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, 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 Item Page 1.0 Purpose and Summary Results 5 2.0 Methodology 6 3.0 Acceptance Criteria 6 4.0 Assumptions 7 5.0 Design Inputs 7 6.0 Design Calculations 8 7.0 Conclusions 13 8.0 Attachments 15 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 #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, 10CFR50.59 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 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 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

Engineering CALCULATION SHEET 7 , Automated Services Corp Page 11 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 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 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 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

Engineering CALCULATION SHEET Page 15 of 18 7 , Automated 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 110E018, 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

Engineering CALCULATION SHEET Page 17 of 18

< / Services Automated 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 Rev. 2 3.1-3 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 Rev. 2 Form 3.1-3 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 1B & 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 Calculation PBNP-994-21-15 Page 1 of 5 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~~ . IM ~:1C Djl6Mý SB zer Power Operated Relief Valves 520 & 618 XX 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 X IX 1(2)SI-896A & B Safet Injection Pt X X 1(2)SI-866A SIT A Cold Le 1(2)SI-866B SI Train B Redundant C 1(2)Sl-878D & B Safety Injection Loop A & B 1(2)SI-878A & C fSIHigh 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 COMMON! Spent Fuel Cooling Heat Exchanger HX-13A SW Outlet 238 X X X X 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 1I2)CC-719 ComDonent Cooling Supply to C t 140 & 137 X X XI X 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 XX[ X Calculation PBNP-994-21-15 Page 2 of 5 Rev 2

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 Calculation PBNP-994-21 -15 Page 3 of 5 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 1tBPressure 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 1A & 1B 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 Page 4 of 5 Rev 2

POINT BEACH NUCLEAR PLANT HELB RECONSITUTION PROGRAM FSAR APPENDIX A.2 REQUIRED EQUIPMENT LIST TABLE 6.0-1

• "*'(,Al * . .. ,rlENT ROOM"*"

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 Calculation PBNP-994-21-15 Page 5 of 5 Rev 2

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 I COMPONENT.DESCRiTi ON . 10-1 --T' 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 x x x x urbine Driven Au) r Pump X x7 x 301 NW & 583 SW 8' TBI\TB2 8' X x 552 X 3-2911 & DPIS Service Water Strainer North Hdr 552 X 112 & DPIS Service Water Strainer South Header 552 CWPH 8' xX x 1(2)Z-27-1. -2, -3, &-4 Traveling Water Screens 552 CWPH 8' COMMON K-2A & B Instrument Air Compressors 310 CB/AIR COMP RM 8'

-7 7- -T COMMON G-01 & G-02 Emergency Diesel Generators Train "A" 308 & 309 8' CB G01 & G02 Rm T-60A-F & T-61A-F Train A Diesel Generators Redunda 8' CB G01 & G02 Rm X x P-206A & P-207A Train A 0GG01 & G02 FL Pumpl DG BLDG 28' x 7- X 308 & 309 8' CB G01 & G02 Rm X x x X 308 & 309 xX X P-241 G01 & G02 DC Fuel Oil Pumps 308 & 309 7- X Train A DG G01 & G02 Room Exhaust Fans 308 & 309 Ovrhtd X W12A 770 & 775 DG BLDG 28' x x x-770 & 775 DG BLDG 28' x x x x 776 DG BLDG 28' x x x x 770 & 775 DG BLDG 28' x x x x W-181A1,A2,& A3 G03 Radiator HX-265A Glycol Cooling Fans 780 DG BLDG 50' x x x X W-1 81B1, B2, & B3 G04 Radiator HX-265B Glycol Cooling Fans 783 DG BLDG 50' x x x x COMMON W-183B & C G03 EDG Rm Small & Large Fans 785 DG BLDG 50' x x x x COMMON W-183C & B G04 EDG Rm Small & Large Fans 784 DG BLDG 50' x x x x W-1 3B1 &W-13B2 Control Room Recirculation Fans 337 CB/H&VROOM 6( x x x W-14A & W-14B Control Room Charcoal Filter Fans 337 CB/H&VROOM 6B HX-107A Control/Cable Spreading Room Backup IA Dryer 337 CB/H&VROOM 6i x x x

/ES 1(2)]A-3047 U1(2)C Instrument Air Inlet Header Control 140 & 137 6' PW-2/PW-3 2( x x x x 1(2)]A-3048 U1(2)C Instrument Air Inlet Header Control 140 & 137 26'PW-2/PW-3 2f x x x x 1(2)CS-218C Main Feed Pump 28A minimum recirc valve 301 NW & 583 SW 8' TBlrFB2 8' x x x 1(2)CS-2 188 Main Feed Pump 28B minimum recirc valve 301 NW & 583 SW 8' TB1ITB2 8' x x x 1(2)CS-466 Main Feedwater Reg Valve for SG 1A 301 W & 583 W 26' TB1/TB2 26' x x x 1(2)CS-476 Main Feedwater Reg Valve for SG 1B 301 W & 583 W 26' TB1ITB2 26' x x x 1(2)CS-480 MFRV Bypass Valve for SG 1A 301 W & 583 W 26' TB1iTB2 26' x x x I (2)CS-481 MFRV Bypass.Valve for SG 1B 301W& 583W 26' TB1/TB2 26' x x x I (2)MS-209C TDAFWP 1(2)P-29 Service Water Beadng 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 MDAFWP P-38A & P-38B Minumum Recirculatio, x x x x

&4019" MDAFWP P-38A & B Disch Pres Control Valves -xý x Ix x Page 1 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 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 willchange 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 1Y06-17 In Support of Other Required Equipment HX-107A 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 112IA-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 Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2

_<E T* ,OMPrQNENT BASEINE EQURED QUIMENTLIS DESCRlPTNI N UC GOTHICROOM.N fýKOMPONENT.*OCATION~ MSI FD -E&

SG 1A&2B BIc &611 CONT21'E X X X SG 1B & 2A Blowdown Containment Isolation Valves 511 &611 CONT 21' E x x SG 1A & 2A Blowdown Header Control Valve 524 & 596 -xXw SG 1B & 2B Blowdown Header Control Valve 524 & 596 x 1(2)MS-201 8 Main Steam Isolation Valve for SG A 524 & 596 & SE x x x 1(2)MS-201 7 Main Steam Isolation Valve for SG B 524 & 596 I'E Ix x xI 1(2)MS-2016 Steam Generator A Atmospheric Relief Valves 524 & 596 FACADE 88- NE & SE x x 1(2)MS-201 5 Steam Generator B Atmospheric Relief Valves 524 & 596 FACADE 88' E X-1(2)RC-430 Pressurizer Power Operated Relief Valves 520 & 618 CONT 76' in Pzr cubicle x -T -x x 1(21RC-431C Pressurizer Power Operated Relief Valves 520 &618 T 76' in Pzr cubicle X X X x I(2)RC-761A RCP P-1A CCW Thermal Barrier Return Hi-Flow Isol 511 &611 CONT 21' W x x X X

x 1(2)RC-761B RCP P-1 B CCW Thermal Barrier Return Hi Flow Isol 511 &8611 1(2)RC-371A ZVCS Letdown Line Containment Isolation Valve 511 &611 X 1(2)CV-200A, B, & C CVCSLetdown Orifice Isolation Valves 511 &611 X 1(2)CV-371 ZVCS Letdown Line Containment Isolation Valve 146 & 145 x 1SW-12A & 2SW-12D Zomponent Cooling 1HX-12A & 2HX-12D CC OutletTemp Control Valves 237 PAB 46' East x x x COMMON SW-12B & 1. Tems Control Valves 237 PAB 46' East -7 7 COMMON TV-LW-61 GBID Evap 187 PAB26' NE of Mr's -w COMMON TV-LW-62. 187 'AB 26' W of Mrs -x -T COMMON RS-SA-9 237 PAB 46' East COMMON RS-SA-10 Jnit 2 MS Supply to Radwaste Steam System 237 PAB 46' East COMMON RS-SA-1 ressure Control Valve 238 E PAB 46' East 7

C. MOTOR OPERATEI x X 1(2)SI-825A & B PAB 8' near P15's xw-T x 7 1(2)SI-896A & B 1(2)S1-866A SI Train A Cold Leg Injection (P15A via MOV 878D & B) 155 & 162 PAB 8' near P15's PWlI17'7PW4 xw-wx x 1(2)S1-866B SI Train B Redundant Cold Leg Iniection (P1 5B via Manual SI-8781 155 & 162 PW1/17'/PW4 -w -w XXx 7 x

1(2)SI-878D & B Safety Iniection Loop A & B Cold Leg Injection 511 & 611 ONT 21' SE &NE -T x -7 7 1(2)S1-878A & C SI High Pressure Core Injection 511 & 611 ONT 21' SE&NE -w 1(21MS-2020 TDAFWP 1(2)P-29 Steam Supply from SG 1A 237 146'SE &NE X X X X 1(2)MS-2019 TDAFWP 1(2)P-29 Steam Supply from SG lB 237 PAB 46' SE & NE x x x x 1(2)MS-2082 304S & 304N T -X 1(2)AF-4001 304S & 304N Xw -X 1(2)-4000 304S & 304N Xw -w x -X 1(2)AF-4006 304S & 304N x Xw COMMON AF-4009 & 4016 MDAFWP P-38A & B Suctions from Service Water respectively 304S & 304N CB/AFWPR 8' x x COMMON AF-4023 & 4022 sch to Steam Generator 1 V 304S CB/AFWPR 8' X Xw -7Xw COMMON AF-4021 & 4020 sch to Steam Generator 1 304N CB/AFWPR 8' X xXw COMMON SW-2891 & 2870 552 & 187 H 8' & PAB 26' x x COMMON SW-2890 & 2869 552 & 187 H 8'& PAB 26' x x x x COMMON SW-2816 South SW Hdr Supply to Primary Auxnlliary Building Cooling (Redundant) 187 PAB 26' SE x x x x COMMON SW-4479 Jr Susolv to Primae ntl PAB 26' SE X X

7- -T COMMON SW-2817 drSupply to Water' I/AFWPR 8' NV Xw Xw x COMMON SW-4478 /AFWPR 8' NV Xw Xw Xw x COMMON SW-2927A PAB 46' W X x Xw -x COMMON SW-2930A Spent Fuel Cooling Heat Exchanger ........... HX-13A Outlet PAB 46' W -x 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 Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 DDURATION~ 6~,ER~SuPPLY4~ REL~ATED EMERGENCF ROCEDURýEýi MOB-58/D16-MOB-59/D16-07 & MOB-335/D22-07 1(2)MS-5959 MOB-71/1Y06-3 & MOB-27112Y06-1 1 21MS-2042 4 MOB-71/1Y06-3 & MOB-271/2Y06-1 EOP 0.1, 2 112)MS-2045 D16-02/021-02 & D22-02/018-02 I (2)MS-2018 D1, 1(2)MS-2017 3 ion Only MOB-63/D16-07 & MOB-263/D22-07 ,0.2, 1,1.2.2 1(2)MS-2016 3 263/022-07 ,0.2,1,1.2,2 1(2)MS-2015 3 I-L 6-(

4 4 MOB-61/D16-07 & MOB-261/D22-07 44 1 EOP 0.1, 0.2 1(2)RC-371A MOB-: EOP 0.1, 0.2 EOP 0.1, 0.2 4 NA Direct acting thermobulb Other RequirE T Other Require

-Fail Closed on loss of air or power EOP 0 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 B32 7 B42 3 B32 & B42 ECA 0.2, 1.2 1(2)SI-878D & B 3 B32 & B42 ECA 0.2, 1.2 1(2)SI-878A & C 3 D27-15 & D13-( P 0 ATT A, 0. 1(2)MS-2020 D11-15 & D12-1 P 0 ATr A, 0. 1(2)MS-2019 3 1-18 & 013-1 Other Requirc 1(2)MS-2082 3 )11-16 & D12-16 EOP 2 1(2)AF-4001 3 127-16& O13-16 EOP2 1(2)4000 3 1B32 & 2B42 In Support of Other Required Equipment 1(2)AF-4006 4 1B32 & 2B42 In Support of Other Required Equipment COMMON AF-4009 & 4016 4 1B32 & 2B32 EOP 0.1, 2 COMMON AF-4023 & 4022 4 1B42 & 2B42 EOP 0.1, 2 COMMON AF-4021 & 4020 4 Both 1B32 In Support of Other Required Equipment COMMON SW-2891 & 2870 4 Both 2642 In Support of Other Required Equipment ,OMMON SW-2890 & 2869 4 1B32 EOP 0 ATT A COMMON SW-2816 4 16B42 EOP 0 ATT A COMMON SW-4479 4 2642 EOP 0 ATT A COMMON SW-2817 4 2632 EOP 0 ATI A COMMON SW4478 4 2B42 EOP 0 ATU A COMMON SW-2927A 4 1B32 EOP 0 ATT A COMMON SW-2930A 2B42 EOP 0 ATT A COMMON SW-2927B 1B42 EOP 0 ATT A COMMON SW-2930B 4 832 &8R42 EOP 0 ATT A 12)SW-2907 & 2908 Page 4 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 COMPONENT~-MPNEN~iCRITI i~~'~

OHCRO~iFI 14 7 COMPONENýThLOCATiONt'J LM U~

D:  :

Letdown Line In-Loop Isolation Ifrom Loop B Cold Leg) 515 & 615 CONT, IN LOOP B 43' x 1(2)CC-719 Component Cooling Supply to Containment x x x 1(21OCC754A & B Component Cooling Supply to RCP P-1A & P-1 B x x x 1(2)CC-759A & B Component Cooling Return From RCP P-1A & P-1B 1(2)CS-2190 & 2189 Feedwater Pump P-28A & P-28B Discharge Valves D. SOLENOID VALVES COMMON DA-6318A-S GO1 Diesel Generator Starting Air (from T-60A, B, & C) (DA-3057B)

COMMON DA-6318B--S G01 Diesel Generator Starting Air (from T-60D, E, & F) (DA-3057A)

COMMON DA-6319A-S G02 Diesel Generator Starting Air (from T61A, B, & C) (DA-3058B) 3092 ___

COMMON DA-6319B-S G02 Diesel Generator Starting Air (from T61 D, E, & F) (DA-3058A) 3092 COMMON DA-6360A-S G03 Diesel Generator Starting Air (from T-170A & B) IDA-6364A) 770 DG BLDG G03 Rm 28' x x x x COMMON DA-6360B-S G03 Diesel Generator Starting Air (from T-170C & D) IDA-6364B) DG BLDG G03 Rm 28' x x G04 Diesel Generator Starting Air (from T-171A & Bl (DA-6365A) DG BLDG G04 Rm 28' x G04 Diesel Generator Starting Air (from T-171C & D) (DA-6365B) DG BLDG G04 Rm 28' X Beanno Coolino CB/AFWPR 8' X E. I 1(2) N-00041 NIS Power Range 41 44' CB 1C133 & 2C130

12) N--00042 NIS Power Range 42 44'CB 1C132 &2C131 1(2) N-00043 NIS Power Range 43 326 44' CB 1C131 & 2C132 x -7 x x 1(2) N-00044 NIS Power Range 44 326 44' CB 1C130 &2C133 -T 7 X x 1121N-00035 NIS Intermediate Ran 326 44' CB 1C133 & 2C130 X x NIS Intermediate Ran 44' CB 1C132 & 2C131 -T x 1(2) N-00036 326 -7

Source Ranoe 326 44' CB 1C133 & 2C130 326 44' CB 1C132 & 2C131 -T 7 x SSource Range 32 I 304N I 8'CB AFWPR North x x x I X or(RTD's) 511 & 611 U1C/U2C 34.5' x x x x 1(2) TE-402AA&B CH-2 White T-4 511 & 611 -w A&B CH-3 Blue T-ht 511 & 611 7 -w A&BI CH-4 Yellow T-hot & T-cold Loop B Temperature Sensor 511 & 611 -T 7 -w RC Loop A T-hot & T-cold Temp Sensor IRTD's) SPARE 511 & 611 -T 7- -w RC Loop A T-hot & T-cold Temp Sensor (RTD's) SPARE 511 &611 CONT PlA CUB 34.5' 7x -T -T 1(2) TE-407A & B RC Loop B T-hot & T-cold Temp Sensor (RTD's) SPARE 511 & 611 CONT PlA CUB 34.5' B RC Loop B T-hot & T-cold Temp Sensor (RTD's) SPARE 511 & 611 CONT P1 B CUB 34.5' -T 7 -T RC Loop A Intermediate Leg Wide Range Pressure 511 & 611 CONT 21',Eof U2 keyway x 7 511 & 611 CONT 21',E of U2 ELHX x 7 Ranoe Pressure RC Loop A Hot Leg Wide Range Pressure 516 & 615 CONT 46', N of T-34B x 7 X

x x 1(2) TE-450A RC Loop A Wide Range Cold Leg Temp RTD RC Loop A Wide Range Hot Leg Temp RTD 516 & 615 516 & 615 SGA HH ele 44' SGA HH ele 44' 7 -T -w 1121 TE-450B

-T 7- x 1(2) TE-450C 1(2) TE-450D RC Loop A Wide Range Cold Leg Temp RTD RC Loop A Wide Range Hot Leg Temp RTD 516 & 615 516 & 615 SGA HH ele 44' SGA HH ele 44' x -w 1)2) TE-451A RC Loop B Wide Range Cold Leg Temp RTD 516 & 615 SGB HH ele 44' x x 1(2) TE-451B RC Loop B Wide Range Hot Leg Temp RTD 516 & 615 SGB HH ele 44' 1(2) TE-451C RC Loop B Wide Range Cold Leg Temp RTD 516 & 615 SGB HH ele 44' 1(2) TE-451D RC Loop B Wide Range Hot Leg Temp RTD 516 & 615 SGB HH ale 44' Pressurizer Level Narrow Range Transmitter 516 & 615 U1(2)C 46' T-34B E x 1(2) LT-426 x x 1(2) LT-427 Pressurizer Level Narrow Range Transmitter 516 & 615 U1(2)C 46' PRT RV Hdr x 1(2) LT-428 1 516& 615 Ul(21C 46' E STAIR IX X x x Page 5 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2

ýOPERATING DURATION.. POWMSu.-,i,,. RCATEEMRGNCY PROCEDURES. ~-. COM"PONENT-11)~

B42 & B32 1121RC-516 & 515 1(2)RC-427 3 ECA 1.2 3 1(2)CC-759A & B 10(2B41 Non-safeguards. ( I opened to cooldown SG's In ! 1I2)CS-2190 & 2189 InI A-6318A-S A .-.. ý m or 031-01 Alt In I 17-12 In!I COMMON DA-6319A-'

m or D41-01 Alt In! COMMON DA-6319B-t 34 Norm or D40 Alt in i COMMON DA-6360A-t 1 34 Norm or 040 Alt In COMMON DA-6360B-'

1 D40-01 from D14 Norm or D28 Alt In ' COMMON DA-6361A-t COMMON DA-6361 B-t COMMON AF-4007 &'

E. INSTRUMENTATIC 1(2) N-00041 1(2) N-00042 EOP 0 1(2) N-00043 EOP 0 1(2) N-00044 1 RED 1C133 & 2C130 EOP 0. 0.1, 1.2 1(2) N-00035 WHITE 1C132 & 2C131 1(2) N-00036 4 RED 1C133 & 2C130 1(2) N-00031 EOP 0.1. 1.2 1(2) N-00032 EOP 0 112) N-00040 EOP 0.1 1(2) TE-401A & B 1(2) TE-402A & B 3 BLUE 1(2) TE-403A & B 3 YELLOW 1(2) TE-404A & B NA NA (Spare Terminated in red rack) NA - Spares, Not In-Use 1(2) TE-405A & B NA NA (Spare Terminated in White rack) NA - Spares, Not In-Use 1(2) TE-406A & B NWA NA (Spare Terminated in Blue rack) NA - Spares, Not In-Use 1(2) TE-407A &B NA NA (Spare Terminated in Yellow rack) NA - Spares, Not In-Use 1(2) TE-408A & B 4 WHITE EOP 0, 0.2,1.2,1.2 FO, ECA 1.2 1(2) PT-420A 4 YELLOW EOP 0, 0.2.1.2.1.2 FO, ECA 1.2 4 RED EOP 0, 0.2,1.2,1.2 FO, ECA 1.2 4 WHITE 1C171B-F & 2C171B-F 4 YELLOW 1C1738-F & 2C173B-F YELLOW 1C173B-F & 2C173R-F 11(2) TE-450C EOP 0, 0.1 FO. 0.2, 1.2 2 FO EOP 0.1, 0.2, 1.2, 2 4 RED 1C170&2C170 EOP 0.1. 0.2. 1.2, 2 YELLOV 2C173F EOP 0.1, 0.2. 1.2. 2 I TE-451D 4ý 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 Page 6 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 T h~ CICROOM ON IMSDICISB, 1 EOMFONENTOCAT h2TCOMPONENTdD K' COMPONENT DSRPINA't 1 1(2) PT-429 P1 X IX 1(2) PT-430 Pi X X 1(2) PT-431 Pressurizer Pressure Transmitter IXVIXZEI X

1(2) TE-424 IXILX 1(21TE-4: 516 & 615 U1(2)C 74' PZR CUBICLE X X am 511 &611 x X X X team Generator 1A Level Transmitter 511 &611 X -7 team Generator 1A Level Transmitter 511 &611 X 7-1(2) LT-4 -T 1V21LT-4 team Generator 1B Level Transmitter 511 & 611 U1CtI2'U2 ELHX E x -x x 1(2) LT-472 team Generator 1B Level Transmitter 511 & 611 UlC/21'/U2 ELHXW x x x X 1(2) LT-473 team Generator 1B Level Transmitter 511 &611 U1(2)C 21' x x x x team Generator 1A Wide Range Level T X X X 1(2) LT-460A & 460 X

1(2) LT-470A & 470 3 Wide Ranoe Level T 7X-1(2) PT-468 Steam Generator 1A Pressure Transmitter 238 PAl x x X X

T X XT 1(2) PT-469 Steam Generator 1A Pressure Transmitter 238 PAl Xw X Xw 1(2) PT-482 Steam Generator 1A Pressure Transmitter 238 PAB 46'/SFPHX x Steam Generator I B Pressure Transmitter -T X X-1(2) PT-478 1(2) PT-479 atorI B Pr x X Xw X X-1(2) PT-483 ator1B Pressure Transmitter 7- X X X 1(2) FT-464 & 465 X X X XT 520 & 618 U1)2)CI66'IPZR NW X 1(21FT-474 & 475 1(2) FT-466 & 467 1A Main 360 & 224 MTN MEZZ 391 WT 26' x X

360 & 224 MTN MEZZ 391 WT 26' X 304S & 304N CB/AFWPR/8' X ter 304S & 304N CB/AFWPRJ8' X

& 1B Flow Transmitter 142 PAB 8'E' & 8' NE at P-1I X x

-T 524 NW & 596 SW Ul Facade 88' U2 Fayade -X DAM-03-09, 1Y-1 245 & 246 Ul EER 46' U2 EER X 524 E & 596 E Ut Facade 88' U2 Facade -T eam L X Xw 1Y-113, White & DAM-06-02, 2Y-113, White 245 & 246 Ul EER 46' U2 EER 1(2) FIC-609 urn Flow 142S & N PAB 8'at PW 2&3 Lwr -w X

1(2) FIC-613 actor Coolant Pump P-1 B CC Return Flow 142S & N PAB 8' at PW 253 Lwr X X X X fety Injecton P-15A/B CC Return Flow 151 West PAB 8' W of Spray pump -T 1(2) FIS-650

'CS Letdown Line Flow (Yellow) 151 West PAB 8' W of Spray pump -T X

1FT-134

'CS Letdown Line Flow (Yellow) 142 North PAB 8' near PW3 Entr. XT X

2FT-134 1(2) LT-972 fueling Water Storage Tank Level 524 NE & 596 SE Ul(2)Faade 6.5' at RWST Xw fueling Water Storage Tank Level 524 NE & 596 SE U1(2)Facade 6.5' at RWST x x x 15ASafety Injection Flow (White) 159 & 162 8' PAB Fan Rm & PW4 x Xw X 15B Safety Injection Flow (Yellow) 159 & 162 8' PAB Fan Rm & PW4 X ndensate Water Storage Tank T-24A Level 301 NE 26' TB (Sof Baft Rms) at CST Xw 7- X-301 NE 26' TB (Sof Batt Rms) at CST X 7-X Condensate Water Storage Tank T-24A Level X Condensate Water Storage Tank T-246 Level 301 NE 26' TB (S of Batt Rms) at CST r-4041 Condensate Water Storage Tank T-24B Level North & South SW Header Pressure Transmitter North & South IA Header Pressure Transmitter INCORE THERM _39 Per Unit) 1(2) TR-00001A Core EDotTIC Digital Recorder x x x X Core Eait TIC Digital Recorder X X X Computer input MUX White

'Computer input MUX Yellow Page 7 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2 S!SCO MPONE NT IO D .

~DURATION POWER SUPvY.FL PW. .

S:* IAREATEDEMERGENCY.RiOCEDURESGi h.-

RED EOP 0, 0.1, 0.2 FO, 1, 1 FOQ1.2 1(2) PT-429 3 EOP 0, 0.1, 0.2 FO, 1, 1 FO, 1.2 112 PT-430 EOP 0, 0.1, 0.2 FO, 1, 1 FO, 1.2 1(?2)PT-.43 t 3

4 EOP 0.1, 1.2 1121 TE-424 4 EOP 0.1, 1.2 1(2) TE-425 4 EOP 0, 0 ATT A, 0.0, 0.1, 0.2. 1, 1 FO, 1.2, 1.2 FO, ECA 1.2 FO 4 EOP 0, 0 ATT A, 0.0, 0.1, 0.2. 1, 1 FO, 1.2, 1.2 FO, ECA 1.2 F (1(2) LT--462 4 Y 1.2 F5 11(21LT-463 4 A1.2 FO 11(2)LT-471 4 RED 4 WHITE ED & WHITE NA - 1o to Hot Shutdown Not Required to 1(2) LT-460A & 460B 4 D & YELLOW NA - Not Required to go to Hot Shutdown 1(21LT-470A & 470B 4 RED EOP 0,0FO, 0.0, 0.1,1,1 FO, 1.2, 1.2 FO, 2, ECA 1.2 FO 1(2) PT-468 WHITE EOP 0,0 FO, 0.0, 0.1.1,1 FO 1.2,1.2 FO, 2, ECA1.2FO 1(2 PT-469 BLUE EOP 0,0FO, 0.0,0.1,1, 1FO, 1.2, 1.2 FO, 2, ECA 1.2 FO 1(2 PT-482 4 BLUE EOP 0,0FO, 0.0,0.1, 1, 1FO, 1.2,1.2 FO, 2, ECA 1.2 FO 1(2) PT-478 4 YELLOW 1.1.1 FO. 1.2. 1.2 FO. 2. ECA 1.2 FO 112)PT-479 4 RED 1, 1,1 FO. 1.2,1.2 FO, 2, ECA 1.2 FO 1(2) PT-483 RED 1(2) FT-464 & 465 BLUE 1(2) FT-474 & 475 1 RED In Support of Other Required Equipment 11(2FT-466 & 467 1 BLUE In SUDDOrt of Other Reauired Eauioment 1(2) FT-476 & 477 4 RED EOP 0, 0 FO, 0.1, 0.1 FO, 1, 1 FO, 1.2,1.2 FO, ECA 1.2 FO 1(2) FT-4002 4 BLUE EOP 0, 0 FO, 0.1, 0.1 FO, 1, 1 FO, 1.2, 1.2 FO, ECA 1.2 FO 4 ITE& YELLOW EOP 0, 0 FO, 0.1, 0.1 FO, 1, 1 FO, 1.2,1.2 FO, ECA 1.2 EO 4 1RE-231, DAM-03-09, 1Y114/Yellow & 2RE-231, DAM-I ellow EOP 0 FO, 0.0, 1, 2, ECA 1.2 FO NA NA-Place Holder In Support of 1RE-231 & 2RE-231 4 IRE-232, DAM-05-02, 1Y113/White & 2RE-232, DAM-I EOP 0 FO, 0.0, 1, 2, ECA 1.2 FO 1121RE-232 NA NA-Place Holder In Support of 1RE-232 & 2RE-232 3 1(2)C03 ANNUNCIATOR POWER EOP 0. 0.1, 0.2, 1, 1.2, ECA 1.2.

3 1(2)C03 ANNUNCIATOR POWER EOP 0. 0.1, 0.2,1,1.2, ECA 1.2.

3 MOB-124/1Y06 & MOB-179/2Y06 In Support of Other Required Equipment 1(2) FIS-650 1 YELLOW 1C125 from 1Y04 In Support of Other Required Equipment 1FT-134 YELLOW 2C125 from 2Y04 In Support of Other Required Equipment 2FT-134 WHITE 1C-171B-F/1Y103 & 2C-171B-FI EOP 0, 1 FO, 2 FO, 1.2 FO 1(2) LT-972 4 EOP 0, 1 FO, 2 PO, 1.2 FO 1(2) LT-973 3 EOP 0 ATF A, 0.0 1(2) FT-925 3 v EOP 0 AT] A, 0.0 1(2) FT-924 4 EOP 0 FO, 0.1 FO, 0.2 FO, 1 FO, 1.2 FO, 2, 2 FO, ECA 1.2 FP COMMON LT-4038 4 YELLOW 1 EOP 0 FO, 0.1 FO, 0.2 FO, 1 FO, 1.2 FO, 2,2 FO, ECA 1.2 FO COMMON LT-4040 4 EOP 0 FO, 0.1 FO, 0.2 FO, 1 PO, 1.2 FO, 2,2 FO, ECA 1.2 FO. COMMON LT-4039 4 EOP 0 FO, 0.1 FO, 0.2 FO, 1 FO, 1.2 FO, 2. 2 FO, ECA 1.2 FP COMMON LT-4041 4 In Support of Other Required Equipment COMMON PT-2844 & 2845 4 EOP 0, 0.1, 1 COMMON PT-3084 & 3083 4 3-08 & MOB-474/2Y103-08 4

Support of Other Required Equipment COMMON C-177 YELLOW 1Y104-03 & 2Y104-( upport of Other Required Equipment [COMMON C-179 Page 8 of 12

POINT BEACHNUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2

~

17~~~COMPONPNTI:D

.""JiCii, ~§",~ ~ ~~'~.O2NNOECI~O~

~ _ý ii-5-YROM' Q.H COMPONENT LOCTO( ~SP' iB 1-970 White X XX x 1-971 Yellow x7F3 I -w 44' CB, 1C20 & 2C20 X X -w

-w PPCS-009 UNIT 1 Yellow RTP Data Link Server 333 -w PPCS-004 [UNIT 2 White RTP Data Link Server -w 511& 611 -w 1(2) TE-500 RV LT Head Vent Sensing TIC 505 & 611 al -w 1TE-501 a Sensine TIC 520 x x -w 2TE-501 RV LT Thimble Sensing T/C NA /av -w 112)TE-502 RV LT Thimble Sensing T/C 505 & 608 UlC/8'/U2C -w 1TE-503 (Ul Onty, RV LT Thimble Sensing T/C 5c -T x 1(2) LT-494 & 496 RV Narrow Range Level Transmitte 505 & 608 X

-w 112)LI-494 & 496 RVLIS TRAIN "B" RV Narrow Range Level Indicators 326 7-

-w 112) TE-506 RV LT Head Vent Sensing T/C 511 &611 x

-w 1(2) TE-507 RV LT Head Vent Sensing T/C 505 & 608 7-7-

X

-w 1TE-508 RV LT Thimble Sensing T/C 520 66' Ut CONT 7- -w 2TE-508 RV LT Thimble Sensing T/C NA Minus 1' RV Key Way x

-w 1(2) TE-509 RV LT Thimble Sensing TIC NA Minus 1' RV Key Way x 1TE-510 (Ul 0nlvl a Sensino 505 8'U1 CONT .L-

"F -w x 1(2) LT-495 & 4 RV Narrow Range Level Transmitter 505 & 611 U1C NE/8'/U2C HR-53 x -w RV Narrow Range Level Indicators 326 44' CB 1C20 & 2C20 x

-w x

F. MANUALE ý, I ONS AND ELECTRICAL DISTRIBUTION SYSTEMS Manual St Actuation PB's (All 4 Train "A"+ "B") 44' CB C01 S&&N -T 1(2) Manual SI Push Buttons 326

-L -w 112)Train "A" Block Sl CS SI-A Block/Auto Unblock Control Switch 326 44' CB C01 S & N

-w "F 112)Train "B" Block SI CS SI-B Block/Auto Unblock Control Switch 326 44'CB C01 S & N x -w 1(2) Sl RESET Train A 1(2) SI RESET Train B SI-A Reset Push Buttons SI-B Reset Push Buttons 326 326 44' CB C01 Center 44' CB C01 Center

-w X X

1(2) Cl RESET Train A -I-A Reset Push Buttons 326 44' CB COt Center

-T X X 112)Cl RESET Train B c1-BReset Push Buttons 326 44' Ce C01 Center TF -w T X 1(2)86-803 NSG LORelays 303 Non-Safeguards Equipment Lockout Relays 326 44' CB Rear of C01 112)86-B04 NSG LORelays 304 Non-Safeguards Equipment Lockout Relays 326 44' CB Rear of C01 "F X -F 1(2) MS-2018-CS M1SIV 2018 Control Switch (Both Train "A"+ "B"I 326 44' CB 1C03 & 2C03 TF X 1(2) MS-2017-CS MiSIV2017 Control Switch (Both Train "A"+ "B") 326 44'CB 1C03 &2C03 "F

326 1C04/CO1 & C02/2C04 326 1C04/C01 & C02/2C04 X X

245 & 246 46' Elect Equip Rm X -T

- 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 DOURATIONL&* * $ .* o*b,4OER SUP: Y' RELATEI:EMERG ENCY RROC EDLURES COMPONENi~T- ,niO*

EOP 0, 0 FO, 0.1, 0.1 FO, 0.2,0.2 FO, 1, 1 FO, 1.2, 1.2 FO 4 WHITE I EOP 0, 0 FO. 0.1, 0.1 FO, 0.2,0.2 FO, 1, 1 FO. 1.2,1.2 FO 4 YELLOW EOP 0, 0 FO, 0.1, 0.1 FO, 0.2,0.2 FO, 1, 1 FO, 1.2, 1.2 FO 4 (1Y104-03 Norm, 2Y104-03 Alt) EOP 0, 0 FO, 0.1, 0.1FO, 0.2, 0.2 FO, 1, 1 FO, 1.2, 1.2 FO 4 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 RVLIS TRAIN "A" 4 WHIJE In Support of Other Required Equipment 4 WHITE 1C171B-R & 2C171B-R In Support of Other Required Equipment 4 WHITE 1C171B-R In Support of Other Required Equipment 4 WHITE 2C171B-R In Support of Other Required Equipment 4 WHITE 1C171B-R & 2C171B-R ouired Eouioment 4 E 1C171B-R (Unit quired Equipment 1TE-503 (Ul Only) 4 WHITE 1C171A-F 1(2) LT-494 & 496 4 TE 1C171A-F 1(2) L1-494 & 496 RVLIS TRAIN "I 4 In Sunoort of Other Reauired Eauioment 1(2) TE-506 4 In Support of Other Required Equipment 1)2) TE-507 4 YELLOW 1C173B-R In Support of Other Required Equipment 1TE-508 4 YELLOW 2C173B-R In Support of Other Required Equipment 2TE-508 4 YELLOW 1C173B-R & 2C173B-R In Support of Other Required Equipment 1(2) TE-509 4 .LOW 1C173B-R (Unit 1 only) In Support of Other Required Equipment ITE-510 (Ut Only) 4 YELLOW 1C173A-F & 2C173A-F EOP 0.2, 1.2 1(2) LT-495 & 497

4. YELLOW 1C173A-F & 2C173A-F EOP 0.2, 1.2 1(21 LI-495 & 497 0&D21-10forU1 & D22-10&D18-10forU2 EOP 0, 0.1, 0.2 FO 1J2) Manual SI Push Buttons D16-10 & D22-10 EOP 0.2 1(2) Train "A"Block SI CS 2 D21-10 & D18-10 EOP 0.2 1)2) Train "B" Block SI CS (D16-10 & D22-10) EOP 0, 1, 1.2 1)2) SI-A MANUAL RESET PE (D21-10 & D18-10) EOP 0, 1, 1.2 1)2) SI-B MANUAL RESET PE (D16-10 & D22-10) EOP 0, 1 1(2) CI RESET Train A (121-10 & D18-10) EOP 0, 1 1)2) Cl RESET Train B MOB-102/D17-03 & MOB-158/017-08 EOP 0, 1 1(2) 86-B03 NSG LO Relays MOB-152I019-03 & MOB-208/D19-08 22-10 + D21-10 for Ul & D22-10 + D18-10 for U2 22-10 + D21-10 for Ul & D22-10 + 018-10 for U2 EOP 0, 2 1(2) MS-2017-CS D16-09 & 022-09 EOPO0 Ut (2) Tmn'A" RxTrip PB's

-i D21-09 & 018-09 EOP 0 U1(2) Tm "B" Rx Trip PB's D16-05 & D22-05, also 1(2) G-06 and/orG-07 1 022-05 & D18-05, Page 10 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 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 VITALAC 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 1C04 & 2C04 X X X X 1@2T-001E Control Switch 3ench of U (2)C04 Reactor Plant Control Panel 326 44'CB 1C04 & 2C04 X X X X Page 11 of 12

POINT BEACH NUCLEAR PLANT Calculation PBNP-994-21-15 HELB RECONSITUTION PROGRAM Rev. 0 BASELINE REQUIRED EQUIPMENT LIST TABLE 6.0-2

~DIRATO; REL-ATEDEMERGENCY', ______________ IFC~JEt<<<~

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 D009in 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 1B42 (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 1AO4NORM 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 (AllAC 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 1L21T-001E 3 1B52-12B 12B52-36B) Supply Breaker 125 VDC Control Power EOP 0.1, 1.2 1/2) T-001C Control Switch 3 1B52-21B (2B52-29B) Supply Breaker 125 VDC Control Power EOP 0.1, 1.2 112) T-001D Control Switch 1 1B52-22C (2B52-30C) Supply Breaker 125 VDC Control Power EOP 0.1, 1.2 1(2) T-001E Control Switch Page 12 of 12