Text

Application to Revise Technical Specifications to Adopt TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements (BFN TS-558)
	ML25338A084
Person / Time
Site:	Browns Ferry
Issue date:	12/03/2025
From:	Sowa J; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	CNL-25-088
	Download: ML25338A084 (0)
	v • d • e

10 CFR 50.90 1101 Market Street, Chattanooga, Tennessee 37402 CNL-25-088 December 3, 2025 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Application to Revise Technical Specifications to Adopt TSTF-592-A, Revision 2, "Revise Automatic Depressurization System (ADS) Instrumentation Requirements" (BFN TS-558)

Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Tennessee Valley Authority (TVA) is submitting a request for an amendment to the Technical Specifications (TS) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3.

TVA requests adoption of Technical Specifications Task Force (TSTF) traveler TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements.

The TS 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation, Required Actions are revised to reflect the plant design and the safety significance of inoperable ADS monitoring channels.

The enclosure provides a description and assessment of the proposed change. Attachment 1 to the enclosure provides the existing BFN Units 1, 2, and 3 TS pages marked up to show the proposed change. Attachment 2 to the enclosure provides the existing BFN Unit 1 TS Bases pages marked up to show revised text associated with the proposed TS changes (BFN Units 2 and 3 changes will be similar). Changes to the existing TS Bases are provided for information only and will be implemented under the Technical Specifications Bases Control Program.

TVA requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLIIP). Approval of the proposed amendment is requested within 6 months of acceptance. Once approved, the amendment shall be implemented within 120 days.

U. S. Nuclear Regulatory Commission CNL-25-088 Page 2 December 3, 2025 In accordance with 10 CFR 50.91, a copy of this application with attachments is being provided to the designated Alabama official.

There are no new regulatory commitments associated with this submittal. Please address any questions regarding this application to Amber V. Aboulfaida, Senior Manager, Fleet Licensing, at avaboulfaida@tva.gov.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 3rd day of December 2025.

Respectfully, Jeffrey R. Sowa General Manager (Acting), Nuclear Regulatory Affairs & Emergency Preparedness

Enclosure:

Description and Assessment of the Proposed Change cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant State Health Officer, Alabama Department of Public Health Sowa, Jeffrey R Digitally signed by Sowa, Jeffrey R Date: 2025.12.03 13:41:35 -05'00'

Enclosure CNL-25-088 E1 of 5 Description and Assessment of the Proposed Change

Subject:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Application to Revise Technical Specifications to Adopt TSTF-592-A, Revision 2, "Revise Automatic Depressurization System (ADS) Instrumentation Requirements" (BFN TS-558)

CONTENTS 1.0

SUMMARY

DESCRIPTION.............................................................................................. 2

2.0 ASSESSMENT

.................................................................................................................. 2 2.1 Applicability of Safety Evaluation.................................................................................. 2 2.2 Optional Changes and Variations.................................................................................. 2

3.0 REGULATORY EVALUATION

.......................................................................................... 3 3.1 No Significant Hazards Consideration Analysis............................................................ 3 3.2 Conclusion..................................................................................................................... 5

4.0 ENVIRONMENTAL CONSIDERATION

............................................................................ 5 Attachments:

1. Proposed TS Changes (Markup) for BFN Units 1, 2, and 3

2. Proposed TS Bases Changes (Markup) for BFN Unit 1 (For Information Only)

Enclosure CNL-25-088 E2 of 5 1.0

SUMMARY

DESCRIPTION Tennessee Valley Authority (TVA) requests adoption of Technical Specifications Task Force (TSTF) traveler TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements. The Technical Specification (TS) 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation, Required Actions are revised to reflect the plant design and the safety significance of inoperable ADS monitoring channels.

2.0 ASSESSMENT

2.1 Applicability of Safety Evaluation TVA has reviewed the safety evaluation for TSTF-592-A, Revision 2, provided to the TSTF in a letter dated January 31, 2024. This review included a review of the Nuclear Regulatory Commission (NRC) staffs evaluation, as well as the information provided in TSTF-592-A, Revision 2. TVA has concluded that the justifications presented in TSTF-592-A, Revision 2, and the safety evaluation prepared by the NRC staff are applicable to Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, and justify this amendment for the incorporation of the changes to the BFN TS.

2.2 Optional Changes and Variations TVA is proposing the following variations from the TS changes described in TSTF-592-A, Revision 2, or the applicable parts of the NRC staffs safety evaluation:

In BFN TS 3.3.5.1, the 8-day Completion Times for Required Actions F.2 and G.2 are being combined with the Risk Informed Completion Time, similar to the Completion Time for Required Action H.2. While not presented this way in TSTF-592, Revision 2, this non-technical variation provides clarity for operators and is consistent with the intent of the TSTF traveler. This variation is also consistent with a previously NRC-approved amendment for Columbia Generating Station (ML25072A188).

A Note of The Risk Informed Completion Time Program is not applicable when a loss of function occurs. is being added to the Completion Times for Required Actions F.2 and G.2. This change is consistent with the BFN amendments adopting TSTF-505 (ML23073A290).

The BFN TS 3.3.5.1 does not contain the Note to Required Action G.1 regarding which Table 3.3.5.1-1 functions are applicable. Therefore, removal of the Note as described in TSTF-592-A, Revision 2, is not applicable to BFN.

The BFN TS Table 3.3.5.1-1 does not contain Functions 4.h or 5.h (Manual Initiation).

Therefore, the change of the functions from Condition G to Condition H is not applicable to BFN.

All (continued) statements at the bottom of BFN TS Table 3.3.5.1-1 are being deleted.

This is a non-technical variation and is consistent with the BWR/4 STS.

The BFN TS 3.3.5.1 does not contain Required Actions D.2.1 or D.2.2. Therefore, the change to TS Bases 3.3.5.1 Actions D.2.1 and D.2.2 as described in TSTF-592-A, Revision 2, is not applicable to BFN.

Enclosure CNL-25-088 E3 of 5 Unrelated to TSTF-592-A, Revision 2, TVA is including a change to BFN Surveillance Requirement (SR) 3.8.4.5 to add a operator before the 48 amp charging requirement.

This change was not identified during the TS change that resulted in Amendment Nos. 336, 359 and 319 (ML25241A019), and it is intended to clarify the SR for operators and procedure writers. This is a technical variation from TSTF-592-A, Revision 2, that is consistent with the BWR/4 STS.

Unrelated to TSTF-592-A, Revision 2, TVA is including a change to BFN TS Limiting Condition for Operation (LCO) 3.10.3 for Units 2 and 3. This change removes an LCO 3.10.3.d reference to Function 13 of Table 3.3.1.1-1 which was deleted from the BFN TS in 2002 (ML020990743). This is an non-technical variation from TSTF-592-A, Revision 2, and is not applicable to Unit 1.

The BFN ADS initiation logic design differs from the design described in the BWR/4 STS.

The ADS logic in each trip system is arranged in two strings. Each string has a contact from each of the following variables: Reactor Vessel Water Level - Low Low Low, Level 1; Drywell Pressure - High; High Drywell Pressure Bypass Timer; and Pump Discharge Pressure - High.

One of the two strings in each trip system must also have a confirmed Reactor Vessel Water Level - Low, Level 3 (confirmatory). Either the Drywell Pressure - High or the High Drywell Pressure Bypass Timer contacts and all remaining contacts in both logic strings must close and the ADS initiation timer must time out to initiate an ADS trip system. Either the A or B trip system will cause all the ADS relief valves to open. Once the Drywell Pressure - High signal, the ADS High Drywell Pressure Bypass Timer, or the ADS initiation signal is present, it is individually sealed in until manually reset.

This has no effect on the traveler technical justification. No changes to the proposed TS markups are required. The BFN design is reflected in the proposed TS Bases. Therefore, this difference does not affect the applicability of the traveler to BFN.

3.0 REGULATORY EVALUATION

3.1 No Significant Hazards Consideration Analysis Tennessee Valley Authority (TVA) requests adoption of Technical Specifications Task Force (TSTF) traveler TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements. The Technical Specifications (TS) 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation, Required Actions are revised to reflect the plant design and the safety significance of inoperable ADS monitoring channels.

Enclosure CNL-25-088 E4 of 5 TVA has evaluated if a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in Title 10 of the Code of Federal Regulations (10 CFR) 50.92, Issuance of amendment, as discussed below:

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

Response: No The proposed change revises the applicable TS Required Actions when one or more ADS monitoring channels are inoperable to be consistent with the plant design and the safety significance of the condition. The actions taken when an ADS monitoring channel is inoperable are not an initiator of any accident previously evaluated. The proposed actions implement the appropriate actions to be taken if automatic initiation of ADS is not available (i.e., declaring the ADS valves inoperable), which ensures the equipment assumed to be available to mitigate the consequences of accidents previously evaluated is available or the plant is placed in a safe condition.

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

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

Response: No The proposed change revises the applicable TS Required Actions when one or more ADS monitoring channels are inoperable to be consistent with the plant design and the safety significance of the condition. The proposed change does not affect the design function or operation of the ADS or the ADS initiation instrumentation. The proposed change does not create a new or different type of failure for the ADS or the ADS initiation instrumentation due to credible new failure mechanisms, malfunctions, or accident initiators not currently considered in the design and licensing bases.

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

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

Response: No The proposed change revises the applicable TS Required Actions when one or more ADS monitoring channels are inoperable to be consistent with the plant design and the safety significance of the condition. The proposed change does not affect any controlling values of parameters established in the design or licensing basis and does not alter any design basis or safety limit.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Enclosure CNL-25-088 E5 of 5 Based on the above, TVA concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.

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

4.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed 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 amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or a 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 amendment 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 amendment.

Enclosure CNL-25-088 Proposed Technical Specifications Changes (Markups) for BFN Units 1, 2, and 3 (44 pages)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-39 Amendment No. 234, 328

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

F.1 Declare Automatic Depressurization System (ADS) valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND F.2 Place channel in trip.

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

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable OR

NOTE---------

Not applicable when a loss of function occurs

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-40 Amendment No. 234, 328

In accordance with the Risk Informed Completion Time Program AND

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

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program OR

NOTE----------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-41 Amendment No. 234, 328

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

G.1 Declare ADS valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND G.2 Restore channel to OPERABLE status.

NOTE----------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or RCIC inoperable OR

NOTE---------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-42 Amendment No. 234, 328

AND

NOTE----------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program OR

NOTE---------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-40a Amendment No. 234, 328

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

H.1

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

1. Only applicable for Functions 4.e, 4.f, 5.e, and 5.f.

2. Only applicable when both ADS trip systems are inoperable due to Core Spray/LPCI Pump Discharge Pressure -

High channels inoperable.

Declare ADS valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-41a Amendment No. 234, 328

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

(continued)

H.2

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

1. Only applicable for Functions 4.e, 4.f, 5.e, and 5.f.

2. Only applicable when one ADS trip system is inoperable due to Core Spray/LPCI Pump Discharge Pressure -

High channels inoperable.

Restore affected channels to OPERABLE status.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels concurrent with HPCI or RCIC inoperable AND 8 days or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels AND H.3 Restore channel to OPERABLE status.

30 days (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-42a Amendment No. 234, 328

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME HI.

Required Action and associated Completion Time of Condition B, C, D, E, F, G, or GH not met.

HI.1 Declare associated supported ECCS feature(s) inoperable.

Immediately

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-44 Amendment No. 234, 257, 315, 311, 322

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 3.3.5.1.6 398 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 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 3.3.5.1.6 435 psig and 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 1647 gpm and 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 6 seconds and 8 seconds Pump A (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 0 seconds and 1 second Pump B (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 6 seconds and 8 seconds (continued)

(a) Deleted.

(b) 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-45 Amendment No. 234, 257, 315, 311, 322

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 12 seconds and 16 seconds Pump D (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 18 seconds and 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 3.3.5.1.6 398 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 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 3.3.5.1.6 435 psig and 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-46 Amendment No. 234, 250, 257, 315, 311, 322

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 3.3.5.1.6 215 psig and 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 3.3.5.1.6 312 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 0 seconds and 1 second Pump A (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 0 seconds and 1 second Pump B (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 6 seconds and 8 seconds Pump C (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 12 seconds and 16 seconds Pump D (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 18 seconds and 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 1 3.3-47 Amendment No. 234, 257, 315, 322

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 3.3.5.1.6 470 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 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 3.3.5.1.6 583 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 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 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 3.3.5.1.6 671 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 3.3.5.1.6 398 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 3.3-48 Amendment No. 234, 257, 258, 315, 322

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 2.5 psig c.

Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G

SR 3.3.5.1.5 SR 3.3.5.1.6 115 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 3.3.5.1.6 528 inches above vessel zero e.

Core Spray Pump Discharge Pressure - High 1,

2(d), 3(d) 4 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 175 psig and 195 psig f.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1,

2(d), 3(d) 8 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 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 3.3.5.1.6 322 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 3.3.5.1.6 398 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 3.3-49 Amendment No. 234, 257, 258, 315, 322

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 2.5 psig c.

Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G

SR 3.3.5.1.5 SR 3.3.5.1.6 115 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 3.3.5.1.6 528 inches above vessel zero e.

Core Spray Pump Discharge Pressure - High 1,

2(d), 3(d) 4 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 175 psig and 195 psig f.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1,

2(d), 3(d) 8 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 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 3.3.5.1.6 322 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.

DC Sources - Operating 3.8.4 BFN-UNIT 1 3.8-25 Amendment No. 234, 315, 336

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85%

of expected life with capacity <

100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity 100%

of manufacturer's rating SR 3.8.4.5

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

Credit may be taken for unplanned events that satisfy this SR.

Verify each required battery charger supplies 300 amps for the Unit and 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.

In accordance with the Surveillance Frequency Control Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-40 Amendment No. 253, 351

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

F.1 Declare Automatic Depressurization System (ADS) valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND F.2 Place channel in trip.

NOTE----------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable OR

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-41 Amendment No. 253, 351

NOTE--------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program AND

NOTE----------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program OR

NOTE--------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-42 Amendment No. 253, 351

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

G.1 Declare ADS valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND G.2 Restore channel to OPERABLE status.

NOTE----------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or RCIC inoperable OR

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-43 Amendment No. 253, 351

NOTE--------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program AND

NOTE----------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program OR

NOTE--------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-41a Amendment No. 253, 351

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

H.1

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

1. Only applicable for Functions 4.e, 4.f, 5.e, and 5.f.

2. Only applicable when both ADS trip systems are inoperable due to Core Spray/LPCI Pump Discharge Pressure - High channels inoperable.

Declare ADS valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-42a Amendment No. 253, 351

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

(continued)

H.2

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

1. Only applicable for Functions 4.e, 4.f, 5.e, and 5.f.

2. Only applicable when one ADS trip system is inoperable due to Core Spray/LPCI Pump Discharge Pressure -

High channels inoperable.

Restore affected channels to OPERABLE status.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels concurrent with HPCI or RCIC inoperable AND 8 days or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels AND H.3 Restore channel to OPERABLE status.

30 days (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-43a Amendment No. 253, 351

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME HI.

Required Action and associated Completion Time of Condition B, C, D, E, F, G, or GH not met.

HI.1 Declare associated supported ECCS feature(s) inoperable.

Immediately

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-45 Amendment No. 253, 296, 338, 334, 345

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 3.3.5.1.6 398 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 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 3.3.5.1.6 435 psig and 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 1647 gpm and 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 6 seconds and 8 seconds Pump A (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 0 seconds and 1 second Pump B (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 6 seconds and 8 seconds (continued)

(a) Deleted.

(b) 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-46 Amendment No. 253, 296, 338, 334, 345

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 12 seconds and 16 seconds Pump D (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 18 seconds and 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 3.3.5.1.6 398 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 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 3.3.5.1.6 435 psig and 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-47 Amendment No. 253, 289, 296, 338, 334, 345

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 3.3.5.1.6 215 psig and 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 3.3.5.1.6 312 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 0 seconds and 1 second Pump A (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 0 seconds and 1 second Pump B (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 6 seconds and 8 seconds Pump C (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 12 seconds and 16 seconds Pump D (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 18 seconds and 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 2 3.3-48 Amendment No. 253, 296, 338, 345

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 3.3.5.1.6 470 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 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 3.3.5.1.6 583 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 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 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 3.3.5.1.6 671 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 3.3.5.1.6 398 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 3.3-49 Amendment No. 253, 260, 296, 338, 345

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 2.5 psig c.

Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G

SR 3.3.5.1.5 SR 3.3.5.1.6 115 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 3.3.5.1.6 528 inches above vessel zero e.

Core Spray Pump Discharge Pressure - High 1,

2(d), 3(d) 4 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 175 psig and 195 psig f.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1,

2(d), 3(d) 8 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 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 3.3.5.1.6 322 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 3.3.5.1.6 398 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 3.3-50 Amendment No. 253, 296, 338, 345

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 2.5 psig c.

Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G

SR 3.3.5.1.5 SR 3.3.5.1.6 115 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 3.3.5.1.6 528 inches above vessel zero e.

Core Spray Pump Discharge Pressure - High 1,

2(d), 3(d) 4 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 175 psig and 195 psig f.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1,

2(d), 3(d) 8 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 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 3.3.5.1.6 322 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.

DC Sources - Operating 3.8.4 BFN-UNIT 2 3.8-25 Amendment No. 253, 338, 359

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85%

of expected life with capacity <

100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity 100%

of manufacturer's rating SR 3.8.4.5

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

Credit may be taken for unplanned events that satisfy this SR.

Verify each required battery charger supplies 300 amps for the Unit and 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.

In accordance with the Surveillance Frequency Control Program

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 BFN-UNIT 2 3.10-7 Amendment No. 253

3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal - Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

b. LCO 3.9.4, "Control Rod Position Indication";

c. All other control rods are fully inserted; and

d. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b, 7.a, 7.b, 10, 11, 12, and 13 12 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY - Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 3 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY:

MODE 3 with the reactor mode switch in the refuel position.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-40 Amendment No. 213, 311

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

F.1 Declare Automatic Depressurization System (ADS) valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND F.2 Place channel in trip.

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

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable OR

NOTE---------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-41 Amendment No. 213, 311

AND

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

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program OR

NOTE---------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-42 Amendment No. 213, 311

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

G.1 Declare ADS valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND G.2 Restore channel to OPERABLE status.

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

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or RCIC inoperable OR

NOTE-------

Not applicable when a loss of function occurs

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-43 Amendment No. 213, 311

In accordance with the Risk Informed Completion Time Program AND

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

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program OR

NOTE-------

Not applicable when a loss of function occurs In accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-41a Amendment No. 213, 311

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

H.1

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

1. Only applicable for Functions 4.e, 4.f, 5.e, and 5.f.

2. Only applicable when both ADS trip systems are inoperable due to Core Spray/LPCI Pump Discharge Pressure -

High channels inoperable.

Declare ADS valves inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems AND (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-42a Amendment No. 213, 311

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

(continued)

H.2

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

1. Only applicable for Functions 4.e, 4.f, 5.e, and 5.f.

2. Only applicable when one ADS trip system is inoperable due to Core Spray/LPCI Pump Discharge Pressure -

High channels inoperable.

Restore affected channels to OPERABLE status.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels concurrent with HPCI or RCIC inoperable AND 8 days or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels AND H.3 Restore channel to OPERABLE status.

30 days (continued)

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-43a Amendment No. 213, 311

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME HI. Required Action and associated Completion Time of Condition B, C, D, E, F, G, or GH not met.

HI.1 Declare associated supported ECCS feature(s) inoperable.

Immediately

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-45 Amendment No. 213, 254, 298, 294, 305

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 3.3.5.1.6 398 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 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 3.3.5.1.6 435 psig and 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 1647 gpm and 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 6 seconds and 8 seconds Pump A (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 0 seconds and 1 second Pump B (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 6 seconds and 8 seconds (continued)

(a) Deleted.

(b) 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-46 Amendment No. 213, 254, 298, 294, 305

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 12 seconds and 16 seconds Pump D (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 18 seconds and 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 3.3.5.1.6 398 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 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 3.3.5.1.6 435 psig and 465 psig (continued)

(a) Deleted.

(b) 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.

ECCS Instrumentation 3.3.5.1 BFN-UNIT 3 3.3-47 Amendment No. 213, 248, 254, 298, 294, 305

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 3.3.5.1.6 215 psig and 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 3.3.5.1.6 312 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 0 seconds and 1 second Pump A (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 0 seconds and 1 second Pump B (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 6 seconds and 8 seconds Pump C (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 12 seconds and 16 seconds Pump D (with normal power) 1,2,3 1

C SR 3.3.5.1.5 SR 3.3.5.1.6 18 seconds and 24 seconds (continued)

(a) Deleted.

(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 3.3-48 Amendment No. 213, 254, 298, 305

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 3.3.5.1.6 470 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 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 3.3.5.1.6 583 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 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 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 3.3.5.1.6 671 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 3.3.5.1.6 398 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 3.3-49 Amendment No. 212, 213, 219, 254, 298, 305

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 2.5 psig c.

Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G

SR 3.3.5.1.5 SR 3.3.5.1.6 115 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 3.3.5.1.6 528 inches above vessel zero e.

Core Spray Pump Discharge Pressure High 1,

2(d), 3(d) 4 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 175 psig and 195 psig f.

Low Pressure Coolant Injection Pump Discharge Pressure High 1,

2(d), 3(d) 8 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 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 3.3.5.1.6 322 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 3.3.5.1.6 398 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 3.3-50 Amendment No. 213, 254, 298, 305

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 2.5 psig c.

Automatic Depressurization System Initiation Timer 1,

2(d), 3(d) 1 G

SR 3.3.5.1.5 SR 3.3.5.1.6 115 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 3.3.5.1.6 528 inches above vessel zero e.

Core Spray Pump Discharge Pressure High 1,

2(d), 3(d) 4 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 175 psig and 195 psig f.

Low Pressure Coolant Injection Pump Discharge Pressure High 1,

2(d), 3(d) 8 GH SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 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 3.3.5.1.6 322 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.

DC Sources - Operating 3.8.4 BFN-UNIT 3 3.8-25 Amendment No. 212, 298, 319

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85%

of expected life with capacity <

100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity 100%

of manufacturer's rating SR 3.8.4.5

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

Credit may be taken for unplanned events that satisfy this SR.

Verify each required battery charger supplies 300 amps for the Unit and 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.

In accordance with the Surveillance Frequency Control Program

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 BFN-UNIT 3 3.10-7 Amendment No. 212

3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal - Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

b. LCO 3.9.4, "Control Rod Position Indication";

c. All other control rods are fully inserted; and

d. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b, 7.a, 7.b, 10, 11, 12, and 13 12 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY - Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 3 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY:

MODE 3 with the reactor mode switch in the refuel position.

Enclosure CNL-25-088 Proposed Technical Specifications Bases Changes (Markups) for BFN Unit 1 (For Information Only)

(9 pages)

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-162 Amendment 328

Revision 0 BASES ACTIONS B.1, B.2, and B.3 (continued)

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." For Required Action B.1, the Completion Time only begins upon discovery that redundant features in the same system (e.g.,

both CS subsystems) cannot be automatically initiated due to inoperable, untripped channels within the same Function as described in the paragraph above. For Required Action B.2, the Completion Time only begins upon discovery that the HPCI System cannot be automatically initiated due to inoperable, untripped channels within the same Function as described in the paragraph above. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time from discovery of loss of initiation capability is acceptable because it minimizes risk while allowing time for restoration or tripping of channels.

Because of the diversity of sensors available to provide initiation signals and the redundancy of the ECCS design, an allowable out of service time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months has been shown to be acceptable (Ref. 4) to permit restoration of any inoperable channel to OPERABLE status. Alternatively, a Completion Time can be determined in accordance with the Risk Informed Completion Time Program (if there is no loss of function). If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, the channel must be placed in the tripped condition per Required Action B.3. Placing the inoperable channel in trip would conservatively compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue. Alternately, if it is not desired to place the channel in trip (e.g., as in the case where placing the inoperable channel in trip would result in an initiation), Condition HI must be entered and its Required Action taken.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-164 Revision 0, 125

BASES ACTIONS C.1 and C.2 (continued)

The Note states that Required Action C.1 is only applicable for Functions 1.c, 2.c, 1.e, 2.d, and 2.f. Required Action C.1 is also not applicable to Function 3.c (which also requires entry into this Condition if a channel in this Function is inoperable). The loss of one Function 3.c channel results in a loss of the Function (two-out-of-two logic). This loss was considered during the development of Reference 4 and considered acceptable for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowed by Required Action C.2.

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." For Required Action C.1, the Completion Time only begins upon discovery that redundant features in the same system (e.g.,

both CS subsystems) cannot be automatically initiated due to inoperable channels within the same Function as described in the paragraph above. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time from discovery of loss of initiation capability is acceptable because it minimizes risk while allowing time for restoration of channels.

Because of the diversity of sensors available to provide initiation signals and the redundancy of the ECCS design, an allowable out of service time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months has been shown to be acceptable (Ref. 4) to permit restoration of any inoperable channel to OPERABLE status. Alternatively, a Completion Time can be determined in accordance with the Risk Informed Completion Time Program (if there is no loss of function). If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, Condition HI must be entered and its Required Action taken. The Required Actions do not allow placing the channel in trip since this action would either cause the initiation or it would not necessarily result in a safe state for the channel in all events.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-167 Revision 0

BASES ACTIONS E.1 and E.2 (continued)

For Required Action E.1, the Completion Time only begins upon discovery that a redundant feature in the same system (e.g.,

both CS subsystems) cannot be automatically initiated due to inoperable channels within the same Function as described in the paragraph above. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time from discovery of loss of initiation capability is acceptable because it minimizes risk while allowing time for restoration of channels.

If the instrumentation that controls the CS pump minimum flow valve is inoperable, such that the valve will not automatically open, extended CS pump operation with no injection path available could lead to pump overheating and failure. If there were a failure of the instrumentation, such that the valve would not automatically close, a portion of the pump flow could be diverted from the reactor vessel injection path, causing insufficient core cooling. These consequences can be averted by the operator's manual control of the valve, which would be adequate to maintain ECCS pump protection and required flow.

Furthermore, other ECCS pumps would be sufficient to complete the assumed safety function if no additional single failure were to occur. The 7 day Completion Time of Required Action E.2 to restore the inoperable channel to OPERABLE status is reasonable based on the remaining capability of the associated ECCS subsystems, the redundancy available in the ECCS design, and the low probability of a DBA occurring during the allowed out of service time. If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, Condition HI must be entered and its Required Action taken. The Required Actions do not allow placing the channel in trip since this action would not necessarily result in a safe state for the channel in all events.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-169 Amendment 328

Revision 0 BASES ACTIONS F.1 and F.2 (continued)

Because of the diversity of sensors available to provide initiation signals and the redundancy of the ECCS design, an allowable out of service time of 8 days has been shown to be acceptable (Ref. 4) to permit restoration of any inoperable channel to OPERABLE status if both HPCI and RCIC are OPERABLE.

Alternatively, a Completion Time can be determined in accordance with the Risk Informed Completion Time Program (if there is no loss of function). If either HPCI or RCIC is inoperable, the time is shortened to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . If the status of HPCI or RCIC changes such that the Completion Time changes from 8 days to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program (if there is no loss of function), the 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months begins upon discovery of HPCI or RCIC inoperability.

However, the total time for an inoperable, untripped channel cannot exceed 8 days. If the status of HPCI or RCIC changes such that the Completion Time changes from 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months to 8 days, the "time zero" for beginning the 8 day "clock" begins upon discovery of the inoperable, untripped channel. If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, the channel must be placed in the tripped condition per Required Action F.2. Placing the inoperable channel in trip would conservatively compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue. Alternately, if it is not desired to place the channel in trip (e.g., as in the case where placing the inoperable channel in trip would result in an initiation), Condition HI must be entered and its Required Action taken.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-170 Revision 0

BASES ACTIONS G.1 and G.2 (continued)

Required Action G.1 is intended to ensure that appropriate actions are taken if multiple, inoperable channels within similar ADS trip system Functions result in automatic initiation capability being lost for the ADS. Automatic initiation capability is lost if either (a) one Function 4.c channel and one Function 5.c channel are inoperable, (b) a combination of Function 4.e, 4.f, 5.e, and 5.f channels are inoperable such that channels associated with five or more low pressure ECCS pumps are inoperable, or (bc) one or more Function 4.g channels and one or more Function 5.g channels are inoperable.

In this situation (loss of automatic initiation capability), the 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or 8 day allowance, as applicable, of Required Action G.2 is not appropriate, and all ADS valves must be declared inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after discovery of loss of ADS initiation capability in both trip systems.

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." For Required Action G.1, the Completion Time only begins upon discovery that the ADS cannot be automatically initiated due to inoperable channels within similar ADS trip system Functions as described in the paragraph above. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time from discovery of loss of initiation capability is acceptable because it minimizes risk while allowing time for restoration or tripping of channels.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-171 Amendment 328

Revision 0 BASES ACTIONS G.1 and G.2 (continued)

Because of the diversity of sensors available to provide initiation signals and the redundancy of the ECCS design, an allowable out of service time of 8 days has been shown to be acceptable (Ref. 4) to permit restoration of any inoperable channel to OPERABLE status if both HPCI and RCIC are OPERABLE (Required Action G.2). Alternatively, a Completion Time can be determined in accordance with the Risk Informed Completion Time Program (if there is no loss of function). If either HPCI or RCIC is inoperable, the time shortens to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . If the status of HPCI or RCIC changes such that the Completion Time changes from 8 days to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , or in accordance with the Risk Informed Completion Time Program (if there is no loss of function), the 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months begins upon discovery of HPCI or RCIC inoperability. However, the total time for an inoperable channel cannot exceed 8 days. If the status of HPCI or RCIC changes such that the Completion Time changes from 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months to 8 days, the "time zero" for beginning the 8 day "clock" begins upon discovery of the inoperable channel. If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, Condition HI must be entered and its Required Action taken. The Required Actions do not allow placing the channel in trip since this action would not necessarily result in a safe state for the channel in all events.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-172 Amendment 328

Revision 0 BASES ACTIONS H.1, H.2, and H.3 Required Action H.1 requires that the ADS valves be declared inoperable when a combination of Functions 4.e, 4.f, 5.e, and 5.f channels are inoperable such that neither ADS Trip System A or B has two OPERABLE Pump Discharge Pressure - High channels associated with one low pressure ECCS pump.

In this situation (loss of automatic initiation capability), the 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or 8 day allowance, as applicable, of Required Action H.2 is not appropriate, and all ADS valves must be declared inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after discovery of loss of ADS initiation capability in both trip systems. The Notes to Required Action H.1 state that Required Action H.1 is only applicable for Functions 4.e, 4.f, 5.e, and 5.f, and that it is only applicable when both ADS trip systems are inoperable due to Core Spray/LPCI Pump Discharge Pressure - High functions being inoperable.

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal time zero for beginning the allowed outage time clock. For Required Action H.1, the Completion Time only begins upon discovery that the ADS cannot be automatically initiated due to inoperable channels within similar ADS trip system Functions as described in the paragraph above. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completions Time from discovery of loss of initiation capability is acceptable because it minimizes risk while allowing time for restoration of channels. If the inoperable channels cannot be restored to OPERABLE status within the Completion Time, Condition I must be entered and its Required Action taken.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-173 Amendment 328

Revision 0 BASES ACTIONS H.1, H.2, and H.3 (continued)

Required Action H.2 is intended to ensure that appropriate actions are taken if there are not two OPERABLE Pump Discharge Pressure - High channels associated with one low pressure ECCS pump within one ADS trip system, which results in automatic initiation capability being lost for that ADS trip system. Because of the diversity of sensors available to provide initiation signals and the redundancy of the ECCS design, a Completion Time of 8 days has been shown to be acceptable (Ref. 4) to permit restoration of two inoperable Pump Discharge Pressure - High channels associated with one low pressure ECCS Pump to OPERABLE status if both HPCI and RCIC are OPERABLE (Required Action H.2).

Alternatively, a Completion Time can be determined in accordance with the Risk Informed Completion Time Program.

If either HPCI or RCIC is inoperable, the Completion Time shortens to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program. If the status of HPCI or RCIC changes such that the Completion Time changes from 8 days to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , the 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months begins upon discovery of HPCI or RCIC inoperability. However, the total time to restore the required inoperable channels to OPERABLE status cannot exceed 8 days. If the status of HPCI or RCIC changes such that the Completion Time changes from 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months to 8 days, the time zero for beginning the 8 day clock begins upon discovery of the inoperable channel. If the minimum required inoperable channels cannot be restored to OPERABLE status within the Completion Time, Condition I must be entered and its Required Action taken. The Required Actions do not allow placing the channel in trip since this action would not necessarily result in a safe state for the channel in all events. The Notes to Required Action H.2 state that Required Action H.2 is only applicable for Functions 4.e, 4.f, 5.e, and 5.f, and that it is only applicable when one ADS trip system is inoperable due to Core Spray/LPCI Pump Discharge Pressure - High functions being inoperable.

ECCS Instrumentation B 3.3.5.1 (continued)

BFN-UNIT 1 B 3.3-174 Amendment 328

Revision 0 BASES ACTIONS H.1, H.2, and H.3 (continued)

Required Action H.3 is intended to ensure that appropriate actions are taken if inoperable channels within one ADS trip system do not result in loss of automatic initiation capability to respond to a design basis event, but require restoration per Table 3.3.5.1-1. This applies to Functions 4.e, 4.f, 5.e, and 5.f.

The 30 day Completion Time of Required Action H.3 is acceptable, based on operating experience, considering the multiple channels available for meeting the low pressure ECCS pump discharge pressure permissive, and the availability of automatic ADS initiation. If the inoperable channel cannot be restored to OPERABLE status within the Completion Time, Condition I must be entered and its Required Action taken.

HI.1 With any Required Action and associated Completion Time not met, the associated feature(s) may be incapable of performing the intended function, and the supported feature(s) (Core Spray, LPCI, HPCI, or ADS) associated with inoperable untripped channels must be declared inoperable immediately.

CNL-25-088, Application to Revise Technical Specifications to Adopt TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements (BFN TS-558)

Contents

Text

Subject:

Enclosure:

Subject:

SUMMARY

2.0 ASSESSMENT

3.0 REGULATORY EVALUATION

4.0 ENVIRONMENTAL CONSIDERATION

SUMMARY

2.0 ASSESSMENT

3.0 REGULATORY EVALUATION

4.0 ENVIRONMENTAL CONSIDERATION

Navigation menu

CNL-25-088, Application to Revise Technical Specifications to Adopt TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements (BFN TS-558)

Text

Subject:

Enclosure:

Subject:

SUMMARY

2.0 ASSESSMENT

3.0 REGULATORY EVALUATION

4.0 ENVIRONMENTAL CONSIDERATION

SUMMARY

2.0 ASSESSMENT

3.0 REGULATORY EVALUATION

4.0 ENVIRONMENTAL CONSIDERATION

Navigation menu

Search