ML062780135

Technical Specification, Enclosure to Amendment, Implementation of 24-Month Fuel Cycle, (TAC No. MC4161), (TS-433)

ML062780135
Person / Time
Site:	Browns Ferry
Issue date:	09/28/2006
From:	Chernoff M NRC/NRR/ADRO/DORL/LPLII-2
To:	Singer K Tennessee Valley Authority
Chernoff M, NRR/DORL, 415-4041
Shared Package
ML062770404	List: ML062170002 ML062780135
References
TAC MC4161
Download: ML062780135 (32)

Text

(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) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 263 , are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.

Renewed License No. DPR-33 Amendment No.263

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY Verify the concentration and temperature of Once within boron in solution are within the limits of 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> after Figure 3.1.7-1. discovery that SPB concentration is

> 9.2% by weight AND 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> thereafter SR 3.1.7.5 Verify the minimum quantity of Boron-1 0 in the 31 days SLC solution tank and available for injection is

_ 186 pounds.

SR 3.1.7.6 Verify the SLC conditions satisfy the following 31 days equation:

AND

( C )( Q )( Ew)

(13 wt. %)(86 gpm)(1 9.8 atom%) > Once within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> after where, water or boron is added to the solution C = sodium pentaborate solution concentration (weight percent)

Q = pump flow rate (gpm)

E= Boron-10 enrichment (atom percent Boron-1 0)

SR 3.1.7.7 Verify each pump develops a flow rate > 39 24 months gpm at a discharge pressure __1275 psig.

(continued)

BFN-UNIT 1 3.1-25 Amendment No. 234,-*254 263

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.8 Verify flow through one SLC subsystem from 24 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all piping between storage tank and 24 months pump suction is unblocked.

SR 3.1.7.10 Verify sodium pentaborate enrichment is within 24 months the limits established by SR 3.1.7.6 by calculating within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> and verifying by AND analysis within 30 days. After addition to SLC tank SR 3.1.7.11 Verify each SLC subsystem manual, power 31 days operated,-and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

. BFN-UNIT I 3..1-26 Amendment No. 234, 251, 263

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 --------- NOTE----------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the 92 days fully closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in _ 60 seconds after receipt of an actual or simulated scram signal; and

b. Opens when the actual or simulated scram signal is reset.

BFN'UNIT 1 3.1-29 Amendment No.-284-,263

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. 184 days SR 3.3.1.1.11 (Deleted)

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.13 ----------------- NOTE-----------

Neutron 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 is Ž 30% RTP.

SR 3.3.1.1.16 -- NOTE---- .-------------

NO For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 184 days BFN-UNIT 1 3.3-5 Amendment No. 234, 262, 263

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

- . . . -- I--

N OT E S- -------- -

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM 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 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.2 -------------------- NOTE ---------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at < 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ------- NOTE ----------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 --- ------------- NOTE ---.......--------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months (continued)

BFN-UNIT 1 3.3-18 Amendment No. 234, 262, 263

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.5 Verify the RWM is not bypassed when 24 months

• THERMAL POWER is *10% RTP.

S.R 3.3.2.1.6 -------- NOTE -----------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.7 Verify control rod sequences input to the Prior to declaring RWM are in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SR 3.3.2.1.8 ------- NOTE------------------......

Neutron detectors are excluded.

Verify the RBM: 24 months

a. Low Power Range - Upscale Function is not bypassed when THERMAL POWER is Ž 27% and

• 62% RTP.

b. Intermediate Power Range - Upscale Function is not bypassed when THERMAL POWER is > 62% and *82%

RTP.

c. High Power Range - Upscale Function is not bypassed when THERMAL POWER is > 82% RTP.

BFN-UNIT 1 3.3-19 Amendment No.-234, 262, 263

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS

---

-------- NOTE ................................................

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 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR. 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The 24 months.

Allowable Value shall be< 586 inches above vessel zero.

SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including valve actuation.

BFN-UNIT 1 3.3-22 Amendment No.-2,4, 263

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK for each required 31 days PAM instrumentation channel.

SR 3.3.3.1.2 (Deleted).

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION of the 184 days Reactor Pressure Functions.

SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for each 24 months required PAM instrumentation channel except for the Reactor Pressure Function.

BFN-UNIT 1 3.3-25 Amendment No. 234, 253, 263

Backup Control System 3.3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.

SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for the 24 months Suppression Pool Water Level Function.

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel except for the Suppression Pool Water Level Function.

BFN-UNIT 1 3.3-28 Amendment No. 2-34, 263

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

---

-- - - - -- NO' 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 hours0.25 days <br />0.0357 weeks <br />0.00822 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

>30% RTP.

SR 3.3.4.1.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

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

a 550 psig.

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

BFN-UNIT 1 3.3-31 Amendment No. 2,34-,263

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS

---

-------- NOTE ....---- -----...------------ - ............---

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 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK of the Reactor 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> Vessel Water Level - Low Low, Level 2 Function.

SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

a. Reactor Vessel Water Level - Low Low, Level 2: Ž 471.52 inches above vessel zero; and

b. Reactor Steam Dome Pressure - High:

< 1146.5 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including breaker actuation.

BFN-UNIT 1 3.3-34 Amendment No. 234-,263

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS NOTES---------- ------------------

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

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 184 days SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 1 3.3-41 Amendment No. 2-4-,263

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

---

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

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Function 2 and (b) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Function 1 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 1 3.3-50 Amendment No. 24-r263

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

---

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

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 122 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

.1 BFN-UNIT 1 3.3-57 Amendment No.234, 269,.263

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1

3. HPCI System Isolation (continued)

d. HPCI Steam Line Space 1,2,3 2 F SR 3.3.6.1.2 :5200'F HPCI Pump Room Area Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 I

e. HPCI Steam Line Space 1,2,3 2 F SR 3.3.6.1.2 :5 180*F Torus Area (Exit)

Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 I

f. HPCI Steam Line Space Torus Area (Midway) 1,2,'3 2 F SR 3.3.6.1.2 SR 3.3.6.1.5 s180*F I Temperature - High SR 3.3.6.1.6

g. HPCl Steam Line Space 1,2,3 2 F SR 3.3.6.1.2 :5 180*17 Torus Area (Entry)

Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 I

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Line Flow - 1,2,3 1 F SR 3.3.6.1.2 *450" H20 High SR 3.3.6.1.5 SR..3.3.6.1.6

b. RCIC Steam Supply Line 1,2,3 3 F SR 3.3.6.1.2 Ž50 psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6

c. RCIC Turbine 1,2,3 3 F SR 3.3.6.1.2 _520 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6

d. RCIC Steam Line Space 1,2,3 2 F SR 3.3.6.1.2 5 180°F RCIC Pump Room Area SR 3.3.6.1.5 Temperature - High SR 3.3.6.1.6

e. RCIC Steam Line Space 1,2,3 2 F SR 3.3.6.1.2 :5 180*F Torus Area (Exit)

Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 I

f. RCIC Steam Line Space Torus Area (Midway) 1,2,3 2 F SR 3.3.6.1.2 SR 3.3.6.1.5

<180*F I Temperature - High SR 3.3.6.1.6

g. RCIC Steam Line Space 1,2.3 2 F SR 3.3.6.1.2 *180*1 Torus Area (Entry) SR 3.3.6.1.5 Temperature - High SR 3.3.6.1.6 (contInud (continued)

BFN-UNIT 1 3.3-59 Amendment No. 234, 260, 263_.

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1

5. Reactor Water Cleanup (RWCU) System Isolation

a. Main Steam Valve Vault 1,2,3 2 F SR 3.3.6.1.2 < 201"F Aiea Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

b. Pipe Trench Area Temperature - High 1,2,3 2 F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

• 135°F 1

c. Pump Room A Area 1,2,3 2 F SR 3.3.6.1.2 < 152°F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 I

d. Pump Room B Area 1,2,3 2 F SR 3.3.6.1.2 < 152°F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

e. Heat Exchanger Room 1,2,3 2 F SR 3.3.6.1.2 < 170°F Area (West Wall) SR 3.3.6.1.5 Temperature - High SR 3.3.6.1.6 I

f. Heat Exchanger Room Area (East Wall) 1,2,3 2 F SR 3.3.6.1.2 SR 3.3.6.1.5

< 143°F I Temperature - High SR 3.3.6.1.6

g. SLC System Initiation 1,2 2a) H SR 3.3.6.1.6 NA

h. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 2 528 inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6

6. Shutdown Cooling System Isolation

a. Reactor Steam Dome 1,2,3 I F SR 3.3.6.1.2 < 115 psig Pressure - High SR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor Vessel Water 3,4,5 1 SR 3.3.6.1.1 2 528 inches 2 (b)

Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6

c. Drywell Pressure - High 1,2,3 2 F SR 3.3.6.1.2 _<2.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6 (a) One SLC System Initiation signal provides logic input to close both RWCU valves.

(b) Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

BFN-UNIT I 3.3-60 Amendment No. 234, 258, 26&- 263

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

-.-----.-------- NOTES-----.-------------------

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains secondary containment isolation capability.

3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for performance of a CHANNEL CALIBRATION or maintenance, entry into associated Conditions and Required Actions may be delayed for up to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> provided the downscale trip of the inoperable channel is placed in the tripped condition.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

. BFN-UNIT 1 3.3-63 Amendment No. 2,4-,263

CREV System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS

- -- r-':----

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

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains CREV initiation capability.

3. For Functions 3 and 4,-when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> provided the downscale trip of the inoperable channel is placed in the trip condition.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL 184 days TEST.

SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 1 3.3-68 Amendment No. 234-263

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The 184 days Allowable Values shall be:

a. Overvoltage < 132 V, 'With time delay set to _4 seconds.

b. Undervoltage _>108.5 V, with time delay set to

• 4 seconds.

c. Underfrequency > 56 Hz, with time delay set to < 4 seconds.

SR 3.3.8.2.3 Perform a system functional test. 24 months BFN-UNIT 1 3.3-77 Amendment No. 234-263

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4

SR 3.4.3.1 Verify the safety function lift settings of the In accordance required 12 S/RVs are within +/- 3% of the with the Inservice setpoint as follows: Testing Program Number of Setpoint S/RVs (psiq) 4 1105 4 1115 5 1125 Following testing, lift settings shall be within

+/- 1%.

SR 3.4.3.2 --------------------------- NOTE -----------------------

Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify each required S/RV opens when 24 months manually actuated.

BFN-UNIT 1 3.4-8 Amendment No. 244-,263

RCS Leakage Detection Instrumentation 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of required 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> primary containment atmospheric monitoring system instrumentation.

SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required primary containment atmospheric monitoring system instrumentation.

SR 3.4.5.3 Perform a CHANNEL CALIBRATION of 184 days required drywell sump flow integrator instrumentation.

SR 3.4.5.4 Perform a CHANNEL CALIBRATION of 24 months required leakage detection system instrumentation.

BFN-UNIT 1 3.4-14 Amendment No. 2-34-,263

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1-SR 3.5.1.7 ------------- NOTE ------------

Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 1010 and 92 days

>_920 psig, the HPCI pump can develop a flow rate >_5000 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.8 ----------- NOTE--------......-

Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 165 psig, the 24 months HPCI pump can develop a flow rate > 5000 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.9 ------------------- NOTE----------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.

(continued)

BFN-UNIT 1 .3.5-6 Amendment No. 2-44,263

ECCS -'Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.10 -------------------- NOTE -----------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.

SR 3.5.1.11 --------- NOTE----------

Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify each ADS valve opens when manually 24 months actuated.

SR 3.5.1.12 (Deleted).

BFN-UNIT 1 3.5-7 Amendment No. 2Z4-,24-263

ECCS - Shutdown 3:5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify each required ECCS pump develops In accordance the specified flow rate against a system head with the Inservice corresponding to the specified pressure. Testing Program SYSTEM HEAD CORRESPONDING TO A VESSEL TO TORUS NO. OF DIFFERENTIAL SYSTEM FLOW RATE PUMPS PRESSURE OF CS >_6250 gpm 2 >_105 psid INDICATED NO. OF SYSTEM SYSTEM FLOW RATE PUMPS PRESSURE LPCI  ;Ž 9,000 gpm 1 >-125 psig SR 3.5.2.5 -------------------------- NOTE -------------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.

BFN-UNIT 1 3.5-11 Amendment No. 234-,263

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with 31 days water from the pump discharge valve to the injection valve.

SR 3.5.3.2 Verify each RCIC System 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.

SR 3.5.3.3 ------ NOTE ------------------......

Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 1010 psig and 92 days

> 920 psig, the RCIC pump can develop a flow rate _> 600 gpm against a system head corresponding to reactor pressure.

SR 3.5.3.4 -------------- NOTE -----------

Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 165 psig, the 24 months RCIC pump can develop a flow rate _>600 gpm against a system head corresponding to reactor presgure.

(continued)

BFN-UNIT 1 3.5-13 Amendment No. 244-,263

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 ----------- NOTE-----------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual 24 months or simulated automatic initiation signal.

BFN-UNIT 1 3.5-14 Amendment No. 234-263

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with the Primary containment air lock testing, in accordance Containment with the Primary Containment Leakage Rate Leakage Rate Testing Program. Testing Program SR 3.6.1.1.2 Verify drywell to suppression chamber 24 months differential pressure does not decrease at a rate > 0.25 inch water gauge per minute over a 10 minute period at an initial differential pressure of 1 psid.

BFN-UNIT 1 3.6-2 Amendment No. 2-34-,263

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.5 Verify the isolation time of each power In accordance operated, automatic PCIV, except for MSIVs, with the Inservice is within limits. Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is > 3 In accordance seconds and < 5 seconds. with the Inservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to the 24 months isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV 24 months actuates to the isolation position on a simulated instrument line break signal.

SR 3.6.1.3.9 Remove and test the explosive squib from 24 months on a I each shear isolation valve of the TIP System. STAGGERED TEST BASIS SR 3.6.1.3.10 Verify leakage rate through each MSIV is In accordance

< 100 scfh and that the combined leakage with the Primary rate for all four main steam lines is < 150 scfh Containment when tested at > 25 psig. Leakage Rate Testing Program SR 3.6.1.3.11 Verify combined leakage through water tested In accordance lines that penetrate primary containment are with the Primary within the limits specified in the Primary Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program BFN-UNIT 1 3.6-16 Amendment No.-234,261, 263

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 -------- NOTES--------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. 14 days SR 3.6.1.5.2 Perform a functional test of each vacuum 92 days breaker.

SR 3.6.1.5.3 Verify the opening setpoint of each vacuum 24 months breaker is < 0.5 psid.

BFN-UNIT 1 3.6-21 Amendment No. 234-,263

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 --------- NOTES-------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. One drywell suppression chamber vacuum breaker may be nonfully closed so long as it is determined to be not more than 30 open as indicated by the position lights.

Verify each vacuum breaker is closed. 14 days SR 3.6.1.6.2 Perform a functional test of each required In accordance vacuum breaker. with the Inservice Testing Program SR 3.6.1.6.3 Verify the differential pressure required to 24 months open each vacuum breaker is < 0.5 psid.

BFN-UNIT I 3.6-23 Amendment No. 2-34-,263

Main Turbine Bypass System

- 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify one complete cycle of each main 31 days turbine bypass valve.

SR 3.7.5.2 Perform a system functional test. 24 months SR 3.7.5.3 Verify the TURBINE BYPASS SYSTEM 24 months RESPONSE TIME is within limits.

BFN-UNIT 1 3.7-17 Amendment No. 2-,4ý, 263