Text

Appendix a, Technical Specifications - Part 2
	ML031150536
Person / Time
Site:	Peach Bottom
Issue date:	05/07/2003
From:	; Office of Nuclear Reactor Regulation
To:	;
	Solorio, D L, NRR/DRIP/RLEP, 415-1973
References
	Download: ML031150536 (183)
	v • d • e

ECCS -Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of five safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) is not required to be OPERABLE with reactor steam dome pressure S 150 psig and ADS valves are not required to be OPERABLE with reactor steam dome pressure 5 100 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable. subsystem(s) to OPERABLE status.

OR One low pressure coolant injection (LPCI) pump in each subsystem inoperable.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

PBAPS UNIT 2 3.5-1 Amendment No. 210

ECCS-Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System C.1 Verify by Immediately inoperable. administrative means RCIC System is OPERABLE.

AND C.2 Restore HPCI System 14 days to OPERABLE status.

D. HPCI System D.1 Restore HPCI System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. to OPERABLE status.

AND OR One low pressure ECCS D.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months injection/spray ECCS injection/spray subsystem is subsystem to OPERABLE inoperable. status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition C or AND D not met.

E.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to

< 150 psig.

F. One ADS valve F.1 Restore ADS valve to 14 days inoperable. OPERABLE status.

(continued)

PBAPS UNIT 2 3.5-2 Amendment No. 210

ECCS -Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. One ADS valve G.1 Restore ADS valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND OR One low pressure ECCS G.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months injection/spray ECCS injection/spray subsystem inoperable. subsystem to OPERABLE status.

H. Two or more ADS valves H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

AND OR H.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and dome pressure to associated Completion s 100 psig.

Time of Condition F or G not met.

I. Two or more low I.1 Enter LCO 3.0.3. Immediately pressure ECCS injection/spray subsystems inoperable for reasons other than Condition A.

OR HPCI System and one or more ADS valves inoperable.

PBAPS UNIT 2 3.5-3 Amendment No. 210

ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 ------------------- NOTE--------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling isolation pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.1.3 Verify ADS nitrogen supply header pressure 31 days is 2 85 psig.

SR 3.5.1.4 Verify the LPCI cross tie valve 31 days is closed and power is removed from the valve operator.

(continued)

PBAPS UNIT 2 3.5-4 Amendment No. 210

ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.5 ------------ NOTE--------------------

Not required to be performed if performed within the previous 31 days.

Verify each recirculation pump discharge Once each valve cycles through one complete cycle of startup prior full travel or is de-energized in the to exceeding closed position. 25% RTP SR 3.5.1.6 Verify automatic transfer of the power 61 days supply from the normal source to the alternate source for each LPCI subsystem inboard injection valve and each recirculation pump discharge valve.

SR 3.5.1.7 -------------------NOTE--------------------

For the core-spray pumps, SR 3.5.1.7 may be met using equivalent values for flow rate and test pressure determined using pump curves.

Verify the following ECCS pumps develop the 92 days specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray 2 3,125 gpm 1 2 105 psig LPCI 2 10,900 gpm I - 20 psig (continued)

PBAPS UNIT 2 3.5-5 Amendment No. 210

ECCS-Operating 3.5.1 l

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure g 1053 and 2 940 psig, the HPCI pump can develop a flow rate 2 5000 gpm against a system head 92 days I

corresponding to reactor pressure.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure g 175 psig, 24 months the HPCI pump can develop a flow rate

> 5000 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.10 -------------------NOTE--------------------

Vessel injection/spray may be excluded.

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

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

Valve actuation may be excluded.

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

(continued)

PBAPS UNIT 2 3.5-6 Amendment No.f*,-

212

ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.12 Verify each, ADS valve actuator strokes when 24 months manually actuated in the depressurization mode.

PBAPS UNIT 2 3.5-7 Amendment No.1*0,224

ECCS -Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS-Shutdown LCO 3.5.2 Two low pressure ECCS injection/spray subsystems shall be OPERABLE.

APPLICABILITY: MODE 4, MODE 5, except with the spent fuel storage pool gates removed, water level 2 458 inches above reactor pressure vessel instrument zero, and no operations with a potential for draining the reactor vessel (OPDRVs) in progress.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCS A.1 Restore required ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection/spray injection/spray subsystem inoperable. subsystem to OPERABLE status.

B. Required Action and B.1 Initiate action to Immediately associated Completion suspend OPDRVs.

Time of Condition A not met.

C. Two required ECCS C.1 Initiate action to Immediately injection/spray suspend OPDRVs.

subsystems inoperable.

AND C.2 Restore one ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection/spray subsystem to OPERABLE status.

(continued)

PBAPS UNIT 2 3.5-8 Amendment No. 210

ECCS -Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status.

AND D.2 Initiate action to Immediately restore one standby gas treatment subsystem for Unit 2 to OPERABLE status.

AND D.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months coolant injection (LPCI) subsystem, the suppression pool water level is > 11.0 ft.

(continued)

PBAPS UNIT 2- 3.5-9 Amendment No. 210

ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.5.2.2 Verify, for each required core spray (CS) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystem, the:

a. Suppression pool water level is 2 11.0 ft; or

b. ----------------- NOTE-----------------

Only one required CS subsystem may take credit for this option during OPDRVs.

Condensate storage tank water level is 2 17.3 ft.

SR 3.5.2.3 Verify, for each required ECCS injection/ 31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.4 -------------------NOTE--------------------

One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

PBAPS UNIT 2 3 .5-10 Amendment No. 210

ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.4 SR 3.5.2.5 --------------- NOTE--------------------

For the CS pumps, SR 3.5.2.5 may be met using equivalent values for flow rate and test pressure determined using pump curves.

Verify each required ECCS pump develops the 92 days specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF CS Z 3,125 gpm 1 2 105 psig LPCI 2 10,900 gpm 1 Ž 20 psig SR 3.5.2.6 -------------------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.

PBAPS UNIT 2 3.5-11 Amendment No. 210

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System 14 days to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to

< 150 psig.

PBAPS UNIT 2 3.5-12 Amendment No. 210

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 1053 psig 92 days and 2 940 psig, the RCIC pump can develop a flow rate 2 600 gpm against a system head I

corresponding to reactor pressure.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 175 psig, 24 months the RCIC pump can develop a flow rate 2 600 gpm against a system head corresponding to reactor pressure.

(continued)

PBAPS UNIT 2 3.5-13 Amendment No.ift0 212

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 24 months actual or simulated automatic initiation signal.

PBAPS UNIT 2 -. 5-14 3 .5-14 Amendment No. 210

Primary Containment 3.6.1.1 I 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. containment to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT 2 3 .6-1 Amendment No. 210

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 containment air lock testing, in Primary accordance with the Primary Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program SR 3.6.1.1.2 Verify drywell to suppression chamber 24 months bypass leakage is equivalent to a hole

< 1.0 inches in diameter. AND

NOTE------

Only required after two consecutive tests fail and continues until two consecutive tests pass 12 months PBAPS UNIT 2 3.6-2 Amendment No. .4.W-14

Primary Containment Air Lock 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Lock LCO 3.6.1.2 The primary containment air lock shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

1. Entry and exit is permissible to perform repairs of the air lock components.

2. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One primary ------------NOTES------------

containment air lock 1. Required Actions A.1, door inoperable. A.2, and A.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND (conti nued)

PBAPS UNIT 2 3.6-3 Amendment No. 210

Primary Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed.

AND A.3 --- NOTE---------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed.

B. Primary containment ------------ NOTES------------

air lock interlock 1. Required Actions B.1, mechanism inoperable. B.2, and B.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry into and exit from containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND

__ (continued)

PBAPS UNIT 2 3.6-4 Amendment No. 210

Primary Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed.

AND B.3 -------- NOTE---------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door is locked closed.

C. Primary containment C.1 Initiate action to Immediately air lock inoperable evaluate primary for reasons other than containment overall Condition A or B. leakage rate per LCO 3.6.1.1, using current air lock test results.

AND C.2 Verify a door is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months closed.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

PBAPS UNIT-2 3.6-5 Amendment No. 210

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------NOTES------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.1.

Perform required primary containment air In accordance lock leakage rate testing in accordance with the with the Primary Containment Leakage Rate Primary Testing Program. Containment Leakage Rate Testing Program (continued)

-r- .. ,

PBAPS UNIT 2 3.6-6 Amendment No. k 214

Primary Containment Air Lock 3.6.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.6.1.2.2 ------------------ NOTE-------------------

Only required to be performed upon entry into primary containment when the primary containment is de-inerted.

Verify only one door in the primary 184 days containment air lock can be opened at a time.

PBAPS UNIT 2 3.6-7 Amendment No. 210

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers and scram discharge volume vent and drain valves, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, 'Primary Containment Isolation Instrumentation."

ACTIONS

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

1. Penetration flow paths except for purge or exhaust valve penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in-exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to penetration flow path for main steam penetration flow paths by use of at least line with two PCIVs. one closed and

_ de-activated AND automatic valve, One or more closed manual valve, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main penetration flow paths blind flange, or steam line with one PCIV check valve with flow inoperable except for through the valve MSIV leakage not secured.

within limit.

AND (continued)

PBAPS UNIT 2 - - 3.6-8 Amendment No. 210

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --------NOTE-Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4, if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment (continued)

Q-PBAPS UNIT--2 3.6-9 Amendment No. 210

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.--------- NOTE--------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path penetration flow paths by use of at least with two PCIVs. one closed and de-activated automatic valve, One or more closed manual valve, penetration flow paths or blind flange.

with two PCIVs inoperable except for MSIV leakage not within limit.

C. --------- NOTE--------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to penetration flow path for excess flow penetration flow paths by use of at least check valves with only one PCIV. one closed and (EFCVs) de-activated automatic valve, AND One or more closed manual valve, penetration flow paths or blind flange. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for with one PCIV EFCVs inoperable. AND (continued)

PBAPS UNIT 2 3 .6-10 Amendment No. 210

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION ICOMPLETION TIME C. (continued) C.2 -------- NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4, if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment D. One or more D.1 Restore leakage rate 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months penetration flow paths to within limit.

with one or more MSIVs not within MSIV leakage rate limits.

(continued)

PBAPS UNIT 2 3 .6-11 Amendment No. 210

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3.

associated Completion 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Time of Condition A, AND B, C, or D not met in MODE 1, 2, or 3. E.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Required Action and F.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A, with a potential for B, C, or D not met draining the reactor for PCIV(s) required vessel.

to be OPERABLE during MODE 4 or 5. OR F.2 Initiate action to Immediately restore valve(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 Verify Containment Atmospheric Dilution 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (CAD) System liquid nitrogen storage tank level is ; 16 inches water column.

SR 3.6.1.3.2 Verify Safety Grade Instrument Gas (SGIG) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months System header pressure is > 80 psig.

(continued)

PBAPS UNIT 2 3.6-12 Amendment No. 210

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 -------------- NOTE-------------------

Not required to be met when the 6 inch or 18 inch primary containment purge and 18 inch primary containment exhaust valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 6 inch and 18 inch primary 31 days containment purge valve and each 18 inch primary containment exhaust valve is closed.

1*

SR 3.6.1.3.4 ------------------NOTES------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

3. Not required to be performed for test taps with a diameter < 1 inch.

Verify each primary containment isolation 31 days manual valve and blind flange that is located outside primary containment and is required to be closed during accident conditions is closed.

(continued)

PBAPS UNIT 2 3.6-13 Amendment No. 210

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.6.1.3.5 ------------------NOTES------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual Prior to isolation valve and blind flange that is entering MODE 2 located inside primary containment and is or 3 from required to be closed during accident MODE 4 if conditions is closed. primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.6 Verify continuity of the traversing 31 days incore probe (TIP) shear isolation valve explosive charge.

SR 3.6.1.3.7 Verify each SGIG System manual valve in 31 days the flow paths servicing the 6 and 18 inch primary containment purge valves and the 18 inch primary containment exhaust valves, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

PBAPS UNIT 2 3.6-14 Amendment No. 210

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify the isolation time of each power In accordance operated and each automatic PCIV, except with the for MSIVs, is within limits. Inservice Testing Program SR 3.6.1.3.9 Verify the isolation time of each MSIV is In accordance 2 3 seconds and

5 seconds. with the Inservice Testing Program SR 3.6.1.3.10 Verify each automatic PCIV actuates to 24 months the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.11 Verify a representative sample of reactor 24 months instrumentation line EFCVs actuates to the isolation position on a simulated instrument line break signal.

SR 3.6.1.3.12 Remove and test the explosive squib from 24 months on a each shear isolation valve of the TIP STAGGERED TEST System. BASIS SR 3.6.1.3.13 Verify the CAD System supplies nitrogen 24 months to the SGIG System upon loss of the normal air supply.

(continued)

PBAPS UNIT 2 -- 3.6-15 Amendment No.-2@-

235

PCIVs 3.6.1.3 I CIIrnITI Aurr DrnivDFrurerr l- -4..- A

.uflYLLLLniI1Lnc t.aIJ 1.1 IP. I IIueauJ SURVEILLANCE FREQUENCY SR 3.6.1.3.14 Verify leakage rate through each MSIV is In accordance s 11.5 scfh when tested at k 25 psig. with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.15 Verify each 6 inch and 18 inch primary 24 months containment purge valve and each 18 inch primary containment exhaust valve is blocked to restrict opening greater than the required maximum opening angle.

I SR 3.6.1.3.16 Replace the inflatable seal of each 96 months 6 inch and 18 inch primary containment

,purge valve and each 18 inch primary containment exhaust valve.

PBAPS UNIT 2 3.6-16 Amendment No. 220

Drywell Air Temperature 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Air Temperature LCO 3.6.1.4 Drywell average air temperature shall be s 1450F.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air limit. temperature to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.4.1 Verify drywell average air temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limit.

PBAPS UNIT-2 3.6-17 Amendment No. 210

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.5 Each reactor building-to-suppression chamber vacuum breaker shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each line.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one reactor building- breaker.

to-suppression chamber vacuum breaker not closed.

B. One or more lines with B.1 Close one open vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two reactor building- breaker.

to-suppression chamber vacuum breakers not closed.

C. One line with one or C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months more reactor building- breaker(s) to to-suppression chamber OPERABLE status.

vacuum breakers inoperable for opening.

(continued)

PBAPS UNIT 2 3.6-18 Amendment No. 210

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two lines with one or D.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months more reactor building- breakers in one line to-suppression chamber to OPERABLE status.

vacuum breakers inoperable for opening.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify Containment Atmospheric Dilution 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (CAD) System nitrogen storage tank level is 2 16 inches water column.

SR 3.6.1.5.2 Verify Safety Grade Instrument Gas (SGIG) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months System header pressure 2 80 psig.

(continued)

PBAPS UNIT 2 3.6-19 Amendment No. 210

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.6.1.5.3 ------------------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 3.6.1.5.4 Verify each SGIG System manual valve in 31 days the flow paths servicing the reactor building-to-suppression chamber vacuum breakers, that is not locked, sealed or otherwise secured in position, is in the correct position.

SR 3.6.1.5.5 Perform a functional test of each vacuum 92 days breaker.

SR 3.6.1.5.6 Verify the setpoint for full opening of 18 months each air operated vacuum breaker is s 0.75 psid.

SR 3.6.1.5.7 Verify the CAD System supplies nitrogen 24 months to the SGIG System upon loss of normal air supply.

PBAPS UNIT 2 3.6-20 Amendment No. 210

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.6 Nine suppression chamber-to-drywell vacuum breakers shall be OPERABLE for opening.

AND Twelve suppression chamber-to-drywell vacuum breakers shall be closed, except when performing their intended function.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required A.1 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months suppression chamber- vacuum breaker to to-drywell vacuum OPERABLE status.

breaker inoperable for opening.

B. One suppression B.1 Close the open vacuum 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months chamber-to-drywell breaker.

vacuum breaker not closed.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT 2 3.6-21 Amendment No. 210

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

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

Verify each vacuum breaker is closed. 14 days SR 3.6.1.6.2 Perform a functional test of each 31 days required vacuum breaker.

SR 3.6.1.6.3 Verify the setpoint for full opening of 24 months each required vacuum breaker is

< 0.5 psid.

PBAPS UNIT 2 , 3.6-22 Amendment No. 210

Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be:

a. s 95'F when any OPERABLE wide range neutron monitor (WRNM) channel is at 1.OOEO % power or above and no testing that adds heat to the suppression pool is being performed;

b. s 105'F when any OPERABLE WRNM channel is at 1.00EO %

power or above and testing that adds heat to the suppression pool is being performed; and C. 5 110'F when all OPERABLE WRNM channels are below 1.OOEO

- % power.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool A.1 Verify suppression Once per hour average temperature pool average

> 950 F but s 110°F. temperature s 110*F.

AND AND Any OPERABLE WRNM at A.2 Restore suppression 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months I 1.00E0 % power or above.

pool average temperature to s 950F.

AND Not performing testing that adds heat to the suppression pool.

(continued)

PBAPS UNIT 2 3.6-23 Amendment No. ;120-222

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion until all OPERABLE Time of Condition A WRNM channels are not met. below 1.OOEO % power.

C. Suppression pool C.1 Suspend all testing Immediately average temperature that adds heat to the

> 105 0F. suppression pool. -

AND Any OPERABLE WRNM at 1.OOEO % power or above.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool D.1 Place the reactor Immediately average temperature mode switch in the

> 110 0 F but s 120 0F. shutdown position.

AND D.2 Verify suppression Once per pool average 30 minutes temperature s 120 0F.

AND D.3 Be in MODE 4 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

PBAPS UNIT 2 - 3.6-24 Amendment No. - O-,0222

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E.1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months average temperature reactor vessel to

> 120F. < 200 psig.

AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is within the applicable limits. AND 5 minutes when performing testing that adds heat to the suppression pool

PBAPS UNIT 2 3.6-25 Amendment No. 210

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be 2 14.5 feet and S 14.9 feet.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within pool water level to limits. within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limits.

PBAPS UNIT 2 , 3.6-26 Amendment No. 210

RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Two RHR suppression pool cooling subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR 7 days pool cooling subsystem suppression pool inoperable. cooling subsystem to OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool cooling suppression pool subsystems inoperable. cooling subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT 2 3.6-27 Amendment No. 210

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each required RHR pump develops a In accordance flow rate x 10,000 gpm through the with the associated heat exchanger while operating Inservice in the suppression pool cooling mode. Testing Program PBAPS UNIT--2--.:- 3.6-28 Amendment No. 210

RHR Suppression Pool Spray 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray LCO 3.6.2.4 Two RHR suppression pool spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR 7 days pool spray subsystem suppression pool inoperable. spray subsystem to OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool spray subsystems suppression pool inoperable. spray subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT--2-- 3.6-29 Amendment No. 210

RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.4.2 Verify each suppression pool spray nozzle 10 years is unobstructed.

PBAPS UNIT 2 , 3.6-30 Amendment No. 210

CAD System 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Containment Atmospheric Dilution (CAD) System LCO 3.6.3.1 Two CAD subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both CAD A.1 --------NOTE---------

subsystems inoperable. LCO 3.0.4 is not applicable.

Restore CAD 30 days subsystem(s) to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

PBAPS UNIT 3.6-31 Amendment No. 210

CAD System 3.6.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify Safety Grade Instrument Gas (SGIG) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months System header pressure is 2 80 psig.

SR 3.6.3.1.2 Verify CAD System liquid nitrogen storage 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months tank level is 2 33 inches water column.

SR 3.6.3.1.3 Verify each CAD subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.3.1.4 Verify each SGIG System manual valve in 31 days the flow paths servicing CAD System valves, that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.3.1.5 Verify the CAD System supplies nitrogen 24 months to the SGIG System upon loss of the normal air supply.

PBAPS UNIT 2 3.6-32 Amendment No. 210

Primary Containment Oxygen Concentration 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Primary Containment Oxygen Concentration LCO 3.6.3.2 The primary containment oxygen concentration shall be

< 4.0 volume percent.

I APPLICABILITY: MODE I during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to a reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oxygen concentration concentration to not within limit. within limit.

B. Required Action and B.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion to s 15% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify primary containment oxygen 7 days concentration is within limits.

PBAPS UNIT 2 3.6-33 Amendment No. 210

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, containment to 2, or 3. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Secondary containment C.1 -------- NOTE---------

inoperable during LCO 3.0.3 is not movement of irradiated applicable.

fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel OPDRVs. assemblies in the secondary containment.

AND (continued)

PBAPS UNIT 2 3.6-34 Amendment No. 210

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment 31 days equipment hatches are closed and sealed.

SR 3.6.4.1.2 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.3 Verify each standby gas treatment (SGT) 24 months on a subsystem will draw down the secondary STAGGERED TEST containment to 2 0.25 inch of vacuum BASIS water gauge in & 120 seconds.

SR 3.6.4.1.4 Verify each SGT subsystem can maintain 24 months on a 2 0.25 inch of vacuum water gauge in the STAGGERED TEST secondary containment for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a BASIS flow rate s 10,500 cfm.

PBAPS UNIT 2 3.6-35 Amendment No. 227

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

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

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months penetration flow paths penetration flow path with one SCIV by use of at least inoperable. one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

PBAPS UNIT 2 3.6-36 Amendment No. 210

SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -------- NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

B. ---------NOTE--------- B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path penetration flow paths by use of at least with two isolation one closed and valves. de-activated automatic valve, closed manual valve, One or more or blind flange.

penetration flow paths with two SCIVs inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

PBAPS UNIT 2 3.6-37 Amendment No. 210

SCIVs 3.6.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 -------- NOTE---------

associated Completion LCO 3.0.3 is not Time of Condition A applicable.

or B not met during movement of irradiated fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS, or during secondary OPDRVs. containment.

AND D.2 Suspend CORE Immediately ALTERATIONS.

AND D.3 Initiate action to Immediately suspend OPDRVs.

PBAPS UNIT 2 3.6-38 Amendment No. 210

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEI LANCE FREQUENCY SR 3.6.4.2.1 ------------------NOTES------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment 31 days isolation manual valve and blind flange that is required to be closed during accident conditions is closed.

SR 3.6.4.2.2 Verify the isolation time of each power In accordance operated and each automatic SCIV is with the within limits. Inservice Testing Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to 24 months the isolation position on an actual or simulated actuation signal.

PBAPS UNIT 2 3.6-39 Amendment No. 210

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.1 Restore SGT subsystem 7 days inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and ------------NOTE-------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated C.1 Place OPERABLE SGT Immediately fuel assemblies in the subsystem in secondary containment, operation.

during CORE ALTERATIONS, or during OR OPDRVs.

(continued)

PBAPS UNIT 2 3 .6-40 Amendment No. 210

SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to Immediately suspend OPDRVs.

D. Two SGT subsystems D.1 Enter LCO 3.0.3 Immediately inoperable in MODE 1, 2, or 3.

E. Two SGT subsystems E.1 ---- NOTE---------

inoperable during LCO 3.0.3 is not movement of irradiated applicable.

fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel OPDRVs. assemblies in secondary containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

PBAPS UNIT 2-- 3.6-41 Amendment No. 210

SGT System 3.6.4.3

.t N SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 31 days

- 15 minutes with heaters operating.

SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 24 months actual or simulated initiation signal.

PBAPS UNIT 2 3.6-42 Amendment No. 210

HPSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 High Pressure Service Water (HPSW) System LCO 3.7.1 Two HPSW subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One HPSW subsystem -----------NOTE-------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown," for RHR shutdown cooling made inoperable by HPSW System.

A.1 Restore HPSW 7 days subsystem to OPERABLE status.

B. Both HPSW subsystems -----------NOTE-------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by HPSW System.

B.1 Restore one HPSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystem to OPERABLE status.

(continued)

= -PBAPS UNIT 2 3.7-1 Amendment No. 210

HPSW System 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each HPSW manual and power operated 31 days 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.

PBAPS UNIT 2 3.7-2 Amendment No. 210

ESW System and Normal Heat Sink 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Emergency Service Water (ESW) System and Normal Heat Sink LCO 3.7.2 Two ESW subsystems and normal heat sink shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I A. One ESW subsystem A.1 Restore ESW subsystem 7 days inoperable. to OPERABLE status.

B. Water temperature of B.1 Verify water Once per the normal heat sink temperature of the hour is > 90'F and s 920F. normal heat sink is s 90'F averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

I C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or AND B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Both ESW subsystems inoperable.

OR Normal heat sink inoperable [for reasons other than condition B].

PBAPS UNIT 2 3.7-3 Amendment No. 2CE, 244

ESW System and Normal Heat Sink 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the pump bays of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the pump structure is Z 98.5 ft Conowingo Datum (CD) and 5 113 ft CD.

SR 3.7.2.2 Verify the average water temperature of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months normal heat sink is s 900F.

SR 3.7.2.3 -------------------NOTE ------------

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

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

SR 3.7.2.4 Verify each ESW subsystem actuates on an 24 months actual or simulated initiation signal.

PBAPS UNIT 2 3.7-4 Amendment No. 210

Emergency Heat Sink 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Emergency Heat Sink LCO 3.7.3 The emergency heat sink shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required emergency A.1 Restore required 14 days cooling tower fan emergency cooling inoperable. tower fan to OPERABLE status.

B. Emergency heat sink B.1 Restore emergency 7 days inoperable for reasons heat sink to OPERABLE other than status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT-2 3.7-5 Amendment No. 210

Emergency Heat Sink 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the water level of emergency heat 31 days sink reservoir is ; 17 ft.

SR 3.7.3.2 Operate each required emergency cooling 92 days tower fan for x 15 minutes.

PBAPS UNIT 2 3.7-6 Amendment No. 210

MCREV System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Emergency Ventilation (MCREV) System LCO 3.7.4 Two MCREV subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREV subsystem A.1 Restore MCREV 7 days inoperable. subsystem to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and ------------NOTE-------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated C.1 Place OPERABLE MCREV Immediately fuel assemblies in the subsystem in secondary containment, operation.

during CORE ALTERATIONS, or during OR OPDRVs.

(continued)

PBAPS UNIT 2 3.7-7 Amendment No. 210

MCREV System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to Immediately suspend OPDRVs.

D. Two MCREV subsystems D.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3.

E. Two MCREV subsystems ------------NOTE-------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, E.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the OPDRVs. secondary containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

PBAPS UNIT 2 3.7-8 Amendment No. 210

MCREV System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREV subsystem for 31 days 2 15 minutes.

SR 3.7.4.2 Perform required MCREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.4.3 Verify each MCREV subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.7.4.4 Verify each MCREV subsystem can maintain a 24 months on a positive pressure of > 0.1 inches water STAGGERED TEST gauge relative to the turbine building BASIS during operation at a flow rate of 2 2700 cfm and s 3300 cfm.

PBAPS UNIT 2 3.7-9 Amendment No. 210

Main Condenser Offgas 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Main Condenser Offgas LCO 3.7.5 The gross gamma activity rate of the noble gases measured at the steam jet air ejector (SJAE) discharge at the offgas sample rack shall be < 320,000 pCi/second after decay of 30 minutes.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated and SJAE in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity A.1 Restore gross gamma 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rate of the noble activity rate of the gases not within noble gases to within limit. limit.

B. Required Action and B.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion steam lines.

Time not met.

OR B.2 Isolate SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR B.3.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.3.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT 2 3. 7-10 Amendment No. 210

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -------------------NOTE--------------------

Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.

Verify the gross gamma activity rate of the 31 days noble gases is s 320,000 pCi/second after decay of 30 minutes. AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a 2 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level PBAPS U-NIT-2 3.7-11 Amendment No. 210

Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR The following limits are made applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR.

APPLICABILITY: THERMAL POWER z 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO not met. requirements of the LCO.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

PBAPS UNIT 2 3.7-12 Amendment No. 210

Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each main 31 days turbine bypass valve.

SR 3.7.6.2 Perform a system functional test. 24 months SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM RESPONSE 24 months TIME is within limits.

PBAPS UNIT-2 3.7-13 Amendment No. 210

Spent Fuel Storage Pool Water Level 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be > 232 ft 3 inches plant elevation.

APPLICABILITY: During movement of fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 -------- NOTE---------

pool water level not LCO 3.0.3 is not within limit. applicable.

Suspend movement of Immediately fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water 7 days level is x 232 ft 3 inches plant elevation.

PBAPS UNIT 2 3.7-14 Amendment No. 210

AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the Unit 2 onsite Class lE AC Electrical Power Distribution System;

b. Four diesel generators (DGs) capable of supplying the Unit 2 onsite Class 1E AC Electrical Power Distribution System;

c. The qualified circuit(s) between the offsite transmission network and the Unit 3 onsite Class 1E AC electrical power distribution subsystem(s) needed to support the Unit 3 powered equipment required to be OPERABLE by LCO 3.6.4.3, 'Standby Gas Treatment (SGT)

System," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.4, "DC Sources-Operating"; and

d. The DG(s) capable of supplying the Unit 3 onsite Class 1E AC electrical power distribution subsystem(s) needed to support the Unit 3 powered equipment required to be OPERABLE by LCO 3.6.4.3, LCO 3.7.3, and LCO 3.8.4.

APPLICABILITY: MODES 1, 2, and 3.

PBAPS UNIT 2 3.8-1 Amendment No. 210

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. for OPERABLE offsite circuits. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature(s) with no discovery of no offsite power offsite power to available inoperable one 4 kV when the redundant emergency bus required feature(s) concurrent with are inoperable. inoperability of redundant required feature(s)

AND A.3 Restore offsite 7 days circuit to OPERABLE status. AND 14 days from discovery of failure to meet LCO 3.8.1.a or b (continued)

PBAPS UNIT 2 3.8-2 Amendment No. 210

AC Sources-Operating 3.8.1 ACTIONS (continued)

CONDITION E REQUIRED ACTION O COMPLETION TIME B. One DG inoperable. B.1 Verify correct Immediately breaker alignment, required equipment AND available, and indicated power Once per available for the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Conowingo Tie-Line. thereafter AND B.2 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for OPERABLE offsite circuits. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.3 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s), supported discovery of by the inoperable DG, Condition B inoperable when the concurrent with redundant required inoperability of feature(s) are redundant inoperable. required feature(s)

AND B.4.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR B.4.2 Perform SR 3.8.1.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for OPERABLE DG(s).

AND (continued)

PBAPS UNIT 2 - 3.8-3 Amendment No. 210

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.5 Restore DG to 14 days from OPERABLE status. discovery of failure to meet LCO 3.8.1.a or b C. Required Action B.1 C.1 Restore DG to 7 days and associated OPERABLE status.

Completion Time not met.

D. Two or more offsite D.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from circuits inoperable. feature(s) inoperable discovery of when the redundant Condition D required feature(s) concurrent with are inoperable. inoperability of redundant required feature(s)

AND D.2 Restore all but one 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months offsite circuit to OPERABLE status.

(continued)

PBAPS UNIT-2 3.8-4 Amendment No. 210

AC Sources-Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One offsite circuit ----- NOTE-------------

inoperable. Enter applicable Conditions and Required Actions of AND LCO 3.8.7, "Distribution Systems-Operating," when One DG inoperable. Condition E is entered with no AC power source to any 4 kV emergency bus.

E.1 Restore offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

OR E.2 Restore DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

F. Two or more DGs F.1 Restore all but one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. DG to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, AND C, D, E, or F not met.

G.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Required Action B.2, B.3, B.4.1, B.4.2, or B.5 and associated Completion Time not met.

(continued)

PBAPS UNIT 2 3.8-5 Amendment No. 210

AC Sources-Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One or more offsite H.1 Enter LCO 3.0.3. Immediately circuits and two or more DGs inoperable.

OR Two or more offsite circuits and one DG inoperable.

SURVEILLANCE REQUIREMENTS

-_-_-_-_-------------------NOTE-------------------------------------

SR 3.8.1.1 through SR 3.8.1.20 are applicable only to the Unit 2 AC sources.

SR 3.8.1.21 is applicable only to the Unit 3 AC sources.

SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for each offsite circuit.

(continued)

PBAPS UNIT 2 3.8-6 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.2 -------------------NOTES-------------------

1. Performance of SR 3.8.1.7 satisfies this SR.

2. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

3. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

4. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts from standby 31 days conditions and achieves steady state voltage > 4160 V and s 4400 V and frequency

> 58.8 Hz and s 61.2 Hz.

{continued)

PBAPS UNIT 2 3.8-7 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.8.1.3 ------------------- NOTES-------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

5. A single test will satisfy this Surveillance for both units, with synchronization to the Unit 2 4 kV emergency bus for one periodic test and synchronization to the Unit 3 4 kV emergency bus during the next periodic test. However, if the test is not performed on Unit 3, then the test shall be performed synchronized to the Unit 2 4 kV emergency bus.

Verify each DG is synchronized and loaded 31 days and operates for > 60 minutes at a load

> 2400 kW and < 2600 kW.

SR 3.8.1.4 Verify each day tank contains > 250 gal of 31 days fuel oil.

SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank.

(continued)

PBAPS UNIT 2 3.8-8 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify the fuel oil transfer system 31 days operates to automatically transfer fuel oil from storage tank to the day tank.

SR 3.8.1.7 --------------- NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts from standby 184 days condition and achieves, in < 10 seconds, voltage 2 4160 V and frequency 2 58.8 Hz, and after steady state conditions are reached, maintains voltage 2 4160 V and s 4400 V and frequency z 58.8 Hz and

< 61.2 Hz.

SR 3.8.1.8 ------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of the 24 months unit power supply from the normal offsite circuit to the alternate offsite circuit.

(continued)

PBAPS UNIT-2 3.8-9 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 ------------------NOTES--------------------

1. If performed with the DG synchronized with offsite power, it shall be performed at a power factor s 0.89.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG rejects a load greater than 24 months or equal to its associated single largest post-accident load, and:

a. Following load rejection, the frequency is S 66.75 Hz;

b. Within 1.8 seconds following load rejection, the voltage is Z 3750 V and s 4570 V, and after steady state conditions are reached, maintains voltage 2 4160 V and c 4400 V; and

c. Within 2.4 seconds following load rejection, the frequency is Z 58.8 Hz and < 61.2 Hz.

SR 3.8.1.10 ------------------NOTE---------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG operating at a power factor 24 months

< 0.89 does not trip and voltage is maintained s 5230 V during and following a load rejection of 2 2400 kW and c 2600 kW.

(continued)

PBAPS -UNIT 2 3. 8-10 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 -------------------NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, or 3.

However, credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of 24 months offsite power signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes associated 4 kV emergency bus in < 10 seconds,

2. energizes auto-connected shutdown loads through individual load timers,

3. maintains steady state voltage x 4160 V and < 4400 V,

4. maintains steady state frequency 2 58.8 Hz and s 61.2 Hz, and

5. supplies auto-connected shutdown loads for ; 5 minutes.

(continued)

PBAPS UNIT 2 3.8-11 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.8.1.12 NOTE--------------------

All DG starts may be preceded by an engine prelube period.

Verify on an actual or simulated Emergency 24 months Core Cooling System (ECCS) initiation signal each DG auto-starts from standby condition and:

a. In < 10 seconds after auto-start achieves voltage > 4160 V, and after steady state conditions are reached, maintains voltage 2 4160 V and

- 4400 V;

b. In s 10 seconds after auto-start achieves frequency - 58.8 Hz, and after steady state conditions are reached, maintains frequency > 58.8 Hz and s 61.2 Hz;

c. Operates for 2 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized or auto-connected through individual load timers from the offsite power system.

I (continued)

PBAPS UNIT,2. 3.8-12 Amendment No. 210

AC Sources-Operating 3.8.1 tIPIID~Ti~ ifA~r'

_II DPfniITPPMPNT5q (rnntinitpril

. _ - . ..- , I SURVEILLANCE FREQUENCY i.

SR 3.8.1.13 ------------------NOTE---------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG's automatic trips are 24 months bypassed on an actual or simulated ECCS initiation signal except:

a. Engine overspeed;

b. Generator differential overcurrent;

c. Generator ground neutral overcurrent; and

d. Manual cardox initiation.

(continued)

PBAPSUNIT 2 3.8-13 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.14 ------------------- NOTES-------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. If grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

3. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG operating at a power factor 24 months

< 0.89 operates for > 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For ? 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 2800 kW and 5 3000 kW; and

b. For the remaining hours of the test loaded 2 2400 kW and 5 2600 kW.

(continued)

PBAPS UNIT 2 3.8-14 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1*

SR 3.8.1.15 -------------------NOTES-------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated > 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 2400 kW and 5 2600 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

3. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts and achieves, in 24 months

- 10 seconds, voltage > 4160 V and frequency 2 58.8 Hz, and after steady state conditions are reached, maintains voltage

4160 V and < 4400 V and frequency 2 58.8 Hz and 5 61.2 Hz.

(continued)

PBAPS UNIT'2 3.8-15 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.4 SR 3.8.1.16 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG: 24 months

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

1.

SR 3.8.1.17 -------------------NOTE--------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify with a DG operating in test mode and 24 months connected to its bus, an actual or simulated ECCS initiation signal overrides the test mode by:

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

A.

(continued)

PBAPS UNIT 2 3.8-16 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.9 SR 3.8.1.18 ------------------NOTE---------------------

This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify interval between each timed load 24 months block is within +/- 10% of design interval for each individual load timer.

(continued)

_ PBAPS UNIT 2

-- 3.8-17 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.19 -------------------NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, or 3.

However, credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of 24 months offsite power signal in conjunction with an actual or simulated ECCS initiation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes associated 4 kV emergency bus in < 10 seconds,

2. energizes auto-connected emergency loads through individual load timers,

3. achieves steady state voltage

- 4160 V and < 4400 V,

4. achieves steady state frequency 2 58.8 Hz and < 61.2 Hz, and

5. supplies auto-connected emergency loads for 2 5 minutes.

.1.

(continued)

PBAPS UNIT 2 3.8-18 Amendment No. 210

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.8.1.20 - --------------- NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify, when started simultaneously from 10 years standby condition, each DG achieves, in

< 10 seconds, voltage 2 4160 V and frequency 2 58.8 Hz.

SR 3.8.1.21 ------------------- NOTE--------------------

When Unit 3 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 3 SR 3.8.2.1 is applicable.

For required Unit 3 AC sources, the SRs of In accordance Unit 3 Specification 3.8.1, except with applicable SR 3.8.1.8 (when only one Unit 3 offsite SRs circuit is required), SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.17, SR 3.8.1.18 (ECCS load block requirement only), and SR 3.8.1.19, are applicable.

I PBAPS UNIT 2 3 .8-19 Amendment No. 210

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the Unit 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown";

b. Two DGs each capable of supplying one Unit 2 onsite Class 1E AC electrical power distribution subsystem required by LCO 3.8.8;

c. One qualified circuit between the offsite transmission network and the Unit 3 onsite Class IE AC electrical power distribution subsystem(s) needed to support the Unit 3 powered equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," and LCO 3.8.5, 'DC Sources-Shutdown"; and

d. One DG capable of supplying one Unit 3 onsite Class lE AC electrical power distribution subsystem needed to support the Unit 3 powered equipment required to be OPERABLE by:

1. LCO 3.6.4.3.

OR

2. LCO 3.8.5.

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

PBAPS UNIT 2 3.8-20 Amendment No. 210

AC Sources-Shutdown 3.8.2 ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required ------------ NOTE-------------

offsite circuits Enter applicable Condition inoperable. and Required Actions of LCO 3.8.8, with one or more required 4 kV emergency buses de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature(s),

with no offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND (continued)

________________________ J PBAPS UNIT, 2 3.8-21 Amendment No. 210

AC Sources-Shutdown 3.8.2 i

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate action to Immediately restore required offsite power circuit(s) to OPERABLE status.

B. One required DG B.1 Declare affected Immediately inoperable. required feature(s) with no DG available inoperable.

OR B.2.1 Suspend CORE Immediately ALTERATIONS AND B.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND B.2.3 Initiate action to Immediately suspend OPDRVs.

AND B.2.4 Initiate action to Immediately restore required DGs to OPERABLE status.

(continued)

PBAPS UNIT 2 3.8-22 Amendment No. 210

AC Sources-Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two or more required C.1 Suspend CORE Immediately DGs inoperable. ALTERATIONS.

AND C.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND C.3 Initiate action to Immediately suspend OPDRVs.

AND C.4 Initiate action to Immediately restore required DG(s) to OPERABLE status.

PBAPS UNIT 2-. 3.8-23 Amendment No. 210

AC Sources -Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I.

SR 3.8.2.1 -------------------NOTE--------------------

The following SRs are not required to be performed: SR 3.8.1.3,-SR 3.8.1.9 through SR 3.8.1.11, SR 3.8.1.13 through SR 3.8.1.16, SR 3.8.1.18, and SR 3.8.1.19.

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

The requirements of SR 3.8.1.12, SR 3.8.1.13, and SR 3.8.1.19 are not required to be met during periods that ECCS are not required.

For required Unit 2 AC sources the SRs of In accordance Specification 3.8.1, except SR 3.8.1.8, with applicable SR 3.8.1.17, and SR 3.8.1.20, are SRs applicable.

4 SR 3.8.2.2 ------------------- NOTE--------------------

When Unit 3 is not in MODE 1, 2, or 3, the Note to Unit 3 SR 3.8.2.1 is applicable.

For required Unit 3 AC sources, the SRs of In accordance Unit 3 Specification 3.8.1, except with applicable SR 3.8.1.8 (when only one Unit 3 offsite SRs circuit is required), SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.17, SR 3.8.1.18 (ECCS load block requirement only), SR 3.8.1.19, and SR 3.8.1.20, are applicable.

PBAPS UNIT 2 3.8-24 Amendment No.221

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required diesel generator (DG).

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months fuel oil level level to within

< 31,000 gal and limits.

> 27,500 gal in storage tank.

B. One or more DGs with B.1 Restore lube oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months lube oil inventory inventory to within

< 350 gal and limits.

> 300 gal.

C. One or more DGs with C.1 Restore fuel oil 7 days stored fuel oil total total particulates to particulates not within limit.

within limit.

(continued)

PBAPS UNIT 2 3.8-25 Amendment No. 210

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more DGs with D.1 Restore stored fuel 30 days new fuel oil oil properties to properties not within within limits.

limits.

E. One or more DGs with E.1 Restore required 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months required starting air starting air receiver receiver pressure pressure to

< 225 psig and 2 225 psig.

> 150 psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One or more DGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

PBAPS UNIT 2 3.8-26 Amendment No. 210

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains 31 days

> 31,000 gal of fuel.

SR 3.8.3.2 Verify lube oil inventory is 2 350 gal. 31 days SR 3.8.3.3 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure 31 days is 2 225 psig.

SR 3.8.3.5 Check for and remove accumulated water from 31 days each fuel oil storage tank.

PBAPS UNIT-2 3.8-27 Amendment No. 210

DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 The following DC electrical power subsystems shall be OPERABLE:

a. Unit 2 Division I and Division II DC electrical power subsystems; and

b. Unit 3 Division I and Division II DC electrical power subsystems.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Unit 3 DC -------------NOTE------------

electrical power Enter applicable Conditions subsystem inoperable and Required Actions of LCO due to performance of* 3.8.7, "Distribution SR 3.8.4.7 or Systems-Operating," when SR 3.8.4.8. Condition A results in de-energization of a Unit 2 4 kV emergency bus or de-energization of a Unit 3 DC bus.

A.1 Restore Unit 3 DC 7 days electrical power subsystem to OPERABLE status.

(continued)

PBAPS UNIT 2 3.8-28 Amendment No. 210

DC Sources-Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Unit 3 DC ------------- NOTE------------

electrical power Enter applicable Conditions subsystem inoperable and Required Actions of LCO for reasons other than 3.8.7, "Distribution Condition A. Systems-Operating," when Condition B results in de-energization of a Unit 2 4 kV emergency bus.

B.1 Restore Unit 3 DC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months electrical power subsystem to OPERABLE status.

C. One Unit 2 DC C.1 Restore Unit 2 DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power electrical power subsystem inoperable. subsystem to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, AND B, or C not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two or more inoperable E.1 Enter LCO 3.0.3. Immediately DC electrical power subsystems.

PBAPS UNIT 2 3.8-29 Amendment No. 210

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS

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

SR 3.8.4.1 through SR 3.8.4.8 are applicable only to the Unit 2 DC electrical power subsystems. SR 3.8.4.9 is applicable only to the Unit 3 DC electrical power subsystems.

SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is ----- NOTE------

2 123.5 V on float charge. The 7 day Frequency is not applicable if the battery is on equalize charge or has been on equalize charge at any time during the previous 1 day.

7 days AND 14 days SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.

OR Verify battery connection resistance is s 40 E-6 ohms.

SR 3.8.4.3 Verify battery cells, cell plates, and 12 months racks show no visual indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

(continued)

PBAPS UNIT 2 3.8-30 Amendment No. 210

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.4 Remove visible corrosion and verify battery 12 months cell to cell and terminal connections are coated with anti-corrosion material.

SR 3.8.4.5 Verify battery connection resistance is 12 months

< 40 E-6 ohms.

SR 3.8.4.6 Verify each required battery charger 24 months supplies 2 200 amps at 2 125 V for 2 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SR 3.8.4.7 ------------------- NOTES-------------------

1. SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 once per 60 months when SR 3.8.4.8 envelops the duty cycle of the battery.

2. This Surveillance shall not be performed in MODE 1, 2, or 3.

However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to 24 months supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

(continued)

PBAPS UNIT 2 3.8-31 Amendment No. 210

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE I FREQUENCY SR 3.8.4.8 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is > 80% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation or has reached 85%

of expected life with capacity < 100%

of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity > 100%

of manufacturer's rating (continued)

PBAPS UNIT 2 3.8-32 Amendment No. 210

DC Sources-Operating 3.8.4 1wourWTi

.JfLOI%

1 Amrr DPrnhlTflFMPTq L a &Lrfl*SI -_5"<* MS 4S'--t- . -

( rnnt;nnadl~r

- TF SURVEILLANCE FREQUENCY l

SR 3.8.4.9 -------------- NOTE--------------------

When Unit 3 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 3 SR 3.8.5.1 is applicable.

For required Unit 3 DC electrical power In accordance subsystems, the SRs of Unit 3 Specification with applicable 3.8.4 are applicable. SRs

£ ____________________________________________________________

PBAPS UNIT 2 3.8-33 Amendment No. 210

DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO 3.8.5 The following DC electrical power subsystems shall be OPERABLE:

a. Unit 2 DC electrical power subsystems needed to support the DC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown";

and

b. Unit 3 DC electrical power subsystems needed to support the DC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown."

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

_- _-- ------------------------ NOTE-------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected Immediately DC electrical power required feature(s) subsystems inoperable. inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND (continued)

PBAPS UNIT 2 3.8-34 Amendment No. 210

DC Sources-Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate action to Immediately restore required DC electrical power subsystems to OPERABLE status.

PBAPS UNIT 2 3.8-35 Amendment No. 210

DC Sources-Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1*

SR 3.8.5.1 NOTE--------------------

The following SRs are not required to be performed: SR 3.8.4.7 and SR 3.8.4.8.

For required Unit 2 DC electrical power In accordance subsystems, the following SRs are with applicable applicable: SRs SR 3.8.4.1 SR 3.8.4.4 SR 3.8.4.7 SR 3.8.4.2 SR 3.8.4.5 SR 3.8.4.8.

SR 3.8.4.3 SR 3.8.4.6 SR 3.8.5.2 ------------------ NOTE--------------------

When Unit 3 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 3 SR 3.8.5.1 is applicable.

For required Unit 3 DC electrical power In accordance subsystems, the SRs of Unit 3 Specification with applicable 3.8.4 are applicable. SRs PBAPS UNIT 2 3.8-36 Amendment No. 210

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the station batteries shall be within the limits of Table 3.8.6-1.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cells 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6-1 Category A or B Category C limits.

limits.

AND A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

(continued)

PBAPS. UNIT 2 - --- 3.8-37 Amendment No. 210

I Battery Cell Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR One or more batteries with average electrolyte temperature of the representative cells not within limits.

OR One or more batteries with one or more battery cell parameters not within Category C limits.

PBAPS UNIT 2 3.8-38 Amendment No. 210

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY J.

SR 3.8.6.1 Verify battery cell parameters meet ------NOTE-----

Table 3.8.6-1 Category A limits. The 7 day Frequency is not applicable if the battery is on equalize charge or has been on equalize charge at any time during the previous 4 days.

7 days AND 14 days I

SR 3.8.6.2 Verify each battery cell meets 92 days Table 3.8.6-1 Category B limits.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery discharge

< 100 V AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery overcharge

> 145 V SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is 2 400F.

PBAPS UNIT 2 3.8-39 Amendment No. 210

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameter Requirements CATEGORY A: CATEGORY B: CATEGORY C:

LIMITS FOR EACH LIMITS FOR EACH ALLOWABLE LIMIT DESIGNATED PILOT - CONNECTED CELL FOR EACH PARAMETER CELL CONNECTED CELL Electrolyte > Minimum level > Minimum level Above top of Level indication mark, and indication mark, plates, and not s 4 inch above and s 4 inch above overflowing maximum level maximum level indication mark(a) indication mark(a)

Float Voltage 2 2.13 V 2 2.13 V > 2.07 V Specifi ;t 1.195 2 1.195 Not more than Gravity.b)(c) 0.020 below AND average of all connected cells Average of all connected cells AND

> 1.205 Average of all connected cells

> 1.190 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature and level. Level correction is not required, however, when on float charge and battery charging current is < 1 amp.

(c) A battery charging current of < 1 amp when on float charge is acceptable for meeting specific gravity limits following a battery recharge for:

1) a maximum of 30 days if a deep discharge did not occur; and 2) a maximum of 180 days if a deep discharge did occur. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to the expiration of the applicable allowance.

PBAPS UNIT 2 3.8-40 Amendment No. 210

Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE:

a. Unit 2 Division I and Division II AC and DC electrical power distribution subsystems; and

b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.7, "Residual Heat Removal (RHR)

Shutdown Cooling System-Hot Shutdown," LCO 3.5.1,

'ECCS-Operating," LCO 3.6.2.3, "RHR Suppression Pool Cooling," LCO 3.6.2.4, "RHR Suppression Pool Spray,"

LCO 3.6.3.1, "Containment Atmospheric Dilution (CAD)

System," LCO 3.6.4.3, "Standby Gas Treatment (SGT)

System," LCO 3.7.1, "High Pressure Service Water (HPSW)

System," LCO 3.7.2, "Emergency Service Water (ESW)

System and Normal Heat Sink," LCO 3.7.3, "Emergency Heat Sink," and LCO 3.8.1, "AC Sources-Operating."

APPLICABILITY: MODES 1, 2, and 3.

PBAPS UNIT 2 3.8-41 Amendment No. 210

Distribution Systems-Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required --------- NOTE------------

Unit 3 AC electrical Enter applicable Conditions power distribution and Required Actions of LCO subsystems inoperable. 3.8.4, "DC Sources-Operating," when Condition A results in a de-energization of a required Unit 3 125 V battery charger.

A.1 Restore required 7 days Unit 3 AC electrical power distribution subsystemts) to OPERABLE status.

B. One required Unit 3 DC B.1 Restore Unit 3 DC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months electrical power electrical power distribution subsystem distribution inoperable. subsystem to OPERABLE status.

C. One Unit 2 AC C.1 Restore Unit 2 AC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months electrical power electrical power distribution subsystem distribution AND inoperable. subsystem to OPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a (continued)

PBAPS UNIT 2 3. 8-42 Amendment No. 210

Distribution Systems-Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One Unit 2 DC D.1 Restore Unit 2 DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power electrical power distribution subsystem distribution AND inoperable. subsystem to OPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, AND B, C, or D not met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Two or more inoperable F.1 Enter LCO 3.0.3. Immediately electrical power distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify: 7 days

a. Correct breaker alignments to required AC electrical power distribution subsystems; and

b. Indicated power availability to required AC and DC electrical power distribution subsystems.

PBAPS UNIT 2 3.8-43 Amendment No. 210

Distribution Systems-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems-Shutdown LCO 3.8.8 The necessary portions of the following AC and DC electrical power distribution subsystems shall be OPERABLE:

a. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE; and

b. Unit 3 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.4.8, "Residual Heat Removal (RHR)

Shutdown Cooling System-Cold Shutdown," LCO 3.5.2, "ECCS-Shutdown," LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3.8.2, "AC Sources-Shutdown,"

LCO 3.9.7, "RHR-High Water Level," and LCO 3.9.8, "RHR-Low Water Level."

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC or DC electrical supported required power distribution feature(s) subsystems inoperable. inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND (continued)

PBAPS UNIT 2 3.8-44 Amendment No. 210

Distribution Systems -Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend handling of Immediately irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate actions to Immediately restore required AC and DC electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.

IJ PBAPS UNIT 2 3.8-45 Amendment No. 210

Distribution Systems-Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify: 7 days

a. Correct breaker alignments to required AC electrical power distribution subsystems; and

b. Indicated power availability to required AC and DC electrical power distribution subsystems.

.1 _____________________________

PBAPS UNIT 2 3.8-46 Amendment No. 210

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel Immediately refueling equipment fuel movement with interlocks inoperable. equipment associated with the inoperable interlock(s).

PBAPS UNIT 2 3.9-1 Amendment No. 210

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment interlock inputs:

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded, I d. Refuel platform frame mounted auxiliary hoist, fuel loaded, I e. Refuel platform monorail mounted hoist, fuel loaded.

PBAPS UNIT -2 - 3.9-2 Amendment No.Y4-4 229

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one- A.1 Suspend control rod Immediately rod-out interlock withdrawal.

inoperable.

AND A.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

(continued)

PBAPS UNIT 2 3.9-3 Amendment No. 210

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.2.2 -------------------NOTE--------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days PBAPS UNIT 2 3.9-4 Amendment No. 210

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1 Suspend loading fuel Immediately rods not fully assemblies into the inserted. core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months PBAPS UNIT 2-, 3.9-5 Amendment No. 210

Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod "full-in" position indication for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS

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

Separate Condition entry is allowed for each required position indication.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Suspend in-vessel Immediately control rod position fuel movement.

indications inoperable. AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

OR (conti nued)

PBAPS UNIT 2 3.9-6 Amendment No. 210

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to Immediately fully insert the control rod associated with the inoperable position indicator.

AND A.2.2 Initiate action to Immediately disarm the control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required position indication has Each time the no "full-in" indication on each control rod control rod is that is not full-in." withdrawn from the "full-in" position PBAPS UNIT 2 3.9-7 Amendment No. 210

-I Control Rod OPERABILITY-Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE S.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to Immediately control rods fully insert inoperable. inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 -------------------NOTE--------------------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least 7 days one notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 2 940 psig.

PBAPS UNIT 2 3.9-8 Amendment No#27 211

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 2 458 inches above RPV instrument zero.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 2 458 inches 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months above RPV instrument zero.

-. - PBAPS UNIT 2 3.9-9 Amendment No. 210

RHR-High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) -High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

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

The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level > 458 inches above RPV instrument zero.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A assemblies into the not met. RPV.

AND B.2 Initiate action to Immediately restore secondary containment to OPERABLE status.

AND (continued)

PBAPS UNIT -2 3. 9-10 Amendment No. 210

RHR-High Water Level 3.9.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to Immediately restore one standby gas treatment subsystem for Unit 2 to OPERABLE status.

AND B.4 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown C.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in coolant circulation discovery of no operation. by an alternate reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor Once per hour coolant temperature.

PBAPS UNIT 2 3.9-11 Amendment No. 210

RHR-High Water Level 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is operating.

PBAPS UNIT 2 3.9-12 Amendment No. 210

RHR-Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) -Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

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

The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 458 inches above RPV instrument zero.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RHR shutdown cooling method of decay heat subsystems inoperable. removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Initiate action to Immediately associated Completion restore secondary Time of Condition A containment to not met. OPERABLE status.

AND (continued)

PBAPS UNIT 2 3.9-13 Amendment No. 210

RHR-Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Initiate action to Immediately restore one standby gas treatment subsystem for Unit 2 to OPERABLE status.

AND B.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown C.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in coolant circulation discovery of no operation. by an alternate reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor Once per hour coolant temperature.

PBAPS UNIT 3.9-14 Amendment No. 210

RHR-Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is operating.

PBAPS UNIT 2 3.9-15 Amendment No. 210

Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown," may be suspended, to allow performance of an inservice leak or hydrostatic test provided the following MODE 3 LCOs are met:

a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, and 4 of Table 3.3.6.2-1;

b. LCO 3.6.4.1, "Secondary Containment";

c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)"; and

d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."

APPLICABILITY: MODE 4 with average reactor coolant temperature > 212*F.

PBAPS UNIT 2 3. 10-1 Amendment No. 210

Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 --------NOTE---------

above requirements not Required Actions to met. be in MODE 4 include reducing average reactor coolant temperature to

- 2120F.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Suspend activities Immediately that could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reactor coolant temperature to

< 212VF.

PBAPS UNIT 2 3.10-2 Amendment No. 210

Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to MODE 3 LCOs. the applicable SRs PBAPS UNIT 2., 3.10-3 Amendment No. 210

Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LCO 3.10.2 The reactor mode switch position specified in Table 1.1-1 for MODES 3, 4, and 5 may be changed to include the run, startup/hot standby, and refuel position, and operation considered not to be in MODE 1 or 2, to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided:

a. All control rods remain fully inserted in core cells containing one or more fuel assemblies; and

b. No CORE ALTERATIONS are in progress.

APPLICABILITY: MODES 3 and 4 with the reactor mode switch in the run, startup/hot standby, or refuel position, MODE 5 with the reactor mode switch in the run or startup/hot standby position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend CORE Immediately above requirements not ALTERATIONS except met. for control rod insertion.

AND A.2 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months insertable control rods in core cells containing one or more fuel assemblies.

AND (continued)

PBAPS UNIT 2 3.10-4 Amendment No. 210

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

OR A.3.2 -------- NOTE---------

Only applicable in MODE 5.

Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in core cells containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months PBAPS UNIT 2 3.10-5 Amendment No. 210

Single Control Rod Withdrawal-Hot Shutdown 3.10.3 3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal -Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

b. LCO 3.9.4, "Control Rod Position Indication";

c. All other control rods are fully inserted; and

d. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b, 7, 12, 13, and 14 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY-Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed, at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 3 requirements, may be changed to allow the single control rod to be withdrawn to be assumed the highest worth control rod.

APPLICABILITY: MODE 3 with the reactor mode switch in the refuel position.

PBAPS UNIT 2 3.10-6 Amendment No. 210

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 ACTIONS Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 -------- NOTES--------

above requirements not I. Required Actions met. to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to Immediately fully insert all insertable control rods.

AND A.2.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

__________________________ L _________________

PBAPS UNIT 2 3.10-7 Amendment No. 210

Single Control Rod Withdrawal-Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.3.2 -------------------NOTE--------------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, are fully inserted.

PBAPS UNIT 2 3.10-8 Amendment No. 210

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal -Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, and subsequent removal of the associated control rod drive (CRD) if desired, provided the following requirements are met:

a. All other control rods are fully inserted;.

b. 1. LCO 3.9.2, 'Refuel Position One-Rod-Out Interlock,"

and LCO 3.9.4, "Control Rod Position Indication,"

OR

2. A control rod withdrawal block is inserted;

c. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b, 7, 12, 13, and 14 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY-Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed, at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 4 requirements, may be changed to allow the single control rod to be withdrawn to be assumed the highest worth control rod.

APPLICABILITY: MODE 4 with the reactor mode switch in the refuel position.

PBAPS UNIT 2 3.10-9 Amendment No. 210

Single Control Rod Withdrawal-Cold Shutdown 3.10.4 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION J REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 -------- NOTES--------

above requirements not 1. Required Actions met with the affected to fully insert control rod all insertable insertable. control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to Immediately fully insert all insertable control rods.

AND A.2.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

(continued)

PBAPS UNIT 2 3. 10-10 Amendment No. 210

Single Control Rod Withdrawal-Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the B.1 Suspend withdrawal of Immediately above requirements not the control rod and met with the affected removal of associated control rod not CRD.

insertable.

AND B.2.1 Initiate action to Immediately fully insert all control rods.

OR B.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.4.2 -------------------NOTE--------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn; in a five by five array centered on the control rod being withdrawn, are disarmed.

(continued)

- -PBAPS UNIT 2 3.10-11 Amendment No. 210

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, are fully inserted.

SR 3.10.4.4 ------------------ NOTE--------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

PBAPS UNIT 2 3. 10-12 Amendment No. 210

Single CRD Removal -Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10.5 Single Control Rod Drive (CRD) Removal-Refueling LCO 3.10.5 The requirements of LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation"; LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring"; LCO 3.9.1, "Refueling Equipment Interlocks"; LCO 3.9.2, "Refuel Position One Rod Out Interlock"; LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling," may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted;

b. All other control rods in a five by five array centered on the withdrawn control rod are disarmed;

c. A control rod withdrawal block is inserted and LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 5 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and

d. No other CORE ALTERATIONS are in progress.

APPLICABILITY: MODE 5 with LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend removal of Immediately above requirements not the CRD mechanism.

met. -

AND (continued)

PBAPS UNIT 2 3.10-13 Amendment No. 210

Single CRD Removal -Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to Immediately.

fully insert all control rods.

OR A.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD, are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD, in a five by five array centered on the control rod withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 (continued)

PBAPS UNIT,2 3.10-14 Amendment No. 210

Single CRD Removal -Refueling 3.10.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months PBAPS UNIT 2 3.10-15 Amendment No. 210

Multiple Control Rod Withdrawal -Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal -Refueling LCO 3.10.6 The requirements of LCO 3.9.3, "Control Rod Position";

LCO 3.9.4, Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling," may be suspended, and the 'full in' position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met:

a. The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted; and

c. Fuel assemblies shall only be loaded in compliance with an approved spiral reload sequence.

APPLICABILITY: MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend withdrawal of Immediately

- above requirements not control rods and met. removal of associated CRDs.

AND A.2 Suspend loading fuel Immediately assemblies.

AND (continued)

PBAPS UNIT-2 3.10-16 Amendment No. 210

Multiple Control Rod Withdrawal -Refueling 3.10.6 ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to Immediately fully insert all control rods in core cells containing one or more fuel assemblies.

OR A.3.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months containing one or more fuel assemblies are fully inserted.

SR 3.10.6.3 -------------------NOTE--------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months compliance with an approved spiral reload sequence.

PBAPS UNIT-2 3.10-17 Amendment No. 210

Control Rod Testing-Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing-Operating LCO 3.10.7 The requirements of LCO 3.1.6, "Rod Pattern Control," may be suspended to allow performance of SDM demonstrations, control rod scram time testing, control rod friction testing, and the Startup Test Program, provided:

a. The banked position withdrawal sequence requirements of SR 3.3.2.1.8 are changed to require the control rod sequence to conform to the specified test sequence.

OR

b. The RWM is bypassed; the requirements of LCO 3.3.2.1, "Control Rod Block Instrumentation," Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

APPLICABILITY: MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend performance Immediately LCO not met. of the test and exception to LCO 3.1.6.

PBAPS UNIT 2 3.10-18 Amendment No. 210

Control Rod Testing-Operating 3.10.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.7.1 -------------------NOTE--------------------

Not required to be met if SR 3.10.7.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the specified test by a second licensed operator or other qualified member of the technical staff.

1 SR 3.10.7.2 -------------------NOTE--------------------

Not required to be met if SR 3.10.7.1 satisfied.

Verify control rod sequence input to the Prior to RWM is in conformance with the approved control rod control rod sequence for the specified movement test.

PBAPS UNIT 2 3. 10-19 Amendment No. 210

SDM Test -Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test -Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a, I 2.d and 2.e of Table 3.3.1.1-1;

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation,"

MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, OR

2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode;

e. No other CORE.ALTERATIONS are in progress; and

f. CRD charging water header pressure k 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

PBAPS UNIT 2 3.10-20 Amendment No 24.2-9.8,232

SDM Test-Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------NOTE--------- A.1 --------NOTE---------

Separate Condition Rod worth minimizer entry is allowed for may be bypassed as each control rod. allowed by LCO

_--_ _3.3.2.1, "Control Rod Block One or more control Instrumentation," if rods not coupled to required, to allow its associated CRD. insertion of inoperable control rod and continued operation.

Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control rod.

AND A.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

B. One or more of the B.1 Place the reactor Immediately above requirements not mode switch in the met for reasons other shutdown or refuel than Condition A. position.

PBAPS UNIT 2 -- 3.10-21 Amendment No. 210

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to I LCO 3.3.1.1, Functions 2.a, 2.d and 2.e of the applicable Table 3.3.1.1-1. SRs SR 3.10.8.2 -------------------NOTE--------------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1. the applicable SRs SR 3.10.8.3 -------------------NOTE--------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

(continued)

PBAPS UNIT 2 3.10-22 Amendment No.20Q, 232

SDM Test-Refueling 3.10.8 SURVEILLANCE REOUIREMENTS continued' SURVEILLANCE FREQUENCY l

SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to

'full out, position Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days 2 940 psig. I PBAPS UNIT 2 3.10-23 Amendment No.-HO*v 211

Design Features Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries shall be as shown in Figure 4.1-1.

4.1.2 Low Population Zone (LPZ)

The LPZ shall be a 7300 meter radius from the plant stack.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 185 cruciform shaped control rod assemblies. The control materials shall be boron carbide and hafnium metal as approved by the NRC.

(continued)

PBAPS UNIT 2 4.0-1 Amendment No. 210

Design Features Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum k-infinity of 1.362 in the normal reactor core configuration at cold conditions;

b. k ff 5 0.95 if fully flooded with unborated water, wtich includes an allowance for uncertainties as described in Section 10.3 of the UFSAR; and

c. A nominal 6.280 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.1.2 The new fuel storage racks shall not be used for fuel storage. The new fuel shall be stored in the spent fuel storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below plant elevation 219 ft.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3819 fuel assemblies.

PBAPS UNIT 2 4.0-2 Amendment No. 210

Design Features 4.0 e '4 I

Figure 4.1-1 (page 1 of 1)

Site and Exclusion Area Boundaries PBAPS UNIT 2 4.0-3 Amendment No. 228

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The Plant Manager or his designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.

5.1.2 The Shift Supervisor shall be responsible for the control room command function. During any absence of the Shift Supervisor from the control room while the unit is in MODE 1, 2, or 3, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.

During any absence of the Shift Supervisor from the control room while the unit is in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

Q' PBAPS UNIT 2 5 .0-1 Amendment No. 210

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the UFSAR;

b. The Plant Manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c. The Vice President-Peach Bottom Atomic Power Station shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall also include the following:

(continued)

PBAPS UNIT-27-- 5.0-2 Amendment No. 210

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

a. A total of five non-licensed Operators shall be assigned for PBAPS Units 2 and 3 at all times.

I

b. Each on-duty shift crew composition may be less than the I minimum requirements of 10 CFR 50.54(m)(2)(i) and Specification 5.2.2.a and 5.2.2.f for a period of time not to I exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. An individual qualified in radiation protection procedures I shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., licensed Senior Reactor Operators (SROs), licensed Reactor Operators (ROs), health physicists, non-licensed operators, and key maintenance personnel).

I (continued)

PBAPS UNIT 2 5.0-3 Amendment No. 240

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviation from the above guidelines shall be authorized in advance by the Plant Manager or the Plant Manager's designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation. Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

e. The Senior Manager-Operations or an Operations Manager shall hold an SRO license.

f. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

PBAPS UNIT 2 5.0-4 Amendment No. 240

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions described in the UFSAR, with the following exceptions: 1) the Manager-Radiation Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-02-100, dated June 19, 2002), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

PBAPS UNIT 2 5.0- 5 Amendment No. 245

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 1972;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.

PBAPS UNIT 2 5.0-6 Amendment No. 210

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release reports required by Specification 5.6.2 and Specification 5.6.3.

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2. Shall become effective after review and acceptance by the Plant Operations Review Committee and the approval of the Plant Manager; and (continued)

PBAPS UNIT 2- 5.0-7 Amendment No. 210

Manuals Programs and Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. System leak test requirements for each system, to the extent permitted by system design and radiological conditions, at refueling cycle intervals or less.

5.5.3 Post Accident Sampling This program provides controls that ensure the capability to obtain and analyze reactor coolant and containment atmosphere samples under accident conditions and radioactive iodine and particulates in plant gaseous effluents under accident conditions.

The program shall include the following:

a. Training of personnel;

b. Procedures for sampling and analysis; and

c. Provisions for maintenance of sampling and analysis equipment.

(continued)

PBAPS UNIT 2 5.0-8 Amendment No. 210

Programs and Manuals Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions from liquid radioactive effluents and determination of cumulative dose contributions from gaseous radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when projected doses averaged over one month would exceed 0.12 mrem to the total body or 0.4 mrem to any organ (combined total from the two reactors at the site);

g. Limitations to ensure gaseous effluents shall be processed, prior to release, through the appropriate gaseous effluent treatment systems as described in the ODCM; (continued)

PBAPS UNIT- 5.0-9 Amendment No. 210

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls ProQram (continued)

h. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and

2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives

> 8 days: less than or equal to a dose rate of 1500 mrems/yr to any organ;

i. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

j. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

k. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Table 4.2.4, cyclic and transient occurrences to ensure that components are maintained within the design limits.

PBAPS UNIT 2 5. 0-10 Amendment No. 240

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 732 days

b. The provisions of SR 3.0.2 are applicable to the Frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

5.5.7 Ventilation Filter Testing Program (VFTP)

The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems.

Tests described in Specifications 5.5.7.a, 5.5.7.b, and 5.5.7.c shall be performed:

(continued)

PBAPS UNIT 2 5.0-11 Amendment No. 210

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Program (VFTP) (continued)

1) Once per 12 months for standby service or after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation; and,

2) After each complete or partial.replacement of the HEPA filter train or charcoal adsorber filter; after any structural maintenance on the system housing; and, following significant painting, fire, or chemical release in any ventilation zone communicating with the system while it is in operation.

Tests described in Specifications 5.5.7.d and 5.5.7.e shall be performed once per 24 months.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

a. Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass

< 1.0% when tested in accordance with Regulatory Guide 1.52, Revision 2, Section 5c, and-ASME N510-1989, Sections 6 I (Standby Gas Treatment (SGT) System only) and 10, at the system flowrate specified below.

ESF Ventilation System Flowrate (cfm)

SGT System 7200 to 8800 Main Control Room Emergency 2700 to Ventilation (MCREV) System 3300 -

(continued)

PBAPS UNIT 2 5.0-12 endment No.-40,

.. 421 3

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 1.0% when tested in accordance with Regulatory Guide 1.52, Revision 2, Section 5d, and ASME N510-1989, Sections 6 (SGT System only) and 11, at the system flowrate specified below.

ESF Ventilation System Flowrate (cfm)

SGT System 7200 to 8800 MCREV System 2700 to 3300

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, Section 6b, shows the methyl iodide penetration less than the value specified below when tested in accordance with the laboratory testing criteria of ASTM D3803-1989 at a temperature of 30 degrees C [86 degrees F], face velocity, and the relative humidity specified below.

ESF Ventilation System SGT System MCREV System Penetration 5 5

(%)

Face Velocity 60 57 (FPM)

Relative Humidity: 70 95

(%)

(continued)

PBAPS UNIT 2 5.0-13 Amendment No. R-9, DE-,

237

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Program (VFTP) (continued)

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters (if installed), and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Ventilation System Delta P (inches wc) Flowrate (cfm)

SGT System < 3.9 7200 to 8800 MCREV System <8 2700 to 3300

e. Demonstrate that the heaters for the SGT System dissipate 2 40 kw.

5.5.8 ExDlosive Gas Monitoring Program This program provides controls for potentially explosive gas mixtures contained downstream of the off-gas recombiners.

The program shall include:

a. The limit for the concentration of hydrogen downstream of the off-gas recombiners and a surveillance program to ensure the limit is maintained. This limit shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas Monitoring Program surveillance frequencies.

5.5.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

(continued)

PBAPS UNIT 2 5.0-14 Amendment No. 210

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Diesel Fuel Oil Testing Program (continued)

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within limits,

2. kinematic viscosity, when required, and a flash point within limits for ASTM 2-D fuel oil, and

3. a clear and bright appearance with proper color or a water and sediment content within limits;

b. Other properties for ASTM 2-D fuel oil are within limits, within 31 days following sampling and addition to storage tanks; and

c. Total particulate concentration of the fuel oil is

10 mg/l when tested every 31 days in accordance with ASTM D2276, Method A, except that the filters specified in the ASTM method may have a nominal pore size of up to three (3) microns.

5.5.10 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:

A change in the TS incorporated in the license; or A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

(continued)

PBAPS UNIT 2 5.0 -15 Amendment No. 2--, 242

Programs and Manuals Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Technical Specifications (TS) Bases Control Program (continued)

d. Proposed changes that meet the criteria of b. above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.11 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.

a. The SFDP shall contain the following:

1. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

2. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

3. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

4. Other appropriate limitations and remedial or compensatory actions.

b. A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

(continued)

PBAPS UNIT 2 5.0-16 Amendment No. 210

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination ProQram (SFDP) (continued)

1. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

2. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

3. A required system redundant to support system(s) for the supported systems (b.1) and (b.2) above is also inoperable.

c. The SFDP identifies where a loss of safety function exists.

If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate

.<wri testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01,.Rev. 0, "Industry Guideline for Implementing Performance-Based-Option of 10 CFR Part 50, Appendix J." Section 10.2:

a. MSIV leakage is excluded from the combined total of 0.6 L.

for the Type B and C tests.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 49.1 psig.

The maximum allowable primary containment leakage rate, L., at P.,

shall be 0.5% of primary containment air weight per day.

Leakage Rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is s 1.0 L.. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 L.for the Type B and Type C tests and s

> 0.75 L.for Type A tests; (continued)

PBAPS UNIT 2 5.0-17 Amendment No. 223

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

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is s 9000 scc/min when tested at 2 P..

c. MSIV leakage acceptance criteria are as specified in SR i 3.6.1.3.14.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

PBAPS UNIT 2 5.0-18 Amendment No- 223

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation ExDosure Report

__---------------NOTE-------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving an annual deep dose equivalent > 100 mrem and the associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescence dosimeter (TLD), or film badge measurements. Small exposures totalling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report shall be submitted by March 31 of each year.

5.6.2 Annual Radiological Environmental ODerating Report

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

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 31 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring activities for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

(continued)

PBAPS UNIT 2 5. 0-19 Amendment No. _Lqk7l

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radioloqical Environmental ODerating Report. (continued)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

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

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Monthly ODerating Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis nolater than the 15th of each month following the calendar month covered by the report.

(continued)

PBAPS UNIT 2 5.0-20 Amendment No.-h 14l

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

2. The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.1;

3. The Linear Heat Generation Rate for Specification 3.2.3; and

4. The Control Rod Block Instrumentation for Specification 3.3.2.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version as specified in the COLR);

2. NEDC-32162P, "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Units 2 and 3," Revision 2, March, 1995;

3. PECo-FMS-0001-A, "Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code";

4. PECo-FMS-0002-A, "Method for Calculating Transient Critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPECo)";

5. PECo-FMS-0003-A, "Steady-State Fuel Performance Methods Report";

6. PECo-FMS-0004-A, "Methods for Performing BWR Systems Transient Analysis";

(continued) -

PBAPS UNIT-2 5.0-21 Amendment No. 2l9,244, 236

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

7. PECo-FMS-0005-A, "Methods for Performing BWR Steady-State Reactor Physics Analysis"; and

8. PECo-FMS-0006-A, "Methods for Performing BWR Reload Safety Evaluations."

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

PBAPS UNIT 2 5.0-22 Amendment No. D214Il

High Radiation Areas 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Areas As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates not Exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation):

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit {RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area ("radiation monitoring and indicating device"), or

2. A-radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached

("alarming dosimeter"), with an appropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)

PPAPS TTUTM 2 5.0-23 Amendment No. 240

High Radiation Areas 5.7 5.7 High Radiation Areas 5.7.1 High Radiation Areas with Dose Rates not Exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation): (continued)

4. A self-reading dosimeter (e.g., pocket ion chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel radiation exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel shall receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation). but less than 500 rads/hour (at 1 meter from the radiation source or from any surface penetrated by the radiation)

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents-unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

PBAPS UNIT 2 5.0-24 Amendment No. 240

High Radiation Areas 5.7 5.7 High Radiation Areas 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface nenetrated by the radiation). but less than 500 rads/hour (at 1 meter from the radiation source or from any surface penetrated by the radiation) (continued)

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual (whether alone or in a group) entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3. A self-reading dosimeter (e.g., pocket ion chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continually displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or PBAPS UNIT 2 5.0-25 Amendment No. 240

High Radiation Areas 5.7 5.7 High Radiation Areas 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation), but less than 500 rads/hour (at 1 meter from the radiation source or from any surface nenetrated by the radiation) (continued)

(ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where the options of Specifications 5.7.2.d.2 and 5.7.2.d.3, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable, principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel shall receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

PBAPS UNIT 2 5X0-26 Amendment No. 240

ML031150536

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