Text

Limiting Conditions for Operation and Surveillance Requirements
	ML020250280
Person / Time
Site:	Beaver Valley
Issue date:	01/17/2002
From:	; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML020250280 (56)
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DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 3/4.1.1.1 3/4.1.1.2 3/4.1.1.3 3/4.1.1.4 3/4.1.1.5 3/4.1.2 3/4.1.2.8 3/4.1.2.9 3/4.1.3 3/4.1.3.1 3/4.1.3.2 BORATION CONTROL Shutdown Margin -

Tavg > 200'F.............

Shutdown Margin -

Tavg

200°F..............

Boron Dilution............................

Moderator Temperature Coefficient.........

Minimum Temperature for Criticality BORATION SYSTEMS Refueling Water Storage Tank (RWST)

Isolation of Unborated Water Sources Shutdown..................................

MOVABLE CONTROL ASSEMBLIES Group Height....

Position Indication Systems - Operating...

3/4 3/4 3/4 3/4 3/4 1-1 1-3 1-4 1-5 1-6 3/4 1-16 3/4 1-17a 3/4 3/4 1-18 1-20 BEAVER VALLEY -

UNIT 1 Amendment No. 246 III

DPR-66 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.1.3.4 3/4.1.3.5 3/4.1.3.6 3/4. 2 POWER 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.4 3/4.2.5 Rod Drop Time.............................

Shutdown Rod Insertion Limit..............

Control Rod Insertion Limits..............

DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE.....................

HEAT FLUX HOT CHANNEL FACTOR..............

NUCLEAR ENTHALPY HOT CHANNEL FACTOR.......

QUADRANT POWER TILT RATIO DNB PARAMETERS PAGE 3/4 1-22 3/4 1-23 3/4 1-23a 3/4 3/4 3/4 3/4 3/4 2-1 2-5 2-8 2-10 2 -12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring......................

3/4.3.3.5 Remote Shutdown Instrumentation...........

3/4.3.3.8 Accident Monitoring Instrumentation.......

3/4.3.3.11 Explosive Gas Monitoring Instrumentation..

BEAVER VALLEY -

UNIT 1 3/4 3-1 3/4 3-14 3/4 3/4 3/4 3/4 3-33 3-44 3-50 3-54 Amendment No. 246 IV

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 3/4.4.1.1 3/4.4.1.2 3/4.4.1.3 3/4.4.1.4.1 3/4.4.1.5 3/4.4.3 3/4.4.4 3/4.4.5 3/4.4.6 3/4.4.6.1 3/4.4.6.2 3/4.4.6.3 3/4.4.8 3/4.4.9 3/4.4.9.1 3/4.4.9.3 3/4.4.11 REACTOR COOLANT LOOPS Normal Operation...........................

Hot Standby................................

Shutdown...................................

Loop Isolation Valves - Operating..........

Isolated Loop Startup......................

SAFETY VALVES..............................

PRESSURIZER................................

STEAM GENERATORS...........................

REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Instrumentation..........

Operational Leakage........................

Pressure Isolation Valves..................

SPECIFIC ACTIVITY..........................

PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.....................

Overpressure Protection Systems............

RELIEF VALVES..............................

BEAVER VALLEY -

UNIT 1 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 4-1 4-2b 4-2c 4-3 4-4 4-6 4-7 4-8 4-11 4-13 4-14a 4-18 4-22 4-27a 4-29 Amendment No. 246 V

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.7 PLANT 3/4.7.1 3/4.7.1.1 3/4.7.1.2 3/4.7.1.3 3/4.7.1.4 3/4.7.1.5 3/4.7.3 3/4.7.4 3/4.7.5 3/4.7.7 3/4.7.8 SYSTEMS TURBINE CYCLE Main Steam Safety Valves (MSSVs)

Auxiliary Feedwater System................

Primary Plant Demineralized Water (PPDW)

Activity..................................

Main Steam Line Isolation Valves..........

COMPONENT COOLING WATER SYSTEM............

REACTOR PLANT RIVER WATER SYSTEM..........

ULTIMATE HEAT SINK -

OHIO RIVER...........

CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS...................................

SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM............................

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES 3/4.8.1.1 Operating.................................

3/4.8.1.2 Shutdown..................................

BEAVER VALLEY -

UNIT 1 PAGE 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 7-1 7-5 7-7 7-8 7-10 7-12 7-13 7-14 3/4 7-16 3/4 7-19 3/4 8-1 3/4 8-5 VII Amendment No.246

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 3/4.8.2.1 A.C. Distribution - Operating................

3/4 8-6 3/4.8.2.2 A.C. Distribution -

Shutdown.................

3/4 8-7 3/4.8.2.3 D.C. Distribution - Operating................

3/4 8-8 3/4.8.2.4 D.C. Distribution -

Shutdown.................

3/4 8-10 3/4.9 REFUELING OPERATIONS 3/4.9.1 3/4.9.2 3/4.9.3 3/4.9.4 3/4.9.8 3/4.9.8.1 3/4.9.8.2 3/4.9.9 3/4.9.10 3/4.9.11 3/4.9.12 3/4.9.14 BORON CONCENTRATION.......................

INSTRUMENTATION DECAY TIME................................

CONTAINMENT BUILDING PENETRATIONS RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level..........................

Low Water Level...........................

CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM....................................

WATER LEVEL-REACTOR VESSEL................

STORAGE POOL WATER LEVEL FUEL BUILDING VENTILATION SYSTEM -

FUEL MOVEMENT..................................

FUEL STORAGE -

SPENT FUEL STORAGE POOL....

BEAVER VALLEY -

UNIT 1 3/4 3/4 3/4 3/4 9-1 9-2 9-3 9-4 3/4 9-8 3,/4 9-8a 3/4 3/4 3/4 9-9 9-10 9-11 3/4 9-12 3/4 9-14 Amendment No. 246 VIII

DPR-66 INDEX BASES SECTION PAGE 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS........................

B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO..................

B 3/4 2-5 3/4.2.5 DNB PARAMETERS B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 AND 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-2 3/4.3.3.1 Radiation Monitoring Instrumentation.........

B 3/4 3-2 3/4.3.3.5 Remote Shutdown Instrumentation...............

B 3/4 3-3 3/4.3.3.8 Accident Monitoring Instrumentation.........

B 3/4 3-3 3/4.3.3.11 Explosive Gas Monitoring Instrumentation...

B 3/4 3-4 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS......................

B 3/4 4-1 3/4.4.3 SAFETY VALVES B 3/4 4-ig 3/4.4.4 PRESSURIZER................................

B 3/4 4-2 3/4.4.5 STEAM GENERATORS B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE................

B 3/4 4-3 3/4.4.6.1 Leakage Detection Instrumentation............

B 3/4 4-3 3/4.4.6.2 Operational Leakage........................

B 3/4 4-3d 3/4.4.6.3 Pressure Isolation Valve Leakage..............

B 3/4 4-3j BEAVER VALLEY -

UNIT 1 Amendment No.246 X

DPR-66 INDEX BASES SECTION 3/4.4.8 3/4.4.9 3/4.4.11 SPECIFIC ACTIVITY.........................

PRESSURE/TEMPERATURE LIMITS...............

RELIEF VALVES PAGE B 3/4 4-4 B 3/4 4-5 B 3/4 4-11 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS 3/4.5.2 AND 3/4.5.3 ECCS SUBSYSTEMS....................

3/4.5.4 BORON INJECTION SYSTEM....................

3/4.5.5 SEAL INJECTION FLOW.......................

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 3/4.6.1.1 3/4.6.1.2 3/4.6.1.3 3/4.6.1.4 3/4.6.1.6 3/4.6.2 3/4.6.2.1 3/4.6.2.3 3/4.6.3 3/4.6.4 PRIMARY CONTAINMENT Containment Integrity Containment Leakage.......................

Containment Air Locks.....................

AND 3/4.6.1.5 Internal Pressure and Air Temperature...............................

Containment Structural Integrity DEPRESSURIZATION AND COOLING SYSTEMS AND 3/4.6.2.2 Containment Quench and Recirculation Spray Systems...............

Chemical Addition System..................

CONTAINMENT ISOLATION VALVES..............

COMBUSTIBLE GAS CONTROL...................

BEAVER VALLEY -

UNIT 1 B

B B

B 3/4 3/4 3/4 3/4 5-1 5-1 5-2 5-3 B

B B

3/4 31/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 6-1 6-1 6-1 6-9 6-9 6-10 6-11 6-12 6-12 Amendment No. 246 XI

DPR-66 BASES SECTION 3/4.7 PLANT SYSTEMS 3/4.7.1 3/4.7.1.1 3/4.7.1.2 3/4.7.1.3 3/4.7.1.4 3/4.7.1.5 3/4.7.3 3/4.7.4 3/4.7.5 3/4.7.7 3/4.7.8 TURBINE CYCLE Main Steam Safety Valves (MSSVs)

Auxiliary Feedwater System................

Primary Plant Demineralized Water.........

Activity..................................

Main Steam Line Isolation Valves..........

COMPONENT COOLING WATER SYSTEM............

RIVER WATER SYSTEM........................

ULTIMATE HEAT SINK........................

CONTROL ROOM EMERGENCY HABITABILITY SYSTEM....................................

SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM............................

B B

3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 7-1 7-2 7-2j 7-3 7-3 7-4 7-4 7-4 B 3/4 7-5 B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 AND 3/4.8.2 A.C.

SOURCES, D.C.

SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................

3/4.9.2 INSTRUMENTATION B 3/4 8-1 B

B 3/4 9-1 3/4 9-1 BEAVER VALLEY -

UNIT 1 INDEX PAGE Amendment No.246 XII

DPR-66 BASES SECTION 3/4.9.3 3/4.9.4 3/4.9.8 3/4.9.9 3/4.9.10 3/4.9.12 3/4.9.14 3/4.10 3/4.10.1 3/4.10.2 3/4.10.3 3/4.10.4 3/4.10.5 INDEX AND DECAY TIME................................

CONTAINMENT BUILDING PENETRATIONS RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...............................

CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM....................................

3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL..............................

FUEL BUILDING VENTILATION SYSTEM..........

FUEL STORAGE -

SPENT FUEL STORAGE POOL....

SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN...........................

GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS PRESSURE/TEMPERATURE LIMITATIONS-REACTOR CRITICALITY...............................

PHYSICS TESTS.............................

NO FLOW TESTS.............................

PAGE B 3/4 B 3/4 9-1 9-1 B 3/4 9-3 B 3/4 9-3 B

B B

3/4 3/4 3/4 9-4 9-4 9-5 B 3/4 10-1 B 3/4 10-1 B

B B

3/4 3/4 3/4 10-1 10-1 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.4 Liquid Holdup Tanks.......................

B 3/4 11-1 BEAVER VALLEY -

UNIT 1 XIII Amendment No.

246

DPR-66 Table Index (cont.)

TABLE 3.3-11 4.3-7 3.3-13 4.3-13 4.4-1 4.4-2 4.4-3 4.4-12 3.7-1 3.7-2 4.7-2 3.8-1 3.9-1 Accident Monitoring Instrumentation Accident Monitoring Instrumentation Surveillance Requirements Explosive Gas Monitoring Instrumentation Explosive Gas Monitoring Instrumentation Surveillance Requirements Minimum Number of Steam Generators to be Inspected During Inservice Inspection Steam Generator Tube Inspection Reactor Coolant System Pressure Isolation Valves Primary Coolant Specific Activity Sample and Analysis Program OPERABLE Main Steam Safety Valves versus Applicable Power in Percent of RATED THERMAL POWER (RTP)

Steam Line Safety Valves Per Loop Secondary Coolant System Specific Activity Sample and Analysis Program Battery Surveillance Requirements Beaver Valley Fuel Assembly Minimum Burnup vs.

Initial U235 Enrichment For Storage in Region 2 Spent Fuel Racks 3/4 3/4 8-9a 9-15 BEAVER VALLEY -

UNIT 1 TITLE PAGE 3/4 3-51 3/4 3-52 3/4 3-55 3/4 3-57 3/4 4-10g 3/4 4-10h 3/4 4-14b 3/4 4-20 3/4 7-2 3/4 7-4 3/4 7-9 Amendment No. 246 XVI I

DPR-66 REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS 3/4.1.2.1 - 3/4.1.2.7 (These Specification numbers are not used.)

BEAVER VALLEY -

UNIT 1 3/4 1-7 (Next Page is 3/4 1-16)

Amendment No. 246

REACTIVITY CONTROL SYSTEMS REFUELING WATER STORAGE TANK (RWST)

LIMITING CONDITION FOR OPERATION 3.1.2.8 The RWST shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 & 4.

ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 The RWST shall be verified OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration is between 2,400 and 2,600 ppm, and

2.

Verifying a contained volume between 439,050 gallons and 441,100 gallons of borated water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST solution temperature is

Ž 45°F and

55 0F when the RWST ambient air temperature is

< 45'F or > 55°F.

BEAVER VALLEY -

UNIT 1 3/4 1-16 (Next page is 3/4 1-17a)

Amendment No. 246

DPR-66 SURVEILLANCE REQUIREMENTS (Continued) 4.1.3.2.2 Each of the analog rod position indicators shall be determined to be OPERABLE by:

a.

Performing a

CHANNEL CHECK by intercomparison**

between each analog rod position indicator and its corresponding group demand counter at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Verifying that the analog rod position indicators agree with the demand position indicators within 12 steps(1) over the full-range of indicated rod travel at least once per 18 months.

For Core PHYSICS TESTING in Mode 2,

primary detector voltage measurements may be used to determine the position of rods in shutdown banks A

and B

and control banks A

and B

for the purpose of satisfying Specification 3.1.3.2.

During Mode 2

operation, rod position indicators for shutdown banks A and B and control banks A and B may deviate from the group demand indicators by greater than + 12 steps during reactor startup and shutdown operations, while rods are being withdrawn or inserted.

If the rod position indicators for shutdown banks A and B and control banks A and B deviate by greater than +/- 12 steps from the group demand indicator, rod withdrawal or insertion may continue until the desired group height is achieved.

When the desired group height is

achieved, a one hour soak time is allowed below 50% reactor power to permit stabilization of the rod position analog indicators.

To attain thermal equilibrium during the one hour soak time, the absolute value of rod motion shall not exceed 6 steps.

For power levels below 50% one hour thermal "soak time" is permitted.

During this soak time, the absolute value of rod motion is limited to six steps.

BEAVER VALLEY -

UNIT 1 Amendment No.

246 3/4 1-20c

REACTIVITY CONTROL SYSTEMS 3/4.1.3.3 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 Amendment No.

246 3/4 1-21

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABLE MODES SETPOINT(

3 )

MEASUREMENT RANGE

1. AREA MONITORS

a. Deleted

b. Containment

i.

Purge & Exhaust Isolation (RMVS 104 A & B) ii.

Area (RM-RM-219 A & B)

c. Control Room Isolation (RM-RM-218 A & B) 2 2

2 (2) 1,2,3 & 4 1,2,3,4 and (4)

1.6 x 103 cpm

1.5 x 104 R/hr

.47 mR/hr 10 -

106 cpm 1

7 R/hr 10-2 _ 103 mR/hr

2. PROCESS MONITORS

a. Containment

i.

Gaseous Activity RCS Leakage Detection (RM 215B) ii.

Particulate Activity RCS Leakage Detection (RM 215A)

I 1

1,2,3 & 4 1,2,3 & 4 N/A N/A I0 10 6 cpm 10 -

106 cpm

b. Deleted BEAVER VALLEY -

UNIT 1 ACTION 22 35 41 20 20 DPR-66 Amendment No. 246 3/4 3-34

TABLE 3.3-6 (Continued)

TABLE NOTATIONS (Not used)

During movement of recently irradiated fuel assemblies within the containment and during movement of fuel assemblies over recently irradiated fuel assemblies within the containment.

Above background.

During movement of irradiated fuel assemblies and during movement of fuel assemblies over irradiated fuel assemblies.

ACTION STATEMENTS ACTION 20 ACTION 21 ACTION 22 ACTION 35 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

This Action is not used.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

a)

Initiate the preplanned alternate method monitoring the appropriate parameter(s),

and of ACTION 41 -

b)

Return the channel to OPERABLE status within 30

days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

a)

With the number of Unit 1

OPERABLE channels one less than the Minimum Channels OPERABLE requirement:

1.

Verify the respective Unit 2

control room radiation monitor train is OPERABLE within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 31 days.

BEAVER VALLEY -

UNIT 1 DPR-66 (1)

(2)

(3)

(4)

Amendment No. 246 3/4 3-35

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL CHECK CALIBRATION TEST INSTRUMENT

1.

AREA MONITORS

a.

Deleted

b.

Containment

i.

Purge & Exhaust Isolation (RMVS 104 A & B) ii.

Area (RM-RM-219 A & B)

c.

Control Room Isolation (RM-RM-218 A & B)

2.

PROCESS MONITORS

a.

Containment S

S S

M R

R R

M M###

MODES IN WHICH SURVEILLANCE REQUIRED 1,2,3,& 4 1,2,3,4, and # #

i.

Gaseous Activity RCS Leak age Detection (RM 215B) ii.

Particulate Activity RCS Leakage Detection (RM 215A)

S S

M M

1,2,3 & 4 1,2,3 & 4

b.

Deleted During movement of recently irradiated fuel assemblies within the containment and during movement of fuel assemblies over recently irradiated fuel assemblies within the containment.

Surveillance interval may be extended to the upcoming refueling outage if the interval between refueling outages is greater than 18 months.

During movement of irradiated fuel assemblies and during movement of fuel assemblies over irradiated fuel assemblies.

Control Room intake and exhaust isolation dampers and CREBAPS solenoid valves are not actuated.

BEAVER VALLEY -

UNIT 1 Amendment No. 246 3/4 3-36

REACTOR COOLANT SYSTEM 3/4.4.2 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 3/4 4-5 Amendment No. 246

REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a

lift setting*

of 2485 PSIG +1% -3%.**

APPLICABILITY:

MODES 1, 2 and 3, MODE 4

with all RCS cold leg temperatures the enable temperature specified in 3.4.9.3.

ACTION:

a.

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN with any RCS cold leg temperature

< the enable temperature specified in 3.4.9.3 and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With a pressurizer code safety valve having discharged liquid water from a water solid pressurizer to mitigate an overpressure event, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN with any RCS cold leg temperature

the enable temperature specified in 3.4.9.3 and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3 No additional requirements other than those required by Specification 4.0.5.

The Lift Setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

Within +/- 1% following pressurizer code safety valve testing.

BEAVER VALLEY -

UNIT 1 Amendment No. 246 3/4 4-6

REACTOR COOLANT SYSTEM 3/4.4.7 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 3/4 4-15 (Next Page is 3/4 4-18)

Amendment No. 246

DPR-66 REACTOR COOLANT SYSTEM 3/4.4.9.2 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 Amendment No. 246 3/4 4-27

REACTOR COOLANT SYSTEM 3/4.4.10 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 Amendment No. 246 3/4 4-28

DPR-66 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued)

SHUTDOWN within the following 6

hours.

With one block valve inoperable, restore the block valve to OPERABLE status within 1

hour or close it, power operation may continue until the next refueling outage.

e.

With more than one block valve inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valves to OPERABLE status or place the associated PORVs in manual control.

Restore at least one block valve to OPERABLE status within the next hour if three block valves are inoperable; restore a

minimum of two block valves to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.11.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by operating the PORV through one complete cycle of full travel using:

a)

The normal air supply system, and b)

The backup nitrogen supply system.

4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed to meet required ACTIONS b or c.

BEAVER VALLEY UNIT 1 Amendment No. 246 3/4 4-29a

DPR-66 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT QUENCH SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two separate and independent containment quench spray subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one containment quench spray subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment quench spray subsystem shall be demonstrated OPERABLE;

a.

By verifying, at least once per 31 days, that each valve (manual, power-operated, or automatic) in the flow path not locked,

sealed, or otherwise secured in

position, is in its correct position; and

b.

By verifying, at the frequency specified in the Inservice Testing Program, that each quench spray pump's developed head at the flow test point is greater than or equal to the required developed head as specified in the Inservice Testing Program and the Containment Integrity Safety Analysis.

BEAVER VALLEY -

UNIT 1 Amendment No.

246 3/4 6-11

PLANT SYSTEMS 3/4.7.2 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 Amendment No. 246 3/4 7-11

PLANT SYSTEMS 3/4.7.6 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 1 Amendment No. 246 3/4 7-15

REFUELING OPERATIONS 3/4.9.5 -

3/4.9.7 (These Specification numbers are not used.)

BEAVER VALLEY -

UNIT 1 3/4 9-5 (Next page is 3/4 9-8)

Amendment No. 246

NPF-73 INDEX BASES SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE.................................

B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE................

B 2-2 LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY......................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL 3/4.1.1.1 Shutdown Margin -

Tavg > 200FF................

3/4 1-1 3/4.1.1.2 Shutdown Margin -

Tavg

200FF................

3/4 1-3 3/4.1.1.3 Boron Dilution...............................

3/4 1-4 3/4.1.1.4 Moderator Temperature Coefficient (MTC)......

3/4 1-5 3/4.1.1.5 Minimum Temperature for Criticality 3/4 1-6 3/4.1.2 BORATION SYSTEMS 3/4.1.2.8 Refueling Water Storage Tank.................

3/4 1-15 BEAVER VALLEY -

UNIT 2 Amendment No. 124 III

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.1.2.9 3/4.1.3 3/4.1.3.1 3/4.1.3.2 3/4.1.3.4 3/4.1.3.5 3/4.1.3.6 Isolation of Unborated Water Sources Shutdown.....................................

MOVABLE CONTROL ASSEMBLIES Group Height.................................

Position Indication Systems -

Operating......

Rod Drop Time................................

Shutdown Rod Insertion Limit.................

Control Rod Insertion Limits.................

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL F

.H 3/4.2.4 QUADRANT POWER TILT RATIO...

3/4.2.5 DNB PARAMETERS..............

FQ(Z)

FACTOR 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...........

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..............................

3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring.........................

3/4 3-3 BEAVER VALLEY -

UNIT 2 PAGE 3/4 1-17 3/4 3/4 3/4 3/4 3/4 1-18 1-21 1-23 1-24 1-25 3/4 3/4 3/4 3/4 3/4 2-1 2-4 2-7 2-9 2-11 4

9 Amendment No. 124 IV

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.3.3.5 3/4.3.3.8 3/4.3.3.11 Remote Shutdown Instrumentation..............

Accident Monitoring Instrumentation..........

Explosive Gas Monitoring Instrumentation.....

PAGE 3/4 3-52 3/4 3-57 3/4 3-61 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 3/4.4.1.1 3/4.4.1.2 3/4.4.1.3 3/4.4.1.4 3/4.4.1.5 3/4.4.1.6 3/4.4.3 3/4.4.4 3/4.4.5 3/4.4.6 3/4.4.6.1 3/4.4.6.2 3/4.4.6.3 3/4.4.8 3/4.4.9 3/4.4.9.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Normal Operation.............................

Hot Standby..................................

Shutdown.....................................

.1 Loop Isolation Valves - Operating............

Isolated Loop Startup........................

Reactor Coolant Pump-Startup.................

SAFETY VALVES................................

PRESSURIZER..................................

STEAM GENERATORS.............................

REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Instrumentation............

Operational Leakage..........................

Pressure Isolation Valves....................

SPECIFIC ACTIVITY............................

PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.......................

BEAVER VALLEY -

UNIT 2 3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-5 3/4 4-6 3/4 4-7 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-17 3/4 4-19 3/4 4-21 3/4 4-27 3/4 4-30 Amendment No. 124 V

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.9.3 Overpressure Protection Systems..............

3/4 4-35 3/4.4.11 RELIEF VALVES................................

3/4 4-39 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS.................................

3/4.5.2 ECCS SUBSYSTEMS Tavg Ž 350OF................

3/4.5.3 ECCS SUBSYSTEMS Tavg < 350°F................

3/4.5.4 SEAL INJECTION FLOW..........................

3/4 3/4 3/4 3/4 5-1 5-3 5-6 5-7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 3/4.6.1.1 3/4.6.1.2 3/4.6.1.3 3/4.6.1.4 3/4.6.1.5 3/4. 6.1.6 3/4. 6.2 3/4. 6.2.1 3/4.6.2.2 3/4.6.2.3 3/4.6.3 PRIMARY CONTAINMENT Containment Integrity Containment Leakage..........................

Containment Air Locks........................

Internal Pressure............................

Air Temperature..............................

Containment Structural Integrity DEPRESSURIZATION AND COOLING SYSTEMS Containment Quench Spray System..............

Containment Recirculation Spray System.......

Chemical Addition System.....................

CONTAINMENT ISOLATION VALVES.................

BEAVER VALLEY -

UNIT 2 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 6-1 6 -2 6-4 6-6 6-8 6-9 6-10 6-12 6-14 6-15 Amendment No. 124 VI

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6.4 COMBUSTIBLE GAS CONTROL 3/4.6.4.1 Hydrogen Analyzers.........................

3/4 6-31 3/4.6.4.2 Electric Hydrogen Recombiners.................

3/4 6-32 3 / 4. 7 PLANT 3/4.7 1 3/4.7.1.1 3/4.7.1.2 3/4.7.1.3 3/4.7.1.4 3/4.7.1.5 3/4.7.3 3/4.7.4 3/4.7.5 3/4.7.7 3/4.7.8 SYSTEMS TURBINE CYCLE Main Steam Safety Valves (MSSVs)...........

Auxiliary Feedwater System.................

Primary Plant Demineralized Water (PPDW)...

Activity...................................

Main Steam Line Isolation Valves...........

PRIMARY COMPONENT COOLING WATER SYSTEM.....

SERVICE WATER SYSTEM (SWS).................

ULTIMATE HEAT SINK -

OHIO RIVER............

CONTROL ROOM EMERGENCY AIR CLEANUP AND PRESSURIZATION SYSTEM......................

SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS).............................

BEAVER VALLEY -

UNIT 2 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 7-1 7-4 7-6 7-7 7-9

'7-11 7-12 7-13 3/4 7-15 3/4 7-18 Amendment No. 124 VII

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES 3/4.8.1.1 Operating....................................

3/4.8.1.2 Shutdown.....................................

3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEM 3/4.8.2.1 A.C. Distribution - Operating................

3/4.8.2.2 A.C. Distribution -

Shutdown.................

3/4.8.2.3 D.C. Distribution -

Operating................

3/4.8.2.4 D.C. Distribution -

Shutdown.................

3/4.9 REFUELING OPERATIONS PAGE 3/4 3/4 3/4 3/4 3/4 3/4 3/4.9.1 3/4.9.2 3/4.9.3 3/4.9.4 3/4.9.8 3/4.9.8.1 3/4.9.8.2 3/4.9.9 3/4.9.10 3/4.9.11 BORON CONCENTRATION..........................

INSTRUMENTATION..............................

DECAY TIME...................................

CONTAINMENT BUILDING PENETRATIONS............

RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.............................

Low Water Level..............................

CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.......................................

WATER LEVEL-REACTOR VESSEL...................

STORAGE POOL WATER LEVEL.....................

BEAVER VALLEY -

UNIT 2 8-1 8-6 8-7 8-8 8-9 8-12 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 9-1 9-2 9-3 9-4 9-8 9-9 9-10 9-11 9-12 Amendment No. 124 VIII

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM -

3/4.9.14 FUEL MOVEMENT...............................

FUEL STORAGE -

SPENT FUEL STORAGE POOL......

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.............................

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.........................

3/4.10.3 PHYSICS TESTS...............................

3/4.10.4 REACTOR COOLANT LOOPS.......................

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.4 Liquid Holdup Tanks.........................

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.5 Gaseous Waste Storage Tanks.................

3/4.11.2.6 Explosive Gas Mixture.......................

3/4 9-13 3/4 9-15 3/4 10-1 3/4 3/4 3/4 10-2 10-3 10-4 3/4 11-2 3/4 11-4 3/4 11-5 BASES SECTION PAGE 3/4.0 APPLICABILITY......................................

B 3/4 0-i 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL............................

B 3/4 1-i 3/4.1.2 BORATION SYSTEMS............................

B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES..................

B 3/4 1-4 BEAVER VALLEY -

UNIT 2 Amendment No. 124 IX

NPF-73 INDEX BASES SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS FQ(Z)

AND FXH............

3/4.2.4 3/4.2.5 QUADRANT POWER TILT RATIO....................

DNB PARAMETERS...............................

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..........

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.......................

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation.........

3/4.3.3.5 Remote Shutdown Instrumentation..............

3/4.3.3.8 Accident Monitoring Instrumentation..........

3/4.3.3.11 Explosive Gas Monitoring Instrumentation.....

PAGE B 3/4 2-1 B

B B

3/4 3/4 3/4 2-2 2-5 2-5 B 3/4 3-1 B 3/4 3-1 B

B B

B 3/4 3/4 3/4 3/4 3-10 3-11 3 -11 3-11 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION..................................

B 3/4 4-1 3/4.4.3 SAFETY VALVES................................

B 3/4 4-2 3/4.4.4 PRESSURIZER..................................

B 3/4 4-2 BEAVER VALLEY -

UNIT 2 Amendment No.124 X

NPF-73 INDEX BASES SECTION 3/4.4.5 3/4.4.6 3/4.4.8 3/4.4.9 3/4.4.11 STEAM GENERATORS...........................

REACTOR COOLANT SYSTEM LEAKAGE.............

SPECIFIC ACTIVITY..........................

PRESSURE/TEMPERATURE LIMITS................

REACTOR COOLANT SYSTEM RELIEF VALVES.......

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS...............................

3/4.5.2 AND 3/4.5.3 ECCS SUBSYSTEMS.....................

3/4.5.4 SEAL INJECTION FLOW........................

PA B

B B

B 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT........................

B 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.......

B 3/4.6.3 CONTAINMENT ISOLATION VALVES...............

B 3/4.6.4 COMBUSTIBLE GAS CONTROL....................

B 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..............................

B 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM.....

B GE 3/4 4-2 3/4 4-4 3/4 4-5 3/4 4-6 3/4 4-16 3/4 5-1 3/4 5-1 3/4 5-2 3/4 6-1 3/4 6-10 3/4 6-12 3/4 6-12 3/4 7-1 3/4 7-3 BEAVER VALLEY -

UNIT 2 Amendment No. 124 XI

NPF-73 BASES SECTION 3/4.7.4 3/4.7.5 3/4.7.7 3/4.7.8 INDEX B

B SERVICE WATER SYSTEM......................

ULTIMATE HEAT SINK........................

CONTROL ROOM EMERGENCY AIR CLEANUP AND PRESSURIZATION SYSTEM.....................

SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS)............................

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES..............................

3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS.........

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................

3/4.9.2 INSTRUMENTATION...........................

3/4.9.3 DECAY TIME................................

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...............................

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM....................................

3/4.9.10 AND 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL..............................

PAGE 3/4 3/4 7-3 7-3 B 3/4 7-4 B 3/4 7-5 B

B B

B 3/4 3/4 3/4 3/4 3/4 3/4 8-1 8-1 9-1 9-1 9-1 9-2 B 3/4 9-6 B 3/4 9-7 B 3/4 9-7 BEAVER VALLEY -

UNIT 2 Amendment No. -

24 XII

NPF-73 INDEX FUEL BUILDING VENTILATION SYSTEM..........

FUEL STORAGE -

SPENT FUEL STORAGE POOL....

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.......................

3/4.10.3 PHYSICS TESTS.............................

3/4.10.4 REACTOR COOLANT LOOPS.....................

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS..........................

3/4.11.2 GASEOUS EFFLUENTS.........................

B 3/4 10-1 B

B B

3/4 3/4 3/4 10-1 10-1 10-1 B 3/4 11-i B 3/4 11-1 DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION......................................

5-1 5.2 REACTOR CORE.......................................

5.3 FUEL STORAGE.......................................

5-1 5-1 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.....................................

6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS..........

BEAVER VALLEY -

UNIT 2 BASES SECTION 3/4.9.12 3/4.9.14 PAGE B 3/4 B 3/4 9-8 9-9 6-1 Amendment No. ]24 XIII

REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS 3/4.1.2.1 -

3/4.1.2.7 (These Specification numbers are not used.)

BEAVER VALLEY -

UNIT 2 3/4 1-7 (Next Page is 3/4 1-15)

Amendment No. 124

NPF-73 REACTIVITY CONTROL SYSTEMS Refueling Water Storage Tank (RWST)

LIMITING CONDITION FOR OPERATION 3.1.2.8 The RWST shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 & 4.

ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 The RWST shall be verified OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration is between 2,000 and 2100 ppm, and

2.

Verifying a minimum usable volume of 859,248 gallons.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST solution temperature is 2

45 0F and

50OF when the RWST ambient air temperature is

> 50OF or < 45 0 F.

BEAVER VALLEY -

UNIT 2 3/4 1-15 (Next page is 3/4 1-17)

Amendment No. 124

NPF-73 REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS -

OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Position Indication System shall be OPERABLE and capable of determining the control rod positions within +/- 12 steps.

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With a maximum of one digital rod position indicator per bank inoperable either:

1.

Determine the position of the nonindicating rod(s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With a maximum of one demand position indicator per bank inoperable either:

1.

Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or

2.

Reduce THERMAL POWER to less than 50%

of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.2.1 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.1.3.2.2 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps over the full-range of indicated rod travel at least once per 18 months.

BEAVER VALLEY -

UNIT 2 Amendment No. 124 3/4 1-21

REACTIVITY CONTROL SYSTEMS 3/4.1.3.3 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 2 Amendment No. 124 3/4 1-22

NPF-73 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABLE MODES SETPOINT(3)

MEASUREMENT RANGE

1. AREA MONITORS

a.

Deleted

b.

Containment Area (2RMR-RQ206

& 207)

c.

Control Room Area (2RMC-RQ201

& 202) 2 1,2,3 & 4 2

1,2,3,4, and (4)

<2.0 x 10 4R/hr

<0.476 mR/hr 1 to 107 R/hr 10- 2 to 103 mR/hr

2.

PROCESS MONITORS

a.

Containment

i.

Gaseous Activity (Xe-133)

RCS Leakage Detection (2RMR-RQ303B) ii.

Particulate Activity (1-131)

RCS Leakage Detection (2RMR-RQ303A)

b.

Deleted 1

1,2,3 & 4 1,2,3 & 4 N/A N/A 10-6 to 10- 1lCi/cc 10-to 10-5 [JCi/cc BEAVER VALLEY -

UNIT 2 35 46,47 20 20 ACTION Amendment No.124 3/4 3-40

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE

2. PROCESS MONITORS (Continued)

c. Noble Gas and Effluent Monitors

i.

Deleted APPLICABLE MODES SETPOINT(

3 )

MEASUREMENT RANGE ii.

Containment Purge Exhaust (Xe-133)

(2HVR-RQl04A & B) iii.

Main Steam Discharge (Kr-88)

(2MSS-RQI01A,B & C) 2

. 01x10 -3 Ci/cc (5) l/SG 1,2,3&4

3.9xl0 -2Ci/cc 10- 6 to 10- 1aCi/cc 10-2 to 103 JCi/cc BEAVER VALLEY -

UNIT 2 ACTION 22 35 NPF-73 Amendment No. 124 3/4 3-41

NPF-73 TABLE 3.3-6 (Continued)

TABLE NOTATIONS (1) Not used.

(2)

Not used.

(3)

Above background.

(4)

During movement of recently irradiated fuel assemblies and during movement of fuel assemblies over recently irradiated fuel assemblies.

(5)

During movement of recently irradiated fuel assemblies within the containment and during movement of fuel assemblies over recently irradiated fuel assemblies within the containment.

ACTION STATEMENTS ACTION 20 ACTION 21 ACTION 22 ACTION 35 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

This Action is not used.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1)

Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and

2)

Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a

timely manner.

BEAVER VALLEY -

UNIT 2 Amendment No.124 3/4 3-42

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED

1.

AREA MONITORS

a.

Deleted

b.

Containment Area (2RMR-RQ206

& 207)

c.

Control Room Area (2RMC-RQ201

& 202)

S S

R R

M M

1, 2,

3, 4

1, 2,

3, 4,

and ##

2.

PROCESS MONITORS

a.

Containment

i.

Gaseous Activity RCS Leakage Detection (2RMR-RQ303B) ii.

Particulate Activity RCS Leakage Detection (2RMR-RQ303A)

S S

M M

1, 2, 3 & 4 1, 2, 3 & 4

b.

Deleted

Surveillance interval may be extended to the upcoming refueling outage if the between refueling outages is greater than 18 months.

1. During movement of recently irradiated fuel assemblies and during movement of assemblies over recently irradiated fuel assemblies.

interval fuel BEAVER VALLEY -

UNIT 2 Amendment No. 124 3/4 3-43

TABLE 4.3-3 (Continued)

CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST REQUIRED INSTRUMENT

2.

PROCESS MONITORS (Continued)

c.

Noble Gas Effluent Monitors

i.

Deleted ii.

Containment Purge Exhaust (2HVR-RQI04A

& B) iii.

Main Steam Discharge (2MSS-RQI01A, B & C)

S S

R R

M M

1, 2, 3 & 4 During movement of recently irradiated fuel assemblies within the containment and during movement of fuel assemblies over recently irradiated fuel assemblies within the containment.

BEAVER VALLEY -

UNIT 2 (Continued)

TABLE 4.3-3 Amendment No ]24 3/4 3-44

REACTOR COOLANT SYSTEM 3/4.4.2 (This Specification number is not used.)

BEAVER VALLEY -

UNIT 2 Amendment No. ]24 3/4 4-8

REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting*

of 2485 psig + 1% -

3%.**

APPLICABILITY:

MODES 1, 2, and 3, With all RCS cold leg temperatures the enable temperature specified in 3.4.9.3.

ACTION:

a.

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN with any RCS cold leg temperature

the enable temperature specified in 3.4.9.3 and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

After any pressurizer code safety valve lift, as indicated by the safety valve position indicator, involving loop seal or water discharge; be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN with any RCS cold leg temperature

the enable temperature specified in 3.4.9.3 and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3 No additional requirements other than those required by Specification 4.0.5.

The lift setting shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

- Within +/- 1% following pressurizer code safety valve testing.

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UNIT 2 Amendment No. 124 3/4 4-9

REACTOR COOLANT SYSTEM 3/4.4.7 (This Specification number is not used.)

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Amendment No. 124

NPF-73 REACTOR COOLANT SYSTEM 3/4.4.9.2 (This Specification number is not used.)

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UNIT 2 Amendment No. 124 3/4 4-34

REACTOR COOLANT SYSTEM 3/4.4.10 (This Specification number is not used.)

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UNIT 2 3/4 4-38 Amendment No. 124

NPF-73 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT QUENCH SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two separate and independent containment quench spray subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3,

and 4.

ACTION:

With one containment quench spray subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment quench spray subsystem shall be demonstrated OPERABLE:

a.

By verifying, at least once per 31 days, that each valve (manual, power operated or automatic) in the flow path that is not

locked, sealed, or otherwise secured in position, is in its correct position.

b.

By verifying, at the frequency specified in the Inservice Testing Program, that each quench spray pump's developed head at the flow test point is greater than or equal to the required developed head as specified in the Inservice Testing Program and the Containment Integrity Safety Analysis.

c.

At least once per 18 months by:

1.

Cycling each power operated (excluding automatic) valve in the flow path through at least one complete cycle of full travel.

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UNIT 2 Amendment No. ]24 3/4 6-10

PLANT SYSTEMS 3/4.7.2 (This Specification number is not used.)

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UNIT 2 Amendment No.

124 3/4 7-10

PLANT SYSTEMS 3/4.7.6 (This Specification number is not used.)

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UNIT 2 Amendment No.

124 3/4 7-14

REFUELING OPERATIONS 3/4.9.5 -

3/4.9.7 (These Specification numbers are not used.)

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UNIT 2 3/4 9-5 (Next Page is 3/4 9-8)

Amendment No. 124

ML020250280

Text

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