Text

Markup of Proposed Technical Specification Pages
	ML25357A076
Person / Time
Site:	Dresden, Peach Bottom, Clinton, Quad Cities, LaSalle
Issue date:	12/23/2025
From:	; Constellation Energy Generation
To:	; Document Control Desk
Shared Package
ML25357A073	List: ML25357A075; ML25357A076; ML25357A077; RS-25-164, Constellation - License Amendment Request to Eliminate Technical Specification for Automatic MSIV Closure on High Temperature and Add New Technical Specification, Main Steam Line (MSL) Area Temperature;
References
	RS-25-164
	Download: ML25357A076 (0)
	v • d • e

ATTACHMENT 2a License Amendment Request Clinton Power Station, Unit 1 Docket No. 50-461 Markup of Proposed Technical Specification Pages

Subject:

License Amendment Request for Proposed Changes to the Technical Specification Primary Containment and Drywell Isolation Instrumentation Tables and New Main Steam Line (MSL) Area Temperature Technical Specification List of TS pages:

vi 3.3-55 3.7-16 3.7-17 3.7-18

V TABLE OF CONTENTS (continued) 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 B 3.7 B 3.7.1 B 3.7.2 B 3.7.3 B 3.7.4 B 3.7.5 B 3.7.6 B 3.7.7 3.8 3.8.l 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 3.8.10 B 3.8 B 3.8.l B 3.8.2 B 3.8.3 B 3.8.4 B 3.8.5 B 3.8.6 B 3.8.7 B 3.8.8 B 3.8.9 B 3.8.10 CLINTON PLANT SYSTEMS.......................

Division 1 and 2 Shutdown Service Water (SX) Subsystems and Ultimate Heat Sink (UHS)...

Division 3 Shutdown Service Water (SX)

Subsystem..........

Control Room Ventilation System.

Control Room Air Conditioning (AC) System.......

Main Condenser Offgas........

Main Turbine Bypass System.

Fuel Pool Water Level PLANT SYSTEMS.......................

Division 1 and 2 Shutdown Service Water (SX)

Subsystems and Ultimate Heat Sink (UHS)......

Divisi9n 3 Shutdown Service Water Subsystem (SX}.

Control Room Ventilation System.....

Control Room Air Conditioning (AC) System Main Condenser Offgas........

Main Turbine Bypass System............

Fuel Pool Water Level ELECTRICAL POWER SYSTEMS....

AC Sources-Operating......

AC Sources-Shutdown..................

Diesel Fuel Oil, Lube Oil, and Starting Air......

DC Sources-Operating.

DC Sources-Shutdown...

Battery Cell Parameters..

Inverters-Operating........

Inverters-Shutdown.....

Distribution Systems-Operating............

Distribution Systems-Shutdown ELECTRICAL POWER SYSTEMS...

AC Sources-Operating..

AC Sources-Shutdown...

Diesel Fuel Oil, Lube Oil, and Starting Air DC Sources-Operating..

DC Sources-Shutdown...

Battery Cell Parameters.........

Inverters-Operating...

Inverters-Shutdown.........

Distribution Systems-Operating...

Distribution Systems-Shutdown....

3.7-1 3.7-1 3.7-3 3.7-4 3.7-8 3.7-11 3.7-13 3.7-14 B 3.7-1 B 3.7-1 B 3.7-7 B 3.7-10 B 3.7-17 B 3.7-22 B 3.7-25 B 3.7-28 3.8-1 3.8-1 3.8-16 3.8-20 3.8-24 3.8-27 3.8-30 3.8-34 3.8-36 3.8-39 3.8-42 B 3.8-1 B 3.8-1 B 3.8-33 B 3.8-40 B 3.8-49 B 3.8-58 B 3.8-62 B 3.8-69 B 3.8-74 B 3.8-78 B 3.8-89 (continued) vi Revision No. O Insert "3.7.8 Main Steam Line (MSL) Area Temperature.............. 3.7-16" Insert "B 3.7.8 Main Steam Line (MSL) Area Temperature.......... B 3.7-39"

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-55 Amendment No. 169 Table 3.3.6.1-1 (page 1 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.

Main Steam Line Isolation

a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8

-148.1 inches

b. Main Steam Line Pressure-Low 1

4 H

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 841 psig

c. Main Steam Line Flow-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 284 psid

d. Condenser Vacuum-Low 1,2(a),

3(a) 4 G

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7.6 inches Hg vacuum

e. Main Steam Tunnel Temperature-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

f. Main Steam Line Turbine Building Temperature-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 Modules 1-4 142°F, Module 5 150°F

g. Manual Initiation 1,2,3 4

J SR 3.3.6.1.6 NA (continued)

(a)

With any turbine stop valve not closed.

Insert "Deleted" Insert "Deleted"

MSL Area Temperature 3.7.8 Clinton Power Station 3.7-16 Amendment 3.7 PLANT SYSTEMS 3.7.8 Main Steam Line (MSL) Area Temperature LCO 3.7.8 The MSL Area temperature for each area in Table 3.7.8-1 shall be less than or equal to the limit APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each MSL area.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MSL Area temperature greater than the limit in Table 3.7.8-1 A.1 Initiate action to verify there is no leakage from the MSL pressure boundary.

AND A.2 Verify there is no leakage from the MSL pressure boundary.

Immediately Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.

Required Action and associated Completion Time not met B.1 Be in MODE 3.

AND B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

MSL Area Temperature 3.7.8 Clinton Power Station 3.7-17 Amendment SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify each MSL area temperature is less than or equal to the limit in Table 3.7.8-1 In accordance with the Surveillance Frequency Control Program

MSL Area Temperature 3.7.8 Clinton Power Station 3.7-18 Amendment Table 3.7.8-1 (page 1 of 1)

Main Steam Line Area Temperature Limits MSL Area Temperature Limit

1. Main Steam Line Tunnel Temperature - High 171 °F

2. Main Steam Line Turbine Building Temperature - High (Modules 1-4) 142 °F

3. Main Steam Line Turbine Building Temperature - High (Module 5) 150 °F

ATTACHMENT 2b License Amendment Request Dresden Nuclear Power Station, Units 2 and 3 Docket No. 50-237 and 50-249 Markup of Proposed Technical Specification Pages

Subject:

License Amendment Request for Proposed Changes to the Technical Specification Primary Containment Isolation Instrumentation Tables and New Main Steam Line (MSL) Area Temperature Technical Specification List of TS pages:

iii 3.3.6.1-6 3.7.9-1 3.7.9-2 3.7.9-3

Dresden 2 and 3 iii Revision 1 TABLE OF CONTENTS (continued) 3.7 PLANT SYSTEMS 3.7.1 Containment Cooling Service Water (CCSW) System................................................... 3.7.1-1 3.7.2 Diesel Generator Cooling Water (DGCW) System......................................................... 3.7.2-1 3.7.3 Ultimate Heat Sink (UHS).............................................................................................. 3.7.3-1 3.7.4 Control Room Emergency Ventilation (CREV) System.................................................. 3.7.4-1 3.7.5 Control Room Emergency Ventilation Air Conditioning (AC) System............................................................................................ 3.7.5-1 3.7.6 Main Condenser Offgas................................................................................................. 3.7.6-1 3.7.7 Main Turbine Bypass System........................................................................................ 3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level............................................................................ 3.7.8-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC SourcesOperating................................................................................................. 3.8.1-1 3.8.2 AC SourcesShutdown................................................................................................ 3.8.2-1 3.8.3 Diesel Fuel Oil and Starting Air...................................................................................... 3.8.3-1 3.8.4 DC SourcesOperating................................................................................................. 3.8.4-1 3.8.5 DC SourcesShutdown................................................................................................ 3.8.5-1 3.8.6 Battery Parameters....................................................................................................... 3.8.6-1 3.8.7 Distribution SystemsOperating................................................................................. 3.8.7-1 3.8.8 Distribution SystemsShutdown................................................................................. 3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks.................................................................................... 3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock......................................................................... 3.9.2-1 3.9.3 Control Rod Position..................................................................................................... 3.9.3-1 3.9.4 Control Rod Position Indication.................................................................................... 3.9.4-1 3.9.5 Control Rod OPERABILITYRefueling........................................................................... 3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water LevelIrradiated Fuel................................................................................................. 3.9.6-1 3.9.7 Reactor Pressure Vessel (RPV) Water LevelNew Fuel or Control Rods.................................................................................................... 3.9.7-1 3.9.8 Shutdown Cooling (SDC)High Water Level................................................................ 3.9.8-1 3.9.9 Shutdown Cooling (SDC)Low Water Level................................................................. 3.9.9-1 3.10 SPECIAL OPERATIONS 3.10.1 Reactor Mode Switch Interlock Testing........................................................................ 3.10.1-1 3.10.2 Single Control Rod WithdrawalHot Shutdown.......................................................... 3.10.2-1 3.10.3 Single Control Rod WithdrawalCold Shutdown......................................................... 3.10.3-1 3.10.4 Single Control Rod Drive (CRD)

RemovalRefueling.................................................................................................... 3.10.4-1 3.10.5 Multiple Control Rod WithdrawalRefueling.............................................................. 3.10.5-1 3.10.6 Control Rod TestingOperating................................................................................... 3.10.6-1 3.10.7 SHUTDOWN MARGIN (SDM) TestRefueling.............................................................. 3.10.7-1 3.10.8 Inservice Leak and Hydrostatic Testing Operation........................................................ 3.10.8-1 (continued)

Insert "3.7.9 Main Steam Line (MSL) Area Temperature......................................... 3.7.9-1"

FUN CT ION

1.

Main Stea!'l Line Isolation

a.

Reactor Vessel Water Level-Low Low

b.

Main Steam Line Pressure-Low

c.

Main Steam Pressure****Timer

d.

~ain Steam Line Fl ow-~i gr

e.

Main Steam Line Tunnel Temperature-High

2.

Primary Containment Isolation

a.

Reactor Vessel Water Level-Low

~.

Drywell Pressure-High

c.

Drywel l Radiation-High Dresden 2 and 3 Table Primary Containment Isolation Instrumentation

3. 3. 6.1 3.3.6. :-1 (page of Primary Containment Isolation InstrJmenta;;1on APPL! CAB LE CONDI TI ON S t'OJES OR REQUIRED REFERENCED OTHER CbANNELS FROM SPECIF !ED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SYSTEM ACT:O~ c.1 REQUIREMENTS VALUE 1,2,3 2

D SR 3.3.6.1.1

~ 56.34 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.2

~ 791 psig SR 3.3.6.1.4 SR 3.3.6.1.7 E

SR 3.3.6.1.2 0.280 SR 3.3.6.1.6 seconds SR 3.3.6.1.7 (Unit 2)

$ 0.236 secorcs (Unit 3) 1, 2. 3 2 per 0

SR 3.3.6.1.l

$ 259.2 psid MSL SR 3.3.6.1.2 (Unit 2)

SR 3.3.6.1.4

$ 252.6 psid SR 3.3.6.. 7 (Unit 3) 1'2'3 per trip D

SR 3.3.6.1.5 s 200°F string s' 3.3.6.1.6 SR 3.3.6.1.7

,2,3 2

G SR 3.3.6.1.1 2.65 inches SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7

1. 2 '3 2

G SR 3.3.6.1.2

.94 psi g SR 3.3 6.1.4 SR 3 3.6.

7 1'2,3 s~ 3.3.6.1.1

,;; 17 R/hr SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.

(continued) 3.3.6.1-6 Amendment No.237 I 230 Insert "Deleted"

MSL Area Temperature 3.7.9 Dresden 2 and 3 3.7.9-1 Amendment 3.7 PLANT SYSTEMS 3.7.9 Main Steam Line (MSL) Area Temperature LCO 3.7.9 The MSL Area temperature for each area in Table 3.7.9-1 shall be less than or equal to the limit APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

MSL Area temperature greater than the limit in Table 3.7.9-1.

A.1 Initiate action to verify there is no leakage from the MSL pressure boundary.

AND A.2 Verify there is no leakage from the MSL pressure boundary.

Immediately Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE. 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

MSL Area Temperature 3.7.9 Dresden 2 and 3 3.7.9-2 Amendment SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify each MSL area temperature is less than or equal to the limit in Table 3.7.9-1.

In accordance with the Surveillance Frequency Control Program

MSL Area Temperature 3.7.9 Dresden 2 and 3 3.7.9-3 Amendment Table 3.7.9-1 (page 1 of 1)

Main Steam Line Area Temperature Limits MSL Area Temperature Limit Main Steam Line Tunnel Temperature 200°F

ATTACHMENT 2c License Amendment Request LaSalle County Station, Units 1 and 2 Docket No. 50-373 and 50-374 Markup of Proposed Technical Specification Pages

Subject:

License Amendment Request for Proposed Changes to the Technical Specification Primary Containment Isolation Instrumentation Tables and New Main Steam Line (MSL) Area Temperature Technical Specification List of TS pages:

iii 3.3.6.1-1 3.3.6.1-6 3.7.9-1 3.7.9-2 3.7.9-3

LaSalle 1 and 2 iii Revision 0 TABLE OF CONTENTS (continued) 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System.......3.7.1-1 3.7.2 Diesel Generator Cooling Water (DGCW) System.............3.7.2-1 3.7.3 Ultimate Heat Sink (UHS).................................3.7.3-1 3.7.4 Control Room Area Filtration (CRAF) System...............3.7.4-1 3.7.5 Control Room Area Ventilation Air Conditioning (AC) System...............................3.7.5-1 3.7.6 Main Condenser Offgas....................................3.7.6-1 3.7.7 Main Turbine Bypass System...............................3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level......................3.7.8-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC SourcesOperating.....................................3.8.1-1 3.8.2 AC SourcesShutdown......................................3.8.2-1 3.8.3 Diesel Fuel Oil and Starting Air.........................3.8.3-1 3.8.4 DC SourcesOperating.....................................3.8.4-1 3.8.5 DC SourcesShutdown......................................3.8.5-1 3.8.6 Battery Parameters.......................................3.8.6-1 3.8.7 Distribution SystemsOperating...........................3.8.7-1 3.8.8 Distribution SystemsShutdown............................3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks...........................3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock....................3.9.2-1 3.9.3 Control Rod Position.....................................3.9.3-1 3.9.4 Control Rod Position Indication..........................3.9.4-1 3.9.5 Control Rod OPERABILITYRefueling........................3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water LevelIrradiated Fuel...................................................3.9.6-1 3.9.7 Reactor Pressure Vessel (RPV) Water LevelNew Fuel or Control Rods...................................3.9.7-1 3.9.8 Residual Heat Removal (RHR)High Water Level.............3.9.8-1 3.9.9 Residual Heat Removal (RHR)Low Water Level..............3.9.9-1 3.10 SPECIAL OPERATIONS 3.10.1 Reactor Mode Switch Interlock Testing....................3.10.1-1 3.10.2 Single Control Rod WithdrawalHot Shutdown...............3.10.2-1 3.10.3 Single Control Rod WithdrawalCold Shutdown..............3.10.3-1 3.10.4 Single Control Rod Drive (CRD)

RemovalRefueling......................................3.10.4-1 3.10.5 Multiple Control Rod WithdrawalRefueling................3.10.5-1 3.10.6 Control Rod TestingOperating............................3.10.6-1 3.10.7 SHUTDOWN MARGIN (SDM) TestRefueling.....................3.10.7-1 3.10.8 Inservice Leak and Hydrostatic Testing Operation.........3.10.8-1 (continued)

Insert "3.7.9 Main Steam Line (MSL) Area Temperature.............. 3.7.9-1"

Primary Containment Isolation Instrumentation 3.3.6.1 LaSalle 1 and 2 3.3.6.1-1 Amendment No. 259/244 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.1-1.

ACTIONS

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

1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each channel.

3.

For Function 1.e, when automatic isolation capability is inoperable for required Reactor Building Ventilation System corrective maintenance, filter changes, damper cycling, or required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.

For Function 1.e, when automatic isolation capability is inoperable due to loss of reactor building ventilation or for performance of SR 3.6.4.1.3 or SR 3.6.4.1.4, entry into associated Conditions and Required Action may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

A.1 Place channel in trip.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or in accordance with the Risk Informed Completion Time Program for Functions 2.b, 2.f, and 5.a (continued)

Primary Containment Isolation Instrumentation 3.3.6.1 LaSalle 1 and 2 3.3.6.1-6 Amendment No.169/155 Table 3.3.6.1-1 (page 1 of 4)

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

1. Main Steam Line Isolation

a. Reactor Vessel Water LevelLow Low Low, Level 1 1,2,3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5

-137.0 inches

b. Main Steam Line PressureLow 1

2 E

SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 826.5 psig

c. Main Steam Line FlowHigh 1,2,3 2 per MSL D

SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 128.0 psid

d. Condenser VacuumLow 1,2(a),

3(a) 2 D

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 3.8 inches Hg vacuum

e. Main Steam Line Tunnel Differential TemperatureHigh 1,2,3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 66.4F

f. Manual Initiation 1,2,3 2

G SR 3.3.6.1.5 NA

2. Primary Containment Isolation

a. Reactor Vessel Water LevelLow Low, Level 2 1,2,3 2

H SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5

-58.0 inches

b. Drywell PressureHigh 1,2,3 2

H SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 1.93 psig

c. Reactor Building Ventilation Exhaust Plenum RadiationHigh 1,2,3 2

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 42.0 mR/hr

d. Fuel Pool Ventilation Exhaust RadiationHigh 1,2,3 2

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 42.0 mR/hr (continued)

(a) With any turbine stop valve not closed.

Insert "Deleted"

MSL Area Temperature 3.7.9 LaSalle 1 and 2 3.7.9-1 Amendment 3.7 PLANT SYSTEMS 3.7.9 Main Steam Line (MSL) Area Temperature LCO 3.7.9 The MSL Area temperature for each area in Table 3.7.9-1 shall be less than or equal to the limit APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

MSL Area temperature greater than the limit in Table 3.7.9-1 A.1 Initiate action to verify there is no leakage from the MSL pressure boundary.

AND A.2 Verify there is no leakage from the MSL pressure boundary.

Immediately Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.

Required Action and associated Completion Time not met B.1 Be in MODE 3.

AND B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

MSL Area Temperature 3.7.9 LaSalle 1 and 2 3.7.9-2 Amendment SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify each MSL area temperature is less than or equal to the limit in Table 3.7.9-1 In accordance with the Surveillance Frequency Control Program

MSL Area Temperature 3.7.9 LaSalle 1 and 2 3.7.9-3 Amendment Table 3.7.9-1 (page 1 of 1)

Main Steam Line Area Temperature Limits MSL Area Temperature Limit Main Steam Line Tunnel Differential Temperature 66.4 °F

ATTACHMENT 2d License Amendment Request Peach Bottom Atomic Power Station, Unit 2 Docket No. 50-277 Markup of Proposed Technical Specification Pages

Subject:

License Amendment Request for Proposed Changes to the Technical Specification Primary Containment Isolation Instrumentation Tables and New Main Steam Line (MSL) Area Temperature Technical Specification List of TS pages:

iii 3.3-52 3.7-15 3.7-16 3.7-17

LICENSEE-CONTROLLED TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.6 Main Turbine Bypass System............................ 3.7-12 3.7.7 Spent Fuel Storage Pool Water Level................... 3.7-14 3.8 ELECTRICAL POWER SYSTEMS.................................. 3.8-1 3.8.1 AC Sources Operating................................. 3.8-1 3.8.2 AC Sources Shutdown.................................. 3.8-20 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air........... 3.8-25 3.8.4 DC Sources Operating................................. 3.8-28 3.8.5 DC Sources Shutdown.................................. 3.8-34 3.8.6 Battery Cell Parameters............................... 3.8-37 3.8.7 Distribution Systems Operating....................... 3.8-41 3.8.8 Distribution Systems Shutdown........................ 3.8-44 3.9 REFUELING OPERATIONS...................................... 3.9-1 3.9.1 Refueling Equipment Interlocks........................ 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock................. 3.9-3 3.9.3 Control Rod Position.................................. 3.9-5 3.9.4 Control Rod Position Indication....................... 3.9-6 3.9.5 Control Rod OPERABILITY Refueling.................... 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level............. 3.9-9 3.9.7 Residual Heat Removal (RHR) High Water Level......... 3.9-10 3.9.8 Residual Heat Removal (RHR) Low Water Level.......... 3.9-13 3.10 SPECIAL OPERATIONS........................................ 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation...... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing................. 3.10-4 3.10.3 Single Control Rod Withdrawal Hot Shutdown........... 3.10-6 3.10.4 Single Control Rod Withdrawal Cold Shutdown.......... 3.10-9 3.10.5 Single Control Rod Drive (CRD)

Removal Refueling................................. 3.10-13 3.10.6 Multiple Control Rod Withdrawal Refueling............ 3.10-16 3.10.7 Control Rod Testing Operating........................ 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test Refueling................. 3.10-20 4.0 DESIGN FEATURES............................................... 4.0-1 4.1 Site 4.0-1 4.2 Reactor Core.............................................. 4.0-1 4.3 Fuel Storage.............................................. 4.0-2 5.0 ADMINISTRATIVE CONTROLS....................................... 5.0-1 5.1 Responsibility............................................ 5.0-1 5.2 Organization.............................................. 5.0-2 5.3 Unit Staff Qualifications................................. 5.0-5 5.4 Procedures................................................ 5.0-6 5.5 Programs and Manuals...................................... 5.0-7 5.6 Reporting Requirements.................................... 5.0-18 5.7 High Radiation Areas...................................... 5.0-22 PBAPS UNIT 2 iii Amendment No. 330 LICENSEE-CONTROLLED Insert "3.7.8 Main Steam Line (MSL) Area Temperature...... 3.7-15

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

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

1. Main Steam Line Isolation

a. Reactor Vessel Water Level Low Low Low (Level 1) 1,2,3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

-160.0 inches

b. Main Steam Line Pressure Low 1

2 E

SR 3.3.6.1.3 SR 3.3.6.1.7 825.0 psig

c. Main Steam Line Flow High 1,2,3 2 per MSL D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 173.8 psid

d. Deleted

e. Turbine Building Main Steam Tunnel Temperature High 1,2,3 6

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 200.0°F

f. Reactor Building Main Steam Tunnel Temperature-High 1,2,3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 230.0°F

2. Primary Containment Isolation

a. Reactor Vessel Water Level Low (Level 3) 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 1.0 inches

b. Drywell Pressure High 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 2.0 psig

c. Main Stack Monitor Radiation High 1,2,3 1

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.7 2 X 10-2

µCi/cc

d. Reactor Building Ventilation Exhaust Radiation High 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.3 SR 3.3.6.1.7 16.0 mR/hr

e. Refueling Floor Ventilation Exhaust Radiation High 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.3 SR 3.3.6.1.7 16.0 mR/hr (continued)

PBAPS UNIT 2 3.3-52 Amendment No. 299 Insert "Deleted" Insert "Deleted"

MSL Area Temperature 3.7.8 Peach Bottom Unit 2 3.7-15 Amendment 3.7 PLANT SYSTEMS 3.7.8 Main Steam Line (MSL) Area Temperature LCO 3.7.8 The MSL Area temperature for each area in Table 3.7.8-1 shall be less than or equal to the limit APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each MSL area.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MSL Area temperature greater than the limit in Table 3.7.8-1 A.1 Initiate action to verify there is no leakage from the MSL pressure boundary.

AND A.2 Verify there is no leakage from the MSL pressure boundary.

Immediately Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.

Required Action and associated Completion Time not met B.1 Be in MODE 3.

AND B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

MSL Area Temperature 3.7.8 Peach Bottom Unit 2 3.7-16 Amendment SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify each MSL area temperature is less than or equal to the limit in Table 3.7.8-1 In accordance with the Surveillance Frequency Control Program

MSL Area Temperature 3.7.8 Peach Bottom Unit 2 3.7-17 Amendment Table 3.7.8-1 (page 1 of 1)

Main Steam Line Area Temperature Limits MSL Area Temperature Limit

1. Turbine Building Main Steam Line Tunnel Temperature - High 200 °F

2. Reactor Building Main Steam Line Tunnel Temperature - High 230 °F

ATTACHMENT 2e License Amendment Request Peach Bottom Atomic Power Station, Unit 3 Docket No. 50-278 Markup of Proposed Technical Specification Pages

Subject:

License Amendment Request for Proposed Changes to the Technical Specification Primary Containment Isolation Instrumentation Tables and New Main Steam Line (MSL) Area Temperature Technical Specification List of TS pages:

iii 3.3-52 3.7-15 3.7-16 3.7-17

LICENSEE-CONTROLLED TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.6 Main Turbine Bypass System............................ 3.7-12 3.7.7 Spent Fuel Storage Pool Water Level................... 3.7-14 3.8 ELECTRICAL POWER SYSTEMS.................................. 3.8-1 3.8.1 AC Sources Operating................................. 3.8-1 3.8.2 AC Sources Shutdown.................................. 3.8-20 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air........... 3.8-25 3.8.4 DC Sources Operating................................. 3.8-28 3.8.5 DC Sources Shutdown.................................. 3.8-34 3.8.6 Battery Cell Parameters............................... 3.8-37 3.8.7 Distribution Systems Operating....................... 3.8-41 3.8.8 Distribution Systems Shutdown........................ 3.8-44 3.9 REFUELING OPERATIONS...................................... 3.9-1 3.9.1 Refueling Equipment Interlocks........................ 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock................. 3.9-3 3.9.3 Control Rod Position.................................. 3.9-5 3.9.4 Control Rod Position Indication....................... 3.9-6 3.9.5 Control Rod OPERABILITY Refueling.................... 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level............. 3.9-9 3.9.7 Residual Heat Removal (RHR) High Water Level......... 3.9-10 3.9.8 Residual Heat Removal (RHR) Low Water Level.......... 3.9-13 3.10 SPECIAL OPERATIONS........................................ 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation...... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing................. 3.10-4 3.10.3 Single Control Rod Withdrawal Hot Shutdown........... 3.10-6 3.10.4 Single Control Rod Withdrawal Cold Shutdown.......... 3.10-9 3.10.5 Single Control Rod Drive (CRD)

Removal Refueling................................. 3.10-13 3.10.6 Multiple Control Rod Withdrawal Refueling............ 3.10-16 3.10.7 Control Rod Testing Operating........................ 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test Refueling................. 3.10-20 4.0 DESIGN FEATURES............................................... 4.0-1 4.1 Site

................................................... 4.0-1 4.2 Reactor Core.............................................. 4.0-1 4.3 Fuel Storage.............................................. 4.0-2 5.0 ADMINISTRATIVE CONTROLS....................................... 5.0-1 5.1 Responsibility............................................ 5.0-1 5.2 Organization.............................................. 5.0-2 5.3 Unit Staff Qualifications................................. 5.0-5 5.4 Procedures................................................ 5.0-6 5.5 Programs and Manuals...................................... 5.0-7 5.6 Reporting Requirements.................................... 5.0-19 5.7 High Radiation Areas...................................... 5.0-23 PBAPS UNIT 3 iii Amendment No. 333 LICENSEE-CONTROLLED Insert "3.7.8 Main Steam Line (MSL) Area Temperature........ 3.7-15"

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

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

1.

Main Steam Line Isolation

a. Reactor Vessel Water Level Low Low Low (Level 1) 1,2,3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

-160.0 inches

b. Main Steam Line Pressure Low 1

2 E

SR 3.3.6.1.3 SR 3.3.6.1.7 825.0 psig

c. Main Steam Line Flow High 1,2,3 2 per MSL D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 173.8 psid

d. Deleted

e. Main Steam Tunnel Temperature High 1,2,3 8

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 200.0°F

2. Primary Containment Isolation

a. Reactor Vessel Water Level Low (Level 3) 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 1.0 inches

b. Drywell Pressure High 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 2.0 psig

c. Main Stack Monitor Radiation High 1,2,3 1

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.7 2 X 10-2

µCi/cc

d. Reactor Building Ventilation Exhaust Radiation High 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.3 SR 3.3.6.1.7 16.0 mR/hr

e. Refueling Floor Ventilation Exhaust Radiation High 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.3 SR 3.3.6.1.7 16.0 mR/hr (continued)

PBAPS UNIT 3 3.3-52 Amendment No. 302 Insert "Deleted"

MSL Area Temperature 3.7.8 Peach Bottom Unit 3 3.7-15 Amendment 3.7 PLANT SYSTEMS 3.7.8 Main Steam Line (MSL) Area Temperature LCO 3.7.8 The MSL Area temperature for each area in Table 3.7.8-1 shall be less than or equal to the limit APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

MSL Area temperature greater than the limit in Table 3.7.8-1 A.1 Initiate action to verify there is no leakage from the MSL pressure boundary.

AND A.2 Verify there is no leakage from the MSL pressure boundary.

Immediately Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.

Required Action and associated Completion Time not met B.1 Be in MODE 3.

AND B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

MSL Area Temperature 3.7.8 Peach Bottom Unit 3 3.7-16 Amendment SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify each MSL area temperature is less than or equal to the limit in Table 3.7.8-1 In accordance with the Surveillance Frequency Control Program

MSL Area Temperature 3.7.8 Peach Bottom Unit 3 3.7-17 Amendment Table 3.7.8-1 (page 1 of 1)

Main Steam Line Area Temperature Limits MSL Area Temperature Limit Main Steam Tunnel Temperature - High 200 °F

ATTACHMENT 2f License Amendment Request Quad Cities Nuclear Power Station, Units 1 and 2 Docket No. 50-254 and 50-265 Markup of Proposed Technical Specification Pages

Subject:

License Amendment Request for Proposed Changes to the Technical Specification Primary Containment Isolation Instrumentation Tables and New Main Steam Line (MSL) Area Temperature Technical Specification List of TS pages:

iii 3.3.6.1-6 3.7.10-1 3.7.10-2 3.7.10-3

Quad Cities 1 and 2 iii Revision 1 TABLE OF CONTENTS (continued) 3.6 CONTAINMENT SYSTEMS (continued) 3.6.4.1 Secondary Containment................................................................................................ 3.6.4.1-1 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)......................................................... 3.6.4.2-1 3.6.4.3 Standby Gas Treatment (SGT) System.......................................................................... 3.6.4.3-1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System.............................................. 3.7.1-1 3.7.2 Diesel Generator Cooling Water (DGCW) System......................................................... 3.7.2-1 3.7.3 Ultimate Heat Sink (UHS).............................................................................................. 3.7.3-1 3.7.4 Control Room Emergency Ventilation (CREV) System.................................................. 3.7.4-1 3.7.5 Control Room Emergency Ventilation Air Conditioning (AC) System............................................................................................ 3.7.5-1 3.7.6 Main Condenser Offgas................................................................................................. 3.7.6-1 3.7.7 Main Turbine Bypass System........................................................................................ 3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level............................................................................ 3.7.8-1 3.7.9 Safe Shutdown Makeup Pump (SSMP) System............................................................. 3.7.9-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC SourcesOperating................................................................................................. 3.8.1-1 3.8.2 AC SourcesShutdown................................................................................................ 3.8.2-1 3.8.3 Diesel Fuel Oil Properties and Starting Air.................................................................... 3.8.3-1 3.8.4 DC SourcesOperating................................................................................................. 3.8.4-1 3.8.5 DC SourcesShutdown................................................................................................ 3.8.5-1 3.8.6 Battery Cell Parameters................................................................................................ 3.8.6-1 3.8.7 Distribution SystemsOperating................................................................................. 3.8.7-1 3.8.8 Distribution SystemsShutdown................................................................................. 3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks.................................................................................... 3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock......................................................................... 3.9.2-1 3.9.3 Control Rod Position..................................................................................................... 3.9.3-1 3.9.4 Control Rod Position Indication.................................................................................... 3.9.4-1 3.9.5 Control Rod OPERABILITYRefueling........................................................................... 3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water LevelIrradiated Fuel................................................................................................. 3.9.6-1 3.9.7 Reactor Pressure Vessel (RPV) Water LevelNew Fuel or Control Rods.................................................................................................... 3.9.7-1 3.9.8 Residual Heat Removal (RHR)High Water Level........................................................ 3.9.8-1 3.9.9 Residual Heat Removal (RHR)Low Water Level......................................................... 3.9.9-1 3.10 SPECIAL OPERATIONS 3.10.1 Reactor Mode Switch Interlock Testing........................................................................ 3.10.1-1 3.10.2 Single Control Rod WithdrawalHot Shutdown.......................................................... 3.10.2-1 3.10.3 Single Control Rod WithdrawalCold Shutdown......................................................... 3.10.3-1 3.10.4 Single Control Rod Drive (CRD)

RemovalRefueling.................................................................................................... 3.10.4-1 (continued)

Insert "3.7.10 Main Steam Line (MSL) Area Temperature............................. 3.7.10-1"

Primary Containment Isolation Instrumentation 3.3.6.1 Quad Cities 1 and 2 3.3.6.1-6 Amendment No. 248/243 Table 3.3.6.1-1 (page 1 of 3)

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

Main Steam Line Isolation a.

Reactor Vessel Water LevelLow Low 1,2,3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7

-55.2 inches b.

Main Steam Line PressureLow 1

2 E

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.7 791 psig c.

Main Steam Line PressureTimer 1

2 E

SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 0.331 seconds d.

Main Steam Line Flow-High 1,2,3 2 per MSL D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 248.1 psid(c) e.

Main Steam Line Tunnel TemperatureHigh 1,2,3 2 per trip string D

SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 198F 2.

Primary Containment Isolation a.

Reactor Vessel Water LevelLow 1,2,3 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 3.8 inches b.

Drywell PressureHigh 1,2,3 2

G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.7 2.43 psig c.

Drywell RadiationHigh 1,2,3 1

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 70 R/hr (continued)

(c) Function 1.d is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint.

Insert "Deleted"

MSL Area Temperature 3.7.10 Quad Cities 3.7.10-1 Amendment 3.7 PLANT SYSTEMS 3.7.10 Main Steam Line (MSL) Area Temperature LCO 3.7.10 The MSL Area temperature for each area in Table 3.7.10-1 shall be less than or equal to the limit APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

MSL Area temperature greater than the limit in Table 3.7.10-1 A.1 Initiate action to verify there is no leakage from the MSL pressure boundary.

AND A.2 Verify there is no leakage from the MSL pressure boundary.

Immediately Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.

Required Action and associated Completion Time not met B.1 Be in MODE 3.

AND B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours

MSL Area Temperature 3.7.10 Quad Cities 3.7.10-2 Amendment SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Verify each MSL area temperature is less than or equal to the limit in Table 3.7.10-1 In accordance with the Surveillance Frequency Control Program

MSL Area Temperature 3.7.10 Quad Cities 3.7.10-3 Amendment Table 3.7.10-1 (page 1 of 1)

Main Steam Line Area Temperature Limits MSL Area Temperature Limit Main Steam Line Tunnel Temperature - High 198 °F

ML25357A076

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