ML101940389

Calculation PBNP-994-21-15, Rev. 2, HELB Reconstitution Program - Task 15, Required Equipment List, Enclosure 1, Attachment 16

ML101940389
Person / Time
Site:	Point Beach
Issue date:	10/29/2009
From:	Agan C E, Ziller E Automated Engineering Services Corp
To:	Florida Power & Light Co, Office of Nuclear Reactor Regulation
References
PBNP-994-21-15, Rev. 2
Download: ML101940389 (33)

Text

ENCLOSURE I ATTACHMENT 16 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 261 EXTENDED POWER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PBNP-994-21-15, REVISION 2, HELB RECONSTITUTION PROGRAM -TASK 15, REQUIRED EQUIPMENT LIST 32 pages follow U/ Automated Engineering CALCULATION SHEET Page 4 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client:' FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE AganE Ziller Calc. Title: HLELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 TABLE OF CONTENTS 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 Item Purpose and Summary Results Methodology Acceptance Criteria Assumptions Design Inputs Design Calculations Conclusions Attachments Page 5 6 6 7 7 8 13 15 Form 3.1-3 Rev. 2 Form 3.1-3 Rev. 2 Automated Engineering CALCULATION SHEET Page 5 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared-By:

CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 1.0 Purpose and Summary Results: The December 19, 1972 AEC letter (Design Input 5.1) and its enclosure (Items 11 and 13), as clarified in January 1973, required the identification of those systems and components required to detect and mitigate HELB events and to ultimately bring the unit to cold shutdown.

Point Beach responded to the letter by submitting information in FSAR Appendix I0A. However, Appendix A.2 does not include a required equipment list.The purpose of this calculation is to document the selection of the equipment required to respond to HELB events in those systems, or portions thereof, that were identified in HELB Reconstitution Program Task 2, Calculation

1. PBNP-994-21-02, Table 6.0-1 (Design Input 5.2) as meeting the definition of high energy and provide the basis for revising FSAR Appendix A.2. The required equipment list is provided in two levels of detail -(1) at a detail level commensurate for inclusion in the FSAR and (2) additional information for each component, such as power source, duration required to operate, reason for being included, etc.. Any sub-tier component associated with a listed component (i.e. control switch, push button, etc.) that is required for proper operation of the listed component will have to be identified and its physical location determined.

The identification of these sub-tier components is not within the current scope of the HELB Reconstitution Program or this calculation.

The results of this calculation will be used as input to HELB Reconstitution Program Task 20, 1OCFR50.59 Evaluation and USAR Appendix A.2 Revision.

It will also be transmitted to the Point Beach EQ Program engineer for evaluation of potential effects on the program, but that activity is not included in the HELB Reconstitution Program.These systems, or portions thereof, meeting the definition of high energy are: Main Steam (MS) Feedwater (FW)CVCS Letdown (CV) Steam Generator Blowdown (SB)Condensate (CS) Heater Drain Tank Pump Discharge (FD)Extraction Steam (EX) Heater and Reheater Vents & Drains (FD & MSR)Section 6.0 provides a discussion for each of the systems. Tables 6.0-1 and 6.0-2 provide the required equipment list for the various HELB events.Form 3.1-3 Rev. 2 Automated Engineering CALCULATION SHEET Page 6 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R*Krukowski List Safety Related Yes X No Date: 10/29/09 2.0 Methodology:

Applicable sections of the FSAR (6, 9, 10, A.2, 14, etc.) and Emergency Operating Procedures (Design Input 5.3) were reviewed to identify the plant's response to the various postulated high energy line break accidents.

For each of the high energy line breaks, the applicable flow diagrams (Design Input 5.4) and Electrical Master Data Book (Design Input 5.5) were reviewed and flow paths selected to accomplish the actions identified below to ultimately place the plant in a cold shutdown condition.

• Reactor trip* Reactivity control* RCS pressure control* RCS inventory control* Decay heat removal* Event monitoring All components, except passive components (tanks, filters, manual valves, etc.) in the selected flow paths were identified.

The instrumentation required to detect, initiate protective action and monitor plant response to the postulated accidents was also identified.

Component numbers, locations, power supplies, etc. were obtained from the Point Beach Passport File (Design Input 5.6) and related 499B466 elementary wiring diagrams.The equipment required to respond to each of the high energy system line breaks is listed in attached Tables 6.0-1 (FSAR format) and 6.0-2 (detailed format). A discussion of the selection process for each of the HELB events is included in Section 6.0. The tables provide a matrix of all of the required equipment and the accident for which is required.3.0 Acceptance Criteria: The acceptance criteria for this calculation is compliance with the requirements of the December 19, 1972 AEC letter as clarified in January 1973, the AEC SER and FSAR Appendix A.2.The AEC documents do not identify any minimum acceptable list, only that the accident unit must be ultimately brought to cold shutdown.

They also do not identify an acceptable time period, although the December 1972 AEC letter requests that times be provided.

There is no indication that this time related information was ever submitted to the AEC.Form 3.1-3 Rev. 2 ve 7 of 18 Calc. No.: PBNP-994-21-15 Revision:

2 Client: FP&L Energy Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 4.0 Assumptions The flow diagrams and the Electrical Master Data Book properly reflect the current plant conditions.

The component numbers, locations, power supplies, etc. in the Point Beach Passport Files are correct.In numerous sections of the FSAR (i.e. 7.5.4) Point Beach is a "safe shutdown = hot shutdown" plant.This requires going to and remaining at hot shutdown automatically or manually.

There are no criteria on how long the plant can remain at hot shutdown before ultimately achieving cold shutdown.All identified required equipment is capable of being powered by the emergency diesel generators or the batteries and can be operated from the Control Room or is accessible for manual operation.

A loss of off-site power may occur concurrently with the HELB event or delayed for up to ten (10)minutes.The only HELB required components identified that are located in the Turbine Hall are associated with the feedwater flow control valves, feedwater pumps and condensate storage tank level. The feedwater components are required to terminate flow to a faulted steam generator (main steam or blowdown HELB event). The EPU Project will be adding a fast closing valve in each feedwater line in the Facade, thereby relegating the flow control valves and feedwater pumps to the status of back-up to the new valves. The condensate storage tank level was identified as a Reg Guide 1.97 component and is mentioned in numerous emergency procedures.

The auxiliary feedwater pumps are protected by safety related low suction pressure switches located in the safety related portion of the Turbine Hall and can be supplied from the safety-related service water system. However, the condensate storage tank level transmitters were retained on the FSAR Appendix A.2 required equipment list. Since the swing battery and associated components are not normally aligned systems they were removed from the required equipment list.The other identified high energy systems are located entirely within the Turbine Hall (condensate, heater drain tank pump discharge, heater drains, etc.) and do not require any of the previously mentioned components, except condensate storage tank level. As noted in Sections 6.6, 6.7, 6.8 and 6.9 the plant response to a HELB event in these systems would be the same as a feedwater system HELB event. Therefore, it was determined that their inclusion as a HELB event column was not required.Form 3.1-3 Rev. 2

'U Automated Engineering CALCULATION SHEET Page 8 'of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc.Title:

HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 5.0 Design Inputs: 5.1 AEC letter to WEP dated December 19, 1972, A Giambusso to JG Quale 5.2 AES Calculation PBNP-994-21-02, Rev. 0 5.3 Emergency Operating Procedures 1 EOP-0, Rev. 47/49, Reactor Trip or Safety Injection 2 EOP-0.1, Rev. 34/33, Reactor Trip Response 3 EOP-0.2, Rev. 26/26, Natural Circulation Cooldown 4 EOP-1, Rev. 38/37, Loss of Reactor or Secondary Coolant 5 EOP-1.2, Rev. 28/28, Small Break LOCA Cooldown and Depressurization 6 EOP-2, Rev. 20/20, Faulted Steam Generator Isolation 7 ECA-1.2, Rev. 18/18, LOCA Outside Containment

5.4 Piping

and Instrument Drawings -See Attachment 8.1 5.5 Electrical Master Data Book 5.6 PBNP Passport Files 6.0 Design Calculations:

The December 19, 1972 AEC letter (Design Input 5.1) and its enclosure, as clarified in January 1973, identify requirements such as loss of redundancy, ability to reach cold shutdown, identification of required equipment, operation of equipment from the Control Room, etc. The Point Beach Emergency Operating Procedures, including the background documents, (Design Input 5.5) and various FSAR-Sections describe the plant's response to HELB events and were used as guidance for identifying the required equipment.

Form 3.1-3 Rev. 2 Automated Engineering CALCULATION SHEET Page 9 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Caic. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 6.1 All HELB Events The following functions are applicable to all postulated HELB events: 1 The plant must be capable of meeting the single failure criteria.2. Safety injection pumps provide borated water to the core, thereby limiting any core power transient and bringing the reactor to a sub-critical condition.

3. Following a reactor trip, core decay heat removal will be required, which would be accomplished by the Auxiliary Feedwater System and steam generator power operated relief valves.4. The auxiliary feedwater system and main steam atmospheric relief valves will provide the heat removal capability for reducing the temperature of the reactor coolant system to approximately 3500 F. Normally, the residual heat removal (RHR) system would be used to cool the plant from this point until reaching a cold shutdown condition.

The use of the auxiliary feedwater system to fill and dump the steam generators will require a much longer time to reach cold shutdown than the use of the RHR System.5. Reactor Coolant System pressure will be maintained by utilizing the pressurizer heaters to maintain pressurizer saturation temperature sufficiently above the primary coolant loop temperature to ensure adequate primary system sub-cooling.

The Reactor Coolant System is protected against overpressure by safety valves and pressurizer power operated relief valves.6. Reactor Coolant System inventory control will be maintained by the Safety Injection System. For break sizes that do not reduce the reactor coolant pressure sufficiently below the safety injection pump shutoff head, the pressurizer power operated relief valves would be operated to reduce system pressure enough to permit safety injection flow.7. Reactivity control will be provided by the Safety Injection System delivery of boric acid from the refueling water storage tank to assure adequate shutdown margin.Form 3.1-3 Rev. 2 U Automated Engineering CALCULATION SHEET Page 10 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 8. Event monitoring will be provided by selected instrumentation identified in the plant's response to Regulatory Guide 1.97. Since the postulated HELB events are in the Facade, Primary Auxiliary Building and Turbine Building, no containment monitoring instrumentation (sump level, radiation, pressure, hydrogen, etc.) is included.

The HELB events assume a loss of off-site power, therefore, no Category 3 instruments are provided.10. Support system components such as service water, component cooling water, control room ventilation, etc. are also identified.

6.2 Main Steam The scope of the main steam system includes the main steam lines from the Containment penetrations to the turbine inlet nozzles and all branch lines servicing other components.

These lines include the supply to the turbine driven auxiliary feedwater pump, steam dump to atmosphere and condenser, steam supply to the moisture separator reheaters, steam to primary and secondary air ejectors, radwaste, etc.For a large break, the safeguards sequence would be actuated by low steam line pressure in the affected steam line. The actuation of the safeguards sequence would initiate safety injection, reactor trip and start various components.

Either high-high steam flow or high steam flow coincident with low Tavg will initiate automatic closure of the main steam line isolation valves.Following initiation of safety injection, the safety injection pumps will deliver boric acid from the refueling water storage tank (minimum 2,700 ppm), which will insert sufficient negative reactivity to ultimately bring the reactor to a cold shutdown condition.

For the large steam line break, the following equipment will be available to accomplish safety functions:

1. Safety injection to pump borated water into the core, thereby limiting the core power transient following the break and bringing the reactor to a subcritical condition.

2. Closure of the main steam isolation valves (MSIV) to limit reactor coolant system cooldown.

For breaks upstream of an MSIV, the closure of the non-return check valve or closure of the other MSIV will limit the mass/energy release to one steam generator.

Form 3.1-3 Rev. 2 7 , Automated Engineering CALCULATION SHEET Page 11 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 For breaks downstream of the MSIVs, it is assumed that one of the MSIVs fails to close, thereby allowing one steam generator to blow down.3. Isolation of main feedwater to the steam generators to limit the reactor coolant system cooldown.

Isolation of main feedwater is redundantly accomplished by closing the feedwater containment isolation valves and control valves, tripping the feedwater pumps and closing their discharge valves.4. Following reactor trip, feedwater will be required to dissipate core decay heat. This would be accomplished by the Auxiliary Feedwater System.After the affected steam generator has emptied or after the break has been isolated, the auxiliary feedwater system and main steam atmospheric relief valves will provide the heat removal capability for reducing the temperature of the reactor coolant system. Normally, the residual heat removal system would be used to cool the plant to the cold shutdown condition.

In accordance with Item 4 of Section 6.1, RHR is not available and auxiliary feedwater is utilized.Main steam line breaks at power that are not large enough to cause safeguards actuation will result in the continued loss of water from the secondary side of the plantand will eventually result in the emptying of the condenser hotwell. Emptying the hotwell will result in loss of feedwater and the reactor will be tripped on low-low steam generator level or low steam generator level coincident with feed flow/steam flow mismatch.

The cooldown would continue until the steam generator feeding the break empties and safety injection initiated on either low pressurizer pressure, low steam line pressure or manually.6.3 Feedwater The scope of the feedwater system is from the feedwater pump discharge nozzles to the #5 A&B feedwater heater inlet nozzles and from the #5 A&B feedwater heater outlet nozzles to the Containment penetrations, including the .regulating by-pass lines.Large breaks would result in a reactor trip due to low-low steam generator water level or low steam generator level coincident with steam flow/feed flow mismatch.

Safety injection would have to be initiated manually.

In order to bring the plant to cold shutdown boron concentration and maintain reactor coolant inventory, the safety injection pumps and pressurizer power operated relief valves would be utilized.Form 3.1-3 Rev. 2 Automated Page 12 of 18 Engineering CALCULATION SHEET Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 Breaks that are not large enough to cause a reactor trip would be detected by the operations staff, who have numerous devices (steam flow verses feedwater flow, steam generator pressure and level, etc.) to assess the event. The operation's staff would assess the plant conditions (location of break, ability to isolate, equipment available, etc.) and determine the actions to be taken. If deemed necessary by the operations staff, shutdown of the plant would be achieved by manually initiating a reactor trip or safety injection.

A small feedwater break (crack) would result in a loss of secondary side water inventory in a manner similar to a small main steam break as discussed in Section 6.2.6.4 CVCS Letdown The scope of the CVCS Letdown system is from the Containment penetration to the non-regenerative heat exchanger inlet nozzle.Large breaks would exceed the capacity of one charging pump and would result in closure of the RCS loop isolation valves on low pressurizer level. This would terminate the HELB event.This HELB event could also be terminated by manual closure of the inside containment isolation valves or RCS loop isolation valves prior to the low level trip.Breaks that are not large enough to cause closure of the RCS loop isolation valves would be detected by the operations staff, who have numerous devices (pressurizer level and pressure, increased charging flow, decreasing volume control tank level, area radiation monitors, etc.) to assess the event.Attaining cold shutdown would be accomplished by the actions described in Sections 6.1 and 6.2.6.5 Steam Generator Blowdown The scope of the steam generator blowdown system is from the Containment penetrations to the steam generator blowdown tank and heat exchanger inlet nozzles.Largebreaks in the steam generator blowdown lines would eventually lead to reactor trip on low-low steam generator level. The HELB event could be terminated by closure of the redundant containment isolation valves. However, one of the postulated break locations is located between the two valves and the plant cannot meet the single failure criteria.

Therefore, Form 3.1-3 Rev. 2 Page 13 of 18 Calc. No.: PBNP-994-21-15 Revision:

2 Client: FP&L Energy Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 feedwater addition to the faulted steam generator must be isolated and the event will continue until the faulted steam generator empties.Attaining cold shutdown would be accomplished by the actions described in Sections 6.1 and 6.2.6.6 Condensate The scope of the condensate system is from the #2 A&B feedwater heater tube side outlet nozzles to the #3 A& B feedwater heater inlet nozzles, the #3 A& B feedwater outlet nozzles to the #4 A&B feedwater inlet nozzles and the #4 A&B feedwater heater outlet nozzles to the feedwater pump suction nozzles. The condensate return line from the steam generator blowdown heat exchangers is also included.The plant response to a HELB event in the system would be the same as a feedwater system HELB event.6.7 Heater Drain Tank Pump Discharge This scope of the heater drain system is from the heater drain tank pump discharge nozzles to the connection to the common feedwater pump suction header.The plant response to a HELB event in the system would be the same as a feedwater system HELB event.6.8 Extraction Steam The scope of the extraction steam system includes the extraction lines from the high pressure turbine nozzles to the #5 A& B feedwater heater shell side inlet nozzles and the high pressure turbine exhaust nozzles to the #4 A&B feedwater heaters and the heating steam system.The plant response to a HELB event in the system would be the same as a feedwater system HELB event.Form 3.1-3 Rev. 2 re 14 of 18 Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 6.9 Heater & Reheater Vent and Drain Systems The scope these systems is from #5 A&B feedwater heater drain nozzles to the heater drain tank, heater drain tank vent to #4 A&B feedwater heaters, #2 A&B, #3 A&B, #4 A&B, #5 A&B feedwater heater vent nozzles to various locations and reheater drain tank drain nozzles to the #5 A&B feedwater heaters and condensers.

The plant response to a HELB event in the system would be the same as a feedwater system I-IELB event.6.10 Support System Flow Paths The support systems include those portions of the Service Water, Component Cooling Water, Safety Injection, Control Room Ventilation, Reactor Protection, Diesel Generator, 4160/480v Electrical, etc. systems necessary to support the identified required equipment.

7.0

Conclusions:

Table 6.0-2 identifies the required equipment for each of the identified HELB events. Table 6.0-1 presents the required equipment in a format for FSAR Appendix A.2.8.0 Attachments:

8.1 Piping

and Instrument Drawings 8.2 Electrical and Logic Drawings Form 3.1-3 Rev. 2 7 , Automated Engineering CALCULATION SHEET Page 15 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: FIELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 Attachment

8.1 Piping

and Instrument Drawing List 541F091, Sheet 1, Rev. 45, Unit 1 Reactor Coolant System 541F091, Sheet 3, Rev. 42, Unit 1 Reactor Coolant System 541F445, Sheet 1, Rev. 44, Unit 2 Reactor Coolant System 541F445, Sheet 3, Rev. 40, Unit 2 Reactor Coolant System 684J741, Sheet 2, Rev. 68, Unit I Chemical & Volume Control 684J741, Sheet 3, Rev. 15, Unit 1 Chemical & Volume Control 685J175, Sheet 2, Rev. 56, Unit 2 Chemical & Volume Control 685J175, Sheet 3, Rev. 16, Unit 2 Chemical & Volume Control 1 10E018, Sheet 2, Rev. 21, Unit 1 Auxiliary Coolant System 110E018, Sheet 3, Rev. 40, Unit 1 Auxiliary Coolant System I 10E029 Sheet 2, Rev. 17, Unit 2 Auxiliary Coolant System I 10E029, Sheet 3, Rev. 43, Unit 2 Auxiliary Coolant System 1 10E017, Sheet 1, Rev. 53, Unit 1 Safety Injection System I IOE0 17, Sheet 2, Rev. 57, Unit 1 Safety Injection System 1 10E035, Sheet 1, Rev. 48, Unit 2 Safety Injection System I 10E035, Sheet 2, Rev. 50, Unit 2 Safety Injection System PBM-227, Rev. 31, Radwaste Steam Supply Form 3.1-3 Rev. 2 Automated Engineering CALCULATION SHEET Page 16 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 Attachment 8.1 (Continued)

Piping and Instrument Drawing List M-201, Sheet 1, Rev. 52, Unit 1 Main & Reheat Steam System M-201, Sheet 3, Rev. 27, Unit 1 S. G. Blowdown System M-2201, Sheet 1, Rev. 45, Unit 2 Main & Reheat Steam System M-2201, Sheet 3, Rev. 28, Unit 2 S. G. Blowdown System M-202, Sheet 2, Rev. 43, Unit 1 Feedwater System M-2202, Sheet 2, Rev. 45, Unit 2 Feedwater System M-207, Sheet 1, Rev. 64, Unit 1 Service Water M-207, Sheet IA, Rev. 25, Unit 1 Service Water M-207, Sheet 2, Rev. 45, Unit I Service Water M-207, Sheet 3, Rev. 58, Unit 1 Service Water M-207, Sheet 4, Rev. 22, Unit I Service Water M-2207, Sheet 1, Rev. 56, Unit 2 Service Water M-2207, Sheet 2, Rev. 10, Unit 2 Service Water M-209, Sheet 12, Rev. 19, Unit 1, EM. Diesel Air Starting Sys.M-209, Sheet 14, Rev. 11, Unit 1 & 2 Starting & Service Air System Diesel Generator Building M-209, Sheet 15, Rev. 11, Unit 1 & 2 Starting Air System Diesel Generator Building, M-217, Sheet 1, Rev. 73, Unit 1 & 2, Auxiliary Feedwater System Form 3.1-3 Rev. 2

< / Automated Engineering CALCULATION SHEET Page 17 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 Attachment 8.1 (Continued)

Piping and Instrument Drawing List M-217, Sheet 2, Rev. 46, Unit I & 2 Auxiliary Feedwater System M-219, Sheet 1, Rev. 42, Unit 1 Fuel Oil System M-219, Sheet 2, Rev. 12, Unit 1 & 2 Fuel Oil System Diesel Generator Building M-219, Sheet 3, Rev. 14, Unit 1 & 2 Fuel Oil System Diesel Generator Building M-227, Sheet 1, Rev. 10, Unit I & 2 Glycol Cooling System Diesel Generator Building M-227, Sheet 2, Rev. 9, Unit 1 & 2 Glycol Cooling System Diesel Generator Building M-144, Sheet 2, Rev. 16, Unit I & 2 Heating & Ventilation Temperature Control Form 3.1-3 Rev. 2 Form 3.1-3 Rev. 2

_ Automated Engineering CALCULATION SHEET Page 18 of 18 Services Corp Calc. No.: PBNP-994-21-15 Client: FP&L Energy Revision:

2 Station: Point Beach Nuclear Plant Prepared By: CE Agan,E Ziller Calc. Title: 1HELB Reconstitution Program -Task 15, Required Equipment Reviewed By: R Krukowski List Safety Related Yes X No Date: 10/29/09 Attachment

8.2 Electrical

and Logic Drawings 883D 195, Sheet 2, Rev. 09, Units 1 & 2 Reactor Trip Signals 883D195, Sheet 7, Rev. 21, Units 1 & 2 Safeguards Actuation Signals 883D195, Sheet 13, Rev. 05, Units 1 & 2 Pressurizer Trip Signals 883D195, Sheet 14, Rev. 08, Units 1 & 2 Steam Generator Trip Signals Form 3.1-3 Rev. 2 Form 3.1-3 Rev. 2 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM FSAR APPENDIX A.2 REQUIRED EQUIPMENT LIST TABLE 6.0-1 A. MECHANICAL COMPONENTS_

1(2)P-11A

& B Component Cooling Water Pumps 142 NE X X X X 1(2)P-15A

& B Safety injection Pumps/1500 PSI 151 E X X X X COMMON P38A & B. Motor Driven Auxiliary Feedwater Pumps 304S & 304N X X X X 1(2)P-29 Turbine Driven Auxiliary Feedwater Pump 304S & 304N X X X X 1(2)P28A & B Main Feed water pumps 301 NW & 583 SW X X X COMMON P32A,B,C,D,E, & F Service Water Pumps 552 X X X X COMMON BS-2911 & DPIS Service Water Strainer North Hdr 552 X X X X COMMON BS-2912 & DPIS Service Water Strainer South Header 552 X X X X 1(2)Z-27-1, -2, -3, & -4 Traveling Water Screens 552 X X X X X X X X COMMON G-01 & G-02 Emergency Diesel Generators Train "A" 308 & 309 X X X X T-60A-F & T-61A-F Train A Diesel Generators G01 & G02 Redundant Starting Air Receivers 308 & 309 X X X X P-206A & P-207A Train A DG G01 & G02 Fuel Oil Transfer Pumps 771 X X X X G-01-P-FTC1

& FTC2 G01 Fuel Oil to Bottoms Tank Pumps 308 & 309 X X X X G-02-P-FTC1

& FTC2 G02 Fuel Oil to Bottoms Tank Pumps 308 & 309 X X X X P-241A & P-241B G01 & G02 DC Fuel Oil Pumps 308 & 309 X X X X W12A & B, W12C & D Train A DG G01 & G02 Room Exhaust Fans 308 & 309 Ovrhds X X X X COMMON G-03 & G-04 Emergency Diesel Generators Train "B" 770 & 775 X X X X T-170A -D & T-171A-D Train B Diesel Generators G03 & G04 Redundant Starting Air Receivers 770 & 775 X X X X P-206B & P-207B Train B DG G03 & G04 Fuel Oil Transfer Pumps 776 X X X X P-209A & P-209B G03 & G04 DC Fuel Oil Pumps 770 & 775 X X X X W-1 81 Al, A2, & A3 G03 Radiator HX-265A Glycol Cooling Fans 780 X X X X W-1 811B3, B2, & B3 G04 Radiator HX-265B Glycol Cooling Fans 783 X X X X COMMON W-183B & C G03 EDG Rm Small & Large Fans 785 X X X X COMMON W-183C & B G04 EDG Rm Small & Large Fans 784 X X X X W-13B1 & W 1382 Control Room Recirculation Fans 337 X X X W-14A & W-14B Control Room Charcoal Filter Fans 337 X X X B. AIR OPERATED CONTROL VALVES 1 2)CS-466 Main Feedwater Reg Valve for SG 1A 301 W & 583W X X X 1(2)CS-476 Main Feedwater Reg Valve for SG 1 B 301 W & 583 W X X X 1(2)CS-480 MFRV Bypass Valve for SG 1A 301 W&583W X X X 112)CS-481 MFRV Bypass Valve for SG lB 301 W & 583 W X X X 1 2)MS-2090 TDAFWP 1(2)P-29 Service Water Bearng Cool 304S & 304N X X X X 1 2)AF-4002 TDAFWP 1(2)P-29 Minimum Recirculation Valve 304S & 304N X X X X COMMON AF-4007 & 4014 MDAFWP P-38A & P-38B Minumum Recirculation Valves 304S & 304N X X X X COMMON AF-4012 & 4019 MDAFWP P-38A & B Disch Pres Control Valves 304S & 304N X X X X 1 2)MS-5958 SG 1A & 2B Blowdown Containment Isolation Valves 511 & 611 X X X 1(2)MS-5959 SG 1 B & 2A Blowdown Containment Isolation valves 511 & 611 X X X 1(2)MS-2018 Main Steam Isolation Valve for SG A 524 & 596 X X X X 1 2)MS-2017 Main Steam Isolation Valve for SG B 524 & 596 X X X X 1(2)MS-2016 Steam Generator A Atmospheric Relief Valves 524 & 596 X X X X 1 2)MS-2015 Steam Generator B Atmospheric Relief Valves 524 & 596 X X X X 1(2)RC-430 Pressurizer Power Operated Relief Valves 520 & 618 X X X X Page 1 of 5 Calculation PBNP-994-21-15 Rev 2 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM FSAR APPENDIX A.2 REQUIRED EQUIPMENT LIST TABLE 6.0-1;COMPUONENT ID'CiO MPOQN ENJT>;K~~ Djl6Mý .I M~:1C SB zer Power Operated Relief Valves 520 & 618 X X X X A CCW Thermal Barrier Return Hi-Flow Isol 511 & 611 X IX X IX Thermal Barrier Return Hi Flow Isol 511 & 611 X X X X ine Containment Isolation Valve 511 &611 X ation Valves 511 &611 X nment Isolation Valve 146 & 145 X 1 CC OutletTemp Control Valves 237 X IX XIX letTemp Control Valves 237 X X- Xrx COMMONR.237 X COMMON RS-,'______237 Xn COMMON RS-SA-1 238 E X i--t-t-1--

C. MOTOR OPERATED VALVES-+ -XIX 1(2)SI-825A

& B Safet Injection PL 1(2)SI-896A

& B Safet Injection Pt 1(2)SI-866A SIT A Cold Le X IX X X 1(2)SI-866B SI Train B Redundant C 1(2)Sl-878D

& B Safety Injection Loop A & B 1(2)SI-878A

& C fSI High Pressure Core Inject 1(2)MS-2020 TDAFWP 1(2)P-29 Steam Supply I 1(2)MS-2019 TDAFWP 1 2)P-29 Steam Supply fror 1 2)MS-2082 TDAFWP 1 (2)P-29 Trip and Throttle 1(2)AF-4001 TDAFWP 1(2)P-29 Discharge to SG 1A 12)AF-4000 TDAFWP 1 (2)P-29 Discharge to SG 1 B 12)AF-4006 TDAFWP 1(2)P-29 Suction from Service Wat COMMON AF-4009 & 4016 MDAFWP P-38A & B Suctions from Service 'COMMON AF-4023 & 4022 MDAFWP P-38A Disch to Steam Generator 1 COMMON AF-4021 & 4020 MDAFWP P-38B Disch to Steam Generator 1 COMMON SW-2891 & 2870 South Service Water Header Isolation valves COMMON SW-2890 & 2869 North Service Water Header Isolation valves COMMON SW-2816 South SW Hdr Supply to Primary Auxilliar Building Cooling (Redui COMMON SW-4479 South SW Hdr Supply to Primary Auxilliary Building Cooling (Redundant)

COMMON SW-2817 North SW Hdr Sup ly to Water Treatment

& Area Cooling (Redundant)

COMMON SW-4478 North SW Hdr Supply to Water Treatment

& Area Cooling (Redundant) 304N X X X X COMMON!West SW Hdr Supply to Spent Fuel Cooling, HX-13A Inlet 238_XXXX Spent Fuel Cooling Heat Exchanger HX-13A SW Outlet 238 X X X X COMMON!COMMON SW-2927B West SW Hdr Supply to Spent Fuel Cooling, HX-13B Inlet 238 X X X X COMMON SW-2930B Spent Fuel Cooling Heat Exchange HX-13B SW Outlet 238_XXXX 1(2)SW-2907

& 2908 CONT Coolers 1 (2)HX-15A-D SW Combined Return (Parallel Valves) 1_187 X X X X 1I2)RC-516

& 515 Pressurizer PORV 430 & 431 C Isolation Valves 520 & 618 X X X IX 1(2)RC-427 Letdown Line In-Loop Isolati n (B Cold Leg) 515 & 615 X t 140 & 137 X X XI X 1I2)CC-719 ComDonent Cooling Supply to C Component Cooling Supply to RCP P-1A & P-1B 140 & 137 X X X IX ComDonent Cooling Return From RCP P-1A & P-1 B 140 & 137 X X X IX Feedwater Pump P-28A & P-28B Discharge Valves 301 NW & 583 SW X X[ X Calculation PBNP-994-21-15 Rev 2 Page 2 of 5 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM FSAR APPENDIX A.2 REQUIRED EQUIPMENT LIST TABLE 6.0-1 COMPONENT1 IA.b CORNN -. CA- MS] FDIc SC COMMON DA-6318A-S G01 Diesel Generator Starting Air (from T-60A, B, & C) (+DA-3057B) 308 X X X X COMMON DA-6318B-S G01 Diesel Generator Starting Air (from T-60D, E, & F) (+DA-3057A) 308 X X X X COMMON DA-6319A-S G02 Diesel Generator Starting Air (from T61A, B, & C) (+DA-3058B) 309 X X X X COMMON DA-6319B-S G02 Diesel Generator Starting Air (from T61D, E, & F) (+DA-3058A) 309 X X X X COMMON DA-6360A-S G03 Diesel Generator Starting Air (from T-170A & B) (+DA-6364A) 770 X X X X COMMON DA-6360B-S G03 Diesel Generator Starting Air (from T-170C & D) (+DA-6364B) 770 X X X X COMMON DA-6361A-S G04 Diesel Generator Starting Air (from T-171A & B) (+DA-6365A) 775 X X X X COMMON DA-6361B-S G04 Diesel Generator Starting Air (from T-171C & D) (+DA-6365B) 775 X X X X COMMON AF-4007 & 4014 MDAFWP P-38A & B Service Water Bearing Cooling 304S & 304N X X X X E. INSTRUMENTATION 1(2) N-00041 NIS Power Range 41 326 X X X X 1(2) N-00042 NIS Power Range 42 326 X X X X 1(2) N-00043 NIS Power Range 43 326 X X X X 1(2) N-00044 NIS Power Range 44 326 X X X X 1(2) N-00035 NIS Intermediate Range 35 326 X X X X 1(2) N-00036 NIS Intermediate Range 36 326 X X X X 1(2) N-00031 NIS Source Range 31 326 X X X X 1(2) N-00032 NIS Source Range 32 326 X X X X 1(2) N-00040 Gamma-Metrics Flux Monitor -Wide Range 304N X X X X 1(2) TE-401A & B CH-1 Red T-hot & T-cold Loop A Temperature Sensor (RTD's) 511 & 611 X X X X 1(2) TE-402A & B CH-2 White T-hot & T-cold Loop A Temperature Sensor (RTD's) 511 & 611 X X X X 1(2) TE-403A & B CH-3 Blue T-hot & T-cold Loop B Temperature Sensor (RTD's) 511 & 611 X X X X 1(2) TE-404A & B CH-4 Yellow T-hot & T-cold Loop B Temperature Sensor (RTD's) 511 & 611 X X X X 1(2) TE-405A & B RC Loop A T-hot & T-cold Temp Sensor (RTD's) SPARE 511 & 611 X X X X 1(2) TE-406A & B RC Loop A T-hot & T-cold Temp Sensor (RTD's) SPARE 511 & 611 X X X X 1(2) TE-407A & B RC Loop B T-hot & T-cold Temp Sensor (RTD's) SPARE 511 & 611 X X X X 1(2) TE-408A & B RC Loop B T-hot & T-cold Temp Sensor (RTD's) SPARE 511 & 611 X X X X 1(2) PT-420A RC Loop A Intermediate Leg Wide Range Pressure 511 & 611 X X X X 1(2) PT-420B RC Loop B Intermediate Leg Wide Range Pressure 511 & 611 X X X X 1(2) PT-420C RC Loop A Hot Leg Wide Range Pressure 516 & 615 X X X X 1(2) TE-450A RC Loop A Wide Range Cold Leg Temp RTD 516 & 615 X X X X 1(2) TE-450B RC Loop A Wide Range Hot Leg Temp RTD 516 & 615 X X X X 1(2) TE-450C RC Loop A Wide Range Cold Leg Temp RTD 516 & 615 X X X X 1(2) TE-450D RC Loop A Wide Range Hot Leg Temp RTD 516 & 615 X X X X 1(2).TE-451A RC Loop B Wide Range Cold Leg Temp RTD 516 & 615 X X X X 1(2) TE-451B RC Loop B Wide Range Hot Leg Temp RTD 516 & 615 X X X X 1(2) TE-451C RC Loop B Wide Range Cold Leg Temp RTD 516 & 615 X X X X 12) TE-451D RC Loop B Wide Range Hot Leg Temp RTD 516 & 615 X X X X 1(2) LT-426 Pressurizer Level Narrow Range Transmitter 516 & 615 X X X X 1(2) LT-427 Pressurizer Level Narrow Range Transmitter 516 & 615 X X X X 1(2) LT-428 Pressurizer Level Narrow Range Transmitter 516 & 615 X X X X 1(2) PT-429 Pressurizer Pressure Transmitter 516 & 615 X X X X 1(2) PT-430 Pressurizer Pressure Transmitter 516 & 615 X X X X!2' PT-431 Pressurizer Pressure Transmitter 516 & 615 X X X X 1(2) PT-449 Pressurizer Pressure Transmitter 516 & 615 X X X X 1(2) TE-424 Pressurizer Liquid Space RTD 516 & 615 X X X X Page 3 of 5 Calculation PBNP-994-21

-15 Rev 2 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM FSAR APPENDIX A.2 REQUIRED EQUIPMENT LIST TABLE 6.0-1 1(2) TE-425 Pressurizer Vapor Space RTD 516 & 615 X X X X 1(2) LT-461 Steam Generator 1A Level Transmitter 511 & 611 X X X X 1(2) LT-462 Steam Generator 1A Level Transmitter 511 & 611 X X X X 1(2) LT-463 Steam Generator 1A Level Transmitter 511 & 611 X X X X 1(2) LT-471 Steam Generator 1B Level Transmitter 511 & 611 X X X X 1(2) LT-472 Steam Generator 1 B Level Transmitter 511 & 611 X X X X 1(2) LT-473 Steam Generator 1 B Level Transmitter 511 & 611 X X X X 1(2) LT-460A & 460B Steam Generator 1A Wide Range Level Transmitter 511 & 611 X X X X 1(2) LT-470A & 470B Steam Generator IB Wide Range Level Transmitter 511 & 611 X X X X 1(2) PT-468 Steam Generator 1A Pressure Transmitter 238 X X X X 1(2) PT-469 Steam Generator 1A Pressure Transmitter 238 X X X X 1(2) PT-482 Steam Generator 1A Pressure Transmitter 238 X X X X 1(2) PT-478 Steam Generator 1B Pressure Transmitter 272 & 273 X X X X 1(2) PT-479 Steam Generator 1tB Pressure Transmitter 272 & 273 X X X X 1(2) PT-483 Steam Generator 1iB Pressure Transmitter 272 & 273 X X X X 1(2) FT-464 & 465 1A Main Steam Line Flow Transmitter 520 & 618 X X X X 1(2) FT-474 & 475 1B Main Steam Line Flow Transmitter 520 & 618 X X X X 1(2) FT-466 & 467 1A Main Feedwater Line Flow Transmitter 360 & 224 X X X 1(2) FT-476 & 477 1B Main Feedwater Line Flow Transmitter 360 & 224 X X X 1(2) FT-4002 1 (2)P-29 Discharge Flow Transmitter 304S & 304N X X X X COMMON FT-4007 & 4014 P-38A & B Discharge Flow Transmitter 304S & 304N X X X X 1(2) FT-4036 & 4037 Auxiliary Feedwater to SG 1 A & 1 B Flow Transmitter 142 X X X X COMMON PT-4042 P-38A AFP Suction Pressure Transmitter (Includes pump trip protection) 304S X X X X COMMON PT-4043 P-38B AFP Suction Pressure Transmitter (Includes pump trip protection) 304N X X X X 1(2) PT-4044 1(2) P-29 AFP Suction Pressure Transmitters (plus pump trip protection) 304S & 304N X X X X 1(2) RE-231 1A Main Steam Line Release Radiation Monitor 524 NW & 596 SW X 1(2) RE-232 1B Main Steam Line Release Radation Monitor 524 E & 596 E X 1(2) FIC-609 Reactor Coolant Pump P-1A CC Return Flow 142 S & N X X X X 1(2) FIC-613 Reactor Coolant Pump P-1 B CC Return Flow 142 S & N X X X X 1(2) FIS-650 Safety Injecton P-1 5A/B CC Return Flow 151 West X X X X 1FT-134 CVCS Letdown Line Flow 151 West X 2FT-134 CVCS Letdown Line Flow 142 North X 1(2) LT-972 Refueling Water Storaee Tank Level 524 NE & 596 SE X X X X 1(2) LT-973 Refueling Water Storage Tank Level 524 NE & 596 SE X X X X 1(2) FT-925 P-15A Safety Inaection Flow 159 & 162 X X X X 1(2) FT-924 P-1 5B Safety Injection Flow 159 & 162 X X X X COMMON LT-4038 Condensate Water Storage Tank T-24A Level 301 NE X X X COMMON LT-4040 Condensate Water Storaee Tank T-24A Level 301 NE X X X COMMON LT-4039 Condensate Water Storage Tank T-24B Level 301 NE X X X COMMON LT-4041 Condensate Water Storage Tank T-24B Level 301 NE X X X COMMON PT-2844 & 2845 North & South SW Header Pressure Transmitter 309 & 308 X X X X INCORE THERMOCOUPLES (39 thermocouples per unit)1(2) TR-00001A Core Exit T/C Digital Recorder 326 X X X X 1(2) TR-00001 B Core Exit T/C Digital Recorder 326 X X X X Calculation PBNP-994-21-15 Rev 2 Page 4 of 5 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM FSAR APPENDIX A.2 REQUIRED EQUIPMENT LIST TABLE 6.0-1,rlENT ...SUBCOOLING (Uses 4 thermocouples/unit) 1(2) TSS-970 RTD/TC Input to 1(2) TI-970 326 X X X X 1(2) TSS-971 RTD/TC Input to 1(2) TI-971 326 X X X X 1(2) TI-970 ASIP Subcooling Digital Indicator 326 X X X X 1(2) TI-971 ASIP Subcooling Digital Indicator 326 X X X X RVLIS TRAIN "A" 1(2) TE-499 RV LT Head Vent Sensing T/C 511 & 611 X X X X 1(2) TE-500 RV LT Head Vent Sensing T/C 505 & 611 X X X X 1TE-501 RV LT Thimble Sensing T/C 520 X X X X 2TE-501 RV LT Thimble Sensing TIC NA (In RV keyway) X X X X 1(2) TE-502 RV LT Thimble Sensing T/C 505 & 608 X X X X 1TE-503 (Unit 1 Only) RV LT Thimble Sensing TIC 505 X X X X 1(2) LT-494 & 496 RV Narrow Range Level Transmitter 505 & 608 X X X X 1(2) LI-494 & 496 RV Narrow Range Level Indicators 326 X X X X RVLIS TRAIN "B" 1(2) TE-506 RV LT Head Vent Sensing T/C 511 & 611 X X X X 1(2) TE-507 RV LT Head Vent Sensing T/C 505 & 608 X X X X 1TE-508 RV LT Thimble Sensing T/C 520 X X X X 2TE-508 RV LT Thimble Sensing T/C NA (In RV keyway) X X X X 1(2) TE-509 RV LT Thimble Sensing T/C NA (In RV keyway) X X X X 1TE-510 (Unit 1 Only) RV LT Thimble Sensing T/C 505 X X X X 1(2 LT-495 & 497 RV Narrow Range Level Transmitter 505 & 611 X X X X 1(2) LI-495 & 497 RV Narrow Range Level Indicators 326 X X X X 1(2 Manual St Push Buttons Manual Sl Acturation Push Buttons (Each PB Train "A" + "B") 326 X X X X 1(2) Train "A" Block SI CS SI-A Manual Block/Auto Unblock Control Switch 326 X X X X 1(2) Train "B" Block Sl CS SI-B Manual Block/Auto Unblock Control Switch 326 X X X X 1(2) MS-2018-CS SG 1A MSIV 2018 Control Switch (Each CS Train "A":+ "B") 326 X X X X 1(2 MS-2017-CS SG 1B MSIV 2017 Control Switch (Each CS Train "A"+ "B") 326 X X X X U1(2) Train "A' Rx Trip PB's Reactor Trip Breaker Push Button for RTA & BYB 326 X X X X Ul2 Train "B" Rx Trip PB's Reactor Trip Breaker Push Button for RTB & BYA 326 X X X X 1(2) 52-RTA & BYA Reactor Trip Bkrs RTA & BYA [Both on 1 (2C-41] 245 & 246 X X X X 1(2) 52-RTB & BYB Reactor Trp Bkrs RTB & BYB [Both on 1(2)C-411 245 & 246 X X X X DC SYSTEM STATUS VOLTS & AMPS for all 5 Safety Related Batteries

+ Charger Status 326 X X X X COMMON D05 BatteryD05 -Train "A" RED 307 X X X X COMMON D06 Battery D06 -Train "B" BLUE 306 X X X X COMMON D305 Swimn Batten D305 301 NE X X X X COMMON D105 Batter D105, WHITE 228 X X X X COMMON D106 Batter D106, YELLOW 225 X X X X COMMON D109 Swing Charger D109 227 X X X X DIESEL GENERATOR STATUS G01, G02, G03, & G04 KILOWATTS

& FREQUENCY 326 X X X X 1(2) A05 4160 Volt Train A Switchgear 305 X X X X 1(2) A06 4160 Volt Train B Switchgear 773 & 777 X X X X 1(2)603 480 Volt Train A Switchgear 318 S & N X X X X 1(2) B04 480 Volt Train B Switchgear 318 S & N X X X X VITAL AC SYSTEM STATUS SAFEGUARDS VOLTS 1(2)AO5/A06

& 1(2)B03/B04

+ Bkr Status 326 X X X X 1( 2) T-001C 200 KW Pressurizer Backup Heater Group C 516 & 615 X X X X 1 (2) T-001D 200 KW Pressurizer Backup Heater Group D 516 & 61 X Page 5 of 5 Calculation PBNP-994-21-15 Rev 2 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 I COMPONENT.DESCRiTi ON .10-1 --T'Calculation PBNP-994-21-15 Rev. 0 1(21P-11A

& B r PumpS 142 NE 1(2)P-15A

& B Safety injection Pumps/1500 PSI 151 E P38A & B lotor Driven Auxili urbine Driven Au)r Pump 3-2911 & DPIS 112 & DPIS 1(2)Z-27-1.

-2, -3, & -4 COMMON K-2A & B COMMON G-01 & G-02 Service Water Strainer North Hdr Service Water Strainer South Header Traveling Water Screens Instrument Air Compressors Emergency Diesel Generators Train "A" 301 NW & 583 SW 552 552 552 552 310 308 & 309 CWPH 8'8' TBI\TB2 8'CWPH 8'T-60A-F & T-61A-F Train A Diesel Generators CB/AIR COMP RM 8'8' CB G01 & G02 Rm 8' CB G01 & G02 Rm DG BLDG 28'8' CB G01 & G02 Rm x X X X X X x x x X X X x x7 x-7 7-x 7-x x-T 7-x x x Redunda P-206A & P-207A Train A 0G G01 & G02 FL Pumpl 308 & 309 x X X X X X 308 & 309 P-241 G01 & G02 DC Fuel Oil Pumps W12A Train A DG G01 & G02 Room Exhaust Fans W-181A1,A2,&

A3 W-1 81B1, B2, & B3 COMMON W-183B & C COMMON W-183C & B W-1 3B1 &W-13B2 W-14A & W-14B HX-107A 1(2)]A-3047 1(2)]A-3048 1(2)CS-218C 1(2)CS-2 188 1(2)CS-466 1 (2)CS-476 1 (2)CS-480 I (2)CS-481 I (2)MS-209C 1 (2)AF-4002 G03 Radiator HX-265A Glycol Cooling Fans G04 Radiator HX-265B Glycol Cooling Fans G03 EDG Rm Small & Large Fans G04 EDG Rm Small & Large Fans Control Room Recirculation Fans Control Room Charcoal Filter Fans Control/Cable Spreading Room Backup IA Dryer/ES U1(2)C Instrument Air Inlet Header Control U1(2)C Instrument Air Inlet Header Control Main Feed Pump 28A minimum recirc valve Main Feed Pump 28B minimum recirc valve Main Feedwater Reg Valve for SG 1A Main Feedwater Reg Valve for SG 1 B MFRV Bypass Valve for SG 1A MFRV Bypass.Valve for SG 1B TDAFWP 1(2)P-29 Service Water Beadng Cool TDAFWP 1(2)P-29 Minimum Recirculation Valve MDAFWP P-38A & P-38B Minumum Recirculatio, MDAFWP P-38A & B Disch Pres Control Valves 308 & 309 308 & 309 Ovrhtd 770 & 775 770 & 775 776 770 & 775 780 783 785 784 337 337 337 140 & 137 140 & 137 301 NW & 583 SW 301 NW & 583 SW 301 W & 583 W 301 W & 583 W 301 W & 583 W 301W& 583W 304S & 304N 304S & 304N DG BLDG 50'DG BLDG 50'CB/H&V ROOM 6(CB/H&V ROOM 6B CB/H&V ROOM 6i 6' PW-2/PW-3 2(26' PW-2/PW-3 2f 8' TBlrFB2 8'8' TB1ITB2 8'26' TB1/TB2 26'26' TB1ITB2 26'26' TB1iTB2 26'26' TB1/TB2 26'DG BLDG 28'DG BLDG 28'DG BLDG 28'DG BLDG 28'DG BLDG 50'DG BLDG 50'x x x -x x x x x x x x x x x x x x x X x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x-xý x Ix x& 4019" Page 1 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0 DUA -.POWER'SURPLY.;.

REL i zi,,i6NyIl~iE-E,(ý.PNN, A. MECHANICAL COMPONENTS 4 B03 & B04 EOP 0 ATT A, 0.1, 0.2, 1,1.2, ECA 1.2 1(2)P-1 tA & B 3 A05 & A06 EOP 0, 0 ATT A, 0.0, 0.2, 1, 1FO, 1.2.1.2 FO, ECA 1.2 1(2)P-15A

& B 4 1B03 & 2804 (NOTE: These will change to 4.16KV under MR 04-017A & B) EOP 0, 0.1, 1, 2 COMMON P38A & B 3 Main Steam EOP 0, 0.1 1 (2P-29 1 A01 & A02 ... Non-Safeguards EOP 0, 0.1, 2 1(2)P28A & B 4 P32A-1B03, B-11B03, C-1B04, D-2B04. E-2B04. & F-2B03 EOP 0 ATT A, COMMON P32A, BC.D.E, & F 4 2843 from Norm 2B01 or Alt 2B02 & SLELP-3...

BS non safeguards, OPIS is. In Support of Other Required Equipment COMMON BS-2911 & DPIS 4 SLELP 3 Breakers 9 & 5respectivel, (1842) BothSafeluards.

In Support of Other Required Equipment COMMON BS-2912 & DPIS 4 (1 (2 B43 from Norm 1(2)B01 or Alt 1(2 802... Redundant non safeguards)

In Support of Other Required Equipment 1 (2Z-27-1, -2, -3, & -4 4 1B32 & 2B42 EOP 0, 0.1, 1 COMMON K-2A & B 3 Multiple train A supplies AC and DC. Cooled by SW System EOP 0, 1. 1.2 COMMON G-01 & G-02 1 NA In Support of Other Required Equipment T-60A-F & T-61A-F 3 1B30 & 2B30 from 1(2)B32 In Support of Other Required Equipment P-206A & P-207A 3 480 VAC from G-01 Gen, via shared breaker in C-64 In Support of Other Required Equipment G-01-P-FTCt

& FTC2 3 480 VAC from G-02 Gen, via shared breaker in C-65 In Support of Other Required Equipment G-02-P-FTCl

& FTC2 3 RED D26-07 via C78-05 & White D31-08 via C79-05 In Support of Other Required Equipment P-241A & P-241B 3 W12A-1B32.

W12B, C, Dall2B32 In Support of Other Required Equipment W/12A & B \ W12C & D 3 Multiple train B supplies.. .AC and DC. Cooled by Forced Air Glycol HEX's EOP 0, 1, 1.2 COMMON G-03 & G-04 1 NA In Support of Other Required Equipment T-170A-D & T-171A-D 3 1B40 & 2B40 from 1(2)A06 In Support of Other Required Equipment P-206B & P-207B 3 C-81 from Norm D28-01 or 09 Alt & C82 from Norm D40-01 or 09 Alt. In Support of Other Required Equipment P-209A & P-209B 3 1B40 from 1A06 In Support of Other Required Equipment W-181A1. A2, & A3 3 2140 from 2A06 In Support of Other Required Equipment W-1 8181, B2, & B3 3 BOTH IB40 from 1A06 In Support of Other Required Equipment COMMON W-183B & C 3 BOTH 2B40 from 2AO6 In Support of Other Required Equipment COMMON W-183C & B 3 2B32 & 1842 EOP 0, 0.1, 1, ECA 1.2 W-13B1 & W-13B2 3 1B32 & 2B42 EOP 0.1 W-14A & W-14B 3 1 Y06-17 In Support of Other Required Equipment HX-1 07A B. AIR OPERATED CONTROL VALVES 4 MOB-106/D17-03

& MOB161/D17-08 EOP 0, 1 1 2)IA-3047 4 MOB-110/D19-03

& MOB-165/D19-08 EOP O, 1 112 IA-3048 1 MOB-70/1YO5

& MOB-270/2Y05 (1 2)Y05 are non-safeguards)

In Support of Other Required Equipment 1t2)CS-2180 1 MOB-70/11YO5

& MOB-270/2Y05

{1(2)YO5 are non-safeguards)

In Support of Other Required Equipment 1 2)CS-2188 I MOB-84/D16-13

& MOB-254IDt8-13 EOP 0, 0.1, 2, ECA 1.2 FO 112)CS-466 1 MOB-65/016-13

& MOB-265/D18-13 EOP 0, 0.1, 2, ECA 1.2 FO 1 2)CS-476 1 MOB-89/116-13

& MOB-2590D18-13 EOP 0, 0.1, 2, ECA 1.2 FO 1 2)CS-480 1 MOB-66/D16-13

& MOB-266/D18-13 EOP 0, 0.1, 2, ECA 1.2 FO 1(2)CS-481 3 MOB-71/tY06

& MOB-271/240/2Y06 In Support of Other Required Equipment 1(2)MS-2090 3 D13-05 & D14-15 In Support of Other Reg ired Equipment 112)AF-4002 4 011-11 & D13-11 In Support of Other Required Equipment COMMON AF4007 & 4014 4 MOB-2/tY0l

& MOB-281/2Y02 EOP 0.1 COMMON AF4012 & 4019 Page 2 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0_<E T * ,OMPrQNENT DESCRlPTN I N U C GOTHICRO OM.N BASEINE EQURED QUIMENTLIS fýKOMPONENT.OCATION~

MSI FD -E&&611 CONT21'E X X X SG 1A&2B BIc 1 (2)MS-201 8 1 (2)MS-201 7 1(2)MS-2016 1 (2)MS-201 5 1 (2)RC-430 SG 1 B & 2A Blowdown Containment Isolation Valves SG 1A & 2A Blowdown Header Control Valve SG 1 B & 2B Blowdown Header Control Valve Main Steam Isolation Valve for SG A Main Steam Isolation Valve for SG B Steam Generator A Atmospheric Relief Valves Steam Generator B Atmospheric Relief Valves Pressurizer Power Operated Relief Valves Pressurizer Power Operated Relief Valves RCP P-1A CCW Thermal Barrier Return Hi-Flow Isol RCP P-1 B CCW Thermal Barrier Return Hi Flow Isol ZVCS Letdown Line Containment Isolation Valve CVCS Letdown Orifice Isolation Valves ZVCS Letdown Line Containment Isolation Valve Zomponent Cooling 1 HX-12A & 2HX-12D CC OutletTemp Control Valves 1(21RC-431C I(2)RC-761A 1(2)RC-761B 1(2)RC-371A 1 (2)CV-200A, B, & C 1(2)CV-371 1SW-12A & 2SW-12D COMMON SW-12B & 1.COMMON TV-LW-61 COMMON TV-LW-62.COMMON RS-SA-9 COMMON RS-SA-10 COMMON RS-SA-1 C. MOTOR OPERATEI 1(2)SI-825A

& B 1(2)SI-896A

& B 1(2)S1-866A 1(2)S1-866B 1(2)SI-878D

& B 1(2)S1-878A

& C 511 &611 524 & 596 524 & 596 524 & 596 524 & 596 524 & 596 524 & 596 520 & 618 520 & 618 511 &611 511 &8611 511 &611 511 &611 146 & 145 237 237 187 187 237 237 CONT 21' E& SE x x x-x x Xw I'E Ix x xI FACADE 88- NE & SE FACADE 88' E CONT 76' in Pzr cubicle x x-T X--x x x T 76' in Pzr cubicle X X X x x x CONT 21' W Tems Control Valves G BID Evap Jnit 2 MS Supply to Radwaste Steam System PAB 46' East PAB 46' East PAB 26' NE of Mr's'AB 26' W of Mrs PAB 46' East PAB 46' East PAB 46' East PAB 8' near P15's x-x x xw xw-w-T x ressure Control Valve 238 E x-7-w-T-T-w x-w x-w X X X X x x x x 7 7 7 x 7 x 7 X PAB 8' near P15's SI Train A Cold Leg Injection (P1 5A via MOV 878D & B)SI Train B Redundant Cold Leg Iniection (P1 5B via Manual SI-8781 Safety Iniection Loop A & B Cold Leg Injection SI High Pressure Core Injection TDAFWP 1(2)P-29 Steam Supply from SG 1A TDAFWP 1(2)P-29 Steam Supply from SG lB 1(21MS-2020 1 (2)MS-2019 1(2)MS-2082 1(2)AF-4001 1(2)-4000 1 (2)AF-4006 COMMON AF-4009 & 4016 COMMON AF-4023 & 4022 COMMON AF-4021 & 4020 COMMON SW-2891 & 2870 COMMON SW-2890 & 2869 COMMON SW-2816 COMMON SW-4479 COMMON SW-2817 COMMON SW-4478 COMMON SW-2927A COMMON SW-2930A 155 & 162 155 & 162 511 & 611 511 & 611 237 237 304S & 304N 304S & 304N 304S & 304N 304S & 304N 304S & 304N 304S 304N 552 & 187 552 & 187 187 146'SE & NE X X X X PWlI17'7PW4 PW1/17'/PW4 ONT 21' SE & NE ONT 21' SE&NE x x-7 X X PAB 46' SE & NE x x T Xw Xw x x x-7-w Xw Xw x-X-X-X MDAFWP P-38A & B Suctions from Service Water respectively sch to Steam Generator 1 V sch to Steam Generator 1 South SW Hdr Supply to Primary Auxnlliary Building Cooling (Redundant)

CB/AFWPR 8'CB/AFWPR 8'CB/AFWPR 8'H 8' & PAB 26'H 8'& PAB 26'PAB 26' SE PAB 26' SE I/AFWPR 8' NV/AFWPR 8' NV PAB 46' W PAB 46' W x X X x x x Xw Xw x x x x x Jr Susolv to Primae ntl dr Supply to Water'x X X X Xw Xw x 7-x Xw Xw x-T x Xw Xw x x-x-x Spent Fuel Cooling Heat Exchanger

...........

HX-13A Outlet West SW Hdr Supply to Spent Fuel Cooling, HX-13B Inlet Spent Fuel Cooling Heat Exchanger

...........

HX-13B Outlet 238W ombined Return (Parallel Valves) 187 Page 3 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0 DDURATION~

6~,ER~SuPPLY4~

REL~ATED EMERGENCF ROCEDURýEýi MOB-58/D16-MOB-59/D16-07

& MOB-335/D22-07 MOB-71/1Y06-3

& MOB-27112Y06-1 MOB-71/1Y06-3

& MOB-271/2Y06-1 D16-02/021-02

& D22-02/018-02 1(2)MS-5959 1 21MS-2042 4 EOP 0.1, 2 3 3 4 3 4 4 4 1 4 T 112)MS-2045 I (2)MS-2018 1 (2)MS-2017 1 (2)MS-2016 D1, ion Only MOB-63/D16-07

& MOB-263/D22-07

,0.2, 1,1.2.2 263/022-07

,0.2,1,1.2,2 1 (2)MS-2015 I-L 6-(MOB-61/D16-07

& MOB-261/D22-07 MOB-: EOP 0.1, 0.2 EOP 0.1, 0.2 EOP 0.1, 0.2 Other RequirE Other Require EOP 0 1 (2)RC-371A NA Direct acting thermobulb-Fail Closed on loss of air or power N-61 1 EOP 0 iI--I EOP 0 ATl A, ECA 1.2 1 120 VAC From B-46 Control 1 C. MOTOR OPERATED VALVE 3 3 3 7 3 3 B32 B42 B32 & B42 B32 & B42 D27-15 & D13-(D11-15 & D12-1 3 ECA 0.2, 1.2 ECA 0.2, 1.2 P 0 ATT A, 0.P 0 ATr A, 0.Other Requirc EOP 2 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 1-18 & 013-1)11-16 & D12-16 127-16 & O13-16 1B32 & 2B42 1B32 & 2B42 1B32 & 2B32 1B42 & 2B42 Both 1 B32 Both 2642 1 B32 16B42 2642 2632 2 B42 1 B32 2 B42 1 B42 832 & 8R42 EOP2 In Support of Other Required Equipment In Support of Other Required Equipment EOP 0.1, 2 EOP 0.1, 2 In Support of Other Required Equipment In Support of Other Required Equipment EOP 0 ATT A EOP 0 ATT A EOP 0 ATT A EOP 0 ATI A EOP 0 ATU A EOP 0 ATT A EOP 0 ATT A EOP 0 ATT A EOP 0 ATT A 1(2)SI-878D

& B 1 (2)SI-878A

& C 1(2)MS-2020 1(2)MS-2019 1(2)MS-2082 1(2)AF-4001 1(2)4000 1 (2)AF-4006 COMMON AF-4009 & 4016 COMMON AF-4023 & 4022 COMMON AF-4021 & 4020 COMMON SW-2891 & 2870 ,OMMON SW-2890 & 2869 COMMON SW-2816 COMMON SW-4479 COMMON SW-2817 COMMON SW4478 COMMON SW-2927A COMMON SW-2930A COMMON SW-2927B COMMON SW-2930B 12)SW-2907

& 2908 4 Page 4 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 COMPONENT~-MPNEN~iCRITI i~~'~ FI 14 7 OHCRO~i COMPONENýThLOCATiONt'J LM D: U~ : Calculation PBNP-994-21-15 Rev. 0 1(2)CC-719 1(21OCC754A

& B 1(2)CC-759A

& B 1(2)CS-2190

& 2189 D. SOLENOID VALVES COMMON DA-6318A-S COMMON DA-6318B--S COMMON DA-6319A-S COMMON DA-6319B-S COMMON DA-6360A-S COMMON DA-6360B-S Letdown Line In-Loop Isolation Ifrom Loop B Cold Leg)Component Cooling Supply to Containment Component Cooling Supply to RCP P-1A & P-1 B Component Cooling Return From RCP P-1A & P-1B Feedwater Pump P-28A & P-28B Discharge Valves GO1 Diesel Generator Starting Air (from T-60A, B, & C) (DA-3057B)

G01 Diesel Generator Starting Air (from T-60D, E, & F) (DA-3057A)

G02 Diesel Generator Starting Air (from T61A, B, & C) (DA-3058B)

G02 Diesel Generator Starting Air (from T61 D, E, & F) (DA-3058A)

G03 Diesel Generator Starting Air (from T-170A & B) IDA-6364A)

G03 Diesel Generator Starting Air (from T-170C & D) IDA-6364B)

G04 Diesel Generator Starting Air (from T-171A & Bl (DA-6365A)

G04 Diesel Generator Starting Air (from T-171C & D) (DA-6365B) 515 & 615 x x x x x x CONT, IN LOOP B 43'x 3092 ___3092 __770 Beanno Coolino E. I DG BLDG G03 Rm 28'DG BLDG G03 Rm 28'DG BLDG G04 Rm 28'DG BLDG G04 Rm 28'CB/AFWPR 8'44' CB 1C133 & 2C130 44'CB 1C132 & 2C131 44' CB 1C131 & 2C132 44' CB 1C130 & 2C133 44' CB 1C133 & 2C130 44' CB 1C132 & 2C131 44' CB 1C133 & 2C130 44' CB 1C132 & 2C131 x x x-T-T-T x x x X X-7 x-7 7 7 x x 1(2) N-00041 12) N--00042 1(2) N-00043 1(2) N-00044 NIS Power Range 41 NIS Power Range 42 NIS Power Range 43 NIS Power Range 44 NIS Intermediate Ran NIS Intermediate Ran 1121 N-00035 326 326 326 326 326 326 x X x X x x 1(2) N-00036; Source Ranoe S Source Range 32 x I 304N I 8'CB AFWPR North x x x I X or (RTD's)1(2) TE-402A A&B CH-2 White T-4 A&B CH-3 Blue T-ht A&BI CH-4 Yellow T-hot & T-cold Loop B Temperature Sensor RC Loop A T-hot & T-cold Temp Sensor IRTD's) SPARE RC Loop A T-hot & T-cold Temp Sensor (RTD's) SPARE RC Loop B T-hot & T-cold Temp Sensor (RTD's) SPARE RC Loop B T-hot & T-cold Temp Sensor (RTD's) SPARE RC Loop A Intermediate Leg Wide Range Pressure 1(2) TE-407A & B B Ranoe Pressure 1(2) TE-450A 1121 TE-450B 1(2) TE-450C 1(2) TE-450D 1)2) TE-451A 1(2) TE-451B 1(2) TE-451C 1(2) TE-451D 1(2) LT-426 1(2) LT-427 1(2) LT-428 RC Loop A Hot Leg Wide Range Pressure RC Loop A Wide Range Cold Leg Temp RTD RC Loop A Wide Range Hot Leg Temp RTD RC Loop A Wide Range Cold Leg Temp RTD RC Loop A Wide Range Hot Leg Temp RTD RC Loop B Wide Range Cold Leg Temp RTD RC Loop B Wide Range Hot Leg Temp RTD RC Loop B Wide Range Cold Leg Temp RTD RC Loop B Wide Range Hot Leg Temp RTD Pressurizer Level Narrow Range Transmitter Pressurizer Level Narrow Range Transmitter 511 & 611 511 & 611 511 & 611 511 & 611 511 & 611 511 &611 511 & 611 511 & 611 511 & 611 511 & 611 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 516 & 615 CONT PlA CUB 34.5'CONT PlA CUB 34.5'CONT P1 B CUB 34.5'CONT 21',Eof U2 keyway CONT 21',E of U2 ELHX CONT 46', N of T-34B SGA HH ele 44'SGA HH ele 44'SGA HH ele 44'SGA HH ele 44'SGB HH ele 44'SGB HH ele 44'SGB HH ele 44'SGB HH ale 44'U1(2)C 46' T-34B E U1(2)C 46' PRT RV Hdr U1C/U2C 34.5'x-T-T-T x x x-T x x x 7 7 7 7 7 x x 7 7 7 X x 7--T-T-T 7-x x x-w-w-w-w-T x-w x-w x x x 1 516& 615 Ul(21C 46' E STAIR IX X x x Page 5 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0ýOPERATING DURATION..

POWMSu.-,i,,.

RCATEEMRGNCY PROCEDURES.

~-. COM"PONENT-11)~

B42 & B32 1121RC-516

& 515 1(2)RC-427 3 ECA 1.2 3 10(2B41 Non-safeguards.

(I opened to cooldown SG's In !InI In I In!I In!in i In In '1(2)CC-759A

& B 1I2)CS-2190

& 2189 A-6318A-S A .-.. ým or 031-01 Alt 17-12 m or D41-01 Alt 34 Norm or D40 Alt 1 34 Norm or 040 Alt 1 D40-01 from D14 Norm or D28 Alt EOP 0 EOP 0 EOP 0. 0.1, 1.2 COMMON DA-6319A-'

COMMON DA-6319B-t COMMON DA-6360A-t COMMON DA-6360B-'

COMMON DA-6361A-t COMMON DA-6361 B-t COMMON AF-4007 &'E. INSTRUMENTATIC 1(2) N-00041 1(2) N-00042 1(2) N-00043 1(2) N-00044 1(2) N-00035 1(2) N-00036 1(2) N-00031 1(2) N-00032 112) N-00040 1(2) TE-401A & B 1(2) TE-402A & B 1(2) TE-403A & B 1(2) TE-404A & B 1(2) TE-405A & B 1(2) TE-406A & B 1(2) TE-407A & B 1(2) TE-408A & B 1(2) PT-420A 1 RED 1C133 & 2C130 WHITE 1C132 & 2C131 4 RED 1C133 & 2C130 EOP 0.1. 1.2 EOP 0 EOP 0.1 3 3 NA NA NWA NA 4 4 4 4 4 BLUE YELLOW NA (Spare Terminated in red rack)NA (Spare Terminated in White rack)NA (Spare Terminated in Blue rack)NA (Spare Terminated in Yellow rack)WHITE YELLOW RED WHITE 1C171B-F & 2C171B-F YELLOW 1C1738-F & 2C173B-F YELLOW 1C173B-F & 2C173R-F NA -Spares, Not In-Use NA -Spares, Not In-Use NA -Spares, Not In-Use NA -Spares, Not In-Use EOP 0, 0.2,1.2,1.2 FO, ECA 1.2 EOP 0, 0.2.1.2.1.2 FO, ECA 1.2 EOP 0, 0.2,1.2,1.2 FO, ECA 1.2 11 (2) TE-450C 4 RED 1C170&2C170 YELLOV 4ý2C173F EOP 0, 0.1 FO. 0.2, 1.2 2 FO EOP 0.1, 0.2, 1.2, 2 EOP 0.1. 0.2. 1.2, 2 EOP 0.1, 0.2. 1.2. 2 EOP 0, 0.1 FO, 0.2 FO, 1, 1 FO, 1.2 FO EOP 0, 0.1 FO, 0.2 FO, 1, 1 FO, 1.2 FO EOP 0, 0.1 FO, 0.2 FO. 1. 1 FO, 1.2 FO I TE-451D Page 6 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0 h2TCOMPONENTdD T h~K'COMPONENT DSRPINA't 1 CICROOM 1 EOMFONENTOCAT ON IMSDICISB, 1(2) PT-429 1(2) PT-430 1(2) PT-431 1(2) TE-424 P1 X IX Pi Pressurizer Pressure Transmitter X X I X X VIXZEI IXILX 1(21 TE-4: am 516 & 615 511 &611 511 &611 511 &611 511 & 611 U1(2)C 74' PZR CUBICLE 1(2) LT-4 1V21 LT-4 team Generator 1A Level Transmitter team Generator 1A Level Transmitter team Generator 1 B Level Transmitter team Generator 1 B Level Transmitter team Generator 1 B Level Transmitter team Generator 1A Wide Range Level T x X X x X X X-7-T 7-X-x U1CtI2'U2 ELHX E x X 1(2) LT-472 1(2) LT-473 1(2) LT-460A & 460 1(2) LT-470A & 470 1(2) PT-468 1(2) PT-469 1(2) PT-482 1(2) PT-478 1(2) PT-479 1(2) PT-483 1(2) FT-464 & 465 511 & 611 UlC/21'/U2 ELHXW x x x X 511 &611 U1(2)C 21'3 Wide Ranoe Level T Steam Generator 1A Pressure Transmitter Steam Generator 1A Pressure Transmitter Steam Generator 1A Pressure Transmitter Steam Generator I B Pressure Transmitter 238 PAl 238 PAl 238 PAB 46'/SFPHX ator I B Pr ator 1 B Pressure Transmitter 1(21 FT-474 & 475 1(2) FT-466 & 467 1A Main ter& 1 B Flow Transmitter DAM-03-09, 1Y-1 eam L 1 Y-113, White & DAM-06-02, 2Y-113, White 1(2) FIC-609 1(2) FIC-613 1(2) FIS-650 1FT-134 2FT-134 1(2) LT-972 urn Flow 520 & 618 360 & 224 360 & 224 304S & 304N 304S & 304N 142 524 NW & 596 SW 245 & 246 524 E & 596 E 245 & 246 142S & N 142S & N 151 West 151 West 142 North 524 NE & 596 SE 524 NE & 596 SE 159 & 162 159 & 162 301 NE 301 NE 301 NE U1)2)CI66'IPZR NW MTN MEZZ 391 WT 26'MTN MEZZ 391 WT 26'CB/AFWPR/8' CB/AFWPRJ8' PAB 8'E' & 8' NE at P-1I Ul Facade 88' U2 Fayade Ul EER 46' U2 EER Ut Facade 88' U2 Facade Ul EER 46' U2 EER PAB 8'at PW 2&3 Lwr PAB 8' at PW 253 Lwr PAB 8' W of Spray pump PAB 8' W of Spray pump PAB 8' near PW3 Entr.Ul(2)Faade 6.5' at RWST U1(2)Facade 6.5' at RWST 8' PAB Fan Rm & PW4 8' PAB Fan Rm & PW4 26' TB (S of Baft Rms) at CST 26' TB (S of Batt Rms) at CST 26' TB (S of Batt Rms) at CST x x x x X X X X X X X X X x X X X X X X X-T-X-T Xw-w-T-T XT Xw x Xw Xw x X x T Xw x-T Xw 7-X x X X X X X X X X X X x X X 7 X-XT Xw X-X-X XT actor Coolant Pump P-1 B CC Return Flow fety Injecton P-15A/B CC Return Flow'CS Letdown Line Flow (Yellow)'CS Letdown Line Flow (Yellow)fueling Water Storage Tank Level fueling Water Storage Tank Level 15A Safety Injection Flow (White)15B Safety Injection Flow (Yellow)ndensate Water Storage Tank T-24A Level X X X x X X X X 7-x x 7-X X-r-4041 Condensate Water Storage Tank T-24A Level Condensate Water Storage Tank T-246 Level Condensate Water Storage Tank T-24B Level North & South SW Header Pressure Transmitter North & South IA Header Pressure Transmitter

_39 Per Unit)Core EDot TIC Digital Recorder Core Eait TIC Digital Recorder Computer input MUX White'Computer input MUX Yellow INCORE THERM 1(2) TR-00001A x x x X X X X Page 7 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0~DURATION PW. POWER SUPvY.FL .RED 3 3 4 4 4 4 4 4 4 4 4 4IAREATEDEMERGENCY.RiOCEDURESGi h.-EOP 0, 0.1, 0.2 FO, 1, 1 FOQ 1.2 EOP 0, 0.1, 0.2 FO, 1, 1 FO, 1.2 EOP 0, 0.1, 0.2 FO, 1, 1 FO, 1.2 EOP 0.1, 1.2 EOP 0.1, 1.2 EOP 0, 0 ATT A, 0.0, 0.1, 0.2. 1, 1 FO, 1.2, 1.2 FO, ECA 1.2 FO EOP 0, 0 ATT A, 0.0, 0.1, 0.2. 1, 1 FO, 1.2, 1.2 FO, ECA 1.2 F S!SC O MPONE NT IO D .1(2) PT-429 112 PT-430 1(?2) PT-.43 t 1121 TE-424 1(2) TE-425 (1(2) LT--462 Y 1.2 F5 11(21 LT-463 A1.2 FO 11(2) LT-471 4 4 4 RED WHITE ED & WHITE D & YELLOW RED WHITE BLUE BLUE YELLOW RED RED BLUE RED BLUE RED BLUE ITE & YELLOW NA -Not Required to 1o to Hot Shutdown 1(2) LT-460A & 460B NA -Not Required to go to Hot Shutdown 1(21 LT-470A & 470B EOP 0,0FO, 0.0, 0.1,1,1 FO, 1.2, 1.2 FO, 2, ECA 1.2 FO 1(2) PT-468 EOP 0,0 FO, 0.0, 0.1.1,1 FO 1.2,1.2 FO, 2, ECA1.2FO 1(2 PT-469 EOP 0,0FO, 0.0,0.1,1, 1FO, 1.2, 1.2 FO, 2, ECA 1.2 FO 1(2 PT-482 EOP 0,0FO, 0.0,0.1, 1, 1FO, 1.2,1.2 FO, 2, ECA 1.2 FO 1(2) PT-478 1.1.1 FO. 1.2. 1.2 FO. 2. ECA 1.2 FO 1, 1,1 FO. 1.2,1.2 FO, 2, ECA 1.2 FO 112) PT-479 1(2) PT-483 1(2) FT-464 & 465 1(2) FT-474 & 475 11(2 FT-466 & 467 1(2) FT-476 & 477 1(2) FT-4002 1 In Support of Other Required Equipment 1 4 4 4 4 NA 4 NA 3 3 3 1 In SUDDOrt of Other Reauired Eauioment 1RE-231, DAM-03-09, 1Y114/Yellow

& 2RE-231, DAM-I NA-Place Holder IRE-232, DAM-05-02, 1Y113/White

& 2RE-232, DAM-I NA-Place Holder 1(2)C03 ANNUNCIATOR POWER 1(2)C03 ANNUNCIATOR POWER MOB-124/1Y06

& MOB-179/2Y06 YELLOW 1C125 from 1Y04 YELLOW 2C125 from 2Y04 WHITE 1C-171B-F/1Y103

& 2C-171B-FI ellow EOP 0, 0 FO, 0.1, 0.1 FO, 1, 1 FO, 1.2,1.2 FO, ECA 1.2 FO EOP 0, 0 FO, 0.1, 0.1 FO, 1, 1 FO, 1.2, 1.2 FO, ECA 1.2 FO EOP 0, 0 FO, 0.1, 0.1 FO, 1, 1 FO, 1.2,1.2 FO, ECA 1.2 EO EOP 0 FO, 0.0, 1, 2, ECA 1.2 FO In Support of 1RE-231 & 2RE-231 EOP 0 FO, 0.0, 1, 2, ECA 1.2 FO In Support of 1RE-232 & 2RE-232 EOP 0. 0.1, 0.2, 1, 1.2, ECA 1.2.EOP 0. 0.1, 0.2,1,1.2, ECA 1.2.In Support of Other Required Equipment In Support of Other Required Equipment In Support of Other Required Equipment EOP 0, 1 FO, 2 FO, 1.2 FO EOP 0, 1 FO, 2 PO, 1.2 FO EOP 0 ATF A, 0.0 EOP 0 AT] A, 0.0 EOP 0 FO, 0.1 FO, 0.2 FO, 1 FO, 1.2 FO, 2, 2 FO, ECA 1.2 FP EOP 0 FO, 0.1 FO, 0.2 FO, 1 FO, 1.2 FO, 2,2 FO, ECA 1.2 FO EOP 0 FO, 0.1 FO, 0.2 FO, 1 PO, 1.2 FO, 2,2 FO, ECA 1.2 FO.EOP 0 FO, 0.1 FO, 0.2 FO, 1 FO, 1.2 FO, 2. 2 FO, ECA 1.2 FP In Support of Other Required Equipment EOP 0, 0.1, 1 1121 RE-232 4 3 3 4 4 4 4 4 4 4 4 v 1(2) FIS-650 1 FT-134 2FT-134 1(2) LT-972 1(2) LT-973 1(2) FT-925 1(2) FT-924 COMMON LT-4038 COMMON LT-4040 COMMON LT-4039 COMMON LT-4041 COMMON PT-2844 & 2845 COMMON PT-3084 & 3083 YELLOW 1 3-08 & MOB-474/2Y103-08 Support of Other Required Equipment COMMON C-177 YELLOW 1Y104-03 & 2Y104-(upport of Other Required Equipment

[COMMON C-1 79 Page 8 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0 17~~~COMPONPNT

~ ~ ~ ~ _ý .""JiCii, §",~ ~~'~.O2NNOECI~O~

I:D Q.H ii-5-YROM' COMPONENT LOCTO( ~SP' iB 1-970 White X X X 1-971 Yellow x7F3 I 44' CB, 1C20 & 2C20 X X PPCS-009 UNIT 1 Yellow RTP Data Link Server 333 PPCS-004 [UNIT 2 White RTP Data Link Server 511& 611 1(2) TE-500 RV LT Head Vent Sensing TIC 1TE-501 a Sensine TIC 505 & 611 520 NA 505 & 608 al 2TE-501 112) TE-502 1TE-503 (Ul Onty, 1(2) LT-494 & 496 112) LI-494 & 496 RVLIS TRAIN "B" RV LT Thimble Sensing T/C RV LT Thimble Sensing T/C RV LT Thimble Sensing T/C RV Narrow Range Level Transmitte RV Narrow Range Level Indicators RV LT Head Vent Sensing T/C RV LT Head Vent Sensing T/C RV LT Thimble Sensing T/C RV LT Thimble Sensing T/C RV LT Thimble Sensing TIC/av UlC/8'/U2C 5c 112) TE-506 1(2) TE-507 1TE-508 2TE-508 1(2) TE-509 1TE-510 1(2) LT-495 & 4 (Ul 0nlvl a Sensino F. MANUALEý, I 1(2) Manual SI Push Buttons 112) Train "A" Block Sl CS 112) Train "B" Block SI CS 1(2) Sl RESET Train A 1(2) SI RESET Train B 1(2) Cl RESET Train A 112) Cl RESET Train B 1(2)86-803 NSG LO Relays 112) 86-B04 NSG LO Relays 1(2) MS-2018-CS 1(2) MS-2017-CS RV Narrow Range Level Transmitter RV Narrow Range Level Indicators ONS AND ELECTRICAL DISTRIBUTION SYSTEMS Manual St Actuation PB's (All 4 Train "A" + "B")SI-A Block/Auto Unblock Control Switch SI-B Block/Auto Unblock Control Switch SI-A Reset Push Buttons SI-B Reset Push Buttons-I-A Reset Push Buttons c1-B Reset Push Buttons 303 Non-Safeguards Equipment Lockout Relays 304 Non-Safeguards Equipment Lockout Relays M1SIV 2018 Control Switch (Both Train "A" + "B"I MiSIV 2017 Control Switch (Both Train "A" + "B")505 & 608 326 511 &611 505 & 608 520 NA NA 505 505 & 611 326 326 326 326 326 326 326 326 326 326 326 326 326 326 245 & 246 66' Ut CONT Minus 1' RV Key Way Minus 1' RV Key Way 8'U1 CONT U1C NE/8'/U2C HR-53 44' CB 1C20 & 2C20 44' CB C01 S&&N 44' CB C01 S & N x-T 7-7-7-7-x.L-"F x-T TF T"F TF"F x X x X-w x x x-L-w-w-w x 44'CB C01 S & N 44' CB C01 Center 44' CB C01 Center 44' CB COt Center 44' Ce C01 Center 44' CB Rear of C01 44' CB Rear of C01 44' CB 1C03 & 2C03 44'CB 1C03 &2C03 1 C04/CO1 & C02/2C04 1 C04/C01 & C02/2C04 46' Elect Equip Rm x-w-w-w-w-w-w-w-w-w-w x-w-w-w-w-w-w x-w-w-T-w"F X X X-w-F-T X X X X X X X-245 &246 1 46' Elect Equip 1 Page 9 of 12 POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2$ R SUP: Y' RELATEI:EMERG E NCY RROC EDLURES COMPONENi~T- 4 4 4 4 4 4 4 4 4 4 4 4 4 WHITE I YELLOW (1Y104-03 Norm, 2Y104-03 Alt)03-03 AlIt EOP 0, 0 FO, 0.1, 0.1 FO, 0.2,0.2 FO, 1, 1 FO, 1.2, 1.2 FO EOP 0, 0 FO. 0.1, 0.1 FO, 0.2,0.2 FO, 1, 1 FO. 1.2,1.2 FO EOP 0, 0 FO, 0.1, 0.1 FO, 0.2,0.2 FO, 1, 1 FO, 1.2, 1.2 FO EOP 0, 0 FO, 0.1, 0.1FO, 0.2, 0.2 FO, 1, 1 FO, 1.2, 1.2 FO EOP 0. 0 FO, 0.1, 0.1 FO, 0.2, 0.2 FO, 1, 1 FO, 1.2, 1.2 FO In Support of Other Required Equipment In Support of Other Required Equipment In Support of Other Required Equipment In Support of Other Required Equipment RVLIS TRAIN "A" WHIJE WHITE 1C171B-R & 2C171B-R WHITE 1C171B-R WHITE 2C171B-R WHITE 1C171B-R & 2C171B-R E 1C171B-R (Unit WHITE 1C171A-F ouired Eouioment quired Equipment TE 1C171A-F In Sunoort of Other Reauired Eauioment 4 4 4 4 4 4 4.2 YELLOW 1C173B-R YELLOW 2C173B-R YELLOW 1C173B-R & 2C173B-R.LOW 1C173B-R (Unit 1 only)YELLOW 1C173A-F & 2C173A-F YELLOW 1C173A-F & 2C173A-F 0&D21-10forU1

& D22-10&D18-10forU2 D16-10 & D22-10 D21-10 & D18-10 (D16-10 & D22-10)(D21-10 & D18-10)(D16-10 & D22-10)(121-10 & D18-10)MOB-102/D17-03

& MOB-158/017-08 MOB-152I019-03

& MOB-208/D19-08 In Support of Other Required Equipment In Support of Other Required Equipment In Support of Other Required Equipment In Support of Other Required Equipment In Support of Other Required Equipment EOP 0.2, 1.2 EOP 0.2, 1.2 EOP 0, 0.1, 0.2 FO EOP 0.2 EOP 0.2 EOP 0, 1, 1.2 EOP 0, 1, 1.2 EOP 0, 1 EOP 0, 1 EOP 0, 1 1TE-503 (Ul Only)1(2) LT-494 & 496 1(2) L1-494 & 496 RVLIS TRAIN "I 1(2) TE-506 1)2) TE-507 1TE-508 2TE-508 1(2) TE-509 ITE-510 (Ut Only)1(2) LT-495 & 497 1(21 LI-495 & 497-i 1J2) Manual SI Push Buttons 1(2) Train "A" Block SI CS 1)2) Train "B" Block SI CS 1)2) SI-A MANUAL RESET PE 1)2) SI-B MANUAL RESET PE 1(2) CI RESET Train A 1)2) Cl RESET Train B 1(2) 86-B03 NSG LO Relays 22-10 + D21-10 for Ul & D22-10 + D18-10 for U2 22-10 + D21-10 for Ul & D22-10 + 018-10 for U2 D16-09 & 022-09 D21-09 & 018-09 D16-05 & D22-05, also 1(2) G-06 and/orG-07 EOP 0, 2 1(2) MS-2017-CS EOPO0 Ut (2) Tmn 'A" Rx Trip PB's EOP 0 U1(2) Tm "B" Rx Trip PB's 1 022-05 & D18-05, Page 10 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 COM~tENID~

o ~MONNTDECRPTONGOTHIC RO-)f, -,MPONENT LOCATION MS FD DC SYSTEM STATUS VOLTS & AMPS for 5 Safety Related Batteries and Charger Status 326 44' CB ASIP 2C-20 x x x x COMMON D05 Batter D05 -Train "A" RED 307 CB-8', 4.16 KV Swlr Rm X X X X COMMON 006 Battery D06 -Train "B" BLUE 306 CB-8', 4.16 KV Swgr Rm X X X X COMMON D305 Swing Battery D305 301 NE 26' TB East Above CB X X X X COMMON D105 Battery D105, WHITE 228 35'PAB NE X X X X COMMON D106 Battery D106, YELLOW 225 26'PAB NE X X X X COMMON D109 Swing Charger D109 -White or Yellow. 227 26' PAB NE X X X X DIESEL GENERATOR STATUS G01, G02, G03, & G04 KILOWATTS

& FREQUENCY 326 .44' CB PANEL C02 X X X X 12) A05 4160 Volt Train A Switch ear 305 CB-8'ele 4 KV Swgr Rm X X X X 112 A06 4160 Volt Train B Swiftchear 773 & 777 DG BLDG 28' X X X X 1(2) B03 480 Volt Train A Switchgear 318 S & N CB-26'-Cable Sprd Rm X X X X 12) B04 480 Volt Train B Switchgear

.318 S & N CB-26'-Cable Sprd Rm X X X X VITAL AC SYSTEM STATUS SAFEGUARDS VOLTS 1(2 A05/A06/B031B04 and Supply Bkr. Status 326 44' CB PANEL C02 X X X X 1(2) T-001C 200 KW Pressurizer Backup Heater Group C 516 & 615 CONT @ PZR 48' X X X X 1 2 T-001D 200 KW Pressurizer Backup Heater Group D 516 & 615 CONT @ PZR 48' X X X X 1(2) T-001E 200 KW Pressurizer Proportional Heater Group E 516 & 615 CONT @ PZR 48' X X X X 1(2) T-O01C Control Switch Bench of Ul 2)C04 Reactor Plant Control Panel 326 44' CB 1C04 & 2C04 X X X X 1 (2) T-O01D Control Switch 3ench of Ul 2)C04 Reactor Plant Control Panel 326 44' CB 1 C04 & 2C04 X X X X 1@2 T-001E Control Switch 3ench of U (2)C04 Reactor Plant Control Panel 326 44'CB 1C04 & 2C04 X X X X Calculation PBNP-994-21-15 Rev. 0 Page 11 of 12 POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 Calculation PBNP-994-21-15 Rev. 0~DIRATO; REL-ATED EMERGENCY', IFC~JEt<<<~

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4 NA (All DC System Control Room Indications on ASIP 2C20) EOP 0, 0.1, 1, 1.2 DC SYSTEM STATUS 4 CHARGER D07 fed from 1B42 (D07 is in Room 3051 In Support of Other Required Equipment COMMON D05 4 CHARGER D08 fed from 2642 (D08 is in Room 3051 In Support of Other Required Equipment COMMON D06 4 Red or Blue SWING CHARGER D09 fed from 2B03 or 1B04 D009 in Rm 305) In Support of Other Required Equipment COMMON D305 4 CHARGER D107 fed from 21342 (D107 is in Room 2271 In Support of Other Required Equipment COMMON D105 4 CHARGER D108 fed from 1 B42 (D108 is in Room 2271 In Support of Other Required Equipment COMMON D106 4 White or Yellow SWING CHARGER D109 fed from 1B32 or 2B42 (D109 in Rm 227) In Support of Other Required Equipment COMMON D109 4 NA (All Diesel Generator Control Room Indications are on Shared PANEL C02) EOP 0, 0.1, 1.1.2 (All Reference AOP-22 for KW & Frequency)

DIESEL GENERATOR STATUS 4 1A03 NORM OR G-01 EMERG & 2AO3 NORM OR G-02 EMERG In Support of Other Required Equipment 1(2) A05 4 1AO4 NORM OR G-03 EMERG & 2AO4 NORM OR G-04 EMERG In Support of Other Required Equipment 1(2 A06 4 1A05 & 2A05 In Support of Other Required Equipment 1(2) B03 4 1AO6 & 2A06 In Support of Other Required Equipment 1(2) B04 4 NA (All AC System Control Room Indications on Shared Electrical Panel C02 EOP 0, 0.0, 1, 1.2 VITAL AC SYSTEM STATUS 3 1B03 via PP14 & 2B03 via PP19 EOP 0.1, 1.2 1(2) T-001 C 3 1804 via PP13 & 2804 via PP18 EOP 0.1, 1.2 1(2) T--001D 1 1B04 via PP12 & 2B04 via PP17 EOP 0.1, 1.2 1L21 T-001E 3 1B52-12B 12B52-36B)

Supply Breaker 125 VDC Control Power EOP 0.1, 1.2 1/2) T-001C Control Switch 3 1 B52-21B (2B52-29B)

Supply Breaker 125 VDC Control Power EOP 0.1, 1.2 11 2) T-001D Control Switch 1 1 B52-22C (2B52-30C)

Supply Breaker 125 VDC Control Power EOP 0.1, 1.2 1(2) T-001E Control Switch Page 12 of 12