Text

Cable Separation Analysis Rept
	ML20073L591
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/30/1983
From:	; LONG ISLAND LIGHTING CO.
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ML20073L588	List: ML20073L583; ML20073L591;
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o CABLE SEPARATION ANALYSIS REPORT SHOREHAM NUCLEAR POWER STATION

,O UNIT NO.1 l

o L a.se =

!!#1s8 era 88gg,

TABLE OF CONTENTS

() Section

.1 PURPOSE.

Title Page 1

2 GENERAL METHOD OF ANALYSIS . . . . . . . . . . . . . . . . 1 3 ASSUMPTIONS. . . . . . . . . . . . . . . . . . . . . . . . 1 I 4 SPECIFIC METHODS OF ANALYSIS . . . . . . . . . . . . . . . 2 4.1 AFFECTED AREAS . . . . . . . . . . . . . . . . . . . . . 2 4.2 SHUTDOWN MODEL . . . . . . . . . . . . . . . . . . . . . 2

} 4.3 SHUTDOWN EQUIPMENT . . . . . . . . . . . . . . . . . . . 3 4.4 DEVELOPMENT OF SHUTDOWN EQUIPMENT BY AREA. . . . . . . . 7 5 RESULTS AND RECOMMENDATIONS. . . . . . . . . . . . . . . 8 6 CONCLUSIONS. . . . . . . . . . . . . . . . . . . . . . . . 9 7 MAINTENANCE OF CABLE SEPARATION ANALYSIS REPORT. . . . . . 9 APPENDIX A - Cable Separation Analysis Results - Secondary Containment l

APPENDIX B - Drawings l

i 1

iii Original

} April 1983

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,,,,r n n ,, _ , ,,,,,.,,_,,_n_ ,_..,.,w,_ _,,,_,_-_n,,--..,,,.,,_-_.,n,nm__,,

LIST OF TABLES Table Title 4.1-1 Secondary Containment Area Boundaries 4.4-? Systems with Class 1E Cables 4.4-2 Shutdown Equipment List LIST OF FIGURES Figure Title 4.1-1 Arrangement of Secondary Containment Areas 4.2-1A Shutdown Model 4.2-1B Shutdown Model 4.2-1C Shutdown Model 4.4-1 Development of Shutdown Equipment by Area O

l iv Original April 1983

1 PURPOSE This analysis is made to demonstrate that sufficient separation

\ exists between_ safety-related components of redundant systems located in the secondary containment, and necessary for shutdown such that a postulated event causing the disability of all cables in raceways in the designated area will not prevent plant safe shutdown. This report is based upon as-built drawings listed in Appendix B.

4 2 GENERAL METHOD OF ANALYSIS

, The secondary containment is divided into "Affected Areas." All j cables and raceways in each "Affected Area" are assumed to be 4

disabled such as to render them unavailable for use in shutdown.

l A determination is then made whether shutdown can be achieved I using the remaining shutdown equipment of other unaffected areas.

The areas are chosen such as to maintain a minimum 20 ft

separation, as required by 10CFR50 Appendix R, between safety-i- related components of redundant systems and the disabling event

is fire.

l 3 ASSUMPTIONS The following are the assumptions and design bases for the ;

! separation analysis:

l 1. It is assumed that:

1 I \

a. The reactor is operating at 100 percent power'when i the postulated event occurs.

b. Only onsite power is available in achieving safe

shutdown.

i

c. The reactor is isolated from the main condenser.

(

d. T1.[ :e is an automatic scram (or manual at-the direction of the shift supervisor) to bring the plant to hot shutdown.

e. Single failure is not considered.

2. As presented in the NRC review reminder (1) , it is !

t assumed that there is a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months period in which to i achieve cold shutdown. During this three day period, credit may be taken for manual system operation as well as for reasonable repairs, etc.

(1) Nuclear Regulatory Commission. " Review Reminder" from V. Benaroya to Auxiliary System Branch Staff Members, August 8, 1978.

Original l

( 1 April 1983 l i

l l

{

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4 SPECIFIC METHODS OF ANALYSIS 4.1 AFFECTED AREAS In order to separate the secondary containment into conservative affected areas, overlapping segments are defined as described below.

The secondary containment is segmented as shown in Figure 4.1-1.

There are distinct floor levels within the secondary containment, and vertical boundaries are established for the secondary containment areas at each floor elevation. Cable and raceways in each segment are assumed to be disabled and a determination made whether shutdown can be accomplished with the remaining equipment. Upon completion of the analysis of each area, the procedure is repeated with new segments which are rotated or indexed 22.5 degrees from the previously analyzed segments. This overlap operation assures that no sensitive interface boundaries exist.

Figure 4.1-1 illustrates the arrangement of the secondary containment areas, and Table 4.1-1 describes the area boundaries.

The analysis assumes that all shutdown components fed from floor-mounted equipment such as motor control centers, panels, or racks located in an affected area are disabled. This is accomplished by assuming either the power source (cable) disabled if the equipment is red from the top, or the entire equipment disabled if fed from the bottom. The analyses also assumes the loss of upstream n.otor control centers (MCCs) as a result of cable disablement occurring anywhere along the MCC cascade.

4.2 SHUTDOWN MODEL In order to make a determination that shutdown is achievable with the cable and raceway in a given area disabled, it is necessary to develop a functional model for shutdown. This model is illustrated in Figures 4.2-1A, 4.2-1B, and 4.2-1C.

Paths to successful shutdown are shown in this model. All systems which can contribute to plant shutdown are identified.

All auxiliary systems, such as ventilation, cooling water, control and instrumentation, as well as electrical power sources are included. In the analysis, however, credit is taken only for safety-related systems and equipment.

2 Original April 1983

4.3 SHUTDOWN EQUIPMENT g- s Based on the protection sequence and use of safety-related t

\ ') systems only, the selection of shutdown systems is made as follows: ,

1. System B21 - Nuclear Boiler The seven ADS and all eleven safety-relief valves are required to operate only manually. Automatic initiation is not necessary and will not normally occur since no LOCA and therefore no high drywell pressure is assumed which is required for automatic initiation.

The two head vent valves MOV083, and 084 are required not to operate " simultaneously" in order to prevent blowdown of the reactor vessel steam into the primary containment. Thus the valves are not needed for drywell safe shutdown but are required not to be operated.

The SRV's may be utilized for a combination hot / cold i shutdown operation. With the vessel at high pressure, the valves can provide sufficient pressure relieving capacity to enable the low head systems (LPCI and Core Spray) to provide core inventory. With the vessel at low pressure, the valves can provide extended core and/or suppression pool cooling by holding the valves open, enabling the low head systems to provide a

(}

\_j suppression pool / reactor Cooling would be provided directly or indirectly via vessel circulation path.

the RHR exchanger. The above modes are designated as the RHR/CS/SRV flow path in the separation analysis.

2. System B31 - Reactor Recirculation System The two pressure switches, PS023A and B, required for automatic RHR system operation are needed.

3. System C41 - Standby Liquid Control The Category I portions of this system should be available in case control rod insertion is not completed. It is essential that this system not operate unless it is actually required.

1

4. System C61 - Reactor Plant Remote Shutdown l

The eight Category I indicating transmitter circuits i for RHR main flow (FT001), reactor vessel pressure l (PT006), service water header pressure (PTGil),

l suppression pool temperature (TT022A and B), and level l

3 Original

[\-)# April 1983 l

1 (LT026), and drywell pressure (PT012) and temperature (TT021) are required.

5. System Ell - Residual Heat Removal All Category I components, except the following ten valves, are required: The two flow to suppression pool valves MOV042A and B are not required since the normally closed upstream valves are protected. The two head spray isolation valves MOV053 and 054 are not required for shutdown since cable failure resulting in both valves opening presents no problem since there is a check valve in series with these MOVs to prevent reactor blowdown. The four heat exchanger vent valves MOV055A and B and 056A and B are not required for shutdown even during the steam condensing mode since cable failure resulting in opening of these valves will drain a one inch line from the heat exchanger opening to the suppression pool, an acceptable event. The two hydrogen recombiner subsystem valves AOV057A and B are not required for a non-LOCA condition and failure of valve cabling will cause valves to open, an event which will not result in significant degrading of the RHR cooling system.

6. System E21 - Core Spray All Category I components are required, except the two testable check valve bypass valves MOV081A and B, which are not required during shutdown. If these valves were to change state, there would be no adverse effect on system operation. Automatic initiation which is based on reactor water level is also required. Initiation signals based on reactor primary containment pressure are not required since there should be no high pressure condition without LOCA. Also, failure of the high drywell pressure initiation signal will not prevent injection nor cause the injection valves to open prematurely because a reactor pressure permissive in the control circuit of the injection valves will prevent valve opening on high reactor pressures. This permissive is considered a required component.

7. System E41 - High Pressure Coolant Injection All Category I components are required, except the five items described below. One is the loop level pump P-050 which if lost will not adversely affect the system since the time prior to initiation and between operating cycles should be short enough to prevent significant draindown of the pump discharge piping.

Another item is the inboard isolation bypass valve 4 Original April 1983

MOV047 which is not required for shutdown and will not affect system operation in either the open or closed

(~'N position. Also, the turbine exhaust vacuum breaker

( ,1 MOV049 is not required and is used only after a LOCA.

Lastly, the condenser exhaust vacuum breaker PCV144 and steamline trap bypass valve LCV091 are not required for shutdown and will, in fact, fail in the closed position on loss of air due to loss of offsite power. Assuming availability of air, failure of the control circuit resulting in valve opening is not detrimental to system operation. Automatic initiation based on reactor water level is required. Initiation due to high drywell pressure is not required since there should be no such condition without LOCA. Also, failure of drywell pressure initiation signal will not prevent injection, and if premature injection occurs, it will not adversely affect reactor operation. Instrumentation to identify HPCI steamline break which can cause steamline isolation is required.

8. System E51 - Reactor Core Isolation Cooling All Category I components are required, except those five corresponding to the E41 System (P-051, MOV047, MOV049, PCV144 and LCV091) and for the same reasons.

Automatic initiation is also required.

,s 9. System G33 - Reactor Water Cleanup i )

'/

' The containment isolation valves MOV033 and 034 are required to be closed to isolate the reactor from the remainder of the RWCU System. This isolation is necessary if standby liquid control system initiation is required.

10. System G41 - Fuel Pool Cooling and Cleanup The two service water inlet valves, MOV032A and B, used for ultimate cooling water connection and the corresponding valves in the service water system, are required to be closed to prevent pumping service water to the spent fuel storage pool, an event which in time could cause flooding in the reactor building.

11. System M43 - Fire Protection Only the Category I portion of this system is required to prevent inadvertent shutdown of the ventilation system or closure of motorized CO2 dampers.

p

( ) 5 Original

'~' April 1983

12. System M50 - RBSVS and Control Room A/C Chilled Water All Category I components are required. Most instruments required to start the chilled water units and associated chilled water and condensate pumps are local to the chiller units.

13. System P41 - Service Water All Category I components are required, except the two radiation monitoring system isolation valves MOV102A and B which are not needed during a non-LOCA condition.

In addition, a failure causing the valves to open will not result in unacceptable conditions. Automatic initiation is also required.

14. System P42 - Reactor Building Closed Loop Cooling Water System The three P-005A, B, and C RBCLCW circulating pumps and the two heat exchanger inlet isolation valves MOV042A and B are required to supply cooling to RHR pump seals.

Valves separating Category I from Category II piping and Division I from Division II piping are not required based on the assumption or no seismic event and, therefore, no piping failure. Operation of selected components will be manual and no automatic initiation is required.

15. System P50 - Compressed Air The MOV's and pressure switches used to supply and/or isolate the air co the SRV accumulators are required.

All other components are Category II.

16. Systems R22, 23, 24, 35, 42, 43 - Electrical Distri-bution All Class 1E electrical distribution and interconnecting cable is required.

17. System T46 - Standby Ventilation System Only a portion of the fourteen unit coolers in the reactor building are required to maintain the ambient temperature around the components needed for shutdown.

Manual operation only is required; automatic initiation is not needed. Ventilation equipment required for maintaining negative pressure in the reactor building secondary containment is not needed. The filtering equipment is not required since there is no LOCA/ release of radiation.

6 Original April 1983 s

18. System X41 - Miscellaneous Room HVAC 7y All Category I ventilation components are required in

( ) these miscellaneous areas.

19. System X60 - Diesel / Generator Ventilation All Category I ventilation components in the D/G rooms are required. l

20. System X61 - Control Room A-C All Category I components are required, except the two air-operated valves AOV37A and B which isolate the redundant portions of ducts that will remain intact, assuming no seismic condition. These dampers will fail closed on loss of offsite power.

4.4 DEVELOPMENT OF SHUTDOWN EQUIPMENT BY AREA The development of shutdown equipment by affected area is illustrated in the schematic diagram Figure 4.4-1.

The first step consists of developing a shutdown equipment list.

This is accomplished by using the shutdown model developed, as described in Section 4.2, and identifying all systems with safety-related cable (Table 4.4-1). These are then compared to the model requirements as indicated in Section 4.3 to sort out

/) the safety-related equipment for shutdown. The shutdown

\ _/ equipment list is contained in Table 4.4-2.

The second step is to incorporate the elementary diagram (ESK) information on the shutdown equipment list. Since a complete equipment versus ESK list already exists within the computerized Electrical Cable Schedule Information System (ECSIS), the shutdown equipment list is input to the computer, compared against the equipment versus ESK list, and sorted to get the shutdown equipment versus ESK list.

The third step is to identify the cables associated with each piece of shutdown equipment. This is accomplished by comparing the shutdown equipment versus ESK list generated in the previous step with the cable versus ESK list in the ECSIS.

Having identified, at this point, all shutdown equipment and its associated cable, it remains to identify the cable in each area and compare to the shutdown equipment in order to identify the disabled equipment.

The fourth step is to compile lists of cable trays and conduit by area, input to the computer, and compare against the cable versus n

('/ ) 7 Original April 1983

raceway list in the ECSIS thus creating the shutdown equipment cable versus area lists.

The fifth step is to compare the shutdown equipment versus cable h list from step three against the cable versus area lists from step four to identify the shutdown equipment lost for each area.

The final step is to compare the unaffected shutdown equipment versus area lists against the shutdown model to determine the impact on safe shutdown capability.

5 RESULTS AND RECOMMENDATIONS Appendix A presents the results of the separation analysis for the secondary containment.

The results are presented for each area investigated in the following format:

1. Systems Impacted (Divisions I, II, and III) - A listing of any system which computer analysis indicated had associated shutdown cable or cables in the area of interest.

2. System Functions Disabled -

All safety systems and components previously identified as essential and listed in Tables 4.4-1 and 4.4-2 are evaluated for their importance in achieving a safe shutdown. Those components whose failure would not necessarily cause a ,

system function loss are reviewed and, where no impact upon safe shutdown exists, are so noted under Disabled Function Evaluation below. As an example, in Section 008-07, Paragraph 1(C) identifies unit cooler 1T46*UC002A as a disabled 1T46, Division I, component.

However, the loss of that cooler does not affect the remaining Division I cooler (1T46*UC003A) and Division I 1T46 RBSVS components which have the capability of providing cooling for the Division I equipment utilized for safe shutdown and identified in Paragraph 4, Shutdown Capability.

Where an event damages extensive equipment in one train (Divisions I, II, or III), a statement such as "No credit taken for Division I system functions" is made, and the remaining statements generally refer to disabled functions in other Divisior s. In such a case, the analysis has determined that no Division I system functions are required to achieve safe shutdown.

3. Disabled Function Evaluation -

Identifies, at the system level, the importance to safe shutdown of any function that may be lost as a result of the event.

8 Original April 1983 L

4. Shutdown Capability -

Identifies whether redundant means of providing necessary safe shutdown functions

"')

x ,/

are available (given the Disabled Functions generally describes an available procedure in 3) and for safe 4 shutdown.

5. Further Action Recommended - Provides recommendations for required modifications which will further improve existing plant shutdown capability. These recommendations are not necessarily requisites to achieving shutdown but rather enhancements which would augment existing capabilities.

6. Action To Be Taken - Indicates specific action to be taken based on the recommendation, if any.

6 CONCLUSIONS

.For the postulated event, with concurrent loss of offsite power, hot and cold shutdown can be accomplished in each case using only safety-related systems and equipment. This considers the extreme case where an event is assumed to disable all shutdown cable terminating in or routed through each affected area.

It was not cecessary to take credit for separation by distance, covers on cable trays, fire suppression, etc, within the affected area nor for any nonsafety-related systems and equipment.

7 MAINTENANCE OF CABLE SEPARATION ANALYSIS REPORT All new conduit design by LILCO, C/J, S&W etc shall be sent to S&F1 Boston for review to assure that the designed routing does not jeopardize the analysis.

Therefore, prior to installaiton S&W Boston shall approve routing of conduit and if there are any problems the reviewer will attempt to indicate an acceptable path.

When cable is added to any existing raceway of any kind, S&W shall be notified so they may assure that the report is still valid.

5 9 Original April 1983

~O

TABLE 4.1-1 SECONDARY CONTAINMENT AREA BOUNDARIES Primary Segment Boundary Overlap Area From To Area From To N1 08 458 01 22.58 67.58 N2 458 908 02 67.58 112.58 N3 908 1358 03 112.58 157.58 N4 1358 1808 04 157.58 202.58 NS 1808 2258 05 202.58 247.58 N6 2258 2708 06 247.58 292.58 N7 270s 3158 07 292.58 337.58 N8 3158 08 08 337.58 22.5 8 Elevation From To 008 008 040 040 040 063 063 063 078 078 078 112 112 112 150 150 150 175 175 175 -

Segments are Numbered Elevation - Area Example:

063-N6; Elevation 063 to 078, Area 2258 to 2708 See Figure 4.1-1 10 Original April 1983

TABLE 4.4-1 7s ALL SYSTEMS WITH CLASS 1E CABLES

() SHOREHAM NUCLEAR POWER STATION LONG ISLAND LIGHTING COMPANY System No. Description B

B21 Nuclear Boiler

B31 Reactor Recirculation C

C11 Control Rod Drive Hydraulic (CRDH)

Control

C41 Standby Liquid Control (SLC)

C51 Neutron Monitoring

C61 Reactor Plant Remote Shutdown (RPRS)

C71 Reactor Protection (RPS)

D D11 Process Radiation Monitoring D21 Area Radiation Monitoring E

Residual Heat Removal (RHR)

O,

Ell

E21 Core Spray (CS)

E41 High Pressure Coolant Injection (HPCI)

E32 MSIV Leakage Control System

E51 Reactor Core Isolation Cooling (RCIC)

G Gil Radwaste

G33 Reactor Water Cleanup (RWC)

G41 Fuel Pool Cooling and Cleanup (T?CC)

H

H11 Main Control Room Panels i *H21 Miscellaneous Local Panels and j Racks

M M43 (Control Building) Fire Protection

M50 RBSVS and Control Room AC Chilled Water i

i

!h, l \/

11 Original April 1983

TABLE 4.4-1 (Cont)

System No. Description N

N11 Main Steam N21 Condensate and Feedwater P

P21 Demineralized and Make-up Water

P41 Service Water

P42 Reactor Building Closed Loop Cooling Water (RBCLCW)

P50 Compressed Air R

R22 Metal Clad Switchgear

R23 Unit Substaticns

R24 Motor Control Centers (MCC)

R35 AC Control and Instrumer.t Power R36 AC Uninterruptible (Vital) Power

R42 Battery Power (125 V DC)

R43 Diesel Emergency Power R81 Heat Tracing Power T

T22 Reactor Building Superstructure T23 (N2 to drywell floor Reactor Containment seal)

T46 Standby Ventilation System T48 Primary Containment Atmospheric Control System X

X40 Control Building Kitchen and Lavatory

X41 Miscellaneous Computer, Screen-well, Relay and Battery Room HVAC

X60 Diesel Generator Ventilation System

X61 Control Room Air-Conditioning System (CRAC) 12 Original April 1983 L.

~ ^ -

l 1..

1 i

4 TABLE 4.4-1 (Cont) j System

No. Description l

i. Z j Z93 Post-Accident Monitoring j Z97 -Emergency Response Facility I-a

$ NOTES: '

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l j

Safe Shutdown Systems. l I l i t i f

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I 13 Original i April 1983 !

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TABLE 4.4-2 SHUTDOWN EQUIPMENT LIST EQUIP LOC (1)

IDfNTITY DESCRIPTION ESK CKT NO2 PWR SC PWR SC LOC EL-AZ AUTOMATIC DEPRESSURIZATION SYSTEF 1821*SV092AX/Y ADS VLV 1821*RV92A SOVA/B 1.61-236/7 1 R42* PN LA2/ B2 EL 40' RELAY RM 102-218 1821*SV092BX/Y ADS VLV 1821*RV928 SOVA/B 1.61-236/7 1R42*PNLA2/B2 EL 40' RELAY RM 102-234 1821*SV092CX ADS VLV 1821*RV92C SOVA 1.61-238 1R42*PNLA2 EL 40' RELAY RM 102-234 1821*SV092DX ADS VLV 1821*RV92D SOVA 1.61-238 1R42*PNLA2 EL 40' RELAY RM 102-244 1821*SV092EX/Y ADS VLV 1821*RV92E SOVA/B 1.61-236/7 1R42*PNLA2/B2 EL 40' RELAY RM 102-253 1821*SV092FX ADS VLV 1821*RV92F SOVA 1.61-238 1 R42

PN LA2 EL 40' RELAY RM 102-124 1821*SV092GX ADS VLV 1B21*RV92G SOVA 1.61-238 1R42*PNLA2 EL 40' RELAY RM 102-115 1821*SV092HX/Y ADS VLV 1821*RV92H SOVA/B 1.61-236/7 1R42*PNLA?/B2 EL 40' RELAY RM 102-142 1B21*SV092JX/Y ADS VLV 1821*RV92J SOVA/B 1.61-236/7 1R42*PNLA2/02 EL 40' RELAY RM 102-126 1821*SV092KX/Y ADS VLV 1821*RV92K SOVA/B 1.61-236/7 1R42*PNLA2/B2 EL 40' RELAY RM 102-090 1821 *SV092 LX/Y ADS VLV 1B21*RV92L SOVA/B 1.61-236/7 1R42*PNLA2/B2 EL 40' RELAY RM 102-270 CORE SPRAY SYSTEM DIVISION 1 1E21*P013A CORE SPRAY PUMP SE21A01 1E21A01 1R22*SWG101 EPER SWGR RM EL 25' 8-103 1E21*PO49A LOOP LEVEL PUMP 6E2101 1E21A02 1R24*MCC1117 R.B. EL 40' 8-101 1E21*MOV031A PUMP SUCTION VV 6E2102 1E21A02 1R24*MCC1117 R.B. EL 40'24-148 1E21*MOV033A DISCHARGE VV 6E2103 1E21A04 1R24*MCC1113 R.B. EL 112' 104-115 1E21*MOV035A RECIRC VV 6E2105 1E21A06 1R24*MCC1111 R.B. EL 40'53-108 1E21*MOV034A MIN FLOW VV 6E2106 1E21A07 1R24*MCC1117 R.B. EL 40'14-098 j, 1B21*PT158A 1B21*PT158C PRES INTLK 1821-N097A(H21*P004)

PRES INTLK 1821-N097C(H21*P009) 1.61-272 1.61-272 78-079 78-102 4

I 1E21*PDS033A CS D/P I NTLK ( H21*P001) 8-110 1E21*FIS002A MIN FLOW (H21*P001) 8-110 DIVISION 2 1E21*P013B CORE SPRAY PUMP SE2102 1E21801 1R22*SWG102 EMER SWGR RM EL 25' 8-257 1E21*PO498 KEEP FILLED PUMP 6E2101 1E21802 1R24*MCC1127 R.B. EL 40' 8-259 1E21*MOV0318 PUMP SUCTION VV 6E2102 1E21802 1R24*MCC1127 R.B. EL 40'24-112 1E21*MOV033B DISCHARGE VV 6E2103A 1E21B04 1R24*MCC1123 R.B. EL 112' 104-245 1E21*MOV0350 RECIRC VV 6E2105 1E21806 1R24*MCC1121 R.B. EL 40'53-253 1E21*MOV034B MIN FLOW VV 6E2106 1E21BO7 1R24*MCC1127 R.B. EL 40'14-262 1821*PT158B PRES INTLK IB21-N097B(H21*P005) 1.61-273 78-257 1B21*PT158D PRES INTLK 1B21-N097D(H21*P010) 1.61-273 78-280 1E21*PDS033B CS D/P INTLK (H21*P019) 8-248 1E21*FIS002B MIN FLOW (H21*P019) 8-248 1E41*P074 VACUUM PUMP 11E4101 1E41N01 1R42*MCCOB1 R.B. EL 40' 8-170 1E41*P075 VACUUM TANK COND PUMP 11E4101A 1E41N02 1R42*MCCUB1 R.B. EL 40' 8-166 1E41*P127 AUX LO PUMP 11E4102 1E41NO3 1R42*MCCOB1 R.B. EL 40' 8-160 1E41*MOV031 HPCI PUMP SUCT FM CON ST TK VV 11E4109 1E41N09 1R42*MCCOB1 R.B. EL 40'20-220 1E41*MOV032 HPCI PUMP SUCT FM SUP POOL VV 11E4110 IE41N10 1R42*MCCOB1 R.B. EL 40'24-210 1E41*MOV034 HPCI STEAM SUP OUTBRD ISO VV 11E4105 1E41N05 1R42*MOC0b2 R.B. EL 112'64-161 O ri g i na l April 1982 O O O

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\ ,,

EQUIP LOC (1)

IDENTITY DESCRIPTION ESK CKT NO, fWR SC PWR SC LOC EL-AZ 1E41*MOVC35 HPCI PUMP DISCHARGE VV 11E4106 IE41N06 1R42*MCC082 R.B. EL 112'64-168 1E41*MOV036 MIN FLOW VV 11E4112 1E41N12 1R42*MCCOB1 R.B. EL 40'18-197 1E41*MOV037 HPCI TEST BYPASS VV TO CST VV 11E4107 1E41N07 1R42*MCC001 R.B. EL 40'18-195 1E41*MOV038 HPCI TEST BYPASS VV TO CST VV 11E4108 1E41N08 1R42*MCCOB1 R.B. EL 40'18-205 1E41*MOV039 LUB OIL COOL VV 11E4114 1E41N13 1R42*MCCOB1 R.B. EL 40'16-190 1E41*MOV041 STEAM SUPPLY INBRD ISOL VV 6E4102 1E41A01 1R24*MCC1118 R.B. EL 112'66-188 1E41*MOV042 HPCI STEAM OUT BRD ISOL VV 11E4103 1E41801 1R42*MCCOB2 R.B. EL 112'66-192 1E41*MOV043 HPCI STEAM TO TUBINE SUPPLY VV 11E4104 1E41N04 1R42*MCCOB2 R.B. EL 112'17-184 1E41*MOV044 HPCI TURBINE EXHAUST VV 11E4114 1E41N19 1R42*MCCOB1 R.B. EL 40'20-187 1E41*SOV081 STM LN DRN VV (015-190) 1.61-267 15-190 1E41*SOV082 STM LN DRN VV (015-190) 1.61-267 15-190 1E41*SOV083 COND DISCH VV (009-184) 1.61-267 9-184 1E41*SOV095 COND DISCH VV (009-184) 1.61-267 12-185 1E41*FS003 HPCI PP DISCH (H21*P014) 1.61-264 8-167 1B21*LT1548 HL TRIP 1821-N080B(H21*P004) 1.61-263 78-79 1821*LT154D HL TRI P 1821-N0800( H21*P005) 1.61-263 78-297 1E41*PS021L LO PP SUCT E41-N010(H21*P014) 1.61-263 8-167 1E41*PS026A HI TURB EX E41-N017A(H21*P014) 1.61-263 8-167 1E41*PS0268 HI TURB EX E41-N017B( H21*P014 ) 1.61-263 0-167 1E41*PS025B HI TURB EX E41-N012B(H21*P014) 1.61-263 8-167 1E41*PS025D Hi TURB EX E41-N012D(H21*P014) 1.61-263 8-167 1E41*PS023B STM PRES L E41-P0018(H21*P036) 1.61-263 8-160 1E41*PS023D STM PRES L E41-N001D(H21*P036) 1.61-263 8-160 1E41*PDS022B Hi STM D/P E41-N005 (H21*0026) 1.61-264 8-160 1E41*TE054B HI AREA T E41-N028B(034-185) 1.61-241 25-189 1E41*TE055B HI AREA T E41-N029B(034-210) 1.61-241 16-183 g IE41*TE054A HI AREA T E41-N028A(034-100) 1.61-241 25-203 Fa 1E41*TE055A HI AREA T E41-N029A(034-200) 1.61-241 15-187 j' 1E41*PDS022A 1821B-K32A Hi SIM D/P E41-N004 (H21*P016)

B218-K32A(H11*P614) 1.61-264 1.61-264 8-157 CB/63-C12 1821B-K32B B218-K32B(H11*P614) 1.61-264 MC/21-N12 1831B-K31A B31B-K31A(H11*P614) 1.61-207 MG/21-P12 1831B-K31B B318-K31B(H11*P614) 1.61-208 8-178 1E41*PS025A HI TURB EX E41-N012A(H21*P034) 1.61-264 8-178 1E41*PS025C Hi TURB EX E41-N012C(H21*P034) 1.61-264 6-157 IE41*PSO23A STM PPES L E41-N001A(H21*P016) 1.61-264 8-157 1E41*PS023C STM PRES L E41-N001C(H21*P016) 1.61-264 8-157 1E41*LSO92A SUPR POOL LVL E41-N015A 1.61-263 27-135 1E41*LSO92B SUPR POOL LVL E41-N015B 1.61-263 27-325 1E41*LSO93A COND STRG TK-30 LVL E41-N002 1.61-263 YARD 1E41*LSO938 COND STRG TK-30 LVL E41-N003 1.61-263 YARD 1E41*TE56A HPCI EQUlP AREA T E41-NO30A 70-193 1E41*TE56B HPCI EQUIP AREA T E41-NO308 68-196 VV TURB STOP & LVL SW 1.61-264 1E41*MOV043-LS6 HPCI STM TO TURBINE E41-F001 1.61-264 17-184 1E41*MOV043-LS8 HPCI SIM TO TURBINE E41-F001 1.61-264 24-210 VV RV LL (H21-P005) 1.61-264 78-257 VV RV LL (H21-P005) 1.61-264 78-257 Original Ap ri l 1982

EQUIP LOC (1)

DESCRIPTION ESK CKT NO. PuR SC PWR SC_ LOC EL-AZ IDENTITY 1.61-264 78-79 CKT RV HL & TRIP (H21*P004) CB/63-C12 CKT MAN ISOL ( H11*P601) 1.61-264 1.61-200 63-208 CKT TRIP SOL REACTOR CORE ISOLATION COOLING SYSTEM-RB DIVisl0N 1 1E51*P076 COND VACUUM PUMP 11E5101 1E51N11 1R42*MCCOA2 R.B. EL 112' 8-227 1E51*P077 COND CONDENSATE PUMP 11E5116 1E51N12 1R42*MCCOA2 R.B. EL 112' 8-230 RC PUMP SUCT FROM CON TK VV 11E5108 1E51N01 1R42*MCCOA2 R.B. EL 112'11-217 1E51*MOV031 1E51*MOV032 RCIC PUMP SUCT SUP POOL VV 11E5106 1E51N02 1R42*MCCOA2 R.B. EL 112'24-202 1E51*HOV034 RCIC PUMP DISCHARGE VV 11E5105 1E51N04 1R42*PCCOA1 R.B. EL 40'16-200 RCIC PUMP DISCHARGE VV 11E5104 1E51N05 1R42*MCCOA2 R.B. EL 112'78-193 1E51*MOV035 R.B. EL 112'20-234 1E51*MOV036 HIN FLOW VV 11E5109 1E51N06 1R42*MCCOA2 1E51*MOV037 TEST BYPASS VV 11E5107 1E51N07 1H42*MCCOA1 R.B. EL 40'20-201 LUBE OIL COLL. VV 11E5110 1E51N08 1R42*MCC0A2 R.B. EL 112'15-220 1E51*MOV038 1R24*MCC1128 R.B. EL 112'87-180 1E51*MOV041 RCIC STEAM SUP INBRD ISO VV 65ES102 1E51A01 RCIC STEAM SUP TO TUR Of VV 11E5102 1E51031 1R42"MCCOA2 R.B. EL 112'88-180 1E51*MOV042 1R42*MCCOA2 R.B. EL 112'11-224 1E51*MOV043 RCIC STEAM SUP TO TUR SUP VV 11E5103 1E51N09 1E51*MOV044 RCIC TUR TRIP AND THROTTLE VV 11E5111 1E51N10 1R42*MCCOA2 R.B. EL 112'11-222 RCIC TUR EXH TO SUP POOL VV 11E5113 1E51N14 1R42*MCCOA1 R.B. EL 40'31-217 1E51*MOV045 1R42*MCCOA1 R.B. EL 40'29-226 1E51*MOV046 VAC PP DISCH VV 11E5114 1E51N15 BYPASS VV 11E5112 1E51802 1R42*MCCOA2 R.B. EL 112'86-180 1E51*MOV048 09-245 1E51*A0V081 DRAIN POT DRAIN 1.61-211 COND E-36 DRAIN 1.61-211 09-245 1E51*A0V083 09-245 1E51*LCV095 COND E-38 DRAIN 1.61-211 REAC PRS L E51-N019A(H21*P035) 1.61-207 40-100

, 1E51*PS023A 40-170 ss 1E51*PS023B REAC PRS L E51-N019B(H21*P038) 1.61-208 40-100 m 1E51*PS023C REAC PRS L E51-N019C(H21*P035) 1.61-207 1.61-208 40-170 8

1E51*PSO23D REAC PRS L E51-N019D(H21*P038) 8-205 1E51*PSO25A HI TURB EX E51-N012A(H21*P017) 1.61-207 Hi TURB EX E51-N012B(H21*P037) 1.61-208 8-175 1E51*PS0250 8-205 1E51*PS025C Hi TURB EX E51-N012C(H21*P017) 1.61-207 Hi TURB EX E51-N012D(H21*P037) 1.61-208 8-175 1E51*PS025D 40-100 1E51*PDS022A HI STM D/P E51-N017 (H21*P035) 1.61-207 40-170 1E51*PDS022B Hi SIM D/P E51-N018 (H21*P038) 1.61-208 20-204 1E51*TE053A HI AREA T E51-N601A 1.61-242 HI AREA T E51-N601B 1.61-242 27-219 1E51*TE053B 72-194 1E51*TE054A HI AREA T E51-N602A 1.61-242 69-197 1E51*TE054B HI AREA T E51-N602B 1.61-242 78-079 1821*LT154A Hi WTR LVL 1B21-N080A(H21*P004) 1.61-207 78-257 1821*LT154C HI WTR LVL 1821-N080C(H21*P005) 1.61-208 8-205 1E51*PS02tL LO PP SUCT E51-N006 (H21*P017) 1.61-207 1.61-207 8-205 1E51*PS026A Hi TURB EX E51-N009A(H21*P017) 8-205 1E51*PS026B HI TURB EX E51-N009B(H21*P017) 1.61-207 11-224 IE51*MOVO43 INTLKS 1.61-207 MIN FLOW,,1E51*MOV36 (H21*P017) 1.61-208 8-205 1E51*FS003 24-202 1E51*MOV032 INTLKS 1.61-208 HI AREA TEMP E51-N025A 1.61-240 65-190 1E51*TE55A Original April 1982 O O e

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EQUIP LOC (1)

IDENTITY DESCRIPTION M CKT NO. EdR_.jp PWR SC LOC EL-AZ 1E51*TE55B HI AREA TEMP E51-N025B 1.61-240 64-190 1E51*TE55C HI AREA TEMP E51-N025C 1.61-240 69-190 1E51*TE55D Hi AREA TEMP E51-N025D 1.61-240 72-190 1E51*TE56A' Hi AREA TEMP E51-N026A 1.61-240 65-187 1E51*TE56B HI AREA TEMP E51-N026B 1.61-240 66-194 1E51*TE56C HI AREA TEMP E51-N026C 1.61-240 65-185 1E51*TE56D HI AREA TEMP E51-N026D 1.61-240 66-184 LS RCIC TRIP CKT,H1/H2(C61*P-RSP) 1.61-208 63-208 LS4 RCIC TRI P CKT,TURB STP VV( P-RSP) 1.61-208 63-208 IE51*LS001 H1/H2 (C61*P-RSP) 1.61-208 63-208 CKT RCIC INITI ATE (H11*P602) 1.61-207 CB/63-C13 CKT RCIC TRIP 1.61-207 CKT RCIC TRIP 1.61-211 63-208 RHR SHUTDOWN COOLING SYSTEM ae COOLING MODE DIVISION 1 1E11*P014A RHR PUMP SE1101 1E11A01 1R22*SWG101 EMER SWGR RM EL 25' 8-095 1E11*P014C RHR PUMP SE1103 1E11C01 1R22*SWG103 EMER SWGR RM EL 25' 8-080 1E11*MOV032A RHR SHUTDOWN COOL INJECTION W 6E1103 1E11A04 1R24*MCC1112 R.B. EL 112'15-083 1E11*MOV032C RHR SHUTDOWN COOL INJECTION W 6E1134 1E11C04 1R24*MCC1113 R.B. EL 112'18-064 1E11*MOV033A RHR HX SHELL SIDE INLET W 6E1116 1E11A16 1R24*MCC1119 R.B. EL 40'25-105 1E11*MOV034A RHR HX SHELL SIDE BYPASS VV 6E1120 1E11A17 1R24*MCC1112 R.B. EL 112'28-073 1E11*MOV035A RHR HX SHELL SIDE OUTLET W 6E1115 .1E11A18 1R2t;*MCC1117 R.B. EL 40' 31-087-1E11*HOV036A RHR OUTBOARD W 6E1126 1E11A19 1R24*MCC111X R.B. EL 112'73-092 1E11*MOV037A RHR INBOARD W 6E1125 1E11A07 .1R24*MCC111X R.B. EL 112'73-083 1E11*MOV047 RHR SHUT COOL SUCT INB ISOS W 6E1105 1E11N02 1R24*MCC1118 R.B. EL 112'84-016 4 DIVISION 2

' 1E11*P0148 RHR PUMP SE1102 1E11001 1R22*SWG102 EMER SWGR RM EL 25' 8-265 1E11*P014D RHR PUMP 5E1104 1E11D01 1R22*SWG103 EMER SWGR RM EL 25' 8-280 1E11*MOV032B RHR SHUTDOWN COOL INJI CTION W 6E1104 1E11804 1R24*MCC1122 R.B. EL 112'15-277 1E11*MOV032D RHR SHUTDOWN COOL INJECTION W 6E1131 1E11D04 1R24*MCC1122 .R.B. EL 112'18-296 IE11*MOV0333 RHR HX SHELL SIDE INLET W 6E1138 1E11B16 1R24*MCC1129 R.B. EL 40'25-255 1E11*MOY034B RHR HX SHELL SIDE BYPASS W 6E1141 1E11B17 1R24*MCC1122 R.B. EL 112'28-288 1E11*MOV0358 RHR HX SHELL SIDE OUTLET W 6E1135 1E11B18 1R24*MCC1127 R.B. EL 40'31-278 1E11*MOV036B RHR OUTBOARD W 6E1142 1E11R19 1R24*MCC112Y R.B. EL 112'73-265 1E11*MOV0378 RHR INBOARD VV 6E1143 1E11B07 1R24*MCC112Y R.B. EL 112'73-263 1E11*MOV048 RHR SHUT COOL SUCT OUB I SOL W 11E1101 1E11N05 1R42*MCCOB2 R.B. EL 112'73-096 1E11*MOV050 RHR CROSS HDR SHUTOFF VV 6E1124 1E11N01 1R24*MCC1128 R.B. EL 112'66-281 REACTOR RECIRCULATION SYS FOR RHR SHUTDOWN COOLING MODE DIVISION 1 1831*MOV031A RECIRC PUMP SUCT VV 6B3102 1B31A06 1R24*MCC1112 R.B. EL 112'17-085 1831*MOV032A RECIRC PUMP DISCH W 6B3103 1831A07 1R24*MCC111X R.B. EL 112'14-082 Original Ap ri i 1982

EQUIP LOC (1)

IDENTITY DESCRIPTION [SK CKT NO. PWR SC PWR SC LOC EL-AZ DIVISION 2 1831*MOV031B RECIRC PUMP SUCT VV 6B3107 1B31B06 1R24*MCC1122 R.B. EL 112'24-275 1B31*MOV0326 RECIRC PUMP DISCH VV 683103 1831807 1R24*MCC112Y R.B. EL 112'15-278 RHR LOW PRESSURE COOLANT INJECTION MODE-RB DIVISION 1 1E11*P014A RHR PUMP SE1101 1E11A01 1F22*SWG101 EMER SWCR RM EL 25' 8-095 1E11*P014C RHR PUMP SE1103 1E11C01 1R22*SWG103 EMER SWGR RM EL 25' 8-080 1E11*MOV031A RHR PUMP SUCTION VV 6E1101 1E11A03 1R24*MCC1113 R.B. EL 112'24-085 1E11*MOV031C RHR PUMP SUCTION VV 6E1101 1E11C03 1R24*MCC1113 R.B. EL 112'24-069 1E11*MOV034A RHR HX SHELL BYPASS VV 6E1120 1E11A17 1R24*MCC1112 R.B. EL 112'28-073 1E11*MOV036A RHR OUTBOARD VV 6E1126 1E11A19 1R24*MCC111X R.B. EL 112'73-092 IE11*MOV037A RHR INBOARD VV 6E1125 1E11A07 1R24*MCC111X R.B. EL 112'73-083 DIVISI9N 2 1E11*P0148 RHR PUMP 5E1102 1E11B01 1R22*SWG102 EMER SWGR RM EL 25' 8-265 1E11*P014D RHR PUMP SE1104 1E11001 1R22*SWG103 EMER SWGR RM EL 25' 8-280 1E11*MOV0318 RHR PUMP SUCTION VV 6E1129 1E11803 1R24*MCC1122 R.B. EL 112'24-275 1E11*MOV031D RHR PUMP SUCTION VV 6E1102 1E11003 1R24*MCC1122 R.B. EL 112'24-291 1E11*MOV0348 RHR HX SHELL VV 6E1141 1E11B17 1R24*MCC1122 R.B. EL 112'28-288 RESIDUAL HEAT REMOVAL SYSTEM-RB RHR-CONTAINMENT SPRAY DIVISION 1 d, 1E11*MOV038A CONT. SPRAY VV 6E1109 1E11A08 1R24*MCC1118 R.D. EL 112' 103-090 os 1E11*MOV039A CONT. SPRAY VV 6E1111 1E11A09 1R24*MCC1118 R.B. EL 112' 103-090 1 1E11*MOV040A RHR CORE SPRAY HD VV 6E1110 1E11A10 1R24*MCC1112 R.B. EL 112'72-090 1E11*MOV041A RHR CORE SPRAY HD VV 6E1113 1E11A11 1R24*MCC1111 R.B. EL 40'51-105 1E11*MOV043A RCIC SUCT VV 6E1118 1E11A13 1R24*MCC1119 R.B. EL 40'17-090 1E11*MOV044A CONT. SPRAY VV 6E1117 1E11A14 1R24*MCC1111 R.B. EL 40'17-090 1E11*MOV045A CONT. SPRAY MIN FLOW VV 6E1114 1E11A15 1R24*MCC111X R.B. EL 112'17-090 1E11*MOV049 HPCI STM LN VV 6E1123 1E11N08 1R24*MCC1117 R.B. EL 40'66-180 1E11*MOV051 RHR-RW ISOL VV 11E1103 1E11N06 1R42*MCC0A1 R.B. EL 40'63-285 1E11*MOV081A CONT. SPRAY VV 6E1144 1E11A21 1R24*MCC1113 R.B. EL 112' 81 DIVISION 2 1E11*MOV038B CONT. SPRAY VV 6E1133 1E11B08 1R24*MCC1128 R.B. EL 112' 103-275 1E11*MOV039B CONT. SPRAY VV 6E1111 1E11809 1R24*MCC1128 R.B. EL 112' 103-275 1E11*MOV045B CONT. SPRAY MIN FLOW VV 6E1114 1E11815 1R24*MCC112Y R.B. EL 112'17-275 1E11*MOV040B RHR CORE SPRAY VV 6E1128 1E11810 1R24*MCC1122 R.B. EL 112' 72 1E11*MOV041B RHR CORE SPRAY VV 6E1136 1Ee1811 1R24*MCC1121 R.B. EL 40'40-260 1E11*MOV0438 RCIC SUCT VV 6E1139 1E11813 1R24*MCC1129 R.B. EL 40'17-275 IE11*MOV044B CONT. SPRAY VV 6E1140 1E11014 1R24*MCC1121 R.B. EL 40'17-275 1E11*MOV052 RHR-RW ISOL VV 6E1107 1E11NO3 1R24*MCC1121 R.B. EL 40'73-285 1E11*MOV081B CONT. SPRAY VV 6E1144A 1E11B21 1R24MCC112B R.B. EL 112' 81 Original April 1982 O O O

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EQUIP LOC (1)

IDENTITY DESCRIPTION ESK CKT NO. PWR SC PWR SC LOC EL-AZ RHR CONDENSING MODE-RB 1E41*MOV041 STEAM SUPPLY INBOARD ISOL VLV 6E4102 1E41A01 1R24*MCC1118 R.B. EL 112'66-188 4

RHR INTERLOCKS & TRIPS

, DIVISION 1 40-180 1831*PS023A LP INTLK B31-N018A(M21*P006) 1.61-196 1821*PT158C PRES INTLK B21-N097C(H21*P009) 1.61-272 78-102 1821*PT158A PRES INTLK B21-N097A(H21*P004) 1.61-272 78-079 1821*LT154A LO WTR LVL B21-N080A(H21*P004) 1.61-27 78-079 1821*LT154C LO WTR LVL B21-N080C(H21*P005) 1.61-27 '78-257

}

1821*K83 B21-k83 (H11*P622) 1.61-219 'CB/44-C12 j 1B21*K6A B21-K6A ( H11*P609) 1.61-196 CB/63-C13 j 1821*K6C B21-K6C (H11*P609) 1.61-196 CB/63-C13 i 1E11*PNS031A PHP INTLK 1.61-220 24-085 1E11*PNS031C PMP INTLK 1.61-220 24-069 j 14-082 1E11*PNS032A PMP INTLK 1.61-220 9

. 1E11*PNS032C PMP INTLK 1.61-220 18-064 1E11*PDS001A MINFLOW (H21*P018) 1.61-219 8-075 1821*TL157A LL/HP B21-N091A(H21*P004) 1.61-272 78-079 1E11*PT165A LL/HP E11-N091A(H21*P004) 1.61-219 78-079 1821*LT157C LL/HP B21-N091C(HP21*P004) 1.61-272 78-079 4

DIVISION 2

IB31*PS023C LP INTLK B31-N018B(H21*P022) 1.61-196 40-353 1821*PT158D PRES INTLK B21-N097D(H21*P0010) 1.61-273 78-280 1 1B21*PT158B PRES INTLK B21-N097B(H21*P005) 1.61-273 78-257 IB21*LT1548 LO WTR LVL B21-N080B(H21*P004) 1.61-155 78-079

[$ 1.61-155 78-257 i 1821*LT154D LO NTR LVL B21-N080D(H21*P005) CB/44-C12 IB21*K84 B21-K84 ( H11*P623) 1.61-196

' 1821*K6B B21-K68 (H11*P611) 1.61-193 CB/63-C13 1821*K6D B21-k6D (H11*P611) 1.61-193 CB/63-C13 1E11*PNS031B PHP INTLK 1.61-233 24-275 1E11*PNS031D PMP INTLK 1.61-223 24-291 1E11*PNS032B PMP INTLK 1.61-223 15-278 1E11*PNS032D PMP lNTLK 1.61-223 18-296 l 1E11*PDSOO1B MINFLOW (H21*P021) 1.61-219 8-287 i CKT MAN INITIATE 1.61-219 1E11*PT165B LL/HP E11-N091B(H21*P005) 1.61-219 78-257 STANDBY LIQUID CONTROL SYSTEM J

1 DIVISION 1

! 1C41*P024A SLC LIQUID CONT PUMP 6C4101 1C41A01 1R24*MCC1113 R.B. EL 112' 112-168 i

i l

i4 Original i April 1983 i

I l

1 1

EQUIP LOC (1)

ESK CKT N0 1 PWR SC PWR SC LOC EL-AT IDENTITY DESCRIPTION DIVISION 2 112-166 1C41*P024B SLC LIQUID CONT PUMP 6C4101 1R24*MCC1123 R.B. EL 112' CO2 FIRE PROT CKT, DIESEL RM 11M4304 1R42*PNLA2, CONTROL BUILDING EL 63' INTER CKT B2 & C1 CO2 FIRE PROT CKT, BTY RM 11M4303 1R42*PNLA2, CONTROL BUILDING EL 63' INTER CKT B2 & C1 CO2 FIRE PROT CKT, EMER-SWC RM 11M4305 1R42*PNLA2, CONTROL BUILDING EL 63' INTER CKT B2 & C1 CO2 FIRE PRO 1 CKT, RELAY RM 11M4306 1R42*PNLA1 EMER SWGR RM EL 25' C^NTROL BUILDING EL 25' INTER CKT SERVICE WATER SYSTEM-PH/RB DIVISION 1 1R22*SWG101 EMER SWGR RM EL 25' SCREENWELL EL 20' IP41*P003A SERVICE WATER PUMP 5P4101 1P41A01 6P4101 1 Pt41 A02 1R21*MCC1110 4 SCRW EL 20'-6" SCREENWELL EL 20' IP41*MOV031A SWP DISCH VV 1 P241 AOS 1R24*MCC1110 SCRW EL 20'-6" SCREENWELL EL 20' 1P41*MOV032A SW HEADER ISOL W 6Pl103 4

6P4108 1P41A03 1R24*MCC1119 R.B. EL 40'30-030 1P41*MOV033A SW CROSS TIE VV 1 Pl41 CO3 iR2f*MCC1119 R.B. EL 40' 31-Ol0 4

1P41*MOV033C SW CROSS TIE VV 6 Pl4109 4 6P4110 1 Pl41 A08 1R245MCC1112 R.B. EL 112'27-091 1P41*MOV034A RHR HX DISCH VV 1Pl41AC6 1R24*MCC1140 SCRW EL 20'-6" SCREENWELL EL 20' 1P41*HOV035A TBCLCH ISOL W 6P4104 IPf1*MOV036A VENT CHILL ISOL W 6P4105 1P41A07 1R24*MCC1116 DIESEL GEN RM LL 22'12-046 4

6P4107 1P41A09 1R24*MCC1112 R.D. EL 112'23-290 1P41*MOV037A RBCLCW HX OUTLET W 1P41A04 1R24*MCC1119 R.B. EL 40'34-046 1P41*MOV039A ULT COOLING ORN %V 6 Pl4 102 6P4113 iP41A12 1R24*MCC1119 R.D. EL 40' f 15-040 1P41*MOV042A SW TO FUEL POOL VV 1P41A24 1R35*PNLR1 RELAY RM EL I4 4' CB/27-L13 1P41*A0V016A EMER DIESEL HX OUTLET VV 6P4123 DIVISION 2 SCREENWELL EL 20' N

i 1P41*P0038 SERVICE WATER PUMP 5P4102 1P41801 1R22*SWG102 EMER SWGR RM EL 25' 6P4119 1P41802 1R24*MCC1120 SCRW EL 20'-6" SCREENWELL EL 20' C) 1 Pf41*MOV031B SWP DISCH VV SCREENWELL EL 20'

' 1Pl41*MOV032B SW HEADER ISOL W 6P4121 1 P141805 1R24*MCC1120 SCRW EL 20'-6" 1 P41*MOV03 38 SW CROSS T IE W 6P4108 1 Pl41BG 3 1R24*McC1129 R.B. EL 40'30-030 1P41*MOV033D 5W CROSS TlE VV 6 Pl4109 1P41CO3 1R24*MCC1129 R.B. EL 40'31-010 4

1 P41*MOV0314B RHR HX DISCH VV 6 Pl4118 1F41008 1R24*MCC1128 R.D. EL 112'27-268 6P4120 1P41606 1R2f4*MCC1120 SCRW EL 20'-6" SCREENWELL EL 20' 1P41*MOV0350 TBCLCW ISOL VV 1Pf1807 1R24*MCC1126 DIESEL GEN RM EL 22'12-046 1Pt1*MOV036B VENT CHILL ISOL VV 6 Pt4105 4 1P41809 1R214*MCC1128 R.B. EL 112'23-294 4

1P41*MOV0370 RBCLCW HX OUTLET VV 6P4122 6P4102 1 Pl41 B04 1R24*MCC1129 R.B. EL 40'34-046 IP41*MOV039B ULT COOLING DRN VV 1P41B12 1R24*MCC1129 R.B. EL 40'15-040 1 Pt4 1*MOV042B SW TO FUEL POOL W 6P4113 6 P4114 IP41N01 1R24*MCC1127 R.B. EL 40'12-046 1P41*MOV043 FUEL POOL DRN VV 1R35*PNLB1 RELAY RM EL 4l' CD/27-C13 1Pl1*A0V168 4 EMER DIESEL HX OUTLET W 6P4123 1 Pf4 18214 4 DIVISION 3 1P41*P003C SERVICE WATER PUMP SP4103 1P41C01 1R22*SWG103 EMER SWGR RM EL 25' SCREENWELL EL ?O' I Pl41

P00 3 D SERVICE WATER PUMP SP4104 1Pl1001 4 1R22*SWG103 EMER SWGR RM EL 25' SCREENWELL EL 20' 1P41*MOV031C SWP DISCH W 6P4101 1Pl1CO2 4 1R24*MCC1133 EMER SWGR RM EL 25' SCREENWELL EL 20' 1P41*MOV031D SWP DISCH VV 6P4117 IP41D02 1R24*MCC1133 EMER SWGR RM EL 25' SCREENWELL EL 20' 1P!41*MOV036C VENT CHILL ISOL VV 6P4106 1P41C07 1R24*MCC1134 DIESEL GEN RM EL 22'12-046 6P41214 1P41C24 1R35*PNLO1 RELAY RM EL 25' CB/27-C13 1P41*A0V016C EMER DIESEL HX OUTLET W Original Ap ri i 1983 O O e

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EQUIP LOC (1)

IDENTITY DESCRIPTION S f_SA CKT NO. PWR SC PWR SC LOQ EL-AZ EMERG SW TO FUEL POOL DIVISION 1 1G33*MOV033 RV DISCH 6G3308 1G33N12 1R24*MCC1113 EMER SWGR RM EL 25' 121-190 DIVISION 2 1G33*MOV034 RV D I SCH W 11G3301 1G33N13 1R42*MCCOB2 R.B. EL 112' 121-190 REACTOR WATER CLEAN-UP SYSTEM DIVISION 1 1G41*MOV032A SERVICE WTR INLET VV 6G4103 1G41A04 1R24*MCC1114 EMER SWGR RM EL 25' 162-147 DIVISION 2 1G41*MOV032B SERVICE WTR INLET W 6G4103 1G41B04 1R24*MCC1124 R.B. EL 150' 162-149 RBCLCW SYSTEM-RB DIVISION 1 IP42*P005A RBCLCW COOLING WATER PUMP 6P4201 1P42A01 1R24*MCC1112 R.B. EL 112' 150-NW 1P42*MOV042A RBCLCW HX INLET VV 6P4214 1P42A10 1R24*MCC1112 R.B. EL 112'30-349 DIVISION 2 1P42*P005B RBCLCW COOLING WATER PUMP 6P4202 1P42801 1R24*MCC1122 R.B. EL 112'30-352 1P42*MOV0428 RBCLCW HX INLET W 6P4218 IP42B10 1R24*MCC1128 R.B. EL 112' 150-NW DIVISION 3

{ 1P42*P005C RBCLCW COOLING WATER PUMP 6P4203 1P42C01 1R24*MCC1131 R.R. E'. 63' 150-NE T EMERGENCY GENERATOR-EGR DIVISION 1 1R43*G101 EDG G101 PROT-GEN DIFF CKT 8R4301 1R43A03 DG RM/22-L15 1R43*G101 VR CT G-101 PROT 8R4301 1R43A04 DG RM/22-L15-1R43*G101 EMER DG 51/40/32 PROT 8R4301 1R43A05 DG RM/22-L15 1R43*G101 EMER DG SON GND PROT 8R4301 1R43A28 DG RM/22-L15 1R43*G101 CURRENT TEST BCK AND RESIS BOX 8R4301 1R43A27 DG RM/22-L15 1R43*G101 COVERNOR HYDRAULIC ACTUATOR 11R4302 1R43A23 1R42*PNLA1 EMER SWGR RM EL 25' DG RM/22-L15 1R43*G101 EG-A CONT BOX AND MOT OP POT 8R4301 1R43A06 EMER SWGR RM EL 25' DG RM/22-L15 1R43*G101 VR CT G-101 PROT 8R4301 1R43A25 EMER SWGR RM EL 25' DG RM/22-L15 1R43*G101 VOLT REGULATOR 8R4305 1R43A26 EMER SWGR RM EL 25' DG RM/22-L15 1R43*C101 START CIRCUlT 11R4301 1R43A12 1R42*PNLA1 EMER SWGR RM EL 25'- DG RM/22-L15 1R43*G101 START CIRCulT 11R4301 1R43A22 1 R42* PN LA1 EMER SWCR RM EL 25' DG RM/22-L15 1R43*G101 START CIRCULI 11R4302 1R43A23 1 R42* FN LA1 EMER SWGR RM EL 25' DG RM/22-L15 DIVISION 2 1R43*G102 EDG G102 PROT-GEN DIFF CKT 8R4302 1R43803 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 EMER DG 51/40/32 PROT 8R4302 1R43805 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 EMERG DG SON GND PROT 8R4302 1R43B28 EMER SWGR RM EL 25' DG RM/22-C15 O ri g i na l Ap ri l 1983

EQUIP LOC (1)

IDE*4TITY DESCRIPTION ESK CKT NO. PWR SC PWR SC LOC EL-AZ 1R43*G102 CURRENT TEST BCK AND RESIS BOX 8R4302 1R43B27 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 GOVERNOR HYDRAULIC ACTUATOR 11R4304 1R43B23 1R42*PNLB1 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 EG-A CONT BOX AND MOT OP POT 8R4302 1R43806 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 VR CT G-102 PROT 8R4302 1R43B25 EMER SWGR RH EL 25' DG RM/22-C15 1843*G102 VOLT REGULATOR BR4306 1R43B26 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 VR CT G-102 PROT 8R4302 1R43804 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 START CIRCUlT 11R4303 1R43812 1R42*PNLB1 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 START CIRCulT 11R4303 1R43B22 1R42*PNLB1 EMER SWGR RM EL 25' DG RM/22-C15 1R43*G102 START CIRCUIT 11R4304 1R43823 1R42*PNLB1 EMER SWGR RM EL 25' DG RM/22-C15 DIVISION 3 1R43*G103 EDG G103 PROT-GEN DIFF CKT 8R4303 1R43CO3 DG RM/22-L15 1R43*G103 EMER DG 51/40/32 PROT 8R4303 1R43C05 DG RM/22-L15 1R43*G103 EMER DG SON GND PROT 8R4303 1R43C28 DG RM/22-L15 1R43*G103 CURRENT TEST BCK AND RESIS BOX 8R4303 1R43C27 DG RM/22-L15 1R43*G103 COVERNOR HYDRAULIC ACTUATOR 11R4306 1R43C23 1R42*PNLCl EMER SWGR RM EL 25' DG RM/22-L15 1R43*G103 EG-A CONT BOX AND MOT OP POT 8R4303 1R43C06 EMER SWGR RM EL 25' DG RM/22-L15 1R43*C103 VR CT G-103 PROT 8R4303 1R43C25 EMER SWGR RM EL 25' DG RM/22-L15 1R43*G103 VOLT REGULATOR 8R4307 1R43C26 EMER SWGR RM EL 25' DG RM/22-L15 1R43*G103 VR CT G-103 PROT 8R4303 1R43C04 EMER SWCR RM EL 25' DG RM/22-L15 1R43*G103 START CIRCulT 11R4305 1R43C12 1R42*PNLC1 EMER SWGR RM EL 25' DG RM/22-L15 1R43*G103 START CIRCulT 11R4305 1R43C22 1R42*PNLC1 EMER %WGR RM EL 25' DG RM/22-L15 1R43*G103 START CIRCulT 11R4306 1R43C23 1R42*PNLC1 EMER SWGR RM EL 25' DG RM/22-L15 DIESEL FUEL TRANSFER SYS-EGB DIVISION 1 E 1R43*P201A EG FUEL OIL TRANSFER PUMP 6R4304 1R43A09 1R24*MCC1116 DIESEL GEN RM EL 22' YARD ev 1R43*P202A EG FUEL OIL TRANSFER PUMP 6R4304 1R43A10 1R24*MCC1116 DIESEL GEN RM EL 22' YARD i

DIVISION 2 1R43*P201B IG FUEL Ott TRANSFER PUMP 6R4305 1R43809 1R24*MCC1126 DIESEL GEN RM EL 22' YARD 1R43*P2020 EG FUEL OIL TRANSFER PUMP 6R4305 1R43B10 1R24*MCC1126 []IESEL GEN RM EL 22' YARD DIVISION 3 1R43*P201C EG FUEL OIL TRANSFER PUMP 6R4306 1R43C09 1R24*MCC1134 DIESEL CEN RM EL 22' YARD 1R43*P202C EG FUEL OIL TRANSFER PUMP 6R4306 1R43C10 1H24*MCC1134 DIESEL GEN RM EL 22' YARD HVAC SYSTEMS CRAC/RBSVS CHILL WATER SYSTEM-CB DIVISION 1 1M50*P137A CHILLED WATER PUMP 6M5001 1M50A08 1R24*MCC1116 DIESEL GEN RM EL 22' CB/63-L12 1M50*P139A COND WATER PUMP 6M5003 1M50A10 1R24*MCC1116 DIESEL GEN RM EL 22' CD/63-L12 1M50*P231A LUBE OIL PUMP 6M5011 1M50A14 1R24*MCC1116 DIESEL GEN RM EL 22' CB/63-C16 1M50*WC003A WATER CHILLER 5M5001 1M50A01 1R22*SWC101 EMER SWGR RM EL 25' CB/63-L12 1M50*WC003A CHILLER CONTROLS 5M5001A 1M50A03 1R35*PNLR1 RELAY RM EL 44' CD/63-L12 1M50*MOV031A RETURN VV 6M5005 1M50A04 1R24*MCC1116 DIESEL GEN RM EL 22' CB/71-L13 Original April 1983 O O O

. . - . _ - . . _. . ....._.._._s.._.. _ . . , . ._ _ _ . . .__.__. . - _ _ . _ _ . . . _ . . _ . . . - _.- . . _ _ . . _ _ _ . _ . . _ _ _ _ _

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EQUIP LOC (1)

IDEPTITY DESCRIPTION ES!' , CKT NO. PWR SC PWR SC LOC EL-AZ

$ IM50*MOV032A SUPPLY W 6M5006 1M50A05- 1R24*MCC1116 DIESEL CEN RM EL 22' CB/75-L13 ;

1 1M50*MOV033A RET X-0VER W 6M5007 1M50A06 1R24*MCC1116 DIESEL GEN RM EL 22' CB/75-L13 2 1M50*MOV034A SUP X-OVER W 6M5008 1M50A07 1R24*MCC1116 DIESEL GEN RM EL 22' CB/75-L13 2 1M50*A0V068A ISOL BYPASS W 6M5009 1M50A12 1R35*PNLR1 RELAY RM EL'44' CB/71-L12 j 1M50*A0V069A ISOL BYPASS W 6M5010 1M50A13 1R35'PNLR1 RELAY RM EL 44' CB/75-L12 DIVISION 2 a 1M50*P137B CHILLED WATER PUMP 6M5001 1M50B08 1R24*MCC1126 DIESEL CEN RM EL 22' CB/63-L13 1M50*P139B COND WATER PUMP 6M5003 1M50810 1R24*MCC1126 DIESEL GEN RM EL 22' CB/63-L13 l

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EQUIP LOC (1)

DESCRIPTION RK CKT N0 1 PWR SC PWR SC LOC EL-AZ 10_ENTeTY 1M50*P2318 LUBE OIL PUMP 6M5011 1M50B14 1R24*MCC1126 DIESEL GEN RM EL 22' CB/63-L13 1M50*WC003B WATER CHILLER SM5002 1M50801 1R22*SWG102 EMER SWGR RM EL 25' CD/63-L13 1M50*WC003B CHILLER CONTROLS SM5002A 1M50B03 1R35*PNLB1 EMER SWGR RM EL 25' CB/63-L13 1H50*M0v0318 RETURN VV 6M5005 1M50B04 1R24*MCC1126 DIESEL GEN RM EL 22' CB/71-L13 1H50*MOV032B SUPPLY VV 6M5006 1M50B05 1R24*MCC1126 DIESEL GEN RM EL 22' CB/75-L13 1M50*MOVO338 RET X-0VER VV 6M5007 1M50B06 1H24*MCC1126 DIESEL GEN RM EL 22' CB/75-L13 1M50*MOV034B SUP X-OVER VV 6M5008 1M50B07 1R24*MCC1126 DIESEL GEN RM EL 22' CB/71-L13 1M50*A0V068B ISOL BYPASS W 6M5009 1M50B12 1R35*PNLB1 RELAY RM EL 44' CB/71-L13 1M50*AOV069B ISOL BYPASS VV 6M5010 1M50813 1R35*PNLB1 RELAY RM EL 44' CB/75-L13 DIVISION 3 1M50*P1l0A 4 CONO WATER PUMP 6M5004 IM50A11 1R24*MCC1134 DIESEL GEN RM EL 22' CB/63-L12 1M50*P1400 COND WATER PUMP 6M5004 1H50C14 1R24*MCC1134 DfESEL GEN RM EL 22' CD/63-L13 1M50*P233A LUBE Olt PUMP 6M5012 1M50C14 1R24*MCC1134 DIESEL GEN RM EL 22' CD/63-L15 1M50*P233B LUBE OIL PUMP 6M5012 1M50014 1R24*MCC1134 DIESEL GEN RM EL 22' CD/63-L12 1M50*WC004A WATER CHILLER 5M5003 1M50C01 1R22*SWG103 EMER SWCR RM EL 25' CB/63-L12 1M50*WC0048 WATER CHILLER SM5004 1M50D01 1R22*SWG103 EMER SWGR RM EL 25' CD/63-L13 1M50*WC004A CHILLER CONTROLS SM5003A 1M50CO3 1R35*PNLO1 RELAY RM EL 44' CB/63-L12 1M50*WC004B CHILLER CONTROLS SM5004A 1M50003 1R35*P*" 01 RELAY RM EL 4t' 4 CB/63-L13 RBSVS SYSTEM-RB DIVISION 1 1T46*UC002A UNIT COOLER 6T4689 !146A13 1R24*MCC1118 R.B. EL 112' 8-332 1T46*UC003A UNIT COOLER 6T4620 IT46A14 1R24*MCC1118 R.B. EL 112' 8-081 1T46*UC004A REFUEL LVL UC 6T4621 IT46A15 1R24*MCC1112 R.B. EL 112' 218-060 1T46*UC005A REFUEL LVL UC 6T4622 IT46A16 1R24*MCC111? R.B. EL 112' 218-323 6T4625 IT46A23 1R24*MCC1118 EL 112' 112-080 b

1T46*UCO20A 1T46*UCO21A RB MCC RM'A' UC MG RM 111 UC 6T4626 IT46A33 1R24*MCC111W R.B.

R.B. EL 150' 150-022 i CKTIT46A19 RBSVS/CRAC ACC SIGNAL 11T4601 1T46A19 CB/48-C14 CKTIT46A18 RBVS INITIAT SIGNAL 11T4602 CB/48-C14 DIVISION 2 1T46*UC0028 UNIT COOLER 6T4619 1T46B13 1R24*MCC1128 R.B. EL 112'40-275 1T46'UC0038 UNIT COOLER 6T4620 1T46B14 1R24*MCC1128 R.B. EL 112'40-085 1T46*UC0048 REFUEL LVL UC 6T4621 1T46B15 1R24*MCC1122 R.B. EL 112' 218-143 1T46*UC0058 REFUEL LVL UC 6T4622 1T46B16 1R24*MCC1122 R.B. EL 112' 218-240 1146*UCO200 RB MCC RM'B' UC 6T4625 1T46S23 1R24*MCC1128 R.B. EL 112' 112-227 1T46*UCO21B MG RM 112 UC 6T4626 1T46B33 1R24*MCC112W R.D. EL 40' 150-340 CKT1T46B19 RBSVS/CRAC ACC SIGNAL 11T4601 1T46B19 CB/48-C14 CKTIT46B18 RBSVS INITIAT SIGNAL 11T4603 CB/48-C14 DIVISION 3 1T46*UCO228 MC RM 113B UC 6T4627 1T46834 1R24*MCC1131 R.B EL 160' 161-340 1T46*UCO22A MG RM 113A UC 6T4627 1T46834 1R24*MCC1131 R.B EL 160' 161-022 O rig ina l April 1983 9 O O

.. . . = . . . .. _- .

O /% m EQUIP LOC (1)

IDENTITY DESCRIPTION EjK CKT NO. PWR SC PWR SC LOC EL-AZ CKT1T46N04 RBSVS INITIAT SIGNAL 11T4604 ESWG ROOM /

25-K13 RELAY /SWGR ROOM VENT SYSTEM-CB DIVISION 1 1X41*ACUO14A CHILL WT COOL 6X4125 1X41A01 1R24*MCC1116 DIESEL GEN RM EL 22' HVAC/44-C14 1X41* MOD 035A CHILL WT COOL 6X4125 1X41A01 1R24*MCC1116 DIESEL GEN RM EL 22' HVAC/53-C12 1X41*FN029A RELAY RM EXHAUST FAN 6X4121 1X41A02 1R24*MCC1116 DIESEL GEN RM EL 22' HVAC/44-C13 DIVISION 2 1X41*ACUO14B CHILL WT COOL 6X4125 IX41801 1R24*MCC1126 DIESEL GEN RM EL 22' HVAC/44-C13 1X41* MOD 035B CHILL WT COOL 6X4125 IX41B01 1R24*MCC1126 DIESEL GEN RM EL 22' HVAC/53-C12 IX41*FN029B RELAY RM EXHAUST FAN 6X4121 1X41B02 1R24*MCC1126 DaESEL GEN RM EL 22' HVAC/44-C13 CHILLER EQUIP RM VENT SYSTEM-CB DIVISION 1 1X41*FN039A RBSV CHILL EQUlP RM FAN 6X4126 1X41A19 1R24*HCC1116 DlESEL GEN RM EL 22' HVAC/63-C39 1X41* MOD 031A RBSV INTAKE DAMPER 6X4126 1X41A19 1R24*MCC1116 DIESEL GEN RM EL 22' HVAC/63-L16 1X41*M00032A RBSV EXHAUST DAMPER 6X4126 1X41A19 1R24*MCC1116 DIESEL GEN RM EL 22' HVAC/63-flo DIVISION 2 1X41tFN0398 RBSV CHILL EQUIP RM FAN 6X4127 1X41B19 1R24*MCC1126 DIESEL GEN RM EL 22' HVAC/63-C15 1X41* MOD 031B RBSV INTAKE DAMPER 6X4127 1X41B19 1R24*MCC1126 DIESEL GEN RM EL 22' HVAC/63-L16 1X41* MOD 032B RBSV EXHAUST DAMPER 6X4127 1X41B19 1R24*MCC1126 DIESEL GEN RM EL 22' HVAC/63-L16 i BATTERY ROOM VENT SYSTEM-CB N

DIVISION 1 f 1X41*FN072A BTY RM VENT FAN 6X4128 1X41A03 1R24*MCC1115 EMER SWGR RM EL 25' CB/30-K16 1X41* MOD 039A BTY RM DISCilARGE DAMPfR 6X4128 1X41A03 1R24*MCC1115 EMER SWGR RM EL 25' CB/27-K16 IX41* MOD 040A BTY RM EXHAUST DAMPEH 6X4128 1X41A03 1R24*MCC1115 EMER SWGR RM EL 25' CD/30-K16 1X41* MOD 041A BTY RM EXHAUST DAMPER 6X4128 1X41A03 1R24*MCC1115 EMER SWGR RM EL 25' CB/26-K16 DIVISloN 2 1X41*FN072B BTY RM VENT FAN 6X4129 1X41803 1R24*MCC1125 EMER SWGR RM EL 25' CB/30-C16 1X41* MOD 039B BTY RM DISCHARGE DAMPER 6X4129 1X41B03 1R24*MCC1125 EMER SWGR RM EL 25' CB/29-C16 1X41* MOD 040B BTY RM EXllAUST DAMPER 6X4129 1X41803 1R24*MCC1125 EMER SWGR RM EL 25' CB/30-C16 1X41* MOD 0418 BTY RM EXHAUST DAMPER 6X4129 1X41803 1R24*MCC1125 EMER SWGR RM EL 25' CB/26-C16 DIVISION 3 1X41*FN072C BTY RM VENT FAN 6X4130 1Xh1003 1R24*MCC1133 EMER SWGR RM EL 25' CB/39-K16 1X41* MOD 039C BTY RM DISCHARGE DAMPER 6X4130 1X41C03 1R24*MCC1133 EMER SWGR RM EL 25' CB/37-K16 1X41* MOD 040C BTY RM EXHAUST DAMPER 6X4130 1X41CO3 1R24*MCC1133 EMER SWGR RM EL 25' CD/41-C16 1X41* MOD 041C BTY RM EXHAUST DAMPER 6X4130 1X41CO3 1R24*MCC1133 EMER SWGR RM EL 25' CB/35-K16 Original April 1983'

EQUIP LOC (1)

IDENTITY DESCRIPTION [.SK CKT NO. PWR SC FWR SC LO_C EL-AZ EMERGENCY GEN ROOM VENT SYSTEM-EGB DIVISION 1 1X61*FN025A FILTER BOOSTER FAN 6X6102 1X61A02 1R24*MCC1116 DIESEL GEN RM EL 22' EGB/63-C12 1X60*FN028A EMER VENT FAN 6X6002 1X60A02 1R24*MCC1116 DIESEL GEN RM EL 22' ECB/22-L15 IX60* MOD 31A DAMPER 6X6002 IX60A02 1R24*MCC1116 DIESEL GEN RM EL 22' ECB/38-L16 1X60* MOD 32A DAMPER 6X6002 1X60A02 1R24*MCC1116 DIESEL GEN RM EL 22' EGB/34-L12 1X60* MOD 032A DAMPER DfVISION 2 1X60*FN025B FILTER BOOSTER FAN 6X6102 1X60CO2 1R24*MCC1126 DIESEL GEN RM EL 22' EGB/63-C12 1X60*FN028B EMER VENT FAN 6X6003 1X60B02 1R24*MCC1126 DIESEL GEN RM EL 22' ECB/22-L15 IX60* MOD 318 DAMPER 6X6003 1X60BC2 1R24*HCC1126 DIESEL GEN RM EL 22' EGB/38-L16 1X60*M0032B DAMPER 6X6003 1X60B02 1R24*MCC1126 DIESEL GEN RM EL 22' EGB/CA12 1X60* MOD 0328 DAMPER DIVISION 3 1X61*FN028C EMER VENT FAN 6X6004 1X60CO2 1R24*MCC1134 DIESEL GEN RM EL 22' EDG/22-L15 1X60* MOD 31C DAMPER 'X6004 1X60CO2 1R24*MCC1134 DIESEL GEN RM EL 22' EDG/38-CA16 1X60* MOD 32C DAMPER JX6004 1X60CO2 1R24*MCC1134 DIESEL GEN RM EL 22' EDG/34-CA12 1X60* MOD 032C DAMPER SCREENWELL PUMP HOUSE VENT DIVISION 1 PP HS FAN 6X4118 1X41A15 1R24*MCC1110 SCREENWELL 1X41*FN068A EL 20' b

es i DIVISION 2 PP HS FAN 6A4119 1X41B15 1R24*MCC1120 SCREENWELL 1X41*FN0688 EL 20' CONTROL ROOM AIR CONDITIONING SYSTEM-CB DIVISION 1 1X61*MOV031A CRAC ISOL VV 6X6104 1X61A05 1R24*MCC1115 EMER SWGR RM EL 25' CB/78-C12 1X61*MOV032A CRAC ISOL VV 6X6110 1X61A09 1R24*MCC1115 EMER SWGR RM EL 25' CB/67-C16 1X61*A0V36A CRAC NORM AIR INTAKE W 6X6106 1X61A06 1R35*PNLR1 RFLAY ROOM EL 44' CB/66-C16 1X61*A0V88A CRAC ISOL VV 6X6108 1X61A03 1R35*PNLR1 RELAY ROOM EL 44' CB/73-C16 1X61*ACUOO7A CRAC UNIT 6X6101 IX61A01 1R24*MCC1116 DIESEL GEN RM EL 22' CB/71-C13 1X61* MOD 34A CRAC UNIT DAMPER 6X6101 1X61A01 1R24*MCC1116 DIESEL GEN RM EL 22' CD/77-C16 1X61*TCV021A CRAC-COOLING C0ll VV 13X6101 1X61A10 CB/71-C13 CKT1X61A0T CRAC EMER INIT SIGN ( PNL VX- ) 11X6101 1X61A07 1R42*PNLA2 CD/44-C12 1X61* TIC 021A CRAC ACUO7A COOLING CONTROL 13X6101 1X61A10 CB/63-K12 1X61*TE021A CRAC TEMP ELEMENT 13X6101 1X61A10 CB/67-12K 1X61*A0V039A ISOL DAMPERS 6X6109 1X61A04 1R35*PNLR1 RELAY RM EL 44' CB/77-C16 IX61*FN025A FILTER BOOSTER FAN 6X6102 1X61A02 1R24*MCC1116 DIESEL GEN RM EL 22' CB/63-C12 1X61* MOD 033A FILTER BOOSTER FAN DAMPER 6X6102 1X61A02 1R24*MCC1116 DIESEL CEN RM EL 22' CB/77-C12 O ri g i na l Aprii 1983 l

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EQUIP LOC (1)

IDENTITY DESCRIPTION E.SK CKT NO. PWR SC PWR SC LOC EL-AZ DIVISION 2 1X61*MOV031B CRAC ISOL VV 6X6105 1X61805 1R24*MCC1125 EMER SWGR RM EL 25' CB/78-C12 1X61*MOV032B CHAC ISOL VV 6X6111 1X61809 1R24*MCC1125 EMER SWGR RM EL 25' CB/70-C16 1X61*A0V36B CRAC NORM AIR INTAKE W 6X6106 1X61B06 1R35"PNLB1 RELAY ROOM EL 44' CB/70-C16 1X61*A0V38B CRAC ISOL VV 6X6108 1X61803 1R35"PNLB1 RELAY ROOM EL 44' CD/73-C16 1X61*ACUO78 CRAC UNIT 6X6101 1X61801 1R24*MCC1126 DIESEL GEN RM EL 22' CB/71-C13 1X61* MOD 34B CRAC UNIT DAMPER 6X6101 1X61801 1R24*MCC1126 DIESEL GEN RM EL 22' CD/77-C16 1X61*TCV021B CRAC-COOLING C0ll VV 13X6102 1X61810 CB/71-C13 CKT1X61807 CRAC EMER INIT SIGN ( PNL VX1) 11X6102 1X61807 1R42*PNLB2 CB/44-C12 IX61*TICO21B CRAC ACU708 COOLING CONTROL 13X6102 1X61810 CB/63-K12 IX61*TE021B CRAC TEMP ELEMENT 13X6101 1X61B10 CB/67-K12 1X61*A0V0398 ISOL DAMPERS 6X6109 1X61804 1R35"PNLB1 RELAY RM EL 44' 1X61*FN025B FILTER BOOSTER FAN 6X6102 1X61B02 1R24*MCC1126 DIESEL CEN RM EL 22' CB/63-C12 IX61* MOD 033B FILTER BOOSTER FAN DAMPER 6X6102 1X61B02 1R24*MCC1126 DIESEL CEN RM EL 22' CB/74-C12 COMPRESSED AIR SYSTEM DIVISION 1 1P50*MOV104 INSTR AIR TO SUPPR CHAMBER W 6P5012 1P50N05 1R24*MCC111Z R.B. EL 78'30-250 1P50*MOV103A INST. NITROGEN OUTBRD ISOL VV 6P5014 1P50A12 1R24*MCC1112 R.B. EL 112'90-250 1P50*MOV105A INST. NITROGEN INBRD ISOL W 6P5016 1P50A13 1R24*MCC1113 R.B. EL 112'75-220 1P50*MOV113A INST. NITROGEN NORMAL SUP VV 6P5018 IP50A14 1R24*MCC1112 H.B. EL 112'90-250 1P50*MOV114A INST. NITROGEN EMERG SUP VV 6P5020 1P50A15 1R24*MCC1118 R.B. EL 112'90-250 1P50*PS113A SERVICE AIR HEADER A NORMAL SUP .61-273 151-170 1P50*PS105A SERVICE AIR HEADER A PRESSURE 1.61-272 151-155 l DIVISION 2 N 1P50*MOV106 INSTR AIR TO SUPPR CHAMBER W 6 P5013 1P50N07 1R24*MCC1129 R.B. EL 40'30-250 y IP50*MOV103B INST. NITROGEN OUTBRD ISOL VV 6P5015 1P50812 1R24*MCC1122 R.B. EL 40'90-070 1P50*MOV105B INST. NITROGEN INBRD ISOL VV 6P5017 1P50813 1R24*MCC1122 R.B. EL 112'89-255 1P50*MOV1138 lNST. NITROGEN NORMAL. SUP W 6P5019 IP5c814 1R24*MCC1123 R.B. EL 112' 151-220 1P50*MOV114B INST. NITROGEN EMERG :. IIP W 6P5015 1P50815 1R24*MCC1123 R.B. EL 112'89-070 4

1P50*PS113B SERVICE AIR HEADER B NORMAL SUP 1.61-273 151-220 1P50*PS105B SERVICE AIR HEADER B PRESSURE 1.61-272 151-220 SWGR MCC PNLS-CR/RB/PH DIVISION 1 1R22*SWG101 4160V-HVN RHR SW CS SWG111 fE1B EL 25' ACB 101-1 EMER BUS NORM SUPPLY >R2209 1R22A01 1R22*SWG101 EMER SWGR RM EL 25' EL 25' ACB 101-2 EMER BUS RES SUPPLY SR2210 1R22A02 1R22*SWG101 EMER SWGR RM EL 25' EL 25' BUS 101 SEQ PROGRAM CKT SW RHR CS HVN SR2217 1R22A03 1R22*SWG101 EMER SWGR RH EL 25' EL 25' BUS 4160 REL & HET CKT CR1205 1R22A04 1R22*SWG101 EMER SWGR RM EL 25' EL 25' DIVISION 2 1R22*SWG102 4160V-HVN RHR SW CS SWG112 FE-1C EMER SWGR RM EL 25' EL 25' ACB 102-1 EMER BUS NORM SUPPLY SR2211 1R22801 1R22*SWG102 EMER SWGR RM EL 25' EL 25' ACB 102-2 EMER BUS RES SUPPLY 5R2212 1R22802 1R22*SWG102 EMER SWGR RM EL 25' EL 25' BUS 102 SEQ PROGRAM CKT SW RHR CS 5R2218 1R22803 1R22*SWG102 EMER SWGR RM EL 25' EL 25' Original Aprii 1983

EQUIP LOC (1)

CMT NO. PWR SC PWR SC LOC EL-AZ IDEN11TY DESCRIPTION E_S K 4160 REL & MET CKT 8R2206 1R22804 1R22*SWG102 EMER SWGR RM EL 25' EL 25' BUS 102 DIVISION 3 EMER SWGR RM EL 25' EL 25' 1R22*SWG103 4160V-HVN RHR 3W SWG113 FE-1B 1R42*PNLC1 EMER BUS NORM SUPPLY SR2213 1R22C01 1R22*SWG103 EMER SWGR RM EL 25' EL 25' ACB 103-1 1R22C02 1R22*SWG103 EMER SWGR RM EL 25' EL 25' ACB 103-2 EMER BUS RES SUPPLY SR2214 PROGRAM CKT SW HVN 5R2219 1R22CO3 1R22*SWG103 EMER SWGR RM EL 25' EL 25' BUS 103 SEQ 1R22C04 1R22*SWG103 EMER SWGR RM EL 25' EL 25' BUS 103 4160 REL & MET CKT BR2207 DIVISION 1 EMER SWGR RM EL ?S' EL 25' FEEDER TO EMERG BUSS 111 5R2303 1R23A01 1R22*SWG101 ACB 101-4 1R22*SWG101 EMER SWGR RM EL 25' EL 25' 1R23*T-101 TRANSFORMER FE-1B EMER SWGR RM EL 25' EL 25' 1R23*SWG111 480V 1R24*MCC1110-9&PNLR1 EMER SWGR RM EL 25' EL 25' 1R24*MCC1111/9 FE-1E 1R23*SWG111 IJB"701 FE-1E 1R23*SWG111 EMER SWGR RM EL 25' EL 25' IJB"703 1R24*MCC1117/4/Y/Z 1R23*SWG111 EMER SWGR RM EL 25' EL 25' 1JB"701/3 FE-1E IJB*300 1R24*MCC1113/8 FE-1E 1R23*SWG111 EMER SWGR RM EL 25' EL 25' IJB*702 DIVISION 2 EMER SWGR RM EL 25' EL 25' FEEDER TO EMERG BUSS 112 SR2304 1R23B01 1R22*SWG102 ACB 102-4 1R22*SWG102 EMER SWGR RM EL 25' EL 25' 1R23*T102 TRANSFORMER FE-1B 480V 1R24*MCC1120-9&PNLB1 EMER SWGR RM EL 25' EL 25' 1R23*SWG112 1R23*SWG112 EMER SWCR RM EL 25' EL 25' IJB*706 1R24*MCC1127/4/X/ FE-1E FE-1E 1R23*SWG112 EMER SWCR RH EL 25' EL 25' 1JB*704 1R24*MCC1121/9 EMER SWGR RM EL 25' EL 25' 1JB*704/6,1R24*MCC112C FE-1E 1R23*SWG112 1JB'301 1R23*SWG112 EMER SWGR RM EL 25' EL 25' IJB*705 1R24*MCC1123/8 FE-1E 8 DIVISION 3 1R22*SWG103 EMER SWGR RM EL 25' EL 25' SR2305 1R23C01

$i ACB 103-5 1R23*SWG113 FEEDER TO EMERG BUS 113 480V 1R24*MCC1131-4&PNLO1 EMER SWGR RM EL 25' EL 25' 1RANSFORMER FE-1B 1R22*SWG103 EMER SWGR RM EL 25' EL 25' 1R23*T103 DIVISION 1 1R23*SWG111 EMER SWGR RH EL 25' SCREENWELL 480V -P41,X41 r'E-1Z 1R24*MCC1110 480V-E11.E21 E51,P41,N11,011,G11 FE-1K 1R23*SWG111 EMER SWGR RM EL 25' R.B. EL 40' 1R24*MCC1111 480V -831,E11,P41,P42,P50,R35, FE-1H 1R23*SWG111 EMER SWGR RM EL 25' R.B. EL 112' 1R24*MCC1112 T46 EMER SWGR RM EL 25' R.B. EL 112' 480V -821,C41,E11,E21,P42,P50, FE-1H 1R23*SWG111 1R24*MCC1113 T46,G33,148 R.B. EL 150' 480 -B21,G41 FE-1K 1R24*MCC111Y EMER SWGR RM EL 25' 1R24*MCC1114 1R23*SWG111 EMER SWGR RM EL 25' EL 25' 1R24*MCC1115 480 -R35,R42,X41,X61,C71,R36 FE-1W DIESEL CEN RM 480 -M50,P41,R35,R43,X41,X60, FE-1X 1R23*SWG111 EMER SWGR RM EL 25' 1R24*MCC1116 X61,D11 R.B. EL 40' 480V -E11,E21,N11,G41 FE-1K 1R23*SWG111 EMER SWGR RM EL 25' 1R24*MCC1117 480V -821, Ell,E41,PSO,T46,T23, FE-1H 1R23*SWG111 EMER SWGR RM EL 25' R.B. EL 112' 1R24*MCC1118 G33,T48 EL 40' 480V -E11,P41,P42 FE-1K 1R23*SWG111 EMER SWGR RM EL 25' R.B.

1R24*MCC1119 1R24*MCC1112 EMER SWGR RM EL 25' R.B. EL 150' 1R24*MCC111W 480V-P41,T46,G11 FE-1AS EL 78' 480V-P42,E32 FE-1K 1R24*SWG111 EMER SWGR RM EL 25' R.B.

1R24*MCC111Y O ri g i na l f April 1983 9 9 e

.. -- . - _ ._ . - . - _-- .~ - . - . . - .- - -~ . . - . . . - - ~ . _ - - . . . . . ~ . . . . - . . . - , _ _ . ., -

I

)

f d i -j j EQUIP LOC (1) ,

IDENTITY DESCRIPTION' fj_K. CKT NO. PWR SC BR SC LOC, EL-AZ --

I' 1R24*MCC111X 480V -B31, E11 FE-1K 1R24*TRS111X R.B. EL 112' R.B. EL 112'6" 1R24*MCC111Z 480V -P50 FE-1K 1R24*MCC111Y R.B. EL 78' R.B. EL 112'6"' '

. 1R24*TRS111X TRANSFER SWITCH FE-1E 1R24*MG113A/111 R.B. EL 150' R.B. EL 150' 1R24*MG111 MOTOR GENERATOR FE-1E 1R23*SWG111 EMER SWGR RM EL 25' R.B. EL 150' 1R24#PNL-111 FE-1E j 1 R24# PNL-113A FE-1E

DIVISION 2*

i 1R24*MCC1120 480V -P41,X41 FE-1Z 1R23*SWG112 EMER SWGR RM EL 25' SCREENWELL 1R24*MCC1121 480V -C61,E11,E21 FE-1M 1R23*SWG112 EMER SWGR RM EL 25' R.B. EL 40' IR21.*MCC11?2 480V -831,C61,E11,P42,P50,T46 FE-1J 1R23*SWG112 EMER SWCR RM EL 25' R.B. EL 112'

1R24*MCC1123 480V -C41,E21,P50, FE-1J 1R23*SWG112 EMER SWGR RM EL 25' R.B. EL 112' i *MCC associated systems with shutdown components i

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I i Original

April 1983 1

I 4

EQUl P LOC ( l )

IDENTITY DESCRIPTION FSK CKT N0 1 PWR SC PWR SC LOC EL-AZ 1R24*MCC1124 480V - C61, G41, D11 FE-1M 1R24*MCC1124 EMER SWGR RM EL 25' R.B. EL 150' 1R24*MCC1125 480V -R35,R42,X41,X61,C71 FE-1W 1R23*SWG-112 EMER SWGR RM EL 25' EMER SWGR ROOM 1R24*MCC1126 480V -M50,P41,R35,R43,X41, X60,X61 FE-1X 1R23*SWG-112 EMER SWGR RM EL 25' DIESEL GEN ROOM 1R24*MCC1127 480V -C61,E11,E21,P41 FE-1M 1R23*SWG-112 EMER SWGR RH EL 25' R.B. EL 40' 1R24*MCC1128 480V -C61, E11, E51, P41, P42,146 FE-1J 1R23*SWG-112 EMER SWGR RM EL 25' R.B. EL 112' 1R24*MCC1129 480V -E11,P41,P50, FE-1M 1R23*SWG-112 EMER SWGR RM EL 25' R.B. EL 40' 1R24*TRS112Y TRANSFER SWITCH FE-1E 1R24*MG113B/ R.B. EL 150' 112 1R24*MCC112W 480V -T46 FE-1AS 1R24*MCC1122 R.B. EL 112' R.B. EL 150' 1R24*MCC112X 480V FE-1M 1R23*SWG-112 R.B. EL150' R.B. EL 78' 1R24*MCC112f 480V - C61,E11 FE-1M 1R24*TRS112Y R.B. CL 112' R.B. EL 112' 1R24*MG112 MOTOR GENERATOR FE-1E 1R23*SWG-112 EMER SWGR RM EL 25' R.B. EL 150' 1R24*PNL-04 480V -C61 FE-1M 1R24*MCC112Y R.B. EL 112' R.B. EL 112' DIVisl0N 3 1R24*MCC1131 480V -P42, T46 FE-1J 1R23*SWG-113 EMER SWGR RM EL 25' R.B. EL 160' 1R24*MCC1133 480V -P41,R35,R42,R43,X41 FE-1W 1R23*SWG-113 EMER SWGR RM EL 25' EMER SWGR ROOM 1R24*MCC1134 480V -M50,P41,R35,R43,X60 FE-1X 1R23*SWG-113 EMER SWGR RM EL 25' DIESEL GEN ROOM 1R24*MG113A MOTOR GENERATOR FE-1E 1R23*SWG-113 EMER SWGR RM EL 25' R.B. EL 150' 1R24*MG1138 MOTOR GENERATOR FE-1E 1R23*SWG-113 EMER SWGR RM EL 25' R.B. EL 150' 1JB*113S FE-1E DIVISION i 1R35*PNL-R1, 120V -B21, C61, E11, M50, P41, P42, FE-1AZ, 1R35A02 1R35*T-R1, EMER SWGR RM EL 25' R2,R3 R24,R43,146,X41 FE-1BA, R2,R3 i FE-1BB E$ 1R35*T-a1 480V/120V XFMR PNL-R1 FE-1W 1R24*MCC1115 EMER SWGR RM EL 25' EMER SWGR RM EL 25' i 1R35*T-R2 TRANSFORMER -PNL-R2 FE-1H 1R24*MCC1112 R.B. EL 112' R.B. Ef. 112' 1R35*T-R3 TRANSFORMER -PNL-R3 FE-1X 1R24*MCC1116 DIESEL GEN RM EL 22' DIESEL GEN ROOM EL 20' DIVISION 2 1R35*PNL-B1 120V -821,C61,E11.M50,P41,P42,R43, FE-1AZ, 1R35802 1R35"T-B1, EMER SWGR RM EL 25' B2,83 146,X41 FL-1BB B2,03 1R35*T-B1 480V/120V XFMR PNL-01 FE-1W 1R24*MCC1125 EMER SWGR RM EL 25' EMER SWGR ROOM EL 25' 1R35*T-B2 TRANSFORMER PNL-B2 FE-1J 1R24*MCC1122 R.B. EL 112' R.B. EL 112' 1R35*T-B3 TRANSFORMER PNL-B3 FE-1X 1R24*MCC1126 DIESEL GEN RM EL 25' DIESEL GEN ROOM DIVISION 3 1R35*T-01 480V/120V XFMR PNL-01 FE-1W 1R24*MCC1133 EMER SWGR RM EL 25' EMER SWGR ROOM EL 25' 1R35*PNL-01, 120V -C61,M50,P41,R43,X41 FE-1BA, 1R35CO2 1R35*T-01,02 EMER SWGR RM EL 25' 02 FE-1BB 1R35*T-02 TRANSFORMER PNL-02 FE-1X 1R24*MCC1134 DIESEL GEN RM EL 22' DIESEL GEN ROOM DIVISION 1 1R42*BC-A1 125DC -1R42*SWG-A1 BAT CH FE-1AT 1R24*MCC1115 EMER SWGR RM EL 25' EMER SWGR ROOM EL-25' 1R42*PNL-A1 125DC -SWG-101&111 DG FE-1AT 1R42*SWG-A1 EMER SWGR RM EL 25' EMER SWGR ROOM 1R42*BA-A1 125DC -1R42*SWG-A1 BAT FE-1AT BATT ROOM 1R42*SWG-A1 125DC -PNL-A1&A2 FE-1AT 1R42*BA-Al BATT ROOM EMER SWGR ROOM EL-25' Original Ap ri l 1983 O O O

c O a

1 IDENTITY DESCRIPTION EQUIP LOC (1)

.E_S K CKT NO. PWR SC PWR SC LOC EL-AZ 1R42*PNL-A2 125DC'-ADS & GE LOGIC FE-1AY 1R42*SWG-Al EMER SWGR RM EL 25' EMER SWGR ROOM 1R42*MCC- 125 VDC MCC FE-1AK 1R42*SWG-A1 EMER SWGR RM EL 25' R.B. EL 40' & 112' OA1,2 1H11*PNL-VC1 125 VDC PNL- FEED 11k4202 1R42*PNL-A2 RELAY RM EL 44' CONTROL ROOM EL-63'

1H11*PNL-VC2 125 VDC PNL- FEED 11R4201 .1R42*PNL-A2 RELAY RM EL 44' CONTROL' ROOM EL-63' j DIVISION 2 1R42*BC-B1 125DC -1R42*SWG-B1 BAT CH FE-1AU 1R24*MCC1125 EMER SWGR RM EL 25' EMER SWGR ROOM 2

1R42*PNL-B1 125DC -SWG 102 & 112 & DG FE-1AU 1R42*SWG-B1 EMER SWGR RM EL 25' EMER SWGR ROOM i 1R42*BA-B1 125DC -1R42*SWG-B1 BAT FE-1AU NA BATT h00M 1R42*SWG-B1 125 DC -PNL-B1 & B2 FE-1AU 1R42*BA-B1 BATT ROOM ENER SWGR ROOM 1R42*PNL-D2 125DC -ADS & CE LOGIC FE-1AY 1R42*SWG-B1 EMER SWGR RM EL 25' EMER SWGR ROOM i

1H11*PNL-VC1 125DC -PNL- FEED 11R1202 4 1 Rf42

PN L-82 RELAY ROOM EL 44' CONTROL ROOM EL -63' 4 1H11*PNL-VC2 125DC -PNL- FEED 11R4?01 1R42*PNL-B2 RELAY ROOM EL 44' CONTROL ROOM EL -63' a DIVISION 3 3 1R42*BC-C1 125DC -1R42*SWGC1 BAT CH FE-1AV 1R24*MCC1133 EMER SWGR RM EL 25' EMER SWGR ROOM 1R42*PNL-C1 125DC -SWG 103 & DG FE-1AV 1R42*SWG-C1 EMER *WGR RM EL 25' EMER SWGR ROOM

!' 1R42*PNL-C4 125DC -SWG 113 FE-1AV 1R42*SWG-C1 EMER 6.iGR RM EL 25' EMER SWGR ROOM f 1R42*BA-C1 125 DC -1R42*SW-C1 BAT FE-1AV NA ' BATT ROOM 1R42*SWG-C1 125DC -PNL-C1 & C4 FE-1AV 1R42*BA-C1 BATT ROOM EMER SWGR ROOM IH11*PNL-VC1 125DC -PNL- FEED 11R4202 1R42*PNL-C1 RELAY ROOM EL 44' CONTROL ROOM EL -63' 1H11*PNL-VC2 125DC -PNL- FEED 11R4201 1R42*PNL-C1 RELAY ROOM EL 44' CONTROL ROOM EL'-63'

] 1R42*MCC- 125DC -C61,E11,E51 FE-1AK TR42*SWG-Al EMER SWGR RM EL 25' R.B. EL 40' & 112' t

OA1,2 4 1R42*MCC- 125DC -C61.E11,E41,G33 FE-1AK 1R42*SWG-B1 EMER SWGR RM.EL 25' R.B. EL 40' & 112' j , 001,2 w

i l

1 l

i i

J (1) THE EQUIPMENT IN THE REACTOR BUILDING IS LOCATED BY ELEVATION ( FT. ) AND AZIMUTH (DECREES): EXAMPLE- 112-230 1.E. REACTOR BUILDING, ELEVATION 112 FT. AND 230 DEGREES. THE EQUIPMENT OUTSIDE THE REACTOR BUILDING IS LOCATED l BY AREA, ELEVATION, LINE AND COLUMN: EXAMPLE-.CB/63-C13 1.E. CONTROL BUILDING, ELEVATION 63 FT., LINE C AND COLUMN 13.

$ 18 of 18 Orig ina l

!l April 1983 i

O O O 1800 JL 1350 225'

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FIG. 4.1-1 45 ARRANGEMENT OF SECONDARY 22.5o CONTAINMENT AREAS SHOREHAM NUCLEAR POWER STATION-UlllT1 k\\\\\N vERLAP SEGMENT CABLE SEPARATION ANALYSIS REPORT O %

I l 0

ESTES:

[I m$HuTDowM T t NT 3. RCic 18 AUTO START . setaUAL RESET.

\ 2. t#R C0u0EN$15G MODE REQUltES #0s-5AFETY

,g Id3TRUMEuf AIR.

& I Pg0TECT10m 3. Im3TRUMEsTATied NOT Inown.

S T AeDSV SYSTEM 4. N - MAmuAt.

I 5. no FotCED C00L00md CAPAalLITY Tuls PATu CONTROL R00 N0wEVEt PLANT Remains SAFE in NOT snuTD0we Olive ST3 TEM C0 EDIT 10s As0 ulLL EVENTDALLY DEPRESSURIZE.

6. ADDITICIAL FLEllSILITY Ell 5TS la inAT PAfils 0F MAmV OPERATIONS MAf SE RETeaCEP.

REACTOR Snuf00st gg LOS$ OF 0FF$lTE POWER AND/0R REACTOR j OFF$1TE POWE2 AVAILABLE AuD REACTOR gg 150 LATED FROM MAIN C0dOEd3E2 A NOT 130 LATED FROM M414 CONDENSER W5 l REACT 0a VissEL V I REACTOR VE3SEL LEVEL AND PRES $dRE LEVEL AND PRE 1$0RE LUSTRUM [NTATICll It5TRUMFeTaf ton #

P > 135 [, P < 135 P < 135 \ P > 135 h l rI v v I REACTOR CORE nlGH PRE 33utE CONTROL COOL DOWN 150LATl08 C00LidG C00LAdi IdJECTION U$ lug n0EMAL (RCIC) (MPCI) EQUIPMENT .

4E i I FEEDmATER EQ I CtelDENSATE

=o ,,, CIRC WATER POOL COOLING MODE SUPP0ti SYSTEM $. ,

Mild STEAM i 8 ConDEn5ER I

r q' 8 RMR I (NOTE 5) PRES 5URE RELIEF

CoaDENSING MODE j SYSTEM (2-4 VALVES

@ u a REQut RED)

I "a ' 1'

= i t , CORE SPEAT . LOW PRES $uRE E (C3) C00LAni leJECil0e I (LPCI)

S

= 1*

RNA RNR LPCI PLUS

$HUTD0ue COOLING POOL COOLING NEAT EXCMANGER

$I M es0DE

, MODE y 5i ins u T

1 EE TENDED C0af C00L'sG FIG. 4.2-IA y SHUTDOWN MODEL PROTECTION SEQUENCE FOR SHUTDOWN SHOREHAM NUCLEAR POWER STATION-UNIT 1 CABLE SEPARATION ANALYSIS REPORT O O O

) ( \ (,%\

N/ %/

PREssutt CORE NPCI RC 4C RCLIEF RNR i

f3 PRAT SYSTEM i !

II LOS C 3 3 EM + II + LOG AC POWER POWE R v4LVES t&LVES SY3D POWit SMTEM VALVE 3

@ 9-E83V5 +8 Is3vs -e, 4tt

$js7 + yTROL + fYs 8.4. BATT D.4. FWEL RLT RM & RS$v$ Y E BSYS

& CalLLEB flad3FER EN 3m68 Ji.IfL 5FSTEM RM V !af Q SE'.s t CE tut l D Y #L CI W TER Q 31W NEAT EECnAm6ERS E3F L&F FAs 3 AC POWER FAs 4 DAMPER AC 70ff t AC POWEt Y DeMPER I tr1 TEM POWER BflTEM + PUMP poker SYSTEM pgegg *#

l ggggg" SEAL C00 Lits l (SNUTD0ut + Ent PUMP 5

? l Cook all i test & 4 CalLL WTE. @

CRAC TO C00LESS 'I s3 T. A l t a CalLE WTt (CDe0Elas-4> Ptf C0 sit 0L (edS) gggg YS TEM + C LOSIC 8T L RSSV5 6 STA400f Q RS$ v5 CBAC AC P0utt REACTOR EsF CWiLL WTR $L RE CI RC. -Gb PIEVEuf AC PosCR + ' L' v4Lvf CORE PYPASS sys P0mit A Pout E 308 $$ RSCLCW S BS gy. 4 POWER REAT EECmaaJEt gL SYS TEM t

88,

6 CalLL WTE. SEtt tCE Cef LLER SEtelCE 4 SIESEL IIIII +

CRAC CelLL 9 TO C00LEt3 WATER 9 NEAT EECn&d6ER$ WATER C00U e6 AC POWER gygyru wit.3757. SYSTEM SYSTEM J

sy ,y l

T STAeOST OF Fal TE FUEL OIL FUEL FOR AC PouER C# 8 LLER COLL AREA 0F AC POWEt DC POWEt SEtriCE g 3YSTEM WATER SYS TEM 7

1 I BREARER lDC POWER 4 T DC P0 met F0FF5l TE 06 800M EIERGESCV SIESEL GEdERATC#

AREA C00Lis6 l SYSTEM 9 C0eff0L ggF C0dit0L LOGIC 4 AC P0pf t SYSTEM i AC PouEg vfdT N q

+ 8ATT Y CONTROL PGrER

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SYSTEM ; AR6ER O $ 4 4 E.Sutt. + AREA Mid6 i sa TT.tM* II' dc paser BREARER IM VEST lvEdi TEMPEBATutt AC P0sta

+ VALvf Puse a SYSTEM C0dit0L

+ C0dTaos FIG. 4.2-1B SHUTDOWN MODEL SHUTDOWN SYSTEMS (IE)

SHOREHAM NUCLEAR POWER STATION-UNIT 1 CABLE SEPARATION ANALYSIS REPORT

, MA le C0dD. FEED ~~ C I RC.

, te51V'8 TSCLCw , STE AM SYS TEM MATER WATE R l

l $ f57EM S YS TEM SYSTEM EPOWE R -EDC0dTROL POWEg iPC PowfR l 0F F54 TE DC poser DC power _DC power

,57$ TEM SYS TM A C0dTROL (IE) leas t PEER .l sAC 70 y3 TEd wit 4 MOV'8 SYSTEM + CONTROL S f3 TEM -E> C0dTROL SYSTEM 4 Cou TR OL (dd$) Pore R (NNS) power [es5) POWER 5 TV ~

Nil ichi TC Of f s TE AC power A PUNP5 8 SEAL AC power

+ settinE 4 PUMP 3 5 ' AC eveER -E> PuMrs 3 AC ParTR A PUMP 3 8 VALVE 3 l 871TEd SEALS 373 FEM VA LVES 'S YS TE.4 VALVES Sf87EM VALVES SL R e s CE e4TER 4 I 4 ~L d gAgggy AdGER TBCLCW + Olt C00LER3 TSCLCu 4 OIL COOLERS PRIMise 4 asalafais SY1 TIM . WATER LEVEL e

leS t.

Alt S YS TEd O

DL 'wER SYS TEM + CodTROL INg5) POWER C i 0F F5 4 TE AC POWER + ORIER A T$ TE'e add MOTORS g

T8CLCu INTERCOOLER AND AFTER COOLER FIG. 4.2-1C SHUTDOWN MODEL SHUTDOWN SYSTEMS (NNS)

SHOREHAM NUCLEAR POWER STATION-UNIT 1 CABLE SEPARATION ANALYSIS REPORT e O O

a i R ACEWAY RACEWAY (EC6) SHUTDOWN ESK VS VS VS EQUIPMENT VS CABLE LIST AREA LIST CABLE LIST (EC1) ESK LIST (EC-35)

COM PA R E COM PA R E (COMPUTER) (M ANU AL)

CABLE VS OWN NI N G ARE A LIST CABLE LIST CO MPA RE (COMPUTER)

I SHUTDOWN EQUIPMENT VS ARE A/ CABLE LIST I

ANALYSIS FIGURE 4.4-1 DEVELOPMENT OF SHUTDOWN EQUIPMENT BY AREA SHOREHAM NUCLEAR POWER STATION-UNIT I CABLE SEPARATION ANALYSIS REPORT 1

i 1

l I

i9 1

i 1

4 f

i l l 1

i t

l APPENDIX A CABLE SEPARATION ANALYSIS RESULTS r SECONDARY CONTAINMENT t-O r

l Original 9 April 1983

SEGMENT 008-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT fsr

- 1. SYSTEMS IMPACTED:

(A) Division I-Systems: Ell, E21, G41, P41, P42, P50, T46 (B) Division II System: P41 (C) Division III Systems: None

2. SYSTEMS FUNCTIONS DISABLED:

(A) No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(B) Division II SW (P41) system fuel pool supply valve 1P41*MOV042B, ultimate cooling drain valves 1P41*MOV039B and 43, and cross tie valves 1P41*MOV033B and D.

3. DISABLED FUNCTION EVALUATIONS:

(A) Remaining Division II systems and Division III systems are available.

(s/ (B) Division II SW (P41) system supply, ultimate cooling drain, and cross tie valves are not necessary since Division II RHR (Ell) system is available.

. 4. SHUTDOWN CAPABILITY:

Hot shutdown is achievaole using Division II HPCI (E41) system.

Cold shutdown is achievable using Division II and III RHR (Ell) systems.

5. FURTHER ACTION RECOMMENDED:

None

[

l l

A-1 Original N . April 1983 i

y a-- 9 - g- -p.-- -'y.y m we -ne--- 4--i nye.= ,my'p--m y pw 3,y re--*- y.m. y-e.q-,- a.wy yvy-ggi-eie *-c.,, m&-m-ve._r--y-z.-w.w---w---we-----i.- me-v- gw -..re-

SEGMENT 008-N2 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I Systems : Ell, E21, G41, P41, P42, PSO, T46 (B) Division II Systems : None (C) Division III Systems: None

2. SYSTEMS FUNCTIONS DISABLED:

No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLZD FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division II and III I systems.

5. FURTHER ACTION RECOMMENDED:

None A-2 Original April 1983

SEGMENT 008-N3 CABLE SEPARATION ANALYSIS

,s SECONDARY CONTAINMENT lG 1

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51, (Division I components only), G33, G41, P41, P42, P50, T46 (B) Division II System: E41 (Division I and II components)

(C) Division III Systems: Ell (C), P42(C), T46(A,B)

2. SYSTEMS FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems functions.

(B) Division II HPCI (E41) system.

(C) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1 Ell *MOVO47.

3. DISABLED FUNCTION EVALUATION 1

/~N (A) Remaining Division II systems are available.

(B) Division I RHR (Ell) system valve 1 Ell *MOV047 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR with (Ell) manual operation of valve lEll*MOVC47, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None

6. ACTION TO BE TAKEN None A-3 Original O. April 1983

SEGMENT OO8-N4 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51, (Division I and II components) G33, G41, P41, P50, T46 (B) Division II System: E41 (Division I and II components)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS FUNCTIONS DISABLED:

(A) No credit taken for Division I or III systems func tions .

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOVO47.

(C) No credit taken for Division II HPCI (E41) systems functions.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division II systems are available.

(B) Division I RHR (Ell) system valve 1E11*MOVO47 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR system with manual operation of valve 1E11*MOVO47 or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

The reduction of fire hazard in the vicinity of the HPCI and RCIC pumps and surrounding raceways may make available the HPCI system as alternative to using the RHR/CS/SRV flow path.

A-4 Original April 1983 t

6. ACTION TO BE TAKEN To reduce the fire hazard in the HPCI/RCIC area, the

! following will be provided:

(A) Additional water spray and cable tray bottoms on selected horizontal " Red" trays.

(B) Curbs around the HPCI and RCIC turbines.

(C) Additional local smoke detection.

(D) A partial fire barrier between vertical cable trays i and the adjacent RCIC turbine.

O ,

b A-5 O Original April 1983

SEGMENT 008-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: B21, Ell, B31, C61, E51 (Division I and II components)

P50 (9) Division II Systems: B21, B31, C41, C61, Ell, E21, E41 (Division I and II components)

G41, P41, P42, P50, T46 (C) Division III Systems: C61, Ell (C), P41(C), P42(C),

T46(A,B)

2. SYSTEMS EUN.CTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) and Reactor Plant Remote Shutdown (C61) systems.

(B) RHR (Ell) system components shutdown cooling outboard isolation valve 1E11*MOV047, 1E11*MOV036B and 1E11*MOVO37B.

(C) No credit taken for ADS (B21) valves 1B21*SOV092C, D, (D)

No credit taken for RWC (B31) components 1B31*PSO23A,B (Il and 1B31*MOVO32B, (E) Division (I) compressed air (P50) valve 1P50*MOV014.

(F) No credit taken for Division II and III systems functions, including the RHR (Ell) system shutdown cooling outboard isolation valve 1 Ell *MOVO48.

(G) Division II Reactor Low Water Level switch 1B21*LIS027C.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I systems are available.

(B) Division (I) compressed air (P50) valve 1P50*MOV104 is not required.

l (C) The loss of Division (I) RHR (Ell) valves 1E11*MOV036B and 37B will not affect shutdown.

A-6 I Original April 1983 l

l

(D) Division I and II RHR system valves 1E11*MOV047 and 1E11*MOV048 can be manually operated, or Division I

~~ RHR/CS/SRV flow path is available.

\m/ (E) The affected electrical components will not cause the spurious opening of RHR (Ell) system valves 1E11*MOV047 and 048.

(F) Division II reactor low water level switch

1B21*L1SO27C is one out of two Division II sensors, and the redundant Division I sensors remain functional.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow a

path.

l Cold shutdown is achievable using Division I RHR system with j manual operation of valves or the Division I RHR/CS/SRV flow path can be used.

5. FURTHER ACTION RECOMMENDED:

f The reduction of fire hazard in the vicinity of the HPCI and RCIC pumps and surrounding raceways may make available the i

RCIC or HPCI systems as alternative to using the RHR/CS/SRV flow path.

j'% .

(, ) 6. ACTION TO BE TAKEN To reduce the fire hazard in the HPCI/RCIC area, the following will be provided

i

~

(A) Additional water spray and cable tray bottoms on selected horizontal " Red" trays.

4 (B) Curbs around the HPCI and RCIC turbines.

(C) Additional local smoke detection.

(D) A partial fire barrier between vertical cable trays and the adjacent RCIC turbine.

i f.

A-7 i

O Original April 1983

- _ ._..____ _ _ _ _ _ , __. , - - . - - . _ _ . . _ , , . - - . . . . . _ ,._.._.~.- - -

SEGMENT 008-NG CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division I and II components), P50 (B) Division II Systems: B21, B31, C41, C61, C71, Ell, E21, E41 (Division II components only), G33, G41, P41, P42, P50, T46 (C) Division III System: Ell (D)

2. SYSTEMS FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) system.

(B) Division I compressed air (P50) system valve 1P50*MOV104 (C) No credit taken for Division II and III (D) systems functions.

(D) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are available.

(B) Division I compressed air (P50) system valve 1P50*MOV104 is not required.

(C) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR, 'C S ,'S RV circulation /suppressi:n pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve IE11*MOV048, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None A-8 Original April 1983

SEGMENT 008-N7 CABLE SEPARATION ANALYSIS c SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Syst,ms: E51 (Division I components only)

(B) Division II Systems: B21, C61, Ell, E21, E41 (Division II components only),

G41, P41, P42, P50 (C) Division III System: Ell (D)

2. SYSTEMS FUNCTIONS DISABLED:

(A) No credit taken for Division I HPCI (E51) system.

(B) No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve lEll*MOVO48.

(C) No credit taken for Division III(D) systems functions.

3. DISABLED FUNCTION EVALUATION:

Remaining Division I and III(C) systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown la achievable using the Division 1 RHR/CS/PRV flow path.

Cold shutdown is achievable using Division I or II RHR (Ell) system.

5. FURTHER ACTION RECOMMENDED:

None i

t A-9 Original

' April 1983 t

SEGMENT 008-N8 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division I components only)

P41, T46 (B) Division II Systems: B21, C61, Ell, E21, E41, (Division II components only)

G41, P41, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS FUNCTIONS DISABLED:

(A) Division I RCIC (E51) pump discharge valve 1E51*MOV034 RBSVS (T46) system unit cooler 1T46*UC002A and service water (P41) system valve 1P41*MOV037A.

(B) No credit taken for Division II systems functions, other than RHR (Ell) system shutdown cooling outboard isolation valve IE11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I systems and Division III systems are available, except Division I (Z51) RCIC system.

W (B) Division I RHR (Ell) system shutdown cooling mode using the Division II RBCLCW (P42) system is unavailable; however, the Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division I RBSVS (T46) unit cooler IT46*UC002A impacts Division II equipment.

(D) Service water (P41) system valve IP41*MOV037 is not required.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None A-10 Original April 1983

SEGMENT 008-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT N 1. SYSTEMS IMPACTED:

(A) Division I Systems: Ell, E21, G41, P41, P42, P50, T46 (B) Division II' System: P41 (C) Division III Systems: None j 2. SYSTEMS' FUNCTIONS DISABLED:

, (A) No credit taken for Division I system functions, other "

than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047, and the RCIC (E51) system.

l (B) Division II SW (P41) system fuel pool supply valve IP41*MOV042B, ultimate cooling drain valves 3

1P41*MOVO39B and 43, and cross tie valves IP41*MOVO33B i and D.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems except SW (P41) system are available.

{'N (B) Division II SW (P41) system supply , ultimate cooling drain and cross tie valves are not necessary since Division II RHR (Ell) system is available.

(C) Division III ystems are available.

4. SHUTDOWN CAPABILITY:

, Hot shutdown is achievable using Division 1 RCIC (E51) system.

Cold shutdown is achievable using Division II and III RHR l (Ell) systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-11 April 1983

SEGMENT 008-02 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C61, Ell, E21 (Division I component only) E51, G41, P41, P42, P50, T46 (B) Division II Systems: None (C) Division III System: Ell (C)

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I and III(C) systems' functions, other than RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISAELED FUNCTION EVALUATION:

Division II and III (D) system are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III (D) systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-12 April 1983

SEGMENT 008-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT g

? i

\/ 1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I component only)

G33, G41, P41, P42, P50, T46 (B) Division II System: E41 (Division I and II components)

(C) Division III Systems: Ell (C), P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions.

(B) No credit taken for Division II HPCI (E41) system.

(C) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available except Division II HPCI (E41) system.

( ,) (B) Division I RER system valve 1E11*MOVO47 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Divis.4cn II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR with manual operation of valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None v

Original A-13 April 1983

SEGMENT 008-04 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: B21, C61, Ell, E51, (Division I and II components) P50 (B) Division II System: E41 (Division I and II components)

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems other than RHR (Ell) shutdown cooling valve 1E11*MOVO47.

(B) No credit taken for Division II HPCI (E41) system.

1. DISABLED FUNCTION EVALUATION:

1 (A) Division II systems are available, except HPCI (E41) system.

(B) Division III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using the Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RER system.

5. FURTHER ACTION RECOMMENDED:

l The reduction of fire hazard in the vicinity of the HPCI and l RCIC pumps and surrounding raceways may make available the HPCI system as alternative to using the RHR/CS/SRV flow path.

6. ACTION TO BE TAKEN:

To reduce the fire hazard in the HPCI/RCIC area, the following will be provided:

(A) Additional water spray, cable tray bottoms on selected horizontal " Red" trays.

i (B) Curbs around the HPCI and RCIC turbines.

(C) Additional local smoke detection.

(D) A partial fire barrier between vertical cable trays and the adjacent RCIC turbine.

Original A-14 April 1983

SEGMENT 008-05 CABLE SEPARATION ANALYSIS SECONDARY CCNTAINMENT

1. SYSTEMS IMPACTED 1 (A) Division I System: E51 (Division I components only) 4

-(B) Division II Systems: B21, B31, C41, C61, C71, Ell, E21, E41 (Division I and II

, components) G33, G41, P41, P42,

! PSO, T46 (C) Division III Systems: C61(D), Ell (D), P41(D), P42(C),

T46(A,B)

SYSTEMS' FUNCTIONS DISABLED:

2.

(A) No credit taken for Division I RCIC (E51) system.

(B) No credit taken for Division II and III system

functions.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve lE11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are available, except RCIC (E53)

/) system.

, (B) Division II RHR (Ell) system valve 1E11*MOV048 can be

! manually operated or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

l 4.

SHUTDOWN CAPABILITY:

Hot shutdown is-achievable using the Division I RHR/CS/SRV flow path.

l Cold shutdown is achievable using the Division I RHR (Ell) l system with manual operation of valve lEll*MOV048, or Division I RHR/CS/SRV flow path.

l

5. FURTHER ACTION RECOMMENDED:

None 1

l O

Original l A-15 April 1983

SEGMENT 008-06 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division I component only)

P5.0 (B) Division II Systems: B21, C61, Ell, E21, E41, (Division II 'orconents only) G33, G41, P41, P42 0 (C) Division III System: Ell (D)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) and compressed air (P50) system valve 1P50*MOV104.

(B) No credit taken for Division II system functions.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I (P50) system valve 1P50*MOV104 is not required.

(B) Division II RHR (Ell) system valve 1E11*M0V048 can be manually operated or Division I RHR/CS/PRV flow path can be used.

(C) Remaining Division I systems and Division III (C) systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/PRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system, with manual operation of valve 1E11*MOV048 or the Division I RHR/CS/PRV circulation / suppression pool cooling flow path.

5. FURTHER ACTION RECOMMENDED:

None O

Original A-16 April 1983

SEGMENT 008-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O 1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division I components only)

P41, T46 (B) Division II Systems: C61, Ell, E21, E41 (Division II components only), G41, P41, P42, P50 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Divicion I SW(P41) system affected components result in the loss of Division I RBCLCW (P42) system.

(B) Division I RBSVS (T46) system unit cooler 1T46*UC002A.

(C) No credit for RHR (E41) system valve 1E51*MOV034.

(D) No credit taken for Division II system functions, other than RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

}

(A) Remaining Division I systems and Division III systems are available.

(B) Division I RHR (Ell) system shutdown cooling mode using the Division II RBCLCW system is unavailable; however, the RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division I RBSVS (T46) system unit cooler 1T46*UC002A impacts Division II equipment.

I

4. SHUTDOWN CAPABILITY:

l Hot shutdown is achievable using Division I RHR/CS/SRV flow l path.

Cold shutdown is achievable using Division I RHR/CS/SRV flow path.

! 5. FURTHER ACTION RECOMMENDED:

Nono O Original A-17 April 1983

SEGMENT 008-08 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: Ell, E21, G41, P41, P42, PSO, T46 (B) Division II Systems: C61, Ell, E21, G41, P41, P42, P50 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Divisions I and II RHR (Ell) system heat exchanger inlet and outlet valves 1 Ell *MOV033A, 033B, 035A and 035B.

(B) Direct cooling of fuel pool by both Division I and II of SW (P41) systems.

(C) RHR (Ell) system emergency cooling backup from SW (P41) system for both Divisions I and II.

(D) Cross tie valves 1P41*MOV033A,B,C, and D of Divisions I and II SW (P41) systems.

(E) SW (P41) and RBCLCW (P42) systems' sides of the RBCLCW system heat exchangers for both Divisions I and II.

(F) Division I RBSVS (T46) system unit cooler 1T46*UC002A.

(G) Division II compressed air (P50) system valve 1P50*MOV106.

(H) Division I and II RHR branch valves.

(I) No credit taken for reactor plant remote shutdown (C61) systems.

3. DISABLED FUNCTION EVALUATION:

l (A) Divisions I and II RHR (Ell) system heat exchanger inlet valves lE11*MOV033A and B are physically located outside this segment and could be manually operated in order to use the RHR system heat exchangers.

(B) Fuel pool cooling can be affected by intermittent use i ,

of Division I RHR system.

(C) SW ultimate cooling not required for shutdown.

(D) Cross-connection of Divisions I and II of SW (P41) l systems is not necessary since both the SW divisions are separately available.

Original A-18 April 1983 i

(E) RBCLCW (P42) is not required for altsrnative RHR/CS/RPV flow path.

(F) Division I RHR shutdown cooling mode is unavailable; 1 e however, Division I or II RHR/CS/SRV Y# circulation / suppression pool cooling flow paths are l available.

(G) Division I RBSVS system unit cooler 1T46*UC002A impacts Division II equipment.

(H) Division II .P50 system valve IP50*MOV106 will not prevent operation of the P50 system for plant shutdown.

(I) Division I and II RHR branch valves will fail in acceptable position and not jeoparidize system operation.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using the Division I RCIC or Division II HPCI systems.

Cold shutdown is achievable using Divisions I or II RHR/CS/SRV flow paths with the RHR (Ell) system used in suppression pool cooling, and manual operation of valves 1E11*MOV33A, 033B, 035A, and 035B.

5. FURTHER ACTION RECOMMENDED:

C'T x-] None j \- / Original A-19 April 1983

. _ _ __~ ._. . . - . _ _ _ -. _

SEGMENT 040-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: Ell, E21, G41, P41, P50 (B) Division II System: B31, Ell (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions, other than RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(B) No credit taken for Division II systems' functions, oth r than RHR (Ell) and HPCI (E41).

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048 (D) Division II Reactor Water Recirculation RWR (B31)

System pressure switch 1B31*PSO23B is a low pressure interlock for the Division II RHR (Ell) system.

3. DISABLED FUNCTION EVALUATION:

g (A) Division II RHR (Ell) System valve 1E11*MOV048 may be manually operated on RHR/CS/PRV circulation / suppression pool cooling path is

available.

(B) Division II RWR (B31) low pressure interlock 1B31*PSO23B may prevent operation of RHR chutdown cooling outboard isolation valve 1E11*MOVO48.

(C) Remaining Division II systems are available.

(D) Division III systems are available.

l

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) System.

Cold shutdown is achievable using Division II RHR (Ell) System l ,

with manual operation of RHR (Ell) System valve 1E11*MOV048 or the Division II RHR/CS/PRV Flowpath.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-20 April 1983

SEGMENT 040-N2 CABLE SEPARATION ANALYSIS

. SECONDARY CONTAINMENT

/h

~s' 1. SYSTEMS' IMPACTED:

(A) Division I Systems: B21, B31, Ell, P42 (B) Division II Systems: T46 (C) Division III Systems: None

2. . SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(C) Division II RBSVS (T46) system unit cooler IT46*UC003B

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated or Division II RHR/S/SRV circulation / suppression pool cooling flow path is 4

available.

(~')

(_)

~(B) Division II RBSVS System Unit cooler IT46*UC003B affects Division I equipment.

(C) Division II systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using HPCI (E41) System.

Cold shutdown is achievable using Divisim. II RHR (Ell) system with manual operation of valve 1E11xMOV047, or i Division II RHR/CS/SRV flow path.

5. FURTHER ACTION PECOMMENDED:

None O Original A-21 April 1983

SEGMENT 040-N3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I components only)

G33, G41, P41, P42, PSO, T46, (B) Division II Systems: E41 (Division I components only)

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolat.on valve 1 Ell *MOVO47.

(C) No credit taken for Division II HPCI (E41) system functions.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system valve 1 Ell *MOVO47 can be manually operated or Division II RHR/CS/fRV circulation / suppression pool cooling path is available.

(B) Remaining Division II and Division III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/RPV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve lE11*MOVO47 or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-22 April 1983

SEGMENT 040-N4 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

(%

t v) 1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, C71, Ell, E21, E51 (Division I and II components) G33, G41, P41, P42, P50, T46 (B) Division II Systems: E41 (Division I components only), T46 (C) Division III Systems: P42 (C), T46 (A, B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOVO47 and HPCI steam supply valve 1E11*MOV049.

(C) No credit taken for Division II HPCI (E41) system.

Division II RBSVS (T46) system unit cooler cs (D) 1T46*UC003B.

(%_-)

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except the HPCI (Ell) system. Division I RHR (Ell) system valve (E11)*MOV049 is not required for safe shutdown.

Division II RBSVS (T46) unit cooler 1T46*UC003B (B) affects Division I equipment.

(C) Division I RHR system valve 1 Ell *MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

t

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

! Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

p 5. FURTHER ACTION RECOMMENDED:

1

\v/ None Original A-23 April 1983

SEGMENT 040-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, C61, Ell, E51 (Division I and II components) P50 (B) Division II Systems: B21, B31, C41, C61, C71, Ell, E21, E41 (Division I and II components) G41, P41, P42, P50, T46 (C) Division III Systems: C61, P41(D), P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II or II. systems functions.

(B) Division II Service Air (P50) valves 1P50*MOV103B, -

114B, 113B, and 106.

(C) No credit taken for Division I ADS (B21) valves, Reactor Plant Remote shutdown (C61) RCIC (E51) and compressed air (P50) systems functions.

(D) Division I RHR (Ell) system shutdown cooling pump suction valves 1E11*MOV032A,B,C,D, inboard isolation valve 1E11*MOV047, HPCI steam supply valve 1E11*MOV049, and 1E11*MOV031A, 031C, and 040A valves.

(E) Division II RHR (Ell) outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV flow path is available also with manual operation of required valves. Division I E21 (CS) also available for RPV makeup.

(B) Affected Division I RHR (Ell) valve 1E11*MOV047 is in series with Division II RHR (Ell) valve 1E11*MOV048 which has been shown not to open spuriously.

(C) Division II service air (P50) valves 1P50*MOV114B 1 be manually operated; valve 1P50*MOV103B will fail open position allowing the system to remain functional; valves 1P50*MOV113B and 1P50*MOV106 are not required.

O Original A-24 April 1983

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I CS/SRV flow path g' for vessel makeup.

(. Cold shutdown is achievable using Division I RHR with manual operation of required valves, or Division I CS/SRV flow path for RPV makeup with RHR in pool cooling via manual valve operation. Division II P50 system can be used for long term SRV operation.

5. FURTHER ACTION RECOMMENDED:

None SEGMENT 040-N6 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Div. II components only)

C61 1 (B) Division II Systems: B21, B31, C41, C61, C71, Ell, E21, E41 (Div. II components only), G33, G41, P41, P42, P50, O

v/

T46

(C) Division III Systems: C61, P41(D), P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Divisions II and III systems' functions.

l (B) Division II RHR (Ell) system shutdown cooling outboard I isolation valve 1 Ell *MOVO48.

l l (C) Division I RCIC (E51) system temperature element 1E51*TE054B.

3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are available, except Division I RCIC system.

(B) RHR system can be manually operated, or Division I RHR/CS/SRV flow path is available.

l O Original A-25 April 1983

}

.. . - . . . . _ ~ _ - - ~ . . - _ - , . _ . _ . - - , , . , _ . . ___

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR with manual operation of valve 1E11*MOV048 or Division I RHR/CS/SRV circulation / suppression pool cooling flow path.

5. FURTHER ACTION RECOMMENDED:

None SEGMENT 040-N7 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: B21, B31, C61, Ell, P41, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems functions.

(B) Division II RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOVO48.

3. DISABLED FUNCTION EVALUATION:

(A) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated or Division I RHR/CS/PRV circulation suppression cooling flow path is available.

(B) Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E11*MOV048 or the Division I RHR/CS/PRV flow path can be used.

5. FURTHER ACTION RECOMMENDED:

None Original A-2<6 April 1983

. - - .. = ._ -

SEGMENT'040-N8 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

() 1. SYSTEMS IMPACTED:

None (A) Division I Systems:

(B) Division II System: B31, C61, Ell, E21, G41, P41, l.

P42, P50 4

(C) Division III Systems: None ;

, 2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit- taken for Division II systems' functions, other than HPCI (E41) system.

(B) Division II Reactor Water Recirculation RWR (B31) system pressure switch 1B31*PS023B is a low pressure interlock for the Division II RHR (Ell) system.

s (C) Division II RHR (Ell) system shutdown cooling outboard

! isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I and III systems, and Division II HPCI (E41) system are available.

, (j (B) Division II RWR (B31) system low pressure interlock i 1B31*PS023B may prevent operation of RHR shutdown cooling outboard isolation valve 1E11*MOV048.

i (C) Division II RHR(Ell) system valve 1E11*MOV048 can be manually operated or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) or j Division II HPCI (E41) systems.

Cold shutdown is achievable using the Division I RHR (Ell)

! system with manual operation of valve 1E11*MOV048, or the Division I or'III RHR/CS/SRV flow path.

1

5. FURTHER ACTION RECOMMENDED:

None Original

A-27 April 1983

-.r-.s,-,-e , ,,r-,.--.-gr -,-,,.-m o , , - ~ - -..i-.<-a.,.:----r.ew..,,,o .-r-,,.-e.g.e%.. ,e...-w-.-w_ - - - - - - . - , y,-.,,,ww

SEGMENT 040-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, Ell, E21, G41, P41, P42, P50 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve lEll*MOV047.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system valve lEll*MOV047 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(B) Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve 1 Ell *MOVO47 or the Division II or III RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None O

Original A-28 April 1983

SEGMENT 040-02 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED 1 (A) Division I Systems: B21, B31, Ell, E21, G41, P41, P42, P50 (B) Division II System: T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I system's functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

l (C) Division II RBSVS (T46) system unit cooler 1T46*UCOO3B.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is

/~'\ available.

N.] cooler 1T46*UC003B (B) Division II RBSVS systems unit 4 affects Division I equipment.

(C) Division II and III system are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve 1E11*MOV047 or Division II or III RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None i

O Original f A-29 April 1983

. ~ _ . . _ _ ._ .-. _ _ _ _ _ . . , __ _ . _ _ _ . . . _ _ _ . . . . , _ _ _ _ . _ _ _ . , _ _ . .

SEGMENT 040-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51, (Division I components only) G33, G41, P41, P42, P50, T46 Division II Systems: E41 (Divisj o- I components (B) only), T46 (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047 and HPCI steam supply valve 1E11*MOV049.

(C) No credit taken for Division II HPCI (E41) system.

Division II RBSVS (T46) system unit cooler (D)

IT46*UC003B.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except the HPCI (E41) system, thus RHR valve 1E11*MOV049 is not required for safe shutdown.

(B) Division II RBSVS (T46) system unit cooler 1T46*UC003B affects Division I equipment.

(C) Division I RHR system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-30 April 1983

SEGMENT 040-04 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

SYSTEMS IMPACTED:

l.

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51, (Division I and II com-ponents) G33, P41, P42, P50, T46 (B) Division II Systems: E41 (Division I components only), T46 4

(C) Division III Systems: P42(C)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve lE11*MOV047 and HPCI steam supply valve 1E11*MOV049.

1 (C) Division II HPCI (E41) system pressure switches 1E41*PS025A&C and. RBSVS (T46) system unit cooler 1T46*UC003B.

(D) No credit taken for Division III systems' function.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except the HPCI (E41) system, thus RHR valve 1E11*MOVO49 is not required for safe shutdown.

(B) Division I RHR system valve 1E11*MOV047 can be manually operated, -or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division II RBSVS system unit cooler 1T46*UC003C affects Division I equipment.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system and manual operation of valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

h a None

, Original A-31 April 1983

SEGMENT 040-05 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, C61, Ell, E51 (Division I and II components), P50 (B) Division II Systems: B21, B31, C41, C61, C71, Ell, E21, E41 (Division II components only), G33, G41, P41, P42, P50, T46 (C) Division III Systems: C61, P41(D), P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II and III systems' functions.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

(C) No credit taken for Division I RCIC (E51) system functions and Division I RHR (Ell) HPCI steam supply valve 1E11*MOV049 and 1E11*MOVO47, 031A, 032A, 040A, 031C, and 032C.

(D) Division II Service Air (P50) valves 1P50*MOV114B and 103B.

3. DISABLED FUNCTION EVALUATION:

(A) RHR valve 1E11*MOV049 is not required for shutdown.

(B) RHR valve 1E11*MOV047 can be manually operated or Division I CS/SRV flow path is available with manual operation of necessary PHR valves.

(C) Remaining Division I systems are available.

(D) Division I RHR (Ell) valve 1E11*MOVO47 is in series with affected 1E11*MOV048 valve and will not open spuriously.

(E) Remaining Division I P50 and B21 components are available.

(F) Division II RHR system valves can be manually operated, or Division I CS/SRV circulation / suppression pool cooling flow path is available.

(G) Division II compressed air (P50) system valve 1P50*MOV114B can be manually operated. Valve Original O

A-32 April 1983

1P50*MOV103B will fail in the open position enabling Division II (P50) system to remain ava21able.

4 4. SHUTDOWN CAPABILITY:

(+1

~# shutdown using Division I CS/SRV flow Hot is achievable path.

Cold shutdown is achievable using Division I RHR system and manual operation of required valves, or Division I CS/SRV flow path, available with RHR in pool cooling via manual valve operation.

5. FURTHER ACTION RECOMMENDED:

None SEGMENT 040-06 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: B21, B31, C61, Ell, E21, G41, P41,-P50, T46 4

(C) Division III Systems: None O

\m- 2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems' functions.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOVO48.

3. DISABLED FUNCTION EVALUATION:

t (A) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is i available.

t (B) Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E41*MOV048 or Division I or III RHR/CS/SRV flow path.

() 5. FURTHER ACTION RECOMMENDED:

original None l A-33 April 1983 l

l

. _ . , m _ ~ ..- _ . _ - . . . _ . . , _ .. _ . . ..._,.___--__.m.,._.,.._ . . _.- _..... -,.._...___ - , , _ , , . . _ . , - , , - - ~ . , ~ _ . - .

SEGMENT 040-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: D21, B31, C61, Ell, E21, G41, P41, P50 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems' functions.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOVO48.

3. DISABLED FUNCTION EVALUATION:

(A) Division II RHR (Ell) system valve 1E11*MOV048 can be operated manually or Division I RHR/CS/SRV circulation supression pool cooling is available.

(B) Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E11*MOV048 or Division I or II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None 1

l l

l.

Original O

A-34 April 1983

7-SEGMENT 040-08 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

[v\

(A) Division I Systems: Ell, E21, G41, P41, P42, P50 (B) Division II Systems: B31, C61, Ell, E21, G41,.P41, P42, P50 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I system functions other than RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047 and the RCIC (E51) system.

(B) No credit taken for Division II system functions other than the HPCI (E41) system and the unaffected Compressed Air (P50) components.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

'(D) Division II RWR (B31) system pressure switch 1B31*PS023B is a low pressure interlock for the Division II RHR system.

O k ,)

m (E) Division II (P50) valves 1P50*MOV104 and 1P50*MOV106.

t

3. DISABLED FUNCTION EVALUATION:

(A) Division I RCIC (E51) and Division II HPCI (E41) systems are aveilable.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated or Division I or III RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division III systems are available.

(D) Remaining Division II (P50) components are available.

(E) 1P50*MOV104 and 1P50*MOV106 valves are not required for shutdown.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) or Division II HPCI (E41) systems.

I Cold shutdown is achievable using Division I or III RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None A-35 Original April 1983 l _- - ~ _ , _ , . - - - . _ . _ - - . _ _ _ _ - - - - . _ _ _ _ _ _ . . _ . _ . .

SEGMENT 063-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: Ell (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' EUNCTIONS DISABLED:

Division I RHR (Ell) system drain valve lEll*MOV051.

3. DlISABLED EUNCTION EVALUATION:

Division I RHR (Ell) system drain valve 1 Ell *MOVO51 is in series with Division II RHR (Ell) system drain valve 1 Ell *MOV052, and therefore Division I RHR (Ell) sysi.em remains available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None O

A-36 Original April 1983

SEGMENT 063-N2 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT f~h

( ') l. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, Ell, P42 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systenis ' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

(A) Division II and III systems are available.

(B) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

[] 4. SHUTDOWN CAPABILITY:

%.)

Hot shutdown is achievable using Division II HPCI (E41)

system.

Cold shutdown is achievable using Division II and III RHR (Ell) system with manual operation of Division I RHR (Ell) valve 1E11*MOV047 or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None l

l O A-37 Original April 1983 l

.. - _ , . . .- . . - r_ .- - - . . - _ . , _ _ . . - - - . . . . _ . _ . . . -

SEGMENT 063-N3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C41, Ell, E21, C61, E51 (Division I components only),

G33, G41, P41, P42, P50, T46 (B) Division II System: Ell, E41 (Division I and II components)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV047.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

(D) No credit taken for Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except HPCI (Ell) system.

(E) RHR (Ell) system valves 1E11*MOV048 and 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow cath is available.

(C) Division I RHR (Ell) system valve 1E11*MOV047 is in series with affected 1E11*MOVO48 and will not open spuriously.

l

4. SHUTDOWN CAPABILITY:

I Hot shutdown is achievable using Division II RHR/CS/SRV flow j path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valves, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path.

l l S. FURTHER ACTION RECOMMENDED:

None O

A-38 Original April 1983 l

SEGMENT 063-N4 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT 7-~

(x. s) 1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I and II components), G33, G41, P41, P42, PSO, T46 (B) Division II Systems: B21, C41, C61, Ell, E21, E41 (Division I and II components), G33, P41, P42, PSO, T46 (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions.

(B) Division I and II RHR (Ell) system shutdown cooling inboard and outboard isolation valves 1E11*MOV047 and 1E11*MOV048.

.s (C) Portions of Division II RBSVS (1T46), SW (P41) and

( compressed air (P50) systems.

)

(D) No credit taken for Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining essential Division II systems or portions thereof are available.

(B) RHR system valves 1E11*MOV047 and 1E11*MOV048 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) The affected electrical components will not cause spurious opening of RHR (Ell) systems valves 1E11*MOV047 and 048.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using the Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR system with manual operation of valves 1E11*MOV047 and 1E11*MOV048, or the Division II RHR/CS/SRV flow path.

(~N

- 5. FURTHER ACTION RECOMMENDED:

A-39 Original None April 1983

SEGMENT 063-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: Ell, E51 (Division I and II components)

(B) Division II Systems: B21, B31, Ell, E21, E32, E41 (Division I and II components), C41, C61, G33, G41, P41, P42, P50, T46 (C) Division III Systems: C61, P41(D), P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) and RHR (Ell) systems other than system shutdown cooling outboard isolation valve 1E11*MOV047.

(B) Division I RHR (Ell) system HPCI steam supply valve 1E11*MOV049.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOVO48.

(D) No credit taken for Division II and III systems' functions.

3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are available, except the RCIC (E51) and RHR (Ell) systems.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division I RHR (Ell) valve 1E11*MOV049 not required for safe shutdown.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system and manual operation of valve 1E11*MOV048, or Division I RHR/CS/SRV flow path.

5. EURTHER ACTION RECOMMENDED:

None A-40 Original April 1983

Note on the Remoto Shutdown Panal A separate analysis was performed to consider a fire in or

(~3i near the Remote Shutdown Panel 1C61*PNL-RSP which is located

( in this segment. A fire occurring in or near the remote

~

shutdown panel, of the severity necessary to cause destruction of the remote shutdown panel and transfer switches, is an extremely unlikely event. The panel, including transfer switches, is located in the reactor building at el 63 ft-0 in. It is located in its own separate cubicle which provides a fully enclosed space protected by a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months rated fire barrier. The cubicle contains both area and panel mounted early warning smoke detectors which sound early warning alarms in the control room. An independent halon fire suppression system is providad for the remote shutdown panel cubicle. It is automatically actuated by ionization detectors with actuation alarmed in the main control room. In addition, portable extinguishers are located just outside the cubicle and two water hose racks are located within 50 ft of the cubicle affording 100 percent coverage with 100 percent overlap. The remote shutdown panel itself contains only low energy control circuits. The panel is designed such that its circuits are deenergized when it is not in use.

If a fire is postulated in the remote shutdown panel, but the transfer switches are not involved, there would be no effect on controls in the main control room. The operator would retain the capability to utilize all shutdown equipment from the main control room. A fire involving the fN--/) remote shutdown panel controls and the transfer switches would not preclude a safe shutdown from the main control room. Sufficient redundant or diverse equipment, not having controls at the remote shutdown panel, are available in the main control room to accomplish safe shutdown should the operator not be able to use any or all equipment having controls located at the remote shutdown panel.

A f

\_/'}

A-41 Original April 1983

SEGMENT 063-N6 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division II components only)

(B) Division II Systems: B21, B31, C41, C61, Ell, E21, E41 (Division II components only), G33, G41, P41, P42, PSO, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems' functions.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

(C) No credit taken for Division I RCIC (E51) system.

3. DISABLED FUNCTION EVALUATION:

(A) Division I and III systems are available, except Division I RCIC (E51) system.

(B) Division II RHR (Ell) system valve 1E11*MOVO48 can be manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1 Ell *MOV048, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None A-42 Original April 1983

SEGMENT 063-N7 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT (G

\~

i

1. SYSTEMS IMPACTED:

(A) Division I System: E11 (B) Division II Systems: B21, B31, C61, Ell (C) Division III Systems: None

2. SYSTEMS' EUNCTIONS DISABLED:

(A) Division I RHR (Ell) system drain valve 1E11*MOV051.

(B) No credit taken for Division II systems' functions.

(C) Division II RHR (Ell) system shutdown cooling outboard

1. solation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I and III systems are available.

(B) Division I RHR (Ell) system drain valve 1E11*MOV051 is in series with affected Division II RHR (Ell) system drain valve 1E11*MOV052 on the Division I RHR flow

(}

(/

path. Division I RHR flow path remains available with manual valve operations.

(C) Division I E21 (CS) remains available. RHR pool cooling available via manual valve operation.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division I and III (RHR

, (Ell) systems with manual operation of Division II RHR (Ell)

valves 1E11*MOVO48, 052 and 051 or the Division I RHR/

CS/SRV flow path with manual operation of required valves.

I

5. EURTHER ACTION RECOMMENDED:

None i

("')

V A-43 l

1 l

SEGMENT 063-N8 i CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: Ell (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

Division I RHR (Ell) system drain valve 1E11*MOV051.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system drain valve 1E11*MOV051 is in series with unaffected Division II RHR (Ell) system drain valve 1E11*MOV052, therefore Division I RHR (Ell) system is available.

(B) Divisions I, II, and III are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None O

A-44 Original Anril 1983

SEGMENT 063-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

/3 N~-]

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, Ell, P42 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

(A) Division II and III systems are available.

(B) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

b

\_/

4. SHUTDOWN CAPABILITY:

i Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division I and II RHR system with manual operation of Division I RHR (Ell) system valve 1E11*MOV047 or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None

() A-45 Original April 1983

SEGMENT 063-02 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: Ell (B) Division II System: Ell (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions, other '.han RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division II systems and Division III systems are available:.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division II RHR (Ell) with manual operation of valve 1E11*MOV048, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path.

5. FURTHER ACTION RECOMMENDED:

None A-46 Original April 1903

SEGMENT 063-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

/m i )

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I components only), G33, G41, P41, P42, P50, T46 (B) Division II Systems: Ell, E41 (Division I and II)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit v.aken for Division I and III systems' functions.

(B) Division I and II RHR (Ell) system shutdown cooling isolation valves 1E11*MOV047 and 1E11*MOV048.

(C) Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

,_ (A) Division II systems are available, except HPCI (E41) system.

(B) Division I and II RHR (Ell) system valves 1E11*MOV047 and 1E11*MOV048 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) The affected electrical components will not cause spurious opening of RHR (Ell) system valves 1E11*MOV047 and 048.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using the Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using the Division II RHR (Ell) system with manual operation of valves 1E11*MOV047 and 1E11*MOV048, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None (m) s/

A-47 Original April 1983

SEGMENT 063-04 CABLE SEPARATION ANALYSTS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: Ell, E51 (Division I and II components)

(B) Division II Systems: Ell, E41 (Division I and II components)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' EUNCTIONS DISABLED:

(A) Division I RHR (Ell) system HPCI steam supply valve lE11*MOV049.

(B) No credit taken for Division I RCIC (E51) and Division II HPCI (E41) systems.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve lEll*MOV048.

(D) No credit taken for Division III RBCLCW (P42) and RBVS (T46) systems

3. DISABLED FUNCTION EVALUATION:

(A) Division I is available, except RCIC (E51) system.

l (B) Division I RHR (Ell) steam supply valve 1 Ell *MOV049 is not required for shutdown.

l (C) Division II RHR (Ell) system valve lEll*MOV048 can be I manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(D) Remaining Division III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV circulation / suppression pool cooling flow path.

Cold shutdown is achievable using the Division I RHR (Ell) system with manual operation of valve lEll*MOVO48, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None A-48 Original April 1983

SEGMENT 063-05 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

() 1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division II components only)

(B) Division II Systems: B21, B31, C41, C61, C71, Ell, E21, E41 (Division II components only), G33, G41, P41, P42, P50, T46 (C) Division III Systems: C61, P41(C), P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I RCIC (E51) system level switch 1B21*LIS027C, temperature element 1E51*TE054B, and steam supply inboard isolation valve 1E51*MOV041.

(B) No credit taken for Division II and III systems' functions.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

i O available, except RCIC (E51)

(,,/ (A) Division I systems are system.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E11*MOV048, or the Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None

~' Original A-49

^

April 1983 i

J w w y- -

,e-w--m-y--- w-m-g - - ,-e-m---ygw ,w -*T*Wwy-a ey----+t--- '-m+m*+e'-----Twm'N-MrPm ---

Nota on th7 R motn Shutdown Prn11 A separate analysis was performed to consider a fire in or near the Remote Shutdown Panel 1C61*PNL-RSP which is located in this segment. A fire occurring in or near the remote shutdown panel, of the severity r. ace s sary to cause destruction of the remote shutdown panel and transfer switches, is an extremely unlikely event. The panel, including transfer switches, is located in the reactor building at el 63 ft-0 in. It is located in its own separate cubicle which provides a fully enclosed space protected by a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months rated fire barrier. The cubicle contains both area and panel mounted early warning smoke detectors which sound early warning alarms in the control room. An independent halon fire suppression system is provided for the remote shutdown panel cubicle. It is automatically actuated by ionization detectors with actuation alarmed in the main control room. In addition, portable extinguishers are located just outside the cubicle and two water hose racks are located within 50 ft of the cubicle affording 100 percent coverage with 100 percent overlap. The remote shutdown panel itself contains only low energy control circuits. The panel is designed such that its circuits are deenergized when it is not in use.

If a fire is postulated in the remote shutdown panel, but the transfer switches are not involved, there would be no effect on controls in the main control room. The operator would retain the capability to utilize all shutdown equipment from the main control room. A fire involving the remota shutdown panel controls and the transfer switches would not preclude a safe shutdown from the main control room. Sufficient redundant or diverse equipment, not having controls at the remote shutdown panel, are available in the main control room to accomplish safe shutdown should the operator not be able to use any or all equipment having controls located at the remote shutdown panel.

A-50 Original April 1983

SEGMENT 063-06 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O 1. SYSTEMS IMPACTED:

(A) Division I System: Ell (B) Division II Systems: B31, C61, Ell (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I RHR (Ell) system drain valve 1E11*MOV051.

(B) No credit taken for Division II systems' functions, other than RHR (Ell) system shutdown cooling isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system valves 1E11*MOV051 and 1E11*MOV052 are in series on Division I RHR flow path; therafore, Division I RHR (Ell) system remains available with manual operation of valves.

(B) Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) or Division II HPCI (E41) systems.

Cold shutdown is achievable using Division I RHR with manual operation of valves 1E11*MOV051 or 053.

5. FURTHER ACTION RECOMMENDED:

None

() A-51 Original April 1983

SEGMENT 063-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: Ell (B) Division II Systems: B21, B31, C61, Ell (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I RHR (Ell) system drain valve 1E11*MOVO51.

(B) No credit taken for Division II systems' functions.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR (Ell) system drain valve 1E11*MOV051 is in series with affected Division II (Ell) RHR system drain valve 1E11*MOV052 on the Division I flow path.

Therefore, Division I RHR system remains available.

(B) Division I and III systems are available.

(C) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division I and III systems with manual operation of Division II RHR (Ell) valves 1E11*MOV048, 051 and/or 052.

5. FURTHER ACTION RECOMMENDED:

None A-52 Original April 1983 l

l l

. - . - -. -. .. . __~ _ .- .-.

SEGMENT 063-08 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

)

1. SYSTEMS IMPACTED:

(A) Division I System: E11 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

Division I RHR (Ell) system drain valve 1E11*MOV051.

3. DISABLED FUNCTION EVALUATION:

Division I RHR (Ell) system drain valve 1E11*MOV051 is in series with unaffected Division II RHR (Ell) system drain valve 1E11*MOV052, therefore Division I RHR (Ell) system remains available.

1 4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None 4

l A-53 Original April 1983

SEGMENT 078-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C61, Ell, G33, P42, P50 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions, other than RCIC(E51) system.

(B) RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RCIC (E51) system is available.

(B) Division II and III systems are available.

(C) Division I RHR system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation /suppressicn pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdcwn is achievable using Division I RCIC (E51) system.

l l Cold shutdown is achievable using Division II and III systems and with manual operation of RHR system valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

l None l

Original A-54 April 1983 1

SEGMENT 078-N2 CABLE SEPARATION ANALYSIS l

SECONDARY CONTAINMENT G

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I components only)

G33, P41, P42, P50, T46,

! (B) Division II System: ~E41 (Division I components only)

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

'(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard 4 valve 1E11*MOV047.

(C) No credit taken for Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except the HPCI

/~' (E41) system.

b) (B) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow j path.

Cold shutdown is achievable using Division II RHR (Ell)

, systems with manual operation of RHR valve 1E11*MOVO47, or Division II RHR/CS/SRV flow path.

i

5. FURTHER ACTION RECOMMENDED:

j None l

i Original A-55 April 1983 l

SEGMENT 078-N3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I components only)

G33, G41, P41, P42, PSO, T46 (B) Division II System: E41 (Division I components only)

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(C) No credit taken for Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Division II and III systems are available, except Division II HPCI (E41) system.

(B) Division I RHR system valve lE11*MOVO47 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. S_HUTDOWN_ CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve lEll*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-56 April 1983

SEGMENT 078-N4 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT Cs

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I components only), G33, G41, P41, P42, P50, T46 (B) Division II Systems: C41, E41 (Division I components only)

(C) Division III System: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions.

(B) RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(C) Division II Standby Liquid Control system SLC (C41) pump 1C41*P024B.

(D) No credit taken for Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except the HPCI (E41) and SLC (C41) systems.

-(B) Division I RHR (Ell) system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division II Standby Liquid Control SLC (C41) system is not required for normal shutdown.

4. SHUTDOWN CAPABILITY

i Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) l system with manual operation of valve 1E11*MOV047, or l Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

Original A-57 April 1983

SEGMENT 078-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division I and II components), T46 (B) Division II Systems: B21, B31, C41, C61, Ell, E21, E32, E41, (Division II ccm-ponents only), G33, G41, P41, P42, P50, T46 (C) Division III System: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems' functions.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

(C) No credit taken for Division I RCIC (E51) system, and RBSVS (T46) automatic isolation circuit.

(D) No credit taken for Division III RBCLCW (P42) and RBSVS (T46) systems.

3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are availnble, except RCIC (E51) system.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division I RBSVS (T46) auto isolation is not required for normal shutdown.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold chutdown is achievable using Division I RHR (Ell)

System with manual operation of valve 1E11*MOVO48, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-58 April 1983

SEGMENT 078-N6 CABLE SEPARATION ANALYSIS f SECONDARY CONTAINMENT i

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division II components only)

(B) Division II Systems: B21, B31, C41, C61, Ell, E21, E32, E41 (Division II components only), G33, G41, P41, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems functions.

(B) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

(C) No credit taken for Division I RCIC (E51) system.

3. DISABLED FUNCTION EVALUATION:

() (A) Division I and III systems are available, except

%s/ Division I RCIC system.

(B) RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Remaining Division I RBSVS T46 coolers available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR (Ell)

System with manual operation of valve 1E11*MOV048, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTIb RECOMMENDED:

None

( Original

{ '"' A-59 April 1983

SEGMENT 078-N7 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division II components only)

(B) Division II Systems: B21, B31, C41, C61, G33, Ell, E21, E41 (Division II components only), G33, P41, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) system.

(B) No credit taken for Division II systems' functions.

(C) Division 1 RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I and Division III systems are available.

(B) RHR (Ell) System valve 1E11*MOV048 can be manually operated or Division I RHR/CS/PRV flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using remaining Division I systems or RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RHR system with l

manual operation of value IE11*MOV048 or the Division I l RHR/CS/PRV flow path.

5. FURTHER ACTION RECOMMENDED:

None l

l Original A-60 April 1983

l 1

s r

SEGMENT 078-N8 ,

CABLE SEPARATION ANALYSIS '

SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I System': E51 (Division II components only)

(B) Division II Systems: B21, B31, G33 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC system functions.

(B) No credit taken for Division II systems's functions, other than HPCI (E41) system and RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION l

(A) Division I systems are available, except RCIC (E51) system.

(B) Division II HPIC (E41) system is available.

(C) Division III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

i Cold Shutdown is achievable using Division I, II, or III RHR systems.

5. FURTHER ACTION RECOMMENDED:

None

5. FURTHER ACTION RECOMMENDED:

None f

Original

()

, A-61 April 1983

SEGMENT 078-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I Systems: B21, B31, C61, Ell, G33, P42, P50 (B) Division II System: E41 (Division I components only)

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions, other than RCIC (E51) system.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(C) No credit taken for Division II HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RCIC (E51) system is available.

(B) RER (Ell) system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division II and III systems are a~ailable, except Division II HPCI (E41) system.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Divisions II and III systems with manual operation of RHR (Ell) system valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-62 April 1983

SEGMENT 078-02 CABLE SEPARATION ANALYSIS S SECONDARY CONTAINMENT

1. SYSTERS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51, (Division I components only), G33, P41, P42, P50, T46 (B) Division II System: E41 (Division I components only)

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) No credit taken for Division II HPCI (E41) system.

(C) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1 Ell *MOVO47.

3. DISABLED FUNCTION EVALUATION:

(A) Division II and III systems are available, except O Division II HPCI (E41) system.

(B) RER (Ell) system valve lEll*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II, RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve lE11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None

> Original

\ A-63 April 1983

--- -_-_ _ . . .. -~, -

SEGMENT 078-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: B21, B31, C41, C61, Ell, E21, E51 (Division I components only), G33, G41, P41, P42, P50, T46 (B) Division II System: E41 (Division I components only)

(C) Division III System: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions.

(B) No credit taken for Division II HPCI (E41) system.

(C) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOVO47.

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available, except HPCI (E41) system.

(B) RHR (Ell) system valve 1E11*MOV047 can be manually operated, or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division III RBCLCW system not available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-64 April 1983

- _______=__ - _ _ _______ - __-_ ______________- __ __-________________ __

SEGMENT 078-04 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: C41, Ell, E21, E51 (Division I components only), G41, P41, T46 (B) Division II System: C41 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems.

(B) Division I and II Standby Liquid Control SLC (C41) system pumps 1C41*P024A and B.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division II systems and Division III systems are available.

(B) Division II Standby Liquid Control SLC (C41) system is not required for normal shutdown.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division II and Division III systems.

5. FURTHER ACTION RECOMMENDED:,

None O A-65 Original April 1983 i

1

SEGMENT 078-05 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division I and II components), T46 (B) Division II Systems: B21, B31, C41, C61, Ell, E21, E32, E41, (Division II components only), G33, G41, P41, P42, P50, T46, (C) Division III System: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS PISABLED:

(A) No credit taken for Division I RCIC (E51) system and RBSVS auto isolation circuit.

(B) No credit taken for Division II and III systems' functions.

(C) Division II(Ell) RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are available, except RCIC (E51) system.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR/CS/SRV circula*. ion / suppression pool cooling flow path is available.

(C) Division I RBSVS auto isolation is not required for normal shutdown.

N

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RHR/CS/ SRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E11*MOVO48, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None original A-66 April 1983

SEGMENT 078-06 CABLE SEPARATION ANALYSIS N SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division II components only)

(B) Division II Systems: B21, B31, C41, C61, Ell, E21, E41 (Division II components),

G33, P41, P42, PSO, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) system.

(B) No credit taken for Division II systems' functions.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I and III systems are available, except

( ,} Division I RCIC (E51) system.

(B) Division II RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I and III RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I RER (Ell) system with manual operation of valve 1E11*MOV048, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None

() A-67 Original April 1983 d

g .v.. ,,.- 4 -

, , , . - , . - - . . - -- - - - - . _ - - , ,+-.,f, -

, ,,w-..- ,- , , , -- m

m. __,,,--,-,_y- - - - - - - - - - - -

SEGMENT 078-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division II components only)

(B) Division II Systems: B21, B31, C61, Ell, G33, P50 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) system.

(B) No credit taken for Division II systems' functions, other than HPCI (E41) system.

(C) Division II RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISI. BLED FUNCTION EVALUATION:

(A) Division I and III systems are available, except Division I RCIC (E51) system.

(B) Division II HPCI (E41) system is available.

(C) Division II RHR (Ell) system valve 1E11*MOV048 can be manually op(- ated or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E11*MOV048 or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-68 April 1983 ll L

SEGMENT 078-08 CABLE SEPARATION ANALYSIS

-~3 SECONDARY CONTAINMENT

\

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II System: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

Divisions I, II, and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Divisions I, II, and III systelas .

5. FURTHER ACTION RECOMMENDED:

Cy None O

Original A-69 April 1983

('))

s. .

SEGMENT 112-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31,C61,E11,P41,P42,P50,T46 (B) Division II Systems: B31,C61,E11, P42,P50, T46 (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I Reactor Water Recirculation RWR (B31), RHR (Ell), RBSVS (T46),

Service Water (P41) RBCLCW(P42) and Compressed Air (P50) systems functions.

(B) No credit taken for Divisien II Reactor Water Recirculation RWR (B31), RHR (Ell), RBSVS (T46),

RBCLCW(P42) and Reactor Plant Shutdown (C61) systems functions.

(C) Division II Compressed Air (P50) system valve 1P50*MOV103B (D) No credit taken for Division III RBCLCW (P42) and RBSVS (T46) systems functions.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I. II, and III systems are available.

(B) Division I er II CS (E21) system available.

(C) Division II valves IP50*MOV103B would fail in the open position enabling this division to remain functional.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using Division II CS/PRV flow path and Division II RHR in pool cooling via manual valve operation.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-70 April 1983

SEGMENT 112-N2 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT V() 1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C41, C61, Ell, E21, G33, P41, P42, P50, T46 (B) Division II Systems: E41 (Division I components only)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions, other than the RCIC (E51) system.

(B) Division I RHR (Ell) system shutdown coc ling i solation valve IE11*MOV047.

(C) No credit taken for Division II HPCI (E41) system.

(D) No credit taken for Division III systems' functions.

3. DISABLED FUNCTION EVALUATION:

/' ) (A) Division I RCIC (E51) system is available.

(d (B) Division I RHR (Ell) system valve 1E11*MOV047 may be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

(C) Division II systems are available, except HPCI (E41) system,

4. SHUTDOWN CAPABI[_ITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division II RHR/CS/SRV flow path or Division II RHR (Ell) System with manual operation of valve 1E11*MOV047.

5. FURTHER ACTION RECOMMENDED:

None O Original A-71 April 1983

SEGMENT 112-N3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C41, C61, Ell, E21, E51 (Division I components only), G33, G41, P41, 42, P50, T46 (B) Division II Systems: E41 (Division I components only)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Diviston 7 and III sys. ems functions.

(B) Division I RHR (Ell) system valve 1E11*MOVO47.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RHR(Ell) system valve can be manually operated or the Division II RHR/CS/PRV circulation / suppression pool flow path is available.

(B) Division II systems are available.

4. SHUTDOWN CAPABILITI:

Hot shutdown is achievable using Division II RHR/CS/PRV flow path.

Cold shutdown is achievable using Division II RHR(Ell) system with manual operation of valve 1E11*MOVO47 or the Division II RHR/CS/PRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original A-72 April 1983

SECMENT 112-N4 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

\ ) 1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C41, C61, Ell, E21, G41, P41, P42, P50, T46 (B) Division II Systems: C41, C61, G41, T46 (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions, other than Division I RHR (Ell) system shutdown cooling inboard isolation valves 1E11*MOV047 and remaining RBSVS (T46) components.

(B) Division II SLC (C41) system pump 1C41*P024B.

(C) Division II fuel pool cooling (G41) system valve 1G41*MOV032B.

(D) Division II RBSVS (T46) system unit cooler for MCC room, 1T46*UC020B.

(E) No credit taken for Division III (P42) and RBSVS (T46)

Isi systems.

'Q

3. DISABLED FUNCTION EVALUATION:

(A) Division II systems are available except as noted.

(B) Division I and II SLC (C41) systems are not required for normal shutdown.

(C) Division I and II emergency fuel pool cooling (G41) systems are not required for normal shutdown; affected G41 valves are in series with unaffected Division II P41 valves and the Division I P41 valves which would not open inadvertently.

(D) Division I RBSVS (T46) system that is redundant to the disabled Division II component is available to cool MCC room.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division I and II systems.

5. FURTHER ACTION RECOMMENDED:

\J )

None Original A-73 April 1983

SEGMENT 112-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: P42 (B) Division II Systems: C41, C61, Ell, E21, G33, G41, P41, P42, P50, T46 (C) Division III System: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division II systems' functions.

(B) No credit taken for Division III RBCLCW (P42) and RBSVC (T46) systems functions.

3. DISABLED FUNCTION EVALUATION:

Division I systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I systems.

5. FURTHER ACTION RECOMMENDED:

None Original 9

A-74 April 1983 i

SEGMENT 112-N6 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Division II components)

(B) Division II Systems: C41, C61, Ell, E21, E41 (Division II components),

G33, G41, P41, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC(E51) valve 1E51*MOV041.

(B) No credit taken for Division II systems' functions.

(C) RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I and Division III systems are available.

(~'}

us (B) Division II RHR system (Ell) valve 1E11*MOV048 can be manaally operated, or Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. EHUTDOWN CAPABILITY:

H >t shutdown is achievable using Division I RHR/CS/PRV flow path.

Cold shutdown is achievable using Division I RHR (Ell) system with manual operation of valve 1E11*MOV048, or Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None Q

Original A-75 April 1983

r SEGMENT 112-N7 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: E51 (Divisiion II components only)

(B) Division II Systems: B31, C41, C61, Ell, E21, G33, P41, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) system.

(B) No crecit taken tor Divis1or 11 systems' functions, other than RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048 and the HPCI (E41) system.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I systems and Division III systems are available.

(B) Division II HPCI (E41) system is available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using the Division II HPCI (E41) system.

Cold shutdown is achievable using remaining Division I systems.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-76 April 1983

SEGMENT 112-N8 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

\

\2 1. SYSTEMS IMPACTED:

(A) Division I System: T46 (B) Division II Systems: C61, Ell, G33, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RBSVS (T46) system functions.

(B) No credit taken for Division II systems' functions.

3. DISABLED FUNCTION EVALUATION:

Remaining Division I and Division III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division I, and II systems, and Division III systems.

/. 5. FURTHER ACTION RECOMMENDED:

( None

,m.

k- Original April 1983 A-77

SEGMENT 112-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C61, Ell, P41, P42, PSO, T46 (B) Division II Systems: None (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I or III systems' functions, other than Division I RHR (Ell) system shutdown cooling inboard isolation valve 1 Ell *MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II systems.

5. FURTHER ACTION RECOMMENDED:

None l

l l

l Original 9

A-78 April 1983

SEGMENT 112-02 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT rN I

(

\- 1. SYSTEMS IMPACTED:

(A) Division I Syctems: B31, C41, C61, Ell, E21, E51 (Division I components only), G33, G41, P41, P42, PSO, T46 (B) Division II System: E41(Division I components only)

(C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems' functions.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(C) No credit taken for Division II HPCI (E41) system.

(D) No credit taken for Division III systems' functions.

3. DISABLED FUNCTION EVALUATION:

1

\m ,/ (A) Remaining Division II systems are available.

(B) Division I RHR (Ell) system shutdown cooling inboard isolation valve 1 Ell *MOV047 can be manually operated or Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available.

4. SHUTDOWN CAPABILITl1 Hot shutdown is achievable using Division II RHR/CS/SRV flow path.

Cold shutdown is achievable using Division II RHR (Ell) system with manual operation of valve 1E11*MOV047, or Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None O

Q)

Original A-79 April 1983 l

k

SEGMENT 112-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C41, C61, Ell, E21, G41, P41, P42, P50, T46 (B) Division II System: C41, C61, G41 (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I and III systems' functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047 and the RCIC (E51) system.

(B) No credit taken for Division II Fuel Pool Cooling and Cleanup (G41) and Standby Liquid Control SLC (C41) systems' functions.

(C) Fuel Pool Cooling and Cleanup (G41) valves are not required since they are in series with unaffected P41 valves.

(D) The standby liquid control (C41) pump is not required.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RCIC system is available.

(B) Remainir g Division II systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division II systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-80 April 1983

SEGMENT 112-04 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

() 1. SYSTEMS IMPACTED:

C41, G41, P42

! (A) Division I Systems:

(B) Division II Systems: C41, C61, G41, P42, T46 l (C) Division III Systems: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I SLC (C41) system pump 1C41*P024A.

(B) Division I, II, and III RBCLCW (P42) system pump 4

1P42*P005A, B, and C.

(C) No credit taken for Division II and III systems' functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

(D) Division I Fuel Pool Cooling and Cleanup (G41)

Syste.n's valves.

, 3. DISABLED FUNCTION EVALUATION:

(A) Division I systems are available, except as noted.

(B) Division I SLC (C41) system is not required for normal shutdown.

(C) Loss of all three RBCLCW system pumps for the RHR pump j seal coulers is acceptable, because the Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available. However, the exposure of these l

pump motor cables is minimal and the risk is slight.

t (D) Division I Fuel Pool Cooling and Cleanup (G41) system valves are not required since isolation is maintained by in-series unaffected Service Water (P41) system valves.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using Division I RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

Original A-81 April 1983

SEGMENT 112-05 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: P42 (B) Division II Systems: C41, C61, Ell, E21, G33, G41, P41, P42, P50, T46 (C) Division III System: P42(C), T46(A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I systems are available, except RBCLCW (P42) systems.

(B) No credit taken for Division II systems' functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048, and the HPCI (E41) system.

(C) Division III systems are available except unit cooler 1T46*UCO22A and 22B, and RBCLCW (P42) system pump P42*POO5C.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Divisions I and III systems are available.

(B) Division II HPCI (E41) system is available.

(C) Division I, II, and III RBCLCW (P42) system pumps 1P42*P005A, B, and C, respectively, are not available.

Their loss eliminates the use of Division I RHR/CS/SRV flow path; however, and alternative RHR/CS/PRV flow path can be used.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

Cold shutdown is achievable using remaining systems or Division I RHR/CS/PRV flow path.

5. FURTHER ACTION RECOMMENDED:

None l

Original A-82 April 1983 l

SEGMENT 112-06 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT f

\ 1. SYSTEMS IMPACTED:

(A) Division I System: E51 (Division II components only)

(B) Division II Systems: B31, C41, C61, Ell, E21, E41 (Division II components), G33, P41, P42 P50, T46, (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I RCIC (E51) system.

(B) No credit taken for Division II systems' functions.

(C) Division II RHR (Ell) system shutdown cooling outboard

? solation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I and III systems are available.

O

(,,,/ (B) Division I RHR (Ell) system valve 1E11*MOV048 can be manually operated, or Division I and III RHR/CS/SRV circulation / suppression pool cooling flow paths are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Divisions I and III RHR/CS/SRV flow path.

Cold shutdown is achievable using Division I and III RHR (Ell) system with manual operation of valve 1E11*MOV048 or Division I and III RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None N

(Y Original 4 A-83 April 1983

SEGMENT 112-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: T46 (B) Division II Systems: C61, Ell, G33, P42, P50, T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I RBSVS (T46) system unit coolers 1T46*UC004A, OOSA, and 021A.

(B) No credit taken for Division II systems' functions, other than RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048, and remaining RBSVS (T46) system functions.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I systems and Division I RBSVS unit coolers are available.

(B) Remaining Division II RBSVS (T46) coolers are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division I and III systems.

5. FURTHER ACTION RECOMMENDED:

None SEGMENT 112-08 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C61, Ell, P41, P42, P50, T46 (B) Division II Systems: B31, Ell, C61, P42, P50, T46 (C) Division III Systems: T46(A,B)

Original O

A-84 April 1983

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit is taken for Division I systems functions.

() (B) Division II Reactor Recirculation (B31) Reactor Plant Remote Shutdown 1E11*MOVO31B, (C61) RHR (Ell) components 031D, 032B, 032D, 034B, 036B, 0403, 045 and 037B, RBSVS (T46) automatic isolation circuit and unit cooler 1T46*UCO21B, 004B, 005B, and RBCLCW (P42) component 1P42*P005B.

(C) Division II (P50) system component 1P50*MOV103B.

(D) No credit is taken for Division III systems functions.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I and II systems are available.

(B) Division II RBSVS (T46) automatic isolation and Unit Cooler 1T46*UCO21B, 004B, 005B and (C61) system is not needed for shutdown.

(C) Necessary Division II RHR (Ell) valves can be manually operated.

(D) Division II RBCLCW (P42) component IP42*P005B is not required since CS/PRV flow path is available.

/{'j (E) Division I or II CS (E21) system is available.

V (F) Division II compressed air (P50) system component 1P50*MOV103B will fail in the open position allowing the system to function.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division II HPCI (E41) system.

l Cold shutdown is achievable using the Division II CS/PRV l flow path can be used with RHR for pool cooling via manual valve operation, as required.

5. FURTHER ACTION RECOMMENDED:

None b ' Original A-85 April 1983

1 SEGMENT 150-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: B31, C61, Ell, P41, P42, P50, T46 (B) Division II Systems: C61, Ell, P42, P50, T46 (C) Division III Systems: P42(C), T46(A, B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems functions except RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047, the RCIC (E51) and CS (E21) systems' functions.

(B) No credit taken for Division III systems functions.

(C) No credit taken for Division II RBSVS (T46) unit coolers 1T46*UCO21B, 004B, and 005B, Reactor Plant Shutdown (C61) system, RHR (Ell) system valves 1E11*MOV036B, 045B, 037B, 031D, 032B, 040B, 031B, 034B, RBCLCW(P42) and Compressed Air (P50) valve 1P50*MOV103B.

(D) No credit taken for Division II RHR (Ell) except for system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Division I RCIC (E51) is available.

(B) Remaining Division II systems are available.

Necessary Division II RHR (Ell) valves can be manually operated.

(C) Divisic.n I or II CS (E21) system is available.

(D) Division II Compressed Air (P50) valve 1P50*MOV103B will fail in the open position allowing the system to remain available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) or Division II HPCI (E41) systems.

Original O

! A-86 April 1983

1 Cold shutdown; is achievable using the Division II CS/PRV flow path with' Division II RHR used for pool cooling _ via manual operation.

5. FURTHER ACTION RECOMMENDED:

None SEGMENT 150-N2 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None

, (B) Division II Systems: None i

(C) Division III. Systems: None

2. . SYSTEMS' FUNCTIONS DISABLED:

None

, 3. DISABLED FUNCTION EVALUATION:

No effect on shutdown.

4. SHUTDOWN CAPABILITY:

! Hot and cold shutdown are achievable using Division I, II, i

and III systems.

t

5. FURTHER ACTION RECOMMENDED:

l.

r .

l None s

l i

O Original l

A-87 April 1983 i

i I

- ,. ,--,.,,,-7,-r -...r.... ,,,,,._,.na,,,.,.n,,r-e.wnn-,,,w e.....m,,w-r -, -er a e,4-~,-,--.mwear-n.,-ven---e, .--w->--mr+r"- - ri-,-- ~--- -

SEGMENT 150-N3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I System: G41 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

Division I Fuel Pool Cooling and Cleanup (G41) system valve 1G41*MOV032A.

3. DISABLED FUNCTION EVALUATION:

(A) Division I Fuel Pool Cooling and Cleanup (G41) system valve 1G41*MOV032A is in series with Service Water (P41) system valve 1P41*MOV042A; therefore, there is no impact on either system.

(B) Division I, II, and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, k and III systems.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-88 April 1983

SEGMENT 150-N4 CABLE SEPARATION ANALYSIS 7-~s SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: Ell, E21, G41, P41, P42, P50 (B) Division II Systems: G41, P42 (C) Division III System: P42 (C)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I system function other than RC1C(E51) system and RHR(Ell) system shutdown outboard valve 1E11*MOVO47.

(B) Division II and III RBCLCW (P42) system pumps 1P42*FOO5B and C, respectively.

(C) Division II Fuel Pool Cooling (G41) system valve 1G41*MOVO32B.

3. DISABLED FUNCTION EVALUATION:

(A) Loss of all three RBCLCW (P42) system puraps for the

(~N RHR pump seal coolers is acceptable, because the

(,,) Division II RHR/CS/SRV circulation / suppression pool cooling flow path is available. However, the exposure of these pump motor cables is minimal and the risk of common damage is slight.

(B) Loss of Division I and II Fuel Pool Cooling (G41) systems valves are not required for normal shutdown and will not prevent operation of the system. They are in series with unaffected Service Water (P41) system valves. Division I Service Water (P41) valve will remain closed wile Division II valve is unaffected.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using the Division I RCIC (E51) system or the Division II HPCI (E41) system.

Cold shutdown is achievable using the Division II RHR/CS/SRV flow path.

5. FURTHER ACTION RECOMMENDED:

None L./'

Original A-89 April 1983

1 SEGMENT 150-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: P42 (B) Division II Systems: C61, Ell, E21, G41, P41, P42, P50, T46 (C) Division III System: P42 (C)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I and III RBCLCW (P42) system pumps 1P42*P005B and C, respectively.

(B) No credit taken for Division II system functions other than RHR (Ell) valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

(A) Loss of all three RBCLCW (P42) system pumps for the RHR pump seal coolers is acceptable, because the Division I RHR/CS/SRV circulation / suppression pool cooling flow path is available. However, the exposure of these pump motor cables is minimal and the risk of common damage is slight.

(B) Division II Fuel Pool Cooling (G41) system valve has no impact due to in-series Service Water (P41) system valve which will remain closed upon failure.

(C) Division I and III RBSVS (T46) are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I or II RHR/CS/3RV flow path.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-90 April 1983

SEGMENT 150-N6 CABLE SEPARATION ANALYSIS q SECONDARY CONTAINMENT NY

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: C61, Ell, E21, G41, P41, P50

(C) Division'III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division II system functions.

3. DISABLED FUNCTION EVALUATION:

4 Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I and III systems.

5. FURTHER ACTION RECOMMENDED

None I

i

\,

Criginal A-91 April 1983

_- - . - . . . - _ _ . . . . _ - . _ . . _ , - - _ . _ . . . ~ . _ . , _ . . _ . ~ _ _.

SEGMENT 150-N7 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I Systems: None (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

No effect on shutdown.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None Original O

A-92 April 1983

4 SEGMENT 150-N8 CABLE SEPARATION ANALYSIS

. SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: T46 (B) Division II Systems: C61, Ell, P42, PSO, T46 (C) Division III Systems: T46 (B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I RBSVS (T46) system unit coolers 1T46*UC004A and 005A.

(B) No credit taken for Division II system functions, other than RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048 and remaining RBSVS (T46) unit coolers.

(C) Division III RBSVS (T46) systems unit cooler 1T46*VCO22B is not required since other T46 components are available.

3. DISABLED FUNCTION EVALUATION:

(A) Remaining Division I and III systems and remaining T46 unit coolers are available.

i (B) Remaining Division II RBSVS (T46) coolers available.

l (C) Division III RBSVS (T46) systems unit cooler 1T46*VCO22B is not required since other T46 components are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division I, II and III systems.

5. FURTHER ACTION RECOMMENDED:

l None lt l

A-93 Original April 1983 l

l

SEGMENT 150-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: T46 (B) Division II Systems: None (C) Division III Systems: P42 (C), T46 (A, B)

2. SYSTEMS' FUNCTIOils DISABLED:

(A) No credit taken for Division I systems' functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

(B) No credit taken for Division III systems' functions.

3. DISABLED FUNCTION EVALUATION:

Division II systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II systems.

5. FURTHER ACTION RECOMMENDED:

None O

Original A-94 April 1983

SEGMENT 150-02 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

.O,

1. SYSTEMS IMPACTED:

i (A) Division I Systems: None (B) Division II Systens: None (C) Division III Systems: None

2. -SY3TEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

l No effect an shutdown.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II,

and III systems.

l

5. FURTHER ACTION RECOMMENDED:

! None i

N J

l 6

O Original A-95 April 1983

. . . . - . - . - ~ - - - - . - - . - - - . . , - . . - . . - - . ~ , _ - _ , . _ , - - , - , - . _ . . . ....

SEGMENT 150-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I System: Ell, E21, G41, P41, P50 (B) Division II System: G41 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems functions other than Division I RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047 and RCIC (E51) system.

(B) Division II Fuel Pool Cooling (G41) system valve 1G41*MOV032B.

3. DISABLED FUNCTION EVALUATION:

Division I and II Fuel Pool Cooling (G41) systems are not required for normal shutdown. G41 system valves are in series with unaffected Division I (P41) system valves which will fail in the closed position enabling the system to remain functional.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using remaining Division I and II, and Division III systems.

5. FURTHER ACTION RECOMMENDED:

None O

Original A-96 April 1983

SEGMENT 150-04 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

O 1. SYSTEMS IMPACTED:

(A) Division I System: P42 (B) DAvision II Systems: G41, P42 (C) Division III System: P42 (C)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) Division I, II, and III RBCLCW (P42) system pumps 1P42*POO5A, B, and C, respectively (B) Division II Fuel Pool Cooling (G41) system valve 1G41*MOVO32B.

3. DISABLED FUNCTION EVALUATION:

(A) Loss of all three RBCLCW system pumps for the RHR pump seal coolers is acceptable, because the Division I or II RHR/CS/SRV circulation / suppression pool cooling flow path is available. The exposure of these pump motor cables is minimal and the risk of common damage is slight.

(B) Division II Fuel Pool Cooling (G41) system valve 1G41*MOVO32B is not required due to the in-series unaffected Service Water (P41) system valve.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using the Division I or II RHR/CS/SRV flow path.

S. FURTHER ACTION RECOMMENDED:

None O

Original A-97 April 1983

SEGMENT 150-05 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: C61, Ell, E21, G41, P41, P50 T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division II systems' functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1 Ell *MOV048.

3. DISABLED FUNCTION EVALUATION:

Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I and III systems.

5. FURTHER ACTION RECOMMENDED:

None O

Original A-98 April 1983

SEGMENT 150-06 CABLE SEPARATION ANALYSIS

SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None

, '(B) Division II Systems: None j (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

i No effect on shutdown.

I 4. SHUTDOWN CAPABILITY:

, Hot and cold shutdown are achievable using Division I, II, 1 and III systems.

5. FURTHER ACTION RECOMMENDED:

None

.i i

i I

i i

i

\

O

! Original I

A-99 April 1983 i

_ . _ . . . - . . . . . . _ . _ . . . _ - . . - _ - - _ . , , . . _ _ _ . . . _ , _ _ . . ~ . _ _ , . _ _ , . . , _ , _ _ _ . _ _ _ , . . _ _ _ _ _ , . . . , _ , , . . . , . _ , , . , . , _ . _ , . _ . _ , . , . . , _ . _ _ _

SEGMENT 150-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

No effect on shutdown.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None O

O Original A-100 April 1983

SEGMENT 150-08 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

/

i ) 1. SYSTEMS IMPACTED:

N (A) Division I Systems: B31, C61, Ell, P41, P42, P50 T46 (B) Division II Systems: C61, Ell, P42, P50, T46 (C) Division III Systems: P42 (C), T46 (A,B)

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I systems other than RCIC (E55) and RHR (Ell) valve 1E11*MOV047 (B) No credit taken for Division III systems' functions.

(C) No credit taken for Division II RBSVS (T46) unit cooler 1T46*UCO21B, 005B, 004B, RBCLW (P42) and Reactor Plant Remote Shutdown (C61) systems' functions.

(D) Division II_ RHR (Ell) components 1E11*MOV031B, 031D, 032B, 032D, 034B, 036B, 037B, 040B, and 045B.

(E) Division II Compressed Air (P50) valve 1P50*MOV103B.

!D

(_,) 3. DISAELED FUNCTION EVALUATION:

(A) Division I'RCIC (E51) system is available.

(B) Division II HPCI (E41), and the remainder of RBSVS (T46) is available.

(C) Necessary Division II RHR (Ell) valves can be manually operated.

(D) Division I or II CS is available for RPV makeup.

(E) Division II system valve 1P50*MOV103B will fail in the open position allowing the system to remain functional.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using either Division II HPCI (E41) or Division I RCIC (E51) systems.

Cold shutdown is achievable using the Division II CS/PRV flow path with RHR operated in pool cooling and valves operated manually as required.

O

\. J

5. FURTHER ACTION RECOMMENDED:

None Original l A-101 April 1983 1

SEGMENT 175-N1 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. S" STEMS IMPACTED:

O (A) Division I System: T46 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I systems' functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems.

5. FURTHER ACTION RECOMMENDED:

None O Original A-102 April 1983 O

SEGMENT 175-N2 CABLE SEPARATION ANALYSIS g SECONDARY CONTAINMENT J

1. SYSTEMS IMPACTED:

(A) Division I System: T46 (B) Division II Systems: None c

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1 Ell *MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems.

5. FURTHER ACTION RECOMMENDED:

None l

i l

Original fs A-103 April 1983 l

SEGMENT 175-N3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II System: T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using the Division I and III systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-104 April 1983 O

SEGMENT 175-N4 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT C-

1. SYSTEMS IMPACTED:

(A) Division I Systems: C61 (B) Division II System: E41 (Division I components only), T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I Reactor Plant remote shutdown (C61) system.

(B) No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

Remaining Division I and II systems, and Division III system are available.

p 4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using remaining Division I and II systems, nnd Division III systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-105 April 1983

SEGMENT 175-N5 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II System: T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1 Ell *MOV048.

3. DISABLED FUNCTION EVALUATION:

Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I and III systems.

5. FURTHER ACTION RECOMMENDED:

None 1

l l

l l Original l A-106 April 1983 l

l

. . _ _ . _ _ . . - . . - . - _ . = - - . - - - . - _ -

SEGMENT 175-N6 3 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II System: T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit. taken for Division II systems functions, other i than the RHR (Ell) system shutdown cooling . '? 'rd .

isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

Division I and III systems are available.

]

4. SHUTDOWN CAPABILITY:

l Hot and cold shutdown are achievable using Division I and III systems.

, 5. FURTHER ACTION RECOMMENDED:

None 4

?

4 Original A-107 April 1983 i

. - _ . . . , _ - _ , , . . . , , , . ._.._._._-__,-~___..-__..-,,_...-m_ _ - - . _ . _ , , . . . . , _ . . . . _ _ _ _ . , . - , _ . , - . . . _ , _ _ , . . , , . - . , - . -

SEGMENT 175-N7 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I System: T46 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISa6 LED:

No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-108 April 1983 O

SEGMENT 175-N8 CABLE SEPARATION ANALYSIS

,q SECONDARY CONTAINMENT

\

1. SYSTEMS IMPACTED:

(A) Division I System: T46 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems.

(s 5. FURTHER ACTION RECOMMENDED:

'b None Original A-109 April 1983 (D

v

SEGMENT 175-01 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I System: T46 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' EUNCTIONS DISABLED:

No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems.

5. FURTHER ACTION RECOMMENDED:

None Original

.\-110 April 1983 O

. - _ - . _ . ._ =_ _ .-

i SEGMENT 175-02 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

%/

1. SYSTEMS IMPACTED:

(A) Division I Systems: None (B) Division II Systems: None (C) Division III Systems: None 1

) 2. SYSTEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

Division I, II, and III systems are available.

. 4. SHUTDOWN CAPABILITY:

l Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None r

l l

(

Original A-111 April 1983

SEGMENT 175-03 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT O

1. SYSTEMS IMPACTED:

(A) Division I Systems: C61 (B) Division II System: E41 (Division 1 components only), T46 (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

(A) No credit taken for Division I Reactor Plant Remote Shutdown (C61) system.

(B) No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED FUNCTION EVALUATION:

Remaining Division I and II Systems and Division III systems are available.

4. SHUTDOWN CAPABILITY:

Hot shutdown is achievable using Division I RCIC (E51) system.

Cold shutdown is achievable using the remaining Division I and II systems and Division III systems.

5. FURTHER ACTION RECOMMENDED:

None Original A-112 April 1983 O

SEGMENT 175-04 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT f.

N.

1. SYSTEMS IMPACTED:

(A) Division I Systems: C61 (B) Division II System: E41 (Division I components only), T46 (C) Division III Systems: None

2. SYSTEMS' EUNCTIONS DISABLED:

(A) No credit for Division I Reactor Plant Remote Shutdown (C61) system.

(B) No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1E11*MOV048.

3. DISABLED EUNCTION EVALUATION:

Remaining Division I and II systems and Division III systems are available.

f- 4. SHUTDOWN CAPABILITY:

Hot shutdown using Division is achievable I RCIC (E51) system.

Cold shutdown is achievable using remaining Division I and II systems, and Division III systems.

5. FURTHER ACTION RECOMMENDED:

l l None l

i l Original l A-113 April 1983 O

V i

u

SEGMENT 175-05 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I Systems: None (B) Division II System: T46 (C) Division III Systems: None

2. SYSTEMS' EUNCTIONS DISABLED:

No credit taken for Division II systems functions, other than the RHR (Ell) system shutdown cooling outboard isolation valve 1 Ell *MOV048.

3. DISABLED FUNCTION EVALUATION:

Division I and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I and III systems.

5. FURTHER ACTION RECOMMENDED:

None r

Original A-114 April 1983 O

SEGMENT 175-06 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT b

v

1. SYSTEMS IMPACTEDi (A) Division I Systems: 1]one (B) Division II Systems: .None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

None

3. DISABLED FUNCTION EVALUATION:

No effect on shutdown.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division I, II, and III systems.

5. FURTHER ACTION RECOMMENDED:

None t

l

)

Original A-115 April 1983 O

SEGMENT 175-07 CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

1. SYSTEMS IMPACTED:

O (A) Division I System: T46 (B) Division II Systems: None (C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I systems functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1 Ell *MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems.

5. FURTHER ACTION RECOMMENDED:

None Original l

A-116 April 1983

. G 1

f l

, SEGMENT 175-08

' CABLE SEPARATION ANALYSIS SECONDARY CONTAINMENT

O 1. SYSTEMS IMPACTED:

(A) Division I System: T46 (B) Division II Systems: None "

(C) Division III Systems: None

2. SYSTEMS' FUNCTIONS DISABLED:

No credit taken for Division I systems' functions, other than the RHR (Ell) system shutdown cooling inboard isolation valve 1E11*MOV047.

3. DISABLED FUNCTION EVALUATION:

Division II and III systems are available.

4. SHUTDOWN CAPABILITY:

Hot and cold shutdown are achievable using Division II and III systems. '

5. FURTHER ACTION RECOMMENDED:

i O. None t

Original

A-117 April 1983 O

- - - _ _ - . _. _ _ _ . - - . . - . . _ . . - . . . _ - - _ = _ _ - . . _ . - = . . . _._. . - .. . - - = - - - .-

i f

1 1 I

, i I

i lO 1

l i

l I

s 1 a

i 1

i I

i !

a b

I i

1 +

b i

t APPENDIX B .

l, DRAWINGS ',

1O i

i t

i

!l l

t F

i P

t i

P r

G Original April 1983 i

i I'

ELEV. 8' Ih Drawing Print

\/ % Number Revision Title SK-C/J-C-FE46A-1 31 Conduit Plan Elev. 8' Northside

Reactor SK-C/J-C-FE46A-2 10 Conduit Sections & Details North Reactor Bldg. Elev. 8' SK-C/J-C-FE46A-3 9 Conduit Sections, Details & Partial

{

Plan Elev. 8' North SK-C/J-C-FE46A-4 15 conduit Sections Elev. 8' North Reactor Bldg.

I

SK-C/J-C-FE46A-5 2 Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46A-6 11 Conduit Sections & Plan View Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46A-7 3 Conduit Sections Elev. 8' North l

Reactor Bldg.

l s SK-C/J-C-FE46A-8 7 Conduit Sections Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46A-9 5 Conduit Support Details Elev. 8' North Reactor Bldg.

l SK-C/J-C-FE46A-10 2 Conduit Layout Elev. 8' Column 7 i

SK-C/5-C-FE46A-11 - Conduit Layout Elev. 8' Column 8 SK-C/J-C-FE46A-12 -

Conduit Layout Elev. 8' Column 9 SK-C/J-C-FE46A-13 0 Conduit Sections & Details Elev. 8' SK-C/J-C-FE46A-14 1 Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46A-15 1 Conduit Sections & Details Elev. 8' North SK-C/J-C-FE46A-16 -

Conduit Sections & Details Elev. 8' Northeast Side Reactor Bldg.

SK-C/J-C-FE46A-17 -

Conduit Sections & Details Elev. 8' Reactor Bldg.

B-1 Original l April 1983 l

l

Drawing Print Number Revision Title SK-C/J-C-FE46A-18 -

Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46A-19 -

Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46AA-1 25 Conduit Plan & Sections Elev. 8' RCIC Northeast SK-C/J-C-FE46AA-2 14 Conduit Supports & Sections Elev. 8' RCIC Area SK-C/J-C-FE46AA-3 13 Conduit Supports & Sections Elev. 8' RCIC Area SK-C/J-C-FE46AA-4 6 Conduit Supports & Sections Elev. 8' RCIC Area SK-C/J-C-FE46AA-5 13 Conduit Sections & Details Elev. 8' Northside SK-C/J-C-FE46AA-6 3 Conduit Sections & Details Elev. 8' North SK-C/J-C-FE46AA-7 3 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46AA-8 4 Conduit Supports, Sections &

Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46AA-9 1 Conduit Sections & Details Elev. 8' SK-C/J-C-F. 'AA-10 Conduit Sections & Details 2

Elev. 8' Northside Reactor Bldg.

SK-C/J-C-FE46AA-11 -

Conduit Sections & Details Elev. 8' Northeast Side Reactor Bldg.

SK-C/J-C-FE46AA-12 -

Conduit Sections & Details Elev. 8' Northeast Side Reactor Bldg.

SK-C/J-C-FE46AAA-1 25 Conduit Plan Elev. 8' North Reactor SK-C/J-C-FE46AAA-2 5 Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46AAA-3 1 Conduit Details Elev. 8' North Reactor Bldg.

B-2 Original O

April 1983

h Drawing Print Number Revision Title b

\-- SK-C/J-C-FE46AAA-4 2 Conduit Sections & Details Elev. 8' North Reactor-Bldg.

SK-C/J-C-FE46AAA-5 4 conduit Sections & Details Elev. 8' North Reactor Bldg.

?

SK-C/J-C-FE46AAA-6 1 Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46AAA-7 1 Conduit Supports, Sections &

i Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46AAA-8 2 Conduit Supports, Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46AAA-9 2 Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46AAA-10 0 Conduit Sections & Details Elev. 8' Secondary Containment SK-C/J-C-FE46AAA-11 1 Conduit Sections, Details & Views Elev. 8' Secondary Contaimnent SK-C/J-C-FE46AAA-12 3 Conduit Sections & Details

< Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46AAA-13 1 Conduit Supports, Sections &

Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46AAA-14 1 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK ;/1-C-FE46AAA-15 1 Conduit Supports, Sections &

Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46B-1 30 Cond. t Plan & Sections Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-2 2 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-3 1 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-4 -

Conduit Sections & Details Elev. 8' South Reactor Bldg.

^

SK-C/J-C-FE46B-5 2 Cond__t Sections & Details Elev. 8' South Reactor Bldg.

k B-3 Original April 1983

. - , , ~ _ , _ . - . _ . _ - _ - - _ _ _ . _ _ . _ . _ - _ _ _ - - - _ - _ - . _ _ _ - _ . . - . _ _ . . _ - . - . . - . . _ ,

Drawing Print flumber Revision Title SK-C/J-C-FE46B-6 11 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-7 3 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-8 3 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-9 1 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-10 5 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-ll 1 Conduit Sectionr. Plan Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-12 VOID Conduit Sections & Details Elev. 8' SK-C/J-C-FE46B-13 1 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46B-14 2 Conduit Sections Plan Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46BB-1 14 Conduit Sections Plan Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46BB-2 3 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46BB-3 1 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46BB-4 3 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46BB-5 2 Conduit Sections & Details Elev. 8' South Reactor Bldg.

SK-C/J-C-FE46BB-6 4 Conduit Support Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46X-1 38 Conduit Plan Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-2 9 Conduit Sections & Details Elev. 8' West Reactor Bldg.

B-4 Original O

April 1983

Drawing Print Number Revision Title

,o

( I

\/ SK-C/J-C-FE46X-3 11 Conduit Sections & Elev. Views Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-4 5 Conduit Sections Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-5 4 Conduit Sections Elev. 8' Reactor Bldg.

SK-C/J-C-FE46X-6 6 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-7 0 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-8 3 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-9 VOID Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-10 1 Conduit Sections & Details Elev. 8' West Reactor Bldg.

g- 3 SK-C/J-C-FE46X-11 1 Conduit Sections & Details Elev. 8' i ) West Reactor Bldg.

SK-C/J-C-FE46X-12 3 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46X-13 2 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-14 1 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46X-15 1 Conduit Sections & Details Elev. 8' North Reactor Bldg.

SK-C/J-C-FE46X-16 1 Conduit Layout Column 11 Elev. 8' l SK-C/J-C-FE46X-17 0 Conduit Layout Column 12 Elev. 8' l

SK-C/J-C-FE46X-18 0 Conduit Layout Column 10 Elev. 8' SK-C/J-C-FE46X-19 1 Conduit Sections & Details Elev. 8' West Reactor Bldg.

l SK-C/J-C-FE46X-20 1 Conduit Sections & Details l Elev. 8' West Reactor Bldg.

/

V) B-5 Original April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46X-21 -

Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-22 1 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-23 -

Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46X-24 0 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46X-25 -

Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46XX-1 22 Conduit Plan Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46XX-2 2 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46XX-3 5 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46XX-4 3 Conduit Support Sections &

Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46XX-5 1 Conduit Support Sections &

Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46XX-6 5 Conduit Sections & Details Elev. 8' West Reactor Bldg.

SK-C/J-C-FE46XX-7 3 Conduit Sections & Details Elev. 8' West Reactor Bldg.

l SK-C/J-C-FE46XX-8 1 Conduit Sections & Details Elev. 8' Reactor Bldg.

i SK-C/J-C-FE46XX-9 3 Conduit Sections & Details Elev. 8' Southwest Pilaster i

l SK-C/J-C-FE46XX-10 -

Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46XX-11 -

Conduit Sections & Details Elev. 8' Southwest Pilaster j SK-C/J-C-FE46Y-1 38 Plan & Sections Elev. 8' East 1

B -6 Original O

April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46Y-2 7 Conduit Sections & Elev. Views East Reactor Bldg.

SK-C/J-C-FE46Y-3 -

Conduit Sections Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-4 11 Conduit Sections Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-5 9 Conduit Sections Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-6 -

No Title SK-C/J-C-FE46Y-7 3 Conduit Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-8 8 Reactor Index Elev. 8' SK-C/J-C-FE46Y-9 4 Conduit Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-10 1 Conduit Sections & Details

/%.

Elev. 8' East Reactor Bldg.

_, SK-C/J-C-FE46Y-ll 0 Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-12 -

Conduit Layout Elev. 8' Column 4 SK-C/J-C-FE46Y-13 0 Conduit Layout Elev. 8' Column 5 SK-C/J-C-FE46Y-14 1 Conduit Layout Elev. 8' Column 6 SK-C/J-C-FE46Y-15 -

Conduit Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46Y-16 4 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46YY-1 27 Conduit Plan Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46YY-2 6 Conduit Sections & Details Elev. 8' East SK-C/J-C-FE46YY-3 6 Conduit Sections Elev. 8' East Reactor Bldg.

~- A B-7 Original April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46YY-4 5 Conduit Plan Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46YY-5 4 Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46YY-6 0 Conduit Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46YY-7 3 Conduit Support Sections &

Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46YY-8 1 Sections & Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46YY-9 ? Sections & Details Elev. 8' East SK-C/J-C-FE46YY-10 1 Conduit Support Details Elev. 8' East Reactor Bldg.

SK-C/J-C-FE46YY-11 3 Conduit Support Details &

Views Elev. 8' North SK-C/J-C-FE46YY-12 1 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46YY-13 1 Conduit Sections & Details Elev. 8' Reactor Bldg.

SK-C/J-C-FE46YY-14 0 Conduit Sections & Details Elev. 8' Reactor Bldg.

l B-8 Original O

April 1983 1

. .m . _ _ . - . __ _ _ _ _. _ __ _ _ - _ _ _ _ . ._ . - m _

i i

i ELEV. 40' Drawing Print k Number Revision Title SK-C/J-C-FE46C-1 44 Plan & Sections Elev. 40' North

, SK-C/J-C-FE46C-2 2 Sections & Details Elev. 40' North .

SK-C/J-C-FE46C-3 1 Conduit Sections Elev. 40' North SK-C/J-C-FE46C-4 7 Part Plan Elev. 40' Northeast SK-C/J-C-FE46C-5 1 Conduit Sections & Details Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46C-6 4 Sections & Details Elev. 40' North Side ;

SK-C/J-C-FE46C-7 2 Conduit Sections & Details North SK-C/J-C-FE46C-8 1 Conduit Sections & Details North l SK-C/J-C-FE46C-9 8 Conduit Support Sections &

Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-10 6 Conduit Support Sections &

Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-11 5 Conduit Support Sections & l Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-12 1 Conduit Support Sections &

Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-13 8 Conduit Support Sections &

Details Elev. 40' SK-C/J-C-FE46C-14 -

Cond_.t Layout Elev. 40' Column 6 i

SK-C/J-C-FE46C-15 -

! SK-C/J-C-FE46C-16 -

Conduit Layout Elev. 40' Column 8 i

SK-C/J-C-FE46C-17 0 Conduit Layout Elev. 40' Column 9 SK-C/J-C-FE46C-18 -

-Conduit Layout Elev. 40' Column 10 i

! SK-C/J-C-FE46C-19 -

Conduit Layout Elev. 40' Column 11 SK-C/J-C-FE46C-20 3 Cond ;t Sections & Details I

B-9 Original April 1983 e

,,w-m., - vor-., ,--...w,,. - - , , .. .,,- - , ,,,,, m-,,, -,,,-,my,-.*,-n.c_.y..,,y_ -..w,,-,-y.ww.,v-,-----,.m,mye,- , ,,w. w- --e-- ..,--.-,%,,,. --

Drawing Print Number Revision Title SK-C/J-C-FE46C-21 1 Conduit Sections & Details Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46C-22 3 Conduit Support Details Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46C-23 2 Conduit Sections & Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-24 -

Conduit Support Sections &

Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-25 -

Conduit Support & Bracing Details Elev. 40' Reactor Bldg.

SK-?/J-C-FE46C-26 -

Conduit Support & Bracing Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-27 2 Conduit Support & Bracing Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46C-28 -

Conduit Sections & Views Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46CC-1 7 Conduit Plan Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46CC-2 1 Conduit Sections & Details Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46CC-3 1 Conduit Support Sections &

Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46CC-4 1 Conduit Support Sections &

Details Elev. 40' Reactor Bldq.

SK-C/J-C-FE46CC-5 0 Cond_:t Support Sections & Details Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46CC-6 3 Conduit Sections & Details Elev. 40' North Reactor Bldg.

SK-C/J-C-FE46CC-7 -

Conduit Support Sections &

Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46D-1 52 Plan & Sections Elev. 40' South SK-C/J-C-FE46D-2 7 Sections Elev. 40' South SK-C/J-C-FE46D-3 5 Sections & Details Elev. 40' South B-10 Original O

April 1983

Drawing Print llumber Revision Title f3

( l

\m / SK-C/J-C-FE46D-4 12 Enlarged Plan Sections & Details Elev. 40' South SK-C/J-C-FE46D-5 7 Sections & Details Elev. 40' South SK-C/J-C-FE46D-6 6 Details Elev. 40' SK-C/J-C-FE46D-7 14 Sections & Details Elev. 40' SK-C/J-C-FE46D-8 7 Enlarged Plan Sections & Details Elev. 40' South Column 4 SK-C/J-C-FE46D-9 0 Enlarged Plan Sections & Details Elev. 40' South Column 4 SK-C/J-C-FE46D-10 0 Conduit Sections & Details Elev. 40' South Side Reactor Bldg.

SK-C/J-C-FE46D-11 9 Plan & Sections Elev. 40' SK-C/J-C-FE46D-12 13 Sections & Details Elev 40' South SK-C/J-C-FE46D-13 6 Conduit Support Sections & Details Elev. 40' Feactor Bldg.

(ry

' ') SK-C/J-C-FE46D-14 3 Conduit Support Sections & Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46D-15 4 Conduit Sections Elev. 40' South Side SK-C/J-C-FE46D-16 2 Conduit Sections & Details Elev. 40' South Reactor Bldg.

SK-C/J-C-FE46D-17 2 Conduit Layout Elev. 40' Column 1 SK-C/J-C-FE46D-18 0 Cond_ t Layout Elev. 40' Column 2 SK-C/J-C-FE46D-19 2 Conduit Layout Elev. 40' Column 3 SK-C/J-C-FE46D-20 0 Conduit Layout Elev. 40' Column 4 SK-C/J-C-FE46D-21 -

Conduit Layout Elev. 40' Column 5 SK-C/J-C-FE46D-22 2 Conduit Layout Elev. 40' Column 12 SK-C/J-C-FE46D-23 3 Strip Plate Details Elev. 40' Primary Containment

(~~\ ~

)

~

'x m

B-11 Original April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46D-24 7 Conduit Sections & Details Elev. 40' Reactor Bldg. .

SK-C/J-C-FE46D-25 1 Conduit Sections & Details Elev. 40' Reactor Bldg.

SK-C/J-C-FE46D-26 4 Conduit Sections & Details Elev. 40' South Side Reactor Bldg.

SK-C/J-C-FE46D-27 4 Part Plan, Sections & Details Elev. 40' South Reactor Bldg.

SK-C/J-C-FE46D-28 2 Conduit Sections & Details Elev. 40' South Reactor Bldg.

SK-C/J-C-FE46D-29 -

flo Title SK-C/J-C-FE46D-30 1 Conduit Sections & Details Elev. 40' South Side Reactor Bldg.

O t

t l

B-12 Original O

April 1983

. . = .. - .

ELEV. 63' i

i O Drawing Number Print Revision Title SK-C/J-C-FE46AC-1 3 Conduit Plan & Sections i Suppression Chamber SK-C/J-C-FE46AC-2 2 Conduit Part Plan & Sections Suppression Chamber SK-C/J-C-FE46AC-3 1 Part Plan & Sections Suppression Chamber ,

SK-C/J-C-FE46AC-4 1 Conduit Part Plan & Sections Suppression Chamber SK-C/J-C-FE46AC-5 1 Conduit Part Plan & Sections Suppression Chamber SK-C/J-C-FE46E-1 30 Conduit Plan Elev. 63' Northeast Side SK-C/J-C-FE46E-2 2 Sections & Details Elev. 63' SK-C/J-C-FE46E-3 26 Conduit Plan-Elee. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-4 4 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-5 2 Conduit Sections & Details

Elev. 63 Northwest Reactor Bldg.

SK-C/J-C-FE46E-6 10 Conduit Plan & Sections Elev. 63' I North CRD Unit SK-C/J-C-FE46E-7 4 Conduit Sections & Details i SK-C/J-C-FE46E-8 5 Conduit Sections & Details Elev. 63' North Reactor Bldg.

SK-C/J-C-FE46E-9 6 Conduit Sections & Details Elev. 63' Northeast Reactor Bldg.

SK-C/J-C-FE46E-10 4 Conduit Sections & Details Elev. 63' North Reactor Bldg.

SK-C/J-C-FE46E-11 1 Conduit Support Details Excess Flow Valves P1 "E" d

B-13 Original April 1983

-- -e:>, i---- % -,,i-m -- .-c.~-w--

- ,r-, +

c ., - y e, -,--g y on et.--,-,re---,----grac. - - g' - -- ,,ey,e- w g- y o

Drawing Print Number Revision Title SK-C/J-C-FE46E-12 9 Conduit Plan & Section Elev. 63' Northeast Side SK-C/J-C-FE46E-13 7 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-14 3 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-15 3 Ambient Temperature Elements Plan Sections & Details Elev. 63'

~

SK-C/J-C-FE46E-16 6 Conduit Plan & Sections Elev. 63' Northeast Side c:;-C/J-C-FE46E-17 3 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-18 7 Conduit Sections & Details Elev. 63' Northeast Reactor Bldg.

SK-C/J-C-FE46E-19 5 Ambient Temperature Elementt Sections & Details Elev. 63' SK-C/J-C-FE46E-20 9 Conduit Plan E32 System SK-C/J-C-FE46E-21 7 Conduit Sections Elev. 63' E32 System SK-C/J-C-FE46E-22 4 Conduit Sections & Details Elev. 63' E32 System SK-C/J-C-FE46E-23 5 Conduit Support Details Elev. 63' North Reactor Bldg.

SK-C/J-C-FE46E-24 3 Conduit Sections & Details Elev. 63' North SK-C/J-C-FE46E-25 3 Conduit Sections & Support Details Elev. 63' West Beactor Bldg.

SK-C/J-C-FE46E-26 4 Conduit Sections & Details Elev. 63' West Reactor Bldg.

SK-C/J-C-FE46E-27 3 Conduit Sections & Support Details Elev. 63' West Reactor Bldg.

SK-C/J-C-FE46E-28 3 Conduit Supports, Sections & Details Elev. 63' North Reactor Bldg.

B-14 Original April 1983

t

Drawing' Print

! Number Revision Title SK-C/J-C-FE46E-29 4 Conduit Sections & Details Elev. 63' E32 System SK-C/J-C-FE46E-30 VOID SK-C/J-C-FE46E-31 1 Conduit Details Elev. 63' l

i .SK-C/J-C-FE46E-32 3 Conduit Sections & Support Details Elev. 63' East Reactor Bldg.

SK-C/J-C-FE46E-33 6 Conduit Support, Sections & Details Elev. 63' East & West SK-C/J-C-FE46E-34 8 Conduit Sections & Details Elev. 63' Reactor Bldg.

'SK-C/J-C-FE46E-35 1 Conduit Support Details Excess Flow Waves Northeast SK-C/J-C-FE46E-36 3 Er.larged Plan, Sections & Details Sep Reduct & Doc Elev. 63' Reactor Bldg.

1 SK-C/J-C-FE46E-37 2 Conduit Support Sections &

Details Elev. 63' SK-C/J-C-FE46E-38 1 Conduit Support Sections Excess 4

Flow Valves SK-C/J-C-FE46E-39 1 Conduit Support Sections

SK-C/J-C-FE46E-40 2 Conduit Support Sections &

[ Details Elev. 63'

)

l SK-C/J-C-FE46E-41 2 Conduit Sections & Details Elev. 63' Nort +ast Side Reactor Bldg.

SK-C/J-C-FE46E-42 0 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

I SK-C/J-C-FE46E-43 3 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-44 -

Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-45 - Conduit Supports & Sections

> Elev. 63' North f k. B-15 Original April 1983

Dmving Print Number Revision Title SK-C/J-C-FE46E-46 1 Conduit Plan Elev. 63' East Mech Room SK-C/J-C-FE46E-47 0 Conduit Sections & Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-48 -

Conduit Support Details Elev. 63' Northwest Reactor Bldg.

SK-C/J-C-FE46E-49 0 SK-C/J-C-FE46E-50 0 Conduit Support Details Elev. 63' Reactor Bldg.

SK-C/J-C-FE46F-1 VOID Conduit Plans & Sections Elev. 63' South Reactor Bldg.

SK-C/J-C-FE46F-2 2 Conduit Plans & Sections Elev. 63' South Reactor Bldg.

SK-C/J-C-FE46F-3 3 Conduit Supports & Details Elev. 63' East Reactor Bldg.

SK-C/J-C-FE46F-4 2 Conduit Partial Plan & Details Excess Flow Valves Plate 'G' Elev. 63' Southeast SK-C/J-C-FE46F-5 1 Conduit & Misc Details Elev. 63' South SK-C/J-C-FE46F-6 5 Sections & Details Elev. 63' South Reactor Bldg.

SK-C/J-C-FE46F-7 11 Conduit .'Isn Elev. 638 South Reaccor Bldg.

SK-C/J-C-FE46F-8 3 Cond_;t Support Details Elev. 63' Reactor Bldg.

SK-C/J-C-FE46F-9 2 Conduit Supports & Details East SK-C/J-C-FE46F-10 3 Conduit Sections Southwest SK-C/J-C-FE46F-11 1 Sections & Details Green Conduit System SK-C/J-C-FE46F-12 0 Sections & Details South SK-C/J-C-FE46F-13 0 Conduit Sections & Details West B-16 Original April 1983

_ _ _ _ _ = . _ _ _ _ _ _. . _ _ _ _ __

Drawing Print Number Revision Title SK-C/J-C-FE46F-14 0 Views & Details South .

SK-C/J-C-FE46F-15 1 Conduit Sections & Support Details East SK-C/J-C-FE46F-16 1 Conduit Plan West Mech Room l

l l

i l

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l B-17 Original April 1983

ELEV. 78' Drawing Print Number Revision Title SK-C/J-C-FE46G-1 25 Conduit Plan Elev 78'-7" North Reactor Bldg.

SK-C/J-C-FE46G-2 15 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-3 7 Blue & Red Conduit Steam Tunnel Secondary Containment SK-C/J-C-FE46G-4 11 Conduit Sections, Details & Views Steam Tunnel Secondary Containment SK-C/J-C-FE46G-5 10 Conduit Layout Elev. 78'-7" East 1H21-PNL-05 & PNL10 & Dagon Valves Plan, Sections & Details SK-C/J-C-FE46G-6 5 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-7 11 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-8 6 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-9 17 Conduit Sections & Details Elev. 78'-7" SK-C/J-C-FE46G-10 16 Conduit Layout Plan Elev. 78'-7" West Reactor Bldg.

SK-C/J-C-FE46G-11 4 Conduit Sections & Details 9 team Tunnel Secondary Containment SK-C/J-C-FE46G-12 12 Conduit Sections & Details Elev. 78'-7" North Reactor Bldg.

SK-C/J-C-FE46G-13 1 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SI-C/J-C-FE46G-14 8 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-15 3 Cor.duit Supports & Details Steam Tunnel Secondary Containment B-18 Original O

April 1983 L

Drawing Print Number Revision Title O SK-C/J-C-FE46G-16 8 Nonsafety-Related Conduit Plan Steam Tunnel Secondary Containment SK-C/J-C-FE46G-17 7 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-18 2 Steam Tunnel Sections & Details SK-C/J-C-FE46G-19 5 Conduit Sections & Details in Views Steam Tunnel Secondary Containment SK-C/J-C-FE46G-20 4 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-21 -

Diagramatic. Conduit Plan Steam Tunnel Secondary Containment SK-C/J-C-FE46G-22 VOID Enlarged Plan Elev. 78'-7" Northwest Reactor Bldg.

SK-C/J-C-FE46G-23 8 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-24 2 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-25 3 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-26 6 Column 11 Sections & Details Elev. 78'-7" West Side SK-C/J-C-FE46G-27 3 Ped & Blue Conduit Steam Ttanel Secondary Containment SK-C/J-C-FE46G-28 2 Conduit Sections, Details & Views Steam Tunnel Secondary Containment

! SK-C/J-C-FE46G-29 1 Conduit Sections, Details & Views Steam Tunnel Secondary Containment SK-C/J-C-FE46G-30 2 Conduit Sections, Details & Views Steam Tunnel Secondary Containment i

SK-C/J-C-FE46G-31 1 Conduit Sections, Details & Views Steam Tunnel Secondary Containment SK-C/J-C-FE46G-32 2 Conduit Sections & Details

- Elev. 78'-7" Reactor Bldg.

i U

B-19 Original i April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46G-33 3 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-34 3 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-35 0 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-36 1 Conduit Sections, Details & Views Steam Tunnel Secondary Containment SK-C/J-C-FE46G-37 1 Conduit Support Sections &

Details Steam Tunnel SK-C/J-C-FE46G-38 0 Conduit Sections & Details Stean Tunnel Secondary Containment SK-C/J-C-FE46G-39 0 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-40 0 Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46G-41 5 Tip Room Plan & Sections Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-42 1 Wall Elev. Sections & Details Elev, 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-43 2 Tip Room Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46G-44 Conduit Sections & Details Elev. 76'-7" Tip Room SK-C/J-C-FE46G-45 0 Cond__t Details Elev. 78'-7" SK-C/J-C-FE46G-46 2 Conduit Sections & Details Elev. 78'-7" Tip Room SK-C/J-C-FE46G-47 -

Column No. 6 Sections & Details Elev. 78'-7" to Elev. 112'-9" SK-C/J-C-FE46H-1 45 Conduit Plan Elev. 78'-7" South Reactor Bldg. (VOID)

SK-C/J-C-FE46H-2 28 B-20 Original O

April 1983

. _ . - _ _ ~ -

Y l

Drawing Print Number Revision Title SK-C/J-C-FE46H-3 3 Conduit Elev. & Sections Elev. 78'-7" East Reactor Bldg.

SK-C/J-C-FE46H-4 2 Conduit Plan & Sections Elev. 96'

& Above West Side Reactor Bldg.

SK-C/J-C-FE46H-5 1 Conduit Sections Elev 78' West Side Reactor Bldg.

SK-C/J-C-FE46H-6 2 Conduit Support Sections Elev. 78'-7" South (VOID)

, SK-C/J-C-FE46H-7 10 Conduit Supports, Sections & Details i Elev. 78'-7" South i

SK-C/J-C-FE46H-8 VOID Part Plan Southwest Green Conduit System Elev. 96' (VOID)

SK-C/J-C-FE46H-9 3 Sections & Details Green Conduit System 4

SK-C/J-C-FE46H-10 0 Conduit Sections & Details l Elev. 78'-7" South Reactor Bldg.

"'N SK-C/J-C-FE46H-11 6 Conduit Sections & Details

(s Elev. 78'-7" East Reactor Bldg.

SK-C/J-C-FE46H-12 2 Sections & Details Elev. 78' South Side Reactor Bldg.

4 SF-C/J-C-FE46H-13 8 Conduit Sections & Details Elev. 78' Reactor Bldg.

SK-C/J-C-FE46H-14 5 Conduit Supports & Details Elev. 78'-7" East Reactor Bldg.

SK-C/J-C-FE46H-15 9 Cond t Sections & Details l

Elev. 78' West Side Reactor Bldg.

SK-C/J-C-FE46H-16 1 Conduit Sections & Details i Elev. 78' South Reactor Bldg.

, SK-C/J-C-FE46H-17 5 Conduit Details Elev. 78' l

South Reactor Bldg.

i l SK-C/J-C-FE46H-18 8 Conduit Supports, Plans &

l- Sections Elev. 78' South SK-C/J-C-FE46H-19 1 Cond_;t Sections & Details

! Elev. 96' & Above

(-

! B-21 Original April 1983

_, _ _ , _ . _ . _ _ - , _ . ~ . . . _ _ . . _ _ _ _ _ _ - _ _ . - - _ . _ , . -..- _ _.. _ _ _ _

Drawing Print Number Revision Title SK-C/J-C-FE46H-20 0 Conduit Sections & Details Elev. 96' & Above SK-C/J-C-FE46H-21 5 conduit Sections & Details Elev. 78' East Side SK-C/J C-FE46H-22 VOID Column 1 Sections & Details Elev. 78'-7" Southwest (VOID)

SK-C/J-C-FE46H-23 VOID Conduit Partial Plan Under-side Elev. 112'-9" (VOID)

SK-C/J-C-FE46H-24 1 Column 2 Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46H-25 2 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46H-26 8 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46H-27 0 Conduit Support Sections & Details Elev. 96' Southwest Side Reactor Bldg.

SK-C/J-C-FE46H-23 3 Conduit Sections & Details Elev. 78' SK-C/J-C-FE46H-29 Not Used SK-C/J-C-FE46H-30 2 Sections & Details Elev. 78' Reactor Bldg.

SK-C/J-C-FE46H ~.2 2 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46H-32 - Sect;:ns & Details Elev. 78' West Side Reactor Bldg.

SK-C/J-C-FE46H-33 0 Conduit Support Details Elev. 78'-7" West SK-C/J-C-FE46H-34 2 Column 12 Sections & Details Elev. 78' Southwest Side i

SK-C/J-C-FE46H-35 0 Conduit Support Sections &

Details West Side Reactor Bldg.

SK-C/J-C-FE46H-36 4 Colu=. 4 Sections & Details From Elev. 78' to Elev. 112' B-22 Original O

April 1983

Drawing Print Number Revision Title p)

N- ' SK-C/J-C-FE46H-37 1 Conduit Sections & Details Elev. 78' Southwest Reactor Bldg.

SK-C/J-C-FE46H-38 0 Secondary Wall Section Elev. 78'-7" North Reactor Bldg.

SK-C/J-C-FE46H-39 1 Conduit Sections & Details Reactor Bldg.

SK-C/J-C-FE46H-40 Not Used SK-C/J-C-FE46H-41 -

Conduit Elev. Secondary Wall Elev. 78'-7" Southeast Reactor Bldg.

SK-C/J-C-FE46H-42 3 conduit Sections & Details Pilaster Wall Elev. 78' East Side Reactor Bldg.

SK-C/J-C-FE46H-43 0 Column 1 Sections & Details Elev. 78' Southwest Side SK-C/J-C-FE46P-1 17 RPS - Conduit Layout East Side Plans Sections & Details r0

(,) SK-C/J-C-FE46P-2 VOID RPS - Conduit Layout East Side Plans Sections & Details SK-C/J-C-FE46P-3 32 RPS - Conduit Layout West Plan Sections & Details Elev. 78'-7" SK-C/J-C-FE46P-4 VOID RPS - Conduit Layout West Side Plan, Sections & Details SK-C,*J-C-FE4r2P 11 Conduit Sections & Details Elev. 78' Reactor Bldg.

SK-C/J-C-FE46P-6 3 RPS Conduit Plan Steam Tunnel Secondary Containment SK-C/J-C-FE46P-7 2 RPS Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46P-8 15 Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46P-3 VOID RPS - Conduit Sections & Details Elev. 78' O

V B-23 Original April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46P-10 9 RPS - Conduit Sections & Details Elev. 78' West Side SK-C/J-C-FE46P-11 4 RPS - Conduit Sections &

Details Elev. 78'-7" West SK-C/J-C-FE46P-12 2 RPS - Conduit Sections & Details Steam Tunnel Secondary Containment SK-C/J-C-FE46P-13 VOID West Side Tray Riser Bank Elev. 78' Reactor Bldg.

SK-C/J-C-FE46P-14 2 Conduit in Blue Tray Riser Plans Elev. 8' to 175'-9" SK-C/J-C-FE46P-15 11 Conduit in Blue Tray Riser Plans Sections & Details Elev. 8' to 175'-9" SK-C/J-C-FE46P-16 1 Conduit Sections & Details Elev. 78', 112', 150' Reactor Bldg.

Sh-C/J-C-FE46P-17 Not Used SI'-C/J-C-FE46P-18 Not Used SK-C/J-C-FE46P-19 3 RPS - Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46P-20 15 Conduit Plans East Riser Bank Reactor Bldg.

. C/J-C-FE46P-21 5 Conduit Plans East Riser Bank Reactor Bldg.

SK-C/J-C-F246P-22 2 Conduit Plans East Riser Bank Reactor Bldg.

SK-C/J-C-FE46P-23 9 Conduit Plans Northwest Riser Bank Reactor Bldg.

SK-C/J-C-FE46P-24 8 Conduit Plans Northwest Riser Bank Reactor Bldg.

SK-C/J-C-FE46P-25 1 Conduit Plans Northwest Riser Bank Reactor Bldg.

SK-C/J-C-FE46P-26 11 West Riser Bank Elev. 8'-0" to 74'-8" Reactor Bldg.

B-24 Original O

April 1983

Drawing Print Number Revision Title p

I

(. / SK-C/J-C-FE46P-27 9 West Riser Bank Elev. 81' to 165'-2" Reactor Bldg.

SK-C/J-C-FE46P-28 12 East Riser Bank Elev. 8' to 788 Reactor Bldg.

SK-C/J-C-FE46P-29 4 East Riser Bank Elev. 81' to 165'-2" Reactor Bldg.

SK-C/J-C-FE46P-30 0 West Riser Bank Sections &

Details Elev. 8' to 40' Reactor Bldg.

SK-C/J-C-FE46P-31 -

West Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-32 -

Northwest Riser Sanks Sections

& Details SK-C/J-C-FE46P-33 -

Northwest Riser Banks Sections

& Details SK-C/J-C-FE46P-34 0 West Riser Bank Sections & Details Elev. 8' to 40' Reactor Bldg.

f-'s SK-C/J-C-FE46P-35 -

Sections & Details Northeast (a ) Riser Banks Elev. 40' to 63' SK-C/J-C-FE46P-36 -

Northeast Riser Banks Sections

& Details Elev. 40' to 63' SK-C/J-C-FE46P-37 -

Northeast Riser Banks Sections

& Details Elev. 63' to 78'-7" SK-C/J-C-FE46P-38 -

Northeast Riser Banks Sections &

Details Elev. 63' to 78'-7" SK-C/J-C-FE46P-39 -

Nort. east Riser Banks Sections &

Details Elev. 63' to 78'-7" SK-C/J-C-FE46P-40 -

Conduit Sections & Details Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46P-41 0 Northwest Riser Banks Sections

& Details Elev. 81' to 108'-2" SK-C/J-C-FE46P-42 -

Northwest Riser Bank Sections &

Details Elev. 81' to 108'-2" SK-C/J-C-FE46P-43 -

Nortr.est Riser Bank Sections &

Details Elev. 94' to 111'-6" 4

[\

(,/

B-25 Original April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46P-44 -

Northwest Riser Bank Sections &

Details Elev. 81' to 108'-2" SK-C/J-C-FE46P-45 0 Northeast Riser Bank Sections &

Details Elev. 8' to 40' SK-C/J-C-FE46P-46 -

Northwest Riser Bank Sections &

Details Elev. 158'-4" to 175'-0" SK-C/J-C-FE46P-47 0 Northeast Riser Bank Sections &

Details Elev. 8' to 40' SK-C/J-C-FE46P-48 -

Northwest Riser Bank Elev. 114'-

10" to 122'-10" SK-C/J-C-FE46P-49 0 Northwest Riser Bank Elev. 114'-

10" to 130'-10" Reactor Bldg.

SK-C/J-C-FE46P-50 -

Northwest Riser Bank Sections &

Details Elev. 158'-4" to 175'-0" SK-C/J-C-FE46P-51 0 Northwest Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-52 -

Northeast Riser Bank Sections &

Details Elev. 8' to 40'-0" SK-C/J-C-FE46P-53 -

Northwest Riser Br.nk Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-54 0 Northeast Riser Bank Sections &

Details Elev. 78'-7" to 95'-3" SK-C/J-C-FE46P-55 SK-C/J-C-FE46P-56 0 East Riser Bank Sections & Details Elev. 81' to 165'-2" Reactor Bldg.

SK-C/J-C-FE46P-57 -

Northwest Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-58 -

Northwest Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-59 -

Northwest Riser Bank Sections &

Details Elev. 112' to 160'-0" SK-C/J-C-FE46P-60 0 Northeast Riser Bank Sections &

Detaa s Reactor Bldg.

B-26 Original O

April 1983

t i

i Drawing Print Number Revision Title s

. f-s_/ SK-C/J-C-FE46P -

Northeast Riser Bank Sections &

i Details Elev. 05' to 112'-9"

.SK-C/J-C-FE46P-62 0 Northeast Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-63 -

Northeast Riser Bank Sections &

Details Elev. 78'-7" to 95'-3" Reactor Bldg.

SK-C/J-C-FE46P-64 -

Northeast Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-65 -

Northeast Riser Bank Sections &

Details Reactor Bldg.

, SK-C/J-C-FE46P-66 -

Northeast Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-67 0 East Riser Bank Sections &

i Details Elev. 154' to 175' Reactor Bldg.

j SK-C/J-C-FE46P-68 0 Northeast Riser Bank Conduit Supports & Details Elev. 154'

( to 175' Reactor Bldg.

SK-C/J-C-FE46P-69 -

Northwest Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46P-70 -

Northwest Riser Bank Sections &

Details Reactor Bldg.

SK-C/J-C-FE46T-1 4 Conduit Partial Plans l Elev. 126'-9" East SK-C/J-C-FE46T-2 2 Conduit Supports Elev. 126'-9" East 1

SK-C/J-C-FE46T-3 1 Conduit Supports Elev. 126'-9" East SK-C/J-C-FE46T-4 29 Conduit Plan Elev. 95'-3" i

. SK-C/J-C-FE46T-5 3 Conduit Sections, Details, & Views Elev. 95'-3" & 101'-6"

SK-C/J-C-FE46T-6 3 Conduit Sections, Details & Views Elev. 126'-9" J

SK-C/J-C-FE46T-7 4 Conduit Supports Elev. 126'-9" East r

.Q 1

O B-27 Original April 1983 i

. .,. ,...._.___-__._._-._...-.m _ , . . . _ . . _ . . . _ . _ - . - . . , , - - _ , , . . . _ _ -

Drawing Print Number Revision Title SK-C/J-C-FE46T-8 -

Conduit Plan Elev. 126'-9" East SK-C/J-C-FE46T-9 5 Conduit Support, Sections & Details Elev. 95'-3" Reactor Bldg.

SK-C/J-C-FE46T-10 2 Conduit Sections & Details Elev. 126'-9" East SK-C/J-C-FE46T-11 1 Conduit Sections & Details Reactor Bldg.

SK-C/J-C-FE46T-12 1 Conduit Support, Sections &

Details Elev. 95'-3" Reactor Bldg.

SK-C/J-C-FE46T-13 6 Sections & Details Elev. 95'-3" &

101'-6" Reactor Bldg.

SK-C/J-C-FE46T-14 2 Conduit Pla lev. 101'-6" SK-C/J-C-FE46T-15 0 Sections & Details Elev. 95'-3" &

101'-6" SK-C/J-C-FE46T-16 3 Section Secondary Wall Elev. 95'-3"

& 101'-6" Reactor Bldg.

SK-C/J-C-FE46T-17 2 Conduit Sections & Details Elev. 95' Reactor Bldg.

SK-C/J-C-FE46Z-1 1 RPS - Conduit Plan & Details- HCU Elev. 78'-7" East Reactor Bldg.

SK-C/J-C-FE46Z-2 1 Conduit Plan & Details - HCU Elev 78'-7" West Reactor Bldg.

SK-CfJ-C-FE46Z-3 1 Conduit Sections & Details - HCU Elev. 78'-7" West Reactor Bldg.

SK-C/J-C-FE46Z-4 -

RPS - Conduit Sections & Details HCU Elev. 78' East Reactor Bldg.

SK-C/J-C-FE46Z-5 -

RPS - Conduit Sections & Details HCU Elev. 78'-7" East & West Reactor Bldg.

SK-C/J-C-FE46Z-6 2 Conduit Sections & Details - HCU Elev. 78'-7" Wesc Reactor Bldg.

SK-C/J-C-FE46Z-7 -

Conduit Sections Elev. 78' East Side B-28 Original O

April 1983

. . .. . . .- . - . . _ . - = - - . . . - . . .. . _ -- . .. . _ - .

I Drawing Print Number Revision Title SK-C/J-C-FE46Z-8 -

Conduit Sections & Details - HCU Elev. 78'-7" Reactor Bldg.

SK-C/J-C-FE46Z-9 -

Conduit Sections & Views - HCU Elev. 78'-7" Reactor Bldg.

l l

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i i

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b i

l ,

l 4

i l

l l

l B-29 Original April 1983 l

l ELEV. 112' Drawing Print Number Revision Title SK-C/J-C-FE46J-1 11 Conduit Index Drawing Plan &

Sections Elev. 112'-9" SK-C/J-C-FE46J-2 4 Conduit Index Drawing Conduit Support Details SK-C/J-C-FE46J-3 5 Conduit Index Drawing Tray &

Conduit Support Details SK-C/J-C-FE46J-4 9 Conduit Layout Plan Sections &

Details West Reactor Bldg.

SK-C/J-C-FE4CJ-5 4 Conduit Layout Sections &

Details West Reactor Bldg.

SK-C/J-C-FE46J-6 VOID SK-C/J-C-FE46J-7 2 Conduit Layout Plan & Section North SK-C/J-C-FE46J-8 2 Conduit Layout Sections & Details 1R24-MCC11D2 & 1R24-MCC12D2 Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-9 1 Conduit Layout North Plan SK-C/J-C-FE46J-10 2 Conduit Layout Plan & Sections North SK-C/J-C-FE46J-11 1 Conduit Layout Sections North SK-C/J-C-FE46J-12 -

Conduit Layout Plan North SK-C/J-C-FE46J-13 10 Conduit Layout Plan Sections &

Details Fire Sep Reduct Doc North Reactor Bldg.

SK-C/J-C-FE46J-14 -

Conduit Sections & Details SK-C/J-C-FE46J-15 11 Standby Liquid Control System Sep Reduct Doc System Elev. 112'-9" SK-C/J-C-FE46J-16 VOID B-30 Original O

April 1983

Drawing Print Number Revision Title Cl SK-C/J-C-FE46J-17 Conduit Layouts Plan, Sections &

Details East SK-C/J-C-FE46J-18 11 Conduit Layout Plan & Supports West SK-C/J-C-FE46J-19 5 Conduit Sections & Views SK-C/J-C-FE46J-20 1 Enlarged Plans & Sections SK-C/J-C-FE46J-21 2 Conduit Sections Northeast SK-C/J-C-FE46J-22 3 Conduit Layout Plan & Supports Sep Reduct Doc Elev. 112'-9" West SK-C/J-C-FE46J-23 33 Plan Drawing Sep Reduct Doc Elev. 112'-9" North SK-C/J-C-FE46J-24 5 Conduit Sections & Views SK-C/J-C-FE46J-25 7 Conduit Support Details SH-1 SK-C/J-C-FE46J-26 2 Conduit Support Details Elev. 112'-9" SH-2 1

J SK-C/J-C-FE46J-27 3 Sections & Details Elev. 112'-9" West SK-C/J-C-FE46J-28 3 Conduit Sections & Supports Details Elev. 112'-9" North Reactor Bldg.

SK- C/J-C-FE46J-29 3 Conduit Support Sections Elev.

112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-30 5 Sections & Details Elev. 112'-9" West SK-C/J-C-FE46J-31 14 conduit Sections & Support Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-32 2 Conduit Sections & Support Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-33 3 Conduit Sections & Details SK-C/J-C-FE46J-34 3 Conduit Layout Plan Supports West SK-C/J-C-FE46J-35 2 Conduit Layout Sections Conduit Support East B-31 Original April 1983

n_

Drrwing Print Number Revision Title SK-C/J-C-FE46J-36 1 Conduit Layout Sections & Conduit Support East SK-C/J-C-FE46J-37 1 Enlarged Plan North Standby Vent System Elev. 133'-3" Reactor Bldg.

SK-C/J-C-FE46J-38 2 Standby Vent System Conduit Sections North SK-C/J-C-FE46J-39 2 Co.2duit Support Details Elev. 112'-9" North SK-C/J-C-FE46J-40 1 Conduit Layout Elev. 112'-9" North Reactor Bldg. Sections SK-C/J-C-FE46.'-41 5 Conduit Sections & Details SK-C/J-C-FE46J-42 2 Conduit Supports Sections & Details Elev. 112'-9" East Reactor Bldg.

SK-C/J-C-FE46J-43 1 Detail Sheet SK-C/J-C-FE46J-44 3 MCC Room East Elev. View Elev. 112'-9" Reactor Bldg.

SK-C/J-C-FE46J-45 7 Enlarged Plan and Sections SK-C/J-C-FE46J-46 3 Conduit Support Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-47 1 Conduit Support Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-48 2 MCC Room West Elev. View Elev. 112'-9" Reactor Bldg.

SK-C/J-C-FE46J-49 VOID Sect;;ns & Details North Pump Room SK-C/J-C-FE46J-50 2 Sections and Details SK-C/J-C-FE46J-51 4 Sections & Details Elev. 112'-9" East SK-C/J-C-FE46J-52 7 Sections & Views Elev. 112'-9" East SK-C/J-C-FE46J-53 8 Sections & Details Elev. 112'-9" NortL Reactor Bldg.

B-32 Original O

April 1983

Drawing Print Number Revision Title

/~~N

\- / SK-C/J-C-FE46J-54 3 Conduit Support Details Elev. 112'-9" North Reactor Oldg.

SK-C/J-C-FE46J-55 6 Conduit Support Sections & Views Elev. 112'-9" Reactor Bldg.

SK-C/J-C-FE46J-56 4 Sections & Details Elev. 112'-9" East Reactor Bldg.

SK-C/J-C-FE46J-57 0 Conduit Support, Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-58 2 Conduit Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-51 5 Conduit Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-60 2 Conduit Support, Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-61 11 Sep Reduct Doc Standby Vent System Enlarged Plan Elev. 124' North Reactor Bldg.

D

(",)N SK-C/J-C-FE46J-62 1 Conduit Support & Details Elev. 112'-9" North SK-C/J-C-FE46J-63 3 Conduit Support & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-64 2 Sections & Views Elev. 112'-9" Reactor Bldg.

SK-C/J-C-FE46J-65 1 Conduit Sections & Details MCC Room Elev. 112'-9" West SK-C/J-C-FE46J-66 3 Conduit Supports, Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-67 2 Conduit Supports, Sections & Views Elev. 112'-9" West Reactor Bldg.

SK-C/J-C-FE46J-68 2 Conduit Supports & Details 1T46 Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-69 4 Conduit Supports & Details Elev. 112'-9" North

' ['k j'\

B-33 Original April 1983 i

L

Drawing Print Number Revision Title l

SK-C/J-C-FE46J-70 3 Conduit Supports & Sections es l Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-71 4 Sections & Views Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-72 3 Conduit Supports & Sections Elev. 1128-9" North Reactor Bldg.

SK-C/J-C-FE46J-73 5 Conduit Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-74 2 Conduit Sections & Details Elev. 1128-9" North Reactor Bldg.

SK-C/J-C 'E46J-75 5 Conduit Support Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-76 3 Conduit Supports, Details & Views Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-77 Drawing Never Issued SK-C/J-C-FE46J-78 2 Conduit Supports & Details Elev. 112'-9" Reactor Bldg.

SK-C/J-C-FE46J-79 1 Conduit Supports, Details & Views SK-C/J-C-FE46J-80 4 Conduit Supports & Details 1R-71Z Elev. 112'-9" Northwest Reactor Bldg.

SK-C/J-C-FE46J-81 3 Conduit Supports & Detcils Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-82 1 Conduit Supports & Details Elev. 112'-9" SK-C/J-C-FE46J-83 0 Conduit Supports & Details Elev. 112'-9" East Reactor Bldg.

SK-C/J-C-FE46J-84 1 Conduit Sections & Details Elev. 112'-9" MCC Room SK-C/J-C-FE46J-85 1 Conduit Sections & Details Elev. 112'-9" West Reactor Bldg.

MCC Room SK-C/J-C-FE46J-86 0 Conduit Supports & Details Elev. 112'-9" East Reactor Bldg.

B-34 Original O

April 1983

-. ~. __ _ _ .

Drawing Print Number Revision Title i

SK-C/J-C-FE46J-87 0 Conduit Supports & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-88 1 Sections & Conduit Support Details Elev. 112'-9" MCC Room East Reactor Bldg.

SK-C/J-C-FE46J 0 Conduit Supports, Sections & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-90 0 Conduit Support, Sections & Details Elev. 112'-9" SK-C/J-C-FE46J-91 1 Conduit Supports & Details Elev. 112'-9" North Reactor Bldg.

SK-C/J-C-FE46J-92 0 Details Elev. 112'-9" North SK-C/J-C-FE46K-1 7 Conduit Plan & Sections Elev. 112'-9" Reactor Bldg.

Southeast Fump Room SK-C/J-C-FE46K-2 34- Pl;n Drawing South Side SK-C/J-C-FE46K-3 3 Conduit Layout Sections & Details 4

(- Elev.112' Reactor Bldg. South Side

- SK-C/J-C-FE46K-4 0 Conduit Layout Plan Sections &

Details Elev. 112' RWCU Pumphouse South S'de Reactor Bldg.

SK-C/J-C-FE46K-5 3 Conduit Section Elev. 112' Reactor Bldg. Southeast Pumphouse SK-C/J-C-FE46K-6 4 Sections, Details & Supports Elev. 112' Southside Reactor Bldg.

SK-C/J-C-FE46K-7 2 Conduit Sections & Views Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-8 1 Conduit Supports & Details Reactor Bldg. Southeast Pump

, Room SK-C/J-C-FE46K-9 1 Conduit Supports & Details Elev. 112' Reactor Bldg.

Southeast Pump Room

, B-35 Original April 1983

., . - - _ _ - .. . _ . _ , . - - - . _ - ~ _ . .

Drawing Print Number Revision Title SK-C/J-C-FE46K-10 0 Conduit Supports, Sections & Details Elev. 112'-9" South Side Reactor Bldg.

SK-C/J-C-FE46K-11 3 Conduit Supports, Sections & Details Elev. 112'-9" South Side Reactor Bldg.

SK-C/J-C-FE46K-12 10 Enlarged Plan Elev. 135' & Grove Reactor Bldg.

SK-C/J-C-FE46K-13 0 Conduit Layout Sections & Details Elev. 112' South Side Reactor Bldg.

.e".-C / J- C-FE4 6 K- 14 4 Conduit Supports, Sections & Details Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-15 3 Conduit Supports, Sections & Details Elev. 112' Reactor Bldg.

SK-C/J-C-FE46K-16 2 Conduit Supports, Sections & Details Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-17 4 Conduit Supports & Details Elev. 112' Reactor Bldg.

SK-C/J-C-FE46K-18 2 Conduit Sections Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-19 2 Conduit S';pports, Sections & Details Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-20 5 Sections & Details SK-C/J-C-FE46K-21 3 Cenduit Supports & Sections Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-22 5 Conduit Supports & Details Elev. 112' South Side Reactor Bldg.

SK-C/J-C-FE46K-23 3 Conduit Supports, Sections & Details Elev. 112' South Side P.eactor Bldg.

SK-C/J-C-FE46K-24 0 Tray Support Details Elev. 112'-9" South Side SK-C/J-C-FE46K-25 0 Tray Support Details Elev. 112'-9" Sout:. Side B-36 Original e

April 1983

Drawing ~ Print Number Revision Title SK-C/J-C-FE46K-26 0 Conduit Sections & Details Elev. 112' & 126' South SK-C/J-C-FE46K-27 1 Conduit Supports & Details Elev. 112'-9" & 126' South SK-C/J-C-FE46K-28 3 Conduit Sections & Views Elev. 112' South side SK-C/J-C-FE46K-29 1 Secondary Wall Southwest Quadrant Elev. 112' Reactor Bldg.

SK-C/J-C-FE46K-30 1 Conduit Supports & Details Elev. 112' Reactor Bldg.

SK-C/J-C-FE4f%-31 4 Conduit Supports & Details SK-C/J-C-FE46K-32 -

Conduit Supports, Sections & Details SK-C/J-C-FE46K-33 1 Conduit Supports & Details O

l i

l l

l B-37 Original

', April 1983 l' - - - - , - . - - - -

ELEV. 150', 159' Drawing Print Number Revision Title SK-C/J-C-FE46L-1 16 Conduit Plan Elev. 150' North Reactor Bldg.

SK-C/J-C-FE46L-2 6 Conduit Layout Plan Details Elev. 159' Reactor Bldg.

SK-C/J-C-FE46L-3 10 Conduit Sections Elev. 150' Reactor Bldg.

SK-C/J-C-FE46L-4 0 Sections & Details Elev. 150' SK-C/J-C-FE46L-5 3 Conduit Layout Sections A-A & B-B Elev. 150' & 159' Reactor Bldg.

SK-C/J-C-FE46L-6 8 Conduit Sections Elev. 150' North Reactor Bldg.

SK-C/J-C-FE46L-7 3 Conduit Layout Plar. Elev.150' North Reactor Bldg.

SK-C/J-C-FE46L-8 8 Conduit Layout Plan, Elev. & Details Elev. 150' North Reactor Bldg.

SK-C/J-C-FE46L-9 9 Conduit Sections & Details Elev. 159' Reactor Bldg.

SK-C/J-C-FE46L-10 7 Conduit Layout Plan Elev. 150' South SK-C/J-C-FE46L-11 Not Used SK-C/J-C-FE46L-12 6 Conduit Support Sections Elev. 150' North Side Reactor Bldg.

i SK-C/J-C-FE46L-13 3 Conduit Support Section Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-14 0 Conduit Sections & Details Elev. 150' North Reactor Bldg.

l SK-C/J-C-FE46L-15 0 Conouit Supports & Sections Elev. 150' Reactor Bldg.

SK-C/J-C-FE46L-16 7 Conduit Supports & Details Elev. 150' North Side Reactor Bldg.

B-38 Original O

April 1983

Drawing Print Number Revision Title

(~g SK-C/J-C-FE46L-17 2 Conduit Sections & Details Elev. 150' South Reactor Bldg.

SK-C/J-C-FE46L-18 4 Conduit Layout Sections & Views Elev. 150' North Reactor Bldg.

SK-C/J-C-FE46L-19 1 Conduit Sections & Details Elev. 150' West Side Reactor Bldg.

SK-C/J-C-FE46L-20 1 Conduit Supports & Sections Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-21 0 Conduit Supports & Sections Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-22 Not Conduit Supports & Details Listed Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-23 Not Conduit Supports & Sections Listed Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-24 1 Conduit Layout Sections C-C, D-D, E-E Elev. 159' Reactor Bldg.

/N SK-C/J-C-FE46L-25 1 Conduit Layout Plan Elev. 150' &

() 159' Reactor Bldg.

SK-C/J-C-FE46L-26 1 Conduit Supports & Details Elev. 150' & 159' Reactor Bldg.

SK-C/J-C-FE46L-27 1 Conduit Supports & Details Elev. 150' & 159' Reactor Bldg.

SK-C/J-C-FE46L-28 Not Conduit Supports & Details Listed Elev. 150' Reactor Bldg.

SK-C/J-C-FE46L-29 3 Conduit Supports, Sections & Details Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-30 Not Conduit Supports & Details Listed Elev. 150' Reactor Bldg.

SK-C/J-C-FE46L-31 Not Conduit Supports & Details Listed Elev. 150' North Reactor Bldg.

SK-C/J-C-FE46L-32 0 Conduit Supports, Sections & Details Elev. 150' North Side Reactor Bldg.

SK-C/J-C-FE46L-33 Not Conduit Supports, Details & Sections

,p_s - Listed Elev. 150' North Reactor Bldg.

k -

)

B-39 Original April 1983

Drcwing Print Number Revision Title SK-C/J-C-FE46L-34 0 Conduit Supports, Sections & Details Elev. 150'-9" South Reactor Bldg.

SK-C/J-C-FE46B-15 17 Conduit Plan M.G. Rooms Elev. 150'-9" South Reactor Bldg.

SK-C/J-C-FE46B-16 11 Conduit Plan M.G. Rooms Elev. 161' Reactor Bldg.

SK-C/J-C-FE46B-17 9 Elev. M.G. Rooms North Wall Looking South SK-C/J-C-FE46B-18 6 West Wall Looking East, East Wall Looking West, Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-19 0 Conduit Supports & Details Elev. 150' South Side Reactor Bldg.

SK-C/J-C-FE46B-20 1 Conduit Supports, Sections & Details for M.G. Rooms Elev. 150' South SK-C/J-C-FE46B-21 2 Conduit Supports, Sections & Details Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-22 3 Conduit Supports, Sections & Details h Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-23 6 Conduit Supports, Sections & Details Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-24 1 Conduit Supports & Details M.G. Room Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-25 1 Conduit Support Elev. 150' &

161' Reactor Bldg.

SK-C/J-C-FE46B-26 3 Conduit Supports & Details Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-27 12 Secondary Wall M.G. Set Rooms Elev. 150' SK-C/J-C-FE46B-28 1 Conduit Supports & Details M.G.

Room Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-29 2 Conduit Supports & Details Elev. 150' Reactor Bldg.

B-40 Original O

April 1983 t

Drawing Print Number Revision Title SK-C/J-C-FE46B-30 5 Conduit Supports & Details Elev. 161' Reactor Bldg.

SK-C/J-C-FE46B-31 1 Conduit Supports & Details Elev. 161' Reactor Bldg.

SK-C/J-C-FE46B-32 5 Conduit Section M.G. Rooms Elev. 161' Reactor Bldg.

SK-C/J-C-FE46B-33 1 Conduit Supports & Details Elev. 161' Reactor Bldg.

SK-C/J-C-FE46B-34 2 Conduit Supports & Details Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-35 0 Grnd Conduit Supports & Details Elev. 150' Reactor Bldg.

SK-C/J-C-FE46B-36 1 Conduit Sections & Details Elev. 150' M.G. Set Rooms SK-C/J-C-FE46B-37 1 Conduit Sections & Details Elev. 160' Reactor Bldg.

/ SK-C/J-C-FE46B-38 3 Conduit Supports Elev. 150'-9"

(,,)N & *61'

. Reactor Bldg.

,O O

B-41 Original April 1983

ELEU. 175' Drawing Print Number Revision Title SK-C/J-C-FE46M-1 2 Conduit Index Drawing Elev. 175'-9" North SK-C/J-C-FE46M-2 1 Conduit Plan Elev. 203'-1" - 229'-

6" North Reactor Bldg.

SK-C/J-C-FE46M-3 8 Conduit Plan Elev. 175'-9" North Reactor Bldg.

SK-C/J-C-FE46M-4 10 Conduit Elevation Reactor Bldg.

Secondary Containment Development Az 72 to 144 SK-C/J-C-FE46M-5 7 Conduit Elevation Reactor Bldg.

Secondary Containment Development Az 144 to 216 SK-C/J-C-FE46M-6 1 Sections & Details Elev. 205'-1" North Reactor Bldg.

SK-C/J-C-FE46M-7 1 Conduit Supports & Details Elev. 203'-1" & Above Reactor Bldg.

SK-C/J-C-FE46M-8 4 Conduit Supports, Sections & Details Elev. 175'-9" - 203'-1" Az 90 -180' SK-C/J-C-FE46M-9 2 Sections & Details Elev. 175'-9" North Reactor Bldg.

SK-C/J-C-FE46M-10 0 Elevator Structure & Details Elev. 175'-9" Reactor Bldg.

SK-C/J-C-FE46M-11 0 Elevator Structure & Details l Elev. 175'-9" Reactor Bldg.

I SK-C/J-C-FE46M-12 VOID SK-C/J-C-FE46M-13 1 Elevator Structure & Details l Elev. 175'-9" Reactor Bldg.

1 1

SK-C/J-C-FE46M-14 2 Conduit Supports & Details Elev. 175'-9" Reactor Bldg.

SK-C/J-C-FE46M-15 2 Conduit Elevation Secondary Containment Development Az 216 -

l 288 Reactor Bldg.

B-42 Original O

April 1983

Drawing Print Number Revision Title 1 s

SK-C/J-C-FE46M-16 0 Conduit Elevations High Bay Area Elev. 219'-6" Truss No. 2 North Side i SK-C/J-C-FE46M-17 0 Conduit Elevations High Bay Area Elev. 219'-6" Truss No. 3 North 4 Side SK-C/J-C-FE46M-18 0 Conduit Supports & Details Elev.

J 203'-1" & Above Reactor Bldg.

SK-C/J-C-FE46M-19 -

Conduit Supports & Details Elev. .

203'-1" & Above Reactor Bldg.

SK-C/J-C-FE46M-20 -

Conduit Supports & Details Elev.

203'-1" & Above Reactor Bldg.

SK-C/J-C-FE46M-21 -

Conduit Supports & Details Elev.

203'-1" & Above Reactor Bldg.

EK-C/J-C-FE46M-22 1 Conduit Supports & Details Elev.

175'-9" & Above Reactor Bldg.

SK-C/J '?-FE46N-1 Conduit Index Drawing Elev. 175'-9" SK-C/J-C-FE46N-2 1 Conduit Plan Elev. 203'-1" to 229'-6"

South Reactor Bldg.

SK-C/J-C-FE46N-3 9 Conduit Plan Elev. 175'-9" South 2

Reactor Bldg.

SK-C/J-C-FE46N-4 7 Conduit Elev. Secoradary Containment Development Az 288' to 0 Reactor Bldg.

SK-C/J-C-FE46N-5 9 Conduit Elev. Secondary Containment

Development Az 0* to 72 Reactor Bldg.

. SK-C/J-C-FE46N-6 1 Conduit Supports & Details Elev.

203'-1" - 229'-6" South Reactor Bldg.

SK-C/J-C-FE46N-7 2 Conduit Supports & Details Elev.

175'-9" South Reactor Bldg.

SK-C/J-C-FE46N-8 2 Conduit Supports & Details ~Elev.

175'-9" to 229'-6" South Reactor Bldg.

4 B-43 Original April 1983

Drawing Print Number Revision Title SK-C/J-C-FE46N-9 2 Conduit Supports & Details Elev.

175'-9" South Reactor Bldg.

SK-C/J-C-FE46N-10 0 Conduit Supports & Details Elev.

179'-9" South Reactor Bldg.

SK-C/J-C-FE46N-11 -

Conduit Supports & Junction Box Details & Views SK-C/J-C-FE96N-12 -

Conduit Elevations High Bay Area Elev. 219'-6" Truss No. 1 Center Reactor Bldg.

SK-C/J-C-FE46N-13 -

Conduit Elevations High Bay Area Elev. 219'-6" Truss No. 3 South Side Reactor Bldg.

SK-C/J-C-FE46N-14 -

Conduit Elevations High Bay Area Elev. 219'-6" Truss No. 2 South Side Reactor Bldg.

SK-C/J-C-FE46N-15 -

Conduit Supports & Details Elev.

203'-1" & Above Reactor Bldg.

SK-C/J-C-Fs46N-16 -

Lighting Plan High Bay Area Elev. 219'-6" Reactor Bldg.

SK-C/J-C-FE46MN-1 -

Conduit Plan & Sections Elev. 175'-9" Unit Coolers SK-C/J-C-FE46MN-2 -

Conduit Sections & Details Elev. 175'-9" to Unit Coolers SK-C/J-C-FE46MN-3 -

Conduit Sections & Details SK-C/J-C-FE46U-1 31 Drywell West Plan & Sections SK-C/J-C-FE46U-2 23 Eas' Plan & Sections SK-C/J-C-FE46U-3 9 Dryuell West Details SK-C/J-C-FE46U-4 4 Drywell East Support Details SK-C/J-C-FE46U-5 2 Under Vessel Wiring Plan Elev. 78' SK-C/J-C-FE46U-6 2 Under Vessel Wiring Sections Elev. 78' SK-C/J-C-FE46U-7 16 Drywell West Support Details B-44 Original O

April 1983

Drawing Print Number Revision Title n

SK-C/J-C-FE46U-8 6 Conduit Elev. & Details Elev. 68'-0" to 72'-3" SK-C/J-C-FE46U-9 7 Supports & Details Drywell West SK-C/J-C-FE46U-10 11 Elevations & Details Drywell East SK-C/J-C-FE46U-11 5 Part Plan Recirc Pump "A" Elev. 76'-4 1/2" & Below SK-C/J-C-FE46U-12 13 Conduit Layout Part Plans Drywell East Elev. 76'-4 1/2" & Below SK-C/J-C-FE46U-14 7 Conduit Layout Part Plsns & Details Drywell East Elev. 76'-4 1/2" & Below SK-C/J-C-FE46U-16 4 Conduit Sections & Details Drywell Northeast Elev. 76'-4 1/2" & Below SK-C/J-C-FE46U-17 4 Conduit Layout Part Plan Drywell South Elev. 76'-4 1/2" & Below SK-C/J-C-FE46U-18 1 Conduit Sections & Details Drywell East O

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( ,/ SK-C/J-C-FE46V-1 26 Drywell West Plan Elev. 76' to 86' SK-C/J-C-FE46V-2 20 Plan & Sections Elev. 76' to 86' East Drywell SK-C/J-C-FE46V-3 21 Plan & Sections Elev. 86' to 96' West Drywell SK-C/J-C-FE4r -4 12 Plan & Sections Elev. 86' to 96' West Drywell SK-C/J-C-FE46V-5 13 West rywell Layout SK-C/J-C-FE46V-6 15 East Drywell Sections & Details SK-C/J-C-FE46V-7 14 East Drywell Supports & Details SK-C/J-C-FE46V-8 6 East Drywell Supports & Details SK-C/J-C-FE46V-9 11 West Drywell Supports & Details SK-C/J-C-FE46V-10 8 Details Elev. 86' to 96' SK-C/J-C-FE46V-11 8 West ;ections & Details ty t

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B-45 Original April 1983

Drcwing Print Number Revision Title SK-C/J-C-FE46V-12 7 Conduit Elev's. & Details Drywell SK-C/J-C-FE46V-13 8 Liner Dev. & Sections Drywell Elev. 76'-4 1/2' to 96'-11 1/2" West SK-C/J-C-FE46V-14 3 Conduit Layout & Elev. Drywell West SK-C/J-C-FE46V-16 4 Liner Dev. Drywell East Elev. 76'-4 1/2' to 96'-11 1/2" SK-C/J-C-FE46V-18 0 conduit Sections & Details Drywell East SK-C/J-C-FE46W-1 28 Drywell West Plan Elev. 96' to 120' SK-C/J-C-FE46W-2 22 Drywell East Sections Elev. 95' to 120' SK-C/J-C-FE46W-3 17 Drywell West Plan & Supports Elev. 120' SK-C/J-C-FE46W-4 15 Drywell East Plan & Supports Elev. 120' SK-C/J-C-FE46W-5 2 Drywell West Supports & Details SK-C/J-C-FE46W-6 9 Drywell East Supports & Details SK-C/J-C-FE46W-7 7 Drywell West Supports & Details SK-C/J-C-FE46W-8 VOID Conduit Elev's. & Details Drywell VOID SK-C/J . "E46W-9 17 Conduit Elev's. Biological Shield Wall Drywell West Elev. 120'-0" to 143'-8" SK-C/J-C-FE46W-10 VOID Liner Dev. Drywell Southeast (VOID)

SK-C/J-C-FE46W-11 10 Conduit Elev Biological Shield Wall Drywell West Elev. 90' to 120' SK-C/J-C-FE46W-12 11 Conduit Elev & Details East Elev. 90' to 120' SK-C/J-C-FE46W-13 10 Drywell West Elev. 90' to 120' SK-C/J-C-FE46W-14 4 Drywell East Elev. 90' to 120' B-46 Original O

April 1983

Drawing Print I Number Revision Title 0 SK-C/J-C-FE46H-16 13 Liner Dev. Drywell East Elev. 120' & Above SK-C/J-C-FE46W-18 -

Conduit Sections & Details Drywell East t

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B-47 Original l

April 1983 l

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ML20073L591

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