6

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

Only required to be met during entry into MODE 2 from MODE 1. Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program. SR 3.3.1.1.7 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program. SR 3.3.1.1.8 (Deleted) FRQWLQXHG (Deleted) Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

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RPS Instrumentation 3.3.1.1 BFN-UNIT 3 3.3-9 Amendment No. 212, 213, 221, 235, 254, 283, Table 3.3.1.1-1 (page 3 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 7. Scram Discharge Volume Water Level - High b. Float Switch 1,2 2 G SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons 5(a) 2 H SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons

8. Turbine Stop Valve - Closure t 26% RTP 4

E SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 d 10% closed

9. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low(d) t 26% RTP 2

E SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 t 550 psig

10. Reactor Mode Switch -

Shutdown Position 1,2 1 G SR 3.3.1.1.4 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.4 SR 3.3.1.1.14 NA

11. Manual Scram 1,2 1

G SR 3.3.1.1.4 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.4 SR 3.3.1.1.14 NA

12. RPS Channel Test Switches 1,2 2

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13. Deleted (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 1 1 4 SR 3 3 1 1 4 SR 3 3 1 1 4 SR 3 3 1 1 4 SR 3 3 1 1 4 SR 3 3 1 1 4 SR 3.3.1.1.8 SR 3 3 1 1 4 SR 3 3 1 1 4 SR 3.3.1.1.12

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SRM Instrumentation 3.3.1.2 BFN-UNIT 3 3.3-15 Amendment No. 213, 000 Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS 1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2(b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With IRMs on Range 2 or below. (b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector. (c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits. SR 3 3 1 2 1 SR 3.3.1.2.3

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ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-46 Amendment No. 213, 254, 000 Table 3.3.5.1-1 (page 4 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3. High Pressure Coolant Injection (HPCI) System a. Reactor Vessel Water Level Low Low, Level 2(f) 1, 2(d), 3(d) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 470 inches above vessel zero b. Drywell Pressure High(f) 1, 2(d),3(d) 4 B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Reactor Vessel Water Level High, Level 8 1, 2(d), 3(d) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 583 inches above vessel zero d. Condensate Header Level Low 1, 2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t Elev. 551 feet e. Suppression Pool Water Level High 1, 2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 7 inches above instrument zero f. High Pressure Coolant Injection Pump Discharge FlowLow (Bypass) 1, 2(d), 3(d) 1 E SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 671 gpm 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water Level Low Low Low, Level 1(f) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-47 Amendment No. 212, 213, 219 254, Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. ADS Trip System A (continued) b. Drywell Pressure High(f) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Automatic Depressurization System Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.3 SR 3.3.5.1.6 d 115 seconds d. Reactor Vessel Water Level Low, Level 3 (Confirmatory)(f) 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 528 inches above vessel zero e. Core Spray Pump Discharge Pressure High 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig f. Low Pressure Coolant Injection Pump Discharge Pressure High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1, 2(d), 3(d) 2 G SR 3.3.5.1.3 SR 3.3.5.1.6 d 322 seconds 5. ADS Trip System B a. Reactor Vessel Water Level Low Low Low, Level 1(f) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-48 Amendment No. 213, 254, 000 Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. ADS Trip System B (continued) b. Drywell Pressure High(f) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 2.5 psig c. Automatic Depressurization System Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.3 SR 3.3.5.1.6 d 115 seconds d. Reactor Vessel Water Level Low, Level 3 (Confirmatory)(f) 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 528 inches above vessel zero e. Core Spray Pump Discharge Pressure High 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig f. Low Pressure Coolant Injection Pump Discharge Pressure High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1, 2(d), 3(d) 2 G SR 3.3.5.1.3 SR 3.3.5.1.6 d 322 seconds (d) With reactor steam dome pressure > 150 psig. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3 3 5 1 3 SR 3.3.5.1.5

CREV System Instrumentation 3.3.7.1 BFN-UNIT 3.3-6 Amendment No. 2, 000 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREV initiation capability. 3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours provided the downscale trip of the inoperable channel is placed in the trip condition. SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. Add these two new rows. For each entry, add Frequency "In accordance with the Surveillance Frequency Control Program"

CREV System Instrumentation 3.3.7.1 BFN-UNIT 3 3.3-70 Amendment No. 212, 213, 219, 249, Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Reactor Vessel Water Level - Low, Level 3 1,2,3 2 B SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 t 528 inches above vessel zero 2. Drywell Pressure - High 1,2,3 2 B SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 2.5 psig 3. Reactor Zone Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 100 mR/hr 4. Refueling Floor Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 100 mR/hr 5. Control Room Air Supply Duct Radiation - High 1,2,3 1 D SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 270 cpm above background SR 3 3 7 1 3 SR 3 3 7 1 3 SR 3 3 7 1 3 SR 3 3 7 1 3 SR 3.3.7.1.5 SR 3 3 7 1 4 SR 3 3 7 1 4 SR 3 3 7 1 4 SR 3 3 7 1 4 SR 3.3.7.1.6

/23,QVWUXPHQWDWLRQ %)181,7 $PHQGPHQW1R 6859(,//$1&(5(48,5(0(176 127( 5HIHUWR7DEOHWRGHWHUPLQHZKLFK65VDSSO\\IRUHDFK/23)XQFWLRQ 6859(,//$1&( )5(48(1&< 65 3HUIRUP&+$11(/&$/,%5$7,21 ,QDFFRUGDQFH ZLWKWKH 6XUYHLOODQFH )UHTXHQF\\ &RQWURO3URJUDP 65 'HOHWHG 65 3HUIRUP/2*,&6<67(0)81&7,21$/ 7(67 ,QDFFRUGDQFH ZLWKWKH 6XUYHLOODQFH )UHTXHQF\\ &RQWURO3URJUDP 'HOHWHG Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

LOP Instrumentation 3.3.8.1 BFN-UNIT 3 3.3-75 Amendment No. 213, Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS PER BOARD SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage) a. Board Undervoltage 2 SR 3.3.8.1. SR 3.3.8.1.3 Reset at t 2813 V and d 2927 V b. Diesel Start Initiation Time Delay 2 SR 3.3.8.1. SR 3.3.8.1.3 t 1.4 seconds and d 1.6 seconds 2. 4.16 kV Shutdown Board Undervoltage (Degraded Voltage) a. Board Undervoltage 3 SR 3.3.8.1.1 SR 3.3.8.1.3 t 3900 V and d 3940 V b.1 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 0.2 seconds and d 0.4 seconds b.2 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 3 seconds and d 5 seconds b.3 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 5.15 seconds and d 8.65 seconds b.4 Time Delay 1 SR 3.3.8.1. SR 3.3.8.1.3 t 0.9 seconds and d 1.7 seconds

3. 4.16 kV Shutdown Board Undervoltage (Unbalanced Voltage Relay) 3 SR 3.3.8.1.

SR 3.3.8.1.3 1.5V at 3 seconds (Permissive Alarm) 3.4V at 8.65 seconds (Lo) 20V at 3.5 seconds (High) SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3 3 8 1 SR 3.3.8.1.2 .1 CNL-21-002 Proposed Technical Specification Changes (Final Typed) for BFN Unit 1 (22 total pages)

Definitions 1.1 BFN-UNIT 1 1.1-1 (continued) Amendment No. 234, BBB000 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. Term Definition ACTIONS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) CHANNEL CALIBRATION ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. The APLHGR shall be applicable to a specific planar height and is equal to the sum of the LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height. A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and WKHCHANNEL FUNCTIONAL TEST. Non-calibratable devices are excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TESTS and source checks. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

Definitions 1.1 BFN-UNIT 1 1.1-2 (continued) Amendment No. 234, BBB000 1.1 Definitions (continued) CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step. CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and b. Control rod movement, provided there are no fuel assemblies in the associated core cell. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

Definitions 1.1 BFN-UNIT 1 1.1-5 (continued) Amendment No. 234, 262, BBB 1.1 Definitions (continued) LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR) MODE A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested. The MCPR shall be the smallest critical power ratio (CPR) that exists in the core. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power. A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

RPS Instrumentation 3.3.1.1 BFN-UNIT 1 3.3-4 Amendment No. 234, 262, 315, ___ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap. Prior to withdrawing SRMs from the fully inserted position SR 3.3.1.1.6

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

Only required to be met during entry into MODE 2 from MODE 1. Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.7 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 BFN-UNIT 1 3.3-5 Amendment No. 234, 262, 263, 266, 299, 310, 315, ___ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 (Deleted) SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.13

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

Neutron detectors are excluded. Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 Verify Turbine Stop Valve Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure Low Functions are not bypassed when THERMAL POWER is t 26% RTP. In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 BFN-UNIT 1 3.3-7 Amendment No. 234, 250, 257, 262, 266, 269, 281, 310, 315, ___ Table 3.3.1.1-1 (page 2 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. Average Power Range Monitors (continued) d. Inop 1,2 3(b) G SR 3.3.1.1.16 NA e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.16 NA f. OPRM Upscale 18%(f) 3(b) I SR 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 NA 3. Reactor Vessel Steam Dome Pressure - High(d) 1,2 2 G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 d 1090 psig 4. Reactor Vessel Water Level - Low, Level 3(d) 1,2 2 G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 t 528 inches above vessel zero 5. Main Steam Isolation Valve - Closure 1 8 F SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 10% closed

6. High Drywell Pressure 1,2 2

G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 2.5 psig 7. Scram Discharge Volume Water Level - High a. Resistance Temperature Detector 1,2 2 G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 50 gallons 5(a) 2 H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 50 gallons (continued) (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (b) Each APRM channel provides inputs to both trip systems. (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. (f) Following Detect and Suppress Solution - Confirmation Density (DSS-CD) implementation, DSS-CD is not required to be armed while in the DSS-CD Armed Region during the first reactor startup and during the first controlled shutdown that passes completely through the DSS-CD Armed Region. However, DSS-CD is considered OPERABLE and shall be maintained OPERABLE and capable of automatically arming for operation at recirculation drive flow rates above the DSS-CD Armed Region.

RPS Instrumentation 3.3.1.1 BFN-UNIT 1 3.3-8 Amendment No. 234, 257, 299, 315, ___ Table 3.3.1.1-1 (page 3 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

7. Scram Discharge Volume Water Level - High (continued) b.

Float Switch 1,2 2 G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons 5(a) 2 H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons

8. Turbine Stop Valve - Closure t 26% RTP 4

E SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 d 10% closed

9. Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low(d) t 26% RTP 2 E SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 t 550 psig

10. Reactor Mode Switch -

Shutdown Position 1,2 1 G SR 3.3.1.1.12 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.12 SR 3.3.1.1.14 NA

11. Manual Scram 1,2 1

G SR 3.3.1.1.8 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.8 SR 3.3.1.1.14 NA

12. RPS Channel Test Switches 1,2 2

G SR 3.3.1.1.4 NA 5(a) 2 H SR 3.3.1.1.4 NA (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

SRM Instrumentation 3.3.1.2 BFN-UNIT 1 3.3-11 Amendment No. 234, 315, ___ SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions. SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2

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

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

SRM Instrumentation 3.3.1.2 BFN-UNIT 1 3.3-14 Amendment No. 234, 315, ___ Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS 1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2(b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With IRMs on Range 2 or below. (b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector. (c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

PAM Instrumentation 3.3.3.1 BFN-UNIT 1 3.3-25 Amendment No. 234, 253, 263, BBB SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK for each required PAM instrumentation channel. In accordance with the Surveillance Frequency Control Program SR 3.3.3.1.2 (Deleted). SR 3.3.3.1.3 PerformCHANNEL CALIBRATIONRIWKH 5HDFWRU3UHVVXUH)XQFWLRQV. In accordance with the Surveillance Frequency Control Program SR 3.3.3.1. PerformCHANNEL CALIBRATIONIRU HDFKUHTXLUHG3$0LQVWUXPHQWDWLRQ FKDQQHOH[FHSWIRUWKH5HDFWRU3UHVVXUH )XQFWLRQ. In accordance with the Surveillance Frequency Control Program

Backup Control System 3.3.3.2 BFN-UNIT 1 3.3-28 Amendment No. 234, 263, BBB SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and transfer switch is capable of performing the intended function. In accordance with the Surveillance Frequency Control Program SR 3.3.3.2.2 Perform CHANNEL CALIBRATION IRU WKH6XSSUHVVLRQ3RRO:DWHU)XQFWLRQ. In accordance with the Surveillance Frequency Control Program SR 3.3.3.2. Perform CHANNEL CALIBRATION IRU HDFKUHTXLUHGLQVWUXPHQWDWLRQFKDQQHO H[FHSWIRUWKH6XSSUHVVLRQ 3RRO :DWHU )XQFWLRQ. In accordance with the Surveillance Frequency Control Program 234

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-41 Amendment No. 234, 263, 315, ___ SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-42 Amendment No. 234, 257, 315, ___ Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3 4(b) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4(b) B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4(b) 2 per trip system C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 435 psig and d 465 psig d. Core Spray Pump Discharge Flow - Low (Bypass) 1,2,3 2 1 per subsystem E SR 3.3.5.1.2 SR 3.3.5.1.5 t 1647 gpm and d 2910 gpm e. Core Spray Pump Start - Time Delay Relay Pumps A,B,C,D (with diesel power) 1,2,3 4 1 per pump C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds (continued) D 'HOHWHG. E Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating." (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. 315

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-43 Amendment No. 234, 257, 315, ___ Table 3.3.5.1-1 (page 2 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System (continued) e. Core Spray Pump Start - Time Delay Relay (continued) Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 18 seconds and d 24 seconds 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4 B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4 C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 435 psig and d 465 psig (continued) D 'HOHWHG. E Deleted. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. 315

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-44 Amendment No. 234, 250, 257, 315, ___ Table 3.3.5.1-1 (page 3 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System (continued) d. Reactor Steam Dome Pressure - Low (Recirculation Discharge Valve Permissive)(e) 1(c),2(c), 3(c) 4 C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 215 psig and d 245 psig e. Reactor Vessel Water Level - Level 0 1,2,3 2 1 per subsystem B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 312 5/16 inches above vessel zero f. Low Pressure Coolant Injection Pump Start - Time Delay Relay Pump A,B,C,D (with diesel power) 1,2,3 4 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 18 seconds and d 24 seconds (continued) (a) 'HOHWHG. (c) With associated recirculation pump discharge valve open. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-45 Amendment No. 234, 257, 315, ___ Table 3.3.5.1-1 (page 4 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3. High Pressure Coolant Injection (HPCI) System a. Reactor Vessel Water Level - Low Low, Level 2(e) 1, 2(d), 3(d) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 470 inches above vessel zero b. Drywell Pressure - High(e) 1, 2(d),3(d) 4 B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Vessel Water Level - High, Level 8 1, 2(d), 3(d) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 583 inches above vessel zero d. Condensate Header Level - Low 1, 2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t Elev. 551 feet e. Suppression Pool Water Level - High 1, 2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 7 inches above instrument zero f. High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2(d), 3(d) 1 E SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 671 gpm 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-46 Amendment No. 234, 257, 258, 315, ___ Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. ADS Trip System A (continued) b. Drywell Pressure - High(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Automatic Depressurization System Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 115 seconds d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)(e) 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 528 inches above vessel zero e. Core Spray Pump Discharge Pressure - High 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig f. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1, 2(d), 3(d) 2 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 322 seconds 5. ADS Trip System B a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-47 Amendment No. 234, 257, 258, 315, ___ Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. ADS Trip System B (continued)

b. Drywell Pressure - High(e) 1, 2(d), 3(d) 2 F

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig

c. Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 115 seconds

d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)(e) 1, 2(d), 3(d) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 528 inches above vessel zero

e. Core Spray Pump Discharge Pressure - High 1,

2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig

f.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig

g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1,

2(d), 3(d) 2 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 322 seconds (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

CREV System Instrumentation 3.3.7.1 BFN-UNIT 1 3.3-68 Amendment No. 234, 263, 315, ___ SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREV initiation capability.

3.

For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours provided the downscale trip of the inoperable channel is placed in the trip condition. SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

CREV System Instrumentation 3.3.7.1 BFN-UNIT 1 3.3-69 Amendment No. 234, 251, 258, 315, ___ Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Reactor Vessel Water Level - Low, Level 3 1,2,3 2 B SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1. t 528 inches above vessel zero 2. Drywell Pressure - High 1,2,3 2 B SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 2.5 psig 3. Reactor Zone Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 100 mR/hr 4. Refueling Floor Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 100 mR/hr 5. Control Room Air Supply Duct Radiation - High 1,2,3 1 D SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 270 cpm above background

LOP Instrumentation 3.3.8.1 BFN-UNIT 1 3.3-73 Amendment No. 235, 315, ___ SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function. SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

LOP Instrumentation 3.3.8.1 BFN-UNIT 1 3.3-74 Amendment No. 234, 309, 315, ___ Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS PER BOARD SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage)

a. Board Undervoltage 2

SR 3.3.8.1.2 SR 3.3.8.1.3 Reset at t 2813 V and d 2927 V

b. Diesel Start Initiation Time Delay 2

SR 3.3.8.1.2 SR 3.3.8.1.3 t 1.4 seconds and d 1.6 seconds

2. 4.16 kV Shutdown Board Undervoltage (Degraded Voltage)

a. Board Undervoltage 3

SR 3.3.8.1.1 SR 3.3.8.1.3 t 3900 V and d 3940 V b.1 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 0.2 seconds and d 0.4 seconds b.2 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 3 seconds and d 5 seconds b.3 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 5.15 seconds and d 8.65 seconds b.4 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 0.9 seconds and d 1.7 seconds

3. 4.16 kV Shutdown Board Undervoltage (Unbalanced Voltage Relay) 3 SR 3.3.8.1.2 SR 3.3.8.1.3 1.5V at 3 seconds (Permissive Alarm) 3.4V at 8.65 seconds (Lo) 20V at 3.5 seconds (High)

.2 CNL-21-002 Proposed Technical Specification Changes (Final Typed) for BFN Unit 2 (22 total pages)

Definitions 1.1 BFN-UNIT 2 1.1-1 (continued) Amendment No. 253, BBB 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) The APLHGR shall be applicable to a specific planar height and is equal to the sum of the LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Non-calibratable devices are excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TESTS and source checks. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

Definitions 1.1 BFN-UNIT 2 1.1-2 (continued) Amendment No. 253, BBB 1.1 Definitions (continued) CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step. CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and b. Control rod movement, provided there are no fuel assemblies in the associated core cell. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

Definitions 1.1 BFN-UNIT 2 1.1-5 (continued) Amendment No. 253,BBB 1.1 Definitions (continued) LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR) MODE A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested. The MCPR shall be the smallest critical power ratio (CPR) that exists in the core. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power. A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel. OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RPS Instrumentation 3.3.1.1 BFN-UNIT 2 3.3-5 Amendment No. 253, 338, ___ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap. Prior to withdrawing SRMs from the fully inserted position SR 3.3.1.1.6

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

Only required to be met during entry into MODE 2 from MODE 1. Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.7 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 BFN-UNIT 2 3.3-6 Amendment No. 258, 323, 333, 338, ___ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 (Deleted) SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.13

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

Neutron detectors are excluded. Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 Verify Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are not bypassed when THERMAL POWER is t 26% RTP. In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 BFN-UNIT 2 3.3-8 Amendment No. 253, 254, 258, 260, 296, 309, 333, 338, ___ Table 3.3.1.1-1 (page 2 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. Average Power Range Monitors (continued)

d. Inop 1,2 3(b)

G SR 3.3.1.1.16 NA

e. 2-Out-Of-4 Voter 1,2 2

G SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.16 NA

f.

OPRM Upscale 18%(f) 3(b) I SR 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 NA

3. Reactor Vessel Steam Dome Pressure - High(d) 1,2 2

G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 d 1090 psig

4. Reactor Vessel Water Level - Low, Level 3(d) 1,2 2

G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 t 528 inches above vessel zero

5. Main Steam Isolation Valve -

Closure 1 8 F SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 10% closed

6. Drywell Pressure - High 1,2 2

G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 2.5 psig

7. Scram Discharge Volume Water Level - High

a. Resistance Temperature Detector 1,2 2

G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 50 gallons 5(a) 2 H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 50 gallons (continued) (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (b) Each APRM channel provides inputs to both trip systems. (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. (f) Following Detect and Suppress Solution - Confirmation Density (DSS-CD) implementation, DSS-CD is not required to be armed in the DSS-CD Armed Region during the first reactor startup and during the first controlled shutdown that passes completely through the DSS-CD Armed Region. However, DSS-CD is considered OPERABLE and shall be maintained OPERABLE and capable of automatically arming for operation at recirculation drive flow rates above the DSS-CD Armed Region.

RPS Instrumentation 3.3.1.1 BFN-UNIT 2 3.3-9 Amendment No. 258, 276, 296, 323, 338, ___ Table 3.3.1.1-1 (page 3 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

7. Scram Discharge Volume Water Level - High (continued)

b. Float Switch 1,2 2

G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons 5(a) 2 H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons

8. Turbine Stop Valve - Closure t 26% RTP 4

E SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 d 10% closed

9. Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low(d) t 26% RTP 2 E SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 t 550 psig

10. Reactor Mode Switch -

Shutdown Position 1,2 1 G SR 3.3.1.1.12 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.12 SR 3.3.1.1.14 NA

11. Manual Scram 1,2 1

G SR 3.3.1.1.8 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.8 SR 3.3.1.1.14 NA

12. RPS Channel Test Switches 1,2 2

G SR 3.3.1.1.4 NA 5(a) 2 H SR 3.3.1.1.4 NA 13.Deleted (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

SRM Instrumentation 3.3.1.2 BFN-UNIT 2 3.3-12 Amendment No. 253, 338, ___ SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions. SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2

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

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

SRM Instrumentation 3.3.1.2 BFN-UNIT 2 3.3-15 Amendment No. 253, 338, ___ Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2

SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2(b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With IRMs on Range 2 or below. (b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector. (c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

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ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-42 Amendment No. 255, 338, ___ SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-43 Amendment No. 253, 296, 338, ___ Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3 4(b) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4(b) B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4(b) 2 per trip system C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 435 psig and d 465 psig d. Core Spray Pump Discharge Flow - Low (Bypass) 1,2,3 2 1 per subsystem E SR 3.3.5.1.2 SR 3.3.5.1.5 t 1647 gpm and d 2910 gpm e. Core Spray Pump Start - Time Delay Relay Pumps A,B,C,D (with diesel power) 1,2,3 4 1 per pump C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds (continued) D 'HOHWHG E Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating." (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. 338

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-44 Amendment No. 253, 296, 338, ___ Table 3.3.5.1-1 (page 2 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System (continued) e. Core Spray Pump Start - Time Delay Relay (continued) Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 18 seconds and d 24 seconds 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1,2,3 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure - High(e) 1,2,3 4 B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive and ECCS Initiation)(e) 1,2,3 4 C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 435 psig and d 465 psig 4 B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 435 psig and d 465 psig (continued) D 'HOHWHG E Deleted. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. 338

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-45 Amendment No. 253, 289, 296, 338, ___ Table 3.3.5.1-1 (page 3 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System (continued) d. Reactor Steam Dome Pressure - Low (Recirculation Discharge Valve Permissive)(e) 1(c),2(c), 3(c) 4 C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 215 psig and d 245 psig e. Reactor Vessel Water Level - Level 0 1,2,3 2 1 per subsystem B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 312 5/16 inches above vessel zero f. Low Pressure Coolant Injection Pump Start - Time Delay Relay Pump A,B,C,D (with diesel power) 1,2,3 4 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 18 seconds and d 24 seconds (continued) (a) 'HOHWHG. (c) With associated recirculation pump discharge valve open. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-46 Amendment No. 253, 296, 338, ___ Table 3.3.5.1-1 (page 4 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3. High Pressure Coolant Injection (HPCI) System a. Reactor Vessel Water Level - Low Low, Level 2(e) 1, 2(d), 3(d) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 470 inches above vessel zero b. Drywell Pressure - High(e) 1, 2(d),3(d) 4 B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Vessel Water Level - High, Level 8 1, 2(d), 3(d) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 583 inches above vessel zero d. Condensate Header Level - Low 1, 2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t Elev. 551 feet e. Suppression Pool Water Level - High 1, 2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 7 inches above instrument zero f. High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2(d), 3(d) 1 E SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 671 gpm 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-47 Amendment No. 253, 260, 296, 338, ___ Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. ADS Trip System A (continued) b. Drywell Pressure - High(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Automatic Depressurization System Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 115 seconds d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)(e) 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 528 inches above vessel zero e. Core Spray Pump Discharge Pressure - High 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig f. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1, 2(d), 3(d) 2 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 322 seconds 5. ADS Trip System B a. Reactor Vessel Water Level - Low Low Low, Level 1(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-48 Amendment No. 253, 296, 338, ___ Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. ADS Trip System B (continued) b. Drywell Pressure - High(e) 1, 2(d), 3(d) 2 F SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Automatic Depressurization System Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 115 seconds d. Reactor Vessel Water Level - Low, Level 3 (Confirmatory)(e) 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 528 inches above vessel zero e. Core Spray Pump Discharge Pressure - High 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig f. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1, 2(d), 3(d) 2 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 322 seconds (d) With reactor steam dome pressure > 150 psig. (e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

CREV System Instrumentation 3.3.7.1 BFN-UNIT 2 3.3-69 Amendment No. 255, 338, ___ SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREV initiation capability. 3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours provided the downscale trip of the inoperable channel is placed in the trip condition. SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

CREV System Instrumentation 3.3.7.1 BFN-UNIT 2 3.3-70 Amendment No. 253, 260, 290, 338, ___ Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Reactor Vessel Water Level - Low, Level 3 1,2,3 2 B SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 t 528 inches above vessel zero 2. Drywell Pressure - High 1,2,3 2 B SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 2.5 psig 3. Reactor Zone Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 100 mR/hr 4. Refueling Floor Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 100 mR/hr 5. Control Room Air Supply Duct Radiation - High 1,2,3 1 D SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 270 cpm above background

LOP Instrumentation 3.3.8.1 BFN-UNIT 2 3.3-74 Amendment No. 255, 338, ___ SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function. SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

LOP Instrumentation 3.3.8.1 BFN-UNIT 2 3.3-75 Amendment No. 253, 332, 338, ___ Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS PER BOARD SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage)

a. Board Undervoltage 2

SR 3.3.8.1.2 SR 3.3.8.1.3 Reset at t 2813 V and d 2927 V

b. Diesel Start Initiation Time Delay 2

SR 3.3.8.1.2 SR 3.3.8.1.3 t 1.4 seconds and d 1.6 seconds

2. 4.16 kV Shutdown Board Undervoltage (Degraded Voltage)

a. Board Undervoltage 3

SR 3.3.8.1.1 SR 3.3.8.1.3 t 3900 V and d 3940 V b.1 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 0.2 seconds and d 0.4 seconds b.2 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 3 seconds and d 5 seconds b.3 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 5.15 seconds and d 8.65 seconds b.4 Time Delay

3. 4.16 kV Shutdown Board Undervoltage (Unbalanced Voltage Relay) 1 3

SR 3.3.8.1.2 SR 3.3.8.1.3 SR 3.3.8.1.2 SR 3.3.8.1.3 t 0.9 seconds and d 1.7 seconds 1.5V at 3 seconds (Permissive Alarm) 3.4V at 8.65 seconds (Lo) 20V at 3.5 seconds (High) .3 CNL-21-002 Proposed Technical Specification Changes (Final Typed) for BFN Unit 3 (22 total pages)

Definitions 1.1 BFN-UNIT 3 1.1-1 (continued) Amendment No. 212, BBB000 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) The APLHGR shall be applicable to a specific planar height and is equal to the sum of the LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Non-calibratable devices are excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TESTS and source checks. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

Definitions 1.1 BFN-UNIT 3 1.1-2 (continued) Amendment No. 212, BBB0 1.1 Definitions (continued) CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step. CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and b. Control rod movement, provided there are no fuel assemblies in the associated core cell. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

Definitions 1.1 BFN-UNIT 3 1.1-5 (continued) Amendment No. 213, BBB0 1.1 Definitions (continued) LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR) MODE A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested. The MCPR shall be the smallest critical power ratio (CPR) that exists in the core. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power. A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel. OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RPS Instrumentation 3.3.1.1 BFN-UNIT 3 3.3-5 Amendment No. 213, 298, ___ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap. Prior to withdrawing SRMs from the fully inserted position SR 3.3.1.1.6

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

Only required to be met during entry into MODE 2 from MODE 1. Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.7 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 BFN-UNIT 3 3.3-6 Amendment No. 212, 213, 215, 221, 283, 293, 298, ___ SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 (Deleted) SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.13

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

Neutron detectors are excluded. Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 Verify Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are not bypassed when THERMAL POWER is t 26% RTP. In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 BFN-UNIT 3 3.3-8 Amendment No. 212, 213, 214, 219, 221, 254, 268, 293, 298, ___ Table 3.3.1.1-1 (page 2 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. Average Power Range Monitors (continued) d. Inop 1,2 3(b) G SR 3.3.1.1.16 NA e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.16 NA f. OPRM Upscale 18%(f) 3(b) I SR 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 NA(e) 3. Reactor Vessel Steam Dome Pressure - High(d) 1,2 2 G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 d 1090 psig 4. Reactor Vessel Water Level - Low, Level 3(d) 1,2 2 G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 t 528 inches above vessel zero 5. Main Steam Isolation Valve - Closure 1 8 F SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 10% closed 6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 2.5 psig 7. Scram Discharge Volume Water Level - High a. Resistance Temperature Detector 1,2 2 G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 50 gallons 5(a) 2 H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 50 gallons (continued) (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (b) Each APRM channel provides inputs to both trip systems. (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. (f) Following Detect and Suppress Solution - Confirmation Density (DSS-CD) implementation, DSS-CD is not required to be armed while in the DSS-DC Armed Region during the first reactor startup and during the first controlled shutdown that passes completely through the DSS-CD Armed Region. However, DSS-CD is considered OPERABLE and shall be maintained OPERABLE and capable of automatically arming for operation at recirculation drive flow rates above the DSS-CD Armed Region.

RPS Instrumentation 3.3.1.1 BFN-UNIT 3 3.3-9 Amendment No. 212, 213, 221, 235, 254, 283, 298, ___ Table 3.3.1.1-1 (page 3 of 3) Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 7. Scram Discharge Volume Water Level - High b. Float Switch 1,2 2 G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons 5(a) 2 H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 d 46 gallons

8. Turbine Stop Valve - Closure t 26% RTP 4

E SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 d 10% closed

9. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low(d) t 26% RTP 2

E SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 t 550 psig

10. Reactor Mode Switch -

Shutdown Position 1,2 1 G SR 3.3.1.1.12 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.12 SR 3.3.1.1.14 NA

11. Manual Scram 1,2 1

G SR 3.3.1.1.8 SR 3.3.1.1.14 NA 5(a) 1 H SR 3.3.1.1.8 SR 3.3.1.1.14 NA

12. RPS Channel Test Switches 1,2 2

G SR 3.3.1.1.4 NA 5(a) 2 H SR 3.3.1.1.4 NA

13. Deleted (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

SRM Instrumentation 3.3.1.2 BFN-UNIT 3 3.3-12 Amendment No. 213, 298, ___ SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions. SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2

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

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

SRM Instrumentation 3.3.1.2 BFN-UNIT 3 3.3-15 Amendment No. 213, 298, ___ Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS 1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2(b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With IRMs on Range 2 or below. (b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector. (c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

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ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-42 Amendment No. 215, 298, ___ SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-43 Amendment No. 213, 254, 298, ___ Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System a. Reactor Vessel Water Level Low Low Low, Level 1(f) 1,2,3 4(b) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure High(f) 1,2,3 4(b) B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure Low (Injection Permissive and ECCS Initiation)(f) 1,2,3 4(b) 2 per trip system C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 435 psig and d 465 psig d. Core Spray Pump Discharge Flow Low (Bypass) 1,2,3 2 1 per subsystem E SR 3.3.5.1.2 SR 3.3.5.1.5 t 1647 gpm and d 2910 gpm e. Core Spray Pump Start Time Delay Relay Pumps A,B,C,D (with diesel power) 1,2,3 4 1 per pump C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump A (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds (continued) D 'HOHWHG E Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating." (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. 298

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-44 Amendment No. 213, 254, 298, ___ Table 3.3.5.1-1 (page 2 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System (continued) e. Core Spray Pump Start Time Delay Relay (continued) Pump C (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 18 seconds and d 24 seconds 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Vessel Water Level Low Low Low, Level 1(f) 1,2,3 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero b. Drywell Pressure High(f) 1,2,3 4 B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig c. Reactor Steam Dome Pressure Low (Injection Permissive and ECCS Initiation)(f) 1,2,3 4 C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 435 psig and d 465 psig (continued) D 'HOHWHG E Deleted. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. 298

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-45 Amendment No. 213, 248, 254, 298, ___ Table 3.3.5.1-1 (page 3 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System (continued) d. Reactor Steam Dome Pressure Low (Recirculation Discharge Valve Permissive)(f) 1(c),2(c), 3(c) 4 C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 t 215 psig and d 245 psig e. Reactor Vessel Water Level Level 0 1,2,3 2 1 per subsystem B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 312 5/16 inches above vessel zero f. Low Pressure Coolant Injection Pump Start Time Delay Relay Pump A,B,C,D (with diesel power) 1,2,3, 4 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump A (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 0 seconds and d 1 second Pump B (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 6 seconds and d 8 seconds Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 12 seconds and d 16 seconds Pump D (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 SR 3.3.5.1.6 t 18 seconds and d 24 seconds (continued) (a) 'HOHWHG (c) With associated recirculation pump discharge valve open. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-46 Amendment No. 213, 254, 298, ___ Table 3.3.5.1-1 (page 4 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel Water Level Low Low, Level 2(f) 1, 2(d), 3(d) 4 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 470 inches above vessel zero

b. Drywell Pressure High(f) 1, 2(d),3(d) 4 B

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig

c. Reactor Vessel Water Level High, Level 8 1,

2(d), 3(d) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 583 inches above vessel zero

d. Condensate Header Level Low 1,

2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t Elev. 551 feet

e. Suppression Pool Water Level High 1,

2(d), 3(d) 1 D SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 d 7 inches above instrument zero

f.

High Pressure Coolant Injection Pump Discharge FlowLow (Bypass) 1, 2(d), 3(d) 1 E SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 671 gpm

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water Level Low Low Low, Level 1(f) 1, 2(d), 3(d) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-47 Amendment No. 212, 213, 219, 254, 298, ___ Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

4. ADS Trip System A (continued)

b. Drywell Pressure High(f) 1, 2(d), 3(d) 2 F

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig

c. Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 115 seconds

d. Reactor Vessel Water Level Low, Level 3 (Confirmatory)(f) 1, 2(d), 3(d) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 528 inches above vessel zero

e. Core Spray Pump Discharge Pressure High 1,

2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig

f.

Low Pressure Coolant Injection Pump Discharge Pressure High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig

g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1,

2(d), 3(d) 2 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 322 seconds

5. ADS Trip System B

a. Reactor Vessel Water Level Low Low Low, Level 1(f) 1, 2(d), 3(d) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 398 inches above vessel zero (continued) (d) With reactor steam dome pressure > 150 psig. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-48 Amendment No. 213, 254, 298, ___ Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. ADS Trip System B (continued)

b. Drywell Pressure High(f) 1, 2(d), 3(d) 2 F

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 d 2.5 psig

c. Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 115 seconds

d. Reactor Vessel Water Level Low, Level 3 (Confirmatory)(f) 1, 2(d), 3(d) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 t 528 inches above vessel zero

e. Core Spray Pump Discharge Pressure High 1,

2(d), 3(d) 4 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 175 psig and d 195 psig

f.

Low Pressure Coolant Injection Pump Discharge Pressure High 1, 2(d), 3(d) 8 G SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 t 90 psig and d 110 psig

g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1,

2(d), 3(d) 2 G SR 3.3.5.1.5 SR 3.3.5.1.6 d 322 seconds (d) With reactor steam dome pressure > 150 psig. (f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable. Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable. The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

CREV System Instrumentation 3.3.7.1 BFN-UNIT 3 3.3-69 Amendment No. 215, 298, ___ SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREV initiation capability.

3.

For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours provided the downscale trip of the inoperable channel is placed in the trip condition. SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

CREV System Instrumentation 3.3.7.1 BFN-UNIT 3 3.3-70 Amendment No. 212, 213, 219, 249, 298, ___ Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Reactor Vessel Water Level - Low, Level 3 1,2,3 2 B SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 t 528 inches above vessel zero 2. Drywell Pressure - High 1,2,3 2 B SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 2.5 psig 3. Reactor Zone Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 100 mR/hr 4. Refueling Floor Exhaust Radiation - High 1,2,3 1 C SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 d 100 mR/hr 5. Control Room Air Supply Duct Radiation - High 1,2,3 1 D SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 d 270 cpm above background 249

LOP Instrumentation 3.3.8.1 BFN-UNIT 3 3.3-74 Amendment No. 215, 298, ___ SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function. SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

LOP Instrumentation 3.3.8.1 BFN-UNIT 3 3.3-75 Amendment No. 213, 292, 298, ___ Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS PER BOARD SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage)

a. Board Undervoltage 2

SR 3.3.8.1.2 SR 3.3.8.1.3 Reset at t 2813 V and d 2927 V

b. Diesel Start Initiation Time Delay 2

SR 3.3.8.1.2 SR 3.3.8.1.3 t 1.4 seconds and d 1.6 seconds

2. 4.16 kV Shutdown Board Undervoltage (Degraded Voltage)

a. Board Undervoltage 3

SR 3.3.8.1.1 SR 3.3.8.1.3 t 3900 V and d 3940 V b.1 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 0.2 seconds and d 0.4 seconds b.2 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 3 seconds and d 5 seconds b.3 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 5.15 seconds and d 8.65 seconds b.4 Time Delay 1 SR 3.3.8.1.2 SR 3.3.8.1.3 t 0.9 seconds and d 1.7 seconds

3. 4.16 kV Shutdown Board Undervoltage (Unbalanced Voltage Relay) 3 SR 3.3.8.1.2 SR 3.3.8.1.3 1.5V at 3 seconds (Permissive Alarm) 3.4V at 8.65 seconds (Lo) 20V at 3.5 seconds (High)

CNL-21-002 Proposed Technical Specification Bases Changes (For Information Only) for Browns Ferry Nuclear Unit 1 (27 total pages)

RPS Instrumentation B 3.3.1.1 (continued) BFN-UNIT 1 B 3.3-37 Revision 0, 40, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.1.3 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. As noted, SR 3.3.1.1.3 is not required to be performed when entering MODE 2 from MODE 1, since testing of the MODE 2 required IRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads, or movable links. This allows entry into MODE 2 if the Frequency is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours after entering MODE 2 from MODE 1. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.1.1.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

RPS Instrumentation B 3.3.1.1 (continued) BFN-UNIT 1 B 3.3-39 Revision 0, 40, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.1.5 and SR 3.3.1.1.6 (continued) REQUIREMENTS If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.1.1.7 LPRM gain settings are determined from the local flux profiles measured by the Traversing Incore Probe (TIP) System. This establishes the relative local flux profile for appropriate representative input to the APRM System. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.1.1.8, SR 3.3.1.1.12 (Deleted) (Deleted)

RPS Instrumentation B 3.3.1.1 (continued) BFN-UNIT 1 B 3.3-42 Revision 0, 40, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.1.15 REQUIREMENTS (continued) This SR ensures that scrams initiated from the Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions will not be inadvertently bypassed when THERMAL POWER is t 26% RTP. This involves calibration of the bypass channels (PIS-1-81A, PIS-1-81B, PIS-1-91A, and PIS-1-91B). Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint. If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at t 26% RTP, either due to open main turbine bypass valve(s) or other reasons), then the affected Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition (Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are enabled), this SR is met and the channel is considered OPERABLE. The Frequency of 24 months is based upon the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis. SR 3.3.1.1.16 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests. SR 3.3.1.1.8, SR 3.3.1.1.12, and

RPS Instrumentation B 3.3.1.1 (continued) BFN-UNIT 1 B 3.3-43 Revision 0, 43, 112, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.1.16 (continued) REQUIREMENTS The SR 3.3.1.1.16 Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The APRM CHANNEL FUNCTIONAL TEST covers the APRM channels (including recirculation flow processing - applicable to Function 2.b, only), the 2-out-of-4 voter channels, and the interface connections into the RPS trip systems from the voter channels. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. (NOTE: The actual voting logic of the 2-out-of-4 Voter Function is tested as part of SR 3.3.1.1.14.) A Note for SR 3.3.1.1.16 is provided that requires the APRM Function 2.a SR to be performed within 12 hours of entering MODE 2 from MODE 1. Testing of the MODE 2 APRM Function cannot be performed in MODE 1 without utilizing jumpers or lifted leads. This Note allows entry into MODE 2 from MODE 1 if the associated frequency is not met per SR 3.0.2. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR. SR 3.3.1.1.8, SR 3.3.1.1.12, and The SR 3.3.1.1.8 and SR 3.3.1.1.12 Surveillance Frequencies are controlled under the Surveillance Frequency Control Program.

SRM Instrumentation B 3.3.1.2 (continued) BFN-UNIT 1 B 3.3-51 Revision 0, 123 March 22, 2020 BASES ACTIONS E.1 and E.2 (continued) With one or more required SRM inoperable in MODE 5, the ability to detect local reactivity changes in the core during refueling is degraded. CORE ALTERATIONS must be immediately suspended and action must be immediately initiated to insert all insertable control rods in core cells containing one or more fuel assemblies. Suspending CORE ALTERATIONS prevents the two most probable causes of reactivity changes, fuel loading and control rod withdrawal, from occurring. Inserting all insertable control rods ensures that the reactor will be at its minimum reactivity given that fuel is present in the core. Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe, conservative position. Action (once required to be initiated) to insert control rods must continue until all insertable rods in core cells containing one or more fuel assemblies are inserted. SURVEILLANCE As noted at the beginning of the SRs, the SRs for each SRM REQUIREMENTS Applicable MODE or other specified conditions are found in the SRs column of Table 3.3.1.2-1. SR 3.3.1.2.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. and SR 3.3.1.2.3

SRM Instrumentation B 3.3.1.2 (continued) BFN-UNIT 1 B 3.3-52 Revision 0, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.2.1 (continued) REQUIREMENTS Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO. SR 3.3.1.2.2 To provide adequate coverage of potential reactivity changes in the core when the fueled region encompasses more than one SRM, one SRM is required to be OPERABLE in the quadrant where CORE ALTERATIONS are being performed, and the other OPERABLE SRM must be in an adjacent quadrant and SR 3.3.1.2.3

SRM Instrumentation B 3.3.1.2 (continued) BFN-UNIT 1 B 3.3-53 Revision 0, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.2.2 (continued) REQUIREMENTS containing fuel. Note 1 states that the SR is required to be met only during CORE ALTERATIONS. It is not required to be met at other times in MODE 5 since core reactivity changes are not occurring. This Surveillance consists of a review of plant logs to ensure that SRMs required to be OPERABLE for given CORE ALTERATIONS are, in fact, OPERABLE. In the event that only one SRM is required to be OPERABLE (when the fueled region encompasses only one SRM), per Table 3.3.1.2-1, footnote (b), only the a. portion of this SR is required. Note 2 clarifies that more than one of the three requirements can be met by the same OPERABLE SRM. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.1.2.3 Deleted. SR 3.3.1.2.4 This Surveillance consists of a verification of the SRM instrument readout to ensure that the SRM reading is greater than a specified minimum count rate, which ensures that the detectors are indicating count rates indicative of neutron flux levels within the core. With few fuel assemblies loaded, the SRMs will not have a high enough count rate to satisfy the SR. Therefore, allowances are made for loading sufficient "source" material, in the form of irradiated fuel assemblies, to establish the minimum count rate. SR 3 3 1 2 3 Deleted

SRM Instrumentation B 3.3.1.2 (continued) BFN-UNIT 1 B 3.3-54 Revision 0, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.1.2.4 (continued) REQUIREMENTS To accomplish this, the SR is modified by a Note that states that the count rate is not required to be met on an SRM that has less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies are in the associated core quadrant. With four or less fuel assemblies loaded around each SRM and no other fuel assemblies in the associated core quadrant, even with a control rod withdrawn, the configuration will not be critical. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.1.2.5 and SR 3.3.1.2.6 Performance of a CHANNEL FUNCTIONAL TEST demonstrates the associated channel will function properly. SR 3.3.1.2.5 is required in MODE 5, and ensures that the channels are OPERABLE while core reactivity changes could be in progress. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

Control Rod Block Instrumentation B 3.3.2.1 (continued) BFN-UNIT 1 B 3.3-67 Revision 0, 40, 123 March 22, 2020 BASES SURVEILLANCE Condition entered and Required Actions taken. This Note is REQUIREMENTS based on the reliability analysis (Ref. 9) assumption of the (continued) average time required to perform a channel Surveillance. That analysis demonstrated that the 6 hour testing allowance does not significantly reduce the probability that a control rod block will be initiated when necessary. SR 3.3.2.1.1 A CHANNEL FUNCTIONAL TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function. It includes the Reactor Manual Control System input. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function. The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs. This test is performed as soon as possible after the applicable conditions are entered. As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until 1 hour after A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

Control Rod Block Instrumentation B 3.3.2.1 (continued) BFN-UNIT 1 B 3.3-69 Revision 0, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.2.1.5 REQUIREMENTS (continued) The RWM is automatically bypassed when power is above a specified value. The power level is determined from feedwater flow and steam flow signals. The automatic bypass setpoint must be verified periodically to be > 10% RTP. If the RWM low power setpoint is nonconservative, then the RWM is considered inoperable. Alternately, the low power setpoint channel can be placed in the conservative condition (nonbypass). If placed in the nonbypassed condition, the SR is met and the RWM is not considered inoperable The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.2.1.6 A CHANNEL FUNCTIONAL TEST is performed for the Reactor Mode Switch - Shutdown Position Function to ensure that the entire channel will perform the intended function. The CHANNEL FUNCTIONAL TEST for the Reactor Mode Switch - Shutdown Position Function is performed by attempting to withdraw any control rod with the reactor mode switch in the shutdown position and verifying a control rod block occurs. As noted in the SR, the Surveillance is not required to be performed until 1 hour after the reactor mode switch is in the shutdown position, since testing of this interlock with the reactor mode switch in any other position cannot be performed without using jumpers, lifted leads, or movable links. This allows entry into MODES 3 and 4 if the Frequency is not met per SR 3.0.2. The 1 hour allowance is based on operating experience and in consideration of providing a reasonable time in which to complete the SRs. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 (continued) BFN-UNIT 1 B 3.3-79 Revision 0, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.2.2.2 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.2.2.3 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

PAM Instrumentation B 3.3.3.1 (continued) BFN-UNIT 1 B 3.3-94 Revision 3, 32, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.3.1.2 REQUIREMENTS (continued) Deleted. SR 3.3.3.1.3 A CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies the channel responds to measured parameter with the necessary range and accuracy. For the PCIV position function, the CHANNEL CALIBRATION consists of verifying the remote indications conform to actual valve positions. For the Primary Containment Area Radiation Function, the CHANNEL CALIBRATION consists of an electronic calibration of the channel not including the detector for ranges above 10 R/hr and a one-point source check of the detector below 10 R/hr with an installed or portable gamma source. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. , SR 3.3.3.1.3, and SR 3.3.3.1.4 Deleted SR 3 3 3 1 3

Backup Control System B 3.3.3.2 BFN-UNIT 1 B 3.3-101 Revision 0, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.3.2.2 REQUIREMENTS (continued) CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies the channel responds to measured parameter values with the necessary range and accuracy. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.3.2.3 Deleted REFERENCES

1. 10 CFR 50, Appendix A, GDC 19.

2. FSAR Section 7.18.

3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

SR 3 3 3 2 3 Deleted and SR 3.3.3.2.3

EOC-RPT Instrumentation B 3.3.4.1 (continued) BFN-UNIT 1 B 3.3-114 Revision 0, 123 March 22, 2020 BASES (continued) SURVEILLANCE The Surveillances are modified by a Note to indicate that when REQUIREMENTS a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains EOC-RPT trip capability. Upon completion of the Surveillance, or expiration of the 6 hour allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Ref. 5) assumption of the average time required to perform channel Surveillance. That analysis demonstrated that the 6 hour testing allowance does not significantly reduce the probability that the recirculation pumps will trip when necessary. SR 3.3.4.1.1 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

ATWS-RPT Instrumentation B 3.3.4.2 (continued) BFN-UNIT 1 B 3.3-126 Revision 0, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.4.2.1 (continued) REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.4.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.4.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

ECCS Instrumentation B 3.3.5.1 (continued) BFN-UNIT 1 B 3.3-173 Revision 0, 13, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.5.1.1 (continued) REQUIREMENTS instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.5.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

ECCS Instrumentation B 3.3.5.1 (continued) BFN-UNIT 1 B 3.3-174 Revision 1, 43, 47, 65, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.5.1.3 REQUIREMENTS (continued) A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.5.1.4 and SR 3.3.5.1.5 Deleted SR 3.3.5.1.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation for a specific channel. The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, and LCO 3.8.1 overlaps this Surveillance to complete testing of the assumed safety function. The LOGIC SYSTEM FUNCTIONAL TEST shall include a calibration of time delay relays and timers necessary for proper functioning of the logic. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. , SR 3.3.5.1.4, and SR 3.3.5.1.5 SR 3 3 5 1 4 and SR 3 3 5 1 5 Deleted

5&,&6\\VWHP,QVWUXPHQWDWLRQ % FRQWLQXHG %)181,7 % 5HYLVLRQ -DQXDU\\ %$6(6 6859(,//$1&( 65 5(48,5(0(176 FRQWLQXHG $&+$11(/)81&7,21$/7(67LVSHUIRUPHGRQHDFK UHTXLUHGFKDQQHOWRHQVXUHWKDWWKHHQWLUHFKDQQHOZLOOSHUIRUP WKHLQWHQGHGIXQFWLRQ $Q\\VHWSRLQWDGMXVWPHQWVKDOOEHFRQVLVWHQWZLWKWKH DVVXPSWLRQVRIWKHFXUUHQWSODQWVSHFLILFVHWSRLQWPHWKRGRORJ\\ 7KH)UHTXHQF\\RI GD\\VLVEDVHGRQWKHUHOLDELOLW\\DQDO\\VLVRI 5HIHUHQFH 7KH6XUYHLOODQFH)UHTXHQF\\LVFRQWUROOHGXQGHU WKH6XUYHLOODQFH)UHTXHQF\\&RQWURO3URJUDP 65 $&+$11(/&$/,%5$7,21LVDFRPSOHWHFKHFNRIWKH LQVWUXPHQWORRSDQGWKHVHQVRU7KLVWHVWYHULILHVWKHFKDQQHO UHVSRQGVWRWKHPHDVXUHGSDUDPHWHUZLWKLQWKHQHFHVVDU\\ UDQJHDQGDFFXUDF\\&+$11(/&$/,%5$7,21OHDYHVWKH FKDQQHODGMXVWHGWRDFFRXQWIRULQVWUXPHQWGULIWVEHWZHHQ VXFFHVVLYHFDOLEUDWLRQVFRQVLVWHQWZLWKWKHSODQWVSHFLILF VHWSRLQWPHWKRGRORJ\\ 7KH)UHTXHQF\\RI65 LVEDVHGXSRQWKHDVVXPSWLRQRI D PRQWKFDOLEUDWLRQLQWHUYDOLQWKHGHWHUPLQDWLRQRIWKH PDJQLWXGHRIHTXLSPHQWGULIWLQWKHVHWSRLQWDQDO\\VLV 7KH 6XUYHLOODQFH)UHTXHQF\\LVFRQWUROOHGXQGHUWKH6XUYHLOODQFH )UHTXHQF\\&RQWURO3URJUDP A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests. Note - This markup page was from the TSTF-425 License Amendment Request, which has not yet been implemented for these SRs.

Primary Containment Isolation Instrumentation B 3.3.6.1 (continued) BFN-UNIT 1 B 3.3-220 Revision 0, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.6.1.2 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.6.1.3 and SR 3.3.6.1.4 Deleted SR 3.3.6.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

Secondary Containment Isolation Instrumentation B 3.3.6.2 (continued) BFN-UNIT 1 B 3.3-235 Revision 0, 43, 123 March 22, 2020 BASES SURVEILLANCE SR 3.3.6.2.2 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This Surveillance for Functions 3 and 4 shall consist of verifying the High Voltage Power Supply (HVPS) voltage at the sensor and convertors (detectors) is within its design limits. A CHANNEL FUNCTIONAL TEST as defined in Section 1.1, "Definitions" shall be performed periodically as part of the CHANNEL CALIBRATION for Functions 3 and 4. SR 3.3.6.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

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ote - This markup page was from the TSTF-425 License Amendment Request, which has not yet been implemented for these SRs. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests.

CREV System Instrumentation B 3.3.7.1 (continued) BFN-UNIT 1 B 3.3-252 Revision 0, 43 January 17, 2007 BASES SURVEILLANCE SR 3.3.7.1.2 (continued) REQUIREMENTS The Frequency of 92 days is based on the reliability analyses of References 3 and 4. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This Surveillance for Functions 3 and 4 shall consist of verifying the High Voltage Power Supply (HVPS) voltage at the Sensor and Convertors (detectors) is within its design limits. A CHANNEL FUNCTIONAL TEST as defined in Section 1.1, "Definitions" shall be performed once per 24 months as part of the CHANNEL CALIBRATION for Functions 3 and 4. SR 3.3.7.1.3 and SR 3.3.7.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Frequencies are based upon the magnitude of equipment drift in the setpoint analysis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Note - This markup page was from the TSTF-425 License Amendment Request, which has not yet been implemented for these SRs. Delete this change

CREV System Instrumentation B 3.3.7.1 BFN-UNIT 1 B 3.3-253 Revision 0, 43 January 17, 2007 BASES SURVEILLANCE SR 3.3.7.1.4 and SR 3.3.7.1.6 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LCO 3.7.3, "Control Room Emergency Ventilation (CREV) System," overlaps this Surveillance to provide complete testing of the assumed safety function. The 184 day Frequency for Function 5 is based on equipment capability. The 24 month Frequency for Functions 1, 2, 3, and 4 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience with these components supports performance of the Surveillance at their designated Frequencies. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. REFERENCES

1. FSAR, Section 10.12.5.3.

2. FSAR, Section 14.6.3.7.

3. GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

4. NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

5. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

Note - This markup page was from the TSTF-425 License Amendment Request, which has not yet been implemented for these SRs. Delete this change

LOP Instrumentation B 3.3.8.1 (continued) BFN-UNIT 1 B 3.3-263 Revision 123 Amendment No. 235 March 22, 2020 BASES SURVEILLANCE As noted (Note 1) at the beginning of the SRs, the SRs for REQUIREMENTS each LOP instrumentation Function are located in the SRs column of Table 3.3.8.1-1. SR 3.3.8.1.1 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.8.1.2 Deleted SR 3.3.8.1.3 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel. The system functional testing performed in LCO 3.8.1 and LCO 3.8.2 overlaps this Surveillance to provide complete testing of the assumed safety functions. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3 3 8 1 2 Deleted and SR 3.3.8.1.2

RPS Electric Power Monitoring B 3.3.8.2 (continued) BFN-UNIT 1 B 3.3-273 Revision 0, 123 March 22, 2020 BASES (continued) SURVEILLANCE SR 3.3.8.2.1 REQUIREMENTS A CHANNEL FUNCTIONAL TEST is performed on each overvoltage, undervoltage, and underfrequency channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.3.8.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

RCS Leakage Detection Instrumentation B 3.4.5 (continued) BFN-UNIT 1 B 3.4-35 Revision 0, 123 March 22, 2020 BASES (continued) SURVEILLANCE SR 3.4.5.1 REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the required primary containment atmospheric monitoring system instrumentation. The check gives reasonable confidence that the channel is operating properly. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.4.5.2 This SR is for the performance of a CHANNEL FUNCTIONAL TEST of the required primary containment atmospheric monitoring system instrumentation. The test ensures that the monitors can perform their function in the desired manner. The test also verifies the alarm setpoint and relative accuracy of the instrument string. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.4.5.3 This SR is for the performance of a CHANNEL CALIBRATION of required drywell floor drain sump flow integrator instrumentation channels. The calibration verifies the accuracy of the instrument string. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

Refueling Equipment Interlocks B 3.9.1 (continued) BFN-UNIT 1 B 3.9-5 Amendment No. 242 Revision 0, 16, 123 March 22, 2020 BASES ACTIONS A.1, A.2.1, and A.2.2 (continued) remain inserted). Required Action A.2.2 is normally performed after placing the rod withdrawal block in effect, and provides a verification that all control rods are fully inserted. This verification that all control rods are fully inserted is in addition to the periodic verifications required by SR 3.9.3.1. Like Required Action A.1, Required Actions A.2.1 and A.2.2 ensure unacceptable operations are blocked (e.g., loading fuel into a cell with the control rod withdrawn). It is not the intent of Actions A.2 to eliminate the first performance of SR 3.9.1.1 prior to in-vessel fuel movement. It is expected that the refueling interlocks would be operable except for equipment failure or expiration of the required surveillance interval, and Actions A.2 would not be entered as a convenience for avoiding the first performance of SR 3.9.1.1. SURVEILLANCE SR 3.9.1.1 REQUIREMENTS Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested. This SR is only required for refueling equipment in use. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.}}

v t e Letter Sequence Request
EPID:L-2021-LLA-0217, TSTF-563, TSTF-205 (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval, Approval Other:
MONTHYEAR2022-01-06 [Table View]

CNL-21-002, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance.

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CNL-21-002, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance.

Text

Subject:

Reference:

Enclosure:

Subject:

1.0 DESCRIPTION

2.0 ASSESSMENT

3.0 REGULATORY ANALYSIS

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3.0 REGULATORY ANALYSIS

5.0 REFERENCES

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