ML20129C248

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Forwards Revised Response to Generic Ltr 81-12 Re Alternative Shutdown Capability for Computer & Control Room, Per 850506,13 & 20 Telcons & 850618 Meeting
ML20129C248
Person / Time
Site: Rancho Seco
Issue date: 07/12/1985
From: Reinaldo Rodriguez
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Thompson H
Office of Nuclear Reactor Regulation
References
GL-81-12, RJR-85-321, TAC-52291, NUDOCS 8507160085
Download: ML20129C248 (175)


Text

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$SMUD SACRAMENTO MUNICIPAL UTluTY DISTRICT O 6201 S Street, P.O. Box 15830, Sacramento. CA 95813; (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-321 July 12,1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO 1 ADDITIONAL INFORMATION ON ALTERNATIVE SHUTDOWN CAPABILITY FOR COMPUTER AND CONTROL ROOM The District submitted additional information to its response to Generic Letter 81-12 (i.e. Alternative Shutdown Capability for Computer and Control Room) on April 5, 1985. Subsequently, telephone conversations on May 6,13, and 20, 1985 and a meeting with your staff on June 18, 1985 raised various questions which the District addresses in Attachment 1.

8ecause of the various discussions referenced above and because of the completion of a number of plant modifications, the District is providing a completely revised response to Generic Letter 81-12 ( Attachment 2). The entire response is being resubmitted and supercedes the District's earlier responses. To facilitate the NRC review, all revisions to the April 5,1985 submittal have been indicated by revision bar lines.

If you have any ad itio 1 questions contact Larry Young at Rancho Seco.

4 R. J. RODRIGUEZ ASSISTANT GENERAL-ANAGER, NUCLEAR Attachments 8507160005 850712 PDR ADOCK 00000312 Cg F

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n ATTACHMENT 1 NRC QUESTIONS ON DISTRICT'S 81-12 RESPONSE OF APRIL 5,1985 1.

NRC 00ESTION What is the basis for sizing the nitrogen supply required for shutdown?

RESPONSE

7The nitrogen supply was based on the maximum air volume needed to

-operate the Atmospheric Dump Valves' (ADV) for a period of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

-(average time required for cooldown). The two valve positions and transducers required 1.6 SCFM which results in a total air volume needed for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of 9,600.SCF.

The nitrogen bottles used to supply air are in 6 packs of 255 SCF cylinders'at normal pressure of 2200 psi. This results in the need.for'42 bottles onsite1for the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> cooldown.

2.

NRC 00ESTION L.

Is there any service or instrument air piping in the Control Room or TSC that could be damaged byLa fire,in those rooms"and' affect the ability to safely shutdown? '

l

RESPONSE

1 l

Service or instrument air piping to the Control Room, TSC or other plant areas are isolated in the hot'shutdowniprocedure, so that the fire in these areas will not affect the' availability'of service air needed for shutdown.

This isolation ensures'that the part of the' service air system needed for-hot shutdown is isolated from a breached air line in any location, as well. This is accomplished by manual local isolation valves near the area of service air needs.

3.

NRC 00ESTION How long until the switchgear room needs cooling from the portable fans?

RESPONSE

Excessive room temperature occurs at 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 15 mimutes after loss of offsite power. This calculation is based on an initial room temperature of 800F, on outside temperature of 1150F, and a heat load assuming all equipment normally operating.

Based on this conservative heat load calculation, it would take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 15 minutes to heat up to 1220F, which is the allowed maximum temperature for the equipment in the room.

The time for portable fan installation is 1/2 hour. Therefore, plenty of time is available for the fan installation prior to overheating and potential equipment damage.

ATTACMENT 1 Page 2 of 8 4.

NRC 00ESTION On page 11-23, -Table ^ 2-1, LT-20504A *is. listed but it appears to be lef t off figure SK-J-5007'

RESPONSE

OTSG wide range ' level ~ transmitters ~ LT-20501, LT-20502, LT-20501 A and LT-20502A only are required for safe shutdown:

Therefore, OTSG operating range level transmitters LT-20504A and 20503B and have been deleted from Table 11-1 and Figure SK-J-500.

Revised Figure SK-J-500 is attached.

5.

NRC OUESTION Figure SK-ICR-14 indicates an instrument which appears to read out in TSC? Please clarify.

RESPONSE

Figure SK-ICR-14 has been revised to show which instruments read out in the TSC and is attached.

6.

NRC OUESTION Figure SK-ISD-8 is missing the summary statement that appears on the other figures?. Please clarify.

RESPONSE

Figure SK-IDS-8 has been revised to contain a summary statement and is attached.

7.

NRC OUESTION On Figure SK-ISO-8, there appears to be a " typo" because PI-21050A is in the figure but title references loop "B"?

Please clarify.

RESPONSE

Figure SK-ISD-8 correct.

PI-21050A was incorrectly shown in loop "A" on Figure SK-J-500 and it has been corrected. Also PI-21031 was incorrectly shown in loop "B" on Figure SK-J-500 and it has been corrected.

Figure SK-J-500 is attached.

8.

NRC 00ESTION j

On Figure SK-ISD-9 there appears to be a " typo" because H2SD is in the figure by H2SP is in the summary note? Please clarify.

ATTACNNENT 1 Page 3 of 8

RESPONSE

' Figure SK-ISD-9 summary statement revised to show H2SD instead of H2SP.

The updated figure is attached.

9.

NRC QUESTION Figures SK-ISO-12 and SK-ISD-13 refer to TE-21031C and TT-21031C and TE-21032C and TT-21032C, while figure SK-J-500 refers to TE-21031C and TT-21031A and TE-21032C and TT-210328. Please clarify.

RESPONSE

1 Figure SK-J-500 has been revised to change TT-21031A to TT-21031C and TT-210328'to TT-21032C. Also interface with NNI cabinets has been deleted as this was incorrect. ;The updated figure is attached.

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10. NRC OUESTION Please clarify the requirements for the HPI pump lube oil coolers.

RESPONSE

Figure SK-M-544 has been revised to show HPI' pump lube oil coolers and is attached.

11. NRC QUESTION As shown on USAR Figure 10.2-4, can HV-20610 open to spurious signal and result in steam generator blowdown?

RESPONSE

HV-20609 (Steam Generator A) and HV-20610 (Steam Generator B) are inside containment and are in series with HV-20611 which is outside containment. Af ter Control Room evaluation, Train B buses (power HV-20611) will be denergized which will shut of f power to HV-20611.

The hot shutdown procedure will require physical verification that this valve is closed.

If the valve is open, it will be manually closed.

12. NRC QUESTION Is the letdown system needed for shutdown?

RESPONSE

NO, the letdown system is not needed for shutdown.

The primary system is bottled up in the proposed shutdown scheme and the cooling of the RCS provides enough contraction volume to maintain RCP seal cooling through RCP seal injection.

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3 ATTACHMENT 1 Page 4 of 8

13. NRC QUESTION With'a' Control Room fire are the Diesel Generators manually started?

How does loss of air affect the starting capability on loss of off site power?

RESPONSE.

As long as the Control Room interface does not disable the diesel

- generator controls, the diesel generator GEA will be automatically started even with a fire in the Control Room and loss of off site power. The under voltage start sensing system is located outside the Control Room.

If the diesel controls are lost before isolating the Control Room interface, the diesel generator will be required to be manually. operated af ter isolating f rom the Control Room.

The loss of. air does not affect the starting capability of the diesel generators on the loss of of fsite power. As stated in USAR Section 8.3.2.1, '"Each diesel has its own separate air starting system. There are-two complete air starting systems consisting of an air compressor with all automatic controls and alarns for a complete unit, two air motors, and three air receivers with a combined storage capacity suf ficient for five starts without compressor operation..." No other equipment on the diesel generator relies on plant air to run the diesels so the loss of plant air does not affect diesel operation..

/

14.NRC QUESTION On the letdown system, if you have a. fault in the motor operated valve and are depending upon the pneumatic valve, will'it close and hold?

RESPONSE

Yes, the solenoid will fail safe closed and remain closed upon loss of air for whatever reason.

15. NRC QUESTION Explain the nakeup/HPI process in detail concerning the recirculation path to the makeup tanks. Also explain how the Reactor Coolant Pump (RCP) seals are cooled?

RESPONSE

The Makeup /High Pressure Injection System performs three functions:

1) inventory control including reactor coolant system pressure control.

2) reactor coolant pump seal injection, and 3) reactivity control through boron addition.

i ATTACHMENT l' Page 5 of 8 These functions are accomplished by aligning the BWST as the suction source and aligning an injection path to the RCS and RC pump seals.

The "A" electrical power train is dedicated to the shutdown panel.

Therefore, following an Appendix R Event, the BWST suction source and injection path must be aligned from outside the Control Room. An operator

-is dispatched to the 480 volt switchgear area to position the isolation switch for the valves that are controlled from the shutdown panel. Once these switches are positioned, the BWST Isolation Valve SFV-25003 (SK-M-522) and the Makeup Tank Outlet Valve SFV-23508 (SK-M-521) are open to provide RCS inventory and pressure control.

The operator dispatched to the 480 switchgear area de-energizes the "A" powered Makeup Recirculation Valve SFV-23645 (SK-M-521) and the operator in the 4160 switchgear area de-energizes the second Make-up Recirculation Valve 5FV-23646 (SK-M-521) by de-energizing 48 bus. An auxiliary operator is dispatched to the lower level Auxiliary Building to verify valve positions.

The two de-energized makeup recirculation valves are verified to be open.

This establishes a recirculation path through the makeup tank. This path will be used until RC pump seal injection and the alternate recirculation path are established.

The RC pump seal injection path is established by an operator at lower level

(-20 foot) in the Auxiliary Building. The operator at the 480 switchgear area has de-energized the RC Pump Seal Injection Valve SFV-23616 (SK-M-521). Once all equipment is de-energized by that operator, the operator proceeds to the (-20 foot) level of the Auxiliary Building to re-establish RC Purp Seal Injection and align the alternate recirculation path. The operator equalized the pneumatic pressure on control valve PV-23606 (SK-M-521) and positions the valve manually to achieve the desired flow as read on the local flow indicator. The operator verifies SFV-23616 is open. This re-establishes RC pump seal injection. The time f rame for this to be accomplished per.the walkdown conducted during validation of the C.13A Procedure is approximately 45 minutes following Control Room evacuation.

In accordance with the walkdown, the same operator will establish the alternate recirculation path.at approximately the 100 minute -

mark.

The alternate recirculation path is established to prevent heatup of the

. Makeup Tank V-235 (SK-M-521 A) during extended. operation of the makeup /HPI pump. The heatup is due to a loss of cooling water to the seal return coolers as would occur with a loss of offsite power. The alternate recirculation path goes through the Recirculation Valves SFV-23645 and SFV-23446. The flow would normally go to the Makeup Tank, but by opening PLS-049 manual valve (SK-M-521A), the flow is directed to BWST thru Decay Heat Removal System line 26102.

The check valves DHS-003 and DHS-004 prevent the flow f rom going back to the nukeup/HPI pump suction.

The flow is directed through the decay heat pump, through the decay heat cooler, through the cross connect, and to the BWST by opening DHS-033. The operator must verify the following valve positions:

r ATTACHMENT 1 Page 6 of 8 l-Devise Name of Device Action PLS-049 MU/DH Cross Connect Verify Open SFV-26040 DH Cooler Outlet Valve Verify Open HV-26038 DH Cooler 8ypass Verify Closed HV-26047 Cross Tie to BWST Verify Open HV-26046 Cross Tie to BWST Verify Closed DHS-033 Common Cross Tie to BWST Verify Open HV-26008 LPI to HPI Verify Closed SFV-29108 R8 Spray Isolation Verify Closed SFV-29107 R8 Spray Isolation Verify Closed HV-23004 Letdown 3-Way Valve Position to Flash Tank PLS-044 MU Tank Inlet Verify Closed CBS-003 R8 Spray Pump Suction Closed CBS-004 R8 Spray Pump Suction Closed Once this lineup is complete, the operator at the shutdown panel will close the Makeup Tank Outlet Valve SFV-23508.

For the duration of the event, the Makeup System can be operated continuously without de-energizing the Makeup /HPI Pump and without fear of pump damage due to low flow. The

~ alignment requires an operator to manually close the RC pump seal injection line twice per hour once the RCS temperature is below 4000F. To this point, the RCS temperature control is maintained by continuous RC pump seal injection and by opening SFV-23811 from the shutdown panel as required to stay within the plant pressure temperature limits.

Below 4000F, the RC pump seals will be batch fed twice per hour by manually controlling PV-23606. This operation will continue until decay heat initiation occurs at approximately 2900F.

Reactivity Control is achieved by using borated water from the BWST.

If the plant is more than 130 effective full power days into the fuel cycle additional boron is required from a concentrated source of borated water.

16 NRC 00ESTION 4

Provide a description of _ auxiliary fee'dwater pump operation including valves.

r-

RESPONSE

4 The Auxiliary Feedwater System through'the Main Steam Safety Valves and Atmospheric Dump Valves (ADV) perforns three functions during an Appendix R event. These functions are:

1) furnish an emergency feedwater supply to the stream generators, 2) remove heat from the Reactor Coolant System so natural circulation i

l may be established,'and 3) reject heat from the secondary system to the atmosphere.

L

o ATTACHMENT 1 Page 7 of 8 These functions are accomplished by aligning the Condensate Storage Tank T-358 (SK-M-532) as the suction supply to the motor driven Auxiliary Feedwater Pump P-319 (SK-M-532). The dual drive AFW Pump P-318 (SK-M-532) will be de-energized electrically by the operator at the 4160 volt switchgear area, and the turbine will be tripped locally by an operator dispatched to the AFW pump area at grade level. The motor driven pump will be isolated from the Control Room by an isolation switch located in the 4160 volt switchgear area and will be operated from the motor switchgear.

AFW Pump P-319 will provide emergency feedwater to the "B" Steam Generator through the AFW Bypass Valve SFV-20578 (SK-M-532), which is isolated from the Control Room interface by an isolation switch and controlled from the shutdown panel. To control the flow to the "B" Steam Generator, the pneumatic AFW Control Valve FV-20528 (SK-M-532) must be closed. The operator that was dispatched to the AFW Pump area will equalize the air pressure on the Control Valve FV-20528 and verify the valve is closed.

The "A" Steam Generator auxiliary feedwater flow was stopped initially to prevent an uncontrolled overcooling of the RCS. This was accomplished by de-energizing and tripping the dual drive AFW Pump P-318 and by closing the AFW Cross Connect Valve HV-31827, which is isolated from the Control Room interface and controlled from the shutdown panel.

Once the operator at the AFW control valve complex has positioned the valves for the "B" Steam Generator, the operator will proceed to the "A" AFW control valve complex.

At the "A" control valve complex, the operator will equalize the air pressure on the pneumatic valve FV-20527 (SK-M-532) and verify the valve is open.

The operator will then return to the AFW pump area and verify the AFW Cross Connect Valve HV-31826 (SK-M-532) is open by manually positioning the valve as required. Valve HV-31826 was de-energized by the operator at the 480 volt switchgear area. Once the Cross Connect Valve HV-31826 and the AFW Control Valve FV-20527 are verified open, the operator at the shutdown panel can control the "A" Steam Generator level from the shutdown panel by controlling the second AFW Cross Connect Valve HV31827 for the "A" Steam Generator. This provides controlled AFW flow to both steam generators from the shutdown panel. Natural circulation heat removal will be established with AFW supplied from the Condensate Storage Tank T-358. The Atomspheric Dump Valves PV-20571 A, 8, and C and PV-20562 A, B and C and the Condenser Dump Valves PV-20561, PV-20563, 'and PV-20564,' and PV-20566 (SK-M-530) are pneumatically controlled valves. With a loss of air pressure due to the loss of offsite power, these valves will fail closed due to the check valve and local accumulator system mounted on'each valve. This assures these valves are closed until manual control over the Atmospheric Dump Valves PV-20571 A, B, and C and PV-20562 A, B,'and C can be established.

With AFW flow established,' steam generators refilling, and the atmospheric dump valves and condenser dump valves de-energized and closed, heat is being removed f rom the Steam Generataors and exhausted to the atmosphere through the main steam safety valves.:

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ATTACHMENT 1 Page 8 of 8 The plant will be controlled by using the valves SFV-20578 and HV-31827 to control steam generator level.

If the condensate storage tank is expended prior to initiating the Decay Heat System, a gravity system is available f rom the reservoir to provide a backup auxiliary feedwater supply.

Final cooldown of the plant is accomplished by achieving control over the atmospheric dump valves by activating the manual loader station from the ADV's. 'This loader station will control the ADV's in order to reduce the secondary side pressure and maintain the plant in a continuous controlled cooldown mode.

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SACRAMENTO MUNICIPAL UTILITY DISTRICT RESPONSE TO CLARIFICATION OF GENERIC LETTER 81-12 d

DATE: JULY 1985 1-i-

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1

. TABLE OF CONTENTS SECTION-DESCRIPTION PAGE

-I Introduction I-1 II.

Response to Attachment.1_of Clarification to 11-1

. Generic Letter 81-12 III-ResponsetoSafeShubownCapability-. Associated

'III-1 Circuits - Attachment' 2 to Clarification 'to Generic Letter 81-1,2,

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IV.

Response to High-Low Pressure Interface Questions IV-1 from Attachment 2 to Clarification to Generic Letter 81-12

+

r-LIST OF TABLES-c.

Table 11-1 List of Instrumentation'and Equipment For Normal II Control Room Shutdown' Requiring ~ Alternative Shutdown

. Table II-2 New Component's1to-be Added to Provide Alternate 11-30 Shutdown Capability

. Table.III-1 Power Circuits in the Control Room that have the III-4 Same Power Source as Alternate Shutdown Equipment Table _III Cables considered for Spurious Operations III-5 1

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LIST OF FIGURES

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Drawina Number Title s

SK-E-87, Sheet i Elementary Diagram Appendix R Analysis Showing Control Room Interface Diesel Engine Control SK-E-87, Sheet 4 Elementary Diagram Appendix R Analysis Showing Control Room Interface Diesel Generator.

SK-E-200 -

Legend For. Electrical Equipment Appendix R Analysis SK-E-203, Sheet 2 Elementary Diagram Appendix R Analysis Showing Control Room Interface P-236 SK-E-203, Sheet 3 Elementary Diagram Appendix R Analysis Showing Control Room Interface P-261A SK-E-203, Sheet 4 Elementary Diagram Appendix R Analysis Showing Control Room Interface P-238A SK-E-203, Sheet 37 Elementary Diagram Appendix R Analysis Showing Control Room Interface P-238A L.O. Pump SK-E-203, Sheet 42 Elementary Diagram Appendix R Analysis Showing Control-Room Interface P-472A, 8 SK-E-203, Sheet 50C Elementary Diagram Appendix-R Analysis Showing Control Room Interface-

-SFV-20577/78 SK-E-203, Sheet 50G Elementary Diagram Appendix R Analysis Showing Control Room Interface'SFV-23811-SK-E-203, Sheet 68 Elementary Diagram Appendix R Analysis Showing Control Room Interface SFV-25003 SK-E-203, Sheet 97 Elementary Diagram Appendix R Analysis Showing Control Room Interface SFV-23508 SK-E-204, Sheet.1 Elementary Diagram Appendix R Analysis Showing Control Room Interface S4A08 SK-E-204, Sheet ilA Elementary Diagram Appendix R Analysis

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Showing Control Room Interface P-888A SK-E-205, Sheet 1

' Elementary Diagram Appendix R Analysis Showing Control Room Interface P-319 SK-E-205, Sheet 20F

< Elementary, Diahram Appendix R Analysis

' Showing Control Room Interface HV-31827

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SK-E-208, Sheet 10 Elementary Diagramf Appendix R Analysis Showing Control, Room Interface 54A09 s..

SK-E-208, Sheet 13A' Elementary' Diagram AppendNc R Analys?s

_" Showing Control Room Interface 53A05 1

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~3, Sheet Index' Appendix'R' Analysis

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SK-I-2 Legend Appendix R Analysis i

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-SK-ICR-1 Lobp Diagram' Appendix R Analysis Control Room Display LT20501 SK-ICR-2

' Loop Diag' ram Appendix R Analysis Control Room Display LT20502 SK-ICR-5 Loop Diagram Appendix R' Analysis Control Room Display LT21503A e

SK-ICR-6 Loop Diagram Appendix R Analysis Control Room Display LT21503C SK-ICR-7 Loop Diagram Appendix R Analysis Control Room Display LT23502A/8 SK-ICR-8 Loop Diagram Appendix R Analysis Control Room Display PT20519A/B

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SK-ICR-9 Loop Diagram Appendix R Analysis Control Room Display LT20520A/8 SK-ICR-10 Locp Diagram Appendix R Analysis Control Room Display Source Range NI-1 and NI-2 SK-ICR-11 Loop Diagram Appendix R Analysis Control

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Room Display PT20543A/B SK-ICR-12 Loop Diagram Appendix R Analysis Control Room Display PT21042/43

. SK-ICR-13 Loop Diagram Appendix R Analysis Control Room Display PT21092/99 SK-ICR-14 Loope Diagram Appendix R Analysis Control Room Display TE21023A/B SK-ICR-15 Loop Diagram Appendix R Analysis Control Room Display TE21024A/B SK-ICR-16 Loop Diagram Appendix R Analysis Control Room Display TE21029/30/33/34 111

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Drawina Number Title

'SK-ISD-l Loop Diagram Appendix R Analysis Alt.

Shutdown Panel LT20501A

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SK-ISO-2 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel LT20502A SK-ISD-3 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel LT215038 SK-ISD-4 Loop Diagram Appendix R Analysis' Alt.

Shutodwn Panel LT215030

-SK-ISD-5 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel LT23502C SK-ISD-6 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel PT20543C SK ISD-7 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel PT20543D

'SK-ISD Loop Diagram Appendix R Analysis Alt.

Shutdown Panel PT21050 SK-ISD-9 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel PT21051 SK-ISD-10 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel TE21024C SK-ISD-11 Loop Diagram Appendix R Analysis Alt.

Shutodwn Panel TE21025C SK-ISD-12 Loop Diagram Appendix R Analysis Alt..

Shutdown Panel TE21031C SK-ISD-13 Loop Diagram Appendix R Analysis Alt.

Shutdown Panel TE21032C SK-ISD-14 Loop Diagram Appendix R Analysis Local

' Display Portable Source Range Neutron Flux Indicator 4

SK-J-500

.P&I. Sketch Appendix R Analysis Safe Shutdown Instrumentation I

SK-M-500 Legend-for Piping and Instrument Sketch Appendix R Analysis SK-M-520, Sheet 1 P&I' Diagram Appendix R' Analysis Reactor Coolant System' i

SK-M-520, Sheet 2 P&I Diagram Appendix R Analysis Reactor i,

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P&I Diagram Appendix R Analysis

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SK-M-524

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SK-M-526 P&I Sketch Aopendix R Analysis Make-up % H,PI Pressure Switches SK-M-530 P&ISketcbAppendixRAnalysis Atmospheric Steam Dump & Turbine

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P&I Sketch; Appendix R Analysis

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SK-M-582 P&I Sketch Appendix R Analysis Diesel Generator 8 One Line Diagram 416,0 Yolt System p4A E-104, Sheet-2

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r SECTION I 2

INTRODUCTION This document contains the Sacramento Municipal Utility District's response to the clarification of Generic Letter 81-12.

It is written in an NRC request - District response format.

Section II provides the additional information on the alternative shutdown methods requested in Attachment 1 of the clarification letter.

Section III provides the details of the District's associated circuit analysis requested in Attachment 2 of the clarification letter.

Section IV discusses all high-low pressure interface as required by the second part of Attachment 2 of the clarification letter.

Supplementary tables and drawings are attached to provide all the information needed to review the District's alternative shutdown method for a fire in the Control Room.

A M

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SECTION II RESPONSE TO ATTACHMENT 1 0F CLARIFICATION TO GENERIC LETTER 81-12 NRC REQUEST 1.

Identify those areas of the' plant that will not meet the requirements of Section III.G.2.of Appendix R and, thus alternative shutdown will be provided or an exemption.from_the requirements of Section III.G.2 of Appendix R will be provided. Additionally, provide a statement that all other areas of the plant are or will be in compliance with Section III.G.2 of Appendix R; DISTRICT RESPONSE The following areas of the~ plant do=not meet the requirements of Section III.G.2 of Appendix R and, thus, alternative shutdown will be provided:

Fire Area 1 - Control / Computer Room Fire Area RT1 - Control / Computer Room Corridor Fire Area 74 - Auxiliary Building. Roof The following areas of the plant do not meet the requirements of Section III.G.2 of Appendix R and exemption requests have been provided:

Fire Area 47 - Corridor to Elevation 47 An exemption request for Fire Area 47 was submitted on March 17, 1981.

It involves a lack of an automatic fire suppression system in the area. The District provided additional information for the exemption for Fire Area 47 on May 28, 1982. The exemption was granted by the NRC on January 10, 1983.

Fire Area 49 - West Containment Valve Area An exemption request for Fire Area 49 was submitted on March 17, 1981.

It involves a lack of an automatic fire suppression system in the area. The District provided additional information for the exemption for Fire Area 49 on May 28, 1982. The exemption was granted by the NRC on January 10, 1983.

II-1

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Fire Area 48 - Train "A" HPI Pump Room An exemption request for Fire Area 48 was submitted on March 17, 1981.

It involves a lack of an automatic fire suppression system in the area and the lack of a one-hour barrier. The District provided additional information for the exemption for F.re Area 48 on May 28, 1982. The exemption was-granted,by the NRC on January 10, 1983.

Fire Area 58 - Makeup Pump Room An exemption request for Fire Area 58 was submitted on March 17, 1981.

It involves a lack of an' automatic fire suppression-system in the area and the lack of a one-hour fire barrier.,~The District provided additional' information for the exemption for Fire Area 58 on May 28, 1982. The exempti_on was granted by the NRC on January 10, 1983.,

Fire Area Auxiliary Feedwater, Pumps An exemption request for' Fife Area 69 regarding the Auxiliary Feedwater Pumps was submitted on February 28, 1985. This is a new exemption which resulted from the Appendix R Re-evaluation.

It involves a lack of separation in an' outdoor situation where a radiant energy shield, and, fire suppression and detection are proposed.

Fire Area 69 - Auxiliary'Feedwater Valves

~

An exemption request for Fire Area 69 regarding the Auxiliary Feedwater: Valves was submitted on February 28..

1985. This is a new exemption which resulted from the Appendix R Re-evaluation. The redundant valves in an-outdoor situation lack suppression and detection but have a fire break installed in an intervening cable tray.

Fire Area 68 - Cables Inside Containment, Electrical Penetration Area An exemption request for Fire Area 68 was submitted on February 28, 1985. This is a new exemption which resulted from the Appendix R Re-evaluation.

Intervening combustibles require a cable tray fire break to be installed which is not listed as an-option under Appendix R.

_ Fire Area ~RG1 - Auxiliary Building Electrical Penetration Area An exemption request for Fire Area RG1 was submitted on February 28, 1985. An exemption request for Fire Area 34

was submitted on July 24, 1984.

Based on the Appendix R Re-evaluation that request requires modifications.

II-2

Fire Area RBI - Auxiliary Building Mechanical Penetration Area An exemption req'est for Fire Area:RB1 was submitted on L

u February 28. 1985., Exemptions for. Fire" Area 49, West Containment Valve Area, and Fire Area 58 Makeup Pump Room. were granted on January 10, 1983. As a result of the Appendix R Re-evaluation,' Fire Area 49, 50, 51, 52, 58, and 60 were incorporated into one fire area, RBl. A new exemption request 3resulted for the fire boundary of RBl. The previous approved exemption for F.A. 49 required wrapping'a' cable tray through F.A. 49 which

~

contains circuits for the makeup pump. This wrapping is no longer necessary as the makeup pump room is part of the new F.A. RBI and this exemption negates the need for the previously' approved exemption.-

72-Hour Cold Shutdown An exemption request for 72-hour cold shutdown was submitted on February 28, 1985. This is a new exemption which resulted from the Appendix R Re-evaluation.

For a loss of offsite power, it is not possible to achieve cold shutdown in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

NSRW Pumps An exemption-request for the NSRW Pumps was submitted on February 28, 1985. This is a new exemption which resulted from'the Appendix R Re-evaluation.

It involves lack of detection and suppression for an outdoor installation with over 400' of separation..

Fire Area 91 - NSEB Roof An exemption request for the NSEB Roof was submitted on April 4, 1985. This is a new exemption which resulted from the Appendix R Re-evaluation.- It involves lack of detection and suppression for redundant essential HVAC units.

Fire Area 69 - Nuclear Service Yard Area An exemption request for the NSW Pumps was submitted on-May 24, 1985., This is a new exemption which resulted from the Appendix R Re-evaluation.

It involves the lack of detection and suppression for an outdoor installation with approximately 55' of separation.

II-3 y

Fire Area 74 - Auxiliary Butiding Roof An exemption request for the Nuclear Service Cooling

Water Surge Tank Level Switches was submitted on May 24, 1985. This is'a new exemption which resulted from the Appendix R Re-evaluation.

It involves the lack of detection and-suppression for.an outdoor installation with approximately 40' ofiseparation.

The following area,of the plant does not' meet the requirements of Section' III.G.3 of, Appendix.R and.an exemption request has been provided:

Fire Area 74 Iuxiliary Building Roof

~

An exemption request f6r the Auxiliary Building Roof was submitted.on~May-24 1985.1 This is a new exemption which resulted from the Appendix R Re-evaluation.

It involves a lack of detection and suppression for redundant

.essentia1 HVAC units.

The following' area of th'e' plant does riot meet the requirements of Section III.G.3 of Appendix R, but an exemption request is not required:

Fire Area 1 - Control / Computer Room The staff's denial of a previously requested exemption (January 10,'1983) for this area stated that, "with the alternate shutdown capability installed, a suppression system is not required in the area."

Fire Area RT1 - Control / Computer Room Corridor Fire detection in the corridor has been installed and a suppression system already exists.

The District has embarked on an Appendix R Re-evaluation-program..This program, to date..has resulted in the-

. identification of 1) crevisions to previously submitted exemptions,2) additional ^ exemption requests, 3) plant modifications, and 4) this revision to the Response to Generic Letter 81-12.

Fire areas requiring plant modifications for compliance with Appendix R are provided with the necessary compensatory measures if the modifications are not complete at this time. The District has ensured Rancho Seco's compliance with Appendix R, III.G, either by analysis,.

modification, exemption request or by putting suitable compensatory measures into place until resolution of the concern is reached.

II-4

~

~

NRC REQUEST For each of those fire areas of the plant requiring an alternative shutdown' system (s) provide a complete set of responses to the following requests for each fire areat DISTRICT RESPONSE The responses provided are developed for Fire Area 1 -

Control / Computer Room.

For Fire Area RT1 - Control / Computer Room and Fire Area 74 - Auxiliary Building Roof, a fire will disable the redundant essential HVAC units and result in evacuation of the. Control Room.

Fire Area RT1 does not contain any other redundant equipment required for safe shutdown and the responses' developed for Fire Area 1 are applicable.

Fire Area 74 contains the redundant Nuclear Service Cooling Water Surge Tank Level Switches (see May 24, 1985 exemption request).

For the fire in Fire Area 74 or Fire Area 1, the method for handling the Nuclear Service Cooling Water Surge Tank. instrumentation is the.same and the responses developed for Fire Area 1 are applicable, a.

List the system (s) or portions thereof used to provide the shutdown capability with the loss of offsite power.

DISTRICT RESPONSE The systems used to reach cold shutdown with a loss of offsite power are the following:

1.

PLS (Purification and Letdown System) and SI!! (Seal Injection and Makeup System).

2.

DHS (Decay Heat System) and CFS (Core Flood System).

3.

RCS Reactor Coolant System).

4.

FWS (Feedwater System - AFW and Main FW Pump Train).

5.

NRW (Nuclear Raw Water System).

6.

NSW (Nuclear Service Water System).

7.

EGS (Emergency Generating System).

8.

HVS (Heating Ventilation and Air Conditioning System)..

9.

SAS (Service Air System).

10. EDS (Electrical Distribution System).
11. Selected Instrumentation.

.II-5

p F

  • i 3

_A NRC REQUEST

~

b.

For those systems identiffed in'"la" for which alternative or dedicated shutdown capability must be provided, list the equipment and components of'the. normal shutdown system in the fire area and identify the functionsfof the circuits of the normal shutdown system in the fire area-(power to what equipment, control of what components and instrumentation).

Describe the system (s) or portions thereof used to provide the alternative shutdown

capability for the fire area and: provide a table that lists the

-equipment and components of the alte' native shutdown system for the fire area.

For each alternative system, identify the function of the new circuits being provided.

Identify the location (fire zone) of the alternative shutdown equipment and/or circuits that bypass the fire area and verify that the-alternative shutdown equipment and/or circuits are separated from the fire area in accordance with Section III.G.2.

DISTRICT RESPONSE A fire in the Control Room is assumed to destroy the controls and instrument indications for equipment of both trains of the systems listed above in "la".

The alternative shutdown capability consists of an alternative method of controlling Train A components of the systems listed in "la" and an alternative set of instrumentation to monitor the necessary plant parameters. Table II-1 lists all the components, circuitry and circuitry function for the Train A equipment of the systems listed above in"la" and located in the Control Room and which require alternate shutdown capability.

Information is provided on Train B valves when in series with a Train A valve on a required flow path.

The alternative shutdown capability does not require any new systems. Existing plant equipment is isolated from the Control Room, pumps are controlled from the switchgear, and controls are provided to throttle valves on the existing shutdown panel. The existing instrumentation on the shutdown panel is supplemented to monitor all parameters necessary to achiev'e and maintain natural circulation. Table II-2 shows the components added to the existing control circuits and instrument loops, and the new instrumentation added. New isolation switches are installed on the switchgear and MCC compartments. Switchgear loads already have local controls, but the ontrols for the MCC loads are installed on the existing shutdown panel located in the West Switchgear Room on-the grade elevation, which is separated from the Control Room in accordance with Section III.G.2.

f II-6

, c NRC REQUEST e.

Verify that the licensee procedures have been or will be developed which describe the tasks to be performed to effect the shutdown method. Provide a summary of these procedures outlining operator actions.

DISTRICT RESPONSE The District has developed procedures for performing shutdown in the event of a fire in the Control Room. The procedures encompass shutdown with and without offsite power.

The procedures have been finalized and approved, and operator training has been conducted.

The methodology used in the procedures was patterned after the Abnormal Transient Operating Guidelines (AT0G) for a loss of offsite power. The objectives of the prccedure were to prevent overcooling of the RCS, establish inventory control, and establish primary to secondary heat transfer. The major operator actions are:

1.

De-energize the EMOV.

2.

Gain control over the AFW and HPI valves controlled from the shutdown panel.

3.

Establish AFW to "B" 0TSG.

4.

Initially isolate AFW to "A" 0TSG. Then re-establish feed to "A" OTSG.

5.

Re-establish plant air.

6.

Assure main steam isolation.

7.

Isolate and start the Diesel Generator as required.

Once these steps are performed, HPI and RC Pump Seal Injection will be established. This will assure control over the plant The plant will be stabilized in a hot shutdown condition before being taken to cold shutdown. All system contraction will be made up from the BWST. With slight variations in the normal shutdown proc _ess,'a one percent delta k/k shutdown margin will be: maintained through the entire cooldown process.

The following is an outline.of the Appendix R Hot and Cold Shutdown Procedures:

This ptocedure is in place for-the first 130 Effective Full Power Days following startup from the 1985 Refueling Outage.

Then a boric acid repair procedure is required.

II-8

On the decision to evacuate the Control Room, the operators will perform the following:

a.

Trip the Reactor / Turbine (confirm all rods in),

verify throttle and governor valves are closed.

b.

Trip both Main Feedwater Pumps.

c.

Evacuate the Control Room d.

Proceed to the 4160 West Switchgear Room area.

2.

The shift supervisor will take action required to receive additional assistance, restrict damage due to the casualty, and classify the event.

3.

The Senior Control Room Operator (SCRO) shall direct operator 1 to proceed to the 480 Volt West Switchgear Room to perform required tasks. The SCR0 will proceed to the 4160 West Switchgear Roou, will announce the fire, will direct the shutdown of the plant and act as the central point for communications with all operators.

4.

The Control Room Operator (CRO) will proceed to the 4160 Volt West Switchgear Room. The CR0 will isolate the 4160 volt equipment needed to operate the event and de-energize the remaining 4160 volt equipment.

5.

Operator 1 will de-energize the EMOV, isolate the motor operated valves controlled from the Shutdown Panel, de-energize the 480 volt equipment, line up RCP seal injection and the alternate recirculation path.

6.

Operator 2 will re-establish >p'lant: air; position the AFW valves, trip the AFW pump turbine and position the makeup s

system valves.

7.

Operator 3 will isolate the' emergency ' diesel and position the main steam valves.

8.

These actiond will result in the reactor being'in hot y

shutdown and once stabilized at hot shutdown, the cooldown will begin.

9.

Cooldown will be achieved by cont'rol'of RCS temperature (by controlling Atmospheric Dump Valves) to maintain RCS temperature versus RCS pressure within the normal cooldown limits _.

10 The Decay Heat Removal System will be initiated at a primary pressure below 255 psig, and RCS temperature below 2900F.

11.

When the primary system tempeature is below 2000F, the plant will be in cold safe shutdown condition.

II-9

r' NRC REQUEST

-f.

Verify that the manpower' required to perform the shutdown functions using the procedures of (e) as well as to provide fire brigade members to fight the fire is available as required by the fire brigade-technical specifications.

DISTRICT RESPONSE The District's currant commitment requires 9 operations personnel on shift for a reactor mode other than cold shutdown (R. J. Rodriguez letter to M. D. Schuster -~NRC. Region V, dated October 19,1984). The Appendix R Hot Shutdown 7

l Procedure requires 5 operations personnel to perform the j

shutdown functions. The fire brigade requires 5 members.

For a fire which requires evacuation of the Control Room, r-operations will respond with 3 personnel for the fire brigade. The additional fire brigade members, for the cas'e of Control Room evacuation, will be provided by non-operations personnel. The Shift Supervisor will assume the position and responsibilities of Emergency Coordinator.

For the limiting.

scenario of hot shutdown and control room evacuation, there is sufficient manpower available to perform all required functions..

i NRC REQUEST-g.

Provide a commitment to perform adequate. acceptance test of the l

alternative shutdown capability. Modify existing surveillance procedures. These tests should verify that:' equipment operates from the local control. station when the trr.nsfer or isolation L

switch is placed in the " local" position, and that equipment operates from the Control Room but cannot be operated at the local i

control station when the.transferLisolation switch is in the

" remote" position.

i

\\.

l

. DISTRICT RESPONSE,

t

^

The District's.swit'ch'has two positions, one is " normal" and j.

the other is " isolate Control Room"._.The " normal" position t-indicates that' control is'available:from-the Control Room and L

the local control station, not alternative shutdown panel.

The " isolate Control Room". position-allows control only from the local station and the, alternative shutdown panel with the Control Room isolated." The overall safety of the plant would n

j be jeopardized by isolating the Control Room for all local control operations that are required for other safety concerns r

independent of Appendix R.

Adequate acceptance testing of the Control Room isolation switches and local controls providing alternate shutdown capability will be performed when the switches are initially installed. Testing will consist of verifying that with the isolation switch placed in the II-10 L

" isolate" position, the equipment cannot be operated froF the control Room but can be operated from the local control station. With the switch in " normal" position, it will be verified that equipment operates from the Control Room.

However, operation from the local station will be possible, but not from the alternative shutdown panel.

Existing surveillance procedures will be modified or new surveillance procedures will be written, as required, to include the new equipment.

NRC REQUEST h.

Provide Technical Specification of the surveillance requirements and limiting conditions for operation for that equipment not already covered by existing Technical Specifications.

For example, if new isolation and control-switches are added to a shutdown syttem, the existing Technical Specification surveillance requirements should be supplemented to verify system / equipment functions from the alternate shutdown station at testing intervals consistent with the guidelines of Regulatory Guide 1.22 and IEE 338. Credit may be taken for other existing tests using group overlap test concepts.

DISTRICT RESPONSE The existing Technical Specifications adequately address the surveillance requirements and limiting conditions for i

operations for required equipment. The testing of isolation i

and control switches will be addressed'in existing and/or new t

surveillance procedures. These surveillance procedures will be written-and approved before the first testing interval following the declaration of the system operability.

NRC REQUEST 1.

For new equipment comprising the alternative' shutdown capability, 1

verify that the systems available are adequate to perform the necessary shutdown function. -The functions required should be based on previous analyses,;1f possible (e.g., in the FSAR), such as a loss of normal ac power or shutdown on Group 1 isolation (BWR). The equipment required for,the alternative capability should be the same or equivalent to that relied on in the above analysis.

DISTRICT RESPONSE ' ~

The equipment required for the alternative shutdown capability is the same or equivalent to that relied upon in the original Safety Analysis. The alternative shutdown panel modifications.

include adding indication and control of existing systems and isolation only.

II-11

4 NRC' REQUEST-j.

Verify tha't repair procedures for cold shutdown systems are developed and material for repairs,is maintained on site.

Provide a summary of these procedures and a-list of the material needed for repairs.

DISTRICT RESPONSE The District has developed the necessary repair procedures for cold shutdown equipment. The following is a summary of each repair procedure:-

Temporary Atmospheric Dump Valve ~(ADV) Nitrogen System The atmospheric dump valves (ADV's) are used to control the cooldown process from hot shutdown to cold shutdown following a fire in the Control Room.

If the plant air system is lost. temporary air. supply to manually operate the ADV's must be provided. A procedure.has been written for the hookup of a temporary nitrogen bank to the plant air-system to operate the ADV's.

Decay Heat System Return Temperature Monitoring During Loss of Non-Nuclear Instrumentation A fire in the Control-Room could destroy the Non-Nuclear 1

Instrumentation (NNI) cabinets, causing a loss of all remote Decay Heat System (DHS) indications. A procedure has been written'to provide..DHS. return temperature indication at'RTD'TE-26043,~.DHS. cooler "A" outlet, using a volt-ohmeter and a calibration curve.

Port'ableSource'RangeNeutronFluxIndIcator J

^

' A fire in the Coritrol Room could destroy the nuclear instrument 6 tion cabinets which supply the source range neutron count rate to indication located'at the emergency shutdown' panel.

'A' portable. sourceirange neutron flux

. indicator is'provided for temporary connection to one of the installed sourc'e4 range detector cable at the penetration into the reactor building. The portable indicator includes a high voltage power supply module, a count rate' amplifier module, a source range test module and a law voltage power supply.

A= procedure has been written for proper connection, operation and disconnection of the portable source range neutron flux indicator.

1 L

II-12 i

r-iloss of Switchgear Ventilation A loss of offsite power or an impairment of the. existing HVAC system may cause an unacceptable heat build-up in safe shutdown switchgear. A procedure has been written to provide a method of ventilating the switchgear rooms by dissipating the heat generated by the switchgear via portable fans and flexible ducting.

Sound-Powered Phone Repair A fire in the Control Room could damage the sound-powered phone system.. A procedure has been written to perform a circuit' isolation of damaged phone lines and return the sound-powered phone system to operation.

Emergency. Repair of Atmospheric Dump Valve (ADV) Air Hoses After a Fire A fire at the ADVs could destroy the air hoses connected to the ADV positioner. A procedure has been written to replace the damaged hoses and return the ADVs to operation.

These procedures, except for boric acid repair procedure which will be finalized and approved before reaching 130 Effective Full Power Days following the start-up from the 1985 refueling outage, have been finalized and approved, and information has been given to appropriate personnel.

A separate Inventory Control system has been developed which includes a list of all material required for making necessary repairs and methods to ensure,the material will be maintained on site. The Inventory Control system.has been finalized and approved.

s e

5 II-13

r TABLE II-1 LIST OF EQUIPMENT AND INSTRUMENTATION REQUIRING ALTERNATIVE SHUTDOWN CAPABILITY System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room PLS & SIM (PURIFICATION AND

~

LETDOWN SYSTEM, SEAL INJECTION AND MAKEUP ~ SYSTEM)

P-238A (3)

SK-E-203 Sh. 4 Ammeter IP1A04A Ammeter circuit HPI Pump "A" SK-M-521 Ammeter.

IP1A04B Ammeter circuit BLPB1-Start IP1A04D PB control & light BLPB3-Stop indication circuit BLPB2-Start 1 PIA 04H PB control & light indication circuit BLPB4-Stop SF actuation circuit 1P1A04J P-238A LOP (7)

SK-E-203 Sh. 37 BLPB1-Start IM1A102F PB control & light HPI Pump "A" SK-M-526 BLPB2-Stop indication circuit Lube 0il Pump SFV-23811 (2)

SK-E-203 Sh. 50G BLPB1-Close 1DIC08C PB Control &-light Loop A Injection SK-M-521 BLPB2-Open indication circuit Valve 101C080 SF actuation circuit i

ID1C08E SF actuation circuit 101C08F SF actuation circuit SFV-23809 (1)

E-203 Sh. 50E BLPB1-Close 1DIC05C PB control & light Loop A Injection SK-M-521 BLPB2-Open Indication. circuit Valve ID1C050 SF actuation circuit 4i 101C05E SF actuation circuit 101C05F SF actuation circuit J

l SFV-23812 (1)

E-203 Sh.-50H BLPB1-Close ID1005C PB control & light Loop B Injection SK-M-521 BLPB2-Open indication circuit j

Valve 101005D SF actuation circuit 101005E SF actuation circuit 1D1D05F SF actuation circuit SFV-23810 (1)

E-203 Sh. 50F BLPB1-Close 1D1003C PB control & light Loop B Injection SK-M-521 BLPB2-Open indication circuit Valve 101D05D SF actuation circuit 101D05E SF actuation circuit 1D1005F SF actuation circuit i

II-14 I

4

T m

TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room P-236 (3)

SK-E-203 Sh. 2 Ammeter IP1A02C Ammeter circuit Make-Up Pump SK-M-521 BLPB1-Start 1P1A02E PB control & light BLPB2-Stop indication circuit 191A02H SF actuation circuit SFV-22023 (5)

E-203 Sh. 48 BLPB1-Open 1M1A133A PB control and Letdown Isola-SK-M-521 BLPB2-Close indication circuit tion Valve IM1A136B SF actuation circuit (SFV-22009) (1)

E-203 Sh. 62 BLPB1-Open 1RIC2200B PB control and Letdown Isola-SK-M-521 BLPB2-Close indication circuit tion Valve 1RIC220DD SF actuation circuit 1RIC220DF Valve indication ckt 1RIC220DE Valve control circuit 101801A Valve power circuit 1RIC220DK Auto close circuit BLPB1-Open 1RIC220DM PB control and BLPB2-Close indication circuit on HIRC panel SFV-24004 (5)

E-203 Sh. 69 BLPB3-Open 1M1A136B PB control and RCP Seal Return SK-M-521 BLPB4-Close indication circuit Valve IM1A136C SF actuation circuit (SFV-24013) (1)

E-203 Sh. 63 BLPB1-Close 1RIC240A PB control and RCP Seal Return SK-M-521 BLPB2-Open indication circuit Valve IR1C240B SF actuation circuit 1RIC240C Valve control circuit 1RIC240D Light indication ckt 1RIC240G Valve auto close ckt 1R1C240H Valve auto close ckt 1RIC240I Valve auto close blocking circuit SFV-23604 (1)

E-203 Sh. 49 BLPB1-Close 101C03C PB control and RC System SK-M-521 BLPB2-Open light-indication ckt MU Isolation MOV 101C03D SF actuation circuit 101C03E SF actuation circuit 101C03F SF actuation circuit HV-23004 (1)

E-203 Sh. 61 BLPB1-Bleed 1M20430A PB control and Letdown to MU SK-M-521 BLPB2-Normal indication circuit or Flash Tank IM20430C Valve actuation Valve signal circuit SFV-23508 (2)

SK-E-203 Sh. 97 PB-Open 1M1A172A PB control & light Make-Up Tank SK-M-521 PB-Close indication circuit Isolation Valve 1M1A1720 SF actuation circuit 11-15

i;

]

TABLE II-1

~ System / Equipment Schematic /P& ids.

Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room SFV-23645 (1)

E-203 Sh. 528 BLPB1-Open IM1A121A PB control'& light indication circuit HPI/MU Pump SK-M-521 BLPB2-Close SF actuation circuit Recire. Valve 1M1A1210 (SFV-23646) (1)

E-203 Sh. 52B BLPB1-Open 1M18141A PB control & light HPI/MU Pump SK-M-521 BLPB2-Close indication circuit Recirc. Valve 1M1B141B SF actuation circuit SFV-25003 (2)

SK-3-203 Sh. 68 BLPB1-Open 1M1A137A PB control.& light HPI/DH Pump "A" SK-M-522 BLPB2-Close indication circuit Suction from BWST BLPB3,4,5,6 1M1A1370 Light indication circuit IM1A137E SF actuation circuit PV-23606 (1)

SK-M-521 1R2C236X1 Valve solenoid Seal Injection actuation circuit Flow Control Valve SFV-23616 (1)

E-203.Sh. 54 BLPB1-Open 1M1B143A PB control & light Seal _to RC Pump SK-M-521 BLPB2-Close indication circuit 1M1B143G Valve auto actuation signal circuit IM18143H RC pump'under power signal circuit DHS (DECAY HEAT SYSTEM)

P-261A (3)

SK-E-203 Sh. 3 Ammeter IP1A05A Ammeter circuit Decay-Heat Pump SK-M-522 1P1A058-PB control & light indication circuit IP1A05C SF actuation circuit.

I SFV-26039 (1)

E-203 Sh. 81 BLPB2-Open 1M1A106B PB control & light DH Cooler SK-M-522 BLPB1-Close indication circuit E-260 Outlet BLPB1-Open IM1A106E PB control & light Valve BLPB2-Close indication circuit IM1A106C SF actuation circuit HV-26037 (1)

E-203 Sh. 80 BLPB1-Op.en 1M1A107A PB control & light DH Cooler SK-M-522 BLPB2-Close indication circuit E-260A Bypass Valve SFV-26005 (4)

E-203 Sh. 50A BLPB1-Close IM1A138A PB control & light LP_ Injection to SK-M-522 BLPB2-Open indication circuit Loop "A" Valve IM1A138B SF actuation circuit i

II-16 i.

.c

~_._-_,-._a

s TABLE II-1

' System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room HV-20001 (1,4)

E-203 Sh. 600 BLPB1-Open 1M1A171A PB control & light RCS to DH SK-M-522 BLPB2-Close indication circuit System Valve 1M1A171F High RC pressure ann. circuit (HV-20002) (1,4)

E-203 Sh. 60E BLPB1-Open IM18107A P8 control & light RCS to DH System SK-M-522 BLPB2-Close indication' circuit Valve 1M18107F High RC pressure ann circuit HV-20005 (1)

E-203 Sh. 118 BLPB1-Open 1M1A1340 PB control & light DH Pump Suction SK-M-522 BLPB2-Close indication circuit From RCS Valve HV-26513 (1,4)

E-203 Sh. SOF BLPB1-Open IM2D228A PB control circuit Core Flood Tank SK-M-522 BLPB2-Close Isolation Valve Valve Test PB 1M2D228D Valve status test circuit BLPB1 IM2D228E Light indication BLPB2 circuit HV-26514 (1,4)

E-203 Sh. 50F BLPB1-Open 1M2D229A PB control circuit-Core Flood Tank SK-M-522 BLPB2-Close Isolation Valve Valve Test PB IM2D2290 Valve stat. test circuit BLPB1 1M20229E Light indication BLPB2 circuit HV-26007 (1)

E-203 Sh. 53B BLPB1-Open IM1A139A PB control and light DHR to HP Injec-SK-M-522 BLPB2-Close indication circuit tion Pump MOV HV-26046 (1)

E-203 Sh. 53A BLPB1-Open 1M1A164A PB control and light DH Cross Tie SK-M-522 BLPB2-Close indication circuit Valve "A"-

(HV-26047).(1)

E-203 Sh. 53A BLPB1-Open IM18165A PB control and light DH Cross Tie SK-M-522 BLPB2-Close indication circuit Valve "B" II-17

r s

TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room RCS (REACTOR COOLANT SYSTEM)

PSV-21511 (1)

E-203 Sh. 65 Switch 86/ DSS 1R2C215VE Valve open/close and Pressurizer SK-M-520 Sh. 1 indication circuit Relief Valve IR2C215VF Valve low setpoint circuit 1R2C215VB Valve auto control circuit (HV-21505)

E-203 Sh. 580 BLPB1-Open IM18182A PB control and light Pressure Relief SK-M-520 Sh. 1 BLPB2-Close indication circuit Block Valee SFV-70001 (5)

E-203 Sh. 48C BLPB1-Open 1M1A157A PB control and Pressurizer SK-M-520 Sh. 1-BLPB2-Close indication circuit Liquid Sample IM1A1578 SF actuation circuit Injection Valve (SFV-70002) (5)

E-203 Sh. 84F BLPB1-Open 1RIC700A PB control and Pressurizer SK-M-520 Sh. 1 BLPB2-Close indication circuit Liquid Sample 1RIC700B SF actuation circuit Isolation Valve 1RIC700C Valve solenoid energizing circuit 1RIC7000 Valve indication ckt This valve is also in series with valve SFV-70001 & circuits having interface with Control Room already listed above SFV-70003 (5)

E-203 Sh. 48C BLPB1-Open IM1A158A PB control and SK-M-520 Sh. 1 BLPB2-Close indication circuit IM1A1588 SF actuation circuit (SFV-70002) (5)

This valve is also Pressurizer in series with valve Liquid Sample SFV-70001 & circuits Isolation Valve having interface with Control Room already listed above II-18

s TABLE 11-1 System / Equipment Schematic /P& ids Component-In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room FWS (FEEDWATER SYSTEM--AFW PUMP TRAIN)

P-319 (3)

SK-E-205 Sh. 1 Ammeter IP1A06A Ammeter circuit Aux Fdwtr Pump SK-M-532 1 PIA 06D Pump start (Motor-Driven) signal circuit BLPB2-Start IP1A06J PB control & light BLPB3-Stop indication circuit BLPB1-Auto 1 PIA 06K Pump auto start PB control & light indication circuit BLPB1-Start IPA 106R PB control &

BLPB2-Stop indication circuit IP1A06S SF actuation circuit SFV-20578 (2)

SK-E-203 Sh. 50C BLPB1-Close IM1A122B PB control & light AFW Control Valve SK-M-532 BLPB2-Open indication circuit By-pass 1M1A122C SF actuation circuit SFV-20577 (1)

SK-E-203 Sh. 50C BLPB1-Close 1M1B160F PB control and light AFW Control Valve SK-M-532 indication circuit By-pass BLPB2-Open IM18160G SF actuation circuit HV-31827 (2)

SK-E-205 Sh. 20F BLPB1-Open 1M1A108A PB control & light AFW Cross Tie SK-M-532 BLPB2-Close indication circuit Isolation MOV (HV-31826) (1)

SK-E-205 Sh. 20F BLPB1-Open 1M1B159A PB control & light AFW Cross Tie SK-M-532 BLPB2-Close indication circuit Isolation MOV FV-20528 (1)'

E-205 Sh. 29 BLPB1-Auto II1F205AB PB control and light AFW Control Valve SK-M-532 BLPB2-Open indication circuit 101A01A Control cabinet H4SDAS powr.r circuit FV-20527 (1)

E-205 Sh. 29A BLPT1-Auto II1F205BB Valve actuation and AFW Control SK-M-532 BLPB2-Open indication circuit Valve II1F205BF PB control and light indication circuit PV-20571A (2,1)

E-342 Sh. 12 & 4 II200165B Modulated signal from PV-205718 (2,1)

SK-M-530 ICS cabinet H4IC to PV-20571C (2,1) signal envtr PY-20571 Atmospheric Steam II2U1016C Valve control circuit Dump SGE-205A ICS cabinet H4IC II-19

TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram-Control Room Control Room PV-20562A (2,1)

E-342 Sh. 12 & 14 II201061C Valve control' circuit PV-205628 (2,1)

SK-M-530 to ICS cabinet H4IC PV-20562C (2,1)

II2U0165A Modulated' signal from Atmospheric Stm ICS cabinet H4IC to Dump SG E-2058 signal cnytr PY-20562 PV-20561 (2,1)

E-342 Sh. 12 & 14 II201062B Modulated signal from PV-20563 (2,1)

SK-M-530 ICS cabinet H4IC to Condenser Dump signal converter Valves SGE-205A PY-20561/PY-20563 II2U1061C Valve control circuit to ICS cabinet H4IC PV-20564 (2,1)

E-342 Sh. 12 & 14 II2U1061C Valve control circuit PV-20566 (2,1)

SK-M-530 to ICS cabinet H4IC Condenser Duinp II2010620 Modulated signal from Valves SGE-205B ICS cabinet H4IC to signal converter PY-20564/PY20566 TV1 (1)

E-201 Sh. 18 PB-Trip 1T2T10A Turbine trip seal-in 4 -

Turbine Throttle seal-in reset on reactor trip ckt Valve-1 IT2T10B Turbine trip on reactor trip valve actuation circuit PB-T1 IT2T10C Throttle valve-1 actuation circuit IT2T10J Turbine trip on low.

E-H oil pressure 102E30A Valve power supply circuit TV2 (1)

E-201 Sh. 18 PB-Trip IT2T10A Turbine trip seal-in Turbine Throttle seal-in reset on reactor trip ckt Valve-2 1T2T10B Turbine trip on reactor trip valve actuation circuit E-201 Sh. 19 PB-T2 1T2T10D Throttle valve-2 actuation circuit 1T2T10J Turbine trip on low E-H oil pressure.

II-20

~

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TABLE II-1 System / Equipment.

Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room TV-3 (1)

E-201 Sh. 18 PB-Trip 1T2T10A Turbine trip seal-in Turbine Throttle seal-in reset on reactor trip ckt Valve-3 1T2T10B Turbine trip on reactor trip valve actuation circuit PB-T3 IT2T10C Throttle valve-3 actuation circuit IT2T10J Turbine trip on low E-H oil pressure TV-4 (1)

E-201 Sh. 18 PB-Trip IT2T10A Turbine trip seal-in Turbine Throttle seal-in reset on reactor trip ckt Valve-4 1T2T10B Turbine trip on reactor trip valve actuation circuit E-201 Sh. 19 PB-T4 1T2T10D Throttle valve-4 actuation circuit IT2T10J Turbine trip on low E-H oil pressure GV1 (1)

E-201 Sh. 18 PB-Trip IT2T10A Turbine trip seal-in Turbine Governor seal-in reset on reactor trip ckt Valve-1 IT2T10B Turbine trip on reactor trip valve actuation circuit 1T2T10J Turbine trip on low E-H oil pressure ekt PB-G1 IT2T10C Governor valve-1 actuation circuit GV2 (1)

E-201 Sh. 18~

PB-Trip IT2T10A Turbine trip seal-in Turbine Governor seal-in reset on reactor trip ckt Valve-2 IT2T10B Turbine trip on reactor trip valve actuation circuit 1T2T10J Turbine trip on low E-H oil pressure ckt.

E-201 Sh. 19 PB-G2 IT2T100 Governor valve-2 actuation circuit II-21

TABLE II-1 System / Equipment Schematic /P& ids

' Component In Circuit in Function of Circuit or LOOP Oiagram Control Room Control Room GV3 (1)

E-201 Sh. 18 PB-Trip IT2T10A Turbine trip seal-in Turbine Governor seal-in reset on reactor trip ckt Valve-3 IT2T108 Turbine trip on reactor trip valve actuation circuit 1T2T10J Turbine trip on low E-H oil pressure ekt PB-G3 IT2T10C Governor valve-3 actuation circuit GV4.(1)

E-201 Sh. 18 PB-Trip IT2T10A Turbine trip seal-in Turbine Governor seal-in reset on reactor trip ckt Valve-4 1T2T10B Turbine trip on reactor trip valve actuation circuit 1T2T10J Turbine trip on low E-H oil pressure ckt PB-G4 1T2T10D Governor valve-4 actuation circuit HV-20560 (1)

E-205 Sh. 20A BLPB1-Open IM1A160A Valve open/close and Main steam to FP SK-M-530 BLPB2-Close indication circuit Turbine Header HV-20565 (1, 16)

E-205 Sh. 20A BLPB1-Open 1M18136A Valve open/close and Main steam to FP SK-M-530 BLPB2-Close indication circuit Turbine Header MOV HV-20569 (1)

E-205 Sh. 20C BLPB1-Open IM1A161A Valve open/close and Steam to Aux FP SK-M-530 BLPB2-Close indication circuit Turbine Header MOV HV-20596 (1, 16)

E-205 Sh. 20C BLPB1-Open IM18137A Valve open/close and Steam to Aux FP SK-M-530 BLPB2-Close indication circuit Turbine MOV HV-20597 (1)

E-205 Sh. 20E BLPB1-Open 1M1A162A Valve open/close and Main steam to SK-M-530 BLPB2-Close indication circuit Re-heater MOV HV-20598 (1, 16)

E-205 Sh. 20E BLPB1-Open IM18138A Valve open/close and Main steam to SK-M-530 BLPB2-Close indication circuit Re-heater MOV II-22

TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit in Function of Circuit or LOOP Diagram Control Room Control Room HV-32243 (1, 16)

E-205 Sh. 30 BLPB1-Open 1M18154A Valve open/close and Pegging Steam to SK-M-530 BLPB2-Close indication circuit 2nf & 4th Htrs.

HV-20611 (1, 16)

E-205 Sh. 30 BLPB1-Open 1M18173A Valve open/close and Steam Gen "A" SK-M-532 BLPB2-Close indication circuit and "B" Blowdown Isolation Valve NRW (NUCLEAR WATER SYSTEM)

P-472A (3)

SK-E-203 Sh. 42 Ammeter IP1A07A Ammeter circuit NS Raw Water SK-M-544 Pump "A" BLPB1-Start IP1A078 PB control & light BLPB2-Stop indication circuit 1P1A07C SF actuation circuit 1

NSW (NUCLEAR SERVICE WATER SYSTEM)

P-482A (6)

E-203 Sh. 43 BLPB1-Start 1N1A18A PB control & light NS Cooling Water SK-M-544 BLPB2-Stop indication circuit Pump "A" 1N1A18C SF actuation circuit SFV-26017 (1)

E-203 Sh. 50 BLPB2-Open IM1A140A PB control & light NS Cooling Water SK-M-544 BLPB1-Close indication circuit to DH Cooler 260A 1M1A140C SF actuation circuit SFV-26019 (1)

E-203 Sh. 50B BLPB2-Open IM1A141A PB control & light NS Cooling Water SK-M-544 BLPB1-Close indication circuit to DH Cooler 260A 1M1A141C SF actuation circuit Outlet Valve SFV-50005 (1)

E-203 Sh. 50J BLPB1-Close IM1A147A PB control & light C@oling Water to SK-M-544 BLPB2-Open indication circuit R. B. Emergency 1M1A1478 SF actuation circuit Cing. Unit A-500A SFV-50009 (1)

E-203 Sh. 50K BLPB1-Close IM1A149A PB control & light C. W. to RB Emerg SK-M-544 BLPB2-Open indication circuit Cing. Unit A-500A 1M1A149B SF actuation circuit SFV-50007 (1)

E-203 Sh. 50J BLPB1-Close 1M1A148A PB control & light Cleaning Water to SK-M-544 BLPB2-Open indication circuit R.B. Emerg. Cing.

1M1A148B SF actuation circuit Unit A-500C II-23

TABLE 11-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room SFV-50011 (1)

E-203 Sh. 50K BLPB1-Close 1M1A150A PB control & light Cleaning Water to SK-M-544 BLPB2-Open indication circuit R.B. Emerg. C1ng.

1M1A150B SF actuation circuit Unit A-500C EGS (EMERGENCY GENERATING SYSTEM)

H20GA SK-E-87 Sh. 1 BLPB1-Stop 1GlQ886AC Shutdown circuit Diesel Generator SK-E-87 Sh. 4 BLPB2-Start 1GlQ886AA PB start control Control Panel SK-M-552 circuit BLPB5-Raise 1GlQ886CK PB control circuit BLPB6-Lower for volt adjustment BLPB4-Lower 1GlQ886CR PB governor BLPB3-Raise control circuit BLPB2-Start IGlQ886AW Manual start BLPB1-Stop stop of engine circuit 1GlQ886AU Shutdown circuit 1GlQ886AV Manual initiating contact from CR to start diesel engine 1GlQ886AX SF initiation circuit to start diesel engine H20EA SK-E-87 Sh. 1 G & W lights 1GlQ886A0 Diesel running Diesel Engine E-208 Sh. 20 status circuit Control Panel SK-M-552 1P1A00F CO2 discharge in 0/G room control circuit P-888A (12)

SK-E-204 Sh. 11A IM1A113C CO2 Trip Block Diesel Fuel Oil SK-M-552 Contact for P-888A Transfer Pump in H4SDAS cabinet P-8888 E-204 Sh. 118 1M1A1140 CO2 Trip Block Diesel Fuel Oil SK-M-582 Contact for P-888B Transfer Pump in H4SDAS Cabinet HVS (HEATING VENTILATING AND AIR CONDITIONING SYSTEM)

A-544A (6)

E-204 Sh. 8 1NIA13G SF initiated trip D/G Room Exhaust SK-M-552 block contact in Fan H4SDA5 Cab.

11-24

TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room A-544B (6)

E-204 Sh. 8A IN1A17G SF initiated trip D/G Room Supply SK-M-552 block contact in Fan H4SDA5 Cab.

A-500A (6)

E-203 Sh. 6 BLPB1-Start IN1A10A PB control & light RB Emerg. Clr SK-M-544 BLPB2-Stop induction circuit IN1A10C SF actuation circuit A-500C (6)

E-203 Sh. 6 BLPB1-Start INIA 14A PB control & light RB Emerg. Clr SK-M-544 BLPB2-Stop induction circuit INIA 14C SF actuation circuit EDS (ELECTRICAL DISTRIBUTION SYS)

S4A08 (3)

SK-E-204 Sh. 1 WH, TD/W 191A08B PT metering circuit 4160 NS Bus PS, TD/ VAR D/G Supply Brkr V

1 PIA 08V Voltmeter circuit WH, TD/W 1 PIA 08C Metering circuit TD/ VAR WM 1P1A08T Metering circuit VAR 1P1A08U Metering circuit IP1A08Q SFA breaker trip clocking circuit 1P1A08R Breaker trip blocking contact circuit from H4SDAS A

1P1A08S Ammeter circuit BLPB1-Close IP1A08W PB control &

BLPB2-Trip indication circuit S4A09 (3)

SK-E-208 Sh. 10 1P1A09F Breaker trip STN Service olocking contact XFMR 4160V Supply in SF Cabinet H4SDAS Breaker Ammeter IP1A09G Ammeter circuit BLPB1-Close 1P1A90H PB control &

BLPB2-Trip indication circuit S3A05 (6)

SK-E-208 Sh. 13A IN1A05C Breaker trip 480V Bus S3A blocking contact Supply Breaker in SF Cabinet H4SDAS INIA 05D SF actuation signal contact in SF Cabinet H4SDAS for closing breaker on SF actuation l

11-25

TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room BLPB1-Close IN1A05E PB control & light BLPB2-Trip indication circuit Voltmeter IN1A05F Voltmeter PT circuit SELECTED INSTRUMENTATION PER SK-J-500 OTSG "A" Level Wide Range (15)

LT-20501 SK-ICR-1 Indicator 1R2Y205KB See SK-ICR-1 LT-20501A (13)

SK-ISD-1 Indicator 1Y3X205A2 See SK-ISD-1 OTSG "B" Level Wide Range (15)

LT-20502 SK-ICR-2 Indicator 1R2Y205KA See SK-ICR-2 LT-20502A (13)

SK-ISD-2 Indicator 1Y3X205B2 See SK-ISD-2 Pressurizer Level (15)

LT-21503A SK-ICR-5 Recorder 1R2C21503 See SK-ICR-5 LT-21503B (13)

SK-ISD-3 Recorder 1R2C215F2 See SK-ISO-3 LT-21503C SK-ICR-6 Record / Indicator 1R2C215C3 See SK-ICR-6 LT-215030 (13)

SK-ISD-4 Indicator 1Y3X215A2 See SK-ISD-4 Make-Up Tank Level (15)

LT-23502A SK-ICR-7 Recorder 1R2C235L3 See SK-ICR-7 LT-23502B SK-ICR-7 Recorder 1R2C235L2 See SK-ICR-7 LT-23502C (13)

SK-ISD-5 Indicator 1Y3X235A2 See SK-ISD-5 l

OTSG "A" Pressure l

Wide Range (15)

PT-20519A SK-ICR-8 Indicator 1R2Y205PM See SK-ICR-8 PT-20519B SK-ICR-8 Indicator 1R2Y205PE See SK-ICR-8 PT-20543A SK-ICR-11 Recorder 1R2Y205PF See SK-ICR-11 PT-20543C (13)

SK-ISD-6 Indicator 1Y3X205C2 See SK-ISD-6 II-26 k

1 TABLE II-1 System / Equipment Schematic /P& ids Component In Circuit In Function of Circuit or LOOP Diagram Control Room Control Room OTSG "B" Pressure Wide Range (15)

PT-20520A SK-ICR-9 Indicator 1R2Y205PD See SK-ICR-9 PT-20520B SK-ICR-9 Indicator 1R2Y205PL See SK-ICR-9 PT-205438 SK-ICR-11 Recorder 1R2Y205PC See SK-ICR-11 PT-205430 (13)

SK-ISD-7 Indicator 1Y3X205D2 See SK-ISO-7 RCS Pressure Wide Range (9,15)

PT-21042 SK-ICR-12 Indicator 1RISO481C See SK-ICR-12 PT-21043 SK-ICR-12 Indicator 1RISO4 CIA See SK-ICR-12 PT-21092 SK-ICR-13 Recorder 1RISO4A1C See SK-ICR-13 PT-21099 SK-ICR-13 Indicator 1R1SO486A See SK-ISD-13 RCS Temperature Cold Leg "A" (15)

TE-21023A SK-ICR-14 Indicator 1R2C210A3 See SK-ICR-14 TE-210238 SK-ICR-14 Indicator 1R2C210M1 See SK-ICR-14 TE-21025C (13)

SK-ISD-11 Indicator 1Y3X210A2 See SK-ISD-11 RCS Temperature Cold Leg "B" (15)

TE-21024A SK-ICR-15 Indicator 1R2C210B3 See SK-ICR-15 TE-21024B SK-ICR-15 Indicator 1R2C210K1 See SK-ICR-15 TE-21024C (13)

SK-ISO-10 Indicator 1Y3X21082 See SK-ISD-10 RCS Temperature Hot Leg "A" (10, 15)

TE-21029 SK-ICR-16 Indicator 1RIPDTIC See SK-ICR-16 TE-21033 SK-ICR-16 Indicator 1RIPCTIC See SK-ICR-16 RCS Temperature Hot Leg "B" (11, 15)

TE-21030 SK-ICR-16 Indicator 1R2PBT1C See SK-ICR-16 TE-21034' SK-ICR-16 Indicator 1RIPATIC See SK-ICR-16 II-27

r-

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TABLE Ih1

'i'

's i

s System / Equipment Schematic /P& ids Component In Circuit In-Function of Circuit or LOOP Diagram Control Room Control Room t-Source Range Indication (15)

XE-00005 (8)

SK-ICR-10 Indicator 1R2IR1HA See SK-ICR-10 1R2IR1LA t CR2IRISA XE-00006' SK-ICR-10 Indicator 1R2IR2HA See SK-ICR-10 1R2IR2LA 1R2IR2,SA

.N w

4 II-28

4 r

TABLE II-1 NOTES FOR TABLE II-1 (1) Manual operator action required.

(2) Alternate control available at the emergency shutdown panel H2SD in 4160V West Switchgear Room.

(3) Alternate controls available at the Switchgear S4A in 4160V West Switchgear Room.

(4)

Breaker is racked out during normal operations.

(5)

System is isolated using other valves.

-(6) Alternate controls available at Switchgear S3A in 480V West Switchgear Room.

(7) Alternate control is available at MCC S2A1 in 480V West Switchgear Room.

(8)

Portable source range indication monitor is provided.

(9)

RCS wide range pressure (PT-21050 and PT-21051) indication is available at emergency shutdown panel H2SD.

(10) RCS hot leg "A" temperature (TE-21031C) indication is available at Emergency Shutdown Panel H2SD.

(11) RCS hot leg "B" temperature (TE-21032C) indication is available at Emergency Shutdown Panel H2SD.

(12) Alternate controls available at 0/G control panel H20GA in 0/G "A"

Room.

(13) Alternate indication available at Emergency Shutdown Panel H2SD.

(14) This table lists channel "A" equipment only except where channel "B" equipment is also required to be operated.

(15) Only one indication for the listed function is required.

(16) Equipment it cf channel "B" and required for main steam line isolation.

S 11-29 t

TABLE II-2 NEW COMPONENTS TO BE ADDED TO PROVIDE ALTERNATE SHUTDOWN CAPABILITY EQUIPMENT AFFECTED COMP 0NENTS TO BE ADDED HPI Pump P-238A Isolation switch Make-Up Pump P-236 Isolation switch HPI Pump A Lube Oil Pump P-238A LOP Isolation switch (already exists)

HPILoopAInjectionhalveSFV-23811 Isolation switch Control switch Indicating lights Make-Up Tank Isolation Valve SFV-23508 Isolation switch Control switch Indicating lights HPI/DH Pump A Isolation switch Suction from BWST SFV-25003 Control switch Indicating lights Nuclear Service Raw Water Pump P-472A Isolation switch l

l Aux. Feedwater Pump P-319 Isolation switch l

Aux. Feedwater Cross Tie Isolation Isolation switch MOV HV-31827 Control switch Indicating lights Aux. Feedwater Bypass Valve SFV-20578 Isolation switch Control switch Indicating lights Diesel Generator GEp. Controls Isolation switch D/G GEA Breaker S4 08 Isolation switch (already exists)

Station Service XFMR Breaker S4A09 Isolation rwitch 480 V Switchgear S3A Bus Isolation switch Supply Breaker S3A05 Decay Heat Removal Pump P-261A Isolation switch Diesel Generator Fuel Oil Transfer Isolation switch Pump P-888A RCP Seal Water Control Valve PV-23606 Hand wheel for local control 11-30 l

e TABLE II-2 EQUIPMENT AFFECTED COMPONENTS TO BE ADDED Steam Generator Wide Range Level LT-20501A Signal isolator LT-20502A Signal isolator Steam Generator Wide Range Pressure PT-20543C Signal isolator PT-205430 Signal isolator RCS Cold Leg Wide Range Temperature TE-21025C Signal isolator TE-21024C Signal isolator

. Pressurizer Level LT-21503D Signal isolator LT-21503B New loop Make-Up Tank Level LT-23502C Signal isolator RCS Hot Leg Wide Range Temperature Relocate TT and TY from NNI Cabinet TE-21031C to West Switchgear Room TE-21032C Signal isolator RCS Wide Range Pressure PT-21051 New Loop PT-21050 New Loop Source Range Neutron Flux Portable Indicator on Penetration H7RP 67 XE-00005 FI-23606A Local indicator for total RCP seal flow l

l l

l l

i II-31

4 h

SECTION III

RESPONSE

TO SAFE SHUTDOWN CAPABILITY - ASSOCIATED CIRCUITS ATTACHMENT 2 TO CLARIFICATION TO' GENERIC ' LETTER 81-12 The District has used the fire area approach in addressing associated circuits.

Our response for the Control Room alternative shutdown method is listed below:

LNRC Request la.

Provide a table that lists all the power. cables in the fire _ area that -

connect to the same power supply of the alternative or dedicated

. shutdown method, and-the function of each power cable listed (i.e.

power for RHR pump).

DISTRICT RESPONSE Table III-l provides the information requested.

4 NRC RE00EST

!j Lib.

Provide a table that lists all the cables in the fire area that were considered for possible spurious operation which would adversely affect shutdown and the function of each cable listed.

DISTRICT RESPONSE Table III-2'provides the infobmation requested.

g NRC REQUEST

-l c.

Provide a table that lists.all the cablei in the fire area that share a common enclosure wi,th circuits of the alternative or, dedicated. shutdown

. systems and the function,ofceach cable listed.;

' DISTRICT RESPONSE

^

t ;

l

~The guidance provided in Attachment 2 to the clarification letter for Generic Letter 181-12 indicates' that common enclosure associated circuits.of concern'are those that have "a common.

L enclosure with ~the shutdown cables (redundant and alternative) and:

i f

III-1

..~...

1.

Are not electrically isolated by acceptable isolation-

. devices and 2.

Will allow propagation of the fire into the common

. enclosure".

The District has analyzed all circuits in the plant 'to determine if it is possible to have a common enclosure associated circuit of concern. The results of the analysis indicate that after

. making modifications to the routing of only two circuits in the plant, there will not be any common enclosure circuits that satisfy the definition quoted above. -The methodology used divided all the circuits in the plant into different categories

-and then verified that either:

;. ~.(

1.

They are adequately' protected by exiting circuit breakers or fuses as determined by analysis, or c

,e r

2.

if they are not'adequatelyiprotected, that the cables run-in dedicated bonduits to limit. propagation of fire, or i_

7

.o n

'the circuits do'not ha'versufficient energy to start a fire.

3.

~%

NRC REQUEST g

.o ld. Show that-fire-induced failures '(hot' shorts, open circuits or shorts to ground)'of each of theicables listed in a;'b, and c will not prevent r

operation or cause maloperation ofsthe alternative or dedicated shutdown method.

DISTRICT RESPONSE ^

?

A.

The District has verified that 'all common power supply source case of associated circuits have:

1.

Interrupting t'ime _overcurrent trip characteristics p

that cause the interrupting device to interrupt the fault current prior to initiation of a trip.of any upsteam device which will cause a' loss of the common l

power source.

i-2.

Power source that has the necessary fault current for l

{-

sufficient time to ensure the proper coordination without loss of function of the shutdown loads.

B.

For circuits of equipment whose spurious operation would affect'the capability to safely shutdown, the District will-electrically isolate this equipment by opening their' power supply breakers and manually aligning the' valves in the required position once the Control Room is evacuated.

Sufficient instrumentation exists at the shutdown panel to l

detect spurious operation.

III-2

7 C.

The District'has identified two common enclosure associated circuits of concern that can propagate the fire outside of the fire area or do not have electrical protection. After routing these circuits separately in rigid steel conduits, there will not be any common enclosure circuits of concern.

The above work has been done in the 1985 outage.

NRC= REQUEST le. For cable listed in a, b, and c where new electrical isolation has been provided or modification to existing electrical isolation has been made, provide detailed electrical-schematic drawings that show how each

_ cable is isolated from the fire area.

DISTRICT RESPONSE The circuits identified in Table III-1 have been analyzed and are found to be protected with properly coordinated breakers. No new

-electrical isolation devices or mdofiications to existing isolation devices are required.

The isolation of the cables identified in "lb" (Table III-2) will be accomplished by opening existing supply breakers or disconnect switches located outside the Control Room. This method will completely de-energize the control circuit preventing further spurious operation. To accomplish-this, no new electrical 4'

isolation devices or modifications 1to existing electrical isolation equipment are required.

~

? ',.

The District has identified two' cables'in '"Ic" that were re-routed in separated: rigid steel conduits in the 1985 outage.

,7

~

r g

i 2

S III-3

TABLE III-1 POWER CIRCUITS IN THE CONTROL ROOM THAT HAVE THE SAME POWER SOURCE AS ALTERNATIVE ~ SHUTDOWN EUQIPMENT g

POWER CIRCUIT-EQUIPMENT SUPPLIED' POWER SOURCE 111A02A Safety Features Cab.

L.

120VAC Panel S1A H2SFA 1

,t 111A09A-1 SF Analog! Cab'.iH4SAA1 120VAC Panel S1A 111A10A' RPS Cab. H4PRIA ~

120VAC Panel S1A 1 ' ff

' 111A11B SF Digital. Cab.'H4SDA~

~

120VAC-Panel S1A

-111A12A-Under Power Panel H4UP1 120VAC Panel S1A q

- 101A01A

'SF Digital-Cabi H4SDA5 125VDC Panel SOA

.101A028 Under' Power Panel H4UP1 125VDC Panel SOA 101 A03A

-SF Digital Cab. H4SDA5 125VDC Panel SOA 111C07B ICS Cab. H41C 120VAC Panel SIC 111C09A.

SF Analog. Cab. H4 SAC 3

-120VAC Panel SIC 111C10A RPS' Cab. H4PRIC 120VAC Panel SIC 111C12A RCP Under Power. Panel H4UP 120VAC Panel sic

- 101CO2A Reactor Under Power 125VDC Panel SOC Panel H4UP3 101C01A' Control Room Lighting 125VDC Panel SOC Panel HBL 120VAC and 125VDC ALTERNATIVE SHUTDOWN POWER SUPPLY SOURCES:

S1A Supplying power for instruments SIC Supplying power for instrumednts SOA Supplying power for switchgear control SOC For SFV-23811 i

III-4

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--.n..

TABLE III-2 CABLES CONSIDERED FOR SPURIOUS OPERATIONS System / Equipment Schematic /P& ids Cable Function or LOOP Oiagram PLS & SIM (PURIFICATION LETDOWN SYSTEM AND SEAL INJECTION MAKE-UP SYSTEM) SYSTEM SFV-23809 E-203 Sh. 50E 101C05C Valve open/close indication circuit (RCS LOOP "A" SK-M-521 101C05D SF actuation circuit j

HPI Valve) 1DIC05E SF actuation circuit 101C05F SF actuation circuit SFV-23810 E-203 Sh. 50F 1D1003C Valve open/close indication circuit (RCS LOOP "B" SK-M-521 1D1003D SF actuation circuit HPI Valve) 101003E SF actuation circuit ID1003F SF actuation circuit SFV-23811 SK-E203 Sh. 50G 101C08C Valve open/close indication circuit (RCS LOOP "A" SK-M-521 1DIC08D SF actuation circuit HPI Valve) 101C08E SF actuation circuit 101C08F SF actuation circuit 1

SFV-23812 E203 Sh. 50H 101005C Valve open/close indication circuit (RCS LOOP "B" SK-M-521 1D1005D SF actuation circuit HPI Valve) 101005E SF actuation circuit ID1005F SF actuation circuit LV-21503 SK-M-521 1R2C215XA Valve actuation circuit (Make-Up Control Valve)

PV-23606 SK-M-521 1R2C236X1 Valve solenoid actuation circuit (Seal Injection Flow Control Valve)

SFV-23645 E-203 Sh. 52B IM1A121A Valve open/close indication circuit (HPI/MU Recire.

SM-M-521 IM1A1210 SF actuation circuit Valve)

SFV-23646 E-203 Sh. 52B 1M18141A Valve open/close indication circuit (HPI/MU Recirc.

SK-M-521 IM1B1418 SF actuation circuit Valve)

SFV-23508 SK-E-203 Sh. 97 IM1A172A Valve open/close indication circuit

~

(MU Tank Isol.

SK-M-521 IM1A1720 SF actuation circuit Valve) 1 j

l III-5

'I

r TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LO0p Diagram SFV-22009 E-203 Sh. 62 1RIC220DA Valve open/close indication circuit (RCS Letdown SK-M-521 1RIC220DB Valve open/close indication circuit Isol. Valve) 1RIC220DC SF actuation circuit 1R1C220DD SF actuation circuit SFV-22023 E-203 Sh. 48 1M1A133A Valve open/close indication circuit (RCS Letdown SK-M-521 1M1A133D SF actuation circuit Isol.-Valve)

FV-23004B E-203 Sh. 61 1M2D430A Valve actuation circuit 3-Way Letdown SK-M-521 1M204300 Valve actuation circuit Bleed Valve HV-23504 E-203 Sh. 75 1RIC235CH Valve open/close indication circuit (MU Tank Vent SK-M-521 1RIC235CD Valve actuation circuit Valve)

HV-23004 E-203 Sh. 61 1M20430A Valve open/close indication circuit (Letdown / Bleed SK-M-521 IM20430B Valve control circuit Valve)

P-236 (MU Pump)

SK-E-203 Sh. 2 1P1A02C Ammeter indication circuit SK-M-521 1P1A02E Pump start /stop indication circuit 1 PIA 02H SF actuation circuit IP1808A Ammeter indication circuit IP1808B Ammeter indication circuit 1P1808D Pump start /stop indication circuit IP1808E SF actuation circuit IP1808J Pump start /stop indication circuit P-2388 (HPI Pump) SK-E203 Sh.4 1P1807A Ammeter indication circuit-SK-M-521 1PAB07B Ammeter indication circuit IP1807C Pump start /stop indication circuit 1P1807E SF actuation circuit IP1807K Pump start /stop indication circuit 1

SFV-25004 E-203 Sh. 68A iM1B146A Valve open/close indication circuit (BWST Outlet SK-M-522 1M1B146B SF actuation circuit Valve) 1M1B1460 Light indication circuit SFV-25003 SK-E203 Sh. 68 1M1A137A Valve open/close indication circuit (BWST Outlet SK-M-522 1M1A1370 Light indication circuit Valve)

IM1A137E SF actuation circuit SFV-23616 E-203 Sh. 54 1M18143G RCP seal control circuit (RCP Seal Water SK-M-521 1M18143H RCP interlock circuit Supply Valve)

IM18143A Valve open/close indication circuit III-6

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram FV-24019 E-203 Sh. 78 1M2D218A Valve open/close indication circuit (RCP Seal Return SK-M-521 1M20218C RCP seal flow signal circuit Isolation Valve)

FV-24020 E-203 Sh. 78 1M2C436A Valve open/close indication circuit (RCP Seal Return SK-M-521 1M2C436C RCP seal flow sigeal circuit Isolation Valve)

FV-24021 E-203 Sh. 78 1M20327A Valve open/close indication circuit (RCP Seal Return SK-M-521 1M20327C RCP seal flow signal circuit Isolation Valve)

FV-24022 E-203 Sh. 78 1M20431A Valve open/close indication circuit (RCP Seal Return SK-M-521 1M20431C RCP seal flow signal circuit Isolation Valve)

FV-24004 E-203 Sh. 69 1M1A136B Valve open/close indication circuit (RCP Seal Water SK-M-521 1M1A136C SF actuation circuit Return Valve)

SFV-24013 E-203 Sh. 63 1RIC240A Valve open/close indication circuit (RCP Seal Water SK-M-521 1RIC240B SF actuation circuit.

Return Valve) 1RIC240I SF actuation circuit 1R10240G SF actuation circuit 1RIC240H SF actuation circuit 1RIC2400 SF actuation circuit 1RIC240C SF actuation circuit SFV-23604 E-203 Sh. 49 1DIC03D SF actuation circuit (RCS MU Isola-SK-M-521 101C03E SF actuation circuit tion MOV) 101C03F SF actuation circuit 101C03C Valve open/close indication circuit HV-23801 E-293 Sh. 60C 1M18179A Valve open/close indication circuit (ECCS Long Term SK-M-521 1M18179D Valve indication power' circuit Cooling MOV)

HV-23802 E-203 Sh. 60B IM18180A Open/close. indication circuit (ECCS Long Term SK-M-521 Cooling MOV)

III-7

TABLE'III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram DHS & CFS (DECAY HEAT SYSTEM AND CORE FLOOD SYSTEM)

SFV-26005 E-203 Sh. 50A 1M1A138A Valve open/close indication circuit (DH System SK-M-522 1M1A138B SF actuation circuit Isolation Valve)

SFV-26006 E-203 Sh. 50A' 1M18147A Valve open/close indication circuit (DH System SK-M-522 1M18147B SF actuation circuit Isolation. Valve)

HV-26037 E-203 Sh. 80 1M1A107A-Valve open/close indication circuit (DH Cooler Bypass Valve)..

SK-M-522 HV-26038 E-203 Sh. 80 1M18142A Valve open/close indication circuit (DH Cooler SK-M-522 Bypass Valve)

HV-26011 E-203 Sh. 58 1M20225A Valve open/close indication circuit (LP Spray SK-M-522 Isolation' Valve)

SFV-26039 E-203 Sh. 81 IM1A1068 Valve open/close indication circuit (DH Clr.

SK-M-522 1M1A106C SF actuation circuit Dischrg Valve) i SFV-26040 E-203 Sh. 81A.

1M18163B Valve open/close indication circuit (DH Cir.

SK-M-522 1M1B163C SF actuation circuit Dischrg Valve)

IM1B163F Valve'open/close indication circuit HV-20005 E-203 Sh. 118 1M1A134D Valve open/close indication circuit (DH System SK-M-522 l

Isolation Valve) i-i HV-20006 E-203 Sh. 119 1M181440 Valve open/close indication circuit j

(DH System.

SK-M-522 Isolation Valve)

HV-26007 E-203 Sh. 53B 1M1A139A Valve open/close indication circuit (HPI Cross SK-M-522 l

Connect Valve) i HV-26008 E-203 Sh. 53B 1M18148A Valve open/close indication circuit (HPI Cross SK-M-522 Connect Valve) i III-8

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram.

HV-26046 E-203 Sh. 53A 1M1A164A Valve open/close indication circuit (DH Cross SK-M-522 Connect Valve)

HV-26047 E-203 Sh. 53A 1M1B165A Valve open/close indication circuit (DH Cross SK-M-522 Connect Valve)

HV-26513 E-203 Sh. 50F 1M20228A Valve open/close indication circuit (CF Tank "A" SK-M-522 1M20228D Valve status test circuit To RCS) 1M2D228E Valve status indication circuit HV-26514 (CF E-203 Sh. 50F 1M2D229A Valve open/close indication circuit Tank "B" to RCS)

SK-M-522 HV-20003 (DH Pump E-203 Sh. 60A 1M1A179A Valve open/close indication circuit to Sump Valve)

SK-M-522 P-261A SK-E-203 Sh. 3 1 PIA 05B Pump start /stop indication circuit (DH Removal SK-M-522 1 PIA 05C SF actuation circuit Pump "A")

IP1A05A Ammeter circuit P-261B E-203 Sh. 3 1P1809B Pump start /stop indication circuit (DH Removal SK-M-522 1P1809C SF actuation circuit Pump "B")

IP1809A Ammeter circuit P-251 E-203 Sh. 17 1M2E101A Pump start /stop indication circuit (LPI HDR Warming SK-M-522 Pump)

RCS (REACTOR COOLANT SYSTEM)

HV-21505 E-203 Sh. 58D IM18182A Open/close indication circuit (Pressurizer SK-M-520 Sh. 1 Relief Stop Valve)

PSV-21511 E-203 Sh. 65 1R2C215VB RPS pressure signal circuit EMOV SK-M-520 Sh. I 1R2C215VE Control indication circuit HV-21516 E-203 Sh. 38 IM20212A Open/close indication circuit (Pressurizer SK-M-520 Sh. 1 Liquid Sample Valve)

III-9

r TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram SFV-70001'.

E-203 Sh. 48C 1M1A157A Open/close indication circuit (RC Sample Cir.

SK-M-520 Sh. 1 1M1A157B SF actuation circuit Isolation Valve)

SFV-70002 E-203 Sh. 48F 1RIC700A Open/close indication circuit (RC Sample Cir.

SK-M-520 Sh. 1 1RIC7008 SF actuation circuit Isolation Valve) 1RIC700C Valve energize circuit 1RIC7000 Valve indication circuit P-210A E-203 Sh. 1 1Q2A03B Ammeter circuit (RC Pump "A")

SK-M-520 Sh. I 1Q2A03C Reactor trip circuit 1Q2A03D Pump start /stop indication circuit 1Q2A03E Pump start block circuit 1Q2A03F Pump control circuit 1Q2A03J Pump control circuit 1Q2A03K Reactor trip circuit 1Q2A03L Reactor trip circuit P-210B E-203 Sh. 1A 1Q2803B Ammeter circuit (RC Pump "B")

SK-M-520 Sh. 2-1Q2803C Reactor trip circuit 1Q2803D Pump start /stop indication circuit 1Q2803E Pump start block circuit 1Q2803F Pump control circuit 1Q2803J Pump control circuit 1Q2B03K Reactor trip circuit 1Q2803L Reactor trip circuit P-210C E-203 Sh. 1B

~

1Q2A028 Ammeter circuit (RC Pump "C")

SK-M-520 Sh. 20 1Q2A02C Reactor trip circuit 1Q2A02D Pump start /stop indication circuit 1Q2A02E Pump start block circuit 1Q2A02F Pump control circuit 1Q2A02J Pump control circuit 1Q2A02K Reactor trip circuit 1Q2A02L Reactor trip circuit P-2100 E-203 Sh. 1C 1Q28028 Ammeter circuit (RC Pump "D")

SK-M-520 Sh. 1 1Q2802C Reactor trip circuit 1Q28020 Pump start /stop indication circuit 1Q2802E Pump start block circuit 1Q2802F Pump control circuit 1Q2B02J Pump control' circuit 1Q2802K Reactor trip circuit 1Q2802L Reactor trip circuit HV-21922 E-203 Sh. 58 1M2C326A Open/close indication circuit (Pressurizer SK-M-520 Sh. 1 Relief Tank Valve)

III-10

(;

~

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram HV-21908 E-203 Sh. 58 1M20216A Open/close indication circuit (Pressurizer SK-M-520 Sh. 1 Relief Tank Valve)

HV-21909 E-203 Sh. 58 1M20217A Open/close indication circuit (Pressurizer SK-M-520 Sh. 1 Relief Tank Valve)

V215L-13, 14, 15 E-203 Sh. 45C IM2A201B Pressurizer heater control circuit (Emergency Przr.

SK-M-520 Sh. 1 1M2A201C Pressurizer heater control circuit Heaters)

IM2A2010 Pressurizer heater control circuit V215L-16, 17, 18 E-203 Sh. 45C IM2A202A Pressurizer heater control circuit (Emergency Przr.

SK-M-520 Sh. 1 Heaters)

V215L-19, 20, 21 E-203 Sh. 45C 1M2A203A Pressurizer heater control circuit (Emergency Przr.

SK-M-520 Sh. 1 Heaters)

V215L-10, 11, 12 E-203 Sh. 46C 1M2B201B Pressurizer heater control circuit (Emergency Przr.

SK-M-520 Sh. 1 1M2B201C Pressurizer heater control circuit Heaters) 1M2B2010 Pressurizer heater control circuit V215L-13, 14, 15 E-203 Sh. 46C IM2B202A Pressurizer heater control circuit (Emergency Przr.

SK-M-520 Sh. 1 Heaters)

V215L-16, 17, 18 E-203 Sh. 46C IM28203A Pressurizer heater control circuit (Emergency Przr.

SK-M-520 Sh. 1 Heaters)

FWS (FEEDWATER SYSTEM--AFW PUMP TRAIN)

P-319 SK-E-205 Sh. 1 191A06A Ammeter circuit (Emergency FW SK-M-532 1P1A06D Pump start signal circuit Pump)

IP1A06J Pump stop signal circuit IP1A06K Pump auto start circuit IPIA06R Pump start /stop indication circuit IP1A06S SF actuation circuit III-11

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Oiagram P-318 SK-E-205 Sh. 27 1P1810A Ammeter circuit (Emergency FW SK-M-532 1PIB10H Pump start signal circuit Pump)

IP1810J Pump stop signal circuit IP1810K Pump indication circuit SFV-20577 E-203 Sh. 50C 1M18160F Valve open/close indication circuit (AFW Control SK-M-532 Valve Bypass)

SFV-20578 E-203 Sh. 50C 1M1A122B Valve open/close indication circuit (AFW Control SK-M-532 1M1A122C SF actuation circuit Valve Bypass)

SFV-20527 E-205 Sh. 29 II1F205B Valve actuation signal circuit (FW to OTSG SK-M-532 II1F205E Valve open/close indication circuit E205A)

SFV-20528 E-205 Sh. 29 lI1F205AA Valve open/close indication circuit (FW to OTSG SK-M-532 II1F205AB Valve actuation signal circuit E205B)

HV-31826 E-205 Sh. 26 1M1B159A Valve open/close indication circuit (AFW Cross-Tie SK-M-532 Isolation MOV)

HV-31827 E-205 Sh. 26 1M1A108A Valve open/close indication circuit (AFW Cross-Tie SK-M-532 Isolation MOV)

PV-20571A, B, C E-342 Sh. 12 & 4 II200165B ICS control circuit (Atmospheric SK-M-530 lI2U1061C ICS control circuit Dump Valves)

PV-20562A, B, C E-342 Sh. 12 & 4 II2U0165A ICS control circuit (Atmospheric SK-M-530 Dump Valves)

HV-20569 E-205 Sh. 20C 1M1A161C Open/close indication circuit (Steam to Emer-SK-M-530 gency FP Turbine)

HV-20596 E-205 Sh. 20C 1M18137C Open/close indication circuit (MS valve to SK-M-530 FP Turbine)

III-12 I

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Oiagram PV-20561 &

E-342 Sh. 12 & 4 II2U1062B ICS control circuit PV-20563 SK-M-530 II2U1061C ICS control circuit (Turbine Bypass Valves)

PV-20564 &

E-342 Sh. 12 & 4 II2U10620 ICS control circuit PV-20566 SK-M-530 (Turbine Bypass Valves)

HV-32243 E-205 Sh. 30 1M18154A Open/close indication circuit (Peg. Steam to SK-M-530 2nd & 4th Heater)

HV-20597 E-205 Sh. 20E IM1A162A Open/close indication circuit (MS to Reheater SK-M-530 MOV)

HV-20598 E-205 Sh. 20E IM18138A Open/close indication circuit (MS to Reheater SK-M-530 MOV)

TV1 (Turbine E-201 Sh. 18 1T2T10A Turbine trip seal-in on reactor Throttle Valve-1) trip circuit IT2T108 Turbine trip on reactor trip valve actuation circuit IT2T10C Throttle valve-1 actuation circuit 1T2T10J Turbine trip on low EH oil pressure 102E30A Valve power supply circuit TV2 (Turbine E-201 Sh. 18 1T2T10A Turbine trip seal-in on reactor Throttle Valve-2) trip circuit 1T2T108 Turbine trip on reactor trip valve actuation circuit 1T2T100 Throttle valve-2 actuation circuit IT2T10J Turbine trip on low EH oil pressure TV3 (Turbine E-201 Sh. 19 1T2T10A Turbine trip seal-in on reactor l

Throttle Valve-3) trip circuit 1T2T10B Turbine trip on reactor trip valve actuation circuit I

1T2T10C Throttle valve-3 actuation circuit 1T2T10J Turbine trip on low EH oil pressure l

4 III-13 t.

TABLE.III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram j

~

TV4 (Turbine E-201 Sh. 19 1T2T10A Turbine trip seal-in on reactor Throttle Valve-4) trip circuit-1T2T108 Turbine trip on reactor trip valve actuation circuit 1T2T108 Throttle valve-4 actuation circuit IT2T10J Turbine trip on low EH oil pressure NRW (NUCLEAR RAW WATER SYSTEM)

P-472A SK-E-203 Sh.-42 1P1A07A Ammeter circuit (NS Raw Water SK-M-544 1P1A078 Open/close indication circuit Pump "A")

IP1A07C SF actuation circuit P-4728 SK-E-203 Sh. 42 1P1806A Ammeter circuit-(NS Raw Water SK-M-544 IP18068 Open/close indication circuit Pump "B")

IP1806C SF actuation circuit NSW (NUCLEAR SERVICE WATER SYSTEM) m P-482A E-203 Sh. 43 1N1A18A Pump start /stop indication circuit 4

(NSCW Pump "A")

SK-M-544 1NIA18C SF actuation circuit

,r

^

P-482B E-203'Sh. 43 1N1818A Pump start /stop indication circuit (NSCW Pump "B")

SK-M-544 1N1818C SF actuation. circuit 1N1818E Ammeter circuit 2

SFV-50005 E-203 Sh. 50J IM1A147A Open/close indication circuit (RB Clr.-

SK-M-544 1M18147B SF actuation circuit Isolation Valve)

SFV-50006' E-203 Sh. 50L 1M18155A Open/close indication circuit (RB Clr.

SK-M-544 1M18155B SF actuation circuit l

I, solation Valve)

SFV-50007 E-203 Sh. 50J 1M1A148A Open/close indication circuit (RB Clr..

SK-M-544 1M1A1488 SF actuation circuit Isolation Valve)

SFV-50008 E-203 Sh. 50L 1M1B156A Open/close indication circuit (RB Cir.

SK-M-544 IM181568 SF actuation circuit Isolation Valve)

SFV-50009 E-203 Sh. 50K IM1A149A Open/close indication circuit (RB Clr.

SK-M-544 1M1A149B SF actuation circuit Isolation Valve)

III-14 i

i

,,_,..,,,d.

.y

,m._,,,_,

...-.wm,m

_.-,,r._-,,,w,,-.. men.,.,.,,,.pc.--w.,.

y

.--+,m-

,m,--

F TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram SFV-50010 E-203 Sh. SOM IM1B157A Open/close indication circuit (RB Clr.

SK-M-544 1M1B1578 SF actuation circuit Isolation Valve)

SFV-50011 E-203 Sh. 50K 1M1A150A Open/close indication circuit (RB Cir.

SK-M-544 IM1A150B SF actuation circuit Isolation Valve)

SFV-50012 E-203 Sh. 50M IM18158A Open/close indication circuit (RB Clr.

SK-M-544 1M18158B SF actuation circuit Isolation Valve)

SFV-26016 E-203 Sh. 50 1M1B149A Open/close indication circuit (DH Cir.

SK-M-544 1M18149C SF actuation circuit Isolation Valve)

SFV-26017 E-203 Sh. 50 1M1A140A Open/close indication circuit (DH Clr.

SK-M-544 1M1A140C SF actuation circuit Isolation Valve)

SFV-26018 E-203 Sh. 50 1M18150A Open/close indication circuit (DH Cir.

SK-M-544 1M18150C SF actuation circuit Isolation Valve)

SFV-26019 E-203 Sh. 50B 1M1A141A Open/close indication circuit (DH Clr.

SK-M-544 1M1A141C SF actuation circuit Isolation Valve)

EGS (EMERGENCY GENERATING SYSTEM)

P-888A SK-E-204 Sh. 11A 1M1A1138 Pump start signal circuit (Fuel Oil SK-M-552 Transfer Pump)

P-8888 SK-E-204 Sh. 11B 1M1A114D Pump start signal circuit (Fuel Oil SK-M-552 Transfer Pump)

P-888C SK-E-204 Sh. 11C 1M18114C Pump start signal circuit (Fuel Oil SK-M-582 Transfer Pump)

P-8880 SK-E-204 Sh. 110 1M18115E Pump start signal circuit (Fuel Oil SK-M-582 Transfer Pump)

III-15

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram CBS (CONTAINMENT BUILDING SPRAY SYSTEM)

P-291A E-203 Sh. 5-IN1A09A Pump start /stop indication circuit (RB Spray.

SK-M-524 IN1A90C SF actuation circuit Pump "A")

IN1A090 Ammeter circuit P-291B-E-203 Sh. 5A IN1809A Pump start /stop indication circuit (RB. Spray SK-M-524 1N1890C-SF actuation circuit Pump "B")

IN18090 Ammeter circuit SFV-29107' E-203 Sh. 55 1M1A144A Valve open/close indication circuit (RB Spray. Pump SK-M-524 1M1A144B SF actuation circuit Discharge MOV)

SFV-29108 E-203 Sh. 55A iM18153A Valve open/close indication circuit (RB Spray Pump SK-M-524 1M18153B SF actuation circuit Discharge MOV)

FWS (FEE 0 WATER SYSTEM MAIN FEED-WATER TRAIN)

FV-20529 E-205 Sh. 18 IM1A131A Open/close indication circuit-(FW to SG Stop SH-M-532 IM1A131B Valve control circuit Valve)

IM1A1310 Valve test circuit 1M1A131E Valve test circuit FV-20530 E-205 Sh. 18 1M18139A Open/close indication circuit (FW'to SG Stop SH-M-532 1M181398 Valve control circuit Valve)

IM181390 Valve test circuit IM18139E Valve test circuit FV-20575 E-205 Sh. 24A II2F206AA Valve open/close indication circuit (MS Failure FW SK-M-532 Valve)

FV-20576 E-205 Sh. 24A II2F206BA Valve open/close indication circuit (MS Failure FW-SK-M-532 Valve)

P-317A E-201 Sh. 31 II2T307AB MFWP turbine trip / reset indication (Main FW Pump "A")

III-16

1; TABLE III-2 System / Equipment Schematic /P& ids Cable Function.

or LOOP Diagram P-317B E-201 Sh. 31 II2T307B8 MFWP turbine trip / reset indication (Main FW Pump "B")

HVS (HEATING VENTILATION AND AIR CONDITIONING SYSTEM)

A-500A E-203 Sh. 6~

IN1A10A Fan start /stop indication circuit (RB Emergency SK-M-544 1NIA10C SF actuation circuit Clr.-)

A-5008 E-203 Sh. 6 IN1810A Fan start /stop indication circuit (RB Emergency SK-M-544 1N1810C SF actuation circuit Cir.)

A-500C E-203 Sh. 6 1N1A14A Fan start /stop indication circuit (RB Emergency SK-M-544 1N1A14C SF actuation circuit Clr.)

A-5000 E-203 Sh. 6 IN1814A Fan start /stop indication circuit (RB Emergency SK-M-544 1N1814C SF actuation circuit Cir.).

A-544A E-204 Sh. 8 IN1A13G Trip block signal circuit (D/G Room Vent SK-M-552 Supply Fan)

A-544B E-204 Sh. 8A IN1A17G Trip block signal circuit (D/G Room Vent SK-M-552 Exhaust Fan)

A-544C' E-204 Sh. 8B IN1806G Trip block signal circuit (D/G Room Vent SK-M-582 Supply Fan E-204 Sh. 8C IN1817G Trip block signal circuit A-5440 SK-M-582 (D/G Room Vent Exhaust Fan)

EDS (ELECTRICAL DISTRIBUTION SYSTEM)

S4A01-E-208 Sh. 9 1P1A01J Close/ trip indication circuit (SU Transformer IP1401K Voltage indication circuit 01 Supply Brkr) 1P1A01H Ammeter circuit III-17

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram S4A10 E-208 Sh. 8A 1P1A10G Close/ trip indication circuit (SU Transformer IP1A10E Voltage indication circuit

  1. 2 Supply Brkr) 1P1A10F Ammeter circuit S4A08 E-204 Sh. 1 1 PIA 088~

i recording circuit (0/G Supply IP1A08C

..ri recording circuit Breaker)

IP1A08Q Bus sequence circuit IP1A08R Bus sequence circuit 1P1A08W Close trip indication circuit E-208 Sh. 8 1P1801F Trip block signal circuit S4801 (SU Transformer IP1801G Voltage indication circuit 02 Supply Brkr) 1P18014 Ammeter circuit IP1801J Breaker close/ trip indication circuit S4804 E-208 Sh. 9 IP1804F Trip block signal circuit (SU Transformer IP1804G Ammeter circuit

  1. 1 Supply Brkr)

IP1804H Breaker close/ trip indication circuit IP1804J Voltage indication circuit S4811 E-204 Sh. 2 1P1811B Bus sequencing circuit (D/G Supply Brkr)

IPIB11C WH recording circuit IP1811Q Trip block signal circuit IP1811V Breaker close/ trip indication circuit S4A203 E-208 Sh. 52 1P1A203A Voltage indication circuit (SU Transformer IP2A203A Ammeter circuit 02 Supply Brkr)

IP1A203C Breaker close/ trip indication circuit S4A207 E-208 Sh. 54 1P2A207A Ammeter circuit (SU Transformer IP1A2078 Voltage indication circuit 01 Supply Brkr)

IP1A207C Breaker close/ trip indication circuit S4A202 E-204 Sh. 19 1P1A202F Voltage indication circuit (D/G Supply Brkr)

IP1A202H Breaker close/ trip indication circuit IP2A202A Metering ct circuit IP2A202B Metering ct circuit IP2A202C Metering ct circuit IP2A202F Metering ct circuit IP2A202D Bus sync pt circuit IP2A202E Bus sync pt circuit SB4203 E-208 Sh. 53 1P18203A Voltage indication circuit (SU Transformer IP28203A Ammeter indication circuit 02 Supply Brkr)

IP18203C Breaker close/ trip indication circuit III-18

TABLE III-2 System / Equipment Schematic /P& ids Cable Function or LOOP Diagram S48207 E-28 Sh. 55 1P2B207A Ammeter circuit (SU Transformer IP182078 Voltage indication circuit

  1. 1 Supply Brkr) 1P18207C Breaker close/ trip indication circuit S4B202 E-204 Sh. 20 1P18202F Voltage indication circuit (D/G Supply Brkr)

IP18202H Breaker close/ trip indication circuit IP18202A Metering ct circuit IP182028 Metering ct circuit IP18202C Metering ct circuit IP18202F Metering ct circuit IP282020 Bus sync pt circuit IP2B202E Bus sync pt circuit III-19 i

SECTION IV RESPONSE TO HIGH-LOW PRESSURE INTERFACE QUESTIONS FROM ATTACHMENT 2 TO CLARIFICATION LETTER TO GENERIC LETTER 81-12 NRC REQUEST a.

Identify each high-low pressure interface that used redundant electrically controlled devices (such as two series motor operated valves).to isolate or preclude rupture of any primary coolant boundary.

DISTRICT RESPONSE The District has identified the following sets of series valve to isolate or preclude the rupture of the primary coolant boundary at a high-low pressure interface.

1.

Pressurizer relief valve and block valve PSV-21511 (non-1E)

HV-21505 (CH B) 2.

Pressurizer vent valves HV-21515 (non-1E)

~HV-21517 (non-1E) 3.

RCS Sample Lines a.

Pressurizer Liquid Sample HV-21516 (non-1E)

SFV-70001 (CH-A)

SFV-70002 (CH-B) b.

RCS Liquid Sample HV-21514 (non-1E)

SFV-70001 (CH-A)

SFV-70002 (CH-B) c.

Pressurizer Vent Gas Sample HV-21515 (non-1E)

SFV-70003 (CH-A)

SFV-70002 (CH-B) 4.

RCS and Pressurizer High Point Vents a.

HV-20533 (CH-A)

SG-A vent HV-20579 (CH-A)

SG-A vent IV-1

l' SECTION IV b.

HV-20534_(CH-B)

SG-B vent HV-20580 (CH-B)

SG-B vent c.

HV-21528 (CH-B)

Pressurizer high point vent HV-21522 (CH-B)

Pressurizer high point vent 5.

RCS to Decay Heat Line HV-20001 (CH-A)

HV-20002 (CH-B) 6.

Letdown System SFV-22023 (CH-A)

SFV-22009 (CH-B) 7.

RCP Seal Return Line SFV-24004 (CH-B)

SFV-24013 (CH-A)

NRC REQUEST o.

For each set of redundant valves identified in (a), verify the redundant cabling (power and control) have adequate physical separation as required by Section III.G.2 of Appendix R.

DISTRICT RESPONSE Circuits for the redundant valves listed in (a) do not satisfy the requirement of section III.G.2 of Appendix R in the fire areas shown below:

1.

PSV-21511 and HV-21505 Fire areas 36, 32, 20, 17, 19, and 1 2.

HV-21515 and HV-21517 Fire areas RG1, 36, 31, 18, 17, RM1, 28, 19, 20, 32, and 1 Circuits for these valves have the same routing.

3.

a.

HV-21516, SFV-70001, SFV-70002 Fire areas 20 and 1 b.

HV-21514, SFV-70001, SFV-70002 Fire area 20 c.

HV-21515, SFV-70003, SFV-70002 Fire areas 1 and 20 IV-2

)

SECTION IV 4.

'HV-20533'and HV-20579. HV-20534 and HV-20580. HV-21528 and 4V-21522 Both the series valves in all three different vent lines belong to the same channel. The respective valve location and their circuit roetings are the same.

5.

HV-20001 and HV-20002 Fire areas RG1, 36, 20, and 1 6.

SFV-22023 and SFV-22009 Fire areas 17 and 1 7.

SFV-24004 and SFV-24013 Fire areas 20, 1, 17, and 31 NRC REQUEST c.

For each case where adequate separation is not provided, show that fire induced failures (hot shorts, open circuits, or short to ground) of the cables.will not cause mal-operative result in a LOCA.

DISTRICT RESPONSE The District has analyzed the effects of potential cable failures on the operation of the valves and listed these cables by common fire areas.

1.

pSV-21511 and HV-21505 Fire areas 32 and 19 contain:

1R2C215VA (PSV-21511)

Open or short in conductors causes the valve to stay in close position. Hot short to 125 V DC cable from SOE panel'can open the valve.

121B182A (HV-21505)

} Open or short in the conductors causes the valve

} to stay as is (normally OPEN).

IM18182B (HV-21505) }

Fire area 20 contains:

1R2C216VA (PSV-21511)

Open or short in conductors.causes the valve to stay in close position. Hot short to 125 V DC cable from SOE panel can open the valve.

1R2C215VB (PSV-21511)

Short or hot short in conductors can open the valve.

1R2C215VF (PSV-21511)

Short or hot short can open the valve.

1M18182A (HV-21505)

Short or hot short can cause the valve to stay open.

IM181828 (HV-21505)

} Open, short, or hot short will cause the valve to

} stay as is (normally OPEN).

1218182A (HV-21505)

}

IV-3

SECTION IV-Fire area 36 contains:

1R2C215VA (PSV-21511)

Open or short drives the valve to close position.

Hot short to 125 V DC cable from SOE panel can open the. valve.

1R2C215VE-(PSV-21511)

Short or hot short can open the valve.

1218182A -(HV-?1505). } Open, short, or hot short will cause the valve to IM181828

} stay as is (normally OPEN).

Fire areas 1 and 17 contain:

1R2C215VB (PSV-21511)

Short or hot short in circuit can open the valve.

1R2C215VE (PSV-21511)

Short or hot short can open the valve.

1R2C215VF-(PSV-21511)

Short or hot short can open tho' valve.

1M18182A (HV-21505)

Open, short, or hot short can cause the valve to stay open.

Fire in areas 32, 19, 20, 36, 17, or the Control Room (area 1) can poten-tially cause the EMOV and its block valve to both open at the same time.

This event can be precluded for fire in areas 32, 19, 20,-36, and the CR by tripping the 125 V DC power supply breaker SOE02. located in the 480 V West Switchgear Room. This will de-energize the solenoid on PSV-21511 allowing the valve to fail close.

In fire area 17, block valve HV-21505 has one circuit only (1M18182). This circuit has been insulated.

So fire in area 17 will damage this circuit and block valve HV-21505 can be closed from the Control Room.

2.

HV-21515 and HV-21517 Fire areas RG1, 36, 31, 18, 17, RM1, and 28 contain control and power circuits from both valves.

Pressurizer vent valves HV-21515 and HV-21517 are 480 V motor operated normally' closed valves.

During the normal plant operation, the supply breakers for these normally closed valves will be racked out. So power and control circuits of these valves would be de-energized during normal operation. Therefore, open, short, or hot short in the' circuits of these valves due to fire in any of the areas will not affect the closed status'of the valves.

3.

a.

HV-21516, SFV-70001 SFV-70002 Fire area 20 and 1 contains the circuits from all three valves. During normal plant operation, the supply breaker for the normally closed valve HV-21516 will be racked out. Pressurizer liquid sample valve HV-21516 is 480 V motor operated normally closed valve.

So, power and control circuits of this valve would be de-energized during normal plant operation.

Therefore, open, short, or hot short in the circuits of this valve due to fire in this area will not affect the closed status of the valve and at least one' valve in the liquid sample line would remain closed all the time.

3.

b.

HV-21514. SFV-70001, SFV-70002 l

Fire area 20 contains the circuits from all three valves.

During normal IV-4

r-SECTION IV plant operation, the supply breaker for the normally closed valve HV-21514 will be racked out. This valve is motor operated normally closed valve.

So power and control circuits of this valve would be de-energized during normal plant operation.

Therefore, open, short, or hot short in the circuits of this valve due to fire in this area will not affect close status of the valve and at least one valve in liquid sample line would remain close all the time.

3.

c.

HV-21515, SFV-70002, and SFV-70003 Fire area 1 and 20 contains the circuits from all the three valves. During normal plant operation, the supply breaker for the HV-21B15 will be racked out.

This valve is a motor operated normally closed valve.

So power and control circuits of this valve would be de-energized during normal plant operation. Therefore, open, short, or hot short in the circuits of this valve due to fire in any.of the above areas will not affect the close status of the valve and at least one valve of this line would remain close all the time.

4.

RCS and Pressurizer High Point Vent Valves HV-20533 and HV-20579, HV-20534 and HV-20580, HV-21528 and HV-21522.

During normal plant operation, the supply breakers for all these normally closed valves (HV-20533, HV-20579, HV-20534, HV-20580, HV-21528, and HV-20522) will be racked out.

So the fire in any area will not affect the close status of the valve.

5.

HV-20001 and 20002 Fire areas 34, 36, 20, and Control Room (AREA 1) contains circuits for both valves. During normal plant operation supply breakers for both valves will be racked out. These valves are 480 V motor operated normally closed valves.

So, power and control ~ circuits of these valves would be de-ener-gized during normal plant operation.

Therefore, open, short, or hot short in the circuits of these valves due to fire in any of the above areas will not affect closed status of the valve and high/ low pressure interface would not be affected due to fire in any of the above areas.

6.

SFV-22023 and SFV-22009 Fire area 17 contains:

l 121A133A (SFV-22023)

Open, short, or hot short has no effect on valve status.

i IM1A133A (SFV-22023)

Short or hot short will open the valve.

1M1A133C (SFV-22023)

Open, short, or hot short has no effect on valve status.

1M1A133B (SFV-22023)

Short or hot short will cause the valve to stay close.

Circuits are in insulated conduits and r

would not be affected by the fire in the area.

1R2C2200M (SFV-22009)

} Circuits are in insulated conduits and would not 1RIC220DN (SFV-22009)

} be affected by the fire in the area.

IV-5

SECTION IV

-Fire area 1 contains:

1M1A133A (SFV-22023)

Short or het short will open the valve.

1M1A133B (SFV-22023)

Short or hot short will cause the valve to stay close.

s 1RIC2200B (SFV-22009),' Short or hot short can open the valve.

1RIC2200D (SFV-22009)

Short or hot short can cause the valve to stay close.

1RIC2200E (SFV-22009)

Opens or short will cause the valve to stay close.

Hot short can open the valve.

1R1C2200F (SFV-22009)

Open, short, or hot short has no effect on valve status.

1RIC2200K (SFV-22009)

Short or hot short will cause the valve to stay close.

1RIC2200M (SFV-22009)

} Circuits are in insulated conduits and would not 1RIC2200N (SFV-22009)

} be affected by the fire in the area.

101801A (SFV-22009)

Open or short causes the valve to stay close.

Hot short does not affect valve status.

So, fire in area 1 (CR) only c\\an cause the letdown line to stay open as all circuits of valve SFV-22009 are insulated in fire area 17. This event can be precluded by opening the breaker 72-B01 in 125sV DC panel SOB de-energizing the solenoid allowing SFV-22009 to fail close. This valve is located outside the containment and can also be c'iosed manually in case it is not possible to de-energize the solenoid.

7.

SFV-24004 and SFV-24013 y

\\

Fire area 20 contains:

IM1A136C (SFV-24004)

,Open circuit has no effect.

Short or hot short circuit causes the valve to stay'close.

1RIC240C (SFV-24013) Open or short in circuit causes the valve to stay close.

Hot short can open the valve.

1RIC2400 (SFV-24013,) ; 'Open,t short, or hot short affects valve indication only.

1RIC240H (SFV-24013)!

Open or short does not affect valve status.

Hot short circuit causes valve to stay close.

1RIC240I (SFV-24013)

Short or hot short circuit causa the valve to stay

(

,close. Open circuit does not affect the valve status.

Fire area 1 contains:

1M1A136B (SFV-24004)

Short or' hot short circuit causes the valve to stay close. Open circuit has no effect.

1M1A136C (SFV-24004)

Short or hot short circuit causes the valve to stay cicso. Open circuit has no effect.

1RIC240C (SFr-24013)

Opendr'short in circuit causes the valve to stay close.

Hot short can open the valve.

r 1RIC2400 (SFV-24013)

Open, short, or hot short in ' circuit will affect valve indications only.

i 1RIC240H (SFV-24013)

Open or short does not affect valve status. Hot IV-6'

7_

SECTION IV short circuits causes the valves to stay close.

1RIC240I (SFV-24013)

Short or hot circuit will cause the valve to stay close. Open circuit does not affect valve status.

1RIC240G (SFV-24013)

Short or hot short in the circuit causes the valve to stay close. Open circuit does not. affect valve status.

1RIC240A (SFV-24013)

Short or hot short in the circuit can open the valve. Open circuit does not affect the valve status.

1RIC240B (SFV-24013)

Short or hot short in the circuit causes the valve to stay close.

Open circuit does not affect valve status.

Fire area 17 contains:

1RIC240H (SFV-24013)

Open or short in the circuit does not affect valve status. Hot short causes the valve to stay close.

1M1A136B (SFV-24004)

Short or hot short circuit causes the valve to stay close. Open circuit has no effect.

IM1A136C (SFV-24004)

Short or hot short causes the valve to stay close.

Open circuit has no effect.

IM1A1360 (SFV-24004)

Open, short, or hot short does not affect valve status.

121A136A (SFV-24004)

Open, short, or hot short does not affect valve status.

Fire area 31 contains:

1R1C2401 (SFV-24013)

Short or hot short circuit causes the valve to stay close. Open circuit does not affect valve status.

1RIC240J (SFV-24013)

Short or hot short circuit causes the valve to stay close. Open circuit does not affect valve status.

1RIC240K (SFV-24013)

Short or hot short circuit causes the valve to stay close. Open circuit does not affect valve status.

1RIC240L (SFV-24013)

Short or hot short circuit causes the valve to stay closs. Open circuit does not affect valve status.

1M1A136D (SFV-24004)

Open, short, or hot short does not affect valve status.

121A136A (SFV-24004)

Open, short, or hot short does not affect valve status.

So fire in areas 20, 1, or 17 does not open both the valves.

IV-7

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u a

a a

u 8

h

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-5 LT-21503A PRESSURIZER LEVEL

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n

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-8 PT-20519 STEAM GEN. WIDE RANGE PRESSURE

-9 PT-20520 u

a a

a a

-10 XE-00005 86 SOURCE RANGE NEUTRON FLUX

-11 PT-20543 STEAM GEN. WIDE RANGE PRESSURE

-12 PT-21042/

RCS PRESSURE WIDE RANGE PT-21043

-13 PT-21092/

RCS PRESSURE WIDE RANGE PT-21099

-14 TE-21023A/

RCS COLD LEG WATER TEMR TE-21023B

-15 TE-21024A/

RCS COLD LEG WATER TEMR U

TE-2l0248 SK-ICR-16 TE-21029/

RCS TEMP. WIDE RANGE TO T-SAT METER TE-21030/

TE-21033/

~

~ ~

TE-21034 SHEET NO.

DEVICE NO.

SYSTEM h

h

'SK-ISD -l. LT-2050l A STEAM GEN. E-205A, WIDE RANGE -

E-205B, a

-2 LT-20502A a

a a

n

-3 LT-21503B PRESSURIZER LEVEL, TRAIN 'A'

-4 LT-21503D u

n

-5 LT-23502C MAKE-UP TANK LEVEL

-6 PT-20543C STEAM GEN. E-205A, WIDE RANGE

-7 PT-20543D E-205 8, n

a a

a

-8 PT-2f050 RCS PRESSURE LOOP 2l050A

-9 PT-21051 2!O51A RCS PRESSURE LOOP,B'

-10 TE-21024C RCS TEMP. COLD LEG 'A

-Il TE-21025C u

n u

u RCS TEMP. T WIDE RANGE LOOP,'A'

-12 TE-2iO31A H

B' V

-13 TE-210328 a

a a

a a

SK-ISD -14 XE-00005 PORTABLE SOUR.CE RANGE NEUTRON FLUX APERTURE CARD NO. TITLE SHEET-INDEX r:A APPENDIX R ANALYSIS

=-

J S ANGL

/ 13 k.On"NN a" enoa$ woY. aus"Ne"$A o

n no su 2 G-2los C6 IAW

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2 /8-85 A'X LkW Gsuun S K-I-l 2

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g c;p m.

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nf SHTS.

-w i--w--

v i

i SYMBOLS i

  • i PANEL ID DEVICE
l. INSTRUMENT
4. COMPUTER POINT 4 ID PLANT LOCATION (RB) REACTOR BLDG PANEL ID SYSTEM
2. INDICATION
5. DISPL AY TYPE PLANT LOCATION (EOF) EMERGENCY OPERATIONS FACILITY

~

(E.SWGR) EAST SWITCHGEAR ROOM (TSC) TECHNICAL SUPPORT CENTER (W.SWGR) WEST SWITCHGEAR ROOM PANEL 10

3. ISOLATION PANEL ID
6. PLANT INPUTS TYPE INPUT ISOLATOR NOTE:

OPEN OR SHORT ON THE OUTPUT HAS NO EFFECT ON THE INPUT.

7. DEVICE IDENTIFICATION XX-XXXX NUMERICAL IDENTIFIER E ELEMENT T TRANSMITTER R RECORDER I INDICATOR Y RELAY, BLIND S SWITCH T TEMPERATURE P PRESSURE L LEVEL H HAND APERTURE CARD NO.

TITLE LEGEND t,*a A APPENDIX R ANALYSIS YSANGL Nf83

  • ~ "

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hhTHD"SECO NUCLEAR GEN _ STATION UNIT NO_ !

oEsiaN ENoa.

supv..EnoRqpRoa. ens EnoR. wor. RELEASE DATE INV T. NO.

pWG,NO.

REV.

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of S MTS.

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l l

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l

.'I (RBT (WEST SWGR)

I H4 CAL LO35 H4CDAC IDADS N

L9801 CRT h

H4CDAR3 H4CDAL UFM CCU (WEST SWGR)

H4SPDS SPDS L9801 CRT WIDE RANGE STEAM GENERATOR LEVEL

'I l

LOOP 20501 TRAIN-A i

i APERT CARD No.

TITLE LOOP DIAGRAM i

~

APPENDIX-R ANALYSIS j

I?Pzi A CONTROL ROOM DISPLAY N'TL FF 83 "7'

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L9802 CRT h

H4CDAR5 H4CDAL UFM CCU l

(EAST SWGR)

H4SPDS SPDS L9802 CRT WIDE RANGE STEAM GENERATOR LEVEL LOOP 20502 TRAIN-B APERT CARD No.

TITLE LOOP DIAGRAM APPENDIX R

ANALYSIS l

fat A CONTROL. ROOM DISPLAY ErEIrr

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LT NNI l

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l I

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H4CDAR3 H4CDAL l

UFM CCU (WEST SWGR)

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PRESSURIZER LEVEL LOOP 21503A APERT CARD No.

TITLE LOOP DIAGRAM APPENDIX R

ANALYSIS i

7"$' A CONTROL ROOM DISPLAY RdTL FF 83

^

lYAYCM"SECO NUCLEAR GEN. STATION UNIT No.1 DE51GN ENG 4.

SUPV. ENGR PROJ. ENG ENGR.MGR.

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H4SPDS SPDS L9007 CRT 1

l PRESSURIZER LEVEL LOOP 21503C L

APERT CARD No.

TITLE LOOP DIAGRAM e

f APPENDIX R

ANALYSIS f

i

$fz$' A CONTROL ROOM DISPLAY j

R5TL FF i

83 i

^

Y[NCA3"SECO NUCLEAR GEN STATION UNIT No.1

^

I DESIGN ENG 4.

SUPV. ENG R PROJ. ENG ENGR.MGR.

RELEASE DATE I*

INVT.NO.

pwG. NO.

REV.

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^

H4CDAL HICO IDADS CCU LO41 NEER

~

CRT CRT (EOF)

(TSC)

H4SPOS h2SP CRT l

H4CDAC IDADS

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L9000 CRT l

l l

I I

(

i-MAKE-UP TANK LEVEL l

APER. CARD NO.

~~ ~ OOP DIAGRAM L

li APPENDIX R AN ALYSIS

,c, ",y l','7, o,,, A CONTROL ROOM DISPLAY o,,

~

G.F.B.11 8 3 l

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.N.

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y EMT. NO.

of SHT3.

o

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20519A w

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l H4CDAL H4SPDS SPOS CCU P9301 CRT

/

l I

IDADS !

H4CDAC IDADS i

rh CRT l

P 93 CRT

% )01 (TSC) ll CRT (EOF)

STEAM GENERATOR A WIDE RANGE PRESSURE LOOP

]

APERT CARD No.

TITLE LOOP DI A GR AM l

APPENDIX R

ANALYSIS 5'-

i*d A CONTROL ROOM DISPLAY RESLIFF Y-83 Y Nd O SECO GENERATION STATION UNIT No.1 OE5IGN ENG 4 SUPV. ENG R PROJ. ENG ENGR. MGR.

RELEASE DATE

- #NV T. No.

pwG. no.

REv.

Osm

.o. ao.

S K-ICR-8 y

C[yn No.

DATE gua g,

,, L, y,g g g,,L,

. n rm sHT. No.

af s wTs.

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20 2052 PT H4 CAL i

05208 l

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CCU P93OO CRT V

D j

IDADS H4CDAC IDADS M

(P 93)OO l

CRT CRT (TSC)

CRT i

(EOF)'

i STEAM. GENERATOR 8 WIDE RANGE PRESSURE LOOP 20520 APERT CARD No.

TITLE LOOP DIAGRAM APPENDIX R

ANALYSIS l

7"d' A CONTROL ROOM DISPLAY Rd LIFF

$9-83 hR NCb"SECO GENERATION STATION UNIT No,I ogs GN ENG 4.

SUPV. ENGR.iPROJ. ENG ENG R. MG R.

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SOURCE R ANGE NEUTRON FLU X I NDIC ATION APERT. CARD NO.

TITLE LOOP DI AGRAM APPE N DI X R AN ALYSIS

?*z$ A CONTROL ROOM DISPL AY.

OR.SY DATE BWO 2-85 NNC 0 SECO MUCLE AR GEN STATION UNIT No I DEslGN ENG

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HELEASE DATE 6N v T. NO.

OWG. NO.

REV.

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NO. DATE ENGR _

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STEAM GEN. WIDE RANGE PRESSURE LOOP 20543 APER CARD No.

TITLE LOOP DI AGR AM APPENDIX R AN A LYSIS

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A 036 u

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H4TSB H4BS UY

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H4CDARI RB)

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CRT

(

WIDE RANGE RCS PRESSURE

~

APERT CARD No.

TITLE LOOP DIAGRAM

. ~...., '

l 3-e--

APPENOlX R

ANALYSIS IowG. ^

x.

OR. ;

f'E CONTROL ROOM DISPLAY RATLIFF kt-9-83 INE[CNSECO NUCLEAR GEN. STATION UNIT No.I

^

OESIGN ENG 4.

SUPV ENGR PROJ. ENG ENG R. MG R.

RELEASE DATE

/h 2 19-85 BWO >'V

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ygy, A l 19 84 RK V/

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N

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of S MTS.

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SFAS NNI H4TSA UY T-SAT 210 31 W.SWGR)

H4SAB H4SAB PT 21099 SFAS IRI SO4 86 A.b D

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