View source for NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2

{{Adams
| number = ML15282A166
| issue date = 09/21/2015
| title = Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2
| author name = 
| author affiliation = Tennessee Valley Authority
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000259, 05000260, 05000296
| license number = DPR-033, DPR-052, DPR-068
| contact person = 
| case reference number = CNL-15-169
| package number = ML15282A154
| document type = Technical Specification, Amendment
| page count = 45
}}

=Text=
{{#Wiki_filter:ATTACHMENT 2 Proposed Technical Specification Markups   (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive , possess , and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: BFN-UNIT 1 Part 20 , Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) (2) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of a4&sect;8 megawatts thermal. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 288, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33 , the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234. Amendment No. 288 Renewed License No. DPR-33   (3) The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's application dated September 6, 1996, as supplemented December 11, 1996; April 11, May 1; August 14, October 15, November 5 and 14, December 3, 4, 11, 22, 23, 29, and 30, 1997; January 23, March 12 and 13, April 16, 201 and 28, May 7, 14, 1 Q, and 27, and June 2, 5 1 1 O and 19, 1998; evaluated in the NRC staftis Safety Evaluation enclosed with this amendment.
This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment. ( 4) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements: 
: 1. Pre-defined coordinated fire response strategy and guidance 2. Assessment of mutual aid fire fighting assets 3. Designated staging areas for equipment and materials 
: 4. Command and control 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 
: 1. Protection and use of personnel assets 2. Communications 
: 3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 
: 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 
: 2. Dose to onsite responders (5) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plari, emergency plan and/or guard training and qualification plan, as appropriate. 
(6) Deleted.
A {7) Deleted. BFN-UNIT 1 Renewed License No. DPR-33 Revised by letter dated August 16 1 2007 INSERT A 2.C.(6) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.C.(1) of Renewed Facility Operating License No. DPR-33, for Browns Ferry Nuclear Plant Unit 1, to reflect the new maximum licensed reactor core power level of 3952 megawatts thermal (MWt), the license is also amended to add the following license condition.
This license condition provides for monitoring and evaluating potential adverse flow effects as a result of extended power uprate (EPU) operation on plant structures, systems, and components (including verifying the continued structural integrity of the replacement steam dryer). a) The following requirements are placed on the initial operation of the facility, above the thermal power level of 3458 MWt, for the power ascension to 3952 MWt. These conditions are applicable until the first time full EPU conditions (3952 MWt) are achieved. 
: 1. During power ascension greater than 3458 MWt, at test increments that do not exceed 5% of 3458 MWt, the main steam line strain gauges shall be monitored against established acceptance limits to assure steam dryer structural integrity is maintained.
If flow-induced resonances are identified and the strains or vibrations increase above the predetermined criteria, power ascension shall be stopped until analysis demonstrating acceptable results is performed. 
: 2. During power ascension greater than 3458 MWt, hold points, in increments that do not exceed 5% of 3458 MWt, shall be established for NRC review of power ascension data. Power shall not be increased above each hold point until 96 hours after the NRC confirms receipt of the evaluations unless, prior to the expiration of the 96 hour period, the NRC communicates that the NRC staff has no objections to the continuation of power ascension.
b) After full EPU power has been achieved, replacement steam dryer data at the full power level shall be provided to the NRC within 96 hours. c) Following power ascension to full EPU conditions, a vibration summary report for piping and valve vibration data collected at full EPU power level shall be provided to the NRC. Vibration data shall be collected for piping and valve locations deemed prone to vibration identified in Attachment 45 to the EPU License Amendment Request, including the identified locations associated with the main steam (MS) system, the feedwater system, the condensate system, the extraction steam system, the heater drain system, safety relief valves, main steam isolation valves, the inboard isolation valve for MS drain piping, the inboard isolation valve for the reactor core isolation cooling turbine steam supply line, and the inboard isolation valve for the high pressure coolant injection turbine steam supply line. The report shall also include an evaluation of the measured vibration data collected during power ascension compared against established acceptance limits. The report shall be submitted to the NRC staff in accordance with 10 CFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. d) Following power ascension to full EPU conditions, a confirmatory analysis shall be performed for the replacement steam dryer. This analysis shall include a final load definition and stress re-analysis of the replacement steam dryer using the biases and uncertainties determined at EPU conditions and a comparison of predicted and measured pressures and strains on the replacement steam dryer. The report shall be submitted to the NRC staff in accordance with 10 CFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. e) During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be performed of all accessible , susceptible locations of the replacement steam dryer in accordance with BWRVIP-139A and General Electric inspection guidelines.
The results of the visual inspections of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.
1.1 Definitions (continued)
Definitions
* 1.1 OPERABLE -OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function( s) are also capable of performing their related support function(s).
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.
These tests are: RATED THERMAL POWER (RTP) BFN-UNIT 1 a. Described in Section 13.10, Refueling Test Program; of the FSAR; b. Authorized under the provisions of 10 CFR 50.59; or c. Otherwise approved by the Nuclear Regulatory Commission.
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3-4p8-MWt. (continued) 1; 1-6 Amendment No. 2J4,269 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure<
785 psig or core flow < 10% rated core flow: THERMAL POWER shall be 0/o l RTr . 23
* 2.1.1.2 With the reactor steam dome pressure 785 psig and core flow 10% rated core flow: SLs 2.0 MCPR shall 1.09 for two recirculation loop operation 1.11 for single loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1 .2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. BFN-UNIT 1 2.0-1 Amendment 267 SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.7.5 SR 3.1.7.6 SR 3.1.7.7 SURVEILLANCE Verify the concentration and temperature of boron in solution are within the limits of Figure 3.1.7-1. Verify the minimum quantity of Boron-10 in the SLC solution tank and available for injection is 2 203 pounds. Verify the SLC conditions satisfy the following equation: ( C )( Q )( E ) * > -1 (+a-wt. %)(-86-gpm)(4-9-:8-atom%) -lCiJ t I 94 I where, C = sodium pentaborate solution concentration (weight percent) Q = pump flow rate (gpm) E = Boron-10 enrichment (atom percent Boron-10)
Verify each pump develops a flow rate 2 39 gpm at a discharge pressure 2 1325 psig. SLC System 3.1.7 FREQUENCY Once within 8 hours after discovery that SPB concentration is > 9.2% by weight AND 12 hours thereafter 31 days 31 days AND Once within 24 hours after water or boron is added to the solution 24 months (continued)
BFN-UNIT 1 3.1-25 Amendment No. &#x17d;, 251, 263, 269 I 3.2 POWER DISTRIBUTION LIMITS APLHGR 3.2.1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL L-mJ ACTIONS CONDITION REQUIRED ACTf ON COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours limits. within limits. B. Required Action and 8.1 Reduce THERMAL 4 hours *associated Completion POWER to< Time not met.* . 23 . BFN-UNIT 1 3.2-1 Amendment No. 234 SURVEILLANCE REQUIREMENTS SR 3.2.1.1 SURVEILLANCE Verify all APLHGRs are less than or equal to the limits specified in the COLR. APLHGR 3.2.1 FREQUENCY Once Within 12 hours after AND 24 hours thereafter BFN-UNIT 1 3.2-2 Amendment No. 234 3.2 *POWER DISTRIBUTION LIMITS \_) 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) MCPR 3.2.2 LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR. APPLICABILITY:
THERMAL RTP. ACTIONS CONDITION REQUIRED ACTION A. Any MCPR not within A.1 Restore MCPR{s) to limits. within limits. -8. Required Action and 8.1 Reduce THERMAL associated Completion POWER to< Time not met. 23 BFN-UNIT 1 3.2-3 COMPLETION TIME 2 hours 4 hours Amendment No. 234 SURVEILLANCE REQUIREMENTS SR 3.2.2.1 SR 3.2.2.2 SURVEILLANCE Verify all MCPRs are greater than or equal to the limits specified in the COLR. Determine the MCPR limits*. MCPR 3.2.2 FREQUENCY Once within 12 hours after 
*L@J AND 24 hours thereafter Once within . 72 hours after each completion of SR 3.1.4:1 Once within 72 hours after each completion of SR 3.1.4.2 BFN-UNIT 1 3.2-4 Amendment No. 234 3.2 POWER DISTRIBUTION LIMITS LHGR 3.2.3 U 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) u LCO 3.2.3 A11 LHGRs shall be less than or .equal to the limits specified in the COLR. APPLICABILITY:
THERMAL RTP. ACTIONS CONDITION REQUIRED ACTION A. Any LHGR not within A.1 Restore LHGR(s} to limits. within limits. 8. Required Act_ion and 8.1 Reduce THERMAL associated Completion POWER to< Time not met. 23 BFN-UN1T 1 3.2-5 COMPLETION TIME 2 hours 4 hours Amendment No. 234 u . SURVEILLANCE REQUIREMENTS SR 3.2.3.1 SURVEILLANCE Verify all LHGRs are less than or equal to the limits specified in the COLR. LHGR 3.2.3 FREQUENCY Once within 12 hours after L@J AND 24 hours thereafter BFN-UNIT 1 3.2-6 Amendment No. 234 ACTIONS (continued)
CONDITION 
: c. One or more Functions C.1 with RPS trip capability not maintained. 
: 0. Required Action and D.1 associated Completion Time of Condition A, B, or C not met. E. As required by Required E.1 Action D.1 and referenced in Table 3.3.1.1-1.
F. As required by Required F.1 Action D .1 and referenced in Table 3.3.1.1-1.
G. As required by Required G.1 Action D.1 and referenced in Table 3.3.1.1-1.
H. As required by Required H.1 Action D.1 and referenced in Table 3.3.1.1-1.
BFN-UNIT 1 REQUIRED ACTION Restore RPS trip capability.
Enter the Condition referenced in Table 3.3.1.1-1 for the channel. Reduce THERMAL POWER to< 26 Be in MODE 2. Be in MODE 3. Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
RPS Instrumentation 3.3.1.1 COMPLETION TIME 1 hour Immediately 4 hours 6 hours 12 hours Immediately 3.3-2 Amendment 262 SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1 
: 1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function. 
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains RPS trip capability.
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 BFN-UNIT 1 SURVEILLANCE Perform CHANNEL CHECK. --------------------------NC>l"E-------------------------
Not required to be performed until 12 hours after THERMAL P()WER Verify the absolute difference between the average power range monitor (APRM) channels and the calculated power is ::;; 2% RTP while operating at 2+.5%.B_TP. -
--------------------------N()l"E-------------------------
Not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL FUNCTIONAL TEST. FREQUENCY 24 hours 7 days 7 days (continued) 3.3-3 Amendment No.-2J4, 262 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.1.1.10 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17 BFN-UNIT 1 SURVEILLANCE FREQUENCY Perform CHANNEL CALIBRATION.
184 days (Deleted)
Perform CHANNEL FUNCTIONAL TEST. 24 months Neutron detectors are excluded.
Perform CHANNEL CALIBRATION.
24 months Perform LOGIC SYSTEM FUNCTiONAL 24 months TEST. Verify '"f urbine Stop Valve -Closure and 24 months '"furbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when '"fHERMAL POWER is --------------------------NOTE-------------------------
For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL FUNC'"flONAL 
'"fEST. 184 days Verify OPRM is not bypassed when APRM 1231 24 months Simulated Thermal Power and
* recirculation drive flow is < 60% of rated recirculation drive flow. 3.3-5 Amendment No. 234, 262, 263,266 FUNCTION 1. Intermediate Range Monitors a. Neutron Flux
* High b. lnop 2. Average Power Range Monitors a. Neutron Flux -High, Set down b. Flow Biased Simulated Thermal Power -H i gh c. Neutron Flux -High Table 3.3.1.1-1(page1of3)
Reactor Protection System Instrumentation APPLICf.\BLE MODES OR OTHER SPECIFIED CONDITIONS 2 5(a) 2 5(a) 2 REQUIRED CHANNELS PER TRIP SYSTEM 3 3 3 3 CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 G H G H G F F (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (b) Each APRM channel provides inputs to both tr i p systems. RPS Instrumentation 3.3.1.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE SR 3.3.1.1.1 SR 3.3.1.1.3 SR 3.3.1.1.5 SR 3.3.1.1 .6 SR 3.3.1.1.9 SR 3.3.1.1.14 SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1.1.14 SR 3.3.1.1.3 SR 3.3.1.1.14 SR 3.3.1.1.4 SR 3.3.1.1.14 SR 3.3.1.1.1 SR 3.3. 1. 1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1: 1.1 SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 :::; 120/125 divisions of full scale s120112s divisions of full scale NA NA Q}J RTP I o.55 I + .g&% RT P L.:::.:::..p and s 120% RTP(c) :::; 120% RTP continued -RTP when reset for single loop operation per LCO 3.4.1 , " Recirculat i on Loops Operating." . BFN-UNIT 1 3.3-6 Amendment No. 236, 262, 269 FUNCTION 7. Scram Discharge Volume Water Level -High (continued) 
: b. Float Switch 8. Turbine Stop Valve -Closure 9. Turbine Control Valve Fast Closure, Trip Oil Pressure -
: 10. Reactor Mode Switch -Shutdown Position 11. Manual Scram 12. RPS Channel Test Switches Table 3.3.1.1".'1 (page 3 of 3) Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 1,2 5(a) 1,2 5(a) 1,2 5(a) 1,2 5(a) REQUIRED CHANNELS PER TRIP SYSTEM 2 2* 4 2 . 1 2 2 CONDITIONS REFERENCED FROM REQUIRED ACTION0.1 G H E E G H G H G H (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
RPS Instrumentation 3.3.1.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE SR 3.3.1.1.8 SR 3.3;1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.4 SR 3.3.1.1.4 s 46 gallons s 46 gallons s 10% closed 2: 550 psig NA NA NA NA NA NA (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the chaMel 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 shan be specified in Chapter 7 of the Updated Final Safety Analysis Report. BFN-UNIT 1 3.3-8 Amendment No. 234 , 267, 259 Feeawater ana Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 
\__) 3.3.2.2. Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Two channels of feedwatet and main turbine high water level trip instrumentation per trip system shall be OPERABLE .. APPLICABILITY:
THERMAL POWER L@J ACTIONS ----------------------------NOTE---------------------------
Separate Condition entry is a11owed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Pla.ce channel(s) in trip. 7 days and main turbine high water level trip channels inoperable, in one trip . system. B. One or more feedwater 8.1 Restore f eedwater and 2 hours and main turbine high main turbine high water water level trip channels level trip capability. 
*inoperable in each trip system. C. Required Action and C.1 Reduce THERMAL .4 hours associated Completion Time not met. 23 BFN-UNIT 1 3.3-21 Amendment No. 234 EOC-RPT Instrumentation 3.3.4.1 -3".3 INSTRUMENTATION. 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation LCD 3.3.4.1 APPLICABILITY; BFN-UNIT 1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:
OR 1. Turbine Stop Valve (TSV) -Closure; and 2. Turbine Control Valve (TCV) Fast Closure, Trip Oi1 Pressure *Low. b. LCO 3.2.2, "MINIMUM CRITlCAL POWER RATIO (MCPR)," limits for inoperable EOC-RPT as specified in the COLR are made applicable; and c. LCD 3.2.3. "UNEAR HEAT GENERATlON RATE (LHGR)," limits for an inoperable EOC-RPT, as specified in the COLR, are made applicable.
THERMAL POWER t! 3R% RTP. L-@J 3.3-29 Amendment No. J . 281 ACTIONS EOC-RPT Instrumentation 3.3.4.1 Separate Condition entry is allowed for each channel. COND1TION A. One or more channels inoperable.
B. One or more Functions with EOC-RPT trip capability not maintained.
AND M CPR and LHGR limits
* for in0perable EOC-RPT not made appflcable.
C. Required Action and associated Completlon Time not met. BFN*UNIT 1 -------------------
REQUIRED ACTION A.1 Restore channel to OPERABLE status. OR A.2 ---NOTE---
Not applicable if inoperable channel is the result of an inoperable breaker. Place channel in trip. B.1 Restore EOC-RPT trip capability.
OR B.2 Apply MCPR and LHGR limits for ;noperable EOC-RPT as specified in the COLR. C.1 Reduce THERMAL POWER 26 3.3-30 COMPLETION TIME 72 hours 72 hours 2 hours 2 hours 4 hours Amendment No. -234 281 EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS
______ _ When a channel is placed in an inoperable status for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains EOC-RPT trip capability: . . ------------------------------------------------------------------------------------------------------------------
SR 3.3.4.1.1 SR 3.3.4.1.2 SR 3.3.4.1.3 SR 3.3.4.1.4 BFN-UNIT 1 SURVEILLANCE FREQUENCY Perform CHANNEL FUNCTIONAL TEST. 92 days Verify TSV -Closure and TCV Fast Closure, 24 months Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER is Lf26l Perform CHANNEL CALIBRATION.
The 24 months Allowable Values shall be: TSV -Closure: 10% closed; and TCV Fast Closure, Trip Oil Pressure -Low: 550 psig. Perform LOGIC SYSTEM FUNCTIONAL TEST including breaker actuation.
24 months 3.3-31 Amendment No.  
.. Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SR 3.4.2.1 BFN-UNIT 1 SURVEILLANCE 
: 1. Not required to be performed until 4 hours after associated recirculation loop is in operation. 
: 2. Not required to be performed until 24 hours after > {i TP. a. Recirculation pump flow to speed ratio differs by s 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by s 5% from established patterns.
* b. Each jet pump diffuser to lower plenum differential pressure differs by s 20% from established pattem_s. c. Each jet pump flow differs by s 10% from established patterns.
FREQUENCY 3.4-6 Amendment No. 234 CAO System 3.6.3.1 .SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 2615 I 
-2500 gal of liquid nitrogen are 31 days contained in each nitrogen storage tank. SR 3.6.3.1.2 Verify each CAD subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position
* or can be aligned to the correct position.
BFN-UNIT 1 3.6-41 Amendment No. 234 Main Turbine Bypass System 3.7.5 3.7 PLANT SYSTEMS 3.7 .5 Main Turbine Bypass System LCO 3.7.5 APPLICABILITY:
ACTIONS The Main Turbine Bypass System shall be OPERABLE.
The following Hmits are made applicable: 
: a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and b. LCO 3.2.2, *MINIMUM CRITICAL POWER RATfO (MCPR): limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and c. LCO 3.2.3. *uNEAR HEAT GENERATION RATE (LHGR)." limits for an inoperable Main Turt>;ne Bypass System, as specified in the COLR. THERMAL CONDITION REQUIRED ACTION COMPLETION A. Requirements of the LCO A.1 not met. B. Required Action and B.1 associated Compfetion Time not met. BFN-UNIT 1 Satisfy the requirements of the LCO. Reduce THERMAL POWER 23 3.7-16 TIME 2 hours 4 hours Amendment No. 234 281 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Program (SFDP) (continued) . A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed.
For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and: a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.
The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
* 5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 4-!f5 psig. The maximum allowable primary 49* 1 containment leakage rate, La, shall be 2% of primary containment air weight per day at Pa-(continued)
BFN-UNIT 1 5.0-20 Amendment No. sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of thermal. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 313, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. For Surveillance Requirements (SRs) that are new in Amendment 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 253. 3) The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to _the appropriate documents, as described in the licensee's Amendment No. 313 BFN-UNIT 2 Renewed License No_ DPR-52   application dated September 6, 1996, as supplemented May 1, August 14, November 5 and 14, December 3, 4, 11, 22, 23, 29, and 30, 1997; January 23, March 12, April 16, 20 and 28, May 7, 14, 19, and 27 1 and June 2, 5, 10 and 19, 1998; evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.
This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment. 
(4) Deleted. (5) Classroom and simulator training on all power uprate related changes that affect operator performance will be conducted prior to operating at uprated conditions.
Simulator changes that are consistent with power uprate conditions will be made and simulator fidelity will be validated in accordance with ANSI/ANS 3.5-1985.
Training and the plant simulator will be modified, as necessary, to incorporate changes identified during startup testing. This amendment is effective i mmediately. 
(6) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements:
1 . Pre-defined coordinate.d fire response strategy and guidance 2. Assessment of mutual aid fire fighting assets 3. Designated staging areas for equipment and materials 
: 4. Command and control 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 
: 1. Protection and use of personnel assets 2. Communications 
: 3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 
: 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 
: 2. Dose to onsite responders (7) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.
BFN-UNIT 2 Renewed License No. DPR-52 Revised by letter dated Augtlst 16 , 2007 INSERT B 2.G.(4) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.C.(1) of Renewed Facility Operating License No. DPR-52, for Browns Ferry Nuclear Plant Unit 2, to reflect the new maximum licensed reactor core power level of 3952 megawatts thermal (MWt), the license is also amended to add the following license condition.
This license condition provides for monitoring and evaluating potential adverse flow effects as a result of extended power uprate (EPU) operation on plant structures, systems, and components (including verifying the continued structural integrity of the replacement steam dryer). a) The following requirements are placed on the initial operation of the facility, above the thermal power level of 3458 MWt, for the power ascension to 3952 MWt. These conditions are applicable until the first time full EPU conditions (3952 MWt) are achieved. 
: 1. During power ascension greater than 3458 MWt, at test increments that do not exceed 5% of 3458 MWt, the main steam line strain gauges shall be monitored against established acceptance limits to assure steam dryer structural integrity is maintained.
If flow-induced resonances are identified and the strains or vibrations increase above the predetermined criteria, power ascension shall be stopped until analysis demonstrating acceptable results is performed. 
: 2. During power ascension greater than 3458 MWt, hold points, in increments that do not exceed 5% of 3458 MWt, shall be established for NRC review of power ascension data. Power shall not be increased above each hold point until 96 hours after the NRG confirms receipt of the evaluations unless, prior to the expiration of the 96 hour period, the NRG communicates that the NRC staff has no objections to the continuation of power ascension.
b) After full EPU power has been achieved, replacement steam dryer data at the full power level shall be provided to the NRG within 96 hours. c) Following power ascension to full EPU conditions, a vibration summary report for piping and valve vibration data collected at full EPU power level shall be provided to the NRG. Vibration data shall be collected for piping and valve locations deemed prone to vibration identified in Attachment 45 to the EPU License Amendment Request, including the identified locations associated with the main steam (MS) system, the feedwater system, the condensate system, the extraction steam system, the heater drain system, safety relief valves, main steam isolation valves, the inboard isolation valve for MS drain piping, the inboard isolation valve for the reactor core isolation cooling turbine steam supply line, and the inboard isolation valve for the high pressure coolant injection turbine steam supply line. The report shall also include an evaluation of the measured vibration data collected during power ascension compared against established acceptance limits. The report shall be submitted to the NRG staff in accordance with 10 GFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. d) Following power ascension to full EPU conditions, a confirmatory analysis shall be performed for the replacement steam dryer. This analysis shall include a final load definition and stress re-analysis of the replacement steam dryer using the biases and uncertainties determined at EPU conditions and a comparison of predicted and measured pressures and strains on the replacement steam dryer. The report shall be submitted to the NRC staff in accordance with 10 CFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. e) During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be performed of all accessible, susceptible locations of the replacement steam dryer in accordance with BWRVIP-139A and General Electric inspection guidelines.
The results of the visual inspections of the steam dryer shall be submitted to the NRG staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.
1.1 Definitions (continued)
PHYSICS TESTS RATED THERMAL POWER *(RTP) SHUTDOWN MARGIN (SOM) .
* BFN-UNIT 2 Definitions 1.1 PHYSICS fESTS shaJJ be those tests performed to measure the fundamental nuclear characteristics of . the reactor core and related instrumentation.
These tests are: a. Oescribed in Section 13.10, Refueling Test Program; *of the FSAR; b. Authorized under the provisions of 10 CFR 50.59; or c. Otherwise approved by the Nuclear Regulatory Commission.
RTP shall be a total reactor core heat transfer rate to the reactor coolant MWt. SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that: a. The reactor is xenon free; b. The moderator temperature is 68&deg;F; and c. All control rods are fully except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM . 1.1-6 (continued)
Amendment No. 254 SEP 0 8 1998 SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2. 1 . 1 Reactor Core S Ls 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow: THERMAL POWER shall 2.1.1.2 With the reactor steam dome pressure 85 psig and core flow 10% rated core flow: MCPR shall 1.06 for two recirculation loop operation 1.08 for single loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. BFN-UNIT 2 2.0-1 Amendment No. 311  

\_) SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.7.5 SR 3.1.7.6 SR 3.1.7.7 BFN-UNIT 2 SURVEILLANCE Verify the concentration and temperature of boron in solution are within the limits of Figure 3.1.7-1. FREQUENCY Once within 8 hours after discovery that SPB concentration is > 9.2% by weight 12 hours thereafter
* Verify the minimum quantity of Boron-10 in the 31 days SLC solution tank and available for injection is ;;:: 4ie pQYILds.
Verify the SLC conditions satisfy the following 31 days equation: ( C )( Q )( E ) (43-wt. %)(-Bf gpm)(19 f 8 a 1 tomo/1 1 LI sol 94 where, C = sodium pentaborate solution concentration (weight percent) Q = pump flow rate (gpm) E = Boron-10 enrichment 
{atom percent Boron-10)
Verify each pump develops a flow 39 gpm at a discharge pressure ;;:: 1325 psig. Once within 24 hours after water or boron is added to the solution 24 months (continued) 3.1-25 Amendment No. 290 I I 3.2 POWER DISTRIBUTION LIMITS .APLHGR 3.2.1 .\__) 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL POWER;:: 2f% RTP. L@J ACTIONS CONDITION* REQUIRED ACTION COMPLETION . TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours limits. within limits. 8. Required Action and 8.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met. 23 BFN-UNIT2 3.2-1 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.2.1.1. SURVEILLANCE Verify all APLHGRs are less than or e*qual to the limits specified in the COLR. APLHGR 3.2.1 FREQUENCY Once within 12 hqurs after RTP AND 24 hours thereafter BFN-UNIT2 3.2-2 Amendment No. 253 3.2 POWER DISTRIBUTION LIMITS \_) 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) MCPR 3.2.2 LCO 3.2.2 All MCPRs shall be g.c_eater than or equal to the MCPR operating limits specified in the COLR. APPLICABILITY:
THERMAL 2f% RTP. ACTIONS CONDITION . REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours limits. within Umits. B. Required Action and 8.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met. 23 . BFN-UNIT 2 3.2-3 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.2.2.1 SR 3.2.2.2 SURVEILLANCE Verify all MCPRs are greater than or equal to the limits specified in the COLR. Determine the MCPR limits. MCPR 3.2.2 FREQUENCY Once within 12 hours after ;:: 2f% RTP .. AND 24 hours thereafter Once within 72 hours after each completion of SR 3.1.4.1 Once within 72 hours after each *completion
* of SR 3.1.4.2 . BFN-UNIT2 3.2-4 Amendment No. 253 3.2 POWER DISTRIBUTION LIMITS \. _ _) 3.2.3 LINEAR HEAT GENERATION RATE LHGR 3.2.3 LCO 3.2.3 All LHGRs shall be Jess than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL POWER RTP. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to 2 hours limits. within limits. 8. Required Action and 8.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met..
* 23 BFN-UNIT2 3.2-5 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.2.3.1 SURVEILLANCE Verify all LHGRs are less than or equal to the limits specified in the COLR. LHGR 3.2.3 FREQUENCY Once within 12 hours after 
.. AND 24 hours thereafter 8FN-UNIT2 Amendment No. 253 ACTIONS (continued)
CONDITION 
: 8. NOTE 8.1 Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR 8.2 One or more Functions with one or more required channels inoperable in both trip systems. C. One or more Functions C.1 with RPS trip capability not maintained.
D. Required Action and D.1 associated Completion Time of Condition A, B, or C not met. E. As required by Required E.1 Action 0.1 and referenced in Table 3.3.1.1-1.
F. As required by Required F.1 Action 0.1 and referenced in Table 3.3.1.1-1.
REQUIRED ACTION Place channel in one trip system in trip. Place one trip system in trip. . .. Restore RPS trip *capability.
Enter the Condition referenced in Table 3.3.1.1-1 for the channel. Reduce THERMAL POWER to< . 26 Be in MODE2. RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours 6 hours 1 hour Immediately 4 hours 6 hours {continued)
BFN-UNIT 2
* 3.3-2 Amendment No. 258 -s,\'l(tlQ; kl.t, at 
&#xa3;41.al c& MAR 11 1399 n 1c O f) -k , 'o:9 .. ) Rv, \&#xa3;JDP1 P II. lqqq_
SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1 *'-._) NOTES---------* 
: 1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function. 
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains RPS trip capability.
SURVEILLANCE 
*FREQUENCY.
SR 3.3.1.1.1 Perform CHANNEL CHECK 24 hours SR 3.3.1.1.2 NOTE Not required to be performed until 12 hours after THERMAL POWER :<: ti% 
*. 23 Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power is 2% RTP while operating at;?;
23 SR 3.3.1.1.3 NOTE Not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL FUNCTIONAL TEST. 7 days {continued) 8FN-UNIT2 3.3-4 Amendment No. 253  
\..._,)
* RPS Instrumentation 3.3.1.1 : SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION.
184 days SR 3.3.1.1.11 (Deleted)
SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.13 NOTE Neutron excluded.
Perform CHANNEL CALIBRATION. 
.24 months SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST. SR 3.3.1.1.15 Verify Turbine Stop Valve -Closure and 24 months Turbine Control Valve Fast Closure, Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER 26 SR 3.3.1.1.16 NOTE For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE2. Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.1.17 Verify OPRM is not bypassed when APRM 1231 24 months Simulated Thermal Power is Z!S% and recirculation drive flow is < 60% of rated recirculation drive flow. BFN-UNIT 2 3.3-6 Amendment No. 258 *;:. c  
\__) \_) RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3) Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION 0.1 1. Intermediate Range MonJtcra a. Neutrortflux
* High 2 3 . G. SR 3.3:1.1.1 s 120/125 SR 3.3.1.1.3 dMsions of fuU SR 3.3.1.1.5 scale SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.14 5(a) 3 H SR 3.3.1.1.1 s 120/125 SR 3.3.1.1.-i dMsJons of fuU SR 3.3.1.1.9 scale SR 3.3.1.1.14 
: b. tnop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.1-i 5{*) 3 H SR 3.3.1.U NA SR 3.3.1.1.14 
: 2. Average Power Range Monlcn ** Neutron Flux
* High, 2 3(b) G SR 3.3.1.1.1 s 'l>>RTP (Setdown)
SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 *SR 3.3.1.1.16 b. Flow Biased Slmulated 1 3(b) F SR 3.3.1.1.1 ThennaJ Pc:Nter -High SR 3.3.1.1.2 
! 61.., I 65.5 I SR 3.3.1.1.7 andS120% I SR 3.3.1.1.13 RTP(e) SR 3.3.1.1.16 
: c. Neutron Fk.cc
* High 1 . 3(b) F SR 3.3.1.1.1 S120%RTP SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 (continued) 
* (a) Wlth arrf control red wtthdrawn frcm a core eel ccntainlng one or more fuel assemblies. (b} Each AP RM channel provides Inputs to both trip systems. (c) ii6. i , .6 7 RTP .men reset for slngle loop operation""'
LCO 3.4.1, "Recirculation loops Operating.*
0.55 65.5 0.55 . . BFN-UNIT2 3.3-7 Pbte: lfli s is eabl e efter eem*ei-d ng C}el e 11 ooe1 ati m. Amendment No. 256 DEC 2 3 1998 FUNCTION 7. Scram Discharge Volume Water level -High (continued) 
: b. Float Switch 8. Turbine Stop Valve -Closure 9. Turbine Control Valve Fast Closure, Trip Oil Pressure -Low(d) 10. Reactor Mode Switch -Shutdo.wn Position 11. Manual Scram 12. RPS Channel Test Switches 13. Deleted Table 3.3.1.1-1(page3of 3} Reactor Protection System Instrumentation APPLICABLE . MODES OR OTHER . SPECIFIED CONDITIONS 1,2 5(a) 1,2 5{a) 1,2 5(a) 1,2 5(a) REQUIRED CHANNELS PER TRIP SYSTEM 2 2 4 2 2 2 CONDITIONS REFERENCED FROM REQUIRED . ACTION D.1 G H E E G H G H G H (a) With any control rod withdrawn from a core ceU containing one or more fuel assemblies.
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS SR 3.3.1.1.B SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 . SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.4 SR 3.3.1.1.4 ALLOWABLE VALUE 46 gallons s 46 gallons s 10% closed 550 psig NA NA NA NA NA NA (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an Initial determination to ensure confidence that the channel can perfor_m as required before retumiug 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 ls 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. BFN-UNIT 2 3.3-9 Amendment No. 258, 276, 296  
\__) Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Two channels off eedwater and main turbine high water I ever trip per trip system shall be OPERABLE.
APPLICABILITY:
_ THERMAL RTP. ACTIONS ---------------------------NOTE--------------------------
Separate Condition entr)' is allowed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Place channel(s) in trip. 7 days and main turbine high water level trip channels inoperable, in one trip system. B. One or more feedwater 8.1 Restore f eedwater and 2 hours and main turbine high main turbine high water water level trip channels
* inoperable 
*in each trip level trip capability.
system .. C. Required Action and C.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met. 23 . BFN-UNIT 2 3.3-22 Amendment No. 253 EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation LCO 3.3.4.1 APPLICABILITY:
BFN-UNIT 2 a. Two channels per trip system for each EOC-RPT
* instrumentation Function listed below shall be OPERABLE:
OR 1. Turbine Stop Valve (TSV) -Closure; and 2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure -Low. b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO {MCPR}," limits for inoperable EOC-RPT as specified in the COLR are made applicable; and c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR}," limits for inoperable EOC-RPT as specified in the COLR are made applicable.
THERMAL RTP. 3.3-30 Amendment No.
ATTACHMENT 2 Proposed Technical Specification Markups   (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive , possess , and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: BFN-UNIT 1 Part 20 , Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) (2) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of a4&sect;8 megawatts thermal. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 288, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33 , the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234. Amendment No. 288 Renewed License No. DPR-33   (3) The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's application dated September 6, 1996, as supplemented December 11, 1996; April 11, May 1; August 14, October 15, November 5 and 14, December 3, 4, 11, 22, 23, 29, and 30, 1997; January 23, March 12 and 13, April 16, 201 and 28, May 7, 14, 1 Q, and 27, and June 2, 5 1 1 O and 19, 1998; evaluated in the NRC staftis Safety Evaluation enclosed with this amendment.
This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment. ( 4) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements: 
: 1. Pre-defined coordinated fire response strategy and guidance 2. Assessment of mutual aid fire fighting assets 3. Designated staging areas for equipment and materials 
: 4. Command and control 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 
: 1. Protection and use of personnel assets 2. Communications 
: 3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 
: 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 
: 2. Dose to onsite responders (5) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plari, emergency plan and/or guard training and qualification plan, as appropriate. 
(6) Deleted.
A {7) Deleted. BFN-UNIT 1 Renewed License No. DPR-33 Revised by letter dated August 16 1 2007 INSERT A 2.C.(6) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.C.(1) of Renewed Facility Operating License No. DPR-33, for Browns Ferry Nuclear Plant Unit 1, to reflect the new maximum licensed reactor core power level of 3952 megawatts thermal (MWt), the license is also amended to add the following license condition.
This license condition provides for monitoring and evaluating potential adverse flow effects as a result of extended power uprate (EPU) operation on plant structures, systems, and components (including verifying the continued structural integrity of the replacement steam dryer). a) The following requirements are placed on the initial operation of the facility, above the thermal power level of 3458 MWt, for the power ascension to 3952 MWt. These conditions are applicable until the first time full EPU conditions (3952 MWt) are achieved. 
: 1. During power ascension greater than 3458 MWt, at test increments that do not exceed 5% of 3458 MWt, the main steam line strain gauges shall be monitored against established acceptance limits to assure steam dryer structural integrity is maintained.
If flow-induced resonances are identified and the strains or vibrations increase above the predetermined criteria, power ascension shall be stopped until analysis demonstrating acceptable results is performed. 
: 2. During power ascension greater than 3458 MWt, hold points, in increments that do not exceed 5% of 3458 MWt, shall be established for NRC review of power ascension data. Power shall not be increased above each hold point until 96 hours after the NRC confirms receipt of the evaluations unless, prior to the expiration of the 96 hour period, the NRC communicates that the NRC staff has no objections to the continuation of power ascension.
b) After full EPU power has been achieved, replacement steam dryer data at the full power level shall be provided to the NRC within 96 hours. c) Following power ascension to full EPU conditions, a vibration summary report for piping and valve vibration data collected at full EPU power level shall be provided to the NRC. Vibration data shall be collected for piping and valve locations deemed prone to vibration identified in Attachment 45 to the EPU License Amendment Request, including the identified locations associated with the main steam (MS) system, the feedwater system, the condensate system, the extraction steam system, the heater drain system, safety relief valves, main steam isolation valves, the inboard isolation valve for MS drain piping, the inboard isolation valve for the reactor core isolation cooling turbine steam supply line, and the inboard isolation valve for the high pressure coolant injection turbine steam supply line. The report shall also include an evaluation of the measured vibration data collected during power ascension compared against established acceptance limits. The report shall be submitted to the NRC staff in accordance with 10 CFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. d) Following power ascension to full EPU conditions, a confirmatory analysis shall be performed for the replacement steam dryer. This analysis shall include a final load definition and stress re-analysis of the replacement steam dryer using the biases and uncertainties determined at EPU conditions and a comparison of predicted and measured pressures and strains on the replacement steam dryer. The report shall be submitted to the NRC staff in accordance with 10 CFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. e) During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be performed of all accessible , susceptible locations of the replacement steam dryer in accordance with BWRVIP-139A and General Electric inspection guidelines.
The results of the visual inspections of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.
1.1 Definitions (continued)
Definitions
* 1.1 OPERABLE -OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function( s) are also capable of performing their related support function(s).
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.
These tests are: RATED THERMAL POWER (RTP) BFN-UNIT 1 a. Described in Section 13.10, Refueling Test Program; of the FSAR; b. Authorized under the provisions of 10 CFR 50.59; or c. Otherwise approved by the Nuclear Regulatory Commission.
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3-4p8-MWt. (continued) 1; 1-6 Amendment No. 2J4,269 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure<
785 psig or core flow < 10% rated core flow: THERMAL POWER shall be 0/o l RTr . 23
* 2.1.1.2 With the reactor steam dome pressure 785 psig and core flow 10% rated core flow: SLs 2.0 MCPR shall 1.09 for two recirculation loop operation 1.11 for single loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1 .2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. BFN-UNIT 1 2.0-1 Amendment 267 SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.7.5 SR 3.1.7.6 SR 3.1.7.7 SURVEILLANCE Verify the concentration and temperature of boron in solution are within the limits of Figure 3.1.7-1. Verify the minimum quantity of Boron-10 in the SLC solution tank and available for injection is 2 203 pounds. Verify the SLC conditions satisfy the following equation: ( C )( Q )( E ) * > -1 (+a-wt. %)(-86-gpm)(4-9-:8-atom%) -lCiJ t I 94 I where, C = sodium pentaborate solution concentration (weight percent) Q = pump flow rate (gpm) E = Boron-10 enrichment (atom percent Boron-10)
Verify each pump develops a flow rate 2 39 gpm at a discharge pressure 2 1325 psig. SLC System 3.1.7 FREQUENCY Once within 8 hours after discovery that SPB concentration is > 9.2% by weight AND 12 hours thereafter 31 days 31 days AND Once within 24 hours after water or boron is added to the solution 24 months (continued)
BFN-UNIT 1 3.1-25 Amendment No. &#x17d;, 251, 263, 269 I 3.2 POWER DISTRIBUTION LIMITS APLHGR 3.2.1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL L-mJ ACTIONS CONDITION REQUIRED ACTf ON COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours limits. within limits. B. Required Action and 8.1 Reduce THERMAL 4 hours *associated Completion POWER to< Time not met.* . 23 . BFN-UNIT 1 3.2-1 Amendment No. 234 SURVEILLANCE REQUIREMENTS SR 3.2.1.1 SURVEILLANCE Verify all APLHGRs are less than or equal to the limits specified in the COLR. APLHGR 3.2.1 FREQUENCY Once Within 12 hours after AND 24 hours thereafter BFN-UNIT 1 3.2-2 Amendment No. 234 3.2 *POWER DISTRIBUTION LIMITS \_) 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) MCPR 3.2.2 LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR. APPLICABILITY:
THERMAL RTP. ACTIONS CONDITION REQUIRED ACTION A. Any MCPR not within A.1 Restore MCPR{s) to limits. within limits. -8. Required Action and 8.1 Reduce THERMAL associated Completion POWER to< Time not met. 23 BFN-UNIT 1 3.2-3 COMPLETION TIME 2 hours 4 hours Amendment No. 234 SURVEILLANCE REQUIREMENTS SR 3.2.2.1 SR 3.2.2.2 SURVEILLANCE Verify all MCPRs are greater than or equal to the limits specified in the COLR. Determine the MCPR limits*. MCPR 3.2.2 FREQUENCY Once within 12 hours after 
*L@J AND 24 hours thereafter Once within . 72 hours after each completion of SR 3.1.4:1 Once within 72 hours after each completion of SR 3.1.4.2 BFN-UNIT 1 3.2-4 Amendment No. 234 3.2 POWER DISTRIBUTION LIMITS LHGR 3.2.3 U 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) u LCO 3.2.3 A11 LHGRs shall be less than or .equal to the limits specified in the COLR. APPLICABILITY:
THERMAL RTP. ACTIONS CONDITION REQUIRED ACTION A. Any LHGR not within A.1 Restore LHGR(s} to limits. within limits. 8. Required Act_ion and 8.1 Reduce THERMAL associated Completion POWER to< Time not met. 23 BFN-UN1T 1 3.2-5 COMPLETION TIME 2 hours 4 hours Amendment No. 234 u . SURVEILLANCE REQUIREMENTS SR 3.2.3.1 SURVEILLANCE Verify all LHGRs are less than or equal to the limits specified in the COLR. LHGR 3.2.3 FREQUENCY Once within 12 hours after L@J AND 24 hours thereafter BFN-UNIT 1 3.2-6 Amendment No. 234 ACTIONS (continued)
CONDITION 
: c. One or more Functions C.1 with RPS trip capability not maintained. 
: 0. Required Action and D.1 associated Completion Time of Condition A, B, or C not met. E. As required by Required E.1 Action D.1 and referenced in Table 3.3.1.1-1.
F. As required by Required F.1 Action D .1 and referenced in Table 3.3.1.1-1.
G. As required by Required G.1 Action D.1 and referenced in Table 3.3.1.1-1.
H. As required by Required H.1 Action D.1 and referenced in Table 3.3.1.1-1.
BFN-UNIT 1 REQUIRED ACTION Restore RPS trip capability.
Enter the Condition referenced in Table 3.3.1.1-1 for the channel. Reduce THERMAL POWER to< 26 Be in MODE 2. Be in MODE 3. Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
RPS Instrumentation 3.3.1.1 COMPLETION TIME 1 hour Immediately 4 hours 6 hours 12 hours Immediately 3.3-2 Amendment 262 SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1 
: 1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function. 
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains RPS trip capability.
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 BFN-UNIT 1 SURVEILLANCE Perform CHANNEL CHECK. --------------------------NC>l"E-------------------------
Not required to be performed until 12 hours after THERMAL P()WER Verify the absolute difference between the average power range monitor (APRM) channels and the calculated power is ::;; 2% RTP while operating at 2+.5%.B_TP. -
--------------------------N()l"E-------------------------
Not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL FUNCTIONAL TEST. FREQUENCY 24 hours 7 days 7 days (continued) 3.3-3 Amendment No.-2J4, 262 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.1.1.10 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17 BFN-UNIT 1 SURVEILLANCE FREQUENCY Perform CHANNEL CALIBRATION.
184 days (Deleted)
Perform CHANNEL FUNCTIONAL TEST. 24 months Neutron detectors are excluded.
Perform CHANNEL CALIBRATION.
24 months Perform LOGIC SYSTEM FUNCTiONAL 24 months TEST. Verify '"f urbine Stop Valve -Closure and 24 months '"furbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when '"fHERMAL POWER is --------------------------NOTE-------------------------
For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL FUNC'"flONAL 
'"fEST. 184 days Verify OPRM is not bypassed when APRM 1231 24 months Simulated Thermal Power and
* recirculation drive flow is < 60% of rated recirculation drive flow. 3.3-5 Amendment No. 234, 262, 263,266 FUNCTION 1. Intermediate Range Monitors a. Neutron Flux
* High b. lnop 2. Average Power Range Monitors a. Neutron Flux -High, Set down b. Flow Biased Simulated Thermal Power -H i gh c. Neutron Flux -High Table 3.3.1.1-1(page1of3)
Reactor Protection System Instrumentation APPLICf.\BLE MODES OR OTHER SPECIFIED CONDITIONS 2 5(a) 2 5(a) 2 REQUIRED CHANNELS PER TRIP SYSTEM 3 3 3 3 CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 G H G H G F F (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (b) Each APRM channel provides inputs to both tr i p systems. RPS Instrumentation 3.3.1.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE SR 3.3.1.1.1 SR 3.3.1.1.3 SR 3.3.1.1.5 SR 3.3.1.1 .6 SR 3.3.1.1.9 SR 3.3.1.1.14 SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1.1.14 SR 3.3.1.1.3 SR 3.3.1.1.14 SR 3.3.1.1.4 SR 3.3.1.1.14 SR 3.3.1.1.1 SR 3.3. 1. 1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1: 1.1 SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 :::; 120/125 divisions of full scale s120112s divisions of full scale NA NA Q}J RTP I o.55 I + .g&% RT P L.:::.:::..p and s 120% RTP(c) :::; 120% RTP continued -RTP when reset for single loop operation per LCO 3.4.1 , " Recirculat i on Loops Operating." . BFN-UNIT 1 3.3-6 Amendment No. 236, 262, 269 FUNCTION 7. Scram Discharge Volume Water Level -High (continued) 
: b. Float Switch 8. Turbine Stop Valve -Closure 9. Turbine Control Valve Fast Closure, Trip Oil Pressure -
: 10. Reactor Mode Switch -Shutdown Position 11. Manual Scram 12. RPS Channel Test Switches Table 3.3.1.1".'1 (page 3 of 3) Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 1,2 5(a) 1,2 5(a) 1,2 5(a) 1,2 5(a) REQUIRED CHANNELS PER TRIP SYSTEM 2 2* 4 2 . 1 2 2 CONDITIONS REFERENCED FROM REQUIRED ACTION0.1 G H E E G H G H G H (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
RPS Instrumentation 3.3.1.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE SR 3.3.1.1.8 SR 3.3;1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.4 SR 3.3.1.1.4 s 46 gallons s 46 gallons s 10% closed 2: 550 psig NA NA NA NA NA NA (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the chaMel 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 shan be specified in Chapter 7 of the Updated Final Safety Analysis Report. BFN-UNIT 1 3.3-8 Amendment No. 234 , 267, 259 Feeawater ana Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 
\__) 3.3.2.2. Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Two channels of feedwatet and main turbine high water level trip instrumentation per trip system shall be OPERABLE .. APPLICABILITY:
THERMAL POWER L@J ACTIONS ----------------------------NOTE---------------------------
Separate Condition entry is a11owed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Pla.ce channel(s) in trip. 7 days and main turbine high water level trip channels inoperable, in one trip . system. B. One or more feedwater 8.1 Restore f eedwater and 2 hours and main turbine high main turbine high water water level trip channels level trip capability. 
*inoperable in each trip system. C. Required Action and C.1 Reduce THERMAL .4 hours associated Completion Time not met. 23 BFN-UNIT 1 3.3-21 Amendment No. 234 EOC-RPT Instrumentation 3.3.4.1 -3".3 INSTRUMENTATION. 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation LCD 3.3.4.1 APPLICABILITY; BFN-UNIT 1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:
OR 1. Turbine Stop Valve (TSV) -Closure; and 2. Turbine Control Valve (TCV) Fast Closure, Trip Oi1 Pressure *Low. b. LCO 3.2.2, "MINIMUM CRITlCAL POWER RATIO (MCPR)," limits for inoperable EOC-RPT as specified in the COLR are made applicable; and c. LCD 3.2.3. "UNEAR HEAT GENERATlON RATE (LHGR)," limits for an inoperable EOC-RPT, as specified in the COLR, are made applicable.
THERMAL POWER t! 3R% RTP. L-@J 3.3-29 Amendment No. J . 281 ACTIONS EOC-RPT Instrumentation 3.3.4.1 Separate Condition entry is allowed for each channel. COND1TION A. One or more channels inoperable.
B. One or more Functions with EOC-RPT trip capability not maintained.
AND M CPR and LHGR limits
* for in0perable EOC-RPT not made appflcable.
C. Required Action and associated Completlon Time not met. BFN*UNIT 1 -------------------
REQUIRED ACTION A.1 Restore channel to OPERABLE status. OR A.2 ---NOTE---
Not applicable if inoperable channel is the result of an inoperable breaker. Place channel in trip. B.1 Restore EOC-RPT trip capability.
OR B.2 Apply MCPR and LHGR limits for ;noperable EOC-RPT as specified in the COLR. C.1 Reduce THERMAL POWER 26 3.3-30 COMPLETION TIME 72 hours 72 hours 2 hours 2 hours 4 hours Amendment No. -234 281 EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS
______ _ When a channel is placed in an inoperable status for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains EOC-RPT trip capability: . . ------------------------------------------------------------------------------------------------------------------
SR 3.3.4.1.1 SR 3.3.4.1.2 SR 3.3.4.1.3 SR 3.3.4.1.4 BFN-UNIT 1 SURVEILLANCE FREQUENCY Perform CHANNEL FUNCTIONAL TEST. 92 days Verify TSV -Closure and TCV Fast Closure, 24 months Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER is Lf26l Perform CHANNEL CALIBRATION.
The 24 months Allowable Values shall be: TSV -Closure: 10% closed; and TCV Fast Closure, Trip Oil Pressure -Low: 550 psig. Perform LOGIC SYSTEM FUNCTIONAL TEST including breaker actuation.
24 months 3.3-31 Amendment No.  
.. Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SR 3.4.2.1 BFN-UNIT 1 SURVEILLANCE 
: 1. Not required to be performed until 4 hours after associated recirculation loop is in operation. 
: 2. Not required to be performed until 24 hours after > {i TP. a. Recirculation pump flow to speed ratio differs by s 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by s 5% from established patterns.
* b. Each jet pump diffuser to lower plenum differential pressure differs by s 20% from established pattem_s. c. Each jet pump flow differs by s 10% from established patterns.
FREQUENCY 3.4-6 Amendment No. 234 CAO System 3.6.3.1 .SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 2615 I 
-2500 gal of liquid nitrogen are 31 days contained in each nitrogen storage tank. SR 3.6.3.1.2 Verify each CAD subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position
* or can be aligned to the correct position.
BFN-UNIT 1 3.6-41 Amendment No. 234 Main Turbine Bypass System 3.7.5 3.7 PLANT SYSTEMS 3.7 .5 Main Turbine Bypass System LCO 3.7.5 APPLICABILITY:
ACTIONS The Main Turbine Bypass System shall be OPERABLE.
The following Hmits are made applicable: 
: a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and b. LCO 3.2.2, *MINIMUM CRITICAL POWER RATfO (MCPR): limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and c. LCO 3.2.3. *uNEAR HEAT GENERATION RATE (LHGR)." limits for an inoperable Main Turt>;ne Bypass System, as specified in the COLR. THERMAL CONDITION REQUIRED ACTION COMPLETION A. Requirements of the LCO A.1 not met. B. Required Action and B.1 associated Compfetion Time not met. BFN-UNIT 1 Satisfy the requirements of the LCO. Reduce THERMAL POWER 23 3.7-16 TIME 2 hours 4 hours Amendment No. 234 281 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Program (SFDP) (continued) . A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed.
For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and: a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.
The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
* 5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 4-!f5 psig. The maximum allowable primary 49* 1 containment leakage rate, La, shall be 2% of primary containment air weight per day at Pa-(continued)
BFN-UNIT 1 5.0-20 Amendment No. sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of thermal. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 313, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. For Surveillance Requirements (SRs) that are new in Amendment 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 253. 3) The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to _the appropriate documents, as described in the licensee's Amendment No. 313 BFN-UNIT 2 Renewed License No_ DPR-52   application dated September 6, 1996, as supplemented May 1, August 14, November 5 and 14, December 3, 4, 11, 22, 23, 29, and 30, 1997; January 23, March 12, April 16, 20 and 28, May 7, 14, 19, and 27 1 and June 2, 5, 10 and 19, 1998; evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.
This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment. 
(4) Deleted. (5) Classroom and simulator training on all power uprate related changes that affect operator performance will be conducted prior to operating at uprated conditions.
Simulator changes that are consistent with power uprate conditions will be made and simulator fidelity will be validated in accordance with ANSI/ANS 3.5-1985.
Training and the plant simulator will be modified, as necessary, to incorporate changes identified during startup testing. This amendment is effective i mmediately. 
(6) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements:
1 . Pre-defined coordinate.d fire response strategy and guidance 2. Assessment of mutual aid fire fighting assets 3. Designated staging areas for equipment and materials 
: 4. Command and control 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 
: 1. Protection and use of personnel assets 2. Communications 
: 3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 
: 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 
: 2. Dose to onsite responders (7) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.
BFN-UNIT 2 Renewed License No. DPR-52 Revised by letter dated Augtlst 16 , 2007 INSERT B 2.G.(4) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.C.(1) of Renewed Facility Operating License No. DPR-52, for Browns Ferry Nuclear Plant Unit 2, to reflect the new maximum licensed reactor core power level of 3952 megawatts thermal (MWt), the license is also amended to add the following license condition.
This license condition provides for monitoring and evaluating potential adverse flow effects as a result of extended power uprate (EPU) operation on plant structures, systems, and components (including verifying the continued structural integrity of the replacement steam dryer). a) The following requirements are placed on the initial operation of the facility, above the thermal power level of 3458 MWt, for the power ascension to 3952 MWt. These conditions are applicable until the first time full EPU conditions (3952 MWt) are achieved. 
: 1. During power ascension greater than 3458 MWt, at test increments that do not exceed 5% of 3458 MWt, the main steam line strain gauges shall be monitored against established acceptance limits to assure steam dryer structural integrity is maintained.
If flow-induced resonances are identified and the strains or vibrations increase above the predetermined criteria, power ascension shall be stopped until analysis demonstrating acceptable results is performed. 
: 2. During power ascension greater than 3458 MWt, hold points, in increments that do not exceed 5% of 3458 MWt, shall be established for NRC review of power ascension data. Power shall not be increased above each hold point until 96 hours after the NRG confirms receipt of the evaluations unless, prior to the expiration of the 96 hour period, the NRG communicates that the NRC staff has no objections to the continuation of power ascension.
b) After full EPU power has been achieved, replacement steam dryer data at the full power level shall be provided to the NRG within 96 hours. c) Following power ascension to full EPU conditions, a vibration summary report for piping and valve vibration data collected at full EPU power level shall be provided to the NRG. Vibration data shall be collected for piping and valve locations deemed prone to vibration identified in Attachment 45 to the EPU License Amendment Request, including the identified locations associated with the main steam (MS) system, the feedwater system, the condensate system, the extraction steam system, the heater drain system, safety relief valves, main steam isolation valves, the inboard isolation valve for MS drain piping, the inboard isolation valve for the reactor core isolation cooling turbine steam supply line, and the inboard isolation valve for the high pressure coolant injection turbine steam supply line. The report shall also include an evaluation of the measured vibration data collected during power ascension compared against established acceptance limits. The report shall be submitted to the NRG staff in accordance with 10 GFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. d) Following power ascension to full EPU conditions, a confirmatory analysis shall be performed for the replacement steam dryer. This analysis shall include a final load definition and stress re-analysis of the replacement steam dryer using the biases and uncertainties determined at EPU conditions and a comparison of predicted and measured pressures and strains on the replacement steam dryer. The report shall be submitted to the NRC staff in accordance with 10 CFR 50.4. The report shall be submitted within 90 days of reaching the full EPU power level. e) During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be performed of all accessible, susceptible locations of the replacement steam dryer in accordance with BWRVIP-139A and General Electric inspection guidelines.
The results of the visual inspections of the steam dryer shall be submitted to the NRG staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.
1.1 Definitions (continued)
PHYSICS TESTS RATED THERMAL POWER *(RTP) SHUTDOWN MARGIN (SOM) .
* BFN-UNIT 2 Definitions 1.1 PHYSICS fESTS shaJJ be those tests performed to measure the fundamental nuclear characteristics of . the reactor core and related instrumentation.
These tests are: a. Oescribed in Section 13.10, Refueling Test Program; *of the FSAR; b. Authorized under the provisions of 10 CFR 50.59; or c. Otherwise approved by the Nuclear Regulatory Commission.
RTP shall be a total reactor core heat transfer rate to the reactor coolant MWt. SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that: a. The reactor is xenon free; b. The moderator temperature is 68&deg;F; and c. All control rods are fully except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM . 1.1-6 (continued)
Amendment No. 254 SEP 0 8 1998 SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2. 1 . 1 Reactor Core S Ls 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow: THERMAL POWER shall 2.1.1.2 With the reactor steam dome pressure 85 psig and core flow 10% rated core flow: MCPR shall 1.06 for two recirculation loop operation 1.08 for single loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 1325 psig. 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. BFN-UNIT 2 2.0-1 Amendment No. 311  

\_) SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.7.5 SR 3.1.7.6 SR 3.1.7.7 BFN-UNIT 2 SURVEILLANCE Verify the concentration and temperature of boron in solution are within the limits of Figure 3.1.7-1. FREQUENCY Once within 8 hours after discovery that SPB concentration is > 9.2% by weight 12 hours thereafter
* Verify the minimum quantity of Boron-10 in the 31 days SLC solution tank and available for injection is ;;:: 4ie pQYILds.
Verify the SLC conditions satisfy the following 31 days equation: ( C )( Q )( E ) (43-wt. %)(-Bf gpm)(19 f 8 a 1 tomo/1 1 LI sol 94 where, C = sodium pentaborate solution concentration (weight percent) Q = pump flow rate (gpm) E = Boron-10 enrichment 
{atom percent Boron-10)
Verify each pump develops a flow 39 gpm at a discharge pressure ;;:: 1325 psig. Once within 24 hours after water or boron is added to the solution 24 months (continued) 3.1-25 Amendment No. 290 I I 3.2 POWER DISTRIBUTION LIMITS .APLHGR 3.2.1 .\__) 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL POWER;:: 2f% RTP. L@J ACTIONS CONDITION* REQUIRED ACTION COMPLETION . TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours limits. within limits. 8. Required Action and 8.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met. 23 BFN-UNIT2 3.2-1 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.2.1.1. SURVEILLANCE Verify all APLHGRs are less than or e*qual to the limits specified in the COLR. APLHGR 3.2.1 FREQUENCY Once within 12 hqurs after RTP AND 24 hours thereafter BFN-UNIT2 3.2-2 Amendment No. 253 3.2 POWER DISTRIBUTION LIMITS \_) 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) MCPR 3.2.2 LCO 3.2.2 All MCPRs shall be g.c_eater than or equal to the MCPR operating limits specified in the COLR. APPLICABILITY:
THERMAL 2f% RTP. ACTIONS CONDITION . REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours limits. within Umits. B. Required Action and 8.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met. 23 . BFN-UNIT 2 3.2-3 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.2.2.1 SR 3.2.2.2 SURVEILLANCE Verify all MCPRs are greater than or equal to the limits specified in the COLR. Determine the MCPR limits. MCPR 3.2.2 FREQUENCY Once within 12 hours after ;:: 2f% RTP .. AND 24 hours thereafter Once within 72 hours after each completion of SR 3.1.4.1 Once within 72 hours after each *completion
* of SR 3.1.4.2 . BFN-UNIT2 3.2-4 Amendment No. 253 3.2 POWER DISTRIBUTION LIMITS \. _ _) 3.2.3 LINEAR HEAT GENERATION RATE LHGR 3.2.3 LCO 3.2.3 All LHGRs shall be Jess than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL POWER RTP. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to 2 hours limits. within limits. 8. Required Action and 8.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met..
* 23 BFN-UNIT2 3.2-5 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.2.3.1 SURVEILLANCE Verify all LHGRs are less than or equal to the limits specified in the COLR. LHGR 3.2.3 FREQUENCY Once within 12 hours after 
.. AND 24 hours thereafter 8FN-UNIT2 Amendment No. 253 ACTIONS (continued)
CONDITION 
: 8. NOTE 8.1 Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR 8.2 One or more Functions with one or more required channels inoperable in both trip systems. C. One or more Functions C.1 with RPS trip capability not maintained.
D. Required Action and D.1 associated Completion Time of Condition A, B, or C not met. E. As required by Required E.1 Action 0.1 and referenced in Table 3.3.1.1-1.
F. As required by Required F.1 Action 0.1 and referenced in Table 3.3.1.1-1.
REQUIRED ACTION Place channel in one trip system in trip. Place one trip system in trip. . .. Restore RPS trip *capability.
Enter the Condition referenced in Table 3.3.1.1-1 for the channel. Reduce THERMAL POWER to< . 26 Be in MODE2. RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours 6 hours 1 hour Immediately 4 hours 6 hours {continued)
BFN-UNIT 2
* 3.3-2 Amendment No. 258 -s,\'l(tlQ; kl.t, at 
&#xa3;41.al c& MAR 11 1399 n 1c O f) -k , 'o:9 .. ) Rv, \&#xa3;JDP1 P II. lqqq_
SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1 *'-._) NOTES---------* 
: 1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function. 
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains RPS trip capability.
SURVEILLANCE 
*FREQUENCY.
SR 3.3.1.1.1 Perform CHANNEL CHECK 24 hours SR 3.3.1.1.2 NOTE Not required to be performed until 12 hours after THERMAL POWER :<: ti% 
*. 23 Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power is 2% RTP while operating at;?;
23 SR 3.3.1.1.3 NOTE Not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL FUNCTIONAL TEST. 7 days {continued) 8FN-UNIT2 3.3-4 Amendment No. 253  
\..._,)
* RPS Instrumentation 3.3.1.1 : SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION.
184 days SR 3.3.1.1.11 (Deleted)
SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.13 NOTE Neutron excluded.
Perform CHANNEL CALIBRATION. 
.24 months SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST. SR 3.3.1.1.15 Verify Turbine Stop Valve -Closure and 24 months Turbine Control Valve Fast Closure, Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER 26 SR 3.3.1.1.16 NOTE For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE2. Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.1.17 Verify OPRM is not bypassed when APRM 1231 24 months Simulated Thermal Power is Z!S% and recirculation drive flow is < 60% of rated recirculation drive flow. BFN-UNIT 2 3.3-6 Amendment No. 258 *;:. c  
\__) \_) RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3) Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION 0.1 1. Intermediate Range MonJtcra a. Neutrortflux
* High 2 3 . G. SR 3.3:1.1.1 s 120/125 SR 3.3.1.1.3 dMsions of fuU SR 3.3.1.1.5 scale SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.14 5(a) 3 H SR 3.3.1.1.1 s 120/125 SR 3.3.1.1.-i dMsJons of fuU SR 3.3.1.1.9 scale SR 3.3.1.1.14 
: b. tnop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.1-i 5{*) 3 H SR 3.3.1.U NA SR 3.3.1.1.14 
: 2. Average Power Range Monlcn ** Neutron Flux
* High, 2 3(b) G SR 3.3.1.1.1 s 'l>>RTP (Setdown)
SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 *SR 3.3.1.1.16 b. Flow Biased Slmulated 1 3(b) F SR 3.3.1.1.1 ThennaJ Pc:Nter -High SR 3.3.1.1.2 
! 61.., I 65.5 I SR 3.3.1.1.7 andS120% I SR 3.3.1.1.13 RTP(e) SR 3.3.1.1.16 
: c. Neutron Fk.cc
* High 1 . 3(b) F SR 3.3.1.1.1 S120%RTP SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 (continued) 
* (a) Wlth arrf control red wtthdrawn frcm a core eel ccntainlng one or more fuel assemblies. (b} Each AP RM channel provides Inputs to both trip systems. (c) ii6. i , .6 7 RTP .men reset for slngle loop operation""'
LCO 3.4.1, "Recirculation loops Operating.*
0.55 65.5 0.55 . . BFN-UNIT2 3.3-7 Pbte: lfli s is eabl e efter eem*ei-d ng C}el e 11 ooe1 ati m. Amendment No. 256 DEC 2 3 1998 FUNCTION 7. Scram Discharge Volume Water level -High (continued) 
: b. Float Switch 8. Turbine Stop Valve -Closure 9. Turbine Control Valve Fast Closure, Trip Oil Pressure -Low(d) 10. Reactor Mode Switch -Shutdo.wn Position 11. Manual Scram 12. RPS Channel Test Switches 13. Deleted Table 3.3.1.1-1(page3of 3} Reactor Protection System Instrumentation APPLICABLE . MODES OR OTHER . SPECIFIED CONDITIONS 1,2 5(a) 1,2 5{a) 1,2 5(a) 1,2 5(a) REQUIRED CHANNELS PER TRIP SYSTEM 2 2 4 2 2 2 CONDITIONS REFERENCED FROM REQUIRED . ACTION D.1 G H E E G H G H G H (a) With any control rod withdrawn from a core ceU containing one or more fuel assemblies.
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS SR 3.3.1.1.B SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 . SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.14 SR 3.3.1.1.4 SR 3.3.1.1.4 ALLOWABLE VALUE 46 gallons s 46 gallons s 10% closed 550 psig NA NA NA NA NA NA (d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an Initial determination to ensure confidence that the channel can perfor_m as required before retumiug 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 ls 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. BFN-UNIT 2 3.3-9 Amendment No. 258, 276, 296  
\__) Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Two channels off eedwater and main turbine high water I ever trip per trip system shall be OPERABLE.
APPLICABILITY:
_ THERMAL RTP. ACTIONS ---------------------------NOTE--------------------------
Separate Condition entr)' is allowed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Place channel(s) in trip. 7 days and main turbine high water level trip channels inoperable, in one trip system. B. One or more feedwater 8.1 Restore f eedwater and 2 hours and main turbine high main turbine high water water level trip channels
* inoperable 
*in each trip level trip capability.
system .. C. Required Action and C.1 Reduce THERMAL 4 hours associated Completion POWER to< Time not met. 23 . BFN-UNIT 2 3.3-22 Amendment No. 253 EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation LCO 3.3.4.1 APPLICABILITY:
BFN-UNIT 2 a. Two channels per trip system for each EOC-RPT
* instrumentation Function listed below shall be OPERABLE:
OR 1. Turbine Stop Valve (TSV) -Closure; and 2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure -Low. b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO {MCPR}," limits for inoperable EOC-RPT as specified in the COLR are made applicable; and c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR}," limits for inoperable EOC-RPT as specified in the COLR are made applicable.
THERMAL RTP. 3.3-30 Amendment No.}}