Text

Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
	ML17030A302
Person / Time
Site:	Peach Bottom
Issue date:	01/30/2017
From:	Jim Barstow; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML17030A302 (248)
	v • d • e

Exelon Generation ~

200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 January 30, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 N RC Docket Nos. 50-277 and 50-278

Subject:

Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGG) requests an amendment to the Technical Specifications (TS} for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3.

The proposed changes replace existing Technical Specifications (TS} requirements related to "operations with a potential for draining the reactor vessel" (OPDRVs) with new requirements on Reactor Pressure Vessel Water Inventory Control (RPV WIG) to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor vessel water level to be greater than the top of active irradiated fuel.

EGG has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 10 CFR 50.92.

The proposed changes have been reviewed by the PBAPS Plant Operations Review Committee in accordance with the requirements of the EGG Quality Assurance Program.

This amendment request contains no regulatory commitments.

Attachment 1 provides an evaluation of the proposed changes. Attachment 2 provides the existing TS pages marked up to show the proposed changes. Attachment 3 provides the existing Bases pages marked up to show the proposed changes (information only).

EGG requests approval of the proposed amendment by September 30, 2017 in support of the Fall 2017 Unit 3 refueling outage. Once approved, the amendments shall be implemented on both units prior to the next refueling outage on either unit.

U.S. Nuclear Regulatory Commission Application to Revise TS to Adopt TSTF-542 Docket Nos. 50-277 and 50-278 January 30, 2017 Page2 In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), EGC is notifying the Commonwealth of Pennsylvania of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official.

If you have any questions or require additional information, please contact Stephanie J.

Hanson at (610) 765-5143.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 301h day of January 2017.

Respectfully, 9 ~ IJ[;:

James Barstow Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments: 1. Evaluation of Proposed Changes

2. Markup of Technical Specifications Pages

3. Markup of Technical Specifications Bases Pages (For Information Only) cc: USNRC Region I, Regional Administrator w/ attachments USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Pennsylvania Bureau of Radiation Protection S. T. Gray, State of Maryland

ATTACHMENT 1 Evaluation of Proposed Changes Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278

Subject:

Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2

1.0 DESCRIPTION

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation 2.2 Variations

3.0 REGULATORY ANALYSIS

3.1 NO SIGNIFICANT HAZARDS CONSIDERATION

4.0 ENVIRONMENTAL CONSIDERATION

5.0 REFERENCES

Evaluation of Proposed Change Attachment 1 Application to Revise TS to Adopt TSTF-542 Page 1 of 5 Docket Nos. 50-277 and 50-278

1.0 DESCRIPTION

Exelon Generation Company, LLC (EGC), proposes changes to the Technical Specifications (TS), Appendix A of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, respectively.

The proposed changes replace existing Technical Specifications (TS) requirements related to "operations with a potential for draining the reactor vessel" (OPDRVs) with new requirements on Reactor Pressure Vessel Water Inventory Control (RPV WIC) to protect Safety Limit 2.1.1.3.

Safety Limit 2.1.1.3 requires reactor vessel water level to be greater than the top of active irradiated fuel.

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation EGC has reviewed the safety evaluation provided to the Technical Specifications Task Force on December 20, 2016, as well as the information provided in TSTF-542. EGC has concluded that the justifications presented in TSTF-542 and the safety evaluation prepared by the NRG staff are applicable to Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, and justify this amendment for the incorporation of the changes to the PBAPS TS.

The following PBAPS TS reference or are related to OPDRVs and are affected by the proposed changes:

3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation 3.3.6.1 Primary Containment Isolation Instrumentation 3.3.6.2 Secondary Containment Isolation Instrumentation 3.3.7.1 Main Control Room Emergency Ventilation (MCREV) System Instrumentation 3.5.2 ECCS - Shutdown 3.6.1.3 Primary Containment Isolation Valves (PCIVs) 3.6.4.1 Secondary Containment 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) 3.6.4.3 Standby Gas Treatment (SGT) System 3.7.4 Main Control Room Emergency Ventilation (MCREV) System 3.8.2 AC Sources - Shutdown 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown 2.2 Variations EGC is proposing the following variations from the TS changes described in TSTF-542. These variations do not affect the applicability of TSTF-542 or the NRG staff's safety evaluation to the proposed license amendment.

EGC proposes to change the number for the OPDRV TS to TS 3.5.4 and the Instrumentation section to TS 3.3.5.4 for consistency purposes. These differences are administrative and do not affect the applicability of TSTF-542 to the PBAPS TS.

Evaluation of Proposed Change Attachment 1 Application to Revise TS to Adopt TSTF-542 Page 2 of 5 Docket Nos. 50-277 and 50-278 PBAPS design for RWCU isolation is on Reactor Vessel Water Level - Low (Level 3), not Reactor Vessel Water Level - Low, Low (Level 2). Therefore, it is appropriate to revise PBAPS TS Table 3.3.5.4.-1 to reflect this design difference for PBAPS.

EGG proposes to revise PBAPS TS Surveillance Requirement (SR) 3.5.4.8 and TS Bases 3.3.5.4 to clarify that for manual initiations PBAPS utilizes hand switches in lieu of push buttons.

EGG is proposing to add a note to TS Table 3.3.5.4-1 (RPV WIG Instrumentation) to clarify the intent of allowing credit for an OPERABLE Low Pressure Coolant Injection subsystem when it is aligned and operating in the decay heat removal mode of RHR. This is appropriate since the associated RHR pump minimum flow valve (while operating in the decay heat removal mode) is closed and deactivated to prevent inadvertent vessel drain down events. Because the minimum flow valve is closed and deactivated, the associated TS Table 3.3.5.4-1 Function 2.b would not be required to be OPERABLE. Without the note, TS 3.3.5.4 Condition D would require that the associated RHR pump be declared inoperable, which would be contrary to the intent of the LCO 3.5.4 Note which allows the LPCI subsystem to be OPERABLE when aligned for decay heat removal.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Determination Exelon Generation Company, LLC (EGG), proposes changes to the Technical Specifications (TS), Appendix A of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, respectively.

EGG requests adoption of TSTF-542 "Reactor Pressure Vessel Water Inventory Control," which is an approved change to the Standard Technical Specifications (STS}, into the PBAPS TS.

The proposed amendment replaces the existing requirements in the TS related to "operations with a potential for draining the reactor vessel" (OPDRVs) with new requirements on Reactor Pressure Vessel Water Inventory Control (RPV WIG) to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor vessel water level to be greater than the top of active irradiated fuel.

EGG has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed changes replace existing TS requirements related to OPDRVs with new requirements on RPV WIG that will protect Safety Limit 2.1.1.3. Draining of RPV water inventory in Mode 4 (i.e., cold shutdown) and Mode 5 (i.e., refueling) is not an accident previously evaluated and, therefore, replacing the existing TS controls to prevent or mitigate such an event with a new set of controls has no effect on any accident previously evaluated. RPV water inventory control in Mode 4 or Mode 5 is not an initiator of any accident previously evaluated. The existing OPDRV controls or the proposed RPV WIG controls are not mitigating actions assumed in any accident previously evaluated.

Evaluation of Proposed Change Attachment 1 Application to Revise TS to Adopt TSTF-542 Page 3 of 5 Docket Nos. 50-277 and 50-278 The proposed changes reduce the probability of an unexpected draining event (which is not a previously evaluated accident) by imposing new requirements on the limiting time in which an unexpected draining event could result in the reactor vessel water level dropping to the top of the active fuel (TAF). These controls require cognizance of the plant configuration and control of configurations with unacceptably short drain times.

These requirements reduce the probability of an unexpected draining event. The current TS requirements are only mitigating actions and impose no requirements that reduce the probability of an unexpected draining event.

The proposed changes reduce the consequences of an unexpected draining event (which is not a previously evaluated accident) by requiring an Emergency Core Cooling System (ECCS) subsystem to be operable at all times in Modes 4 and 5. The current TS requirements do not require any water injection systems, ECCS or otherwise, to be Operable in certain conditions in Mode 5. The change in requirement from two ECCS subsystems to one ECCS subsystem in Modes 4 and 5 does not significantly affect the consequences of an unexpected draining event because the proposed Actions ensure equipment is available within the limiting drain time that is as capable of mitigating the event as the current requirements. The proposed controls provide escalating compensatory measures to be established as calculated drain times decrease, such as verification of a second method of water injection and additional confirmations that containment and/or filtration would be available if needed.

The proposed changes reduce or eliminate some requirements that were determined to be unnecessary to manage the consequences of an unexpected draining event, such as automatic initiation of an ECCS subsystem and control room ventilation. These changes do not affect the consequences of any accident previously evaluated since a draining event in Modes 4 and 5 is not a previously evaluated accident and the requirements are not needed to adequately respond to a draining event.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed changes replace existing TS requirements related to OPDRVs with new requirements on RPV WIG that will protect Safety Limit 2.1.1.3. The proposed changes will not alter the design function of the equipment involved. Under the proposed changes, some systems that are currently required to be operable during OPDRVs would be required to be available within the limiting drain time or to be in service depending on the limiting drain time. Should those systems be unable to be placed into service, the consequences are no different than if those systems were unable to perform their function under the current TS requirements.

The event of concern under the current requirements and the proposed changes are an unexpected draining event. The proposed changes do not create new failure mechanisms, malfunctions, or accident initiators that would cause a draining event or a new or different kind of accident not previously evaluated or included in the design and licensing bases.

Evaluation of Proposed Change Attachment 1 Application to Revise TS to Adopt TSTF-542 Page 4 of 5 Docket Nos. 50-277 and 50-278 Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed changes replace existing TS requirements related to OPDRVs with new requirements on RPV WIG. The current requirements do not have a stated safety basis and no margin of safety is established in the licensing basis. The safety basis for the new requirements is to protect Safety Limit 2.1.1.3. New requirements are added to determine the limiting time in which the RPV water inventory could drain to the top of the fuel in the reactor vessel should an unexpected draining event occur. Plant configurations that could result in lowering the RPV water level to the TAF within one hour are now prohibited. New escalating compensatory measures based on the limiting drain time replace the current controls. The proposed TS establish a safety margin by providing defense-in-depth to ensure that the Safety Limit is protected and to protect the public health and safety. While some less restrictive requirements are proposed for plant configurations with long calculated drain times, the overall effect of the change is to improve plant safety and to add safety margin.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above, EGG concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

4.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

Evaluation of Proposed Change Attachment 1 Application to Revise TS to Adopt TSTF-542 Page 5 of 5 Docket Nos. 50-277 and 50-278

5.0 REFERENCES

1. TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control," dated December 29, 2016.

2. Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control" {TAC No. MF3487)

ADAMS Accession No. ML163438065

ATTACHMENT2 Markup of Technical Specifications Pages Peach Bottom Atomic Power Station Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278 Revised Technical Specifications Pages Unit 2 TS Pages 3.3-58 3.6-35 ii 3.3-59 3.6-36 1.1-3 3.5-1 3.6-38 3.3-32 3.5-8 3.6-40 3.3-33 3.5-9 3.6-41 3.3-35 3.5-10 3.7-7 3.3-39 3.5-11 3.7-8 3.3-40 3.5-12 3.7-9 3.3-47a* 3.5-15* 3.8-21 3.3-47b* 3.5-16* 3.8-22 3.3-47c* 3.5-17* 3.8-23 3.3-47d* 3.5-18* 3.8-35 3.3-50 3.6-12 3.8-44 3.3-54 3.6-34 3.8-45 Unit 3 TS Pages 3.3-58 3.6-35 ii 3.3-59 3.6-36 1.1-3 3.5-1 3.6-38 3.3-32 3.5-8 3.6-40 3.3-33 3.5-9 3.6-41 3.3-35 3.5-10 3.7-7 3.3-39 3.5-11 3.7-8 3.3-40 3.5-12 3.7-9 3.3-47a* 3.5-15* 3.8-21 3.3-47b* 3.5-16* 3.8-22 3.3-47c* 3.5-17* 3.8-23 3.3-47d* 3.5-18* 3.8-35 3.3-50 3.6-12 3.8-44 3.3-54 3.6-34 3.8-45

New TS Page

TABLE OF CONTENTS 1.0 USE AND APPLICATION ........................................... 1 .1-1 1.1 Defi ni ti ans ............................................... 1 . 1 -1

1. 2 Logical Connectors ........................................ 1. 2-1 1.3 Completion Times .......................................... 1.3-1 1.4 Frequency ................................................. 1 . 4-1 2.0 SAFETY LIMITS (SLs) ........................................... 2. 0-1 2 .1 SLs .... . ............ . ................................. 2.0-1 2.2 SL Violations ............................................. 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................... 3.0-4 3 .1 REACTIVITY CONTROL SYSTEMS ................................ 3.1-1

3. 1 . 1 SHUTDOWN MARGIN (SDM) ................................. 3.1-1 3.1 .2 Reactivity Anomalies .................................. 3.1-5 3.1 .3 Control Rod OPERABILITY ............................... 3.1-7 3.1 .4 Control Rod Scram Times ............................... 3.1-12 3.1 .5 Control Rod Scram Accumulators ........................ 3.1-15 3.1 .6 Rod Pattern Control ................................... 3.1-18 3.1 .7 Standby Liquid Control (SLC) System ................... 3.1-20 3.1 .8 Scram Discharge Volume (SDV) Vent and Drain Valves .... 3.1-26 3.2 POWER DISTRIBUTION LIMITS ... . ............................. 3.2-1

3. 2 .1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........................................... 3. 2-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) ................... 3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) ................... 3.2-4 3.3 INSTRUMENTATION ........................................... 3. 3-1 3.3.1 .1 Reactor Protection System (RPS) Instrumentation ....... 3.3-1 3.3.1 .2 Wide Range Neutron Monitor (WRNM) Instrumentation ..... 3.3-10 3.3.2.1 Control Rod Block Instrumentation ..................... 3.3-16 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation .................................... 3.3-22

3. 3 .3.1 Post Accident Monitoring (PAM) Instrumentation ........ 3.3-24 3.3.3.2 Remote Shutdown System ................................ 3.3-27 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ............... 3.3-29 3.3.4.2 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation ............. 3.3-31a thru 3.3-31c 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .. 3.3-32 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation .................................... 3. 3-44 3.3.5.3 Not Used .............................................. 3. 3. 47a 3.3.5.4 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation ........................... . ........ 3. 3. 47b 3.3.6.1 Primary Containment Isolation Instrumentation ......... 3.3-48 3.3.6.2 Secondary Containment Isolation Instrumentation ....... 3.3-55

3. 3. 7 .1 Main Control Room Emergency Ventilation (MCREV)

System Instrumentation ............................. 3.3-59 3.3.8.1 Loss of Power (LOP) Instrumentation ................... 3.3-61 3.3.8.2 Reactor Protection System (RPS) Electric Power Mani tori ng ............................................ 3. 3-66 (continued)

PBAPS UNIT 2 Amendment No. 225

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) . ........................ ..... 3.4-1

3. 4.1 Recirculation Loops Operating ......................... 3.4-1 3.4.2 Jet Pumps ............................................. 3. 4-6 3.4.3 Safety Relief Valves (SRVs) and Safety Valves (SVs) ... 3.4-8 3.4.4 RCS Operational LEAKAGE ............................... 3.4-10 3.4.5 RCS Leakage Detection Instrumentation ................. 3.4-12 3.4.6 RCS Specific Activity ................................. 3.4-14 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown ............................... 3.4-16 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown .............................. 3.4-19 3.4.9 RCS Pressure and Temperature (P/T) Limits ............. 3.4-21 3.4.10 Reactor Steam Dome Pressure ........................... 3.4-28 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) , RPV WATER INVENTORY CONTROL (WIC), AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 5-1

3. 5 .1 ECCS - Operating ....................................... 3.5-1 3.5.2 EGGS - Shutdewn Deleted ................................. 3.5-8 3.5.3 RCIC System ........................................... 3. 5-12 3.5.4 RPV Water Inventory Control .. . ...... . ................ . 3 .5- 13 3.6 CONTAINMENT SYSTEMS ....................................... 3. 6-1

3. 6 .1 . 1 Primary Containment ................................... 3. 6-1 3.6.1 .2 Primary Containment Air Lock .......................... 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) .......... 3.6-8 3.6.1 .4 Drywall Air Temperature ............................... 3.6-17 3.6.1 .5 Reactor Building-to-Suppression Chamber Vacuum Breakers ........................................... 3.6-18 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ........ 3.6-21 3.6 .2.1 Suppression Pool Average Temperature .................. 3.6-23 3.6.2.2 Suppression Pool Water Level .......................... 3.6-26 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cool i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 6- 27 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .... 3.6-29 3.6.2.5 Residual Heat Removal (RHR) Drywell Spray ............. 3.6-30a 3.6.3.1 Deleted ............................................... 3.6-31 3.6.3.2 Primary Containment Oxygen Concentration .............. 3.6-33 3.6.4.1 Secondary Containment ............................. .. .. 3.6-34 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ........ 3.6-36 3.6.4.3 Standby Gas Treatment (SGT) System .................... 3.6-40 3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 -1 3.7.1 High Pressure Service Water (HPSW) System ............. 3.7-1 3.7.2 Emergency Service Water (ESW) System and Normal Heat Sink ......................................... 3. 7-3 3.7.3 Emergency Heat Sink ................................... 3.7-5 3.7.4 Main Control Room Emergency Ventilation (MCREV)

System ........... . ..... . .. . ..... . .................. 3.7-7 3.7.5 Main Condenser Offgas ................................. 3.7-10 (continued)

PBAPS UNIT 2 ii Amendment No. 288

Definitions 1.1 1.1 Definitions (continued)

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that

.....,n-s_e_rt_1..._...., RECIRCULATION PUMP TRIP time interval from initial signal generation by

....____ _~ ( EOC- RPTl SYSTEM RESPONSE the associated turbine stop valve limit switch or TIME from when the turbine control valve hydraulic oil control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywel l, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE A11 LEAKAGE into the drywel l that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE ( LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

(continued)

PBAPS UN IT 2 1. 1-3 Amendment No. ~

PBAPS TSTF-542, Rev 2 1.1 Definitions - Insert 1:

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming :

a) The water inventory above the TAF is divided by the limiting drain rate ;

b) The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate , or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e . g ., seismic event , loss of normal power ,

single human error) , for all penetration flow paths below the TAF except :

1 . Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked , sealed , or otherwise secured in the closed position , blank flanges , or other devices that prevent flow of reactor coolant through the penetration flow paths ;

2 . Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation ; or 3 . Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task ,

who in continuous communication with the control room , is stationed at the controls , and is capable of closing the penetration flow path isolation device without offsite power .

c) The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated , and no water is assumed to be subsequently added to the RPV water inventory ;

d) No additional draining events occur ; and e) Realistic cross-sectional areas and drain rates are used .

A bounding DRAIN TIME may be used in lieu of a calculated value .

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.l Emergency Core Cooling System (ECCS) Instrumentation LCD 3.3.5.l The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.l Enter the Condition Immediately inoperable. referenced in Table 3.3.5.1-1 for the channel.

B. As required by B.l - - - - - - - - NOTE-&- - - - - - - -

Required Action A.l 1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

-:-- Only appl i cable for Functions l.a, l.b, 2.a, and 2.b.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature feature ECCS initiation initiation capability capability in is inoperable. both trip systems (continued)

PBAPS UN IT 2 3.3-32 Amendment No. -2+-G

ECCS Instrumentation

3. 3. 5 .1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 --------NOTE---------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Coolant Injection discovery of

( HPC I) System loss of HPCI inoperable. initiation capability B.3 Pl ace channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C. As required by C.l - - - - - - - - NDTE.£- - - - - - - -

Required Action A.l 1. Onl)' applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

-:- Only applicable for Functions l.c, l.e, l.f, 2.c, 2.d, and

2. f.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS subsystem initiation capability initiation is inoperable. capability in both subsystems Alli2 C.2 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

PBAPS UN IT 2 3.3-33 Amendment No. l--G

ECCS Instrumentation

3. 3. 5 .1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E. 1 - - - - - - - - NOTE.£- - - - - - - -

Required Action A.1 1. Only appli cabl c and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

- Only appl i cable to Functions l.d and 2.g.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS subsystem initiation capability initiation is inoperable. cap ab i l i ty in both subsystems E.2 Restore channel to 7 days OPERABLE status.

(continued )

PBAPS UN IT 2 3 . 3-35 Amendment No. +G

ECCS Instrumentation 3.3.5.l Table 3.3.5 . 1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUN CTI ON CONDITIONS FUNCTION ACTION A. 1 REQUIREMENTS VALUE

1. Core Spray System

a. Reactor Vessel Water 1 , 2 , J, 4(0 ) B SR 3.3.5 . 1.1 ~ -160.0 Level -Low Low Low SR 3.3 . 5. 1.2 inches (Level 1) 4' a ) t 5'tt+ SR 3. 3.5 . 1.4 SR 3.3.5.1.5

b. Drywell 1' 2 , 3 4 \ DI B SR 3.3.5 . 1.1 :s; 2. 0 psig Pressure -High SR 3.3.5.1.2 SR 3.3 . 5. 1.4 SR 3.3.5.1.5

c. Reactor Pressure - Low , 2,3 c SR 3.3.5 . 1.1 ~ 425 . 0 psig (Injection Permissive) SR 3. 3.5.1.2 and SR 3.3.5.1.4 :s; 475 . a psig SR 3.3.5 . 1.5 4I a I ' 5'vt 4 -B -&R a.a .s. L > i! 425.B ~ s ig

-&R 3. 3 . 5 . L2 vfHI

-&R 3.3 . 5. !. 4 ~ psig

-&R 3 .3 . 5. 1. 5

d. Core Spray Pump ,2 , 3, 4 SR 3.3.5. 1. 2 ~ 319 . 0 psi d Discharge Flow -Low Cl per SR 3 .3.5 . 1.4 and (Bypass) 4 (al 5 (# pump ) :s; 351.0 psid

e. Core Spray Pump Start - 1, 2 , 3 4 c SR 3.3.5.1.4 ~ 5 .a seconds Time Delay Relay Closs Cl per SR 3.3.5.1.5 and of offsite power) 4 ' a l , 5' il+ pump ) :s; 7. 0 seconds

f. Core Spray Pump Start-Time Delay Relay (offs i te power available )

Pumps A,C 1,2. 3 2 c SR 3. 3.5 . 1.4 ~ 12 . 1 (1 per SR 3.3.5.1.5 seconds and pump ) :s; 13 . 9 seconds Pumps B,D 1. 2 ' 3 2 c SR 3.3 . 5.1.4 ~ 21 . 4 Cl per SR 3 .3. 5.1.5 seconds and pump ) :s; 24 . 6 seconds IDelett:::~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

(continued)

Cal \IP. e ~ asse ei ateEI ECCS Sijes;stem! s l are F e q~ir e a t e ~e BPERAB LE pe F l EB 3 .5. 2, HES S ~ H t EI - A Cb) Also required to initiate the associated diesel generator COGJ.

PBAPS UN IT 2 3.3-39 Amendment No. ~

ECCS Instrumentation

3. 3. 5. 1 Table 3 . 3 . 5 . 1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICAB LE CONDITIONS MOO ES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUN CTI ON CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. Low Pressure Coolant Injection (LPCIJ System

a. Reactor Vessel Water 1, 2 , J, B SR 3.3.5 . 1.1 ;:., -160 inches Leve 1 -Low Low Low SR 3.3.5 . 1.2 (Level ll 4 ca 1, 5 rtt SR 3.3.5 . 1.4 SR 3.3.5.1.5

b. Orywell , 2, 3 B SR 3.3.5.1.1 s 2.0 psig Pressure -High SR 3.3.5 . 1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Pressure -Low 1, 2 . 3 4 c SR 3 . 3.5.1.1 ;:., 425.0 psig (Injection Permissive) SR 3.3.5.1.2 and SR 3.3.5.l. l* s 475.0 psig SR 3.3.5.1.5 4 ~ 3.3.5.1.1

~ 3.3 . 5.l.2 a-ffil

~ 3.3.S.l.4 :S 475.9 ~Si~

~ 3.3.5 . 1.5

d. Reactor Pressure -Low 1lCJ ,2lC J 0 4 c SR 3.3.5.1.1 ;:., 211.0 psig Low (Recirculation SR 3 . 3.5.1.2 Discharge Valve SR 3.3.5 . 1.4 Permissive) SR 3.3.5.1.5

e. Reactor Vessel Shroud 1, 2 ,3 2 B SR 3.3.5 . 1.1 ;:., -226 . 0 Level -Level 0 SR 3.3.5 . 1.2 inches SR 3.3.5.1.4 SR 3.3.5 . 1.5

f. Low Pressure Cool ant 1, 2, 3, B c SR 3 . 3.5 . 1.4 Injection Pump (2 per SR 3.3.5 . 1.5 Start -Time Delay pump)

Relay (offsite power available )

Pumps A,B ;:., 1. 9 seconds and s 2 . 1 seconds Pumps C,D ;:., 7 . 5 seconds and s 8.5 seconds

g. Low Pressure Coolant 1. 2 . 3 4 SR 3.3.5.1.2 ;:., 299 . 0 psid Injection Pump (1 per SR 3.3.5.1.4 and Discharge Flow -Low pump ) SR 3.3.5.1.5 s 331.0 psid IDelet~----<B_y_pa-ss_l--------------------------------------------------------~

(continued)

(a ) \IAe R as see i atea EGGS s~llsyst em ( s ) are feEjtiiF e el te Ile QPE RAB LE ~eF l 69 3. 5. 2, EGES ShtHtl9\IR. ,,.(

!cl With associated recirculation pump discharge valve open .

PBAPS UN IT 2 3.3-40 Amendment No. ~

PBAPS TSTF-542, Rev 2 New PBAPS TS Section 3.3.5.3 3.3 . 5 . 3 3.3 INSTRUMENTATION 3.3.5.3 Not Used PBAPS UNITS 2 & 3 3 . 3-47a Amendment No . XXX

PBAPS TSTF-542, Rev 2 RPV Water Inventory Control Instrumentation 3.3.5.4 3.3 INSTRUMENTATION 3.3.5.4 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.4 The RPV Water Inventory Control instrumentation for each Function in Table 3 . 3 . 5 . 4- 1 shall be OPERABLE .

APPLICABILITY : According to Table 3 . 3 . 5 . 4-1 .

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

Separate Conditi o n entry is allowed for each channel .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A. 1 Enter the Condition Immediately inoperable . referenced in Table 3 . 3 . 5 . 4-1 for the channel .

B. As required by B. 1 Declare associated Immediately Required Action A . l penetration flow and referenced in path(s) incapable of Table 3 . 3 . 5 . 4 - 1. automatic isolation .

AND B. 2 Calculate DRAIN TIME . Immediately

c. As required by C. l Place channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action A . 1 trip .

and referenced in Table 3.3 . 5 . 4-1.

D. As required by D. 1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action A . l OPERABLE status and referenced in Table 3 . 3 . 5 . 4- 1.

(continued)

PBAPS UNITS 2 & 3 3 . 3-47b Amendment No . XXX

PBAPS TSTF-542, Rev 2 RPV Water Inventory Control Instrumentation 3.3.5.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E. l Declare associated Immediately associated Completion low pressure ECCS Time of Condition C or injection/spray D not met . subsystem inoperable .

SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3 . 3 . 5.4-1 to determine which SRs apply f o r each ECCS Function .

SURVEILLANCE FREQUENCY SR 3.3.5 . 4 . 1 Perform CHANNEL CHECK . In accordance with the Surveillance Frequency Control Program .

SR 3.3.5.4.2 Perform CHANNEL FUNCTIONAL TEST . In accordance with the Surveillance Frequency Control Program .

SR 3.3.5.4.3 Perform LOGIC SYSTEM FUNCTIONAL TEST . In accordance with the Surveillance Frequency Control Program .

(continued)

PBAPS UNITS 2 & 3 3 . 3 - 47c Amendment No . XXX

PBAPS TSTF-542, Rev 2 RPV Water Inventory Control Instrumentation 3.3.5.4 Table 3.3.5.4-1 (page 1 of 1)

RPV Water Inventory Control Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System

a. Reactor Pressure~ Low 4.5 4 c SR 3 . 3.5.4.1 2 425.0 psig (Injection Permissive) SR 3.3.5.4.2 and s. 475.0 psig

b. Core Spray Pump 4,5 1 per pump D SR 3.3.5.4.1 2 319.0 psid Discharge Flow--Low (a) SR 3.3.5.4.2 and s. 351.0 (Bypass) psid

c. Manual Initiation 4,5 1 per D SR 3 . 3 . 5.4.3 A subsystem (a)

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Pressure- Low 4,5 4 c SR 3.3.5.4.1 _ 425.0 psig (Injection Permissive) SR 3.3.5.4.2 and s. 475 . 0 psig

b. Low Pressure Coolant 4,5 1 per pump D SR 3 . 3 . 5 . 4.1 2 299 . 0 psid Injection Pump (a),(c) SR 3.3.5.4.2 and s. 331. 0 Discharge Flow - Low psid (Bypass)

c. Manua 1 Ini ti at ion 4,5 1 per D SR 3.3.5.4.3 NA subsystem (a)

3. RHR System Isolation

a. Reactor Vesse 1 (b) 2 B SR 3.3.5.4.1 ~ 1.0 inches Water Level - Low, SR 3.3.5.4.2 Level 3

4. Reactor Water Cleanup (RWCU) System Isolation

a. Reactor Vessel (b) 2 B SR 3.3.5.4.1 ~ 1.0 inches Water Level - Low, SR 3.3.5.4.2 Level 3 (a) Associated with an ECCS subsystem required to be OPERABLE by LCD 3.5.4, "Reactor Pressure Vessel Water Inventory Control."

(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME .

(c) Function not required to be OPERABLE while associated pump is operating in decay heat removal when minimum flow valve is closed and deactivated.

PBAPS UNITS 2 & 3 3 . 3 - 47d Amendment No . XXX

Primary Containment Isolation Instrumentation

3. 3. 6 .1 ACTIONS (continued)

COND ITION REQUIRED ACT ION COMPLETION TIME H. As required by H.l Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.l standby liquid and referenced in control CS LC)

Table 3.3.6.1-1. subsystem inoperable.

.QR H.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup System.

I. As required by I. 1 Initiate action to Immediately Required Action C.l restore channel to and referenced in OPERABLE status.

Table 3.3.6.1-1.

!tR

~ IRitiate aetieA te Immediately iselate the Residual Heat Reme1;1al ( RHR~

Shutde*..*R Ce el i Ag System .

J. As required by J.l Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action C.l penetration fl ow and referenced in path(s).

Table 3.3.6.1-1.

PBAPS UN IT 2 3.3-50 Amendment No. ~

Primary Containment Isolation Instrumentation 3.3.6.l Table 3.3 . 6. 1-1 (page 3 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REOU I RED REFERENCED OTHER CHANNELS FROM SPEC! FI ED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.l REQUIREMENTS VALUE

s. Reactor Water Cleanup RWCUJ System Isolation

a. IT}Rwcu Flow-High 1 ,2,3 SR 3.3.6.1.l s 125% rated SR 3.3.6.1.3 flow (23.0 SR 3.3.6.1.7 in-we)

b. SLC System Initiation 1,2,3 H SR 3.3.6.1. 7 NA

c. Reactor Vessel Water l. 2. 3 2 F SR 3.3.6.1.l " 1. 0 inches Level-Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.l.S SR 3.3.6.1.7

6. RHR Shutdown Cooling System Isolation

a. Reactor Pressure-High 1,2 ,3 F SR 3.3.6.1.3 s 70.0 psig SR 3.3.6.1.7 2.Ltt

b. Reactor Vessel Water 3,-4,-5 SR 3. 3.6 .1. 1 " 1.0 inches Level - Low (Level 3l SR 3.3.6.1. 2 SR 3.3.6.1.5 SR 3.3.6.1.7

7. Feedwater Recirculation Isolation

a. Reactor Pressure-High l ,2.3 2 F SR 3.3.6.1.l s 600 psi g SR 3.3.6 . 1.2 SR 3.3.6.l.5 SR 3.3.6.1.7 B. Traversing Incore Probe Isolation

a. Reactor Vessel Water I. 2 . 3 2 J SR 3.3.6.1.l ~ 1.0 inches Level - Low (Level 3) SR 3.3.6.l.2 SR 3.3.6 . l . S SR 3.3.6.1.7

b. Drywell Pressure-High 1,2,3 2 J SR 3.3.6.1.l s 2.0 psig SR 3.3.6.1.2 Delete~========================================================~

SR 3.3.6.1.5 SR 3.3.6.l . 7 I

(a) IA t19 El ES 4 aAa S, f:lFeoiE!ee RllR s~~tEle*.rn Gee li Ag S;*s t eA! i ntegPit} i s A!ain taineEI , en1; ene eflaAne 1 f:)el' tFif:l s;steA! **i tll an iselatien si gnal a*1ailae le te ene s~~tfl-e1m eeeling ~utl'~ s~etien i se ' atieA 1ahe ' s Feq~ i rea .

PBAPS UN IT 2 3.3 - 54 Amendment No. ~

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of ll Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPEC! FI ED PER SURVEILLANCE ALLOWABLE FUN CTI ON CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1'2 '3;- SR 3.3.6.2.1 ;,: 1.0 inches Leve 1 -Low (Leve 1 3 J +.rt SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

2. Drywel l Pressure -High 1, 2 , 3 2 SR 3.3.6.2.1 ,;; 2.0 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

3. Reactor Building 1'2 '3' 2 SR 3.3.6.2.1 ,;; 16.0 mR/hr Ventilation Exhaust {-a+, ( b) SR 3.3.6.2.3 Rad i ation -High SR 3.3.6.2.5 1 , 2,3, 2 SR 3.3.6.2.1 ,;; 16.0 mR/hr tt+, ( bl SR 3.3.6.2.3 SR 3.3.6 . 2.5 (a) ~ e~ePatieRs witA a ~e t eRtial f op SPai RiA § the Peaeter 1esse l .

Cbl During movement of RECENTLY IRRADIATED FUEL assemblies in secondary containment.

PBAPS UNIT 2 3.3-58 Amendment No. 6-9

MCREV System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Main Control Room Emergency Ventilation (MCREV) System Instrumentation LCO 3.3.7 . 1 Two channels per trip system of the Control Room Air Intake Radiation-High Function shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, DuriAg operatioAs with a poteRtia l for draiRiAg the reactor vessel ( OPDRV s) .

ACTIONS

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

Separate Cond i tion entry is allowed for each cha nn el.

CONDITION REQUIRED ACT ION COMPLETION TIME A. One or more required A.l Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from channels inoperable. MCREV subsystems discovery of inoperable. loss of MCREV System initiation capability A.2 Pl ace channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

(continued)

PBAPS UN IT 2 3.3-59 Amendment No. Ht

, RPV WATER INVENTORY CONTROL (WIC), ECCS-Operati ng

3. 5 .1 3.5 EMERGENCY CORE COOLING 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~ 150 psig and ADS valves are not required to be OPERABLE with reactor steam dome pressure ~ 100 psig.

ACTIONS

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

LCO 3.0.4.b is not applicable to HPCI.

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.

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

B. Required Action and B.l 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 not met.

(continued)

PBAPS UN IT 2 3 . 5-1 Amendment No . ...2.., 92,....._-

, RPV WATER INVENTORY CONTROL (WIC) ,

ECCS- Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS AND REACTOR CORE ISOLATION COOLING (RCICl SYSTEM EGGS Sl=lutdo1m !Deleted LCO 3.5.2 Two low pressure EGGS injection/spray subsystems sl=lall be OPERABL E.

One LPG! subsystem may be considered OPERABLE during {

alignment and operation for decay l=leat removal if capable of being manually realigned and not otherwise inoperable .

APP LI GABI LITY. MOD E 4 ,

MOD E 5 , e)(cept *,11 t h the spent fuel storage pool gates removed , water level > 458 inches above reactor pressure vessel instrument zero , and no operations with a potential for draiAiAg tl=le reactor vessel (OPDR'Js) in progress .

AGTIO~IS G9NOIHON RE91:JIREO ACTION GOMPLETIO~I TIM E

.{;..- One re~uired EGG S ~ Restore re~uired EGGS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i nj ecti on,1spra,. i njecti oA,1spFay subsystem inoperable . subsystem to OPERABLE status .

~ Re~ttired Action aF18 ~ Initiate action to Immediately associated Comp1et:ion suspeAd OPDRVs .

Th:ie of Coneition A not met .

-:- T*.~e Fe~uiree EGGS ~ Initiate action to Immedia t ely injectionilspFa:Y sttspend OPDRVs .

subsystems inoperable .

A#f}

~ Resto Fe enc EGGS 4 ROUFS injection/spray subsystem to OPERABLE status .

(contintted)

PBAPS UN IT 2 3.5 -8 Amendment No. 5-9

ECCS- Shutdown 3.5.2 ACTIONS (contiAued)

CONDITION REQUIRED ACTION COMPLETION TIME

~ Requi Fed Acti OA c. 2 Initiate action to !fflffledi a tel y and associated restore secondary Completion Time not COAtainfflent to flTe-t-;- OPERABLE status .

Initiate action to I fflm edi ate l )'

restore one standby gas treatment subsystem for Unit 2 to OPERABLE status .

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

.£R- 3. 5. 2.1 Verify , for each required low pressure In accordance coolant injection (LPG!) subsystem , the \Ii tf1 the suppression pool water level is> 11 . 0 ft . Surveillance Frequency Control Program .

(continued)

PBAPS UN IT 2 3 . 5-9 Amendment No . .;y..g

ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS ( coAti Rued)

SURVEILLANCE FREQUENCY 5-R 3. 5 . 2. 2 Verify , for each required core spray (CS) In accordance subsyste111 , the . 'n'i th tl9e Surveillance

-er.- Suppressi OA pool *. rnter 1evel is Frequency

> 11 . 0 ft ; or CoAtrol Program .

0A1y oAe required CS subsystem may tai(e credit for this optioA during OPDRVs .

Condensate storage taAk water level is

~ 17 . 3 f+:-

5-R 3. 5. 2. 3 Verify , for each required EGGS iAjcctioA/

spray subsystem , l ocatioAs susceptible to gas accumulation arc sufficiently filled IA accordance

>i*ith the SuriveillaAcc

,f with h'atcr . FrcquCAcy CoAtrol Program .

.&fl 3. 5. 2.4 Not required to be met for syste111 veRt flow paths opeAed under admiAistrative coAtrol .

Verify each required EGGS iAjectioA/spray IA accordance subsyste111 maAual , power operated , aAd ifith the automatic valve in the flow path , that is Survei 11 aAce Rot locked , scaled , or otherwise secured iA FrequeAcy positioR , is iA the correct positioA . CoAtrol Program.

(contiAued)

PBAPS UN IT 2 3 . 5-10 Amendment No. ~

ECCS- Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued )

SURVEILLANCE FREQUENCY

~ 3 . 5. 2 . 5 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 In accordance specified flow rate against a system head ~ri th the corresponding to the specified reactor Sunei 11 anee presstJre . FreQUency SYSTEM HEAD Contro l CORRESPONDHlG Program .

TO A REACTOR SYSTEM FLOlt' RATE PRESSURE OF

?'! 3 , 125 gpm ~ 105 psig Z: 8 , 600 gpFA ~ 20 psig

~ 3 . 5 . 2. 6 Vessel injection/spray may be excluded .

Verify each required ECCS in j ection/spray In accordance subsystem actuates on an actual or *,fi th the simulated automatic initiation signal . Surveillance Frequency Contro l Program .

PBAPS UN IT 2 3.5-11 Amendment No. 93-

RCIC System

, RPV WATER INVENTORY CONTROL (WIC) , 3.5.3 3.5 EMERGENCY CORE AND REACTOR CORE ISOLATION COOLING CRCIC) 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

- - - - * - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

LCO 3.0.4.b is not applicable to RCIC.

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

AN.D.

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

B. Required Action and B.l 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 UN IT 2 3.5-12 Amendment No. ~

PBAPS TSTF-542, Rev 2 New PBAPS TS Section 3.5.4 RPV Water Inventory Control 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) , RPV WATER INVENTORY CONTROL (WIC) , AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.4 Reactor Pressure Vessel (RPV) Water Inventory Control LCO 3.5.4 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be > 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

AND One low pressure ECCS injection/spray subsystem shall be OPERABLE .

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

A Low Pressure Coolant Injection ' LPCI) subsystem may be considered OPERABLE during alignment and operation for deca y heat removal if capable of being manually realigned and n n t otherwise inoperable .

APPLICABILITY : MODES 4 and 5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS A. l 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. l Initiate action to Immediately associated Completion establish a method of Time of Condition A water injection not met . capable of operating without offsite electrical power .

C. DRAIN TIME < 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. l Verify secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and > 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . containment boundary is capable of being established in less than the DRAIN TIME .

AND (continued)

PBAPS UNITS 2 & 3 3 . 5-15 Amendment No . XXX

PBAPS TSTF-542, Rev 2 RPV Water Inventory Control 3.5.4 ACTIONS (continued)

c. (continued) C. 2 Verify each secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months containment penetration flow path is capable of being isolated in less than the DRAIN TIME .

AND C. 3 Verify one standby 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months gas treatment subsystem is capable of being placed in operation in less than DRAIN TIME .

D. l -- --- -- -NOTE - -- --- -- ---

D. DRAIN TIME< 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power .

Immediately Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for

> 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

AND Immediately D. 2 Initiate action to establish secondary containment boundary .

Immediately AND D. 3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room .

AND (continued)

PBAPS UNITS 2 & 3 3 . 5-16 Amendment No . XXX

PBAPS TSTF-542, Rev 2 RPV Water Inventory Control 3.5.4 ACTIONS (continued)

D. (continued) D. 4 Initiate action to verify Immediately one Standby Gas Treatment subsystem is capable of being placed into operation .

E. Required Action and E. l Initiate action to Immediately associated Completion restore DRAIN TIME to >

Time of Condition C 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

and D not met .

OR DRAIN TIME < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify DRAIN TIME > 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . In accordance with the Surveillance Frequency Control Program .

SR 3.5.4.2 Verify , for a required low pressure coolant In accordance injection (LPCI) subsystem , the suppression with the pool water level is> 11 . 0 ft . Surveillance Frequency Control Program .

SR 3.5.4.3 Verify , for a required Core Spray (CS) In accordance subsystem , the : with the Surveillance a . Suppression pool water level is > Frequency

11. 0 ft . or Control Program .

b . Condensate storage tank water level is >

17 . 3 ft .

(continued)

PBAPS UNITS 2 & 3 3 . 5-17 Amendment No . XXX

PBAPS TSTF-542, Rev 2 RPV Water Inventory Control 3.5.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.4.4 Verify , for each required ECCS In accordance injection/spray subsystem, locations with the susceptible to gas accumulation are Surveillance sufficiently filled with water. Frequency Control Program .

SR 3.5.4.5 ----------------NOTE--------- ---- - - ---

Not required to be met for system vent flow paths open under administrative control.

Verify each required ECCS injection/spray In accordance subsystem manual, power operated, and with the automatic valve in the flow path, that is Surveillance not locked, sealed, or otherwise secured in Frequency position, is in the correct position . Control Program .

SR 3.5.4.6 Operate the required ECCS injection/spray In accordance subsystem through the recirculation line with the for> 10 minutes . Surveillance Frequency Control Program .

SR 3.5.4.7 Verify each valve credited for In accordance automatically isolating a penetration flow with the path actuates to the isolation position on Surveillance an actual or simulated isolation signal . Frequency Control Program .

SR 3.5.4.8 -------------------NOTE----------------

Vessel injection/spray may be excluded .

Verify the required ECCS injection/spray In accordance subsystem can be manually actuated . with the Surveillance Frequency Control Program .

PBAPS UNITS 2 & 3 3 . 5 - 18 Amendment No . XXX

PC I Vs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Purge/Vent flowpath E.l Isolate the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months open for an penetration.

accumulated time greater than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months QR for the calendar year while in MODE 1 or 2 E.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with Reactor Pressure greater than 100 psig.

E.2.2 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 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 in MODE 1, 2, or 3. F. 2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Required Action and B-:+ Initiate action to IFRmediately 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 11essel .

to be OPERABLE during MODE 4 or 5.

~ ru G. ~ Initiate action to Immediately restore valve(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 Verify nitrogen inventory is equivalent In accordance to~ 22 inches water column in the liquid with the nitrogen storage tank. Surveillance Frequency Control Program.

(continued)

PBAPS UNIT 2 3.6-12 Amendment No . ~

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.l Secondary Containment LCO 3.6.4.l The secondary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of RECENTLY IRRADIATED FUEL assemblies in the secondary containment, OuriAg operatioAs with a potential for drainiAg the reactor vessel (OPDRVs ) .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.l 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.l 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 not met.

C. Secondary containment C.l --------NOTE---------

inoperable during LCO 3.0.3 is not movement of RECENTLY applicable.

IRRADIATED FUEL assemblies in the secondary containment Suspend movement of Immediately or duriAg OPDRVs . RECENTLY IRRADIATED FUEL assemblies in the secondary containment.

(continued)

PBAPS UN IT 2 3.6-34 Amendment No. ~

Secondary Containment 3 . 6.4.l ACTimlS CONDITION REQUIRED ACTION COMPLETION TIME

{;--;- (CORtiRued) IRitiate actioR to Iffimediately suspeRd OPDRVs .

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment In accordance equipment hatches are closed and sealed. with the Surveillance Frequency Control Program.

SR 3.6.4.1. 2 Verify one secondary containment access In accordance t

door in each access opening is closed, with the except when the access opening is being Surveillance used for entry or exit. Frequency Control Program.

SR 3.6.4.1.3 Verify secondary containment can be drawn In accordance down to~ 0.25 inch of vacuum water gauge with the in ~ 180 seconds using one standby gas Surveillance treatment (SGT) subsystem. Frequency Control Program.

SR 3.6.4.1.4 Verify the secondary containment can be In accordance maintained~ 0.25 inch of vacuum water with the gauge for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months using one SGT subsystem Surveillance at a flow rate~ 10,500 cfm. Frequency Control Program.

PBAPS UN IT 2 3.6-35 Amendment No. -3{}3.

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

LCD 3.6.4.2 Each SC IV sh a 11 be 0 PERA BL E.

APPLICABILITY: MODES 1, 2, and 3, During movement of RECENTLY IRRADIATED FUEL assemblies in --t--

the secondary containment, Duririg operatioris \rith a potrntial for drairiirig the reactor %

vessel ( OPDRVs ) .

ACTIONS

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

1. Penetration flow paths may be uni sol ated intermittently under administrative controls.

2. Separate Condition entry is allowed f or each penetration flow path.

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

CONDITION REQ UIRED ACTION COMPLETION TIME A. One or more A.l 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.

(continued)

PBAPS UN IT 2 3.6-36 Amendment No. ~

SCI Vs 3.6.4.2 ACTIONS (continued)

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

associated Completion LCO 3.0.3 is not Time of Condition A appli cable.

or B not met during movement of RECENTLY IRRADIATED FUEL Suspend movement of Immediately assemblies in the RECENTLY IRRADIATED secondary containment FUEL assemblies in or during OPORVs . the secondary containment.

Init i ate action to Immediate l y suspend OPORVs .

PBAPS UN IT 2 3. 6-38 Amendment No. ~

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 RECENTLY IRRADIATED FUEL assemblies in ~

the secondary containment, During operations *n*ith a potential for drainiAg tl9e reactor ,f vessel COPDRVs) .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.l Restore SGT subsystem 7 days inoperab l e. to OPERABLE status.

B. Required Action and B. 1 Be i n MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met in MODE l, 2, or 3 .

C. Required Action and - - - - - - - - - - - - NOTE- - - - - - - - - - - - -

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of RECENTLY C.l Place OPERABLE SGT Immediatel y IRRADIATED FUEL subsystem in assemblies in the operation.

secondary containment or during OPDRVs .

(continued)

PBAPS UN IT 2 3.6-40 Amendment No . ~

SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACT ION COMPLETION TIME

c. (continued) c. 2. +/- Suspend movement of Immediately

~

RECENTLY IRRADIATED FUEL assemblies in secondary containment.

Afffi --+-

~ IAH:iate aetieR te 5tl5i;leREl 8PDfH£5 .

Immediately r

0. Two SGT subsystems 0.1 Be i n MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable in MOOE l, 2' or 3.

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

inoperable during LCO 3.0.3 is not movement of RECENTLY IRRADIATED FUEL assemblies in the applicable.

--- -- --- --- 1' secondary containment 9f dt!fiAg 8PDRVs .

Suspend movement of RECENTLY IRRADIATED FUEL assemblies in secondary containment.

Immediately t

Mil -+--

~ IAHi ate aetieR te 5t!Si;leREl 8PDRVs .

ImmeEliate1y r

PBAPS UN IT 2 3.6-41 Amendment No . 6-9

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

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

The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

-1 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 (OPORVs) .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREV subsystem A.l Restore MCREV 7 days inoperable for reasons subsystem to OPERABLE other than Condition status.

B.

B. One or more MCREV B.l Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.

boundary in MODE l, 2 or 3. AND B.2 Verify mitigating 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months actions ensure CRE occupant exposures to radiological/chemical hazards wi 11 not exceed limits and mitigating actions for smoke hazards are taken as required.

AND B.3 Restore CRE boundary 90 days to OPERABLE status.

PBAPS UN IT 2 3.7-7 Amendment No. ~

MCREV System 3.7.4 ACTIONS 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 of Condition A or B not met in MODE 1, 2, or 3.

D. Required Action and - - - - - - - - - - - - NOTE - - - - - - - - - - - - -

associated Completion LCD 3.0.3 is not applicable.

Time of Condition A not met during or movement of irradiated fuel assemblies in the D.l Place OPERABLE MCREV subsystem in Immediately +

secondary containment, operation.

during CORE ALTERATIONS, or duriAg OPDRVs.

D. 2 .1 Suspend movement of Immediately irrad i ated fuel assemblies in the secondary containment.

D.2.2 Suspend CORE Immediately AL TERA TI ONS.

~ IAitiate actioA to Immediately susprnd OPORVs .

E. Two MCREV subsystems E.l Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

-+

PBAPS UNIT 2 3.7-8 Amendment No. ~

MCREV System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREV subsystems - - - - - - - - - - - - NOTE - - - - - - - - - - - - -

inoperable during LCD 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, F.l Suspend movement of Immediate l y

~-;;r during CORE irradiated fuel

~* ALTERATIONS, or during assemblies in the OPDRVs. secondary containment.

OR One or more MCREV subsystems inoperable F.2 Suspend CORE Immediately due to an inoperable ALTERATIONS.

CRE Boundary during movement of irradiated A#B fuel assemblies in the secondary containment, -F-:-3 Initiate action to Imme di a tel :Y during CORE suspend OPDR Vs .

~ _'// ALTERATIONS or during

~- OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.l Operate each MCREV subsystem for In accordance

~ 15 minutes. with the Surveillance Frequency Control Program.

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 In accordance actual or simulated initiation signal. with the Surveillance Frequency Control Program.

SR 3.7.4.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitability Program.

PBAPS UNIT 2 3.7-9 Amendment No. ~

AC Sources - Shutdown 3.8.2 ACTIONS

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

LCD 3.0.3 is not applicable.

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

offsite circuits Enter applicable Condition inoperab l e. 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.l Declare affected Immediately required feature(s),

with no offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately AL TERA TI ONS.

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

~ !Aitiate actioA to Immediately suspeAd operatioAs wit~ a pote ntial for draiAiAg the reactor vessel ( QPORVs ) .

(continued)

PBAPS UN IT 2 3.8-21 Amendment No. +G

AC Sources - Shutdown 3.8.2 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.l Declare affected Immediately inoperable. required feature(s) with no DG available inoperable .

.QR B. 2. 1 Suspend CORE Immediately ALTERATIONS AND B.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

A#-9

~ IAHiat:e aet:ieA t: e Immediat:e l y suspeAd OPDRVs .

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

(continued)

PBAPS UNIT 2 3.8-22 Amendment No. ~

AC Sources- Shutdown 3.8.2 ACTIONS (continued)

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

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

Initiate action to Immediately suspend OPDRVs .

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

PBAPS UN IT 2 3.8-23 Amendment No. ---2+G

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.

~ Initiate action to lfRfftediatel y suspend operations ttith a potential for draining the reactor vessel .

A.2. 4 Initiate action to Immediately

~ restore required DC electrical power 3 subsystems to OPERABLE status.

PBAPS UN IT 2 3.8-35 Amendment No. 1-G

Di stri buti on 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- , ~

"EGGS Strntdo\m ," LCO 3.6.4.3, "Standby Gas Treatment l!J (SGT) System," LCO 3.8.2, "AC Sources-Shutdown,"

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

Inventory Control 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.l Declare associated Immediately AC or DC electrical supported required power distribution feature(s) subsystems inoperable. inoperable.

A.2.1 Suspend CORE Immediately AL TE RATIONS.

(continued)

PBAPS UN IT 2 3 . 8-44 Amendment No. '2-l-G

Di stri buti on 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.

A-:-2-:-3 Initiate action to Immediately suspend operations 1/i tl9 a potential for draining tl9e reactor vessel .

A.2. 4 Initiate actions to Immediately restore required AC and DC electrica l power distribution subsystems to OPERABLE status.

A.2. ~ Declare associated Immediately required shutdown cooling subsystem(s )

inoperable and not in operation.

PBAPS UNIT 2 3.8-45 Amendment No. ~

TABLE OF CONTENTS 1 .0 USE AND APPLICATION ........................................... 1 .1-1 1.1 Definitions ............................................... 1 .1-1 1.2 Logical Connectors ........................................ 1. 2-1 1.3 Completion Times .......................................... 1.3-1 1 .4 Frequency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 . 4-1 2.0 SAFETY LIMITS (SLs} ........................................... 2.0-1 2 .1 SLs ............................................... . ... 2.0-1 2.2 SL Violations ................................. .. .......... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR} APPLICABILITY ................... 3.0-4 3 .1 REACTIVITY CONTROL SYSTEMS ................................ 3.1-1

3. 1 . 1 SHUTDOWN MARGIN (SDM) ................................. 3.1-1 3.1 .2 Reactivity Anomalies .................................. 3. 1-5 3.1 . 3 Control Rod OPERABILITY ............................... 3.1-7 3.1 .4 Control Rod Scram Times ............................... 3.1-12 3.1 .5 Control Rod Scram Accumulators ........................ 3.1-15 3.1 .6 Rod Pattern Control ................................... 3.1-18 3.1 .7 Standby Liquid Control (SLC} System ................... 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves .... 3.1-26 3.2 POWER DISTRIBUTION LIMITS ................................. 3.2-1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR} ........................................... 3.2-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR} ................... 3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR} ................... 3.2-4 3.3 INSTRUMENTATION ................. ... .... .. ............. ... . 3. 3-1

3. 3 .1 .1 Reactor Protection System (RPS} Instrumentation ....... 3.3-1 3.3.1.2 Wide Range Neutron Monitor (WRNM} Instrumentation ..... 3.3-10 3.3. 2.1 Control Rod Block Instrumentation ..................... 3.3-16 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation .. .. ....................... .... ..... 3. 3-22 3.3.3.1 Post Accident Monitoring (PAM} Instrumentation ........ 3.3-24 3.3.3.2 Remote Shutdown System ............................ .. .. 3.3-27

3. 3 . 4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT} Instrumentation ............... 3.3-29 3.3.4.2 End of Cycle Recirculation Pump Trip (EOC-RPT} Instrumentation . . . . . 3.3-31a thru 3.3-31c 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .. 3.3-32 3.3.5.2 Reactor Core Isolation Cooling (RCIC} System Instrumentation .................................... 3.3-44 3.3.5.3 Not Used ..................... . .. . ............... . .. . . . 3.3 .47a 3.3.5.4 Reactor Pressure Vessel (RPV} Water Inventory Control Instrumentation ........... . ........................ 3 .3.47b 3 .3 .6.1 Primary Containment Isolation Instrumentation ......... 3.3-48 3.3.6.2 Secondary Containment Isolation Instrumentation ....... 3.3-55

3. 3. 7 .1 Main Control Room Emergency Ventilation (MCREV}

System Instrumentation ............................. 3.3-59

3. 3. 8.1 Loss of Power (LOP} Instrumentation ................... 3.3-61 3.3.8.2 Reactor Protection System (RPS} Electric Power Mani tori ng ............................................ 3. 3-66 (continued)

PBAPS UNIT 3 Amendment No. 229

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) .............................. 3.4-1

3. 4 .1 Recirculation Loops Operating ......................... 3.4-1 3.4.2 Jet Pumps ............................................. 3.4-6 3.4.3 Safety Relief Valves (SRVs) and Safety Valves (SVs) ... 3.4-8 3.4.4 RCS Operational LEAKAGE ............................... 3.4-10 3.4.5 RCS Leakage Detection Instrumentation ................. 3.4-12 3.4.6 RCS Specific Activity ................................. 3. 4-14 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling Sys tern- Hot Shutdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4-16 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown .............................. 3.4-19 3.4.9 RCS Pressure and Temperature (P/T) Limits ............. 3.4-21 3.4.10 Reactor Steam Dome Pressure ........................... 3.4-28 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) , RPV WATER INVENTORY CONTROL (WIC), AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 5-1

3. 5 .1 ECCS -Operating ... ... ........ . .......... . ............. 3.5-1 3.5.2 EGGS-ShutdownDel eted ................................. 3. 5-8 3.5.3 RCIC System ....... . ................................... 3. 5-12 3.5.4 RPV Water Inventory Control .. .......... . ... . ......... . 3.5-13 3.6 CONTAINMENT SYSTEMS ....................................... 3. 6-1

3. 6 .1 .1 Primary Containment .......... .. ... .. ... . ..... . ........ 3.6-1 3.6.1.2 Primary Containment Air Lock ........ . . ................ 3.6-3 3.6 . 1 .3 Primary Containment Isolation Valves (PCIVs) .......... 3.6-8 3.6.1 .4 Drywall Air Temperature .. ............................. 3 .6-17 3.6.1.5 Reactor Building-to-Suppression Chamber Vacuum Breakers . . ......................................... 3.6-18 3.6.1 .6 Suppression Chamber-to-Drywall Vacuum Breakers ........ 3.6-21 3.6.2.1 Suppression Pool Average Temperature .................. 3.6-23 3.6.2.2 Suppression Pool Water Level .......................... 3.6-26 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .................................... .. ...... 3.6-27 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .... 3.6-29 3.6.2.5 Residual Heat Removal (RHR) Drywall Spray ............. 3.6-30a 3.6.3.1 Deleted ............................................... 3.6-31 3.6.3.2 Primary Containment Oxygen Concentration ..... . ........ 3.6-33 3.6 .4.1 Secondary Containment ....... . ......................... 3.6-34 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ........ 3.6-36 3.6 . 4.3 Standby Gas Treatment (SGT) System ...... . .. .. . .. ... ... 3.6-40 3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 -1 3.7.1 High Pressure Service Water (HPSW) System ............. 3.7-1 3.7.2 Emergency Service Water (ESW) System and Normal Heat Sink ......................................... 3 . 7-3 3.7.3 Emergency Heat Sink ................................... 3. 7-5 3.7.4 Main Control Room Emergency Ventilation (MCREV)

System .......... .... .. .. .. ........ .. ..... . . ........ 3. 7 -7 3.7.5 Main Condenser Offgas ................................. 3.7-10 (continued)

PBAPS UNIT 3 ii Amendment 291

Definitions

1. 1 1.1 Definitions (continued)

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that Insert 1 RECIRCULATION PUMP TRIP time interval from initial signal generation by CEOC-RPT) SYSTEM RESPONSE the associated turbine stop valve limit switch or TIME from when the turbine control valve hydraulic oil control oi 1 pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywel 1 , such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System CRCS) component body, pipe wal 1, or vessel wal 1.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE ( LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

(continued)

PBAPS UN IT 3 1. 1-3 Amendment No. ~