ML15282A169

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Proposed Technical Specification Markups, Part 2 of 2
ML15282A169
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 09/21/2015
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML15282A154 List: ... further results
References
CNL-15-169
Download: ML15282A169 (45)
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Text

ACTIONS EOC-RPT Instrumentation 3.3.4.1 -----------------_..:_-------------NOTE------------------------------

Separate Condition entry is allowed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperabre.

OPERABLE status. OR A.2 ----------NOTE-------

Not applicable if inoperable channel is the result of an inoperable breaker. --------------------------------

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR *. AND 8.2 Apply the MCPR and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> MCPR and LHGR limit for LHGR limit for inoperable inoperable EOC-RPT not EOC-RPT as specified in made applicable.

the COLR. C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 26 BFN-UNJT 2 3.3".'31 Amendment No.

EOC-RPT Instrumentation 3.3.4.1 \_) SURVEILLANCE REQUIREMENTS

\_)

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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function malntains EOC-RPT trip SURVEILLANCE SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. SR 3.3.4.1.2 Verify TSV -Closure and TCV Fast Closure, Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER is 26 SR 3.3.4.1.3 Perform CHANNEL CALIBRATION.

The Allowable Values shall be: TSV -Closure: 10% closed; and TCV Fast Closure, Trip Oil Pressure -Low: 550 psig. SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST including breaker actuation.

BFN-UNIT2 3.3-32 FREQUENCY 92 days 24 months 24 months 24 months Amendment No. 255 J10V S 0 1898

\..J. SURVEILLANCE REQUIREMENTS SR 3.4.2.1 SURVEILLANCE

1. Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after associated recirculation loop is in operation.
2. Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after>
a. Recirculation pump flow to speed ratio differs by 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 diff erentia1 pressure differs by s 20% from *established patterns.
c. Each jet pump flow differs by s 10% from established patterns.

Jet Pumps 3.4.2 FREQUENCY BFN-UNIT 2 3.4-6 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.6.3.1.1 SR 3.6.3.1.2 BFN-UNIT 2 SURVEILLANCE

__ +__ 126151 Verify .zse&gal of liquid nitrogen are contained in each nitrogen storage tank. Verify each CAD subsystem manual, power 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.

3.6-41 CAD System 3.6.3.1 FREQUENCY 31 days 31 days Amendment No. 253 RHRSW System ana UI IS 3.7.1 3.7 PLANT SYSTEMS 3. 7.1 Residual Heat Removal Service Water {RHRSW) System and Ulti_mate Heat Sink (UHS) LCO 3.7.1 -------------------NOTE-------------------

The number of required RHRSW pumps may be reduced by one for each fueled emit that has been in MODE 4 or 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. . . Four RHRSW subsystems aAd UHS shall be OPERABLE with the number of OPERABLE pumps as listed below: 1. 1 unit fueled -four OPERABLE RHRSW pumps. 2. 2 units fueled -six OPERABLE RHRSW pumps. 3. 3 units fueled -eight OPERABLE RHRSW pumps. APPLICABILITY:

MODES 1, 2, and 3 . .

  • BFN-UNIT 2 3.7-1 Amendment No. 254 SEP O 8 1998

". ACTIONS CONDITION A. One required RHRSW pump inoperable.

BFN-UNIT2 REQUIRED ACTION .RHRSW System eRa UHS 3.7.1 COMPLETION TIME A.1 NOTES--OR* **1. <;>nly applicable for the 2 units fueled condition.

2. Only four RHRSW pumps powered from a separate 4 kV shutdown board are required to be OPERABLE if the other fueled unit has been in MODE 4 or 5 for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -. Verify five RHRSW Immediately pumps powered from separate 4 kV shutdown boards .are OPERABLE.

A.2 Restore required RHRSW 30 days pump to OPERABLE status. 3.7-2 (continued)

No. 254 0 8 1598 ACTIONS (continued)

CONDITION

D. Two RHRSW subsystems

0.1 inoperable

.. : BFN-UNIT 2 RHRSW System anef UI IS 3.7.1 REQUIRED ACTION COMPLETION TIME NOTE applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling -Hot Shutdown," for RHR shutdown cooling made Jnoperable by the RHRSW system. Restore RHRSW 30 days subsystem to OPERABLE status. . . Restore one inoperable 7 days RHRSW pump to OPERABLE status. NOTE applicable Conditions and Required Actions of LCO 3.4.7, for RHR shutdown cooling made inoperable by the RHRSW System. Restore one RHRSW 7days subsystem to OPERABLE status. (continued) 3.7-3 Amendment No. 254 SEP 0 8 1998 ACTIONS (continued)

CONDITION E. Three or more required E.1 RHRSWpumps inoperable. . F. Three or more RHRSW F.1 subsystems inoperable.

G. Required Action and G.1 associated Completion Time not met. AND G.2 9R YHS iAepeFaele BFN-UNIT2 RHRSW System ana Ut IS 3.7.1 REQUIRED ACTION COMPLETION TIME Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to OPERABLE status . NOTE Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by the RHRSW System. Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> subsystem to OPERABLE status. Be in MODE 3. Be in MODE4. 3.7-4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Amendment No. 254 SEP O 8 1998

"--/ RHRSW System and UH S 3.7.1 SURVEILLANCE REQUIREMENTS SR 3.7.1.1 SR 3.7.1.2 .* BFN-UNIT2 SURVEILLANCE FREQUENCY Verify each RHRSW manual and power 31 days operated 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 eorrect p_osition.

Ver i fy the water temperature of UH S 24 I 1001 s UH S is within the limits specified in Figure S.7.1-1. te111peratme 3.7-5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> UHS ten 1pe1 atu1 e >9 1°F Amendment No. 254

  • SEP 0 8 1998 8FN-UNIT2 Figure 3.7.1-1 eactor Thennal Power Versus Sink Temperature LI 3.7-6 RHRSW System and UHS 3.7.1 95 Amendment No. 254 SEP 0 8 1398 EECW System and U HS 3.7.2 SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SR 3.7.2.3 BFN-UNIT 2 SURVEILLANCE NOTE Refer to SR a.7.1.2 for additional UHS requirements. FREQUENCY Verify the average water temperature of UHS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 95°F.

Isolation of flow to individual components does not render EECW System inoperable.

Verify each EECW system manual and power 31 days operated valve in the flow paths servicing safety related systems or components, that is not locked, sealed, o r otherwise secured in position, is in the correct position.

Verify each required EECW pump actuates on an actual or simulated initiation signal. 3.7-8 24 months Amendment No. 255 . l}OV 3 0 1998 -;$ha1L atplb

\ __ / 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 limits are made applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RA TE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR. THERMAL 2,§% f(TP. CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO. B. Requi_red Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to .:; Time not met. 23 BFN-UNIT2 3.7-17 ' Amendment No. 2§4, 287 Programs and Manuals 5.5 5.5. Programs and Manuals 5.5.12 Primarv Containment Leakage Rate Testing Program (continued)

The peak calculated containment internal pressure fo"r the design basis loss of coolant accident, P a1 is §Gt§ psig. The ma.xi mum allowable primary 49* 1 containment leakage rate, La, shall be 2% of primary containment air weight per day at Pa* Leakage Rate acceptance criteria are: a. The primary containment leakage rate acceptance criteria is s 1.0 La. During the first unit startup following the testing performed in accordance with this program, the leakage rate acceptance criteria are 0.60 La for the Type 8 and Type C tests ,

0.75 La for the Type A test; and b. Air lock testing acceptance criteria are: 1) Overall air lock leakage rates; 0.05 La when tested Pa. 2) Air lock door seals leakage rate is s; 0.02 La when the overall air lock is pressurized to 2. 5 psig for at least 15 minutes. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. 5.5.13 Control Room Envelope Habitability Program BFN-UNIT 2 A Control Room Envetope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke cha I lenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent

{TEDE) for the duration of the accident.

The program shall include the following elements: (continued) 5.0-21 Amendment No.

302 (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 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) BFN-UNIT 3 Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess megawatts thermal. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 272, 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 212 to Facility Operating License DPR-68, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment 212, 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 212. Amendment No. 272 Renewed License No. DPR-68 BFN-UNIT 3 (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 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, and June 2, 5, 1_0 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.

C (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 immediately.

(6)(a) The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The combined set of plans, which contains Safeguards Information protected under 1 O CFR 73.21, is entitled:

11 Browns Ferry Nuclear Plant Physical Security Plan, Training and Qualification Plan, and Contingency Plan," Revision 4, submitted by letter dated April 28, 2006. (b) The licensee shall fully implement and .maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The licensee CSP was approved by License Amendment No. 265, as amended by changes approved by License Amendment No. 271. (7) Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the safety evaluations dated December 8, 1988; March 31, 1993; April 1, 1993; November 2, 1995; April 25, 2007, and Supplement dated November 3, 1989; subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Renewed License No. DPR-68 Amendment No. 271 INSERT G 2.G.(4) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.G.(1) of Renewed Facility Operating License No. DPR-68, for Browns Ferry Nuclear Plant Unit 3, 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 available on-dryer structural response sensors and 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 NRG review of power ascension data. Power shall not be increased above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRG confirms receipt of the evaluations unless, prior to the expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRG communicates that the NRG 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 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. 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 NRG staff in accordance with 10 GFR 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 GFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.

1.1 -Oefinitions (continued)

\ ... _./ PHYSICS TESTS RATED THERMAL POWER (RTP) SHUTDOWN MARGIN (SOM) BFN-UNIT3 Definitions

1.1 PHYSICS

TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reaetor core and related instrumentation.

These tests are: a. Described in Section 13.10, Refueling Test Program; of the FSAR; b. Authorized under the provisions of 10 CFR 50.59; or c. Othel"Nise approved by the Nuclear Regulatory Commission.

-RTP shall be a totaf reactor core heat transfer rate to the reactor coolant MWt. SOM shall be the amount of reactivity by which the reactor is subcriticaf or would be subcritical assuming that: a. The reactor is xenon free; b. The moderator temperature is 68°F; and c. AH control rods are fully inserted 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. 214 s::: .. :

\ __ / *\._/. 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 s RTP. . L--@] SLs 2.0 With the reactor steam dome pressure 785 psig and core flow i17)Ql 10% rated core flow: 1 _06 2.1.1.2 MCPR shall be 1 for loop operation +.<<-I 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 viofation, the following actions shaH be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 2.2.1 Restore compliance wjth all Sls; and 2.2.2 Insert all rnsertabf e control rods. BFN-UNIT3 2.0-1 Amendment No. 216, 234, 246 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 3 SURVEILLANCE Verify the concentration and temperature of boron in solution are within the limits of Figure 3.1.7-1. FREQUENCY Once withjn a hours after discovery that SPB concentration is > 9.2% by weight AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Verify the minimum quantity of Boron-10 in the 31 days SLC solution tank and available for injection is Verify the SLC conditions satisfy the following 31 days equation: ( C )( Q )( E ) (-a-wt. 1 50. Ll94I 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 39 gpm at a discharge pressure 1325 psig. Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to the solution 24 months (continued) 3.1 .. 25 Amendment No. 2-1-6 1 249 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 2,p% RTP. ACTIONS CONDITION REQUIRED ACTION A Any APLHGR not within A.1 Restore APLHGR(s) to limits. within limits. B. Required Action and B.1 Reduce THERMAL associated Completion POWER to< Time not met. 23 BFN-UNIT3 3.2-1 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours Amendment No. 212 SURVEILLANCE REQUIREMENTS SR 3.2.1.1 SURVEILLANCE Verify all APLHGRs are less than or equal to the limits specified in the COLR. APLHGR 1 3.2.1 FREQUENCY . Once within

  • 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter BFN-UNIT 3 3.2-2 Amendment No. 212

3.2 POWER

DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) MCPR > 3.2.2 LCO 3.2.2 All MCPRs shaJI be greater than or equal to the MCPR operating limits s*pecified in the COLR. APPLICABILITY:

THERMAL RTP. L--@] ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limits. within limits. B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 23 BFN-UNIT 3 3.2-3 Amendment No. 212 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after L-9 AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.1 Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.2 BFN-UNIT3 3.2-4 Amendment No. 212

3.2 POWER

DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) LHGR ' 3.2.3 LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:

THERMAL RTP. L--8 ACTIO N S CONDITION REQUIRED ACTION COMPLETION. . .. TIME A Any LHGR not within A1 Restore LHGR(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limits. within limits. B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met.

  • 23 BFN-UNIT3 3.2-5 Amendment No. 212 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after L@) AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter
  • eFN-UNIT3 3.2-6 Amendment No. 212 ACTIONS (continued)

CONDITION

8. ---------NOTE------------

Not applicable for Functions 2.a, 2.bl 2.c, 2.d, or 2.f.

One or more Functions with one or more required channels inoperable in both trip systems. C. One or more Functions with RPS trip capability not maintained.

D. Required Action and associated Completion Time of Condition A, 8, or C not met. E. As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

F. As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

REQUIRED ACTION 8.1 Place channel in one trip system in trip. OR 8.2 Place one trip system in trip. C.1 Restore RPS trip capability.

0.1 Enter

the Condition referenced in Table 3.3.1.1-1 for the channel. E.1 Reduce THERMAL POWER_ to<

26 F.1 Be in MODE2. RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 6 hours (continued)

BFN-UNIT 3 3.3-2 Amendment No. 212, 213, 221 SEP 2 7 t S S9 st,o)cl .\QL.

a+/-

  • Ob °t RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS
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 ai-sociated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 3 SURVEILLANCE Perform CHANNEL CHECK.

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> THERMAL POWER RTP. 23 FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Verify the absolute between the 7 days average power range monitor (APRM) channels and the calculated power is 2% RTP while operating Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2. Perform CHANNEL FUNCTIONAL TEST. 3.3-4 7 days (continued)

Amendment No. 213 SEP 0 3 1998 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 Neutron detectors are 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 For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 ii% and recirculation drive flow is < 60% of rated recirculation drive flow. BFN-UNIT 3 3.3-6 Amendment No. 212, 213, 215, 221 SEP 7

\ . '-...__../

1. 2. (*) (b) FUNCTION ** Intermediate Range Mcnftors .. Neutrcn FkJx
  • High b. tncp Average Power" Range Manltara .. Neutron Flux
  • High. (Setdown}

ti. Fla.v Blased SlmUlated Thermal Power

  • High c. Neutron Flux -High Table 3.3.1.1-1 (page 1 of 3) Reactor Protection System Instrumentation . APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 2 5(*) 2 5(a) 2 1 1 REQUIRED CHANNELS PERTRJP SYSTEM 3 3 3 3 3(b) 3{b) 3(b) CONDITIONS REFERENCED FROM REQUIRED ACTIOND.1 G H G H G f F With Cr/ control rod wfthdrawn frort\ a core cell containing one or mare fuel assemblies.

Each APRM channel provides Inputs to both trfp systems. RPS Instrumentation 3.3.1.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE SR 3.3.1.1.1 s 120l125 SR 3.3.1.1.3 divisions of full 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 SR 3.3.1.1.1

' s 120/125 SR 3.3.1.1.4 dMsJons of full SR 3.3.1.1.S scale SR 3.3.1.1.14 SR 3.3.1.1.3 NA SR 3.3.1.1.14 SR 3.3.1.1.4 NA SR 3.3.1.1.14 SR 3.3.1.1.1 RTP SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13

! SR 3.3.1.1.7 ands SR 3.3.1.1.13 RTP(c) SR 3.3.1.1.16 SR 3.3.1.1.1 s 12QAMi 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) (c) l"f W

  • 4 RTP when reset far slngle locp opemlcn per LCO 3.4.1, "Recirc:ufatian Loops Operating." 0.55 BFN-UNIT3 3.3-7 Amendment No. 216 DEC 2 3 1998 FUNCTION 7. Scram Discharge Volume Water Level -High b. Float Switch 8. Turbine Stop Valve -Closure 9. Turbine Control Valve Fast Closure, Trip Oil Pressure -Low(d) 1 o. Reactor Mode Switch -Shutdown Position 11. Manual Scram 12. RPS Channel Test Switches 13. Deleted RPS Instrumentation 3.3.1.1 Table3.3.1.1-1 (page3of3)

Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER . SPECIFIED CONDITIONS 1,2 5(a) 1,2 5(a) 1,2 5(2) 1,2 5(a) REQUIRED CHANNELS PER TRIP SYSTEM 2 2 4 2 2 2 CONDITlONS REFERENCED FROM SURVEILLANCE ALLOWABLE REQUIRED REQUIREMENTS VALUE ACTION 0.1 G H E .G H .. G H G H 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

?ne or more fuel assemblies.

{d) During instrument calibrations, if the As Found channel setpoirit is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to ser-1ice in accordance with the Surveillance.

If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel 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 or the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. BFN-UNIT 3 3.3-9 Amendment No. 212 213 221 235 254 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

APPLICABILITY:

THERMAL RTP. L@] ACTIONS Separate Condition entry is allowed for each channel. CONDITION A. One or more feedwater and main turbine high water level trip channels inoperable, in one trip system. B. One or more feedwater and main turbine high water lever trip channels inoperable in each trip system. c. Required Action and associated Completion Time not met. BFN-UNIT 3 REQUIRED ACTION A.1 Place channeJ(s) in trip. B.1 Restore feedwater and main turbine high water level trip capability.

C.1 Reduce THERMAL POWER RTP. 23 3.3-22 COMPLETION TIME 7 days 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours Amendment No. 213 0 =? (:: ;:. ". r-

'\__./ 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 3 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.

ACTIONS EOC-RPT Instrumentation 3.3.4.1 --------------------------NOTE--------------------------------

Separate Condition entry is allowed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.

OPERABLE status. OR A.2 --------NOTE------

Not applicable if inoperable channel is the result of an inoperable breaker. -------------------

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR AND 8.2 Apply the MCPR and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> MCPR and LHGR limit for LHGR limit for inoperable inoperable EOC-RPT not EOC-RPT as specified in made applicable.

the COLR. C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 26 BFN-UNIT 3 3.3-31 Amendment No. 243.-245

  • EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.1.2 Verify TSV -Closure and TCV Fast Closure, 24 months Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER is 26 SR 3.3.4.1.3 Perform CHANNEL CALIBRATION.

The 24 months Allowable Values shall be: TSV -

10% closed; and TCV Fast Closure, Trip Oil Pressure -Low:

psig. SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including breaker actuation.

BFN-UNIT3 3.3-32 Amendment No. 215 r* .-.... r. ,.., . . . . -

stq 0 u bL

  • t. 10

\ __ ., Jet Pumps '3.4.2 SURVEILLANCE REQUIREMENTS SR 3.4.2.1

  • BFN-UNIT3 SURVEILLANCE
1. Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after associated recirculation loop is in operation.
2. Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after>'% RTP. FREQUENCY Verify at least one of the following aiteria (a, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b, or c) is satisfied for each operating recirculation loop: 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 pattems. b. Each jet pump diffuser to lower plenum differential pressure differs by 20% from
  • established patterns.
c. Each jet pump flow differs by s; 10% from established pattems. 3.4-6 Amendment No. 212 CAD System 3.6.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 126151 Verify 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-UNIT3 3.6-41 Amendment No. 212 RHRSW System end UltS 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW} System and Ultimate Heet Sink (UMS) LCO 3.7.1 -------------------NOTE-------------------

The number of required RHRSW pumps may be reduced by one for each fueled unit that has been in MODE 4 or 5 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Four RHRSW subsystems end UHS shall be OPERABLE with the number of OPERABLE pumps as listed befow: 1. 1 unit fueled -four OPERABLE RHRSW pumps. 2. 2 units fueled .. six OPERABLE RHRSW pumps. 3. 3 units fueled .. eight OPERABLE RHRSW pumps. APPLICABILITY:

MODES 1, 2, and 3. BFN-UNIT 3 3.7-1 Amendment No. 214 SEP 0 e 1998 ACTIONS CONDITION A One required RHRSW pump inoperable

.. BFN-UNIT3 REQUJRED ACTION RHRSW System and UHS 3.7.1 COMPLETION TIME A1 NOTES--QB 1. Only appHcable for the 2 units fueled condition.

2. Only four RHRSW pumps powered from
  • a separate 4 kV shutdovm board are required to be OPERABLE if the other fueled unit has been in MODE 4 or 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Verify five RHRSW Immediately pumps powered from separate 4 kV shutdown boards are OPERABLE.

A.2 Restore required RHRSW 30 days pump to OPERABLE status. 3.7-2 (continued)

Amendment No. 214 :* ** ; : ? r:: B ACTIONS (continued)

CONDITION

0. Two RHRSW subsystems

0.1 inoperable

.. -. BFN-UNIT3 RHRSW System efld UI IS 3.7.1 REQUIRED ACTION COMPLETION

.* TIME NOTE Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdo\Yl"l Cooling -Hot Shutdown," for RHR shutdown cooling made inoperable by the RHRSW system. Restore RHRSW 30 days subsystem to OPERABLE status. Restore one inoperable 7 days RHRSW pump to OPERABLE status. NOTE Enter applicable Conditions and Required Actions of LCO 3.4.7, for RHR shutdown cooling made inoperable by the RHRSW System. Restore one RHRSW 7days subsystem to OPERABLE status. (continued) 3.7-3 Amendment No. 214 s [_ p 0 3 ACTIONS (continued)

CONDITION E. Three or more required E.1 RHRSWpumps

.. inoperable. . F. Three or more RHRSW F.1 subsystems inoperable.

G. Required Action and G.1 associated Completion Time not met. AND G.2 2B lJHS iAepeFable BFN-UNIT3 RHRSW System &Ad UHS 3.7.1 REQUIRED ACTION COMPLETION TIME .*. Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> pump to OPERABLE status. NOTE Enter applicable Conditions and Required Actions of LCO 3.4. 7 for RHR shutdovm cooling made inoperable by the RHRSW System. Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> subsystem to OPERABLE status. Be in MODE 3. Be in MODE4. 3.7-4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours AmendmeolNo.

214 0 8 1998 RHRSW System and UI IS 3.7.1 SURVEILLANCE REQUIREMENTS SR 3.7.1.1 SR 3.7.1.2 BFN-UNIT3 . SURVEILLANCE Verify each RHRSW manual and power operated 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 correct position.

FREO'UENCY 31 days Ve1 ify ti 1e water temperature of UI I S 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> UI IS is within the limits specified in Figure a. 7 .1-1. temperature 3.7-5 1 heur UHS temperature Amendment No. 214 SEP 0 8 1998

\...__/* Figure 3.7.1*1 RHRSW System end UHS 3.7.1 eaetor Thermal Power Versu Ultimate Heat Sink Temperature mlt 101,..---------+--------------------r--------------------I-------.

100 +---------

g I 99 J I N &; 17 BFN-UNIT 3 ..... 3.7-6 Amendment No. 214 S L-P f f 1 99 3 EECW System and UHS 3.7.2 \ __ / SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SR 3.7.2.3 BFN-UNIT3 SURVEILLANCE NOTE Refer to SR 3. 7 .1.2 for additional UHS Fcquiremcnts. FREQUENCY Verify the average water temperature of UHS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 95°F.

lsolation of flow to individual components does not render EECW System inoperable.

Verify each EECW system manual and power 31 days operated valve in the flow paths servicing safety related systems or components. that is not locked, sealed, or otherwise secured in position, is in the correct position.

Verify each required EECW pump actuates 24 months on an actual or simulated initiation signal. 3.7-8 Amendment No. 215 ; . _ .. : ', I .-. ...., *' r. ' .... ,

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 The following limits are made applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION. RA TE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR. THERMAL RTP. CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO. 8. Required Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 23 BFN-UNIT 3 3.7-17 Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

The peak calculated containment internal ressure for the desi n basis loss of coolant accident, Pa, is . psig. The maximum allowable primary containment leakage rate, La, shall be 2% of primary containment air weight per day at pa. Leakage Rate acceptance criteria are: a. The primary containment leakage rate acceptance criteria is :S 1.0 La. During the first unit startup following the testing performed in accordance with this program, the leakage rate acceptance criteria ares 0.60 La for the Type B and Type C tests , and s 0. 75 La for the Type A test; and b. Air lock testing acceptance criteria are: 1) Overall air lock leakage rate s 0. 05 La when tested at Pa* 2) Air lock door seals leakage rate is $:. 0.02 La when the overall air lock is pressurized to 2: 2.5 psig for at least 15 minutes. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment leakage Rate Testing Program. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. 5.5.13 Control Room Envelope Habitability Program BFN-UNIT 3 A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke chaHenge.

The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident {OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.

The program shall include the following elements:

5.0-21 Amendment No. 261 ACTIONS EOC-RPT Instrumentation 3.3.4.1 -----------------_..:_-------------NOTE------------------------------

Separate Condition entry is allowed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperabre.

OPERABLE status. OR A.2 ----------NOTE-------

Not applicable if inoperable channel is the result of an inoperable breaker. --------------------------------

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR *. AND 8.2 Apply the MCPR and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> MCPR and LHGR limit for LHGR limit for inoperable inoperable EOC-RPT not EOC-RPT as specified in made applicable.

the COLR. C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 26 BFN-UNJT 2 3.3".'31 Amendment No.

EOC-RPT Instrumentation 3.3.4.1 \_) SURVEILLANCE REQUIREMENTS

\_)

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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function malntains EOC-RPT trip SURVEILLANCE SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. SR 3.3.4.1.2 Verify TSV -Closure and TCV Fast Closure, Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER is 26 SR 3.3.4.1.3 Perform CHANNEL CALIBRATION.

The Allowable Values shall be: TSV -Closure: 10% closed; and TCV Fast Closure, Trip Oil Pressure -Low: 550 psig. SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST including breaker actuation.

BFN-UNIT2 3.3-32 FREQUENCY 92 days 24 months 24 months 24 months Amendment No. 255 J10V S 0 1898

\..J. SURVEILLANCE REQUIREMENTS SR 3.4.2.1 SURVEILLANCE

1. Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after associated recirculation loop is in operation.
2. Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after>
a. Recirculation pump flow to speed ratio differs by 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 diff erentia1 pressure differs by s 20% from *established patterns.
c. Each jet pump flow differs by s 10% from established patterns.

Jet Pumps 3.4.2 FREQUENCY BFN-UNIT 2 3.4-6 Amendment No. 253 SURVEILLANCE REQUIREMENTS SR 3.6.3.1.1 SR 3.6.3.1.2 BFN-UNIT 2 SURVEILLANCE

__ +__ 126151 Verify .zse&gal of liquid nitrogen are contained in each nitrogen storage tank. Verify each CAD subsystem manual, power 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.

3.6-41 CAD System 3.6.3.1 FREQUENCY 31 days 31 days Amendment No. 253 RHRSW System ana UI IS 3.7.1 3.7 PLANT SYSTEMS 3. 7.1 Residual Heat Removal Service Water {RHRSW) System and Ulti_mate Heat Sink (UHS) LCO 3.7.1 -------------------NOTE-------------------

The number of required RHRSW pumps may be reduced by one for each fueled emit that has been in MODE 4 or 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. . . Four RHRSW subsystems aAd UHS shall be OPERABLE with the number of OPERABLE pumps as listed below: 1. 1 unit fueled -four OPERABLE RHRSW pumps. 2. 2 units fueled -six OPERABLE RHRSW pumps. 3. 3 units fueled -eight OPERABLE RHRSW pumps. APPLICABILITY:

MODES 1, 2, and 3 . .

  • BFN-UNIT 2 3.7-1 Amendment No. 254 SEP O 8 1998

". ACTIONS CONDITION A. One required RHRSW pump inoperable.

BFN-UNIT2 REQUIRED ACTION .RHRSW System eRa UHS 3.7.1 COMPLETION TIME A.1 NOTES--OR* **1. <;>nly applicable for the 2 units fueled condition.

2. Only four RHRSW pumps powered from a separate 4 kV shutdown board are required to be OPERABLE if the other fueled unit has been in MODE 4 or 5 for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -. Verify five RHRSW Immediately pumps powered from separate 4 kV shutdown boards .are OPERABLE.

A.2 Restore required RHRSW 30 days pump to OPERABLE status. 3.7-2 (continued)

No. 254 0 8 1598 ACTIONS (continued)

CONDITION

D. Two RHRSW subsystems

0.1 inoperable

.. : BFN-UNIT 2 RHRSW System anef UI IS 3.7.1 REQUIRED ACTION COMPLETION TIME NOTE applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling -Hot Shutdown," for RHR shutdown cooling made Jnoperable by the RHRSW system. Restore RHRSW 30 days subsystem to OPERABLE status. . . Restore one inoperable 7 days RHRSW pump to OPERABLE status. NOTE applicable Conditions and Required Actions of LCO 3.4.7, for RHR shutdown cooling made inoperable by the RHRSW System. Restore one RHRSW 7days subsystem to OPERABLE status. (continued) 3.7-3 Amendment No. 254 SEP 0 8 1998 ACTIONS (continued)

CONDITION E. Three or more required E.1 RHRSWpumps inoperable. . F. Three or more RHRSW F.1 subsystems inoperable.

G. Required Action and G.1 associated Completion Time not met. AND G.2 9R YHS iAepeFaele BFN-UNIT2 RHRSW System ana Ut IS 3.7.1 REQUIRED ACTION COMPLETION TIME Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to OPERABLE status . NOTE Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by the RHRSW System. Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> subsystem to OPERABLE status. Be in MODE 3. Be in MODE4. 3.7-4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Amendment No. 254 SEP O 8 1998

"--/ RHRSW System and UH S 3.7.1 SURVEILLANCE REQUIREMENTS SR 3.7.1.1 SR 3.7.1.2 .* BFN-UNIT2 SURVEILLANCE FREQUENCY Verify each RHRSW manual and power 31 days operated 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 eorrect p_osition.

Ver i fy the water temperature of UH S 24 I 1001 s UH S is within the limits specified in Figure S.7.1-1. te111peratme 3.7-5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> UHS ten 1pe1 atu1 e >9 1°F Amendment No. 254

  • SEP 0 8 1998 8FN-UNIT2 Figure 3.7.1-1 eactor Thennal Power Versus Sink Temperature LI 3.7-6 RHRSW System and UHS 3.7.1 95 Amendment No. 254 SEP 0 8 1398 EECW System and U HS 3.7.2 SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SR 3.7.2.3 BFN-UNIT 2 SURVEILLANCE NOTE Refer to SR a.7.1.2 for additional UHS requirements. FREQUENCY Verify the average water temperature of UHS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 95°F.

Isolation of flow to individual components does not render EECW System inoperable.

Verify each EECW system manual and power 31 days operated valve in the flow paths servicing safety related systems or components, that is not locked, sealed, o r otherwise secured in position, is in the correct position.

Verify each required EECW pump actuates on an actual or simulated initiation signal. 3.7-8 24 months Amendment No. 255 . l}OV 3 0 1998 -;$ha1L atplb

\ __ / 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 limits are made applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RA TE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR. THERMAL 2,§% f(TP. CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO. B. Requi_red Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to .:; Time not met. 23 BFN-UNIT2 3.7-17 ' Amendment No. 2§4, 287 Programs and Manuals 5.5 5.5. Programs and Manuals 5.5.12 Primarv Containment Leakage Rate Testing Program (continued)

The peak calculated containment internal pressure fo"r the design basis loss of coolant accident, P a1 is §Gt§ psig. The ma.xi mum allowable primary 49* 1 containment leakage rate, La, shall be 2% of primary containment air weight per day at Pa* Leakage Rate acceptance criteria are: a. The primary containment leakage rate acceptance criteria is s 1.0 La. During the first unit startup following the testing performed in accordance with this program, the leakage rate acceptance criteria are 0.60 La for the Type 8 and Type C tests ,

0.75 La for the Type A test; and b. Air lock testing acceptance criteria are: 1) Overall air lock leakage rates; 0.05 La when tested Pa. 2) Air lock door seals leakage rate is s; 0.02 La when the overall air lock is pressurized to 2. 5 psig for at least 15 minutes. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. 5.5.13 Control Room Envelope Habitability Program BFN-UNIT 2 A Control Room Envetope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke cha I lenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent

{TEDE) for the duration of the accident.

The program shall include the following elements: (continued) 5.0-21 Amendment No.

302 (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 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) BFN-UNIT 3 Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess megawatts thermal. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 272, 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 212 to Facility Operating License DPR-68, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment 212, 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 212. Amendment No. 272 Renewed License No. DPR-68 BFN-UNIT 3 (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 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, and June 2, 5, 1_0 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.

C (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 immediately.

(6)(a) The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The combined set of plans, which contains Safeguards Information protected under 1 O CFR 73.21, is entitled:

11 Browns Ferry Nuclear Plant Physical Security Plan, Training and Qualification Plan, and Contingency Plan," Revision 4, submitted by letter dated April 28, 2006. (b) The licensee shall fully implement and .maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The licensee CSP was approved by License Amendment No. 265, as amended by changes approved by License Amendment No. 271. (7) Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the safety evaluations dated December 8, 1988; March 31, 1993; April 1, 1993; November 2, 1995; April 25, 2007, and Supplement dated November 3, 1989; subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Renewed License No. DPR-68 Amendment No. 271 INSERT G 2.G.(4) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.G.(1) of Renewed Facility Operating License No. DPR-68, for Browns Ferry Nuclear Plant Unit 3, 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 available on-dryer structural response sensors and 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 NRG review of power ascension data. Power shall not be increased above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRG confirms receipt of the evaluations unless, prior to the expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRG communicates that the NRG 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 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. 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 NRG staff in accordance with 10 GFR 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 GFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.

1.1 -Oefinitions (continued)

\ ... _./ PHYSICS TESTS RATED THERMAL POWER (RTP) SHUTDOWN MARGIN (SOM) BFN-UNIT3 Definitions

1.1 PHYSICS

TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reaetor core and related instrumentation.

These tests are: a. Described in Section 13.10, Refueling Test Program; of the FSAR; b. Authorized under the provisions of 10 CFR 50.59; or c. Othel"Nise approved by the Nuclear Regulatory Commission.

-RTP shall be a totaf reactor core heat transfer rate to the reactor coolant MWt. SOM shall be the amount of reactivity by which the reactor is subcriticaf or would be subcritical assuming that: a. The reactor is xenon free; b. The moderator temperature is 68°F; and c. AH control rods are fully inserted 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. 214 s::: .. :

\ __ / *\._/. 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 s RTP. . L--@] SLs 2.0 With the reactor steam dome pressure 785 psig and core flow i17)Ql 10% rated core flow: 1 _06 2.1.1.2 MCPR shall be 1 for loop operation +.<<-I 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 viofation, the following actions shaH be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 2.2.1 Restore compliance wjth all Sls; and 2.2.2 Insert all rnsertabf e control rods. BFN-UNIT3 2.0-1 Amendment No. 216, 234, 246 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 3 SURVEILLANCE Verify the concentration and temperature of boron in solution are within the limits of Figure 3.1.7-1. FREQUENCY Once withjn a hours after discovery that SPB concentration is > 9.2% by weight AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Verify the minimum quantity of Boron-10 in the 31 days SLC solution tank and available for injection is Verify the SLC conditions satisfy the following 31 days equation: ( C )( Q )( E ) (-a-wt. 1 50. Ll94I 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 39 gpm at a discharge pressure 1325 psig. Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to the solution 24 months (continued) 3.1 .. 25 Amendment No. 2-1-6 1 249 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 2,p% RTP. ACTIONS CONDITION REQUIRED ACTION A Any APLHGR not within A.1 Restore APLHGR(s) to limits. within limits. B. Required Action and B.1 Reduce THERMAL associated Completion POWER to< Time not met. 23 BFN-UNIT3 3.2-1 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours Amendment No. 212 SURVEILLANCE REQUIREMENTS SR 3.2.1.1 SURVEILLANCE Verify all APLHGRs are less than or equal to the limits specified in the COLR. APLHGR 1 3.2.1 FREQUENCY . Once within

  • 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter BFN-UNIT 3 3.2-2 Amendment No. 212

3.2 POWER

DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) MCPR > 3.2.2 LCO 3.2.2 All MCPRs shaJI be greater than or equal to the MCPR operating limits s*pecified in the COLR. APPLICABILITY:

THERMAL RTP. L--@] ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limits. within limits. B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 23 BFN-UNIT 3 3.2-3 Amendment No. 212 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after L-9 AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.1 Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.2 BFN-UNIT3 3.2-4 Amendment No. 212

3.2 POWER

DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) LHGR ' 3.2.3 LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:

THERMAL RTP. L--8 ACTIO N S CONDITION REQUIRED ACTION COMPLETION. . .. TIME A Any LHGR not within A1 Restore LHGR(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limits. within limits. B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met.

  • 23 BFN-UNIT3 3.2-5 Amendment No. 212 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after L@) AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter
  • eFN-UNIT3 3.2-6 Amendment No. 212 ACTIONS (continued)

CONDITION

8. ---------NOTE------------

Not applicable for Functions 2.a, 2.bl 2.c, 2.d, or 2.f.

One or more Functions with one or more required channels inoperable in both trip systems. C. One or more Functions with RPS trip capability not maintained.

D. Required Action and associated Completion Time of Condition A, 8, or C not met. E. As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

F. As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

REQUIRED ACTION 8.1 Place channel in one trip system in trip. OR 8.2 Place one trip system in trip. C.1 Restore RPS trip capability.

0.1 Enter

the Condition referenced in Table 3.3.1.1-1 for the channel. E.1 Reduce THERMAL POWER_ to<

26 F.1 Be in MODE2. RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 6 hours (continued)

BFN-UNIT 3 3.3-2 Amendment No. 212, 213, 221 SEP 2 7 t S S9 st,o)cl .\QL.

a+/-

  • Ob °t RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS
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 ai-sociated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 3 SURVEILLANCE Perform CHANNEL CHECK.

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> THERMAL POWER RTP. 23 FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Verify the absolute between the 7 days average power range monitor (APRM) channels and the calculated power is 2% RTP while operating Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2. Perform CHANNEL FUNCTIONAL TEST. 3.3-4 7 days (continued)

Amendment No. 213 SEP 0 3 1998 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 Neutron detectors are 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 For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 ii% and recirculation drive flow is < 60% of rated recirculation drive flow. BFN-UNIT 3 3.3-6 Amendment No. 212, 213, 215, 221 SEP 7

\ . '-...__../

1. 2. (*) (b) FUNCTION ** Intermediate Range Mcnftors .. Neutrcn FkJx
  • High b. tncp Average Power" Range Manltara .. Neutron Flux
  • High. (Setdown}

ti. Fla.v Blased SlmUlated Thermal Power

  • High c. Neutron Flux -High Table 3.3.1.1-1 (page 1 of 3) Reactor Protection System Instrumentation . APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 2 5(*) 2 5(a) 2 1 1 REQUIRED CHANNELS PERTRJP SYSTEM 3 3 3 3 3(b) 3{b) 3(b) CONDITIONS REFERENCED FROM REQUIRED ACTIOND.1 G H G H G f F With Cr/ control rod wfthdrawn frort\ a core cell containing one or mare fuel assemblies.

Each APRM channel provides Inputs to both trfp systems. RPS Instrumentation 3.3.1.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE SR 3.3.1.1.1 s 120l125 SR 3.3.1.1.3 divisions of full 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 SR 3.3.1.1.1

' s 120/125 SR 3.3.1.1.4 dMsJons of full SR 3.3.1.1.S scale SR 3.3.1.1.14 SR 3.3.1.1.3 NA SR 3.3.1.1.14 SR 3.3.1.1.4 NA SR 3.3.1.1.14 SR 3.3.1.1.1 RTP SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13

! SR 3.3.1.1.7 ands SR 3.3.1.1.13 RTP(c) SR 3.3.1.1.16 SR 3.3.1.1.1 s 12QAMi 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) (c) l"f W

  • 4 RTP when reset far slngle locp opemlcn per LCO 3.4.1, "Recirc:ufatian Loops Operating." 0.55 BFN-UNIT3 3.3-7 Amendment No. 216 DEC 2 3 1998 FUNCTION 7. Scram Discharge Volume Water Level -High b. Float Switch 8. Turbine Stop Valve -Closure 9. Turbine Control Valve Fast Closure, Trip Oil Pressure -Low(d) 1 o. Reactor Mode Switch -Shutdown Position 11. Manual Scram 12. RPS Channel Test Switches 13. Deleted RPS Instrumentation 3.3.1.1 Table3.3.1.1-1 (page3of3)

Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER . SPECIFIED CONDITIONS 1,2 5(a) 1,2 5(a) 1,2 5(2) 1,2 5(a) REQUIRED CHANNELS PER TRIP SYSTEM 2 2 4 2 2 2 CONDITlONS REFERENCED FROM SURVEILLANCE ALLOWABLE REQUIRED REQUIREMENTS VALUE ACTION 0.1 G H E .G H .. G H G H 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

?ne or more fuel assemblies.

{d) During instrument calibrations, if the As Found channel setpoirit is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to ser-1ice in accordance with the Surveillance.

If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel 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 or the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report. BFN-UNIT 3 3.3-9 Amendment No. 212 213 221 235 254 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

APPLICABILITY:

THERMAL RTP. L@] ACTIONS Separate Condition entry is allowed for each channel. CONDITION A. One or more feedwater and main turbine high water level trip channels inoperable, in one trip system. B. One or more feedwater and main turbine high water lever trip channels inoperable in each trip system. c. Required Action and associated Completion Time not met. BFN-UNIT 3 REQUIRED ACTION A.1 Place channeJ(s) in trip. B.1 Restore feedwater and main turbine high water level trip capability.

C.1 Reduce THERMAL POWER RTP. 23 3.3-22 COMPLETION TIME 7 days 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours Amendment No. 213 0 =? (:: ;:. ". r-

'\__./ 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 3 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.

ACTIONS EOC-RPT Instrumentation 3.3.4.1 --------------------------NOTE--------------------------------

Separate Condition entry is allowed for each channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.

OPERABLE status. OR A.2 --------NOTE------

Not applicable if inoperable channel is the result of an inoperable breaker. -------------------

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR AND 8.2 Apply the MCPR and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> MCPR and LHGR limit for LHGR limit for inoperable inoperable EOC-RPT not EOC-RPT as specified in made applicable.

the COLR. C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 26 BFN-UNIT 3 3.3-31 Amendment No. 243.-245

  • EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.1.2 Verify TSV -Closure and TCV Fast Closure, 24 months Trip Oil Pressure -Low Functions are not bypassed when THERMAL POWER is 26 SR 3.3.4.1.3 Perform CHANNEL CALIBRATION.

The 24 months Allowable Values shall be: TSV -

10% closed; and TCV Fast Closure, Trip Oil Pressure -Low:

psig. SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including breaker actuation.

BFN-UNIT3 3.3-32 Amendment No. 215 r* .-.... r. ,.., . . . . -

stq 0 u bL

  • t. 10

\ __ ., Jet Pumps '3.4.2 SURVEILLANCE REQUIREMENTS SR 3.4.2.1

  • BFN-UNIT3 SURVEILLANCE
1. Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after associated recirculation loop is in operation.
2. Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after>'% RTP. FREQUENCY Verify at least one of the following aiteria (a, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b, or c) is satisfied for each operating recirculation loop: 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 pattems. b. Each jet pump diffuser to lower plenum differential pressure differs by 20% from
  • established patterns.
c. Each jet pump flow differs by s; 10% from established pattems. 3.4-6 Amendment No. 212 CAD System 3.6.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 126151 Verify 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-UNIT3 3.6-41 Amendment No. 212 RHRSW System end UltS 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW} System and Ultimate Heet Sink (UMS) LCO 3.7.1 -------------------NOTE-------------------

The number of required RHRSW pumps may be reduced by one for each fueled unit that has been in MODE 4 or 5 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Four RHRSW subsystems end UHS shall be OPERABLE with the number of OPERABLE pumps as listed befow: 1. 1 unit fueled -four OPERABLE RHRSW pumps. 2. 2 units fueled .. six OPERABLE RHRSW pumps. 3. 3 units fueled .. eight OPERABLE RHRSW pumps. APPLICABILITY:

MODES 1, 2, and 3. BFN-UNIT 3 3.7-1 Amendment No. 214 SEP 0 e 1998 ACTIONS CONDITION A One required RHRSW pump inoperable

.. BFN-UNIT3 REQUJRED ACTION RHRSW System and UHS 3.7.1 COMPLETION TIME A1 NOTES--QB 1. Only appHcable for the 2 units fueled condition.

2. Only four RHRSW pumps powered from
  • a separate 4 kV shutdovm board are required to be OPERABLE if the other fueled unit has been in MODE 4 or 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Verify five RHRSW Immediately pumps powered from separate 4 kV shutdown boards are OPERABLE.

A.2 Restore required RHRSW 30 days pump to OPERABLE status. 3.7-2 (continued)

Amendment No. 214 :* ** ; : ? r:: B ACTIONS (continued)

CONDITION

0. Two RHRSW subsystems

0.1 inoperable

.. -. BFN-UNIT3 RHRSW System efld UI IS 3.7.1 REQUIRED ACTION COMPLETION

.* TIME NOTE Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdo\Yl"l Cooling -Hot Shutdown," for RHR shutdown cooling made inoperable by the RHRSW system. Restore RHRSW 30 days subsystem to OPERABLE status. Restore one inoperable 7 days RHRSW pump to OPERABLE status. NOTE Enter applicable Conditions and Required Actions of LCO 3.4.7, for RHR shutdown cooling made inoperable by the RHRSW System. Restore one RHRSW 7days subsystem to OPERABLE status. (continued) 3.7-3 Amendment No. 214 s [_ p 0 3 ACTIONS (continued)

CONDITION E. Three or more required E.1 RHRSWpumps

.. inoperable. . F. Three or more RHRSW F.1 subsystems inoperable.

G. Required Action and G.1 associated Completion Time not met. AND G.2 2B lJHS iAepeFable BFN-UNIT3 RHRSW System &Ad UHS 3.7.1 REQUIRED ACTION COMPLETION TIME .*. Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> pump to OPERABLE status. NOTE Enter applicable Conditions and Required Actions of LCO 3.4. 7 for RHR shutdovm cooling made inoperable by the RHRSW System. Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> subsystem to OPERABLE status. Be in MODE 3. Be in MODE4. 3.7-4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours AmendmeolNo.

214 0 8 1998 RHRSW System and UI IS 3.7.1 SURVEILLANCE REQUIREMENTS SR 3.7.1.1 SR 3.7.1.2 BFN-UNIT3 . SURVEILLANCE Verify each RHRSW manual and power operated 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 correct position.

FREO'UENCY 31 days Ve1 ify ti 1e water temperature of UI I S 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> UI IS is within the limits specified in Figure a. 7 .1-1. temperature 3.7-5 1 heur UHS temperature Amendment No. 214 SEP 0 8 1998

\...__/* Figure 3.7.1*1 RHRSW System end UHS 3.7.1 eaetor Thermal Power Versu Ultimate Heat Sink Temperature mlt 101,..---------+--------------------r--------------------I-------.

100 +---------

g I 99 J I N &; 17 BFN-UNIT 3 ..... 3.7-6 Amendment No. 214 S L-P f f 1 99 3 EECW System and UHS 3.7.2 \ __ / SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SR 3.7.2.3 BFN-UNIT3 SURVEILLANCE NOTE Refer to SR 3. 7 .1.2 for additional UHS Fcquiremcnts. FREQUENCY Verify the average water temperature of UHS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 95°F.

lsolation of flow to individual components does not render EECW System inoperable.

Verify each EECW system manual and power 31 days operated valve in the flow paths servicing safety related systems or components. that is not locked, sealed, or otherwise secured in position, is in the correct position.

Verify each required EECW pump actuates 24 months on an actual or simulated initiation signal. 3.7-8 Amendment No. 215 ; . _ .. : ', I .-. ...., *' r. ' .... ,

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 The following limits are made applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION. RA TE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR. THERMAL RTP. CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO. 8. Required Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< Time not met. 23 BFN-UNIT 3 3.7-17 Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

The peak calculated containment internal ressure for the desi n basis loss of coolant accident, Pa, is . psig. The maximum allowable primary containment leakage rate, La, shall be 2% of primary containment air weight per day at pa. Leakage Rate acceptance criteria are: a. The primary containment leakage rate acceptance criteria is :S 1.0 La. During the first unit startup following the testing performed in accordance with this program, the leakage rate acceptance criteria ares 0.60 La for the Type B and Type C tests , and s 0. 75 La for the Type A test; and b. Air lock testing acceptance criteria are: 1) Overall air lock leakage rate s 0. 05 La when tested at Pa* 2) Air lock door seals leakage rate is $:. 0.02 La when the overall air lock is pressurized to 2: 2.5 psig for at least 15 minutes. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment leakage Rate Testing Program. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. 5.5.13 Control Room Envelope Habitability Program BFN-UNIT 3 A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke chaHenge.

The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident {OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.

The program shall include the following elements:

5.0-21 Amendment No. 261

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