Text

Oct. 2006 Exam - Handouts to Applicants (Folder 3)
	ML063070146
Person / Time
Site:	Oyster Creek
Issue date:	10/02/2006
From:	; AmerGen Energy Co
To:	; Operations Branch I
	Sykes, Marvin D.
References
	Download: ML063070146 (190)
	v • d • e

Oyster Creek Oct. 2 - 9, 2006 Operator Licensing Exam Handouts Reactor Vessel Level/Pressure/Temperature instruments Flow Diagram, Drawing No.

GE 148F712, Rev. 45

3.4 EMERGENCY COOLING tfieTm-ErgmEjol ing systems.

Obiective:

To assure operability of the emergency cooling systems.

L/

Any active loop component becomes inonerable.

Specifications:

The Reactor may remain in operation for a period not to exceed Both Emergency Diesel Generators are OPERABLE.

A.

Core Sprav Svstem

-OR:

Two or more active loop components in the same loop (System 1 or System 2) are inoperable provided no two components are redundant.

NOTE: LCO 3.0.C.2 is not applicable to the Core Spray System

1.

The Core Spray System shall be OPERABLE at all times with irradiated fuel in the reactor vessel with an absorption chamber water volume of at least 82,000 ft3 except as specified Table 3.4.1, or as noted below.

If Specification 3.4.A.1 is not met the reactor shall be PLACED IN the COLD SHUTDOWN CONDITION and no work shall be performed on the reactor or its connected systems which could result in lowering the reactor water level to less than 4'8"above TOP OF ACTIVE FUEL.

in

2.

Table 3.4.1 Run or Startup Mode (except for low power physics testing)

Generator is inoperable.

The Reactor may remain in operation for a period not to exceed 7 Davs.

The Redundant active loop components within the same loop as the inoperable components are verified OPERABLE on a daily basis.

Specification 3.4.A.3 is met unless only a core spray booster pump is inoperable.

All core spray equipment connected to the OPERABLE emergency diesel generator is AmendmentNo.: 75 153 9

Y l-67 247 I04

_I_

L

~-~ -

Run or Startup Mode (except for low power physics testing)

Condition 3ne core spray loop (System I 3r System 2) or its core spray header delta-P instrumentation becomes inoperable.

Both of the redundant components in a loop (System 1 or System 2) are inoperable.

-0R-Two of the four redundant active loop components in the core spray system not in the same loop (System 1 or System

2) are inoperable.

Two or more non-redundant active loop components are inoperable in both loops (System 1 and System 2).

-0R-Condition Maintenance or modifications of core spray systems, their power supplies, or water supplies.

OYSTER CREEK The Reactor may remain in operation for a period not to exceed 7 Days.

The Reactor may remain in operation for a period not to exceed 7 Days.

Shutdown or Refuel Mode

~~

~

Requirement Maintain reduced core spray system availability as follows:

1.At least one core spray pump, and system components necessary to deliver rated core spray to the reactor vessel, must remain OPERABLE to the extent the pump and any necessary valves can be started or operated from the control room or from local control stations.

2.The Fire protection system is OPERABLE to the extent that one diesel driven fire pump is capable of providing water to the core spray system.

3.Verify the systems in 1 & 2 above are OPERABLE on a weekly basis.

Provided:

Both Emergency Diesel Generators are OPERABLE.

The remaining loop (System 1 or System 2) has no inoperable components and is verified daily to be OPERABLE.

Specification 3.4.A.3 is met.

Both Emergency Diesel Generators are OPERABLE.

The Redundant active loop components within the same loop as the inoperable components are verified OPERABLE on a daily basis.

Specification 3.4.A.3 is met.

Provided:

The Reactor is maintained in the COLD SHUTDOWN CONDITION or in the REFUEL MODE with the reactor coolant system maintained at less than 2 12°F and vented.

-AND-No work is performed on the reactor vessel and connected systems that could result in lowering the reactor water Ievel to less than 4'8" above the TOP OF ACTIVE FUEL.

3.4-2 Amendment No.: ?5,!52, re3,

?l-l+W, 247

(i

e.._

Condition Maintenance or modifications of core spray systems, their power supplies, or water supplies while work is in progress having the potential to lower reactor water level below 48 TAF.

The Reactor is in the startup mode for low power physics testing.

-0R-The requirements for maintenance or modification can not be met.

Shutdown or Refuel Mode Requirement Maintain reduced core spray system availability as follows:

1.At least one core spray pump in each loop, and system components necessary to deliver rated core spray to the reactor vessel, must remain OPERABLE to the extent that the pump and any necessary valves in each loop can be started or operated fiom the control room or from local control stations.

2.Fire protection system is OPERABLE to the extent that one diesel driven fire pump is capable of providing water to the core spray system.

3.Verify the systems in 1 & 2 above are OPERABLE every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Initiate work to meet the requirements.

Provided:

The Reactor is:

In the REFUEL MODE with the reactor coolant system maintained at less than 212F.

In the STARTUP MODE for the purpose of low power physics testing.

-0R-Specification 3.4.A.2 is met.

3. In the event of inoperable active loop components the APLHGR of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90% ofthe limits given in Specification 3.10.A. The action to bring the core to 90% of the APLHGR Limits must be-completed within two hours after the component has been determined to be inoperable.

4. The core spray system is not required to be operable when the following conditions are met:

a. The reactor mode switch is locked in the Refuel or Shutdown position.

b. (1)

There is an operable flow path capable of taking suction from the condensate storage tank and transferring water to the reactor vessel, and (2)

The fire protection system is OPERABLE to the extent that one diesel driven fire pump is capable of providing water to the core spray system, and (3)

These systems are verified to be OPERABLE on a weekly basis.

OYSTER CREEK 3.4-3 Amendment No.: 75, ! 55, 1%

c.

The reactor coolant system is maintained at less than 212 O F and vented (except during r&actGTessel pressure testing).

-- -_ - --_^_

&"2:-

_I core spray flow to the reactor vessel, must remain operable to the extent that the pump and any necessary valves can be started or operated from the control room or from local control stations, and the torus is mechanically intact. Verify the pump and components are OPERABLE, as described, on a weekly basis.

(1)

e.

No work shall be performed on the reactor or its connected systems which could result in lowering the reactor water level to less than 4'8" above the TOP OF the ACTIVE FUEL and there is a minimum of 360,000 gallons of water available between the torus and condensate storage tank water inventories. At least two redundant core spray systems including core spray pumps and system components must remain operable as defined in d.

above, At least one recirculation loop discharge valve and its associated suction valve shall be in the full open position. Verify the pumps and components are OPERABLE, as described, on a weekly basis.

OR (2)

The reactor vessel head, fuel pool gate, and separator-dryer pool gates are removed and the water level is above elevation 1 17 feet. When filling or draining the reactor cavity, a sufficient water inventory (between the condensate storage tank and the reactor cavity) to complete the flooding operation shall be maintained. The 360,000 gallons of water minimum requirement in (1) above nd draining operation provided there is a plete the flooding operation.

W,*

Amendment No.: 75 12

'-4

,247

B.

Automatic Depressurization System ich-provide the automatic depressurization and ions, shall be operable when the reactor water temperature is greater than 212°F and pressurized above 110 psig, except as specified in 3.4.B.2 and during Reactor Vessel Pressure Testing consistent with Specifications 1.39 and 3.3.A.(i).

If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.

If Specifications 3.4.B.1 and 3.4.B.2 are not met; reactor pressure shall be reduced to 1 10 psig or less, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

3.

4.

The time delay set point for initiation after coincidence of low-low-low reactor water level and high drywell pressure shall be set not to exceed two minutes.

C.

Containment Spray System and Emergency Service Water Svstem NOTE: LCO 3.0.C.2 is not applicable to the Containment Spray System and Emergency Service Water System

1.

The containment spray system and the emergency service water system shall be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specifications 3.4.C.3, 3.4.C.4,3.4.C.6 and 3.4.C.8.

The absorption chamber water volume shall not be less than 82,000 fi3 in order for the

2.

3.

If one emergency service water system loop becomes inoperable, its associated containment spray system loop shall be considered inoperable. If one containment spray system loop andor its associated emergency service water system loop becomes inoperable during the run mode, the reactor may remain in operation for a period not to exceed 7 days provided the remaining containment spray system loop and its associated emergency service water system loop each have no inoperable components and are verified daily to be operable.

If a pump in the containment spray system or emergency service water system becomes inoperable, the reactor may remain in operation for a period not to exceed 15 days provided the other similar pump is verified daily to be operable. A maximum of two pumps may be inoperable provided the two pumps are not in the same loop. If more than two pumps become inoperable, the limits of Specification 3.4.C.3 shall apply.

During the period when one diesel is inoperable, the containment spray loop and emergency service water system loop connected to the operable diesel shall have no inoperable components.

4.

5.

6.

If primary containment integrity is not required (see Specification 3.5.A), the placed in cold shutdown condition. If the containment spray system or the emergency service water system becomes inoperable, the reactor shall be placed in the cold shutdown condition and no work shall be performed on the reactor or its connected systems which could result in lowering the reactor water level to less than 4'8" above the top of the active fuel.

The containment spray system may be made inoperable during the integrated primary containment leakage rate test required by Specification 4.5, provided that the reactor is maintained in the cold shutdown condition and that no work is performed on the reactor or its connected systems which could result in lowering the reactor level to less than 4'8" above the top of the active fuel.

8.

D.

Control Rod Drive Hydraulic System

1.

The control rod drive (CRD) hydraulic system shall be operable when the reactor water temperature is above 212°F except as specified in 3.4.D.2 and 3.4.D.3 below.

2.

If one CRD hydraulic pump becomes inoperable when the reactor water temperature is above 2 12"F, the reactor may remain in operation for a period not to exceed 7 days provided the second CRD hydraulic pump is operating and is checked at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . If this condition cannot be met, the reactor water temperature shall be reduced to less than 21 2°F.

E.

Core Spray and Containment Spray Pump Compartments Doors The core spray and containment spray pump compartments doors shall be closed at all times except during passage in order to consider the core spray system and the containment spray system operable.

F.

Fire Protection System

1.

The fire protection system shall be operable at all times with fuel in the reactor vessel except as specified in Specification 3.4.F.2.

2.

If the fire protection system becomes inoperable during the run mode, the reactor may remain in operation provided both core spray system loops are operable with no inoperable components.

OYSTER CREEK 3.4-6 Amendment No.: 75, !-BdS, 247 1

L Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F LEVEL INSTRUMENTATION AVAILABILITY 1.0 PREREQUISITES The evaluation of RPV Water Level Instruments has been directed by the Emergency Operating Procedures.

2.0 PREPARATION None 3.0 PROCEDURE An RPV water level instrument may be used to determine RPV water level only when all the following conditions are satisfied for that instrument.

3.1 Record the temperatures of the following instrument reference leg vertical runs as read on recorder TR-IA55 on Panel 8R or the Plant Process Computer.

Level Instrument Temp Instrument No. Recorder Point Temperature NR GEMAC A (LT-1D13A)

TE-130-450 40 Y

o

%. W*-

TE-130-451 41 w

WR GEMAC (LT-lA12)

TE-130-452 42 VCf L/

YARWAY A (LT-RE05/19A)

TE-130-453 43 Yxd YARWAY B (LT-REOS/lgB)

TE-130-454 44 OVER (320002/8)

E6-1

c Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F If reference leg temperatures are in the UNSAFE REGION of the curve, that instrument may no evaluation of reference leg c Verify that the instrument reference leg temperatures are in the SAFE REGION of the RPV Saturation Temperature Curve.

RPV Saturation Temperature 0

200 400 600 800 1000 RPV PRESSURE (psig)

Procedure EMG-3200.02 Support Proc. 28 Rev. 17 t t achment F age 3 of 4 NOTE 3.3 Instruments may be used only when in the Safe Region of the curve.

If the instrument goes in the Unsafe Region of the curve, be used again until it returns to the Safe Region, at which time it is valid for level indication response.

it may not For each instrument below, the instrument reads in the Safe Region of its respective curve.

CEMAC NARROW RANGE 90 - 180 in.

iz' 4

I-C U

106 104 102 100 98 96 94 92 90 88 1

I 200 300 400 500 Reference Leg Temperature (F)

~

- ~ ~ - - + - + - ~ - p c _ u _ b _ _ _ _ b _ _ q _ _ _ c _ _

OVER (320002/8)

E6-3

Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F - -~

___I - -

Y a m y 85 - 185 in.

1 I

1 100 95 90 85 80 200 300 400 500 Reference Leg Temperature (F)

GEMAC Wide Range 21 0 I

- 190

-I 170 a

P c.l,150 m u,

o u rn $130 E.E "110 E

4-E 90 c

$j 70 50 50 150 250 350 450 550 Reference Leg Temperature (F)

(320002/8)

E6-4

3 0

i-dl 7

7 a

z y

0 X

r -

m 0

E2-1

I CONTROL ROOM EVACUATION ATTACHMENT ABN-30-4 SATURATION CONDITIONS 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 PSlG O F 0

212 225.24 227.96 230.57 233.07 235.49 237.82 240.07 242.25 244.36 246.41 248.40 250.33 252.22 254.05 255.84 257.58 259.28 260.95 262.57 264.16 265.72 267.25 268.74 270.21 271.64 273.05 274.44 275.80 277.13 278.45 279.74 281.01 282.26 283.49 284.70 285.90 287.07 288.23 289.37 290.50 291.61 292.71 293.79 294.85 295.90 296.94 297.97 298.99 299.99 300.98 301.96 PSlG O F 55 302.92 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71

' 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100

- 101 1 02 103 104 105 106 107 108 109 303.88 304.83 305.76 306.68 307.60 308.50 309.40 31 0.29 31 1.I6 31 2.03 312.89 31 3.74 314.59 31 5.42 31 6.25 317.07 31 7.88 31 8.68 31 9.48 320.27 321.06 321.83 322.60 323.36 324.12 324.87 325.61 326.35 327.08 327.81 328.53 329.25 329.96 330.66 331.36 332.05' 332.74 333.42 334.10 334.77 335.44 336.11 336.77 337.42 338.07 338.72 339.36 339.99 340.62 341.25 341.88 342.50 343.1 1 343.72 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 137 139 141 143 145 147 149 151 153 155 157 159 161 163 165 167 169 171 173 175 177 179 181 183 185 190 PSlG O F 110 344.33 344.94 345.54 346.1 3 346.73 347.32 195 200 205

- 210 21 5 220 225 All pressures in PSlG are rounded to the nearest whole number.

26.0 347.90 348.48 349.06 349.64 350.21 350.78 351.35 351.91 352.47 353.02 353.57 354.12 354.67 355.21 355.76 356.29 356.83 357.36 357.89 358.42 359.46 360.49 361.52 362.53 363.53 364.53 365.51 366.48 367.45 368.41 369.35 370.29 371.22 372.14 373.06 373.96 374.86 375.75 376.64 377.51 378.38 379.24 380.10 380.95 381.79 383.86 385.90 387.89 389.86 391.79 393.68 395.54 397.37 1

PSlG O F 235 400.95 240 402.70 245 404.42 250 255 260 265 270 275 280 285 295 305 31 5 325 335 345 355 365 375 385 395 405 415 425 435 445 455 465 475 485 505 525 545 565 585 605 625 645 665 685 705 725 745 765 785 805 825 845 865 885 905 925 945 965 985 I000 1025 1035 406.1 1 407.78 409.43 41 1.05 412.65 414.23 41 5.79 417.33 420.35 423.29 426.16 428.97 431.72 434.40 437.03 439.60 442.12 444.59 447.01 449.39 451.73 454.02 456.28 458.50 460.68 462.82 464.93 467.01 471.07 475.01 478.58 482.58 486.21 489.21 493.21 496.58 499.88 506.25 506.25 509.34 512.36 515.33 518.23 521.08 523.88 526.63 529.33 531.98 534.59 537.16 539.68 542.17 544.61 546.22 548.38 550.57

. Amerrnu 1 OYSTER CREEK GENERATING An ~xehm~ompay ---

STATION PROCEDURE ATTACHMENT 202.1-1 DAILY APRM STATUS CHECK NOTE: MARK FAILED OR INOP LPRMS WITH AN X. Complete work sheet per 202.1-4 instructions.

Section 1 : Perform nightly a umber 202.1 403-3 Verified correct (initial) 403-4 Verified correct (initial)

L-l-El-I

OYSTER CREEK GENERATING Number

_I 1(1

- E i E ~ h C o m p a n y. =

STATION PROCEDURE ABN-37 Attachment ABN-37-7 Restartinq Critical Loads P

- - __ I CAUTION ximum allowable SBO tra with the CT Operator and System CRD pump(s) IAW 302.1, Control Rod Drive System Service Water pump(s) IAW 322, Service Water System TBCCW pump(s) IAW 309.1, Turbine Building Closed Cooling Water System Air compressor(s) IAW 334, Instrument and Service Air System RBCCW pump(s) IAW 309.2, Reactor Building Closed Cooling Water System Drywell Cooling fans IAW 31 2.9, Primary Containment Control MAINTAIN SBO transformer load less than 8 MWe.

MWe.

If the first pump in each system below is being started, and time permits, consider starting the pump with its discharge valve closed, in order to

2.

or plant conditions, and if power is available (through other attachments):

Panel Load 4F 200 Kwe each 5F/6F 204 Kwe each 13R I81 Kwe each 5 F/6 F 144 Kwe each 13R 159 Kwe each 11R 25 Kwe each

[

I 25.0

Attachment ABN-37-7 Restarting Critical Loads (continued)

System Panel Load Condensate Transfer pump(s) IAW 31 6. I,

5F/6F 41 Kweeach A Battery Charger IAW 340.1, 125 VDC 8F/9F 65 Kwe B Battery Charger IAW 340.1,125 VDC 8F/9F 65 Kwe Condensate Transfer System

[

I Distribution Systems A & B Distribution Systems A & B

[

I

[

I End of Attachment ABN-37-7

3 L R E A C T O R COOLANT u

Applies to the operating status of the reactor coolant system.

To assure the structure integrity of the reactor coolant system.

Obiective:

Soecification:

A. Pressure Temoerature Relationshios (i) Reactor Vessel Pressure Tests - the minimum reactor vessel temperature at a given pressure shall be in excess of that indicated by the curve A in Figures 3.3.1, 3.3.2 and 3.3.3 for reactor operations to 22, 27 and 32 effective full power years, respectively. The maximum temperature for Reactor Vessel Pressure Testing is 250°F.

(ii) Heatup and Cooldown Operations: Reactor noncritical -- the minimum reactor vessel temperature for heatup and cooldown operations at a given pressure when the reactor is not critical shall be in excess of that indicated by the curve B in Figures 3.3.1, 3.3.2 and 3.3.3 for reactor operations up to 22, 27 and 32 effective full power years, respectively.

power operations at a given pressure shall be in excess of that indicated by the curve C in Figures 3.3.1, 3.3.2 and 3.3.3 for reactor operations up to 22, 27 and 32 effective full power years respectively.

te: Curves A, B and C in Figures 3.3.1, 3.3.2 and 3.3.3 apply en the closure head is on the reactor vessel and studs (iii) Power operations -- the minimum reactor vessel temperature for

~

(iv) Appropriate new pressure temperature limits must be generated when the reactor system has reached thirty-two (32) effective full power years of reactor operation.

B. Reactor Vessel Closure Head Boltdown: The reactor vessel closure head studs may be elongated.020 (1/3 design preload) with no restrictions on reactor vessel temperature as long as the reactor vessel is at atmospheric pressure. Full tensioning of the studs is not permitted unless the temperature of the reactor vessel flange and closure head flange is in excess of 85°F.

C. Thermal Transients

1. The average rate of reactor coolant temperature change during normal heatup and cooldown shall not exceed 100°F in any one hour period.

2. The pump in an idle recirculation loop shall not be started unless the temperature of the coolant within the idle recirculation loop is within 50°F of the reactor coolant temperature.

OYSTERCREEK 3.3-1 Amendment No: 42,120,151,188

-- I-_

.LJ Reactor coolant system leakage shall be limited to:

a.

5 gpm unidentified leakage

b.

c.

25 gpm total (identified and unidentified) 2 gpm increase in unidentified leakage rate within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period while operating at steady state power

2.

With the reactor coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to within the acceptable limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

With any reactor coolant leakage greater than the limit in 3.3.D.1.c above, identifjr the source of leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

For determination of unidentified leakage, the primary containment sump flow monitoring system shall be operable except as specified below:

4.

a.

With the primary containment sump flow integrator inoperable:

s3jEcified in plant procedures.

b.

If Specification 3.3.D.4a cannot be met, place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5.

For determination of identified leakage, the primary containment equipment drain tank monitoring system shall be operable except as specified below:

a.

With the primary containment equipment drain tank monitoring system inoperable:

1.

2.

Restore it to operable status within 7 days.

Calculate the identified leakage rate utilizing an acceptable alternate means as specified in plant procedures.

b.

If Specification 3.3.D.5.a cannot be met, place the reactor in the shutdown condition within the next I 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

OYSTERCREEK 3.3-2 Amendment No: 133 W

eration with steaming rates to the turbine-condenser of less than 100,000 pounds per hour shall be limited to:

conductivity chloride ion 0.1 ppm When the conductivity and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212°F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2 us/cm[s=mhos at 25OC (77"FI

2.

3.

The reactor coolant quality during power operation with steaming rates to the turbine-condenser of greater than or equal to 100,000 pounds per hour shall be limited to:

conductivity 10 uS/cm

[S=mhos at 25°C (77"F)l chloride ion 0.5 ppm When the maximum conductivity or chloride concentration limits given in 3.3.E.3 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212°F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

5.

During power operation with steaming rates on the turbine-condenser of greater than or equal to 100,000 pounds per hour, the time limit above I.O uS/cm at 25OC (77OF) and 0.2 ppm chloride shall not exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for any single incident.

.u' When the time limits for 3.3.E.5 are exceeded, an orderly shutdown shall be initiated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

F.

Recirculation LOOR Operabilitv

1.

During POWER OPERATION, all five recirculation loops shall be OPERATING except as specified in Specification 3.3.F.2.

POWER OPERATION with a maximum of two IDLE RECIRCULATION LOOPS or one IDLE RECIRCULATION LOOP and one ISOLATED RECIRCULATION LOOP is permitted. The reactor shall not operate with two ISOLATED RECIRCULATION LOOPS.

a.

2.

With one ISOLATED LOOP the following conditions shall be met:

1.

The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) as a function of average planar exposure, at any axial location shall not exceed 98% of the limits specified in 3.1 O.A. The action to bring the core to 98% of the APHLGR limits shall be completed prior to isolating the recirculation loop.

OYSTER CREEK 3.3-3 Corrected Letter dated 8/7/2000

- 2.

The circuit breaker of the recirculation pump motor generator set associated w shall be open an An ISOLATED RECIRCULATION LOOP shall not to service unless the reactor is in the COLD SHUTD condition.

3.

b.

When there are two inoperable recirculation loops (either two IDLE RECIRCULATION LOOPS or one IDLE RECIRCULATION LOOP and one ISOLATED RECIRCULATION LOOP) the reactor core thermal power shall not exceed 90% of rated power.

3.

If Specifications 3.3.F.1 and 3.3.F.2 are not met, an orderly shutdown shall be initiated immediately until all operable control rods are fblly inserted and the reactor is in either the REFUEL MODE or SHUTDOWN CONDITION

-, within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.

With reactor coolant temperature greater than 212°F and irradiated fuel in the reactor vessel, at least one recirculation loop discharge valve and its associated suction valve shall be in the full open position.

5.

If Specification 3.3.F.4 is not met, immediately open one recirculation loop discharge valve and its associated suction valve.

6.

With reactor coolant temperature less than 2 12°F and irradiated fuel in the reactor vessel, at least one recirculation loop discharge valve and its associated ion valveshall be in the full open position unless the reactor vessel is flooded to a level above 185 inches TAF or unless the steam separator and dryer are removed.

OYSTERCREEK 3.3-3a Corrected Letter dated 8/7/2000

Operational conditions - Startup and Run Modes; applies to the operational status of the primary coolant system pressure isolation valves.

Objective:

To increase the reliability of primary coolant system pressure isolation valves thereby reducing the potential of an inter-system loss of coolant accident.

Suecification:

1.

During reactor power operating conditions, the integrity of all pressure isolation valves listed in Table 3.3.1 shall be demonstrated. Valve leakage shall not exceed the amounts indicated.

2.

If Specification 1 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

H.

Reauired Minimum Recirculation Flow Rate for Operation in IRM Ranize 10

1.

During STARTUP mode operation, a minimum recirculation flow rate is required before operating in IRM range 10 to ensure that technical specification limits for operation are not exceeded. This minimum flow rate ired once the reactor is in e=--*-

- &.-.s'

---x#ss

2.

39.65 x lo6 lbhr is the minimum recirculation flow rate necessary for operation in IRM range 10 at this time. This flow rate leaves sufficient margin between the minimum flow required by the RWE analysis performed and the minimum flow used while operating in IRM range 10.

NRC Order Dated April 20, 1981 OYSTER CREEK 3.3-4 Corrected Letter dated 8/7/2000 AKeXdment No: 15,42,71,212

STATION PROCEDURE ATTACHMENT 333-1 5 EQUIPMENT ACTUATED BY FIRE PANELS

-FAP #I (Reactor 3uilding)

LFAP # I (Reactor Building) 4P PE-521 Sh. 1 JC 19635 Sh. 1 AP PE-521 Sh. 1 JC 19635 Sh. 1 I)

Actuate one detector from Rx Bldg 23 North side Zone I AND

2) Actuate one detector from Rx Bldg 23 North side Zone 2 OR

3) Actuate manual pull station

1) Actuate one detector from Rx Bldg 23 South side Zone 1 AND

2) Actuate one detector from Rx Bldg 23 South side Zone 2 OR

3) Actuate manual pull station

1) Actuate Deluge System #7

1) Actuate Deluge System #8 E15-1

ii ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS LFAP # I (Reactor Building)

LFAP # I (Reactor Building) 4P PE-521 Sh. 1 JC 19635 Sh. 2 AP PE-521 Sh. 1 JC 19635 Sh. 2 INITIATING "

EVENT

1) Actuate one detector from Rx Bldg 51' North side Zone 1 AND

2) Actuate one detector from Rx Bldg 51' North side Zone 2 OR

3) Actuate manual pull station

1) Actuate one detector from Rx Bldg 51' South side Zone 1 AND

2) Actuate one detector from Rx Bldg 51' South side Zone 2 OR

3) Actuate manual pull station AFFECTED EQU 1-PM ENT

1) Actuate Deluge System #5

1) Actuate Deluge System #6 E l 5-2

STATION PROCEDURE ATTACHMENT 333-1 5 (continued)

,FAP#2 (4160V EQUIPMENT ACTUATED BY FIRE PANELS AP PE-521 Sh. 2 switchgear Area) 2 & D 4160V CO2 System IC 80-02-071 FS FLR-31817-0 NlTlATlNG

^

EVENT I) Detector actuated in C 41 60V Swgr.

Room OR

2) Detector actuated in D 41 60V Swgr.

Room

-~

1) Actuation of manual pull station outside of the C or D 41 60V Swgr.

Rooms

1) Actuate six electric thermal links (ETL) which close dampers and roll-up doors if open.

AND

2) Trip C Swgr. Room Fan AND

3) Trip D Swgr. Room Fan

1) Actuate six electric thermal links (ETL) which close dampers and roll-up doors if open.

AND

2) Trip C Swgr. Room Fan AND

3) Trip D Swgr. Room Fan AND

4) After 15 second time delay, CO2 is actuated in C and D 4160V Switchgear Rooms.

ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS FIRE PANEL NUMBER LFAP #2 (41 60V Switchgear Area)

LFAP #3 (Diesel Generator Area)

LFAP #4 (Turbine Basement North End)

LFAP #5 (Lower Cable Spread Room)

REFERENCE DRAWING AP PE-521 Sh.2

~~~

AP PE-521 Sh. 3 AP PE-521 Sh. 4 AP PE-521 Sh. 5

& 6 INlTlATl NG EVENT

1) Any detector actuated in N B 41 60V Swgr.

Area OR

2) Actuate manual pull station NIA NIA

1) One detector from any of the four zones in the LCSR.

OR

2) Flow alarm from Deluge System

4A OR

3) Flow alarm from Deluge System

4B AFFECTE EN

1) Actuate Preaction Valve V-9-1089 to fill Sprinkler System #22 piping N/A NIA

1) A Control Room HVAC trips.

E l 5-4

ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS LFAP #5 (Lower Cable Spread Room)

LFAP #5 (Lower Cable Spread Room) 4P PE-521 Sh. 5 IC 19635 Sh. 5 4P PE-521 Sh. 5 JC 19635 Sh. 5 I) Actuate one detector from Zone 1 AND

2) Actuate one detector from Zone 2 OR 3 ) Actuate manual pull station

1) Actuate one detector from Zone 3 AND

2) Actuate one detector from Zone 4 OR

3) Actuate manual pull station 4FFECTED EQUIPMENT

1) Actuate Deluge System 4A

1) Actuate Deluge System 4B E l 5-5

-FAP #6 (Control Zoom)

ATTACHMENT 333-15 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS

~EFERENCE 3RAWING 4P PE-521 Sh. 6 JC 19635 Sh. 5 Sh. 1 SN 15050.68-EE-I 3 INITIATIN%

EVENT

1) Any one detector in Halon System A, Zone 1 or 2.

OR

2) Any one detector in Halon System B, Zone I or 2.

OR

3) Any one detector in Halon System C, Zone 1 or 2 OR

4) Any one detector in Zone D, ceiling OR

5) A Supply Duct Detector 4FFECTED EQUIPMENT.

1) A Control Room HVAC trips.

E l 5-6

her-*

1 OYSTER CREEK GENERATING umber STATION PROCEDURE I

333 An Exeb Campany-ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS FIRE PANEL NUMBER LFAP #6 (Control Room)

REFERENCE DRAWING AP PE-521 Sh. 6 JC 19635 Sh. 5 TI OC-12010 Sh. 1 I N IT I AT1 N G EVENT I ) Any one detector in Halon System A, Zone 1 or 2.

OR

2) Any one detector in Halon System B, Zone 1 or 2.

OR

3) Any one detector in Halon System C, Zone 1 or 2 OR

4) Any one detector in Zone D, cei I i ng OR

5) B Supply or Exhaust Duct Detector

1) B Control Room HVAC trips.

E l 5-7

STATION PROCEDURE ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS W

LFAP #6 (Control Room)

LFAP #6 (Control Room) 4P PE-521 Sh. 6 JC 19635 Sh. 5 AP PE-521 Sh. 6 JC 19635 Sh. 5 NlTlATlNG WENT

1) Any one detector in Halon System A, Zone 1 AND

2) Actuate one detector in Halon System A, Zone

2.

OR

3) Actuate Manual Pull Station for Halon System A,

I)

Any one detector in Halon System B, Zone 1 AND

2) Actuate one detector in Halon System B, Zone

2.

OR

3) Actuate Manual Pull Station for Halon System

6.

1) After 15 second delay, Halon System A actuates.

1) After 15 second delay, Halon System B actuates.

i c E l 5-8

STATION PROCEDURE I NlTlATf NG EVENT ATTACHMENT 333-15 (continued)

AFFECTED EQUIPMENT EQUIPMENT ACTUATED BY FIRE PANELS AND LFAP #6 (Control Room)

AND LFAP #7 (480V Switchgear Room)

REFERENCE DRAWING AP PE-521 Sh. 6 JC 19635 Sh. 5 AP PE-521 Sh.7 BR E1345 GE 157B6350 Sh.

50A & 193B

1) Any one detector in Halon System C, Zone 1 AND

2) Actuate one detector in Halon System C, Zone

2.

OR

3) Actuate Manual Pull Station for Halon System C.

I)

Actuate one detector from Zone 3

1) After 15 second delay, Halon System C actuates.

1) Trip A 480V Swgr. Rm.

Supply Fan (FN-56-004)

2) Actuate one detector from Zone 4 OR

3) Actuate manual pull station in A room

2) Trip A 480V Swgr. Rm. Alt.

Exhaust Fan (FN-56-008)

AND

3) Close A room dampers (DM-56-015 & 16)

AND

4) After 60 second time delay, A 480V Room Halon I

actuated.

El5-9

ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS LFAP #7 (480V Switchgear Rooms)

LFAP #7 (480V Switchgear Room) 3EFERENCE

)

3RAWING 4P PE-521 Sh. 7 3R E1345 4P PE-521 sh. 7 BR E1345 GE 157B6350 sh.

72B & 77B I NlTlATl NG EVENT I ) Actuate one detector from Zone 5.

I ) Actuate one detector from Zone 1 AND

2) Actuate one detector from Zone 2 OR

3) Actuate manual pull station in B room.

1) Close fire door DR-814-015

1) Trip B 480V Swgr. Rm.

Supply Fan (SF-1-21)

AND

2) Close B room dampers (DM-56-013 & 14)

AND

3) After 60 second tome delay, B 480V Room Halon actuated.

STATION PROCEDURE ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS

-IRE PAREL-VUMBER LFAP #8 (AB Battery Room/MG Set Room)

LFAP #9 (Main Office Building)

DCX EW95427 SU 3E-665-18-1000 GU 3E-665-14-1000 4P PE-521 Sh. 12 GE 157B6350 Sh.

77A 8~ 83B AP PE-521 Sh. 8 JC 19635 Sh. 4

1) Actuate one detector from Zone 1 AND actuate one detector from Zone 2 OR

2) Actuate one of the manual pull stations OR

3) MG Set Room flow alarm N/A

1) Actuate electric thermal links (ETL) which close dampers for initiating events 1 or 2 only.

AND

2) Trip MG Set Room Spot Coolers for all initiating events (I, 2 or 3).

AND

3) Provides flow input (halon or water) to MFAP #A module

8 Flow for all initiating events (1, 2 or 3) which trips EF-1-20 and SF-1-20 AND

4) After 30 second time delay for initiating events I or 2 only, AB Battery Room halon system actuates.

N/A

STATION PROCEDURE ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS LFAP # I 0

[Monitor &

Shange Area)

LFAP #I 1 (Boiler House, AOG &

ORW)

LFAP # I 2 (Fire Water Pump House)

REFERENCE DRAWING AP PE-521 Sh. 9 JC 19635 Sh. 4 AP PE-521 Sh. 10 AP PE-521 Sh. 11 I NIT1 AT1 NG EVENT

1) One detector above Monitor &

Change ceiling OR

2) One detector below Monitor &

Change ceiling OR

3) Sprinkler system

I 2 flow alarm NIA

1) Actuate one thermal detector in Fire Water Pump House or above fuel tanks OR

2) Actuate Manual Pull Station

1) Close fire doors DR-814-22

& 23.

N/A

1) Actuate Deluge System #9 E15-12

STATION PROCEDURE ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS MFAP #A (Master Fire Alarm Panel A)

MFAP #B (Master Fire Alarm Panel B)

LFAP ER49 (Upper Cable Spread Room)

~

FPP-665-004 (Cable Bridge Tunnels)

~

Cable Bridge Tunnel AP PE-521 Sh. 12 GE 157B6350 Sh.

77A & 83B AP-PE-521 Sh. 12A BG BFE-2099 Sh. 1

& 3 BG BFE-2099 Sh. 3 JC 19479 Sh. 2 Module #8 Flow Alarm (refer to LFAP #8 for actuating devices)

1) Trip SF-1-20 (AB Battery Rm/MG Set Rm Supply Fan)

2) Trip EF-1-20 (AB Battery Rm/MG Set Rm Exhaust N/A NIA N/A N/A N/A N/A pull station V-9-442 to fill Preaction Sprinkler System #I6 piping.

E l 5-1 3

STATION PROCEDURE I_-..

~

W ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS Exciter CO2 System Turbine Bearing 10 C02 System Panel (Transformer Area

& Lube Oil Tank Area)

ER-811-817 GU 3E-812-17-1000 GU 3E-812-17-1 000 AGL 8-5832-1 BR 3042 Sh. 1 GU-3D-811-14-001 INITIATING EVENT

1) Actuate one detector in the exciter housing OR

2) Actuate Manual Pull Station I ) Actuate Bearing 10 detector

1) Actuate one thermal detector at MIA OR

2) Actuate one thermal detector at the Auxiliary Transformers OR

1) Actuate ETLs to close dampers in Exciter AND

2) After time delay, individual COn bottles will sequentially discharge up to approximately 30 minutes.

1) Bearing 10 C02 bottle discharges I ) Actuate Deluge System 1

3) Actuate manual pull station E15-14

ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS

'anel Transformer Area

$ Lube Oil Tank 4rea) fR-811-817 Panel (Transformer Area

& Lube Oil Tank Area)

ER-811-817 Station Blackout Transformer W O )

REFERENCE

~

DRAWING AGL 8-5832-1 BR 3042 Sh. 1

U 3C-811-15-1001 4GL 8-5832-1 Br 3042 Sh. 1 JC 19479 Sh. 2 I) Actuate one thermal detector at M I 6 OR

?) Actuate one thermal detector at the Startup Transformers OR

3) Actuate manual pull station

1) Actuate one thermal detector at Turbine Lube Oil Tank OR

2) Actuate manual pull station I ) Actuate one thermal detector at SBO Transformer OR

2) Actuate manual pull station

) Actuate Deluge System 2

1) Actuate Deluge System 3

1) Actuate Deluge System 10 E l 5-1 5

ATTACHMENT 333-1 5 (con ti nued)

EQUIPMENT ACTUATED BY FIRE PANELS

I J

SEB Fire Panel corridor) 3EB Fire Panel

corridor)

SEB Fire Panel (Corridor) ro x-2556-6 &

3R E0545 ro x-2556-6 &

3R E5045 TO X-2556-6 &

BR E0545 NITIATING EVENT

1) Actuate one detector in the SEB Battery Room (Zone 5 or

6)

I)

Actuate one detector in the SEB Battery Room Zone 5 AND

2) Actuate one detector in the SEB Battery Room Zone 6 OR

3) Actuate Battery Room Pressure Switch OR

4) Actuate manual pull station I)

Actuate one detector in the SEB Electrical Equiment Room (Zone 3 or 4)

E l 5-1 6

1) Trips exhaust Fan FN-843-7

1) Battery Room door closes AND

2) Closes fire dampers DM-843-4 & 5 AND

3) Trips exhaust Fan FN-843-7 if not already tripped AND

4) After 30 second time delay, Battery Room Halon is actuated I ) Trips exhaust Fan FN-843-5 AND

2) Trips supply Fan FN-843-4

STATION PROCEDURE ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS SEB Fire Panel (Corridor)

, -I TO X-2556-6 8t BR E0545

1) Actuate one detector in the SEB Electrical Equiment Room Zone 3 AND

2) Actuate one detector in the SEB Electrical Equipment Room Zone 4 OR

3) Actuate Electric Equipment Room Pressure Switch OR

4) Actuate manual pull station AFFECTED EQUIPMENT-

1) Electric Equipment Room door closes AND

2) Closes fire dampers DM-843-6 & 7 AND

3) Trips unit heater in Electric Equipment Room H-843-1 (UH-2)

AND

4) Trips exhaust fan FN-843-5 if not already tripped AND

5) Trips supply fan FN-843-4 if not already tripped AND

6) After 30 second time delay, Electric Equipment Room Halon is actuated.

E l 5-1 7

STATION PROCEDURE ATTACHMENT 333-15 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS SEB Fire Panel (Corridor)

- 2

'*.I 3EFERENCE

~

3RAWING ro x-2556-6 &

3R E0545 GU 3C-737-11-012 SEB Flow Switch (FS-811-5)

I)

Actuate one detector in the SEB Computer Room Zone 1 AND

2) Actuate one detector in the SEB Computer Room Zone 2 OR

3) Actuate SEB Computer Room Pressure Switch OR

4) Actuate manual pull station I ) Sprinkler System 17A Flow Switch actuation (FS-811-5)

I ) Trips Computer Room ED PAC air conditioning units M-834-4 through 9 AND

2) Closes fire dampers DM-843-3 AND

3) Trips Plant Computer (shunt trip)

AND

4) After 30 second time delay, Battery Room Halon is actuated.

I)

Trip SEB Telephone Room Battery Charger Distribution Panel SEB TEP ii E15-18

ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS Aain Gate Guard iouse

)CAB

)CAB 3CAB OCAB 3EFERENCE 3RAWING

?yrotronics DW NJ 5062 United Fire Prot Corp 941 16 United Fire Prot Corp 941 16 United Fire Prot Corp 941 16 United Fire Prot Corp 941 16 WA

1) Any System Alarm I)

Activation of Zone 7

1) Activation of Zone 8 OR

2) Activation of Zone 12 OR

3) Activation of Zone 16 OR

4) Activation of Zone 17

1) Activation of Zone 22 WA I ) F8 & F9 starters for stair pressurization

1) Alternate elevator recall I)

Elevator recall

1) Elevator shunt trip i/

E15-19

i ATTACHMENT 333-1 5 (continued)

EQUIPMENT ACTUATED BY FIRE PANELS i/'

IRE PANEL IUMBER

)CAB 3uilding 14 Fire

'anel NRW AOG LLRW lnite Fire Prot Corp 141 16 KU F-1069 AP-PE-521 Sh. 10 JH

_ _ 85-0036-020.*__

I) Activation of Zone 18 OR

?) Activation of Zone 19 OR

3) Activation of Zone 20

1) Activation of one detector in Zone I

of Simulator Room AND

2) Activation of one detector in Zone 2 of Simulator Room OR

3) Activation of manual pull station outside Simulator Room NIA N/A NIA

) HVAC trip I ) Trip Simulator Room HVAC AND

2) After short time delay, actuate Simulator Room Halon System NIA NIA N/A E l 5-20

ATTACHMENT 341-5 EDG 1 ENGINEERED SAFEGUARD LOADS AND OTHER CRITICAL LOADS

~

-- INDICATES ENGINEERED FEGUARD LOAD 0 INDICATES PRIORITY PUMP FOR SAFETY SYSTEM INDICATES ALTERNATE PUMP FOR SAFETY SYSTEM A INDICATES VALVE COULD RENDER SYSTEM INOPERABLE SYSTEM

-- CORE SPRAY SYSTEM PUMPS

-- CONT.

SPRAY SYSTEM PUMPS LIQUID POISON SYSTEM PUMPS

-- STANDBY GAS TREAT-MENT FANS CRD SYSTEM PUMPS SERVICE WATER SYS.

PUMP RBCCW SYS.

PUMP HVAC SYSTEM FAN POST ACCIDENT INSTRUMENT

-- CONTROL ROOb POWER PANEL (PAIPP)

CORE SPRAY BOOSTER PUMP NZ03A (247KW) SYS 1 ONLY IF-BOTH NZ03A AND NZ03B NOT RUNNING CORE SPRAY BOOSTER PUMP NZ03D (255KW) SYS 2-AUTO STARTS 1A (254KW) SYS 1 1B (254KW) SYS 1

E5-1

AmerGm.. I OYSTER CREEK GENERATING Number An Fxelw Cotnpany STATION PROCEDURE I

341 ATTACHMENT 341-5 (Continued)

EDG 1 ENGINEERED SAFEGUARD LOADS AND OTHER CRITICAL LOADS

-- INDICATES ENGINEERED SAFEGUARD LOAD 0 INDICATES PRIORITY PUMP FOR SAFETY SYSTEM A INDICATES VALVE COULD RENDER SYSTEM I e INDICATES ALTERNATE PUMP FOR SAFETY SYSTEM

~~

SYSTEM CORE SPRAY 8-SYSTEM CRITICAL VALVES CONT.

SPRAY 8-SYSTEM CRITICAL VALVES BUS 1A2 1A21 1A21A 1A21A 1A21A 1A21 B 1A21 B 1A21 B lA21 B 1A21 B 1A21 B V-20-15 SYSTEM 1 DISCHARGE VALVE (A IF V-20-40 IS OOS/lB21A)

V-20-21 SYSTEM 2 DISCHARGE VALVE (A IF V-20-41 IS 00SllAB2)

A V-20-3 NZOIA (SYS 1) PUMP SUCTION VALVE FROM TORUS 0 A V-20-33 NZOI D (SYS 2) PUMP SUCTION VALVE FROM TORUS 0 A V-20-12 SYSTEM 1 DISCHARGE VALVE V-20-27 SYSTEM 1 RECIR. TEST VALVE TO TORUS A V-21-9 PUMP 51A SUCTION A V-21-7 PUMP 51 B SUCTION A V-21-11 DW SPRAY DISCHARGE V-21-17 TORUS CLG DISCHARGE V-21-18 TORUS SPRAY 5% DISCHARGE A

"C' BAlTERY SHALL BE IN SERVICE TO CONSIDER EDG 1 OPERABLE.

Amerrnu 1 OYSTER CREEK GENERATING Number An Fxrh Company STATION PROCEDURE 1

341 ATTACHMENT 341-6 EDG 2 ENGINEERED SAFEGUARD LOADS AND OTHER --

CRITICAL LOADS

-- INDICATES ENGINEERED SAFEGUARD LOAD 0 INDICATES PRIORITY PUMP FOR SAFETY SYSTEM 0 INDICATES ALTERNATE PUMP FOR SAFETY SYSTEM A INDICATES VALVE COULD RENDER SYSTEM INOPERABLE SYSTEM SYSTEM 1 B2 PUMPS 182 CONT.

--SPRAY SYSTEM PUMPS LIQUID POISON SYSTEM

--GAS TREATMENT SYSTEM 1 B2 1 B2 20 2D 1 B21 1 B24 SYSTEM I 182 WATERSYS. I 183 SYS.

I 182 ROOM HVAC SYSTEM FAN POST ACCIDENT INSTRUMENT POWER PANEL (PA1 PP) 1 B3 182 EQUIPMENT 0 CORE SPRAY MAIN PUMP NZOI B ( 4 7 4 w SYS 2 CORE SPRAY MAIN PUMP NZOlC (474KW) SYS 1 0 CORE SPRAY BOOSTER PUMP NZ03B (247KW) SYS 2 0 CORE SPRAY BOOSTER PUMP NZ03C (247KW) SYS 1 - AUTO STARTS ONLY AFTER EDG BREAKER CLOSURE.

O CONTAINMENT SPRAY PUMP 51 C (239KW) SYS 2 O CONTAINMENT SPRAY PUMP 51 D (239KW) SYS 2 O ESW PUMP 52C (333KW) SYS 2 O ESW PUMP 52D (333KW) SYS 2 LIQUID POISON PUMP NP02-B AND SQUIB VALVE NPO5-B (25KW)

NOTE:

PRIORITY SGTS DEPENDS ON SYSTEM SELECTED ON PANEL 11R -

ALL ASSOCIATED VALVES ARE AIR OPERATED.

O EF-1-9 (SGTS II) (13KW)

~

^_z L -.--

O CRD SYS. PUMP NCO8B (200KW)

O SERVICE WATER PUMP 1-2 (204KW)

O RBCCW PUMP 1-2 (159KW)

SUPPLY FAN, FN-826-008B (14KW)

O PAIPP-2, PDP-733-058 (1.8Kw)

E6-1

h e r m u 1 OYSTER CREEK GENERATING Number An Exeh Company STATION PROCEDURE 1

341 I

I Emergency Diesel Generator Operation 76 ATTACHMENT 341-6 (Continued)

EDG 2

-- INDICATES ENGINEERED SAFEGUARD LOAD 0 INDICATES PRIORITY PUMP FOR SAFETY SYSTEM e INDICATES ALTERNATE PUMP FOR-SAFETY SYSTEM A INDICATES VALVE COULD RENDER SYSTEM INOPERABLE SYSTEM

-- CORE SPRAY SYSTEM CRITICAL VALVES 1 B21A 1 B21A 1B21A lB21A 1 B21A

~

-- CONT.

SPRAY SYSTEM CRITICAL VALVES 1 B21 B 1B21B 1821 B 18218 1 B21 B EQUIPMENT I

O V-20-41 SYSTEM 2 DISCHARGE VALVE (A IF V-20-21 IS OOS/lA21)

V-20-40 SYSTEM 1 DISCHARGE VALVE (A IF V-20-15 IS OOS/lA2)

O A V-20-4 NZOI B (SYS 2) PUMP SUCTION VALVE FROM TORUS 0 A V-20-32 NZOIC (SYS 1) PUMP SUCTION VALVE FROM TORUS 0 A V-20-18 SYSTEM 2 DISCHARGE VALVE V-20-26 SYSTEM 2 RECIR. TEST VALVE TO TORUS A V-21-1 PUMP 51 C SUCTION A V-21-3 PUMP 510 SUCTION A V-21-5 DW SPRAY DISCHARGE V-21-13 TORUS CLG DISCHARGE A V-21-15 TORUS SPRAY 5% DISCHARGE "6'

BAlTERY SHALL BE IN SERVICE TO CONSIDER EDG 2 OPERABLE.

I

-I --__-

- -~--.

E6-2

3.2 REACTIVITY CONTROL ivity andthe operating status of the

.d

. reactivity control systems for the reactor.

Obiective:

To assure reactivity control capability of the reactor.

Specification:

A.

Core Reactivity 1,

The SHUTDOWN MARGIN (SDM) under all operational conditions shall be equal to or greater than:

(a) 0.38% delta Wk, with the highest worth control rod analytically determined; or (b) 0.28% delta Wk, with the highest worth control rod determined by test.

2.

If one or more control rods are determined to be inoperable as defined in Specification 3.2.B.4 while in the STARTUP MODE or the RUN MODE, then a determination of whether Specification 3.2 A. is met must be made within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . If a determination cannot be made within the specified time period, then assume Specification 3.2 A.l is not met.

cification 3.2.A.1 is not met while in the STARTUP Mode or the meet Specification 3.2.A.1 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in the CONDITION within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.

If Specification 3.2.A.1 is not met while in the SHUTDOWN CONDITION, or the COLD SHUTDOWN CONDITION, then:

(a)

Fully insert all insertable control rods within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , AND (b)

If Specification 3.2.A.1 is not met while in the REFUEL MODE, then:

Comply with the requirements of Specifications 3.2.C and 3.5.B.

5.

(a)

(b)

Immediately suspend CORE ALTERATIONS except for fuel assembly removal, AND Immediately initiate action to fully insert all insertable control rods in control cells containing one or more fuel assemblies, AND (c)

Comply with the requirements of Specifications 3.2.C and 3.5.B.

__ B, Control Rod Svstem

1.

The control rod drive housing support shall be in place during power operation and when the reactor coolant system is pressurized above atmospheric pressure with fuel in the reactor vessel, unless all control rods are fully inserted and Specification 3.2.A is met.

The Rod Worth Minimizer (RWM) shall be operable during each reactor startup until reactor power reaches 10% of rated power except as follows:

2.

(a)

Should the RWM become inoperable after the first 12 rods have been withdrawn, the startup may continue provided that a second licensed operator verifies that the licensed operator at the reactor console is following the rod program.

Should the RWM be inoperable before a startup is commenced or before the first twelve rods are withdrawn, one startup during each calendar year may be performed without the RWM provided that the second licensed operator verifies that the licensed operator at the reactor console is following the rod program and provided that a reactor engineer from the Core Engineering Group also verifies that the rod program is being followed. A startup without the RWM as described in this subsection shall be reported in a special report to the Nuclear Regulatory Commission (NRC) within 30 days of the startup stating the reason for the failure of the RWM, the action taken to repair (b)

I Control rod withdrawal sequences shall be established with a banked position withdrawal sequence so that the rod drop accident design limit of 280 cal/gm is not exceeded. For control rod withdrawal sequences not in strict compliance to BPWS, the maximum in sequence rod worth shall be S I.O% AK.

3.

The average of the scram insertion times of all operable control rods shall be no greater than:

Rod Length Insertion Time Inserted (%)

(Seconds) 5 20 50 90 0.375 0.900 2.00 5.00

The average of the scram insertion times for the three fastest control rods of all groups of four control rods in a two-by-two array shall be no greater than:

lia insertion Time 5

0.398 20 0.954 50 2.120 90 5.300 Any four rod group may contain a control rod which is valved out of service provided the above requirements and Specification 3.2.A are met. Time zero shall be taken as the de-energization of the pilot scram valve solenoids.

In service control rods which cannot be moved with control rod drive pressure shall be considered inoperable. If a partially or fully withdrawn control rod drive cannot be moved with drive or scram pressure, the reactor shall be brought to a shutdown condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months unless investigation demonstrates that the cause of the failure is not due to a failed control rod drive mechanism collet housing. Inoperable control rods shall be valved out of service, in such positions that Specification 3.2.A is met. In no case shall the than six during the power operation. If this specification is not met, the reactor shall be placed in the shutdown condition.

4.

I number of inoperable control rods valved out of service be greater I

for approach to criticality nnels have an observed count u

rate equal to or greater than 3 counts per second.

C.

Standbv Liauid Control Svstem

1.

The standby liquid control system shall be operable at all times when the reactor is not shut down by the control rods such that Specification 3.2.A is met and except as provided in Specification 3.2.C.3.

2.

The standby liquid control solution shall have a Boron-I 0 isotopic enrichment equal to or greater than 35 atom %, be maintained within the crosshatched volume-concentration requirement area in Figure 3.2-1 and at a temperature not less than the temperature presented in Figure 3.2-2 at all times when the standby liquid control system is required to be operable.

3.

(a)

If one standby liquid control system pumping circuit becomes inoperable during the RUN mode and Specification 3.2.A is met, the reactor may remain in operation for a period not to exceed 7 days, provided the pump in the other circuit is verified daily to be operable, otherwise be in the Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(b)

If the solution is outside the cross-hatched volume-concentration area but within the shaded volume-concentration area of Figure 3.2-1, return the on to the cross-hatched area within 7 days. If, his time period, the requirement is still not met, submit a report to the NRC within 7 days advising them of plans to return the solution to the cross-hatched volume-concentration area.

If the solution is outside the cross-hatched volume concentration area and outside the shaded volume-concentration areaof-Figure 3.2-1, return the solution to within the shaded volume-concentration area of Figure 3.2-1 or be in the Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If the solution temperature is less than the minimum shown in Figure 3.2-2, increase the temperature to greater than the minimum and verify the solution is within the shaded volume-concentration area of Figure 3.2-1 or be in the Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If the enrichment requirement of 3.2.C.2 is not met:

(1)

Return the Boron-IO isotopic enrichment to greater than or equal to 35 atom % within 7 days of the receipt of the enrichment report. If, after this time period, the enrichment requirement is still not met, submit a report to the NRC within 7 days advising them plans to return the solution to greater than or to 35 atom % Boron-1 0 isotopic enrichment.

(2)

A check shall be made to ensure that the sodium pentaborate solution meets the original design criteria by comparing the enrichment, concentration and volume to established criteria (Boron-IO equal to or greater than 82 pounds). If the sodium pentaborate solution does not meet the original criteria, be in the Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D.

Reactivitv Anomalies The difference between an observed and predicted control rod inventory shall not exceed the equivalent of one percent in reactivity. If this limit is exceeded and the discrepancy cannot be explained, the reactor shall be brought to the cold shutdown condition by normal orderly shutdown procedure. Operation shall not be permitted until the cause has been evaluated and appropriate corrective action has been completed.

The NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of this situation in accordance with Specification 6.6.

OYSTER CREEK 3.2-4 Amendment No: 75, 124, 178

Attachment ABN-29-1 Equipment Availability Matrix for Fires R.B. 119 ELEV.

(RB-FZ-1 A)

Procedure ABN-29 Rev. 9 NA NA NA NA None

References:

GU 3E-911-41-041 GU 3E-911-41-042 (Hot Shutdown Path #3 for RB-FZ-1A)

(Cold Shutdown Path #I for RB-FZ-1A)

Manual Action Required:

IF Instrument Air is lost, (1)

THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 f l in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

FIRE ZONE R.B. 95' ELEV.

(RB-FZ-1 B)

EQUIPMENT POTENTIALLY AFFECTED Attachment ABN-29-1 Equipment Availability Matrix for Fires

" A ISOLATION CONDENSER Stm Vent Vlv (V-14-5)

Control Ckt Stm Vent Vlv (V-14-20)

Control CM Shell Makeup Valve Power and Control CM (V-11-36)

"B" ISOLATION CONDENSER DC Steam Inlet Vlv Ind Ckt (V-14-33)

Stm Vent Vlv Control Stm Vent Vlv Control Power and Control Ckt Shell Makeup Valve (V-11-34)

Ckt (V-14-1)

Ckt (V-14-19)

ALTERNATE CONTROLllNDlCATlON Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual

References:

GU 3E-91141-041 GU 3E-91141-042 (Hot Shutdown Path #3 for RB-FZ-1B)

(Cold Shutdown Path # I for RB-FZ-1 B)

Manual Action Required:

1)

IF Instrument Air is lost, LOCATION OF ALTERNATE CONTROLllNDlCATlON RB 95' EL, East RB 95' EL, East RB 95' EL, East RB 75' EL, East RB 95' EL, East RB 95' EL, East RB 95' EL. East Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE( S) 307 307 307 307 307 307 307 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 fI in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

t------

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYS I1 Parallel Vlvs. Power and Control Ckts (V-20-21,41)

"A" ISOLATION CONDENSER AC Stm Isolation Vlv Power Ckt (V-14-30)

DC Stm Isolation Vlv Pwr and Control Ckt DC Cond Return Valve Pwr and Control Ckt (v-I 4-34)

Steam Vent Vlv Control Ckt (V-14-5)

Steam Vent Vlv Control Ckt (V-14-20)

Shell Makeup Vlv Power and Control Ckt (V-11-36)

(V-I 4-3 I

)

ALTERNATE CONTROLllNDlCATlON Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROLllNDlCATlON RB 75' EL, South RB 75' EL, East RB 75' EL, East RB 75' EL, East RB 95' EL, East RB 95' EL, East RB 95' EL, East Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE(S) 308 307 307 307 307 307 307 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA

FIRE ZONE R.B. 75' ELEV.

(cont'd)

(RB-FZ-1 C)

(

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 EQUIPMENT POTENTIALLY AFFECTED "8" ISOLATION CONDENSER AC Strn Is01 Vlv Power Ckt (V-14-32)

DC Strn lsol Vlv Power, Ind and Control DC Cond Rtn Vlv Power, Ind and Control Ckt (v-14-35)

AC Cond Rtn Vlv Power, Ind and Control CM (V-14-37)

Strn Vent Vlv Is01 Ckt (V-14-1)

Strn Vent Vlv lsol Ckt (V-14-19)

Shell Makeup Vlv Power and Control Ckt (V-14-33)

Ckt (v-I 1-36)

REACTOR WATER CLEANUP RWCU Inlet Is01 Vlv Cont CM (V-16-1)

ELECTRICAL DISTR. SYS.

MCC DC-2 CONTAINMENT SYSTEM Torus Temperature Elements TI-664-43B ALTERNATE CONTROUINDICATION Local Manual Local Manual Local Manual None Local Manual Local Manual Local Manual None None TI-664-43A LOCATION OF ALTERNATE CONTROUINDICATION RB 75' EL, East RB 75' EL, East RB 75' EL, East Drywell RB 95' EL, East RB 95' EL, East RB 75' EL. East Drywell NA 1 F12F APPLICABLE PR OCED U RE( S) 307 307 307 307 307 307 307 303 340.1 NA REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA

( '

EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION FIRE ZONE Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR DOCUMENT REFERENCE Procedure ABN-29 Rev. 9 R.B. 75' ELEV.

(cont'd)

(RB-FZ-1 C)

References:

GU 3E-911-41-041 GU 3E-911-41-042 (Hot Shutdown Path #3 for RB-FZ-IC)

(Cold Shutdown Path # I for RB-FZ-IC)

Manual Action Required:

1)

IF Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ff in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351 2),

or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

2) Cable failures may cause DC-1 to trip.

IF DC-1 trips THEN Either manually control the SDC valves V-I 7-1, 2, 3, 55, 56 & 57 OR Open all load breakers on MCC DC-1 and re-close DC-B breaker #6 and then re-close MCC DC-1 breakers for SDC valves V-17-1, 2, 3, 55,56

& 57. Note that the remaining breakers on MCC DC-1 are not needed and should remain open to isolate the cable failures.

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE POTENTIALLY AFFECTED CO NTROUI N D I CATION FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR LOCATION OF ALTERNATE APPLICABLE DOCUMENT REFERENCE CONTROUI N D I CAT1 0 N P ROC ED U RE (S)

R.B. 51' ELEV. (RB-FZ-ID)

References:

GU 3E-91141-044 Hot Shutdown Path #5 - "B" Isolation Condenser. "B" CRD Pumo. Condensate Transfer PumD. Fuel Zone Level Ind. Ll-622-1001 &

1002, Rx. Pressure lnd.'PI-622-999 & i000, Offsite Pwr available; if spuriously opened EMRV, then Core Spray pumps NZOID & NZOJD, Containment Spray Pump 1 4, ESW pump 14, Torus Level Indicator LI-IPIOB

& Containment Spray Suction Hdr Temperature TR-IP001.

GU 3E-911-41-043 Cold Shutdown Path #3 - 2 EMRV's (with repairs), Core Spray Pumps, Containment Spray Pump, ESW pump, Fuel Zone Level Ind.

Ll-622-1001 & 1002, Rx. Pressure Ind. PI-622-999 & 1000, Rx Wide Range Lvl Ind (with repairs), Torus Water Temperature Ind (with repairs) and Torus Level Indicator LI-IP1 OB NOTE: This 'Cold Shutdown' Path utilizes 'Alternate Decay Heat Removal' per procedure 2000-OPS-3024.27, Section 4.4 to approach the Cold Shutdown condition (Core Spray, Containment Spray in Torus Cooling, and EMRV's). It may be necessary to perform repairs on affected equipment as identified in the list below.

Prompt Manual Actions:

NOTE:

1) NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

During a fire condition on the 51' elevation of the Reactor Building (RB-FZ-ID), the possibility exists that hot shorts will develop in the EMRV cabling such that 125 VDC from an external source will be supplied to an EMRV, causing it to fail open. This spuriously opened EMRV may not be reclosable by any means. Therefore, the following actions are required:

CAUTION: The following action is required to preclude or terminate a spuriously opened EMRV. This action will disable the ADS, High Pressure and manual controls associated with the EMRV's. If the EOP's require the use of the EMRV's the disable switches can be returned to the normal position.

One or more EMRV's exhibit abnormal or spurious operation or there are insufficient indications available to determine the status of an EMRV.

Ensure the reactor is scrammed in accordance with ABN-1 "Reactor Scram".

AND Place the disable switch on the rear of panel 1 F/2F to the "DISABLE" position for those EMRV's affected. NOTE: "EMRV DISABLED" annunciator on Panel 1 F12F (B-6-g) will alarm.

IF THEN

N 0

p3 Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 R.B. 51' ELEV. (RB-FZ-ID) (cont'd)

2) !E THEN

3)

CAUTION IF:

THEN NOTE 1:

4)

NOTE:

IF THEN

5) 1E THEN An EMRV is failed open.

Follow the Emergency Operating Procedures.

1)

The Core Spray parallel injection valves may not automatically open when the valve permissive is satisfied and control from the control room may also be lost. If the valves cannot be controlled automaticallylremotely, then immediately dispatch an operator to manually open the valve to assure adequate core cooling. Note that there is 66 minutes to perform this manual action from the start of the event but the valve permissive may not be satisfied for approximately 33 minutes leaving only 33 minutes to perform this manual action.

SCBA may be required to perform the manual opening of V-20-21 due to the possibility of smoke rising through the open equipment hatch from Rx. Bldg. 51' elevation.

2)

V-20-21 can not be operated from the control room Dispatch an operator with a radio to MCC 1A21 located in the 480V Room to place the breaker for V-20-21 to the "OFF" position. The operator should then proceed directly to 75' elevation and standby to manually open V-20-21 upon direction from the Control Room.

Torus cooling must be initiated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to prevent losing NPSH requirements for the Core Spray System During a fire condition on the 51' elevation (RB-FZ-1 D), the possibility exists that hot shorts will occur in the high flow logic circuitry of the "B" Isolation Condenser. This could cause a spurious isolation of valves V-14-32, V-14-33, V-14-35 and V-14-37.

no other decay heat removal system is available, override the isolation signal by placing the individual valve control switches to the position desired.

Instrument Air is lost.

V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 17.4 ft in the CST may be required for isolation condenser shell makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE R.B. 51' ELEV.

(cont'd)

(RB-FZ-1 D)

EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM I Parallel Vlvs Power and Control Ckts (V-20-15,40)

Booster Pump Disch.

Press. Ind (PT-RV41A) and diff press. sw.

Core Spray Booster Pumps (NZ03A, C)

(D PS-RV40A&C)

CORE SPRAY SYSTEM I I Parallel Vlvs Power and Control Ckts (V-20-21,41)

Pumps NZOl B & NZ03B Containment Istr.

Torus Temp Ind.

Tl-664-43 A&B ALTERNATE CONTROUlNDlCATlON Local Manual Local Gage (PI-4OC)

None Local Manual NZOI D & NZ03D TE 40A Suction Header Temp. for Core & Cont. Spray, LOCATION OF ALTERNATE CONTROUlNDlCATlON RB 51' EL, NW RB 51' EL, NW NA RB 75' EL, South CR TR lPOl Panel I F or perforirepair procedure APPLICABLE PROCEDURE(S) 308 308 NA 308 308 Repair Procedure REPAIR DOCUMENT REFERENCE NA NA NA NA NA 2400-APR-3228.02

0 0

P FIRE ZONE R.B. 51' ELEV.

(cont'd)

(RB-FZ-1 D)

EQUIPMENT POTENTIALLY AFFECTED Attachment ABN-29-1 Eq u i p rn e n t Ava i I a b i I i ty M at ri x for Fires

" A ISOLATION CONDENSER AC Stm Is01 Vlv Power Ckt (V-1430)

DC Stm Is01 Vlv Power and Control Ckt DC Cond Rtn Vlv Power and Control Shell Makeup Vlv Power and Control LT-IGO6A Ind. Circuit (V-I 4-3 1 )

Ckt (V-14-34)

Ckt (V-I 1-36)

"B" Isolation Condenser Hi Flow Protection (lB05-Bl & B2 and 1811-81 & 82)

ELECTROMATIC RELIEF VLVS EMRV " A Control Ckt.

EMRV "B" Control Ckt.

EMRV "C" Control Ckt.

EMRV "D" Control Ckt.

ALTERNATE CONTROUlNDlCATlON Local Manual Local Manual Local Manual Local Manual None Override Isolation Signal EMRV "A' Disable Swt EMRV "B" Disable Swt EMRV "C" Disable Swt EMRV "D" Disable Swt Temporary Control and Indication for NR108D LOCATION OF ALTERNATE CONTROUlNDlCATlON RB 75' EL, East RB 75' EL, East RB 75' EL, East RB 95' EL, East NA 1 F12F (Individual Valve Control Switch)

Rear 1 Fl2F Rear 1 F12F Rear 1 Fl2F Rear 1 F12F NA Procedure ABN-29 Rev. 9 APPLICABLE PROC ED U RE( S) 307 307 307 307 307 307 301 301 30 1 30 1 Repair Procedure REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA 2400-APR-341 1.01 341 1.04 2400-APR-

c FIRE ZONE R.B. 51' ELEV.

(con t'd)

(RB-FZ-1 D)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELECTROMATIC RELIEF VLVS (cont'd)

EMRV " E Control Ckt.

CONTAINMENT SYSTEM i x Low-Low Wtr Lvl (RE02A) Inst. Circuit Rx Low-Low Wtr Lvl (RE02B) Inst.

Circuit Rx Low-Low Wtr Lvl (RE02C) Inst.

Circuit Rx Low-Low Wtr Lvl (RE02D) Inst.

Circuit ALTERNATE EMRV " E Disable Swt I

Rear 1 F12F Ternporaly Control and Indication for NR108E None None None None NA NA NA NA NA Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE (S) 30 1 Repair Procedure NA NA NA NA REPAIR DOCUMENT REFERENCE NA 2400-APR-341 1.01 341 1.04 2400dP R-NA NA NA NA

w 0

P

~~

FIRE ZONE R.B. 51' ELEV.

(cont'd)

(RB-FZ-1 D)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED SHUTDOWN COOLING SYSTEM

" A LOOP Flow (FI 17-1)

"B" LOOP Flow (FI 17-2)

"C" LOOP Flow (FI 17-3)

"A' FUEL ZONE LEVEL LI-IA94A Pl-622-849

" B FUEL ZONE LEVEL LI-IA94B Pl-622-850 RX LEVEUPRESSURE INSTR.

GEMAC Wide Range Level Ind. (LI-IA13)

RBCCW SYSTEM Pump 1-1 Pump 1-2 SID Clg Hx Outlet Vlv Power and Control Ckt (V-5-106)

ALTERNATE CONTROUINDICATION None None None "C" Fuel Zone Lvl.

(Ll-622-1001)

(PI-622-999)

"D" Fuel Zone Lvl.

(Ll-622-1002)

(PI-622-1 000)

Install Local Gage (Ll-626-1007)

None None Local Manual LOCATION OF ALTERNATE CONTROUINDICATION NA NA NA CR PNL 5FI6F or RSP ("B" 480V Swgr Rm)

CR PNL 5FI6F or RSP ("B" 480V Swgr Rm)

RKOI (R.B. 75' EL, East)

NA NA SID Clg Room Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE(S) 305 305 305 41 0 346 41 0 346 Repair Procedure NA NA 305 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA 2400-APR-3665.01 NA NA NA

r" w

0 0

FIRE ZONE R.B. 51' ELEV.

(cont'd)

(RB-FZ-1 D)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CONT. SPRAY SYSTEM I D w e l l Spray Isol.

Valve (V-21-11) Pwr.

and Control Ckt.

Cont Spray System DC Control Power CONT SPRAY SYSTEM I I Cont Spray System DC Control Power RX WTR CLEANUP SYSTEM Aux Pump Suction Is01 Vlv. Pwr and Control Ckt (V-16-2)

Cleanup Inlet lsol Vlv. Pwr and Control Ckt (V-I 6-1 4)

High Press. Isol.

Switch (PS-215-1044)

ALTERNATE CONTROUINDICATION Local Manual Local Manual Local Manual Local Manual Local Manual High Press. Is01 SW (PS-IJ04A)

LOCATION OF ALTERNATE CONTROUIN D ICATION R.B. 51' EL. East See Manual Actions Below See Manual Actions Below R.B. 51' EL. South R.B. 51' EL. South R.B. 75' EL. South Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE(S) 310 NA NA 303 303 303 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA

i i

w 0

P Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 R.B. 51' ELEV. (RB-FZ-1 D)

(cont'd)

Additional Manual Actions Required:

If an EMRV is stuck open, then Containment Spray System must be started within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to prevent loosing NPSH for the core spray and containment spray pumps;

a.

b.

Containment Spray System I1 Containment Spray Pump 1 4 and ESW Pump 1-4 are designated for use during hot shutdown with an EMRV stuck open.

System I may still be used if its components are operable and accessible. However, no emergency lighting is provided for System I.

Operation of the following valves can be performed locally for the Containment Spray System if necessary. However prior to manually operating the valve, open its supply breaker on MCC 1821 B for System II or on MCC 1A21 B for System 1.

D w e l l Smav Valve V-21-5 (SYS II) v-21-11 (Sys I)

Location:

V-21-5 RB 23' East V-21-11 RB 51' East Required Position:

Closed Required Position:

Open TORUS CLG Discharue Valve V-21-13 (Sys II)

V-21-17 (SYS I)

Location:

V-21-13 RB 23' South V-21-17 RB 23' North

c.

Emergency lighting to operate the System II TORUS CLG Discharge Valve, V-21-13, is located near the drywell wall across from the railroad airlock door. This assembly consists of a portable DC light attached to an emergency lighting battery by 40' of cable. If needed, this cable is unwound and the light is used to gain access to the valve and illuminate the valve for operation. Two operators will be required to operate this valve if emergency lighting is required.

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 Close V-15-52 Throttle V-I 5-30 for desired flow on Fl-225-2 Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

w 0

c EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUlNDlCATlON CONTROUlNDlCATlON FIRE ZONE Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR DOCUMENT REFERENCE Procedure ABN-29 Rev. 9 GU 3E-911-41-043 Cold Shutdown Path #3 - 2 EMRVs (with repairs), Core Spray Pumps, Containment Spray Pump (with repairs), ESW pump, Fuel Zone Level Ind. LI-IA94B, Rx. Pressure Ind. PI-622-850, Rx Wide Range Lvl Ind LI-IA13, Torus Water Temperature Ind (with repairs) and Torus Level Indicator LI-IPlOB NOTE: This Cold Shutdown Path utilizes Alternate Decay Heat Removal per procedure 2000-OPS-3024.27, Section 4.4 to approach the Cold Shutdown condition (Core Spray, Containment Spray in Torus Cooling, and EMRVs). It may be necessary to perform repairs on affected equipment as identified in the list below.

Prompt Manual Actions:

NOTE:

1)

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

During a fire condition on the 23 elevation of the Reactor Building (RB-FZ-1 E), the possibility exists that hot shorts will develop in the EMRV cabling such that 125 VDC from an external source will be supplied to an EMRV, causing it to fail open. This spuriously opened EMRV will be reclosable using the normal EMRV control switch on 1 F12F.

CAUTION:

The following action is required to preclude or terminate a spuriously opened EMRV. This action will disable the ADS, High Pressure and manual controls associated with the EMRVs. If the EOPs require the use of the EMRVs, the disable switches can be returned to the normal position.

IF One or more EMRVs exhibit abnormal or spurious operation, There are insufficient indiczons available to determine the status of an EMRV.

OR THEN Ensure the reactor is scrammed in accordance with ABN-1 Reactor Scram, Place the disable switch on the rear of panel 1 F/2F to the DISABLE position for those EMRVs affected.

AND

i' Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 R.B. 23' ELEV.- RB-FZ-1 E (Cont'd)

Prompt Manual Actions (cont'd):

2)

NOTE:

IF THEN The Reactor Recirculation pump control circuits are located in this fire zone and they have to be tripped to utilize the Fuel Zone Level Indicators.

The Reactor Recirculation Pumps won't trip from the control room, trip and locked out (69 switch) focally at their respective switchgear provided that these pumps are not required

3)

IE Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 17.4 ft in the CST may be required for isolation condenser shell makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

FIRE ZONE R.B. 23' ELEV.

w 0

'I Attach men t AB N 1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 EQUIPMENT POTENTIALLY AFFECTED CRD HYDRAULIC SYSTEM CRD Flow to Rx Indication (FI-RD36)

CORE SPRAY SYSTEM I Booster Pump "C" (NZ03C)

" A Pump Suct Vlv "C" Pump Suct Vlv Parallel Vlv (V-20-40)

Booster Pmp Diff Press Sw CORE SPRAY SYSTEM II Booster Pumps "B, "D" Power Ckts (NZOJB,D)

Core Spray Pump Suction Vlvs Power and Control CMs Parallel Vlvs Power and Ckts (V-20-21,41)

Booster Pump Disch.

Press Ind. (PI-RV43B) and Diff Press Sw (V-20-3)

(V-20-32)

(DPS-RV40A)

(V-20-4,33)

(DPS-RV4OB & D)

" A ISOLATION CONDENSER AC Stm lsol Vlv Power and Control Ckt (V-1430)

ALTERNATE CONTROUINDICATION Local Gage (Fl-225-998)

Booster Pump " A (NZ03A)

Local Manual Local Manual Local Manual PI-RV43A None Local Manual Local Manual Local Gage (PI-RV40B)

Local Manual LOCATION OF ALTERNATE CONTROUINDICATION RB 51' EL, SE C.R. Panel 1 F/2F RB -19' EL, NW RB -19' EL, NW RB 51' EL, NW 1 Fl2F NA RB -19' EL, SW RB 75' EL, South RB 23' EL, South RB 75' EL, East APPLICABLE

)ROCEDURE(S) 302.1 308 308 308 308 308 308 308 308 308 307 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE R.B. 23' ELEV.

(cont'd)

(RB-FZ-1 E)

EQUl PMENT POTENTIALLY AFFECTED

'A" ISOLATION CONDENSER DC Stm Is01 Vlv Power

& Control Ckt (V-14-31) 4C Cond Rtn. Vlv Power

& Control Ckt (V-14-36)

DC Cond Rtn. Vlv Power

& Control Ckt (V-14-34)

"6" ISOLATION CONDENSER AC Cond. Rtr Is01 Vlv Power Ckt (V-14-37)

DC Steam Line Vlv Control

& Ind (V-14-33)

DC Cond. Vlv Control &

Ind (V-14-35)

ELECTROMATIC RELIEF VALVES EMRV " A Control Ckt EMRV "B" Control Ckt EMRV "C" Control Ckt EMRV 'ID Control Ckt (co nt'd)

ALTERNATE CONTROUINDICATION Local Manual None Local Manual None Local Manual Local Manual EMRV "A" Disable Swt EMRV "B" Disable Swt EMRV "C" Disable Swt EMRV "D" Disable Swt Temporary Control &

Indication for NRIOBD LOCATION OF ALTERNATE CONTROUINDICATION RB 7 5 EL, East NA RB 75' EL, East Drywell RB 75' EL, East RB 75' EL, East Rear CR PNL 1 F/2F Rear CR PNL 1 Fl2F Rear CR PNL 1 F/2F Rear CR PNL 1 F/2F NA

(

Procedure ABN-29 Rev. 9 APPLICABLE

)ROCEDURE(S) 307 307 307 307 307 307 301 30 1 301 30 1 Repair Procedures REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA 2400-APR-341 1.01 341 1.03 341 1.04 2400-APR-2400-APR-

FIRE ZONE R.B. 23' ELEV.

(cont'd)

(RB-FZ-1 E)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELECTROMATIC RELIEF VALVES (cont'd)

EMRV "E" Control Ckt ALTERNATE CONTROUINDICATION EMRV "E" Disable Swt Temporary Control &

Indication for NR108E LOCATION OF ALTERNATE CONTROUINDICATION Rear CR Pnl 1 F12F NA Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 301 Repair Procedures REPAIR DOCUMENT REFERENCE NA 24004PR-341 1.02 341 1.01 341 1.04 2400-APR-2400-APR-

FIRE ZONE R.B. 23' ELEV.

(cont'd)

(RE-FZ-1 E)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED SHUTDOWN COOLING SYS.

"A" SDC Pump Pwr and Control Ckt "B" SDC Pump Pwr and Control Ckt "C" SDC Pump Pwr and Control Ckt

" A Loop Suct Vlv Pwr

& Control Ckt (V-17-1)

"B" Loop Suct Vlv Pwr

& Control Ckt (V-17-2)

& Control Ckt (V-17-3)

"A" Loop Disch Vlv Pwr

& Control Ckt (V-I 7-55)

"B" Loop Disch Vlv Pwr

& Control Ckt (V-I 7-56)

"C" Loop Disch Vlv Pwr

& Control Ckt (V-1 7-57)

"C" Loop Suct Vlv ALTERNATE CONTROUINDICATION LSP-1A2 RSP None Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUINDICATION "A" 480V Swg. Room "6" 48QV Swg. Room NA SDC Room SDC Room SDC Room SDC Room SDC Room SDC Room Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 305,346 305,346 305 305 305 305 305 305 305 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

Attachment ABN-29-1 Eq u i p m e n t Ava i I a b i I i ty M at r i x for Fi res FIRE ZONE R.B. 23' ELEV.

(cont'd)

(RB-FZ-1E)

EQUIPMENT POTENTIALLY AFFECTED SHUTDOWN COOLING SYS.

SDC Sys Outlet Is01 Vlv Pwr & Control Ckt (v-17-54)

SDC Sys Inlet Is01 Vlv Pwr & Control Ckt Loop Disch Press Ind (cont'd)

(v-17-19)

(PI-RVO9 A, B, C)

Rx LEVEUPRESS INSTR.

Fuel Zone Lvl "C", "D" Fuel Zone Press "C",

(Ll-622-1001, 1002)

"0" (PI-622-999,1000)

CONTAINMENT INSTR.

Torus Temp Ind.

(TI46443 A & B)

RBCCW SYSTEM 1-1 RBCCW Pumo Pwr Ckt 1-2 RBCCW Pumb Pwr ckt ALTERNATE CONTROUINDICATION LSP-1AB2 LSP-1AB2 Local Gages (PIT-RVO6, A,B,C)

Fuel Zone Lvl "A, Fuel Zone Press "A" "B" (LI-IA-94A, B)

"B" (P 1-622-849,850)

TE-644-30B or TE-664-33B None None LOCATION OF ALTERNATE C 0 NTROUI N D lCATl0 N RB 23' EL., NE RB 23' EL., NE SDC Room C.R. Pnl5F16F C.R. Pnl5F16F Control Room Panel 19R SS1 TI-664-42B NA NA I,,

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 305,346 305,346 305 41 0 41 0 Repair Procedure 309.2 309.2 REPAIR DOCUMENT REFERENCE NA NA NA NA NA 2400-APR-3228.02 NA NA

P 0

Iu FIRE ZONE R.B. 23' ELEV.

(cont'd)

(RB-FZ-1 E)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED RBCCW SYSTEM (Cont'd)

RBCCW from DW Is01 Vlv (V-5-167) Pwr & Control Ckt SDC heat Exchangers Outlet Vlv. (V-5-106)

Power & Control Ckt CONTAINMENT SPRAY SYS.

Cont Spray Pump 1-1 Cont Spray Pump 1-2 Cont Spray Pump 1-3 (5 1 -A)

(51-B)

(51-C)

Cont Spray Pump 1-4 (51-D) 51A Pump Suct Vlv 51 B Pump Suct Vlv 51 C Pump Suct Vlv 51 D Pump Suct Vlv Sys I DW Spray lsol Vlv Sys I Torus CLG Discharge Vlv (v-2 1-9)

(V-21-7)

(V-21-1)

(V-2 1 -3)

(V-21-11) p - 2 1 -1 7)

ALTERNATE CONTROUINDICATION Local Manual Local Manual None None Repair Pwr Feeder Use Local Control At USS 1B2 Repair Pwr Feeder Use Local Control At USS 182 Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUINDICATION RB 23' EL., East SDC Room NA NA "B" 480V Swgr Room "B" 480V Swgr Room RB-19' EL., NE RB-19' EL., NE RB-I 9' EL., NE RB-19' EL., NE RB-19' EL., NE RB-23' EL., N

(:

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 309.2 305 310 310 310 310 31 0 310 31 0 310 310 310 REPAIR DOCUMENT REFERENCE NA NA NA NA 2400-APR-3214.01 2400-APR-3214.01 NA NA NA NA NA NA

P 0

G.'

FIRE ZONE R.B. 23' ELEV.

(cont'd)

(RB-FZ-1 E)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CONTAINMENT SPRAY SYS.

(Cont'd)

Sys II DW Spray Is01 Vlv (v-21-5)

Sys II TORUS CLG Discharge Vlv Sys I, Sys II Flow Ind (v-21-13)

(FT-IPO3 A, B)

EMERG SERV WTR. SYS.

ESW Disch Vlv., Sys I ESW Disch Vlv., Sys II (V-3-88)

(v-3-87)

ELECTRICAL DISTRIBUTION MCC 1A21A MCC 1A21B MCC 1B21A MCC 1 B21 B MCC 1AB2 MCC DC-1 RECIRC SYSTEM Recirc Pump Disch Vlv NGO3E (V-37-54) Power And Control Ckt REACTOR CLEANUP SYSTEM Inlet Is01 Vlv (V-16-1)

ALTERNATE CONTROUINDICATION Local Manual Local Manual None Local Manual Local Manual None None None None None None LSP-1AB2 RWCU Aux Relay Pnl.

(ER-215-087)

LOCATION OF ALTERNATE C ONTROLA N D I CAT1 0 N RB-23' EL., SE RB-23' EL., South NA RB 23' EL., North RB 23' EL., South NA NA NA NA NA NA RB 23' EL., NE AIB Battery Room c

Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE(S) 31 0 31 0 310 31 0 310 338 338 338 338 339 340.1 301,305,346 303 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA NA

P P

0 R.B. 23' ELEV.

(RB-FZ-1E)

(cont'd)

Attachment ABN-29-1 Equipment Availability Matrix for Fires MSIV's Inner MSlV (North)

(N S03A)

Inner MSlV (South)

(NSO3B)

Procedure ABN-29 Rev. 9 Outer MSlV (North)

(NS04A)

Outer MSlV (South)

(NS04B)

C.R. Pnl 1 I F C.R. Pnl 1 I F 301 30 1 Manual Action Required:

(1)

CRD Bypass Valves V-15-30 and V-15-237 can be manually opened and V-15-52 closed after the Fire is extinguished if RPV Makeup is required using the CRD pumps. Note that Fl-225-998 can be used for flow indication.

Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

(2)

(3) 1E V-20-41 has to be manually opened, THEN It will be necessary to de-energize MCC 1AB2 by opening VMCC 1 B2, Unit CO1 and VMCC 1A2, Unit BO2 to prevent future spurious operations of the valve.

V-204, V-21-1 (or V-21-3) and V-21-13 have to be manually opened and V-21-5 has to be manually closed, It will be necessary to de-energize MCC 1 B21A & 1 B21 B by opening supply breakers BO1 and DO1 at MCC 1 B21 to prevent future spurious operations of the valves.

(4)

!E THEN

FIRE ZONE R.B. -1 9 ELEV.

NORTHWEST (RB-FZ-1 F3)

P 0

cn Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 EQUIPMENT POTENTIALLY AFFECTED CRD HYDRAULIC SYSTEM A CRD Pump (NCOSB)

B CRD Pump (NC08B)

RBCCW SYSTEM Disch Hdr Press (PT-IA18)

CORE SPRAY SYSTEM I A Core Spray Pump (NZOIA)

C Core Spray Pump (NZOIC)

A Pump Suction Vlv.

C Pump Suction Vlv.

Main Pump Disch. Press.

Ind. (PI-RV04A)

Rx LEVEUPRESS INSTR.

Fuel Zone Lvl C D Fuel Zone Press C D (V-20-3)

(V-20-32)

(Ll-622-1001, 1002)

CONTAINMENT INST.

Torus Level Indication (LT-IP-09 A, B)

ALTERNATE CONTROUINDICATION None None Local Gages PI-50, 51 None None Local Manual Local Manual Local Gages (PIT-RV03A, P I-29A,C)

Fuel Zone Lvl A, Fuel Zone Press A, B (LI-IA94 A, 8)

Wide Range Torus Level (LT-37, 38)

LOCATION OF ALTERNATE CONTROUINDICATION NA NA RB 51 EL East on Pump Disch Pipes NA NA RB -19 EL NW RB -19 EL NW RB -19 EL NW CR Pnl5F/6F CR Pnl5F/6F CR Pnl16R APPLICABLE ROCEDURE(S) 302.1 302.1 309.2 308 308 308 308 308 41 0 41 0 412.1 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA

P 0

P, FIRE ZONE R.B. -19 ELEV.

SOUTHWEST (RB-FZ-1 F2)

R.B. -19 ELEV.

TORUS ROOM (RB-FZ-1 F5)

R.B. -1 9 ELEV.

NORTHEAST (RB-FZ-1 F4)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM I1 6

Core Spray Pump (NZOI B)

D Core Spray Pump (NZO 1 D)

A Pump Suction Vlv.

B Pump Suction Vlv.

01-20-4)

C Pump Suction Vlv.

D Pump Suction Vlv.

Main Pump Disch. Press.

Ind. (PI-RV04B) o/-20-3)

(V-20-32)

(V-20-33)

CORE SPRAY SYSTEM I1 B Core Spray Pump (NZOI 8)

D Core Spray Pump (NZO 1 D)

CONTAINMENT INSTR.

Torus Temp Indications (Tl-664-43 A & B)

CONTAINMENT SPRAY SYS I Cont Spray Pump 1-1 (51A)

Cont Spray Pump 1-2 (51 B)

ALTERNATE CONTROUlNDlCATlON None None Local Manual Local Manual Local Manual Local Manual Local Manual (PIT-RV03B,P 1-298, D)

None None None None None LOCATION OF ALTERNATE CONTROUlNDlCATlON NA NA R.B. -19 EL., NW R.B. -19 EL., SW R.B. -19 EL., NW R.B. -19 EL., SW R.B. -19 EL., SW NA NA NA NA NA Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE (S) 308 308 308 308 308 308 308 308 308 NA 31 0 31 0 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA

FIRE ZONE R.B. -19' ELEV.

NORTHEAST (cont'd)

(RB-FZ-1 F4)

R.B. -19' ELEV.

SOUTHEAST (RB-FZ-1 FI)

References:

GU 3E-911-41-040 GU 3E-911-41-042 Manual Action Required:

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CONTAINMENT SPRAY SYS I 51A Pump Suct Vlv.

(v-21-9) 51 B Pump Suct Vlv.

(v-21-7)

CONTAINMENT SPRAY SYS II Cont Spray Pump 1-3 (51 C)

Cont Spray Pump 1-4 (51 D) 51 C Pump Suct Vlv (v-2 1-1 )

51 D Pump Suct Vlv (v-2 I

-3)

Local Manual RB -19' EL, NE Local Manual RB -19 EL, NE None None Local Manual Local Manual NA NA R.B. -19' El., SE R.B. -19' El., SE (Hot Shutdown Path #I for RB-FZ-1 F)

(Cold Shutdown Path # I for RB-FZ-1 F)

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 31 0 310 31 0 310 31 0 310 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA (I)

For a Fire in RB-FZ-lF3, RPV makeup can be provided from the Condensate Storage Tank (if required) by manually opening Core Spray Supply Valve V-20-1 and Core Spray Condensate Transfer Valve V-20-2 and manually closing Core Spray Torus Suction Valve V-20-4 so that Core Spray System II train B pump suction is aligned to the condensate storage tank. If Core Spray suction valve V-204 cannot be positioned using remote control switch on Panel 1 F/2F, turn off breaker at MCC 1 B21A and position valve manually.

For a fire in RB-FZ-1 FI, -1 F2, -1 F4 or -1 F5, RPV makeup can be provided (if required using the CRD pumps by manually opening CRD bypass valves V-I 5-30 (throttle) and V-15-237 while closing V-15-52 (if necessary).

(2)

(3)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

P 0

p3 ALTERNATE CONTROUINDICATION

(:

Attachment ABN-29-1 Equipment Availability Matrix for Fires LOCATION OF ALTERNATE CONTROUINDICATION FIRE ZONE R.B. SDC ROOM (RB-FZ-1G)

~

References:

GU 3E-911-41-040 GU 3E-911-41-043 EQUIPMENT POTENTIALLY AFFECTED SHUTDOWN COOLING SYSTEM A SDC Pump B SDC Pump C SDC Pump A Loop Suct Vlv B Loop Suct Vlv c Loop Suct Vlv (V-17-3)

A Loop Disch Vlv (V-I 7-55)

B Loop Disch Vlv C Loop Disch Vlv (V-I 7-57)

Loop Disch Press Ind High Suct Temp. Pump Trip Temp Switches (TS-42 A, B, C)

Low Suct Press Pump Trip Press Switches (PS43 A, B, C)

(V-I 7-1)

(V-I 7-2)

(V-I 7-56)

(PI-RVO9 A, B, C)

LSP-1A2 RSP None Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual Local Gages (PIT-RVO6 A, B, C)

None None (Hot Shutdown Path # I for RB-FZ-1G)

(Cold Shutdown Path #3 for RB-FZ-1 G)

A 480V Swgr. Rm.

B 480V Swgr. Rm.

NA SDC Room SDC Room SDC Room SDC Room SDC Room SDC Room SDC Room SDC Room SDC Room Procedure ABN-29 Rev. 9 APPLICABLE ROC ED U R E( S) 305,346 305,346 305 305 305 305 305 305 305 305 305 305 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA NOTE: This Cold Shutdown Path utilizes Alternate Decay Heat Removal per procedure 2000-OPS-3024.27, Section 4.4 to approach the Cold Shutdown condition (Core Spray, Containment Spray in Torus Cooling, and EMRVs). It may be necessary to perform repairs on affected equipment as identified in the matrix.

Manual Action Required:

(1) !E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the holwell. Approximately 17.4 tl in the CST may be required for isolation condenser shell side makeup. Makeup to the CST as necessary from Demineralized Water (procedure 320.1),

High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

P 0

9 Attach men t AB N 1

Equipment Availability Matrix for Fires Procedure AB N -29 Rev. 9 REPAIR DOCUMENT REFERENCE EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE TRUNNION ROOM MSlVs (RB-FZ-1 H)

Outer MSlV (North)

(NS04A)

Outer MSIV (South)

(NS04B)

Inner MSlV (North)

(NS03A)

Inner MSlV (South)

(NSOSB)

C.R. Pnl11 F C.R. Pnl11 F 30 1 30 1

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path # I for RB-FZ-1 H)

(Cold Shutdown Path # I for RB-FZ-1H)

Manual Action Required:

(1) 1E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

m 0

P Equi Attachment ABN-29-1 ment Availability Matrix for Fires Procedure ABN-29 Rev. 9 4160 SWGR RM I C (TB-FA-3A)

References:

GU 3E-911-41-040 Hot Shutdown Path # I - B Isolation Condenser. B CRD PumD. Condensate Transfer Pumo. Fuel Zone Level Ind. Ll-622-1001 & 1002, I

Rx. Pressure Ind. P1-622-999 & 1000, Offsite Pwr available GU 3E-911-41-042 Cold Shutdown Path # I - B & C SDC Pumps, B CRD, RBCCW, Service Water Pumps, Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx.

Pressure Ind. PI-622-999 & 1000 and Reactor Wide range level indicator LI-IA13 Prompt Manual Actions:

NOTE:

1)

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

Confirm scram was completed in control room, if a scram was deemed necessary.

2)

NOTE:

IF CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST (check local indicator if necessary) may be required for isolation condenser shell and reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

If COz was discharged, TB-FA-36 (4160V Swgr ID) is also affected due to a common discharge header. Therefore, Self Contained Breathing Apparatus (SCBA) will be required for actions at the 4160V Swgr. 1 D.

3)

CAUTION:

Prior to Reactor Pressure decreasing to 310 psig, perform the following to prevent the core spray pumps from injecting, provided these pumps are not required to assure adequate core cooling:

a) From the control Room, trip 4160V 1A Switchgear incoming breakers 1A and SIA to de-energize the I C 4160V Switchgear to stop Core Spray b) At the diesel building, trip EDG-1 output breaker and place EDG-1 mode switch in stop to stop Core Spray Pumps NZOIA and NZOI D.

c) Open the breakers on 4160V Swgr. I D for Core Spray Pumps NZOIB and NZOIC, and place 69-permissive switches in trip Pumps NZOIA and NZOI 0.

f FIRE ZONE 4160 SWGR RM I C (contd)

(TB-FA-3A)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELEC. SWGR 41 60V Bus 1 C 125V DC Control Power to 41 60V Bus 1 C from 125V DC Bus C

I EDG Control Circuits DG-1 Breaker Control Circuits CORE SPRAY SYSTEM B Core Spray Pump Control Ckt (NZOI B)

C Core Spray Pump Control Ckt (NZOIC)

EMER. SERV W R SYS C ESW Pump Control Ckt (52C)

D ESW Pump Control Ckt (52D)

RBCCWISERV. WTR SYSTEM RBCCW Disch. Hdr. Press Ind. (PT-IA18)

Sew. Wtr. Disch Hdr.

Press. (PT-6)

2 RBCCW Pump Control Ckt.

SHUTDOWN COOLING SYS.

V-17-19 & V-17-54 ALTERNATE CONTROUINDICATION None None None None Local Breaker Oper.

(see man act below)

Local Breaker Oper.

(see man act below)

None None Local Gages Local Gages (PI-50, 51)

(PI-50, 30)

Local bkr operation (USS 182)

Panel 3F Test Plugs LOCATION OF ALTERNATE CONTROUINDICATION NA NA NA NA 4160V Swgr. 1 D 41 60V Swgr. 1 D NA NA RB 51 EL, East on Pump Disch. Pipes Intake Structure B 480V Room Control Room Panel 3F Procedure ABN-29 Rev. 9 APPLICABLE ROCEDURE(S) 337 340.3 NA NA 308 308 31 0 31 0 309.2 322 309.2 305 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 REPAIR EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT REFERENCE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE 4160 SWGR RM I C (TB-FA-3A) (cont'd)

Additional Manual Actions Required:

(1)

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 Close V-I 5-52 Throttle V-I 5-30 for desired flow on Fl-225-2 (2)

Cable failures may cause VACP-1 to trip.

IF CST level indication (5F-27), RBCCW Pressure Indication (1 3R-63) andlor Service Water Pressure Indication (5F-60) are lost in the control room.

THEN Read all indicators locally AND (when time permits)

Open all load breakers on VACP-1 and re-close VMCC 182 breaker compartment C2R and then re-close VACP-1 breaker 21 for the required indicators. Note that the breakers 16, 23,25 & 26 on VACP-1 are not needed and should remain open to isolate the cable failures.

(3)

Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

(4)

!E the C battery charger is not available THEN V-14-35 can be cycled for short-term operation (approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) but V-14-37 will have to be utilized for long-term operation of the Isolation Condenser with V-14-35 left open or manually cycle V-14-35.

(5)

RBCCW Pump 1-2 cable failure may cause a spurious pump trip.

IF THEN Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF -

THEN RBCCW Pump 1-2 spuriously trips Remove trip fuses from breaker at USS 162 and re-close breaker.

(6)

V-I 7-19 & V-I 7-54 cannot be opened from Control Room Panel 11 F Operate test plugs in Panel 3F per procedure 305, section 9.0.

Attachment ABN-29-1 Equipment Availability Matrix for Fire EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR DOCUMENT REFERENCE 4160 SWGR RM I D (TB-FA-3B)

References:

GU 3E-911-41-040 Hot Shutdown Path #2 - A Isolation Condenser. A CRD PumD. Diesel Fire Pump (IC makeuo). Fuel Zone Level Ind. LI-IA94A. Rx.

I Pressure Ind. PI-622-849, Offsite Pwr available GU 3E-911-41-042 Cold Shutdown Path #2 -A & (B or C) SDC Pumps, A CRD, RBCCW and Service Water Pumps, Fuel Zone Level Ind. LI-IA94A, Rx.

Pressure Ind. P1-622-849 and Reactor Wide Range Level Indicator LI-IA13 Prompt Manual Actions:.

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual symptoms.

1)

Confirm scram was completed in control room, if a scram was deemed necessary.

2)

CAUTION:

If COz was discharged, TB-FA-3A (4160V Swgr IC) is also affected due to a common discharge header. Therefore, Self Contained Breathing Apparatus (SCBA) will be required for any actions at the 4160V Swgr. IC.

Prior to Reactor Pressure decreasing to 310 psig, perform the following to prevent the core spray pumps from injecting, provided these pumps are not required to assure adequate core cooling:

a) From the control Room, trip 4160V 1 B Switchgear incoming breakers 1 B and SIB to de-energize the 1 D 4160V Switchgear to stop Core Spray b) At the diesel building, trip EDG-2 output breaker and place EDG-2 mode switch in stop to stop Core Spray Pumps NZOI B and NZOIC.

Pumps NZOl B and NZOl C.

3) Makeup to the Isolation Condensers may have to be provided by a Fire Diesel pump; valve lineup should be performed in accordance with Procedure 307 (close V-I 1-41 & 63 and open V-9-2099 & V-I 1-49).

4)

NOTE:

IF -

THEN CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 73 minutes) to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST (check local indicator if necessary) may be required for reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

r FIRE ZONE 4160V SWGR RM 1 D (cont'd)

(TB-FA-3 B)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELEC SWGR

2 EDG Control Ckts.

4160V Bus 1 D Feeder Breaker to USS 182 (1 B2P)

Feeder Breaker to USS 1 B3 (1 B3P)

SHUTDOWN CLG SYS.

Loop Inlet lsol Vlvs.

Loop Outlet Isol. Vlvs.

(V-I 7-1,2,3) 01-1 7-55, 56,57)

RBCCWKERV. WTR. SYS SDC Hx Outlet Flow Control Vlv (V-5-106)

RBCCW Disch. Hdr. Press Indic. (PT-1A18)

Sew. Wtr. Disch. Hdr.

Press Indic. (PT-6)

ALTERNATE CONTROUINDICATION LSP-DG2 None LSP-1 D LSP-1 D Local Manual Local Manual Local Manual Local Gages Local Gage (Pl-50,51)

(P 1-30)

LOCATION OF ALTERNATE CONTROUINDICATION

2 EDG Vault NA 4160 Swgr Rm I D 4160 Swgr Rm 1 D SDC Room SDC Room SDC Room RB 51' El, East on Pump Dish Pipes Intake Structure Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 341,346 337 346 346 305 305 305,309.2 309.2 322 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 REPAIR ALTERNATE DOCUMENT REFERENCE LOCATION OF ALTERNATE APPLICABLE EQUIPMENT POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE 4160V. SWGR RM I D (TB-FA-3B) (contd)

Additional Manual Actions Required:

(1)

!E B battery charger is not available, THEN V-14-34 can be cycled for short-term operation (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) and then V-14-36 will have to be utilized for long-term operation of the Isolation Condenser with V-14-34 left open or manually cycle V-14-34.

(2)

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 Close V-I 5-52 Throttle V-I 5-30 for desired flow on Fl-225-2 (3)

Cable failures may cause VACP-1 to trip.

IF THEN Read all indicators locally CST level indication (5F-27), RBCCW Pressure Indication (13R-63) andlor Service Water Pressure Indication (5F-60) are lost in the control room.

AND (when time permits)

Open all load breakers on VACP-1 and re-close VMCC 1 B2 breaker compartment C2R and then re-close VACP-1 breaker 21 for the required indicators. Note that the breakers 16, 23, 25 & 26 on VACP-1 are not needed and should remain open to isolate the cable failures.

(4).

Recharge V-I 1-36 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

(5)

Temporary Control Room ventilation may need to be installed per Procedure 331.1 if B CRHVAC is not available. A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened.

(6)

!E V-5-106 has to be manually opened, THEN Open its supply breaker on MCC 1 B21A and then manually operate V-5-106.

(7)

!E USS 1 B2 is not energized, THEN Open USS 1B2M breaker and remove close fuses. Crosstie USS 1A2 & 182 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this crosstie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1 B21 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1821 breakers and start EF-1-21 & SF-1-21 or provide temporary ventilation IAW Procedure 331.

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUl PMENT ALTERNATE 1

LOCATION OF ALTERNATE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION FIRE ZONE TURB. OPER. FLOOR I (TB-FZ-1 IA)

NONE NIA NIA Procedure ABN-29 Rev. 9 APPLICABLE

'ROC ED U RE( S)

NIA REPAIR DOCUMENT REFERENCE NIA

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path # I for TB-FZ-1 IA)

(Cold Shutdown Path # I for TB-FZ-1 IA)

Manual Action Reauired:

(1)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 fl in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

Attachment ABN-29-1 Eq u i p m e n t Ava i I a b i I i ty Matrix for F i res Procedure ABN-29 Rev. 9 TURBINE BLDG LUBE OIL BAY (TB-FZ-11 B)

References:

GU 3E-911-41-040 Hot Shutdown Path # I GU 3E-911-41-042 Cold Shutdown Path #

- A Isolation Condenser, B CRD Pump, Condensate Transfer Pump, Fuel Zone Level Ind. Ll-IA94B, Rx.

Pressure Ind. Pl-622-850, EDG-2 B & C SDC Pumps, B CRD, RBCCW and Service Water Pumps Fuel Zone Level Ind. LI-IA94B, Rx. Wide Range Level Indicator LI-IA13, Rx. Pressure Ind. PI-622-850.

Prompt Manual Actions:

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

I) Confirm scram was completed in control room, if a scram was deemed necessary.

2)

From the control room, trip the feedwater pumps by taking their control switches to PTL (may not trip) andlor control flow utilizing the Feedwater Regulating Valves V-2-732, 733, 734, 735, and 736 provided that these pumps are not required.

3)

NOTE:

IF THEN The Reactor Recirculation control circuits are located in this fire zone and they have to be tripped to utilize the Fuel Zone Level Indicators.

The Reactor Recirculation Pumps wont trip from the control room, trip the pumps from their respective switchgear (4160V Busses 1A & 1 B) and place their 69 permissive switches in the trip position.

4)

NOTE:

IF CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE LOCATION OF ALTERNATE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR APPLICABLE DOCUMENT PROCEDURE(S)

REFERENCE TURBINE BLDG LUBE OIL BAY (Cont'd)

(TB-FZ-11 B)

Promot Manual Actions (cont'd):

5)

Prior to Reactor pressure decreasing to 310 psig, open the following breakers at their respective switchgear (place 69-permissive switches in 'trip' position on 4160V breakers, remove 'close' fuses on top right of associated 480V breaker cubicle), provided these pumps are not required to assure adequate core cooling:

a.

Core Spray Booster Pumps NZ03A & NZ03D at 480V USS 1A2 (fuse puller at RSP padlock).

b. Core Spray Booster Pumps NZ03B & NZ03C at 480V USS 182 (fuse puller at RSP padlock).

c.

Core Spray Pumps NZOIA & NZOID at 4160V Swgr. IC.

d.

Core Spray Pumps NZOl B & NZOl C at 4160V Swgr. 1 D.

power is lost to 4160V 1 D Bus, USS 183 andlor MCC 1 B32 and control from the control room is not available, THEN Control them at their respective Local Shutdown Panel IAW Procedure 346

6)

a.

LSP-DG2

c.

b.

LSP-ID LSP-183 and confirm the feeder breaker to MCC 1 B32 is closed

d.

LSP-1832

7) NOTE: If offsite power is lost at a latter time, then LSP-DG2 will have to be fully initiated using Procedure 346.

IF I D 4160V Bus is being supplied by Offsite power, THEN TRANSFER only the #I Normal-Alternate switch to "Alternate" (partial initiation) on LSP-DG2 to isolate control room wiring and prevent spurious starting Of EDG-2 and IF EDG-2 is already running, THEN STOP EDG-2 by momentarily taking the mode switch to stop.

8)

When #2 EDG is supplying power to 4160V swgr. ID, ensure that the feeder breaker on 4160V 1 D unit D1 (from 4160V Bus 18) is open and locked out (69-permissive switch in the 'trip' position) to prevent inadvertent paralleling of offsite power with the EDG due to a spurious actuation.

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 TURBINE BLDG LUBE OIL BAY (Cont'd)

(TB-FZ-I 1 B)

Promot Manual Actions (cont'd):

9)

NOTE:

IF THEN A hot short on the 1 D ammeter cable that runs to the control room can cause the 86/1D lockout relay to actuate which will either trip the EDG-2 breaker (if already closed) or will prevent the breaker from closing.

EDG-2 breaker trips or will not close (trips free) and 86/1 D is picked up, Remove 86/1 D fuse pair labeled FU-80 (UB) in switchgear 1 D unit D1 and then reset the 86/1 D lockout. Now that the trip signal on the EDG-2 breaker has been removed, the breaker can be closed.

IO) E Control of USS 1B2M and B CRD pump is required from the RSP (partial initiation of RSP).

Control USS 1 B2M and B CRD pump from the RSP IAW the instructions below.

THEN

1. Confirm feeder breaker 1 B2P to USS 1 B2 is closed.

2.

Obtain key from the Padlock at the RSP.

3.

Rotate keylock CRD and Breaker 1 B2M Control Transfer Switch to Alternate.

4. Confirm closed USS main Breaker, 1B2M at RSP

5. Operate B CRD pump at RSP as required.

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE TURBINE BLDG.

LUBE OIL BAY (TB-FZ-11 B)

EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM

" A Core Spray Pump Control Ckt. (NZOIA)

"C" Core Spray Pump Control Ckt. (NZOI C)

"D" Core Spray Pump Control Ckt. (NZOID)

CONDENSATE TRANSFER SYS Cond. Trans. Pump 1-1 Cond. Trans. Pump 1-2 Cond. Storage Tank Level (LT-35)

EMER. SERV. WATER SYS "A" ESW Pump Control Ckt. (52A)

"B" ESW Pump Control Ckt. (528)

RBCCW SYSTEM RBCCW Disch. Header Press Indic. (PT-IA18)

2 RBCCW Pump Control CM.

SHUTDOWN COOLING SYS.

V-77-19 & V-17-54 CONTROL ROD DRIVE

' B CRD Pump ALTERNATE CONTROUINDICATION Local Breaker Oper.

Local Breaker Oper.

None LSP-1832 Local Gage (Ll-424-993)

Local Manual Local Manual Local Gages (Pl-50,51)

Local bkr operation (USS 182)

Panel 3F Test Plugs RSP LOCATION OF ALTERNATE CONTROUINDICATION 4160V Bus 1 C 4160V Bus 1 D 4160V Bus I C NA Chlor. Bldg.

Cond. Stg. Tank 4160V Swgr. I C 41 60V Swgr. 1 C RB 51' El. East on Pump Disch. Piping

'6' 480V Room Control Room Panel 3F

'B' 480V Room Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 308 308 308 316.1 316.1, 346 316.1 31 0 31 0 309.2 309.2 305 302.1, 346 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA

FIRE ZONE TURBINE BLDG.

LUBE OIL BAY (co nt'd)

(TB-FZ-11 B)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELECTRICAL DIST. SYS.

EDG 1 Control Ckts.

Brkr. I C Control Ckt.

Brkr. EC Control Ckt.

EDG-2 Control Ckts.

Brkr. 1 D Control Ckt.

Brkr. ED Control Ckt.

Brkr 1Al P Control Ckt.

Brkr 1A2P Control Ckt.

Brkr 1A3P Control Ckt.

Brkr 1A3M Control Ckt.

Brkr I A I M Control Ckt.

Brkr.

Powc B2P Control CM.

B3P Control Ckt.

B1 P Control Ckt.

B1 M Control Ckt.

B2M Control Ckt.

B3M Control CM.

Feeder and 125 vdc Cntrl Pwr to USS 1A2 480V Feeder to C1 & C2 Battery Chargers 125 vdc Pwr Feeder to DC-2 125 vdc Power Feeder to DC-F 125 vdc Cntrl Pwr to Swgr 1 B Power Feeder to MCC 1812 VACP-1 SERVICE WATER SYSTEM Service Water Pump 1-1 Control Ckt.

Service Water Pump 1-2 Control Ckt.

Service Water Header Press Indication IPT-6)

ALTERNATE CONTROUINDICATION None Local Local Local Local Local Local Local Local Local LSP-DG2 LSP-1 D LSP-1 D Local Local RSP None LSP-1 B3 None None None None None Switch Cntrl pwr to DC-A None LSP-183 Local Gage (PI-30)

LOCATION OF ALTERNATE CONTROUINDICATION NA I C Swgr.

I C Swgr.

2 EDG Vault I D Swgr.

I D Swgr.

I C Swgr.

USS 1A3 USS 1Al "D" 41 60V Swgr. Room "D" 4160V Swgr. Room I D Swgr USS 1B1

'B 480V Room Intake Structure NA NA NA NA "B' 4160 Swgr Room NA NA Intake Structure Intake Structure Intake Structure

('

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 341 337 337 341,346 337 337 337 337 337 338 338 337,346 337,346 337 338 346 338,346 338,340.3 340.3 340.3 340.3 340.1 339 338 322 322,346 322 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 340.1 NA NA NA NA NA

(:;'

Attachment AB N-29-1 Equipment Availability Matrix for Fires FIRE ZONE TURBINE BLDG.

LUBE OIL BAY (cont'd)

(TB-FZ-1 I B)

Additional Manual Actions EQUIPMENT POTENTIALLY AFFECTED VENTILATION SYSTEM "A" 480V Swgr. Room HVAC Supply and Exhaust Fans Control "A" 480V Swgr. Room HVAC Dampers Control FUEL ZONE LEVEL "A". "B" Fuel Zone Level and "C", 'ID' Fuel Zone Level (Control Room Only) tequired:

ALTERNATE CONTROUINDICATION None None "C", "D" Fuel Zone Level at RSP LOCATION OF ALTERNATE CONTROUINDICATION NA NA

" B 480V Swgr. Room Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE(S) 328 328 346 REPAIR DOCUMENT REFERENCE NA NA NA 1

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

8 Open V-15-237 rn 8

Close V-15-52 Throttle V-I 5-30 for desired flow on Fl-225-2 2

Trip the feedwater pumps from their respective switchgear, and place their 69-permissive switches in the 'trip' position when time permits to ensure feedwater isolation.

3.

4.

Recharge V-I 1-36 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

If power is lost to "C" Battery Room HVAC fans from MCC 1A2, then ensure that the battery room door is opened within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months to prevent a buildup of hydrogen.

RBCCW Pump 1-2 cable failure may cause a spurious pump trip.

If RBCCW Pump 1-2 spuriously trips, then Remove trip fuses from breaker at USS 182 and re-close breaker.

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF THEN

5.

6.

V-17-19 & V-I 7-54 cannot be opened from Control Room Panel 1 1 F Operate test plugs in Panel 3F per procedure 305, section 9.0.

!I Attachment ABN-29-1 Equipment Availability Matrix for Fires m

W 0

Procedure ABN-29 Rev. 9 f IRE ZONE TURB. BLDG.4160 SWGR RM A AND B SWGR RM (TB-FZ-11 C)

References:

GU 3E-911-41-040 Hot Shutdown Path #I

- A Isolation Condenser, 8 CRD Pump, Condensate Transfer Pump, Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx. Pressure Ind. Pl-622-999 & 1000, EDG-2 GU 3E-91141-042 Cold Shutdown Path # I - B & C SDC Pumps, B CRD, RBCCW and Service Water Pumps Fuel Zone Level Ind. L1-622-1001 & 1002, Rx. Wide Range Level Indicator LI-IA13, Rx. Pressure Ind. Pl-622-999 & 1000.

Prompt Manual Actions:

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

1)

Confirm scram was completed in control room, if a scram was deemed necessary.

2)

From the control room, trip the feedwater pumps by taking their control switches to PTL (may not trip) and/or control flow utilizing the Feedwater Regulating Valves V-2-732, 733, 734, 735, and 736 provided that these pumps are not required.

3)

NOTE:

IF -

THEN The Reactor Recirculation pumps trip circuits are located in this fire zone and they have to be tripped to utilize the Fuel Zone The Reactor Recirculation Pumps wont trip from the control room, trip them manually by opening the field breakers for the MG sets at Pnl RY21 in the MG Set Room

.eve1 Indicators.

4)

NOTE:

IF THEN CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 fl in the CST (check local indicator if necessary) may be required for isolation condenser shell and reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

CAUTION: SCBA may be required to get to the I D 4160V switchgear due to smoke. The closest SCBA is located in the Pretreatment Building (east side).

When #2 EDG is supplying power to 4160V swgr. 1 D, ensure that the feeder breaker on 4160V 1 D unit D1 (from 4160V Bus 1 B) is open and locked out (69-permissive switch in the trip position) to prevent inadvertent paralleling of offsite power with the EDG due to a spurious actuation.

5)

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 TURB. BLDG.4160 SWGR RM A AND B SWGR RM (TB-FZ-1 IC)

Prompt Manual Actions (contd):

6) NOTE:

A hot short on the 1 D ammeter cable that runs to the control room can cause the 86/1 D lockout relay to actuate which will either trip the EDG-2 breaker (if already closed) or will prevent the breaker from closing.

CAUTION:

IF:

THEN:

SCBA may be required to get to the 1 D 4160V switchgear due to smoke. The closest SCBA is located in the Pretreatment Building (east side).

EDG-2 breaker trips or will not close (trips free) and 8611 D is picked up, Remove 86/10 fuse pair labeled FU-80 (UB) in switchgear I D unit D1 and then reset the 86/10 lockout. Now that the trip signal on the EDG-2 breaker has been removed, the breaker can be closed.

7)

Prior to Reactor pressure decreasing to 310 psig, open the following breakers at their respective switchgear (place their 69-permissive switches in trip position on 4160V breakers, remove close fuses on top right of associated 480V breaker cubicle), provided these pumps are not required to assure adequate core cooling:

a.

b.

c.

Core Spray Pumps NZOI B & NZOl C at 41 60V Swgr. 1 D.

Core Spray Pumps NZOIA & NZOID at 4160V Swgr. IC.

Core Spray Booster Pumps NZ03A & NZ03D at 480V USS 1A2 (fuse puller located at RSP padlock).

USS 1 B3 is deenergized and cannot be controlled from the control room.

Use Local Shutdown Panel LSP-1 B3 IAW Procedure 346 to control USS 183 and confirm MCC 1832 feeder breaker is closed after power is restored.

8)

!E -

THEN

9)

!E Control of USS 1 B2M and B CRD pump is required from the RSP (partial initiation of RSP).

Control USS 1 B2M and B CRD pump from the RSP IAW the instructions below.

1.

2.

3.

4.

5.

THEN Confirm feeder breaker 1 B2P to USS 182 is closed.

Obtain key from the Padlock at the RSP.

Rotate keylock CRD and Breaker 1 B2M Control Transfer Switch to Alternate.

Confirm closed USS main Breaker, 1 B2M at RSP Operate B CRD pump at RSP as required.

FIRE ZONE TURBINE BLDG.

4160V SWGR. RM.

" A AND "B" SWGR. ROOM (TB-FZ-11 C)

EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM

" A Core Spray Pump Control Ckt. (NZOIA)

"6" Core Spray Pump Control Ckt. (NZOI B)

"C" Core Spray Pump Control Ckt. (NZOIC)

"D" Core Spray Pump Control Ckt. (NZOI D)

EMER SERV WATER SYS

" A ESW Pump Control Ckt (52A)

"B" ESW Pump Control Ckt (528)

"C" ESW Pump Control CM (52C)

"D" ESW Pump Control Ckt (52D)

Attachment ABN-29-1 Equipment Availability Matrix for Fires ALTERNATE CONTROUINDICATION Local Brkr Operation Local Brkr Operation Local Brkr Operation Local Brkr Operation None None None None LOCATION OF ALTERNATE CONTROUINDICATION 4160V Bus I C 4160V Bus 1 D 4160V Bus 1 D 4160V Bus I C NA NA NA NA Procedure ABN-29 Rev. 9 308 1

NA 308 308 1

NA 308 310 NA

S' FIRE ZONE TURBINE BLDG.

4160V SWGR. RM.

" A AND "B" SWGR. ROOM (cont'd)

(TB-FZ-11 C)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED SERVICE WATER SYSTEM Service Water Pump 1-1 Control Ckt.

Service Water Pump 1-2 Control Ckt.

Service Water Hdr Press Indication

( P T 4 ELECTRICAL DIST. SYS.

I EDG Power and Control Ckt.

2 EDG Power Circuit (3 Hr. Fire Barrier)

Power Feeder to Bus 1 C Brkr 1 C Control Ckt.

Brkr 1Al P Control Ckt.

Brkr 1A2P Control Ckt.

Brkr 1A3P Control Ckt.

Brkr 1A3M Control Ckt.

Power Feeder to Bus 1 D Brkr 1 B1 P Control Ckt.

Brkr 1 B2P Control Ckt.

Brkr 1 B3P Control Ckt.

Brkr 1B2M Control Ckt.

Brkr 1 B3M Control Ckt.

125V DC Dist Ctr. "C" Charger 125 vdc Power Feeder to DC-2 125 vdc Power Feeder to DC-F 125 vdc Cntrl Pwr to "1 C" Swgr 125 vdc Cntrl Pwr to USS 1A2 125 vdc Cntrl Pwr to USS 1A3 125 vdc Cntrl Pwr to "1A" Swgr 125 vdc Cntrl Pwr to "1 B" Swgr "CI" & "CY RBCCW SYSTEM RBCCW Disch. Hdr Press Indication (PI-IA1 B)

RBCCW Pump 1-2 ALTERNATE CONTROUINDICATION None LSP-183 Local Gage (PI-30)

None None EDG #I Local Local Local Local Local

2 EDG Local RSP None None None None None None None Switch Cntrl Pwr to DC " A LSP-1 D LSP-1 D LSP-183 Local Gages Breaker at USS 182 (Pl-50,51)

LOCATION OF ALTERNATE CONTROUI N D ICATION NIA Intake Structure Intake Structure NA NA Control Room I C Swgr.

I C Swgr.

USS 1A3 Control Room I D Swgr.

"D" 4160V Swgr. Room "D"4160V Swgr. Room

'6' 480V Room Intake Structure NA NA NA NA NA NA NA

" B 4160V Swgr Room RB 51' El. East on Pump Disch. Piping

'B 480V Swgr Room

(:'

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 322 322,346 322 341 341,346 337 337 337 337 337 338 341,346 337 337,346 337,346 346 338,346 340.3 340.3 340.3 340.3 340.3 340.3 340.3 340.1 309.2 309.2 REPAIR DOCUMENT REFERENCE NA NA NA NA NA (3 hr cable oarrier)

NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 340.1 NA NA

(I FIRE ZONE TURBINE BLDG.

4160V SWGR. RM.

" A AND "B" SWGR. ROOM (cont'd)

(TB-FZ-11 C)

Lldditional Manual Actions Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 EQUl PMENT POTENTIALLY AFFECTED FUEL ZONE LEVEL "A". "B" Fuel Zone Level Indications CONTROL ROD DRIVE

'B CRD Pump SHUTDOWN COOLING SYS.

Lequired:

V-I 7-1 9 & V-17-54 ALTERNATE CONTROUlNDlCATlON "C", "D" Fuel Zone Level Indications RSP Panel 3F Test Plugs CR Pnl5F16F or RSP ("B" 480V Swgr Rm)

'B' 480V Room Control Panel 3F 41 0 346 346 NA NA NA 305 N/A 1

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-15-237 Close V-15-52 Throttle V-I 5-30 for desired flow on Fl-225-2 2

Cable failures may cause VACP-1 to trip.

IF CST level indication (5F-27), RBCCW Pressure Indication (13R-63) and/or Service Water Pressure Indication (5F-60) are lost in the control room.

THEN Read all indicators locally AND (when time permits)

Open all load breakers on VACP-1 and re-close VMCC 182 breaker compartment C2R and then re-close VACP-1 breaker 21 for the required indicators. Note that the Service Water pressure indicator still may not be available due to potential cable failures on the instrument loop SO this indicator may still need to be read locally. In addition, breakers 16, 23, 25 & 26 on VACP-1 are not needed and should remain open to isolate the cable failures.

Trip the Feedwater pumps from their respective switchgear if they are not required, and place their 69-permissive switches in the 'trip' position when time permits to ensure feedwater isolation.

Recharge V-11-36 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

If power is lost to "C" Battery Room HVAC fans from MCC 1A2, then ensure that the battery room door is opened within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months to prevent a buildup of hydrogen.

3.

4.

5.

6 IF:

2 RBCCW Pump spuriously trips (USS 1 B2)

THEN: Remove the trip fuses for this pump at USS 182 and manually re-close the breaker.

Attachment ABN-29-1 Equipment Availability Matrix for Fires I

Procedure ABN-29 Rev. 9 TB-FZ-11 C Manual Action Required (cont'd):

Breaker for #2 Service Water Pump may have to be controlled from LSP-183 and if it spuriously trips open (USS 183)

Remove the trip fuses for this pump at USS 183 and manually re-close the breaker.

THEN:

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-I 7-1 9 and V-I 7-54 from the Main Control Room.

IF:

8.

V-17-19 & V-I 7-54 cannot be opened from Control Room Panel 1 1 F THEN:

Operate test plugs in Panel 3F per procedure 305, section 9.0.

(:

Procedure ABN-29 Rev. 9 Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR EQUIPMENT ALTERNATE I LOCATION OF ALTERNATE APPLICABLE DOCUMENT POTENTIALLY AFFECTED CONTROUINDICATION C 0 NTR 0 VI N D I CAT IO N PROCEDURE( S )

E E E

FIRE ZONE TURBINE BLDG. BASEMENT (TB-FZ-11 D)

References:

GU 3E-911-41-040 Hot Shutdown Path # I -A Isolation Condenser or B Isolation Condenser (if DC-C does not trip), 6 CRD Pump, Condensate Transfer Pump, Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx. Pressure Ind. Pl-622-999 & 1000, EDG-2 GU 3E-911-41-042 Prompt Manual Actions:

Cold Shutdown Path # I - B & C SDC Pumps, B CRD, RBCCW and Service Water Pumps Fuel Zone Level Ind. L1-622-1001 & 1002, Rx.

Wide Range Level Indicator LI-IA13, Rx. Pressure Ind. PI-622-999 & 1000.

NOTE:

1)

2)

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

Confirm scram was completed in control room, if a scram was deemed necessary.

From the control room, trip the feedwater pumps by taking their control switches to PTL (may not trip) andlor control flow utilizing the Feedwater Regulating Valves V-2-732, 733, 734, 735, and 736 provided that these pumps are not required.

3)

NOTE:

The Reactor Recirculation pump control and power cables are located in this fire zone and they have to be tripped to utilize the Fuel Zone Level Ind.

IF -

THEN NOTE:

The Reactor Recirculation Pumps wont trip from the control room, trip the pumps from their respective switchgear (4160V Busses I A & 1 B) and place their 69 permissive switches in the trip position.

CST may drain to the Hotwell on Loss of Instrument Air.

4)

IF THEN CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

(

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE TURBINE BLDG. BASEMENT (contd)

(TB-FZ-11 D)

Prompt Manual Actions (contd):

5)

CAUTION: SCBA may be required I the 1 D 41 60V switchge r due to smoke. The closest SCBA is local d in the Pretreatment Building (east side).

Prior to Reactor pressure decreasing to 31 0 psig, open the following breakers at their respective switchgear and place 69-permissive switches in trip position, provided these pumps are not required to assure adequate core cooling:

a.

b.

Core Spray Pumps NZOIA 8. NZOlD at 4160V Swgr. IC.

Core Spray Pumps NZOIB & NZOIC at 4160V Swgr. ID.

6) power is lost to 41 60V 1 D Bus andlor USS I E3 and control from the control room is not available, THEN Control them at their respective Local Shutdown Panel IAW Procedure 346

a.

LSP-DG2

c.

b.

LSP-ID LSP-183 and confirm the feeder breaker to MCC 1832 is closed

7) NOTE: If offsite power is lost at a latter time, then LSP-DG2 will have to be fully initiated using Procedure 346.

IF 1 D 4160V Bus is being supplied by Offsite power, THEN TRANSFER only the # I Normal-Alternate switch to Alternate (partial initiation) on LSP-DG2 to isolate control room wiring and prevent spurious starting of EDG-2 and IF EDG-2 is already running, THEN STOP EDG-2 by momentarily taking the mode switch to stop.

8)

When #2 EDG is supplying power to 4160V swgr. ID, ensure that the feeder breaker on 4160V 1 D unit D1 (from 4160V Bus 1 B) is open and locked out (69-permissive switch in the trip position) to prevent inadvertent paralleling of offsite power with the EDG due to a spurious actuation. Confirm breakers D2 (USS 1 BI), D4 (B Core Spray Pump), D6 (ESW Pump 52D), D8 (ESW Pump 52C) and D9 (C Core Spray Pump) are tripped and are locked out by placing their 69-permissive switches in the trip position.

2 0

c Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 TURBINE BLDG. BASEMENT (cont'd)

[TB-FZ-1 1 D)

Prompt Manual Actions (cont'd):

3)

NOTE:

A hot short on the 1 D ammeter cable that runs to the control room can cause the 86/1 D lockout relay to actuate which will either trip the EDG-2 breaker (if already closed) or will prevent the breaker from closing.

CAUTION: SCBA may be required to get to the I D 4160V switchgear room. The closest SCBA is located in the Pretreatment Building (east side).

IF: -

THEN:

EDG-2 breaker trips or will not close (trips free) and 8611 D is picked up, Remove 8611 D fuse pair labeled FU-80 (UB) in switchgear I D unit D1 and then reset the 86/1D lockout.. Confirm breakers D2 (USS IBl), D4 (B Core Spray Pump), D6 (ESW Pump 52D), D8 (ESW Pump 52C) and D9 (C Core Spray Pump) are tripped and are locked out by placing their 69-permissive switches in the 'trip' position prior to re-energizing the bus. Now that the trip signal on the EDG-2 breaker has been removed, the breaker can be closed.

Control of USS 1 B2M and B CRD pump is required from the RSP (partial initiation of RSP).

Control USS 1 B2M and B CRD pump from the RSP IAW the instructions below.

Confirm feeder breaker 1 B2P to USS 1 B2 is closed.

Obtain key from the Padlock at the RSP.

Rotate keylock CRD and Breaker 1 B2M Control Transfer Switch to Alternate.

Confirm closed USS main Breaker, 1 B2M at RSP Operate B CRD pump at RSP as required.

IO)

THEN 1,

2.

3.

4.

5.

Attach men t AB N 1 Equipment Availability Matrix for Fires FIRE ZONE TURBINE BLDG.

BASEMENT (cont'd)

(TB-FZ-11 D)

EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM "A" Core Spray Pump Power and Control Ckt "B" Core Spray Pump Power and Control CM "C" Core Spray Pump Power and Control Ckt "D" Core Spray Pump Power and Control Ckt (NZO 1 A)

(NZOI B)

(NZOI C)

(NZOI D)

EMERGENCY SERV VVTR SYS

" A ESW Pump Power Feed &

Control CM (52A)

"B" ESW Pump Power Feed &

Control Ckt (528)

"C" ESW Pump Power Feed &

Control Ckt (52C)

"D" ESW Pump Power Feed &

Control Ckt (52D)

SERVICE WATER SYSTEM Service Water Pump 1-1 Control Ckt ALTERNATE CONTROUINDICATION Local Brkr Operation Local Brkr Operation Local Brkr Operation Local Brkr Operation None None None None None LOCATION OF ALTERNATE CONTROUINDICATION 4160V Bus 1 C 41 60V Bus 1 D 4160V Bus 1 D 4160V Bus I C NA NA NA NA NA Procedure ABN-29 Rev. 9 APPLICABLE

)ROCEDURE(S) 308 308 308 308 31 0 31 0 31 0 310 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

4 0

0 I

FIRE ZONE TURBINE BLDG.

BASEMENT (cont'd)

(TB-FZ-11 D)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED Service Water Pump 1-2

>ontrol Ckt Service Water Hdr Press Indication (PT-6)

-eve1 Indications ELECTRICAL DlST SYSTEM ZDG 1 Pwr and Control Ckts.

EDG 2 Pwr and Control Ckts.

Brkr 1 C Control Ckts.

Brkr EC Control Ckts.

Brkr I D Control Ckts.

Brkr ED Control Ckts.

Power Feeder to Bus 1 C Power Feeder to USS 1A2 Power Feeder to USS 1A3 Brkr 1 B2P Control Ckt.

Brkr 1 B3P Control Ckt.

Brkr 1 B3M Control Ckt.

125VDC Con Pwr to USS USS 1Al USS 1B1 USS 1B2M 1A3 from DC " B RBCCW SYSTEM RBCCW Disch. Header Press Indication RBCCW Pump 1-2 (PT-IA1 8)

ALTERNATE CONTROUINDICATION LSP-1 B3 Local Gage (PI-30)

"C", "D" Fuel Zone Level Indications None LSP-DG2 None None None None None None None LSP-1 D LSP-1 D LSP-183 125VDC Control Power from DC "A" None None RSP Local Gages (PI-50, 51)

Local Bkr operation at USS 1 B2 LOCATION OF ALTERNATE CONTROUINDICATION Intake Structure Intake Structure CR Pnl5FI6F or RSP("B" 480V Swgr Rm)

NA

2 EDG Vault NA NA NA NA NA NA NA "D"416OV Swgr Room "D" 4160V Swgr Room Intake Structure 480V USS 1A3 NA NA

'B' 480 V Swgr Room RB 51' El, East on Pump Disch. Piping B' 480 V Swgr Room Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 322,346 322 410 346 341 341,346 337 337 337 337 337 337 337 337,346 337,346 338,346 340.1 338 338 346 309.2 309.2 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA (Pwr has 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months fire barrier)

NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA

(.

Procedure ABN-29 Rev. 9 4

0 P

FIRE ZONE TURBINE BLDG.

BASEMENT (cont' d)

(TB-FZ-1 ID)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CONTROL ROD DRIVE

'B' CRD Pumu SHUTDOWN COOLING SYS.

V-I 7-1 9 & V-I 7-54 ALTERNATE CONTROUINDICATION RSP Panel 3F Test Plugs REPAIR REFERENCE LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUINDICATION PROCEDURE(S)

'B' 480 V Swgr Room Control Room Panel 3F 346 305 NA NIA Additional Manual Actions Required TB-FZ-11 D

1) It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 0

Close V-15-52 Throttle V-15-30 for desired flow on Fl-225-2

2)

Cable failures may cause VACP-1 to trip.

IF CST level indication (5F-27), RBCCW Pressure Indication (13R-63) andlor Service Water Pressure Indication (5F-60) are lost in the control room.

I H

~

N reaa ail inoicators locally AND (when time permits)

Open all load breakers on VACP-1 and re-close VMCC 1 B2 breaker compartment C2R and then re-close VACP-1 breaker 21 for the required indicators. Note that the breakers 16, 23, 25 & 26 on VACP-1 are not needed and should remain open to isolate the cable failures.

4).

Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

3) E:

the C battery charger is not available THEN:

The Reactor Feedwater Pump and HP Heater outlet valve control circuits run through this area. Trip the Feedwater pumps at their respective switchgear, and place their 69-permissive switches in the 'trip' position to ensure feedwater isolation.

V-14-35 can be cycled for short term operation (approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) but V-14-37 will have to be utilized for long term operation of the Isolation Condenser with V-14-35 left open or manually cycle V-14-35.

4).

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE Additional Manual Actions Required TB-FZ-11 D (cont'd):

4) E:

2 RBCCW Pump spuriously trips (USS 182)

THEN:

Remove the trip fuses for this pump at USS 182 and manually re-close the breaker.

5). Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-I 7-54 from the Main Control Room.

IF:

V-I 7-1 9 & V-17-54 cannot be opened from Control Room Panel 11 F THEN: Operate test plugs in Panel 3F per procedure 305, section 9.0.

Attachment ABN-29-1 Eq u i p men t Ava i I a b i I i ty Matrix for F i res EQUIPMENT ALTERNATE LOCATION OF ALTERNATE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR APPLICABLE DOCUMENT PROCEDURE(S)

REFERENCE CONDENSER BAY (TB-FZ-11E)

References:

GU 3E-911-41-040 Hot Shutdown Path #I

- " A Isolation Condenser, "B" CRD Pump, Condensate Transfer Pump, Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx. Pressure Ind. P1-622-999 & 1000, EDG-2 GU 3E-911-41-042 Prompt Manual Actions:

NOTE:

1)

2)

Cold Shutdown Path #I - "B & C" SDC Pumps, "B" CRD, RBCCW and Service Water Pumps Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx. Wide Range Level Indicator LI-IA13, Rx. Pressure Ind. Pl-622-999 & 1000.

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

Confirm scram was completed in control room, if a scram was deemed necessaty.

From the control room, trip the feedwater pumps by taking their control switches to PTL (may not trip) and/or control flow utilizing the Feedwater Regulating Valves V-2-732, 733, 734, 735, and 736 and/or stop flow by closing V-2-10, V-2-11 and V-2-12 provided that these pumps are not required.

NOTE:

IF THEN

3)

The Reactor Recirculation pumps circuits are located in this fire zone and they have to be tripped to utilize the Fuel Zone Level Indicators.

The Reactor Recirculation Pumps won't trip from the control room, trip the pumps from their respective switchgear (4160V Busses 1A & 1 B) and place their 69 permissive switches in the 'trip' position.

4)

NOTE:

IF THEN CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

5)

Prior to Reactor pressure decreasing to 310 psig, open the following breakers at their respective switchgear (place their 69-permissive switches in 'trip' position on 4160V breakers, remove 'close' fuses on top right of associated 480V breaker cubicle), provided these pumps are not required to assure adequate core cooling:

a.

b.

c.

Core Spray Pumps NZOl B & NZOl C at 4160V Swgr. 1 D.

Core Spray Pumps NZOIA & NZOI D at 4160V Swgr. IC.

Core Spray Booster Pumps NZO3A & NZ03D at 480V USS 1A2 (fuse puller located at RSP padlock).

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 CONDENSER BAY (TB-FZ-11 E)

Prompt Manual Actions (Cont'dl:

6) E power is lost to 41 60V 1 D Bus, USS 1 B3 andlor MCC 1832 and control from the control room is not available, THEN Control them at their respective Local Shutdown Panel IAW Procedure 346

a.

LSP-DG2

c.

b.

LSP-ID LSP-183 and confirm the feeder breaker to MCC 1832 is closed

d.

LSP-1B32

7) NOTE: If offsite power is lost at a latter time, then LSP-DG2 will have to be fully initiated using Procedure 346.

IF 1 D 4160V Bus is being supplied by Offsite power, THEN TRANSFER only the # I Normal-Alternate switch to "Alternate" (partial initiation) on LSP-DG2 to isolate control room wiring and prevent spurious starting Of EDG-2 AND -

IF EDG-2 is already running, THEN STOP EDG-2 by momentarily taking the mode switch to stop.

8) When #2 EDG is supplying power to 4160V swgr. 1 D, ensure that the feeder breaker on 4160V 1 D unit D1 (from 4160V Bus IB) is open and locked out (69-permissive switch in the 'trip' position) to prevent inadvertent paralleling of offsite power with the EDG due to a spurious actuation.

p9 0

EQUIPMENT POTENTIALLY AFFECTED FIRE ZONE Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT REF ERE,,, E CONTROUINDICATION C 0 NTRO UI N D I CAT1 0 N P R 0 C E D U RE (S )

Procedure AB N-29 Rev. 9 CONDENSER BAY (TB-FZ-11 E)

Prompt Manual Actions (Cont'd):

9) NOTE: A hot short on the 1 D ammeter cable that runs to the control room can cause the 86/1D lockout relay to actuate which will either trip the EDG-2 breaker (if already closed) or will prevent the breaker from closing.

IF:

EDG-2 breaker trips or will not close (trips free) and 8611 D is picked up, THEN: Remove 8611D fuse pair labeled FU-80 (UB) in switchgear I D unit D1 and then reset the 8611 D lockout. Now that the trip signal on the EDG-2 breaker has been removed, the breaker can be closed.

IO) E Control of USS 1 B2M and B CRD pump is required from the RSP (partial initiation of RSP).

THEN Control USS 1 B2M and B CRD pump from the RSP IAW the instructions below.

1.

2.

3.

4.

5.

Confirm feeder breaker 1 B2P to USS 182 is closed.

Obtain key from the Padlock at the RSP.

Rotate keylock CRD and Breaker 1 B2M Control Transfer Switch to Alternate.

Confirm closed USS main Breaker, 1 B2M at RSP Operate B CRD pump at RSP as required.

I 1

FIREZONE CONDENSER BAY (cont'd)

(TB-FZ-11 E) i" EQUIPMENT POTENTIALLY AFFECTED Attachment ABN-29-1 Equipment Availability Matrix for Fires CORE SPRAY SYSTEM

" A Core Spray Pump Power and Control Ckt "B" Core Spray Pump Control CM (NZOIB)

" C Core Spray Pump Power and Control Ckt "0" Core Spray Pump Control Ckt (NZOID)

EMERGENCY SERV WTR SYS

" A ESW Pump Control Ckt (52A)

"B" ESW Pump Control Ckt (52B)

"C" ESW Pump Control C kt (52C)

"D" ESW Pump Control CM (52D)

CONDENSATE TRANSFER SYS Cond. Transfer Pump 1-1 Control CM Cond. Transfer Pump 1-2 Control CM Cond. Stg. Tank Level Indication (LT-35)

(NZOIA)

(NZOIC)

CONTROUI N DlCATl ON CONTROUINDICATION Local Brkr Operation Local Brkr Operation Local Brkr Operation Local Brkr Operation None None None None None LSP-1832 Local Gage (Ll-424-993) 4160V Bus I C 4160V Bus 1 D 4160V Bus I D 4160V Bus I C NA NA NA NA NA Chlor. Bldg.

Cond. Stg. Tank Procedure ABN-29 Rev. 9 APPLICABLE PROCEDURE(S) 308 308 308 308 31 0 31 0 31 0 31 0 316.1 316.1, 346 316.1 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA

03 0

P

(;'

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE CONDENSER BAY (cont'd)

(TB-FZ-11 E)

EQUIPMENT POTENTIALLY AFFECTED FUEL ZONE LEVEL "A", "B" Fuel Zone Level Instruments SERVICE WATER SYSTEM Service Wtr Pump 1-1 Control Ckt Service Wtr Pump 1-2 Control Ckt Service Wtr Hdr Press Indication (PT-6)

MSIV'S Outer MSIV (North)

(NS04A)

Outer MSlV (South)

(NS04B)

ELECTRICAL DIST. SYS EDG 1 Control Ckts EDG 2 Control Ckts Brkr 1 C Control Ckts Brkr 1B2P Control Ckts Brkr 1 B2M Control Ckts Brkr 1 B3P Control Ckts Brkr 1 B3M Control Ckts Power Feeder to DC-2 Power Feeder to DC-F 125 vdc Cntrl Pwr to Swgr 1 B Brkr I A l P Control Circuit Brkr 1A2P Control Circuit Brkr 1A3P Control Circuit Brkr I A l M Control Circuit Brkr 1A3M Control Circuit VACP-1 ALTERNATE CONTROUINDICATION "C", "D" Fuel Zone Level Instruments None LSP-1 B3 Local Gage (PI-30)

Inner MSlV (North)

(NS03A)

Inner MSlV (South)

(NS03B)

None None RSP LSP-DG-2 LSP-1 D LSP-I D LSP-183 None None Switch Cntrl to DC-A None None None None None None LOCATION OF ALTERNATE CONTROUINDICATION CR Pnl5F16F or RSP("B" 480V Swgr.Rm)

NA Intake Structure Intake Structure CR Pnl11F CR Pnl1 I F NA

2 EDG Vault NA

" D 4160 Swgr Room

" B 480V Room "D" 4160 Swgr Room Intake Structure NA NA "B" 4160V Swgr Room NA NA NA NA NA NA Procedure ABN-29 Rev. 9 APPLICABLE

)ROC ED U R E( S) 41 0 346 322 322,346 322 30 1 301 34 1 341, 346 337 337,346 346 337,346 338,346 340.3 340.3 340.1 337 337 337 338 338 339 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 340.1 NA NA NA NA NA NA

(

Attachment ABN-29-1 E q u i p me n t Ava i I a b i I i ty M at r ix for Fires EQUIPMENT POTENTIALLY AFFECTED FIRE ZONE ALTERNATE LOCATION OF ALTERNATE CONTROUINDICATION CONTROUI N Dl CAT1 ON CONDENSER BAY (cont'd)

(TB-FZ-11 E)

Additional Manual Actions I.

2.

3.

4.

5.

CONTROL ROD DRIVE "B" CRD Pump Control Circuit

2 RBCCW Pump Control CM.

RBCCW Press Ind (13R-63)

SHUTDOWN COOLING SYS.

V-I 7-1 9 & V-I 7-54

equired:

RSP Local bkr op (USS 182)

Local Gauge (PI-50A or 51A)

Panel 3F Test Plugs "8" 480V Room

'B' 480V Room Intake Structure Control Room Panel 3F Procedure ABN-29 Rev. 9 302.1,346 309.2 309.2 305 NA NA NA NA It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-15-237 Close V-45-52 Throttle V-I 5-30 for desired flow on Fl-225-2 The Reactor Feedwater Purnp/valve control circuits run through this area. Trip the pumps at their respective switchgear, and place their 69-permissive switches in the 'trip' position to ensure feedwater system isolation, Recharge V-I 1-36 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

If power is lost to "C" Battery Room HVAC fans from MCC 1A2, then ensure that the battery room door is opened within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months to prevent a buildup of hydrogen.

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-I 7-1 9 and V-17-54 from the Main Control Room.

IF:

V-17-19 & V-17-54 cannot be opened from Control Room Panel 1 I F THEN: Operate test plugs in Panel 3F per procedure 305, section 9.0.

r" Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 POTENTIALLY AFFECTED CONTROUINDICATION TB-FZ-11 E Manual Action Required (cont'd):

2 RBCCW Pump spuriously trips (USS 182)

Remove the trip fuses for this pump at USS 1 B2 and manually re-close the breaker.

THEN:

Breaker for #2 Service Water Pump spuriously trips open (USS 183)

Remove the trip fuses for this pump at USS 1 B3 and manually reclose the breaker.

THEN:

(:I I I

FIREZONE I

FEED PUMP ROOM (TB-FZ-1 IF) 03 0

0 Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYS I

" A core spray pump power ckt (NZOIA)

"C" core spray pump power ckt (NZOI C)

ELECTRICAL DISTR Brkr 1 D control ckt 125V DC control pwr to 4160V Bus 1 D from DC-B 125V DC control pwr to 480V bus USS 183 from DC-B SHUTDOWN COOLING Loop Inlet lsol Vlvs Loop Outlet lsol Vlvs (V-l7-1,2,3)

(V-l7-55,56,57)

ALTERNATE CONTROUlNDlCATlON None None None Control pwr from Control pwr from DC-A DC-A Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUlNDlCATlON NA NA NA 4160V Swgr 1 D 480V USS 183 SDC Room SDC Room SDC Room

('

Procedure ABN-29 Rev. 9 AP P LlCAB LE

'ROCEDU RE(S) 308 308 337 340.1 340.1 305 305 305, 309.2 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA

03 0

f EQUIPMENT POTENTIALLY AFFECTED FIRE ZONE

('

Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

REFERENCE Procedure ABN-29 Rev. 9 IF THEN Prior to Reactor Pressure decreasing to 31 0 psig, open the breakers on 41 60V Swgr. 1 D and lockout by taking the 69 permissive switch to the "trip" position for Core Spray Pumps NZOl B and NZOl C provided these pumps are not required to assure adequate core cooling.

Makeup to the Isolation Condenser may have to be provided by a fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-I 1-41 & 63 and open V-9-2099 & V-I 1-49).

Temporary Control Room ventilation may need to be installed per Procedure 331.1 if '8' CRHVAC is not available. 'A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened.

feedwater injection can not be terminated due to cable failures trip the condensate pumps and if necessary, lower level using the EMRV's.

IF -

THEN IF THEN Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

B battery charger is not available, V-14-34 can be cycled for short term operation (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) and then V-14-36 will have to be utilized for long term operation of the Isolation Condenser with V-14-34 left open or manually cycle V-14-34.

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF:

THEN:

IF:

THEN:

IF THEN V-I 7-1 9 & V-I 7-54 cannot be opened from Control Room Panel 1 1 F Operate test plugs in Panel 3F per procedure 305, section 9.0.

'B' Battery Charger trips Restore Battery Charger to service per procedures 2000-OPS-3024.1 OC (125VDC Diagnostic & Restoration) and 340.1 (125VDC Distribution Systems A & B).

USS 182 is not energized, Open USS 1B2M breaker and remove close fuses. Cross-tie USS 1A2 & 182 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this cross-tie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1 B21 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1B21 breakers and start EF-1-21 & SF-1-21 or provide temporary ventilation IAW Procedure 331.

(I EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE Attachment ABN-29-1 Eq u i p m e n t Ava i I a b i I i ty Matrix for F i res REPAIR DOCUMENT REFERENCE Procedure ABN-29 Rev. 9 I

( '

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE TURBINE BLDG.

MEZZANINE SOUTH (TB-FZ-11 G)

EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM "B" core spray pump control ckt (NZOI B)

"C" core spray pump control ckt (NZOIC)

EMER SERV WTR SYSTEM "C" ESW pump (52C) control ckt "D" ESW pump (52D) control ckt RBCCWISERV WTR SYS RBCCW disch hdr press indication (PI-IA18)

Serv wtr pump 1-2 control ckt Serv wtr hdr press indication (PT-6)

FUEL ZONE LEVEL "A", "B" fuel zone level indications ALTERNATE CONTROUINDICATION Local Breaker operation Local Breaker operation None None Local gages (Pl-50,51)

LSP-183 Local gage (PI-30)

"C", " D fuel zone level indications LOCATION OF ALTERNATE CONTROUINDICATION 4160V Bus I D 4160V Bus 1 D NA NA RB 51'EI, East on pump disch piping Intake structure Intake structure CR PNL 5FI6F or RSP ("B 480V Swgr room)

APPLICABLE

'ROCEDURE(S) 308 308 310 310 309.2 322,346 322 410 346 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

i Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE LOCATION OF ALTERNATE POTENTIALLY AFFECTED CONTROUlNDlCATlON CONTROUlNDlCATlON FIRE ZONE i

REPAIR APPLICABLE DOCUMENT PROCEDURE(S)

REFERENCE Procedure ABN-29 Rev. 9 Manual Action Required:

CAUTION:

1.

SCBA may be required to get to the 4160V switchgear rooms. The closest SCBA is located in the Pretreatment Building (east side).

Confirm Unit Auxiliary breaker is tripped on 1 B 4160V switchgear unit 83.

2.

Prior to Reactor pressure decreasing to 310 psig, open the following breakers listed below at their respective switchgear (place 69-permissive switches in 'trip' for 4160V breakers), or if the 4160V switchgear rooms are inaccessible and Core Spray System actuating signals are present, THEN override the Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing all ACTUATED switches, whether lit or unlit (Panel I Fl2F) and then close the parallel injection valves (V-20-15, 21,40 & 41). These actions are only to be performed provided these pumps are not required to assure adequate core cooling:

a.

b.

c.

Core Spray Pump NZOI D at 4160V Swgr. 1 C.

Core Spray Pumps NZOl B & NZOIC at 4160V Swgr. 1 D.

Close V-20-15,21,40 & z a n d then trip the core spray pumps once the switchgear rooms are accessible (refer to EOP Support Procedure #4 or #IO for guidance)

Reactor feedwater HP heater outlet valves power and control circuits are contained in this fire zone and may have to trip the Reactor Feedwater pumps andlor control flow utilizing the Main Feedwater Regulating Valves V-2-732, 733, 734, 735 and 736 valves.

OR

3.

4.

NOTE:

IF THEN CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

CST level indication (5F-27), RBCCW Pressure Indication (13R-63) andlor Service Water Pressure Indication (5F-60) are lost in the control room.

Either read all indicators locally

5.

Cable failures may cause VACP-1 to trip.

IF THEN Open all load breakers onVACP-1 and re-close VMCC 1 B2 breaker compartment C2R and then re-close VACP-1 breaker 21 for the required indicators.

Note that the breakers 16, 23, 25 & 26 on VACP-1 are not needed and should remain open to isolate the cable failures.

OR

1 FIREZONE SJAE ROOM:

MECH VAC PUMP CONDUCTIVITY RM, CONIDEMIN AREA I

(TB-FZ-11 H)

ROOM; HI-LOW Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CORE SPRAY SYSTEM "A" core spray pump power ckt (NZOIA)

"B" core spray pump power ckt (NZOI 3)

"C" core spray pump power cM (NZOIC)

"D" core spray pump power ckt (NZOI D)

ELECTRICAL DISTR SYS Brkr I D control ckt Pwr feeder to USS 1 B2 125V DC control pwr to 4160V Swgr I D 124V DC control pwr to 480V Swgr USS 183 SHUTDOWN COOLING SYS Loop Inlet Is01 Vlvs Loop Outlet Is01 Vlvs (V-17-1,2,3)

N-17-55.56.57)

RBCCW.SYSTEM SDC HX Outlet Flow control Vlv (V-5-106)

SHUTDOWN COOLING SYS.

V-I 7-1 9 & V-17-54 ALTERNATE CONTROUINDICATION None None None None None None 125V DC Control Pwr from DC-A 125V DC Control Pwr from DC-A Local Manual Local Manual Local Manual Local Manual Panel 3F Test Plugs LOCATION OF ALTERNATE CONTROUINDICATION NA NA NA NA None None 4160V Swgr 1 D 480V USS 183 SDC Room SDC Room SDC Room Control Room Panel 3F Procedure ABN-29 Rev. 9 AP P LlCAB LE

'ROCEDURE(S) 308 308 308 308 337 338 340.1 340.1 305 305 305, 309.2 305 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

REFERENCE GU 3E-911-41-040 GU 3E-91141-042 Manual Action Required:

(Hot Shutdown Path #2 for TB-FZ-11 H)

(Cold Shutdown Path #2 for TB-FZ-11 H)

(1)

(2)

(3)

(4)

!E Instrument Air is lost, Prior to Reactor Pressure decreasing to 310 psig, open the breakers on 4160V Swgr. I D for Core Spray Pumps NZOIB and NZOIC provided these pumps are not required to assure adequate core cooling.

Makeup to the Isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-I 1-41 & 63 and open V-9-2099 & V-I 1-49).

Temporary Control Room ventilation may need to be installed per Procedure 331.I if B CRHVAC is not available. A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened.

THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V 9 and open V-I 1-247).

(5)

!E B battery charger is not available, THEN V-14-34 can be cycled for short-term operation (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) and then V-14-36 will have to be utilized for long-term operation of the Isolation Condenser with V-14-34 left open or manually cycle V-14-34.

(6)

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF:

V-I 7-19 & V-I 7-54 cannot be opened from Control Room Panel 1 1 F THEN:

Operate test plugs in Panel 3F per procedure 305, section 9.0.

(7) !E USS 182 is not energized, THEN Open USS 1 B2M breaker and remove close fuses. Crosstie USS 1A2 & 1 B2 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this crosstie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1 B21 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1 B21 breakers and start EF-1-21 & SF-1-21 or provide temporary ventilation IAW Procedure 331.

(0 0

P Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 EQUIPMENT TB-FZ-11 H Manual Action Required (cont'd):

(8)

!E V-5-106 has to be manually opened, THEN Open its supply breaker on MCC 1 B21A and then manually operate V-5-106.

Attachment ABN-29-1 Equipment Availability Matrix for Fires "C" BATTERY ROOM (TB-FA-26)

Procedure ABN-29 Rev. 9 ELECTRICAL DISTR. SYSTEM 125V DC Distribution Center "C" CONTROUlNDlCATlON None NA 340.3 I

I I

References:

SU 3E-911-41-040 SU 3E-911-41-042 (Hot Shutdown Path # I for TB-FA-26)

(Cold Shutdown Path # I for TB-FA-26)

Manual Action Required:

(1)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 fl in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

(2).

(3)

If "C" Battery Room HVAC is lost, then ensure that the battery room door is opened within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months to prevent a buildup of hydrogen.

The Reactor Feedwater Pump control circuits run through this area. Place the Feedwater control switches in PTL (IA pump may not trip) andlor control flow utilizing the Feedwater Regulating Valves V-2-732, 733, 734, 735 and 736 andlor stop flow by closing V-2-10, V-2-11 and V-2-12 provided that the feedwater pumps are not required. Also, trip the pumps at their respective switchgear, and place their 69-permissive switches in the 'trip' position to ensure that the feedwater system remains isolated,

FIRE ZONE 3LD CABLE SPREADING ROOM (OB-FZ-4)

UPPER CABLE SPREADING ROOM (OB-FZ-2%)

NORTH CABLE BRIDGE TUNNEL (OB-FZ-22B)

SOUTH CABLE BRIDGE TUNNEL (OB-FZ-22C)

CONTROL ROOM (OB-FZ-5)

Attachment ABN-29-1 Procedure ABN-29 Equipment Availability Matrix for Fires Rev. 9 All SysterdComponents in selected hot and cold shutdown paths are potentially affected by a fire in these areas.

Remote Shutdown Panel 1

Various I 346 and ABN-30 and Local Shutdown Panels REPAIR DOCUMENT REFERENCE NA References :

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path #I for Control Room Complex)

(Cold Shutdown Path # I for Control Room Complex)

Manual Action Required:

(1)

All manual actions for fires in these areas are covered by Procedure -ABN-30, "Control Room Evacuation".

cr) 0 0

(

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE MECHANICAL EQUIPMENT 3OOM 74

[O B-FZ-22 D)

EQUIPMENT POTENTIALLY AFFECTED JENTllATlON SYSTEM 3 control HVAC ALTERNATE CONTROUINDICATION A control room HVAC LOCATION OF ALTERNATE CONTROUINDICATION Control Room APPLICABLE ROCEDURE(S) 331.I REPAIR DOCUMENT REFERENCE NA

References:

GU 3E-911-41-040 GU 3E-911-41-042 Manual Action Required:

(Hot Shutdown Path # I for OB-FZ-22D)

(Cold Shutdown Path # I for OB-FZ-22D)

(1)

Temporary Control Room ventilation may need to be installed per Procedure 331.1 if B CRHVAC is not available since the A CRHVAC may only be available in the FAN mode.

W P

0 Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 "A" 480V SWGR RM (OB-FZ-6A)

References:

GU 3E-91141-040 Hot Shutdown Path #I - "B" Isolation Condenser, "B" CRD Pump, Condensate Transfer Pump, Fuel Zone Level Ind. Ll-622-1001 &

1002, Rx. Pressure Ind. PI-622-999 & 1000, Offsite Pwr available GU 3E-91141-043 Cold Shutdown Path #3 - 2 EMRV's (with repairs), Core Spray Pumps, Containment Spray Pump (with repairs), ESW pump (with repairs), Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx. Pressure Ind. PI-622-999 & 1000, Rx Wide Range Lvl Ind (with repairs), Torus Water Temperature Ind Ti-664-43A and Torus Level Indicator (with repairs)

NOTE: This 'Cold Shutdown' Path utilizes 'Alternate Decay Heat Removal' per procedure 2000-OPS-3024.27, Section 4.4 to approach the Cold Shutdown condition (Core Spray, Containment Spray in Torus Cooling, and EMRV's). It may be necessary to perform repairs on affected equipment as identified in the list below.

Prompt Manual Actions:

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

1)

Confirm scram was completed in control room, if a scram was deemed necessary.

2)

NOTE:

USS 1A2 - USS 1 B2 cable bus tie is located in OB-FZGA and OB-FZ-6B. The USS 1A2 bus tie breaker US2T, is located in OB-FZ-6A and is normally racked out. The cable bus tie is bolted to the main bus at USS 1 B2 in OB-FZ-GB. A fire induced electrical fault on the cable bus tie in OB-FZ-6A could trip the main breaker of USS 182 in OB-FZ-GB.

CAUTION: 1) A fire induced short in the "A" 480 volt switchgear room can cause a loss of and the inability to re-energize USS 182. This repair has to be completed within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months in order to support RPV makeup.

2) SCBA may be required for these actions in the B 480V room.

IF THEN a fire in OB-FZ-GA results in the loss of USS 182 due to the tripping of its main breaker,

1. Disconnect the cable bus tie at USS 182 per Appendix R Repair Procedure 2400-APR-3730.01.

2.

Reenergize USS 1 B2 by closing breaker 1B2P and breaker 1 B2M.

W 0

cn

i.

I Attachment ABN-29-1 Equipment Availability Matrix fc Fires Procedure ABN-29 Rev. 9 REPAIR DOCUMENT REF ERE E

EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION C ONTRO UI N D lCATl0 N PROCEDURE( S)

FIRE ZONE

" A 480V SWGR RM (OB-FZ-6A cont'd)

Prompt Manual Actions (cont'd)

3. E breaker 1 B2M andlor B CRD Pump cannot be controlled from the Control Room, control breaker 1 B2M and B CRD Pump from the RSP IAW the instructions below (partial initiation).

1.

THEN Confirm feeder breaker 1 B2P to USS 1 B2 is closed.

2.

3.

4.

Obtain key from the Padlock at the RSP.

Rotate keylock CRD and Breaker 1 B2M Control Transfer Switch to Alternate.

Confirm closed USS main Breaker, I B2M at RSP

5.

Operate B CRD pump at RSP as required.

3)

Prior to Reactor Pressure decreasing to 310 psig, perform the following provided these pumps are not required to assure adequate core cooling:

a.

b.

d.

4)

NOTE:

IF THEN C.

Open the breakers and remove close fuses on top right of associated 480V USS 182 cubicle for Core Spray Booster Pumps NZO3B and NZOSC (fuse puller at RSP padlock).

Open breaker 1A2P and place 69-permissive in 'trip' at 4160V Swgr. I C for Core Spray Booster Pumps NZ03A and NZO3D.

Open breakers and place 69-permissive in 'trip' at 4160V Swgr. I C for Core Spray Pumps NZOIA and NZOID.

Open breakers and place 69-permissive in 'trip' at 4160V Swgr. 1 D for Core Spray Pumps NZOI B and NZOI C.

CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 39 minutes) to prevent the CST from draining to the hotwell. Approximately 17.4 ft in the CST may be required for isolation condenser shell side makeup. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

CAUTION: SCBA may be required for this manual action in the B 480V room.

The B Isolation Condenser level indicator is not available in the control room.

Obtain the level indication from the RSP indicator.

5)

!E THEN

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE

" A 480V SWGR RM cont'd)

(OB-FZ-6A EQUIPMENT POTENTIALLY AFFECTED CRD HYDRAULIC SYSTEM "A" CRD Pump (NC08A)

"B" CRD Pump (NC08B)

CRD Flow to Rx Ind.

(FI-RD36)

CORE SPRAY SYSTEM All Core Spray Pumps Control Ckts (NZOIA,B,C,D)

Core Spray Booster Pumps Power and Control Ckts. NZ03A and NZ03D Core Spray Booster Pumps Power and Control Ckts.

NZ03B and NZ03C System I Core Spray Pump Suction Vlvs.

Power and Control Ckts System II Core Spray Pump Suction Vlvs.

Power and Control Ckts (v-20433)

System I Parallel Vlvs Control Ckts.

System II Parallel Vlvs Control Ckts.

(v-20-3, 32)

(V-20-15,40)

(v-20-21,41)

ALTERNATE CONTROUlNDlCATlON LSP-1A2 RSP Local Gage (Fl-225-998) or (Fl-225402)

Local Manual Operation at Switchgear If necessary to trip pumps -

open Feeder Breaker at 1A2P If necessary to trip pumps -

open Feeder Breakers at USS 1B2 Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUlNDlCATlON

" A 480V Swgr Rm "B" 480V Swgr Rm RB 51', El SE RB 23' El, E 4160V Swgr. Rms.

I C or I D 4160V Swgr. Rm. 1 C "B" 480V Swgr. Rm.

RB-lqEL, NW RB-Ig'EL, SW RB 51'EL. NW RB 75'EL. SOUTH Procedure ABN-29 Rev. 9 APPLICABLE JROCEDURE(S) 302.1, 346 302.1, 346 302.1 302.1 308 308 308 308 308 308 308 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA

(:,

Attach men t AB N 1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE "A" 480V SWGR.

(cont'd)

ROOM (OB-FZ-6A)

EQUIPMENT POTENTIALLY AFFECTED Sys I Core Spray Pump Disch Press Ind (PI-RV04A)

Sys II Core Spray Pump Disch Press Ind (PI-RV04B)

(FI-RD36)

SHUTDOWN COOLING SYS "A" SDC Pump (NUOIA)

"B" SDC Pump (NU01 B)

"C" SDC Pump (NUOIC)

V-I 7-19 Indication CM.

V-I 7-54 Indication Ckt.

REACTOR LVUPRESS INSTR.

"A" FUEL ZONE LEVEL LI-IA94A PI-622-849 "B" FUEL ZONE LEVEL LI-IA94B Pl-622-850 RX LEVEL INSTR.

GEMAC Wide Range Level Ind.

CONTAINMENT INSTR SYS Torus Level Indication (LI-IA13)

(LI-IPOSA,B)

Torus Temp. Ind.

TI-644-43B ALTERNATE CONTROUlNDlCATlON Local Gages PIT-RVO3A or PI-19A Local Gages (PIT-RV03B or PI-298)

LSP-1A2 RSP None LSP-1AB2 LSP-1AB2 "C" Fuel Zone Lvl.

(Ll-622-1001)

(Pl-622-999)

(Ll-622-1002)

(Pl-622-1000)

Install Local Gage "D" Fuel Zone Lvl.

(Ll-626-1007)

Wide Range Torus Level (Ll-37,38) or Install Temporary Ind (Ll-626-1122)

TI-644-43A LOCATION OF ALTERNATE CONTROUlNDlCATlON RB-19' El. NW RB-19' El, SW "A" 480V Swgr Rm "B" 480V Swgr Rm NA RB 23' El, NE RB 23' El, NE CR PNL 5F/6F or RSP ("B" 480V Swgr Rm)

CR PNL 5F16F or RSP ("B" 480V Swgr Rm)

RKOI (R.B. 75' EL, East)

CR Pnl16R or RB-19 EL, NW CR Panel 1 F12F APPLICABLE

'ROCEDURE(S) 308 308 305,346 305,346 305 305,346 305,346 41 0 346 41 0 346 Repair Procedure 412.1 or Repair Procedure 312 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA 3665.01 NA or 3228.01 NA 2400-APR-2400-APR-

(

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE "A" 480V SWGR RM (cont'd)

(0 B-FZ-6 A)

EQUIPMENT POTENTIALLY AFFECTED CONTAINMENT SPRAY SYS.

All Cont. Spray Pumps Pwr & Control CMs (51 A,B,C,D)

System I Cont. Spray Pumps SUC. Vlvs. Control Ckt (v-21-9,7)

System I I Cont. Spray Pumps Suct. Vlvs.

Control CM (v-21-1,3)

System I Drywell Spray Isol. Vlv. Control Ckt System I TORUS CLG Discharge Vlv. Control Ckt System II Drywell Spray Is01 Vlv. Control Ckt (v-2 1 -5)

System I I TORUS CLG Discharge Vlv Cont. Ckt (v-21-13)

(v-21-11)

(v-21-17)

ALTERNATE CONTROUINDICATION Repair Power Feeders to 51C or51D use local control at USS 182 (manually ratchet closing motor)

Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUINDICATION

" B 480V Swgr Rm RB-19' El, NE RB-19' El, SE RB 51' El, East RB 23' El, North RB 23' El, SE RB 23' El, South Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 31 0 31 0 31 0 31 0 310 31 0 31 0 REPAIR DOCUMENT REFERENCE 2400-AP R-3214.01 NA NA NA NA NA NA

FIRE ZONE A 480V SWGR RM (contd)

(OB-FZ-6A)

(

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED Sys I, Sys 11, Flow Ind EMER SERV WATER SYS ESW Pump Control CKT 52A ESW Pump Control CKT 52B ESW Pump Control CKT 52C ESW Pump Control CKT 52D (FT-IPOBA,B)

ESW Disch Vlv. Sys I ESW Disch Vlv. Sys II CONDENSATE TRANSFER Cond Storage Tank Level (LT-35)

A ISOLATION COND.

AC Steam Isol. Vlv AC Cond. Rtn Isol. Vlv B ISOLATION CONDENSER Shell-side Level Indicator (W-1607B)

RBCCW SYSTEM Discharge Hdr. Pressure Ind. (PT-IA18)

RBCCW Pump 1-1 Power and Control Ckt.

RBCCW Pump 1-2 Power and Control Ckt.

(V-3-88)

(V-3-87)

(V-14-30)

(V-14-36)

Shutdown Clg. Flow Control Vlv. (V-5-106)

Control Ckt.

ALTERNATE CONTROUlNDlCATlON None None None None Repair Control CKT and Control Pump at breaker Local Manual Local Manual Local Gage (L1424-993)

Local Manual None RSP Local Gages (PI-50, 51)

LSP-IA2 RSP Local Manual LOCATION OF ALTERNATE CONTROUINDICATION NA NA NA NA 4160V Swgr. Rm ID RB 23 EL, North RB 23 EL, South Cond Storage Tank RB 75 EL, East NA B 480V Switchgear Room RB 51 EL, East on Pump Disch. Piping A 480V Swgr Rm B 480V Swgr Rm RB. SDC Rm Procedure ABN-29 Rev. 9 APPLICABLE ROCEDURE(S) 310 31 0 310 31 0 Repair Procedure 31 0 310 316.1 307 307 307 309.2 309.2, 346 309.2, 346 305, 309.2 REPAIR DOCUMENT REFERENCE NA NA NA NA 3531.01 NA NA 2400-APR-NA NA NA NA NA NA NA NA

-5 0

0 P

FIRE ZONE "A" 480V SWGR RM (cont'd)

(0 B-FZ-6A)

(:~

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED 3ECIRC SYSTEM

'B" Recirc Loop Suction dlv. Control Ckt.

(NGO2B)

' D Recirc Loop Suction Vlv. Control Ckt.

(NG02D)

"B" Recirc Loop Discharge Vlv Control Ckt (NG03B)

"D" Recirc Loop Discharge Vlv Control Ckt (NG03D)

" E Recirc Loop Discharge Vlv Control Ckt (NG03E)

REACTOR CLEANUP SYSTEM Drywell Isol. Vlv (V-16-1) Control Ckt.

ADS SYSTEM A,B,C,D,E, EMRV ADS Control Ckts (NR108A,B,C,D,E)

ALTERNATE C 0 NT RO UI N D I CAT1 0 N None None None None LSP-1 AB2 None Temporary Control and Ind. for NR108D,E LOCATION OF ALTERNATE CONTROUINDICATION NA NA NA NA RB 23' EL, NE NA NA Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 30 1 301 30 1 301 301,346 303 Repair Procedures REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA 2400-APR-341 1.01 341 1.04

FIRE ZONE "A" 480V SWGR RM (cont'd)

(OB-FZ-6A) i Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED VENTILATION SYSTEM Control Rm HVAC System "A"

" A 480V Swgr Room Supply Fan (FN-56-004)

"A" 480V Swgr Room Exhaust Fan (FN-56-007)

"A" 480V Swgr Rm HVAC Dampers ELECTRICAL DISTR. SYS.

Bus Tie Breaker US-2T Brkr 1 B2M Control Ckt.

480V USS 1A2 480V MCC 1A21 480V Vital MCC 1A2 Power Feeder to 480V MCC 1A23 Power Feeder to 480V MCC IA21A Power Feeder to 480V MCC 1A21B ALTERNATE CONTROUlNDlCATlON Control Rm HVAC System "B" LSP-1A2 LSP-1A2 or Start Alt Exhaust Fan (FN-56-008) from MCC 1821 Local Manual Disconnect Bus-Tie Cable RSP None None None None None None LOCATION OF ALTERNATE CONTROUlNDlCATlON Control Room "A" 480V Swgr Rm "A" 480V Swgr Rm "B" 480V Swgr Rm "A" 480V Swgr Rm "B" 480 Swgr Rm

" B 480V Swgr Rm.

NA NA NA NA NA NA Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 331.I 331,346 331, 346 331 338 338,346 338 338 338 338 338 338 REPAIR DOCUMENT REFERENCE NA NA NA NA 2400-APR-3730.01 NA NA NA NA NA NA NA

('

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 1

FIREZONE 1

" A 480V SWGR RM (OB-FZ-6A)

(cont'd)

EQUIPMENT POTENTIALLY AFFECTED Power Feeder to 480V Vital MCC 1B2 Power Feeder to 480V MCC 1823 Power Feeder to 480V MCC 1B21A Power Feeder to 480V MCC 1 B21 B Power Feeder to 480V MCC 1AB2 Power Feeder to Pnl A2 Power Feeder to RPS MG Set 1-1 Power Feeder to RPS MG Set 1-2 Power Feeder to PAIPP-1 PS-1 via SW-733-169 Power Feeder to PAIPP-2 PS-1 via SW-733-170 (PDP-733-057) & RPS XMR (POP-733-058) 8 RPS XMR ALTERNATE CONTROUlNDlCATlON None None None None None None None None None None LOCATION OF ALTERNATE CONTROUlNDlCATlON NA NA NA NA NA NA NA NA NA NA APPLICABLE

'ROCEDURE(S) 338 338 338 338 338 338 339 339 339 339 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA

2 0

0 0

FIRE ZONE "A" 480V SWGR RM (cont'd)

(OB-FZ-6A)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED Vital LTG Pnl VLDP-1 120V Pnl. VACP-1 120V Pnl. CIP-3 120V Pnl. IP-4 EDG#I ECCS Idle Start Ckt EDG#2 ECCS Idle Start Ckt 120V DC Pnl DC-F Pnl ER18A Pnl ERl8B Brkr 1 B2M Control Ckt.

ALTERNATE CONTROL/INDlCATlON None None None None None LSP-DG2 None None None RSP LOCATION OF ALTERNATE CONTROUINDICATION N/A NA NA NA NA

2 EDG Vault NA NA NA "B" 480V Swgr Rm Procedure ABN-29 Rev. 9 APPLICABLE P ROC ED U RE@)

339 339 339 339 NA 341,346 340.3 308 308 338,346 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA

4 0

0 P

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 REPAIR DOCUMENT RE ER E E

EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROLllNDlCATlON CO NTROUI N D KAT ION PROCEDURE( S)

FIRE ZONE Additional Manual Actions Required OB-FZ-6A (cont'd):

(1)

The "B" 125 VDC Battery M.G. Set charger is fed by an electrical supply located in this fire zone. Within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , (expected battery life under load with no charger in service) either confirm the "8" MG Set battery charger is operating properly accordance with Procedure 340.1, "125 VDC Distribution Systems "A" & "E".

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-15-237 Close V-I 5-52 place the static charger into service for the "B" Battery in (2)

Throttle V-I 5-30 for desired flow on Fl-225-2 (3).

Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

(4) E the C battery charger is not available THEN V-14-35 can be cycled for short term operation (approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) but V-14-37 will have to be utilized for long term operation of the Isolation Condenser with V-14-35 left open or manually cycle V-14-35.

Core Spray Pump NZOI B will be utilized for core cooling (5) IF THEN If power is lost to "C" Battery Room HVAC fans from VMCC 1A2, then ensure that the battery room door is opened within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months to prevent a buildup of hydrogen.

Remove control fuses from breaker (Bus ID, breaker D4) and manually close the breaker at the I D Bus.

(6).

(7)

!E V-204 (MCC 1B21A) & 41 (MCC 1AB2) and V-21-13 (MCC 18218) have to be manually opened andlor V-21-5 (MCC 18218) closed, It will be necessary to de-energize the applicable supply breakers prior to opening the MOVs to prevent future spurious operations of the valves.

THEN

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 REPAIR DOCUMENT REFERENCE EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE "B" 480V SWGR RM (OB-FZ-6s)

References:

GU 3E-911-41-040 Hot Shutdown Path #2 -"A" Isolation Condenser, " A CRD Pump, Firewater for IC makeup, Fuel Zone Level Ind. LI-IA94A, Rx. Pressure Ind. Pl-622-849, Offsite Pwr available GU 3E-911-41-043 Cold Shutdown Path #3 - 2 EMRV's, Core Spray Pumps, Containment Spray Pump, ESW pump, Fuel Zone Level Ind. LI-IA94A, Rx.

Pressure Ind. Pl-622-849, Rx Wide Range Lvl Ind LI-IA13, Torus Water Temperature Ind TI-664-43A and Torus Level Indicator (with repairs)

Prompt Manual Actions:

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

1)

2)

Confirm scram was completed in control room, if a scram was deemed necessary.

Prior to Reactor pressure decreasing to 310 psig, open breaker 1B2P and place 69 Permissive Switch in Trip at 4160V Swgr. I D to prevent Core Spray Booster pumps NZ03B and NZ03C from injecting provided these pumps are not required to assure adequate core cooling.

Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 17.4 ft in the CST may be required for isolation condenser shell makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

THEN

4)

Makeup to the Isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-I 1-41 & 63 and open V-9-2099 & V-I 1-49).

FIRE ZONE "B" 480V SWGR. RM.

(0 B-FZ-6B)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CRD HYDRAULIC SYS.

"B" CRD Pump (NCO8B)

CORE SPRAY SYSTEM "C" Core Spray Pump Control Ckt. (NZOI C)

"B" Core Spray Booster Pump Power and Control Ckt. (NZ03B)

"C" Core Spray Booster Pump Power and Control Ckt. (NZ03C)

System I Core Spray Pump Suction Vlvs.

Power and Control Ckts System I Core Spray Pump Disch. Press. Ind.

(V-20-3,32)

(P I-RV04A)

SHUTDOWN COOLING SYS.

"6" SDC Pump (NUOIB)

"C" SDC Pump (NU01 C)

CONTAINMENT INSTR. SYS.

Torus Level Indication (LI-IPOSA, B)

ALTERNATE CONTROUlNDlCATlON RSP None None None Local Manual Local Gages (PIT-RV03A or PI-RV29A)

RSP None Wide Range Torus Lvl.

(LT-37 andlor LT-38) or install Temporary Ind (LI-626-1 122)

LOCATION OF ALTERNATE CONTROUlNDlCATlON

" B 480V Swgr. Rm.

NA NA NA RB-19' EL, NW RB-19' EL, NW "B" 480V Swgr. Rm.

NA CR Pnl. 16R Or RB -19' El, NW Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 302.1, 346 308 308 308 308 308 305,346 305 412.1 or Repair Procedure REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA Or 3228.01 2400-APR-

(\\:

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 FIRE ZONE "B" 480V SWGR. RM.

(cont'd)

(0 B-FZ-6 B)

EQUIPMENT POTENTIALLY AFFECTED RBCCW SYSTEM Disch. Hdr. Press. Ind.

RBCCW Pump 1-2 Shutdown Clg. Flow Control Vlv. (v-5-106)

Power Supply CONTAINMENT SPRAY SYS.

"C" Cont. Spray Pump Power and Control Ckt.

(51 C)

"D" Cont. Spray Pump Power and Control Ckt.

(51 D)

Sys. II Cont. Spray Pumps Suct. Vlv.

Control Ckt. (V-21-1,3)

Sys. II Drywell Spray Isol. Vlv. Control Ckt.

(v-2 1 -5)

Sys. II TORUS CLG Discharge Vlv. Control Ckt.

(PT-IA1 B)

(V-2 1 -1 3)

"A" ISOLATION CONDENSER Shell Makeup Valve Power Ckt. (V-I 1-36)

ALTERNATE CONTROUlNDlCATlON Local Gages (Pl-50,51)

RSP Local Manual None None Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUlNDlCATlON RB-51' EL, East on Pump Disch. Piping "B" 480V Swgr. Rm.

RB, SDC Room NA NA RB-19' EL, SE RB-23' EL. SE RB-23' EL, South RB-95' EL, East APPLICABLE

'ROCEDURE(S) 309.2 309.2, 346 305, 309.2 31 0 31 0 31 0 310 310 307 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

1 FIREZONE "B" 480V SWGR. RM.

(cont'd)

(0 B-FZ-6B)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED "B" ISOLATION CONDENSER AC Steam Isol. Vlv.

(V-14-32) Control Ckt.

DC Steam Isol. Vlv.

(V-I 4-33) Control CM.

DC Cond. Return Isolation Vlv. Control Ckt.

AC Cond. Return Isolation Vlv. Control Ckt.

Shell Makeup Valve Power Ckt. (V-I 1-34)

Shell Level Indication (V-14-35)

(V-14-37)

(LI-IGO6B)

SERV. WTR. SYSTEM Service Wtr. Hdr.

Pressure Indication (PT-6)

FUEL ZONE LEVEL "C", "D" Fuel Zone Level Instruments VENTILATION SYSTEM "AIB" Battery Room Exhaust Fan (EF 1-20)

"B" 480V Swgr. Rm.

Supply Fan (SF 1-21)

ALTERNATE CONTROUINDICATION RSP or Local Manual RSP or Local Manual RSP or Local Manual RSP RSP or Local Manual RSP Local Gage (PI-29)

W' andlor "B" Zone Lvl. Instruments RSP RSP LOCATION OF ALTERNATE CONTROUINDICATION

" B 480V Swgr. Rm or RB-75'EL, East "B' 480V Swgr. Rm or RB-75'EL, East

" B 480V Swgr. Rm or RB-75'EL, East "B" 480V Swgr. Rm

" B 480V Swgr. Rm RB-95'EL, East "B" 480V Swgr. Rm Intake Structure CR Pnl. 5F/6F "B' 480V Swgr. Rm.

" B 480V Swgr. Rm.

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 307,346 307,346 307,346 307,346 307,346 307,346 322 410 331,346 334,346 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA

~

FIRE ZONE

'OB" 480V SWGR. RM.

(co nt'd)

(0 B-FZ-6B)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED "B" 480V Swgr. Rm.

Exhaust Fan (EF 1-21)

"NB" Battery Room Dampers "B" 480V Swgr. Room Dampers "A" 480V Swgr. Room Alternate Exhaust Fan (FN-56-008)

ELECTRICAL DISTR. SYS 480V USS 182 480V MCC 1 B21 480V Vital MCC 162 Power Feeder to 480V MCC 1B23 Power Feeder to 480V MCC 1 B21A Power Feeder to 480V MCC 1B21B Battery Charger MG Set "A" Battery Charger MG Set "B" N B Battery Static Charger ALTERNATE LOCATION OF ALTERNATE CONTROUlNDlCATlON I CONTROUlNDlCATlON RSP Local Manual Local Manual SF 1-21, EF 1-21 None None None None None None None None None "8" 480V Swgr. Rm.

"NB" Battery Rm.

"B" 480V Swgr. Rm.

CR Pnl. 11 R NA NA NA NA NA NA NA NA NA Procedure ABN-29 Rev. 9 AP P LlCAB LE

'ROCEDURE(S) 331, 346 33 1 33 1 331 338 338 338 338 338 338 340.1 340.1 340.1 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA NA

A P

0 Attachment ABN-29-1 Eq u i p m e n t Ava i I a b i I i ty Matrix for F i res Procedure ABN-29 Rev. 9 LOCATION OF ALTERNATE APPLICABLE CONTROUlNDlCATlON PROCEDURE(S)

EQUIPMENT 1

ALTERNATE 1

POTENTIALLY AFFECTED CONTROUlNDlCATlON FIRE ZONE E 480V SWGR RM (OB-FZ-6B) ( contd)

Additional Manual Actions Required:

(1)

E the A 480 Volt Switchgear Room Ventilation has tripped due to the fire in this fire zone (OB-FZ-SB),

the Licensed Operations Supervisor has directed its restart, confirm dampers DM-56-15 and DM-56-16 are open (manually open by disconnecting linkage if necessary) and DM-56-17 is closed (manually close by disconnecting linkage if necessary) and then restart the ventilation in accordance with Procedure 331 or install portable ventilation in the A 480V Room in accordance with Procedure 331.

AND THEN (2) E B battery charger is not available, THEN V-14-34 can be cycled for short-term operation (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) and then V-14-36 will have to be utilized for long term operation of the Isolation Condenser with V-I 4-34 left open or manually cycle V-14-34.

(3)

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 Close V-I 5-52 Throttle V-I 5-30 for desired flow on Fl-225-2 (4).

Recharge V-11-36 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

(5) Temporary Control Room ventilation may need to installed per Procedure 331.1 if B CRHVAC is not available. A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened per 331.I.

Attachment ABN-29-1 E q u i p m e n t Ava i I a b i I i ty Matrix for F i res A

A A

0 Procedure ABN-29 Rev. 9 EQUIPMENT ALTERNATE RECIRC MG SET RM (OB-FZ-8A)

References:

GU 3E-911-41-040 Hot Shutdown Path #2 - B Isolation Condenser, A CRD Pump, Firewater for IC Makeup, Fuel Zone Level Ind. LI-IA94A, Rx. Pressure Cold Shutdown Path #2 - A & (B or C) SDC Pumps, A CRD. RBCCW and Service Water Pumps, Fuel Zone Level Ind. LI-IA94A, Rx.

Ind. Pl-622-849, Offsite Power available GU 3E-911-41-042 Pressure Ind. PI-622-849 and Reactor Wide Range Level Indicator LI-IA13.

Prompt Manual Actions:

NOTE:

1) Confirm scram was completed in control room, if a scram was deemed necessary.

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

2) NOTE:

CAUTION:

IF THEN 21 NOTE:

IF During a tire condition in the Recirc MG Set Room (OB-FZ-8A), the possibility exists that hot shorts will develop in the EMRV cabling such that 125 VDC from an external source will be supplied to an EMRV, causing it to fail open. This spuriously opened EMRV will be reclosable using the normal EMRV control switch on 1 F12F.

The following action is required to preclude or terminate a spuriously opened EMRV. This action will disable the ADS, High Pressure and manual controls associated with the EMRVs. If the EOPs require the use of the EMRVs the disable switches can be returned to the normal position.

One or more EMRVs exhibit abnormal or spurious operation.

OR There are insufficient indications available to determine the status of an EMRV.

Ensure the reactor is scrammed in accordance with ABN-1 Reactor Scram.

AND -

Place the disable switch on the rear of panel 1 F/2F to the DISABLE position for those EMRVs affected.

The Reactor Recirculation pump circuits are located in this fire zone and they have to be tripped to utilize the Fuel Zone Level Indicators.

The Reactor Recirculation Pumps wont trip from the control room, THEN Trip the pumps from their respective switchgear (A or B 4160V Busses) and place their 69-permissive switches in the trip position.

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 REPAIR 1

ALTERNATE 1

LOCATION OF ALTERNATE 1 APPLICABLE 1

DOCUMENT CONTROUlNDlCATlON PROCEDURE(S)

DCCrDCh,rr FIRE ZONE RECIRC MG SET RM (OB-FZ-8A)

PromDt Manual Actions (cont'd):

3) Prior to Reactor pressure decreasing to 310 psig, open the following breakers at their respective switchgear (place 69-permissive switches in trip' position on 4160V breakers, remove 'close' fuses on top right of associated 480V breaker cubicle) provided these pumps are not required to assure adequate core cooling:

a.

Core Spray Booster Pumps NZ03B & NZ03C at 480V USS 1 B2 (fuse puller at RSP padlock).

b.

Core Spray Pumps NZOIB & NZOIC at4160V Swgr. ID.

4) Make up to the Isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-I 1-41 & 63 and open V-9-2099 & V-I 1-49).

5) E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

2 2

w 0

r----

FIRE ZONE RECIRC. MG SET RM.

(cont'd)

(0 B-FZ-8A)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CRD HYDRAULIC SYSTEM CRD Return to Reactor Flow Indication (FI-RD36)

CORE SPRAY SYSTEM "B", "D" Core Spray Booster Pumps Power Ckt. (NZ03B,D)

" A Core Spray Pump Suction Vlv. Power and Control Ckt. (V-20-3)

"B" Core Spray Pump Suction Vlv. Power and Control Ckt. (V-20-4)

" D Core Spray Pump Suction Vlv.

(Power and Control CKT. (I-20-33)

System I I Parallel Vlvs. Control Ckts.

System I Pump Disch.

Vlv. Power and Control System I I Pump Disch.

Vlv. Power and Control System I I Core Spray Pump Disch. Press. Ind.

(V-20-21,41) ckt. 01-20-12)

Ckt. (V-20-18)

(PI-RV04B)

ALTERNATE LOCATION OF ALTERNATE CONTROUINDICATION CONTROUINDICATION Local Gage (Fl-225-0998 or Fl-225-0002)

None Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual Local Gages (PI-29B, D)

RB-51' EL, SE NA RB-19' EL, NW RB-19' EL, SW RB-19 EL, SW RB-75' EL, South RB-51' EL, NW RB-75' EL, South RB-19' EL, SW Procedure ABN-29 Rev. 9 AP PLlCAB LE PROCEDURE( S) 302.1 308 308 308 308 308 308 308 308 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

A A

P 0

r-----

FIRE ZONE RECIRC. MG SET RM.

(cont'd)

(OB-FZ-8 A)

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 EQUIPMENT POTENTIALLY AFFECTED System II Booster Pump Disch. Press. Ind.

(PI-RV43B)

" A ISOLATION CONDENSER DC Steam Isol. Vlv.

Control Ckt. (V-14-31)

DC Cond. Return Isol.

Vlv. Control Ckt.

(v-I 4-34)

EMRVs Valve Cont. Ckt.

(EMRV A, B, C, D, E)

SHUTDOWN COOLING SYS.

"A" SDC Pump (NU02A)

Cont. Ckt.

" A Loop Suct. Vlv.

Cont. Ckt. (V-I 7-1)

"B" Loop Suct. Vlv.

Cont. Ckt. (V-17-2)

Cont. Ckt. (V-17-3)

"C" Loop Suct. Vlv.

ALTERNATE CONTROUlNDlCATlON

~

Local Gage (PI-4OB)

Local Manual Local Manual EMRV Disable Swts (EMRV A, B, C, D, E)

Temporary EMRV Control and Ind.

for NR108 0, E

LSP-1A2 Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUlNDlCATlON RB-23'EL, SW RB-75' EL, East RB-75' EL. East Rear CR Pnl 1 F/2F NA "A" 480V Swgr. Rm.

SDC Room SDC Room SDC Room APPLICABLE

'ROC ED U R E( S) 308 307 307 301 Repair Procedures 305,346 305 305 305 REPAIR DOCUMENT REFERENCE NA NA NA NA 2400-APR-341 1.01 341 1.02 341 1.03 341 1.04 NA NA NA NA 2400-APR-2400-APR-2400-APR-

(,

Attachment ABN-29-1 Equipment Availability Matrix for Fires A

A c"

0 FIRE ZONE RECIRC. MG SET RM.

(cont'd)

(OB-FZ-8A)

EQUIPMENT POTENTIALLY AFFECTED "A" Loop Disch. Vlv Control Ckt (V-I 7-55)

"B" Loop Disch. Vlv Control Ckt (V-17-56)

"C" Loop Disch. Vlv Control Ckt (V-17-57)

SHUTDOWN COOLING SYS.

V-17-19 & V-I 7-54 CONTAINMENT INSTR.

Drywell Press Ind.

(PI-IP12)

CONTAINMENT SPRAY SYS "C" Containment Spray Pump Power Ckt (51C)

"D" Containment Spray Pump Power Ckt (51 D)

Sys. II Cont Spray Pumps Suction Vlv.

Control Ckt (V-21-1, 3)

Sys. II Drywell Spray Isol. Vlv Control Ckt Sys. I I TORUS CLG Discharge Vlv. Control Ckt (V-21-13)

Sys. II Flow Ind.

EMER SERV WATER SYS ESW Disch Vlv Sys II (v-2 1 -5)

(FI-IP03B)

(V-3-87)

ALTERNATE CONTROUINDICATION Local Manual Local Manual Local Manual Panel 3F Test Plugs D w e l l Press. Ind.

Repair Pwr Feeders to 51C or 51D, use local control at USS 1 B2 (manually ratchet closing motor)

Local Manual Local Manual Local Manual None Local Manual LOCATION OF ALTERNATE CONTROUINDICATION SDC Room SDC Room SDC Room Control Room Panel 3F CR Pnl10R B 480 Swgr Rm RB -19' EL, SE RB -23' EL, SE RB -23' EL, South NA RB 23' EL, South Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 305 305 305 305 312 310 310 31 0 310 310 310 REPAIR DOCUMENT REFERENCE NA NA NA NA NA 2400-APR-3214.01 NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE RECIRC. MG SET RM.

(cont'd)

(OB-FZ-8A)

EQUIPMENT POTENTIALLY AFFECTED RECIRC SYSTEM "E" Loop Discharge Vlv. (NG03E) Cont Ckt MSlVs Inner MSIV, North (NS03A)

Inner MSIV, South (NS03B)

ELECTRICAL DISTR. SYS Power Feeder to 480V Power Feeder to 125VDC 125V DC Control Power to 4160V Swgr 1 D from 125V DC Cont Power to 480V USS 183 from DC-B MCC 1A21A MCC DC-1 DC-B ALTERNATE LOCATION OF ALTERNATE CONTROUINDICATION CONTROUINDICATION LSP-1AB2 Outer MSIV, North (N S04A)

Outer MSIV, South (NS04B)

None None 125V DC from DC-A 125V DC from DC-A RB 23' EL. NE CR Pnl11 F CR Pnl11F NA NA 41 60V Swgr. 1 D USS 1B3 Procedure ABN-29 Rev. 9 APPLICABLE

>ROCEDURE(S) 301,305, 346 30 1 301 338 340.1 340.1 340.1 REPAIR DOCUMENT REFERENCE NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires ALTERNATE LOCATION OF ALTERNATE FIRE ZONE Additional Manual Actions Required: RECIRC MG SET RM (OB-FZ-8A) (cont'd)

Procedure ABN-29 Rev. 9 REFERENCE (1)

RC makeup can be provided (if required) using the CRD pumps by manually opening the CRD bypass valves V-15-30 & 237 and closing V-15-52.

(2)

Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes). Recharge V-11-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

(3)

To restore power to USS 183 for 'B' Control Room HVAC, manually open breaker 1 B3M and remove 'close' fuses, trip all load breakers on 183 and then rack in tie breaker US3T and manually close breaker IAW Procedure 338. Note that temporary Control Room ventilation can be installed per Procedure 331.I if needed.

(4)

!E at least one recirculaiton loop cannot be verified open using Control Room indications, THEN verify at least one loop is open per Attachment ABN-29-2.

(5) Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF: -

THEN:

V-I 7-19 & V-17-54 cannot be opened from Control Room Panel 1 1 F Operate test plugs in Panel 3F per procedure 305, section 9.0.

(6)

Cable failures may prevent operation of Shutdown Cooling Loop Isolation Valves from the Main Control Room.

IF:

THEN:

Any SDC valve (V-17-1, 2, 3, 55, 56 & 57) has to be manually opened, Open their supply breakers at MCC DC-1 on Rx Bldg 23' SE, and manually operate the valves as required.

A A

03 0

EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUlNDlCATlON CONTROUlNDlCATlON PROCEDURE(S)

FIRE ZONE (I

Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR DOCUMENT REFERENCE Procedure ABN-29 Rev. 9 IF:

THEN:

(8)

!E -

THEN (9) !E THEN V-5-106 cannot be operated from the Control Room Manually open breaker BO3 at MCC 1B21A on Rx Bldg 23, and manually operate the valve as required.

USS 182 is not energized, Open USS 1 B2M breaker and remove close fuses. Crosstie USS 1A2 & 1 B2 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this crosstie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1 B21 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1B21 breakers and start EF-1-21 8 SF-1-21 or provide temporary ventilation IAW Procedure 331.

HVAC is lost to the NB battery room and the battery chargers are operating, ensure that the battery room door is opened within 87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months to prevent a buildup of hydrogen.

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED

(

Procedure ABN-29 Rev. 9 REPAIR ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUlNDlCATlON CONTROUlNDlCATlON PROCEDURE(S)

REFERENCE FIRE ZONE VENTILATION SYSTEM Control Room HVAC System A MECH. EQUIPT. RM (0 B-FZ-8B)

Control Room HVAC Control Room 331.I NA System B

References:

GU 3E-911-41-040 GU 3E-911-41-042 Manual Action Required:

(Hot Shutdown Path #2 for OB-FZdB)

(Cold Shutdown Path #2 for OB-FZ-8B)

(1)

Prior to Reactor pressure decreasing to 310 psig, open the following breakers at their respective switchgear, and place 69-permissive switches in trip for 4160V breakers and remove close fuses for 480V breakers, provided these pumps are not required to assure adequate core cooling:

a.

b.

c.

To restore power to USS 183 for B Control Room HVAC, manually open breaker 1 B3M and remove close fuses, trip all load breakers on 1 B3 and then rack in tie breaker 1A3T and manually close breaker IAW with Procedure 338. Note that temporary Control Room ventilation can be installed per Procedure 331.1 if needed.

(3)

!E Instrument Air is lost, Core Spray Booster Pumps NZ03A & NZ03D at 480V USS 1A2.

Core Spray Booster Pumps NZ03B & NZ03C at 480V USS 182.

Core Spray Pumps NZOIB & NZOIC at 4160V Swgr. ID.

(2)

THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

(4)

Makeup to the Isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-I 1-41 & 63 and open V-9-2099 & V-I 1-49).

(5)

The Reactor Recirculation pump control cables run through this area and it may be necessary to trip the pumps from their respective switchgear, and place the 69-permissive switches in the trip position (e.g. for use of isolation condensers or fuel zone level), provided that these pumps are not required.

(1 EQUIPMENT POTENTIALLY AFFECTED Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

REFERENCE f I.>

Procedure ABN-29 Rev. 9 I

I I

FIRE ZONE I

I VIECH. EQUIPT. RM (contd)

[O B-FZ-8 B)

Manual Action Required (contd):

(6)

LE at least one recirculation loop cannot be verified open ising Control Room indications, THEN Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF: -

THEN:

verify at least one loop is open per Attachment ABN-29-2.

(7)

V-17-19 & V-17-54 cannot be opened from Control Room Panel 1 1 F Operate test plugs in Panel 3F per procedure 305, section 9.0.

(8)

Cable failures may prevent operation of Shutdown Cooling Loop Isolation Valves from the Main Control Room.

IF:

Any SDC valve (V-17-1,2, 3,55,56 & 57) has to be manually opened, THEN: Open their supply breakers at MCC DC-1 on Rx Bldg 23 SE, and manually operate the valves as required.

Cable failures may prevent operation of RBCCW Shutdown Cooling Outlet Valve V-5-106 from the main Control Room.

IF:

THEN:

(9)

V-5-106 cannot be operated from the Control Room Manually open breaker BO3 at MCC 1 B21A on Rx Bldg 23, and manually operate the valve as required.

(10) !E USS 182 is not energized, THEN Open USS 1B2M breaker and remove close fuses. Crosstie USS 1A2 & 182 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this crosstie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1821 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1821 breakers and start EF-1-21 & SF-1-21 or provide temporary ventilation IAW Procedure 331.

(1 1)

If HVAC is lost to the NB battery room and the battery chargers are operating, then ensure that the battery room door is opened within 87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months to prevent a buildup of hydrogen.

c EQUIPMENT POTENTIALLY AFFECTED FIRE ZONE

(:

Attachment ABN-29-1 REPAIR ALTERNATE LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUlNDlCATlON CONTROUlNDlCATlON PROCEDURE(S)

REFERENCE Procedure ABN-29 Equipment Availability Matrix d r Fires Rev. 9 REFERENCES GU 3E-91141-040 Hot Shutdown Path #2 - "B" Isolation Condenser, "A" CRD Pump, Firewater for IC Makeup, Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx.

Pressure Ind. Pl-622-999 & 1000. Offsite Power available GU 3E-911-41-042 Cold Shutdown Path #2 - " A & (B or C) SDC Pumps, " A CRD, RBCCW and Service Water Pumps, Ll-622-1001 & 1002, Rx. Pressure Ind.

PI-622-999 & 1000and Reactor Wide Range Level Indicator (with repairs)

Prompt Manual Actions:

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

1)

2)

NOTE:

Confirm scram was completed in control room, if a scram was deemed necessary.

During a fire in the N B Battery Room (OB-FZ-8C), the possibility exists that 125 vdc control power will be lost to the "B" 4160V Switchgear.

CAUTION: The feedwater pumps might have to be secured to prevent an overfill condition.

IF the feedwater pumps are required to be secured, THEN From the control room, Place the Feedwater control switches in PTL (1 B & I C pumps may not trip) andlor stop flow by closing V-2-10, V-2-11 and v-2-12.

3)

NOTE:

IF -

THEN

4)

NOTE:

IF THEN Perform communication using radios.

The Reactor Recirculation pump circuits are located in this fire zone and they have to be tripped to utilize the Fuel Zone Level Indicators.

The Reactor Recirculation Pumps won't trip from the control room, Trip the pumps from their respective switchgear ('A' or 'B' 4160V Busses) and place their 69-permissive switches in the 'trip' position.

During a fire in the AfB Battery Room (OB-FZ-8C), the possibility exists that the Plant page and alarm system may be lost.

The Plant page and alarm system is lost,

-L N

0 lu EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE Attachment ABN-29-1 Equipment Availability Matrix for Fires REPAIR DOCUMENT REFERENCE Procedure ABN-29 Rev. 9 N B BATTERY RM. (OB-FZ-8C)

(cont'd)

Prompt Manual Actions (cont'd)

5) Prior to Reactor pressure decreasing to 310 psig, open the following breakers at their respective switchgear (place 69-permissive switches in trip' position on 4160V breakers, remove 'close' fuses on top right of associated 480V breaker cubicle) provided these pumps are not required to assure adequate core cooling:

a.

b.

c.

d.

Core Spray Booster Pumps NZ03A & NZ03D at 480 USS 1A2 (fuse puller at RSP padlock).

Core Spray Booster Pumps NZ03B & NZ03C at 480V USS 182 (fuse puller at RSP padlock).

Core Spray Pumps NZOIB & NZOIC at 4160V Swgr. ID.

Core Spray Pump NZOIA & NZOI D at 4160V Swgr. I C

6) Make up to the Isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-I 1 4 1 & 63 and open V-9-2099 & V-I 149). Note Isolation Condenser Level indication may not be available in the control room so use the indicator at the RSP.

7) NOTE:

USS 1A2 main breaker may trip IF -

THEN USS 1A2 breaker trips, Control USS 1A2 Main breaker at LSP-1A2 IAW with Procedure 346. Note that control of the A CRD, SDC and RBCCW pumps will also be transferred to LSP-1A2.

8) NOTE:

IF CST may drain to the Hotwell on Loss of Instrument Air.

CST Level indicator is not available in the control room or Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 73 minutes) to prevent the CST from draining to the hotwell. Approximately 10.1 fl in the CST may be required for reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

i:

FIRE ZONE N B BATTERY RM.

I-=-

(cont'd)

(OB-FZ-8C)

(.

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CRD HYDRAULIC SYSTEM "A' CRD Pump Cont. Ckt.

CRD Return to Reactor Flow Ind. (FI-RD36)

CORE SPRAY SYSTEM All Core Spray Pumps Control Ckts.

(NZOIA,B,C,D)

All Core Spray Booster Pumps Power and Control Ckts. (NZ03A, B,C,D)

System I Core Spray Pump Suction Vlvs.

Power and Control Ckts.

(V-20-3,32)

System I I Core Spray Pump Suction Vlvs.

Power and Control Ckts.

(V-204,33)

System I Parallel Vlvs.

Control Ckts. (V-20-15,40) and V 15 Power Ckt.

ALTERNATE CONTROUINDICATION LSP-1A2 Local Gage 002)

(Fl-225-998 or Fl-225-Local Manual at Switchgear None Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUINDICATION "A" 480V Swgr. Rm.

RB 51'EL, SE or RB 23' EL 4160V Swgr. Rooms I C or I D NA RB-Ig'EL, NW RB-l9'EL, SW RBdl'EL, NW Procedure ABN-29 Rev. 9 APPLICABLE

?ROCEDURE(S) 302.1,346 302.1 308 308 308 308 308 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE AfB BATTERY RM.

(co nt' d)

(0 B-FZ-8 C)

EQUIPMENT POTENTIALLY AFFECTED System I1 Parallel Vlvs. Control Ckts.

System I Testable Check Vlvs. Control CMs. (NZO2A,C)

(V-20-21,41)

System I Core Spray Pump Disch. Press. Ind.

(P I-RV04A)

System I1 Core Spray Pump Disch. Press. Ind.

(P I-RV04B)

System I1 Core Spray Booster Pump Disch.

Press. Ind. (PI-RV43B)

" A ISOLATION CONDENSER AC Steam Isol. Vlv.

Control Ckt. (V-14-30)

DC Steam Isol. Vlv.

Control Ckt. 01-14-31)

DC Cond. Return Vlv.

Control CM. (V-14-34)

"B" ISOLATION CONDENSER Shell-side Level Indicator (LI-IG07B )

ALTERNATE CONTROUlNDlCATlON Local Manual None Local Gages (PIT-RV03A or PI-RV29A)

Local Gages (PIT-RV03B or PI-RV29B)

Local Gage (PI-4OB)

Local Manual Local Manual Local Manual RSP LOCATION OF ALTERNATE CONTROUlNDlCATlON RB-75'EL, South NA RB-IVEL, NW RB-I VEL, SW RB-23'EL, SW RB-75'EL, East RB-75'EL, East RB-75'EL, East "B" 480V Switchgear Room Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 308 308 308 308 308 307 307 307 307 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA

FIRE ZONE N B BATTERY RM.

(cont'd)

(0 B-FZ-8C)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED AC Cond. Return Vlv.

Control Ckt. (V-14-36)

Shell Makeup Vlv. Power and Control Ckt.

(V-I 1-36)

EMRVs

" A EMRV Ind. Ckt.

(NR108A)

"B" EMRV Ind. Ckt.

(NR108B)

"C" EMRV Ind. Ckt.

(NRI 0%)

"D" EMRV Ind. Ckt.

(NRIOBD)

"E" EMRV Ind. Ckt.

(NRI 08E)

SHUTDOWN COOLING SYS.

" A SDC Pump Control Ckt.

ALTERNATE CONTROUlNDlCATlON Local Manual Local Manual None None None None None LSP-1A2 LOCATION OF ALTERNATE CONTROUlNDlCATlON RB-75'EL, East RB-95'EL, East NA NA NA NA NA "A" 480V Swgr. Room Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 307 307 308 308 308 308 308 305,346 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA

(:

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED FIRE ZONE N B BATTERY RM.

(cont'd)

(OB-FZ-8C)

"B" SDC Pump Control Ckt.

"C" SDC Pump Control CM.

"A" Loop Suction Vlv.

Control Ckt. 01-17-1)

"B" Loop Suction Vlv.

Control Ckt. (V-17-2)

"C" Loop Suction Vlv.

Control Ckt. (V-I 7-3)

"A" Loop Disch. Vlv.

Control Ckt. (V-17-55)

"B" Loop Disch. Vlv.

Control Ckt. (V-I 7-56)

"C" Loop Disch. Vlv.

Control Ckt. (V-17-57)

SDC System Inlet Isol.

Vlv. Ind. Ckt. (V-I 7-1 9)

SDC System Outlet Isol.

Vlv. Ind. Ckt. (V-I 7-54)

RX. LEVEUPRESS. INSTR.

"A". "B" Fuel Zone Level Instr.

GEMAC Wide Range Level Indication (LI-IA13)

ALTERNATE CONTROUlNDlCATlON RSP None Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual LSP-1 AB2 LSP-1 AB2 "C", "D" Fuel Zone Level Instr.

Install Local Gage (Ll-626-1007)

LOCATION OF ALTERNATE C 0 N TR 0 UI N D I CAT1 0 N "B' 480V Swgr. Room NA SDC Room SDC Room SDC Room SDC Room SDC Room SDC Room RB-23'EL, NE RB-23'EL, NE CR Pnl. 5F16F or RSP

("B" 480V Swgr. Rm.)

RKOI (RB-75'EL, East)

I Procedure ABN-29 Rev. 9 AP P LlCAB LE

>ROCEDURE(S) 305,346 305 305 305 305 305 305 305 305,346 305,346 41 0 346 Repair Procedure REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA 2400-APR-3665.01

(,

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE AIB BATTERY RM.

(cont'd)

(OB-FZ-8C)

EQUIPMENT POTENTIALLY AFFECTED CONTAINMENT INSTR.

Torus Level Indicator (LT-I P09A, B)

Torus Temperature Ind.

(TE-644-43 A&B)

RBCCW SYSTEM Discharge Header Press Indication (PT-IA18)

RBCCW Pump 1-1 Control Ckt.

RBCCW Pump 1-2 Control Ckt.

SDC Flow Control Vlv.

Control CM. (V-5-106)

RX. CLEANUP SYSTEM Aux. Pump Sud. Vlv.

Control Ckt. (V-16-2)

ALTERNATE CONTROUINDICATION Wide Range Torus Level (LT-37,38)

None Local Gages (PI-50,51)

LSP-1A2 or manually close breaker at USS 1A2 RSP Local Manual Local Manual LOCATION OF ALTERNATE CONTROUINDICATION CR Pnl. 16R NA RB-5 'El, Ea%. on Pump Disch. Piping "A" 480V Swgr. Rm.

"B" 480V Swgr. Rm.

SDC Room RBdl'EL, South

(

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 412.1 312 309.2 309.2, 346 309.2,346 305, 309.2 303 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA

r---

FIRE ZONE I

AIB BATTERY RM.

(cont'd)

(OB-FZ-8C)

(

Attachment ABN-29-1 Procedure ABN-29 Equipment Availability Matrix for Fires Rev. 9 POTENTIALLY AFFECTED CONTROUINDICATION Aux. Pump Bypass Vlv.

Control Ckt. (V-16-14)

CONDENSATE TRANSFER Cond. Storage Tank Level Ind. (LT-35)

CONTAINMENT SPRAY SYS Containment spray pumps power (C,D only) and control ckts (51A,B,C,D)

Sys I cont spray pumps suct vlvs control ckt Sys II cont spray prnps suct vlvs control ckt Sys I drywell spray isol vlv control ckt (V-21-11)

Sys I TORUS CLG Discharge vlv control ckt (V-21-17)

Sys I I drywell spray isol vlv control ckt (v-2 I

-5)

Sys I I TORUS CLG Discharge vlv control ckt (V-2 1 -1 3)

(V-2 1 -9,7)

(V-21-1,3)

Local Manual Local Gage (Ll-424-993)

Repair pwr feeders to 51C or 51D. Use local control at USS 182 (manually ratchet closing motor)

Local Manual Local Manual Local Manual Local Manual Local Manual Local Manual LOCATION OF ALTERNATE APPLICABLE CONTROUINDICATION PROCEDURE(S)

RB-51'EL, South Cond. Storage Tan "8" 480V swgr Rrn RB -19 EL, NE RB -19 EL, SE RB 51' EL, East RB 23' EL, North RB 23' EL, SE RB 23' EL, South 303 316.1 310 310 310 310 310 310 31 0 REPAIR DOCUMENT REFERENCE NA NA 2400-APR-321 4.01 NA NA NA NA NA NA

FIRE ZONE AIB BATTERY RM.

(cont'd)

(0 B-FZ-8 C)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED EMER SERV WTR SYS ESW disch vlv, Sys I (V-3-88)

ESW disch vlv, Sys I I (V-3-87)

VENTILATION SYSTEM Control room HVAC sys. " A

'A' 480V Rm Supply Fan FN-564

'A' 480V Rm Exhaust Fan FN-56-7 SERVICE WATER SYS Service wtr htr press indication (PT-6)

RECIRC SYSTEM "E" recirc loop disch vlv control ckt (V-37-54)

MSIV'S Inner MSIV, north (NS03A)

Inner MSIV, south (NS03B)

ELECTRICAL DlSTR SYS 125V DC Battery " A 125V DC Battery "B" ALTERNATE CONTROUINDICATION Local Manual Local Manual Control Room HVAC Sys. "B" LSP-1/42 LSP-1A2 Local gage (PI-29)

LSP-1AB2 Outer MSIV, North (NS04A)

Outer MSIV, south (NS04B)

None None LOCATION OF ALTERNATE CONTROUINDICATION RB 23' EL, North RB 23' EL, South Control Room

'A' 480V Room

'A' 480V Room Intake Structure RB 23' EL, NE CRPNLI 1 F CRPNLI 1 F NA NA r:

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 310 310 331.I 338,346 338,346 322 301,346 301 301 340.1 340.1 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA

s FIRE ZONE AIB BATTERY RM.

(cont'd)

(0 B-FZ-8 C)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELECTRICAL DISTR SYS AIB batteries static charger Battery charger MG set

" B power feeder 480V power to MCCIA21A Static inverter pwr to RSP (ALT)

Brkr 1A2M control ckt Power feeder to pnl DC-1 125V DC Pnl "D"

2 EDG fast start ckt EDG # I & #2 Idle Ckt.

120V AC power to pnl9R Power feeder to pnl ER18A Power feeder to pnl ERI 8B ALTERNATE CONTROUlNDlCATlON None None None Power to RSP from Pnl IP-4 (Norm)

LSP-1 A2 None None LSP-DG2 (will not regain fast start ckt)

None None None None LOCATION OF ALTERNATE CONTROUlNDlCATlON NA NA NA "8" 480V swgr rm

" A 480V swgr rm NA NA

2 EDG Vault NA NA NA NA

\\.

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 340.1 340.1 338 346 338,346 340.1 340.1 341,346 NA 339 340.1 340.1 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA NA NA

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 REPAIR 1

LOCATION OF ALTERNATE DOCUMENT CONTROUINDICATION 1 Pkgk%&)

1 REFERENCE EQUIPMENT 1

POTENTIALLY AFFECTED FIRE ZONE Additional Manual Actions Required:

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 0

Close V-I 5-52 The Reactor Feedwater Pump/FW Regulating valve control circuits run through this area. Trip the Feedwater pumps at their respective switchgear, Throttle V-15-30 for desired flow on Fl-225-2 and place their 69-permissive switches in the 'trip' position as follow up (Feedwater block valves closed earlier) to ensure that the feedwater system remains isolated, Recharge V-I 1-34 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

To restore 'B' Control Room HVAC, it may be necessary to cross-tie USS 1A3 and USS 183. To accomplish this, trip and remove close fuses for breaker 1B3M at USS 1B3, trip all load breakers on 183, close tie breaker 1A3T at USS 1A3 IAW Procedure 338, and confirm Control Room HVAC breaker (Unit 061C) is closed. Note that temporary control room ventilation can be installed per Procedure 331.I if needed.

IF THEN IF THEN IF THEN IF THEN USS 1 B2 is not energized, Open USS 1 B2M breaker and remove close fuses. Crosstie USS 1A2 & 1 B2 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this crosstie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service. Local manual operation of SDC and RBCCW pump may be required. If local operation is required, remove trip fuses prior to manually closing the breaker. In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1 B21 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1B21 breakers and start EF-1-21 & SF-1-21 or provide temporary ventilation IAW Procedure 331.

at least one recirculation loop cannot be verified open using Control Room indications, verify at least one loop is open per Attachment ABN-29-2.

Breaker for RBCCW Pump 1-1 spuriously trips (USS 1A2)

Remove the trip fuses from the breaker cubicle and manually re-close the breaker.

Any MOVs for SDC (V-17-1, 2, 3,55, 56 or 57) or RBCCW (V-5-106) have to be manually opened Open the valve's supply breaker at MCC DC-1 for SDC valves and MCC 1B21A for V-5-106 before manually operating the valve.

May have to use LSP-1AB2 for controlling V-17-19 & 54 and V-37-54 If HVAC is lost to the "NB" battery room and the battery chargers are operating, then ensure that the battery room door is opened within 87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months to prevent a buildup of hydrogen.

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE OFFICE BLDG RMS (OB-FA-9)

EQUIPMENT POTENTIALLY AFFECTED CONDENSATE TRANSFER Cond. Storage Tank Level Ind. (LT-35)

EMRVS "A" EMRV control ckt "B" EMRV control ckt RX. LEVEUPRESS. INSTR.

GEMAC Wide Range Level Indication (LI-IA 13)

RBCCW SYSTEM Discharae Header Press Indication IPT-IA 18)

SERVICE WATER SYS Service water header press indication IPT-62 SHUTDOWN COOLING SYS.

V-I 7-1 9 & V-I 7-54 VENTILATION SYSTEM Control Room HVAC System " A fan power circuit ALTERNATE CONTROUINDICATION Local Gage (Ll-424-993)

None None Install Local Gage (Ll-626-1007)

Local Gages (Pl-50,51)

Local gage (PI-30)

Panel 3F Test Plugs Control Room HVAC System "B" LOCATION OF ALTERNATE CONTROUINDICATION Cond. Storage Tank NA NA RKOI (RB-75'EL. East)

RB-51' El. East on Pump Disch. Piping Intake Structure Control Room Panel 3F Control Room Procedure ABN-29 Rev. 9 APPLICABLE

>ROCEDURE(S) 316.1 308 308 Rep:

P rocec ;re 309.2 322 305 331.1 REPAIR DOCUMENT REFERENCE NA NA NA 2400-APR-3665.01 NA NA NA NA

(:,

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR DOCUMENT REFERENCE OFFICE BLDG RMS (contd)

(OB-FA-9)

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path # I for OB-FA-9)

(Cold Shutdown Path # I for OB-FA-9)A Manual Action Required:

(1)

CST may drain to the Hotwell on Loss of Instrument Air.

IF THEN CST Level indicator is not available in the control room or Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly (within approximately 30 minutes) to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

(2)

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-I 7-19 and V-17-54 from the Main Control Room.

IF: -

THEN:

N B Battery Room Ventilation may be lost due to cable failures in this fire area.

IF: -

THEN:

V-I 7-19 & V-I 7-54 cannot be opened from Control Room Panel 11 F Operate test plugs in Panel 3F per procedure 305, section 9.0.

(3)

N B Battery Room Ventilation is lost.

Repair dampers (block open) if failed closed and EF-1-20 may have to be run with its control switch in the Bypass position or install portable ventilation per Procedure 331.

(4)

B Control Room Ventilation may be lost due to LFAP#6 cable failures in this fire area.

IF:

THEN:

B Control Room Ventilation is lost.

FN-826-8B may have to be run with its control switch in the Bypass position

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION C 0 NTR 0 UI N D I CAT IO N P ROC E D U RE (S )

FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR DOCUMENT REF ERE E

References:

GU 3E-911-41-040 Hot Shutdown Path #2 - "A" Isolation Condenser, "A" CRD Pump, Firewater for IC Makeup, Fuel Zone Level Ind. Ll-622-1001 & 1002, Rx.

Pressure Ind. Pl-622-999 & 1000, Offsite Power available GU 3E-911-41-042 Cold Shutdown Path #2- " A & (B or C) SDC Pumps, " A CRD, RBCCW and Service Water Pumps, L1-622-1001 & 1002, Rx. Pressure Ind. Pl-622-999 & IOOOand Reactor Wide Range Level Indicator (with repairs).

Promnt Manual Actions:

NOTE:

These steps can be performed concurrently and are listed in the order of priority but are dependent on actual plant symptoms.

1) Confirm scram was completed in control room, if a scram was deemed necessary.

2) NOTE During a fire condition in the Monitor and Change Area (OB-FZ-IOA), the possibility exists that hot shorts will develop in the EMRV cabling such that 125 VDC from an external source will be supplied to an EMRV, causing it to fail open. This spuriously opened EMRV will be reclosable using the normal EMRV control switch on 1 F/2F.

CAUTION: The following action is required to preclude or terminate a spuriously opened EMRV. This action will disable the ADS, High Pressure and manual controls associated with the EMRVs. If the EOP's require the use of the EMRVs the disable switches can be returned to the normal position.

One or more EMRVs exhibit abnormal or spurious operation.

There are insuffrcient indications available0 determine the status of an EMRV.

IF OR THEN Ensure the reactor is scrammed in accordance with ABN-1 "Reactor Scram".

Place the disable switch on the rear of Panel 1 F/2F to the "DISABLE" position for those EMRV's affected.

AND

(

EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUlNDlCATlON CONTROUlNDlCATlON PROCEDURE(S)

FIRE ZONE Attach men t AB N I Equipment Availability Matrix for Fires REPAIR DOCUMENT REFERENCE Procedure AB N -29 Rev. 9

4) SF-1 -20 may trip and will have to be run with its control switch in the Bypass position.

5) Makeup to the Isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done IAW the 307 procedure (close V-I 1 4 1 &

63 and open V-9-2099 & V-I 149).

6) E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

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FIRE ZONE MONITOR AND CHANGE AREA (cont'd)

(OB-FZ-1 OA)

EQUIPMENT POTENTIALLY AFFECTED "B" ISOLATION CONDENSER AC Steam Isol. Valve Control Ckt (V-14-32)

DC Steam Isol. Valve Control Ckt (V-14-33)

DC Cond Return Isol. Vlv Control Ckt (V-14-35)

AC Cond Return Isol. Vlv Control Ckt (V-14-37)

Shell Makeup Vlv Control Ckt (V-I 1-34)

Shell Level Indication (LI-IGSB)

EMRV'S

" A EMRV Control Ckt "B" EMRV Control Ckt "C" EMRV Control Ckt

" D EMRV Control Ckt

" E EMRV Control Ckt Attachment ABN-29-1 Equipment Availability Matrix for Fires ALTERNATE CONTROUlNDlCATlON RSP RSP RSP RSP RSP RSP EMRV "A" Disable Swt EMRV "B" Disable Swt EMRV "C" Disable Swt EMRV " D Disable Swt Temporary EMRV Control & Indication EMRV " E Disable Swt Temporary EMRV Control & Indication LOCATION OF ALTERNATE CONTROUlNDlCATlON "B" 480V Swgr. Rm "B" 480V Swgr. Rm "B" 480V Swgr. Rm "B" 480V Swgr. Rm "B" 480V Swgr. Rm "B" 480V Swgr. Rm Rear CR Pnl 1 F12F Rear CR Pnl 1 F/2F Rear CR Pnl 1F12F Rear CR Pnl 1F/2F NA Rear CR Pnl 1 F12F NA Procedure ABN-29 Rev. 9 APPLICABLE ROC ED U RE(S) 307,346 307,346 307,346 307,346 307,346 307,346 30 1 301 301 30 1 Repair Procs.

30 1 Repair Procs.

REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA 2400-APR-3411.01 2400-APR-3411.02 2400-APR-3411.04 2400-APR-3411.01 2400-APR-3411.03 2400-APR-3411.04

FIRE ZONE MONITOR AND CHANGE AREA (cont'd)

(OB-FZ-IOA)

Attachment ABN-29-1 Equipment Ava i I a b i I i ty Matrix for F i res EQUIPMENT POTENTIALLY AFFECTED RX VESSEL LVUPRESSURE ADS Control Ckts Fuel Zone Channel " A Fuel Zone Channel " B GEMAC Wide Range Level Indication (LI-IAI 3)

ALTERNATE CONTROUINDICATION None Fuel Zn. Channel "C" Fuel Zn. Channel "D" Install Local Gage (Ll-626-1007)

LOCATION OF ALTERNATE CONTROUINDICATION NA CR Pnl5F/6F or RSP ("B 480V Rm)

CR Pnl5F/6F or RSP ("B" 480V Rm)

RKOI (RB 75' EL. East)

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 308 410 or 346 41 0 or 346 Repair Procedure REPAIR DOCUMENT REFERENCE NA NA NA 2400-APR-3665.01

A w

W 0

MONITOR AND CHANGE AREA (con t'd)

Attach men t AB N 1 Equipment Availability Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED CONTAINMENT INSTR SYS Drywell Press Ind.

(PI-IPO7)

RBCCWISERV WTR SYSTEM RBCCW Disch Hdr. Press Ind. (PI-IA18)

Shutdown Cooling Flow Control Valve (V-5-106)

Service Wtr Hdr Press Ind. (PT-6)

CONTAINMENT SPRAY SYS Sys I Drywell Spray Isolation Valve Control CM (V-21-11)

System I Flow Ind.

System II Flow Ind.

VENTllATlON SYSTEM "AIB" Battery Room Exhaust Fan Power and Control CM (EFI-20)

"B" 480V Swgr. Rm Supp.

Fan Power and Control "B" 480V Swgr. Rm Exhst Fan Power and Control (FI-IP03A)

(FI-IPO3B)

C kt (SF 1-2 1 )

C kt (EF 1-21 )

ALTERNATE CONTROUINDICATION Drywell Press Ind (PI-IP12)

Local Gages (Pl-50,51)

Local Manual Local Gage Local Manual (P 1-29)

None None RSP RSP RSP LOCATION OF ALTERNATE CONTROUINDICATION CR Pnl 1 F/2F RB 51' EL. East on Pump Disch. Piping SDC Room Intake Structure RB 51' EL. East NA NA "B" 480V Swgr. Room

" 6 480V Swgr. Room "8"

480V Swgr. Room (1,

Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDU RE(S) 312 309.2 305, 309.2 322 310 310 310 331,346 331,346 331,346 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA NA NA

2 P

0 P

FIRE ZONE MONITOR AND CHANGE AREA (cont'd)

(OB-FZ-1 OA)

Attachment ABN-29-1 Eq u i p men t Ava i la b i I i ty Matrix for Fires EQUIPMENT POTENTIALLY AFFECTED ELECTRICAL DISTR. SYS.

125 VAC DC Control Pwr to USS 182 from DC "E" Power Feeder to "NB" Batt Static Charger 12OVAC Power to RSP from Static Inverter (ALT) 125VDC Power to RSP from DC Pnl "D"

Remote Shutdown Pnl RSP Trouble Alarm (SXF-I-F)

SHUTDOWN COOLING SYS A, B, C Loop Suction Valves 01-1 7-1,2,3)

A, B, C Loop Disch.

Valves (V-l7-55,56, 57)

SHUTDOWN COOLING SYS.

V-17-19 & V-17-54 ALTERNATE CONTROUINDICATION 125V DC Control Pwr from DC " A None 12OVAC Power to RSP From Pnl IP-4 (NORM)

None Local Indications on RSP Local Manual Local Manua Panel 3F Test Plugs LOCATION OF ALTERNATE CONTROUINDICATION 480V USS 182 NA

" B 480V Swgr. Room NA "B" 480V Swgr. Room SDC Room SDC Room Control Room Panel 3F I

Procedure ABN-29 Rev. 9 APPLICABLE

>ROCEDURE(S) 340.1 340.1 346 346 346 305 305 305 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA NA

i:.

Attach men t AB N-2 9-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 MONITOR AND CHANGE AREA (OB-FZ-IOA) (contd) hdditional Manual Actions Required:

(1)

B battery charger is not available, THEN V-14-34 can be cycled for short term operation (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) and then V-14-36 will have to be utilized for long term operation of the Isolation Condenser with V-14-34 left open or manually cycle V-14-34.

It may be necessary to use the CRD bypass line due to the loss of instrument air by performing the following:

Open V-I 5-237 Close V-I 5-52 (2)

Throttle V-I 5-30 for desired flow on Fl-225-2 (3).

(4 )

Recharge V-I 1-36 Accumulator per Procedure 307 as required (accumulator is sized for approximately 5 strokes).

Temporary Control Room ventilation may need to be installed per Procedure 331.I if B CRHVAC is not available. A CRHVAC may only be available in the FAN ONLY mode and may have to position its control switch to the Bypass position. In addition, the vent dampers may have to be manually opened per 331.I Procedure.

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF:

(4)

V-I 7-1 9 8 V-I 7-54 cannot be opened from Control Room Panel I 1 F THEN: Operate test plugs in Panel 3F per procedure 305, section 9.0.

(5) E USS 182 is not energized, THEN Open USS 1B2M breaker and remove close fuses. Cross-tie USS 1A2 & 1B2 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this cross-tie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). If local manual operation of the breaker is necessary, then remove the trip fuses prior to manually closing the breaker.

(6)

E Ventilation is tripped in the B 480V Room THEN It has to be restored to support SDC by confirming MCC 1 B21 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1821 breakers and start EF-1-21 & SF-1-21 or if EF-1-21 Ei SF-1-21 wont start due to cable failures, then provide temporary ventilation IAW Procedure 331.

(7)

!E V-5-106 has to be opened manually, THEN Open its supply breaker at MCC 1B21A. prior to opening V-5-106.

i:

Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE CHEM LAB, PASS ROOM, INSTR. SHOP (OB-FZ-I OB)

EQUIPMENT POTENTIALLY AFFECTED SHUTDOWN COOLING SYS A, B, C Loop Suct.

Isolation Valves A, B, C Loop Disch.

Isolation Valves (V-I 7-1,2, 3)

(V-I 7-55,56,57)

ELECTRICAL DISTR SYSTEM 1 B2M Control Circuit 120 VAC Power to RSP From Static Inverter 125VDC Power to RSP From DC Panel "D" 125VDC Control Power to USS 182 from DC "B" Power to "AIB Batt Static Charger (ALT)

ALTERNATE CONTRO UI N D ICATION Local Manual Local Manual Local Manual 12OVAC Power to RSP from Pnl IP4 (NORM)

None 125VDC Control Pwr From DC " A None LOCATION OF ALTERNATE CONTROUINDICATION SDC Room SDC Room "B' 480V Swgr. Room "B" 480V Swgr. Room NA 480V USS 1 B2 NA Procedure ABN-29 Rev. 9 APPLICABLE

'ROCEDURE(S) 305 305 338 346 346 340.1 340.1 REPAIR DOCUMENT REFERENCE NA NA NA NA NA NA NA

A P

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EQUIPMENT ALTERNATE POTENTIALLY AFFECTED CONTROUINDICATION FIRE ZONE

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Attachment ABN-29-1 Equipment Availability Matrix for Fire REPAIR LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUINDICATION PROCEDURE(S)

REFERENCE Procedure ABN-29 Rev. 9

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path #2 for OB-FZ-IOB)

(Cold Shutdown Path #2 for OB-FZ-IOB)

Manual Action Required:

Prior to Reactor pressure decreasing to 310 psig, open the breakers for Core Spray Booster Pumps NZ03B and NZ03C at 480V USS 182, and remove 'close' fuses, provided these pumps are not required to assure adequate core cooling.

Makeup to the isolation Condenser may have to be provided by a Fire diesel pump and valve line-up should be done in accordance with the 307 procedure (close V-11-41 & 63 and open V-9-2099 8, V-1149).

Temporary Control Room ventilation may need to be installed per Procedure 331.I if 'B' CRHVAC is not available. 'A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened.

IF THEN instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V 9 and open V-I 1-247).

USS 1 B2 is not energized, IF THEN Close USS 1B2M breaker and restore the following loads by closing their applicable breakers as necessary. Note local manual operation of USS 182 breakers may be required due to the potential loss of DC control power.

0 RBCCW pump (if needed)

Battery charger to the B battery (static charger from MCC 1 B21 or MG Set from VMCC 182)

Ventilation to the B 480V Room (EF-1-21 & SF-1-21 from MCC 1821) and then starting SF-1-21 and EF-1-21 or provide temporary ventilation IAW Procedure 331.

SDC pump (B or C) for cold shutdown.

A P

0 P

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Attachment ABN-29-1 Equipment Availability Matrix for Fires FIRE ZONE MA1 N TRANSFORM E R AND CONDENSATE TRANSFERPAD (MT-FA-12)

References:

GU 3E-911-41-041 GU 3E-911-41-042 EQUIPMENT ALTERNATE POTENTIALLY AFFECTED CONTROUINDICATION CONDENSATE TRANSFER SYS Condensate Transfer Pmp 1-1 Motor and Control Ckt Condensate Transfer Pmp 1-2 Motor and Control Ckt Condensate Storage Tank Level Indication LT-35 None LSP-1 B32 Local Gage (Ll-424-993)

ELECTRICAL DlSTR SYS 480V Power to MCCI 832 None I

(Hot Shutdown Path #3 for MT-FA-12)

(Cold Shutdown Path #I for MT-FA-12)

LOCATION OF ALTERNATE CONTROUlNDlCATlON NA Chlor. Bldg.

Cond. Stg. Tank NA (1

Procedure ABN-29 Rev. 9 AP P LlCAB LE

'ROCEDURE(S) 316.1 346 316.1 33%

REPAIR DOCUMENT REFERENCE NA NA NA NA Manual Action Required:

(1)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell or if V-2-90 is unavailable, then close V-2-54, 55 & 56 (Condenser Bay) and V-2-230, 231 & 232 (Feedpump Room) as depicted in ABN-37-5.

Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cool down to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

FIRE ZONE INTAKE AREA (C W-FA-1 4)

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUl PMENT POTENTIALLY AFFECTED SERVICE WATER SYSTEM Service Water Pump 1-1 Service Water Pump 1-2 Service Water Hdr Press Indication (PT-6)

EMERGENCY SERV WTR SYS All ESW Pumps Pwr and Control Ckts (52 A, B, C, D)

ELECTRICAL DISTR SYS USS 1A3 USS 1B3 480V MCC 1 B32 VENTILATION SYSTEM Control Room HVAC System "B' CONTROUINDICATION CONTROUINDICATION None LSP-1 B3 Local Gage (PI-30)

NA Intake structure I

Intake Structure Temporaty Power to An ESW Pump from 4160V Swgr 1 D None None None NA NA NA NA Control Room HVAC Control Room System "A" Procedure AB N-29 Rev. 9

~~

APPLICABLE

'ROCEDURE(S) 322 322,346 322 Repair Procedure 338 338 338 331.I REPAIR DOCUMENT REFERENCE NA NA NA 2400-APR-3531.01 NA NA NA NA

(::

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE Procedure ABN-29 Rev. 9 REPAIR DOCUMENT REFERENCE INTAKE AREA (CW-FA-14) (cont'd)

References:

GU 3E-911-41-040 GU 3E-911-41-043 (Hot Shutdown Path # I for CW-FA-14)

(Cold Shutdown Path #3 for CW-FA-14)

NOTE: This 'Cold Shutd vn' Path utilizes 'Alternate Decay Heat Removal' per procedure 2000-OPS-3024.27, Section 4.4 to approach the Cold Shutdown condition (Core Spray, Containment Spray in Torus Cooling, and EMRV's). It may be necessary to perform repairs on affected equipment as identified in the matrix.

Manual Action Required:

(1)

Temporary Control Room ventilation may need to be installed per Procedure 331.1 if 'B' CRHVAC is not available. 'A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened.

Makeup to the Isolation Condensers may have to be provided by a Fire Diesel pump; valve lineup should be performed in accordance with Procedure 307.

(2)

(3)

LE Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 17.4 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

(4)

The Circulating Water Pump control and power cables run through this area.

IF:

THEN:

The SIA or SIB breakers spuriously trip open, Manually open the Circ Water Pump breakers on the bus (Le. breakers A6 and A7 on 4160V bus 1A or B5 and B7 on 4160V bus 1 B),

then manually reclose incoming breaker SIA or SIB, as applicable.

Attachment ABN-29-1 Equipment Availability Matrix for Fires

(

Procedure ABN-29 Rev. 9 REPAIR DOCUMENT RFFFRFNCF EQUIPMENT ALTERNATE LOCATION OF ALTERNATE APPLICABLE POTENTIALLY AFFECTED 1

CONTROUINDICATION CONTROUINDICATION PROCEDURE(S)

FIRE ZONE

I EDGVAULT All # I EDG Control Ckts None NA (D G-FA-1 5)

SHUTDOWN COOLING SYS.

Panel 3F Test Plugs Control Room Panel 3F V-I 7-1 9 & V-I 7-54 341 305 NA NA

References:

GU 3E-91141-040 GU 3E-91141-042 (Hot Shutdown Path #I for DG-FA-15)

(Cold Shutdown Path #I for DG-FA-15)

Manual Action Required:

(1)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

(2)

Cable failures may prevent operation of Shutdown Cooling Isolation Valves V-17-19 and V-17-54 from the Main Control Room.

IF:

V-17-19 & V-17-54 cannot be opened from Control Room Panel 11 F THEN:

Operate test plugs in Panel 3F per procedure 305, section 9.0.

(:~

Attachment ABN-29-1 Equipment Availability Matrix for Fires

(,

Procedure ABN-29 Rev. 9 FIRE ZONE

2 EDG VAULT (DG-FA-17)

EQUIPMENT POTENTIALLY AFFECTED ELECTRICAL DISTRIBUTION

2 EDG Control Ckts.

SHUTDOWN COOLING SYS A, B, C Loop Suction Isolation Valves (V-I 7-1,2,3)

A, B, C Loop Disch.

Isolation Valves (V-I 7-55,56,

57)

RBCCW SYSTEM Shutdown Cooling HX Outlet Flow Control Valve (V-5-106)

ALTERNATE CONTROUINDICATION None Local Manual Local Manual Local Manual LOCATION OF ALTERNATE CONTROUINDICATION NA SDC Room SDC Room SDC Room AP P LlCAB LE

'ROCEDURE(S) 341 305 305 305,309.2 REPAIR DOCUMENT REFERENCE NA NA NA NA

(

~

Attachment ABN-29-1 Equipment Availability Matrix for Fires EQUIPMENT ALTERNATE POTENTIALLY AFFECTED CONTROUINDICATION FIRE ZONE

(\\

Procedure ABN-29 Rev. 9 REPAIR LOCATION OF ALTERNATE APPLICABLE DOCUMENT CONTROUINDICATION PROCEDURE(S)

REFERENCE tc2 EDG VAULT

DG-FA-17)

(contd)

References:

SU 3E-911-41-041 (Hot Shutdown Path #4 for DG-FA-17)

SU 3E-911-41-042 (Cold Shutdown Path #2 for DG-FA-17)

Manual Action Reauired:

Tempo;ary Control Room ventilation may need to be installed per Procedure 331.I if B CRHVAC is not available. A CRHVAC may be available in the FAN ONLY mode, provided vent dampers are manually opened.

IF -

THEN IF THEN -

IF THEN Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 10.1 ft in the CST may be required for reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

USS 182 is not energized, Open USS 1 B2M breaker and remove close fuses. Crosstie USS 1A2 & 1 B2 IAW Procedure 338 by closing the tie-breaker (local manual operation if necessary). Note that this crosstie is required to get another SDC pump (B or C) and RBCCW pump (if needed) in service (local manual operation if necessary). In addition, ventilation will have to be restored to the B 480V Room by confirming MCC 1821 is energized and then confirm closed EF-1-21 (unit E06) and SF-1-21 (unit D06) MCC 1B21 breakers and start EF-1-21 & SF-1-21 or provide temporary ventilation IAW Procedure 331.

V-5-106 has to be manually opened, Open its supply breaker on MCC IB21A and then manually operate V-5-106.

Attachment ABN-29-1 Equipment Availability Matrix for Fires Procedure ABN-29 Rev. 9 Aux Boiler House, Gal. Storage Tank EDG Vaults

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path #I for FS-FA-16)

(Cold Shutdown Path #I for FS-FA-16)

Manual Action Required:

(1)

There are no additional manual actions required for a fire in this area.

FIRE ZONE 4UX BOILER HOUSE

[AB-FA-I 3)

FIRE DIESEL PUMP HOUSE (FW-FA-18)

OLD RAD WASTE BLDG. (OR-FA-19)

NEW RAD WASTE BLDG. (NR-FA-20)

AOG BLDG.

(OG-FA-21)

NEW WAREHOUSE (NW-FA-23)

MAINT. BLDG.

(M B-FA-24)

REDUNDANT FIRE PUMP HOUSE (PH-FA-25)

SITE EMERGENCY BLDG. (EB-FA-28)

LOW LEVEL RAD WASTE STGE. FAC (LL-FA-29)

t.

Attachment ABN-29-1 Equipment Availability Matrix for Fires

(

Procedure ABN-29 Rev. 9

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path #I)

(Cold Shutdown Path #I Manual Action Required:

(1)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-11-247).

FIRE ZONE Attachment ABN-29-1 Equipment Availability Matrix for Fires

(~;

Procedure ABN-29 Rev. 9

~

INDEP. SPENT FUEL STORAGE (LL-FA-30)

OLD/NEW RADWASTE YARD AREA (OR-FA-33)

NEW AUXILIARY BUILDING (AB-FA-34)

SGTS AND VENTILATION TUNNEL (SGTS-FZ-31)

LLRW FACILITY YARD AREA (LL-FA-32)

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path #I)

(Cold Shutdown Path #I)

None Manual Action Required:

(1)

!E Instrument Air is lost, THEN V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

Attachment ABN-29-1 Equipment Availability Matrix for Fires i:

I

(\\

Procedure ABN-29 Rev. 9 I

I I

References:

GU 3E-911-41-040 GU 3E-911-41-042 (Hot Shutdown Path # I or Path #2 depending on which ventilation is affected)

(Cold Shutdown Path # I or Path #2depending on which ventilation is affected)

Manual Action Required:

Instrument Air is lost, V-2-90 in the Condensate Transfer Building should be closed promptly to prevent the CST from draining to the hotwell. Approximately 19.5 ft in the CST may be required for isolation condenser shell and reactor vessel makeup during cooldown to cold shutdown. Makeup to the CST as necessary from Demineralized Water (procedure 320.1), High Purity (procedure 351.2), or the Fire Protection system (as last resort, close V-9-11, open V-9-9 and open V-I 1-247).

Control Room ventilation has to be shutdown due to smoke or both trains of ventilation are affected for a fire on OB Roof, use portable ventilation per procedure 331.I B 480v Room ventilation is affected or AB Battery Room ventilation is affected, use HSP # 2 and CSP #2 A 480V Room ventilation is affected, use HSP # I and CSP # I The fire is at the Condensate Storage Tank (CST),

use HSP #3 (GU 3E-911-41-041) and CSP #3 (GU 3E-911-41-043)

V-5-106 has to be manually opened, Open its supply breaker on MCC 1 B21A and then manually operate V-5-106.

OYSTER CREEK GENERATING STATION PROCEDURE

AmerGen, An fxckn Zompany Number ABN-29 e

I Title PLANT FIRE ATTACH ME NT ABN-29-2 DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES

_-____-____-___1____-~---------------------------------------------

WHEN one (1) open recirculation loop has been determined by this attachment, THEN Tag open the breakers for the recirculation loop suction and discharge valves associated with the open recirculation loop

_-______-____________________I__________--------------------------------------------------------------------------------

Determine one (1) open recirculation loop (discharge valve and its associated suction valve both open) per the following steps. Recirculation loops may be checked in any order.

1.O Recirculation LOOP A 1.I V-37-10, A Recirculation LOOP Discharge valve in MCC IAZIA, Unit A04

{ref. GE 157B6350 Sh 327) 1.I.I 1.I

.2 Open the breaker for the A Recirculation Loop Discharge valve, V-37-10 on MCC 1A21A.

Remove the control power fuse for A Recirculation Loop Discharge valve, V-37-10.

Removed By:

Verified By:

Lift the following leads for the V-37-10 closed limit switch from the terminal strip in Unit A04 (cable 22-376).

1.I

.3 Revision No.

9 TB-1 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

154.0

OYSTER CREEK GENERATING STATION PROCEDURE ArnerGen-an fWbn COmPdOy Number ABN-29 ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES I

L' Title PLANT FIRE I.I

.4 Check that there is no continuity through the V-37-10 closed limit switch lifted leads which indicates V-37-10 is open.

Revision No.

9 Open Not Open 1.I

.5 E

V-37-10 is open, THEN check that the A Recirculation Loop Suction valve, V-37-9 is open.

V-37-10 is not open, 1.I

.6 THEN check a different recirculation loop for open suction and discharge valves.

1.2 V-37-9. A Recirculation LOOD Suction valve in MCC 1A21A. Unit A01

[ref. GE 157B6350 Sh 326) 1.2.1 Open the breaker for the A Recirculation Loop Suction valve, V-37-9 on MCC 1A21A.

1.2.2 Remove the control power fuse for A Recirculation Loop Suction valve, V-37-9.

Removed By:

Verified By:

Lift the following leads for the V-37-9 closed limit switch from the terminal strip in Unit A01 (cable 22-373).

I

.2.3 0 TB-1 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

155.0

OYSTER CREEK GENERATING STATION PROCEDURE AmerGen.

An x&n Company Title PLANT FIRE Number ABN-29 I Revision No.

9 ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES 1.2.4 Check for no continuity through the V-37-9 closed limit switch lifted leads which indicates V-37-9 is open.

Open Not Open 1.2.5 E

V-37-9 is open, THEN no further action is required in this attachment.

1.2.6 V-37-9 is not open, THEN check a different recirculation loop for open suction and discharge valves.

156.0

OYSTER CREEK GENERATING

AmerGen, STATION PROCEDURE An Cmbn Company Title PLANT FIRE ATTACHMENT AB N-29-2 (con tin ued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES Number ABN-29 Revision No.

9 2.0 Recirculation Loop B 2.1 V-37-21, B Recirculation Loop Discharne valve in MCC 1 B21A, Unit A03

[ref. GE 15786350 Sh 347) 2.1.1 Open the breaker for the B Recirculation Loop Discharge Valve, V-37-21 on MCC 1B21A.

2.1.2 Remove the control power fuse for B Recirculation Loop Discharge valve, V-37-21.

Removed By:

Verified By:

Lift the following leads for the V-37-21 closed limit switch from the terminal strip in Unit A03 (cable 22-384).

2.1.3 TB-1 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

2.1.4 Check for no continuity through the V-37-21 closed limit switch lifted leads which indicates V-37-21 is open.

Open Not Open 2.1.5 E

V-37-21 is open, THEN check that the B Recirculation Loop Suction valve, V-37-20 is open.

2.1.6 V-37-21 is not open, THEN Check a different recirculation loop for open suction and discharge valves.

157.0

OYSTER CREEK GENERATING STATION PROCEDURE

AmerGen, An Excbn Company Title PLANT FIRE ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES Number ABN-29 Revision No.

9 2.2 V-37-20, B Recirculation LOOP Suction valve in MCC 1 B21A, Unit A01

{ref. GE 157B6350 Sh 346) 2.2.1 2.2.2 2.2.3 2.2.4 2.2.5 2.2.6 Open the breaker for the B Recirculation Loop Suction Valve, V-37-20 on MCC I B21A.

Remove the control power fuse for B Recirculation Loop Suction valve, V-37-20.

Removed By:

Verified By:

Lift the following leads for the V-37-20 closed limit switch from the terminal strip in Unit A01 (cable 22-382).

I TB-1 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

Check for no continuity through the V-37-20 closed limit switch lifted leads which indicates V-37-20 is open.

Open Not Open IF V-37-20 is open, THEN no further action is required in this attachment.

IF V-37-20 is not open, THEN check a different recirculation loop for open suction and discharge valves.

158.0

OYSTER CREEK GENERATING An fxeiori Company STATION PROCEDURE Number ABN-29 ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES I

Title

J PLANT FIRE 3.0 Recirculation Loo0 C Revision No.

9 3.1 V-37-32, C Recirculation Loop Discharae valve in MCC 1A21A. Unit BO1 lref. GE 157B6350 Sh 328) 3.1.I Open the breaker for the C Recirculation Loop Discharge Remove the control power fuse for C Recirculation Loop Discharge valve, V-37-32.

Removed By:

Verified By:

Lift the following leads for the V-37-32 closed limit switch from the terminal strip in Unit BO1 (cable 22-377).

I Valve, V-37-32 on MCC 1A21A.

3.1.2 3.1.3 TB-1 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

3.1.4 Check for no continuity through the V-37-32 closed limit switch lifted leads which indicates V-37-32 is open.

Open Not Open 3.1.5 V-37-32 is open, THEN check that the C Recirculation Loop Suction valve, V-37-31 is open.

3.1.6 V-37-32 is not open, THEN check a different recirculation loop for open suction and discharge valves.

159.0

OYSTER CREEK GENERATING STATION PROCEDURE AmerGm An Extion Company Title PLANT FIRE Number ABN-29 Revision No.

9 ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES 3.2 V-37-31, C Recirculation Loor, Suction valve in MCC 1A21A. Unit A02 (ref. GE 157B6350 Sh 326) 3.2.1 3.2.2 Open the breaker for the C Recirculation Loop Suction Valve, Remove the control power fuse for C Recirculation Loop Suction valve, V-37-31.

Removed By:

Verified By:

Lift the following leads for the V-37-31 closed limit switch from the terminal strip in Unit A02 (cable 22-374).

TB-I I

V-37-31 on MCC 1A21A.

3.2.3 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

3.2.4 Check for no continuity through the V-37-31 closed limit switch lifted leads which indicates V-37-31 is open.

Open Not Open 3.2.5 V-37-31 is open, THEN no further action is required in this attachment.

3.2.6 V-37-31 is not open, THEN check a different recirculation loop for open suction and discharge valves.

160.0

OYSTER CREEK GENERATING STAT1 0 N P ROC ED U RE

AmerGen, an fxebn Cwnpany Title PLANT FIRE i--

Number ABN-29 Revision No.

9 ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES 4.0 Recirculation LOOP D 4.1 V-37-43, D Recirculation LOOP Discharae valve in MCC 1B21A, Unit A04 fref. GE 15766350 Sh 347) 4.1.1 4.1.2 Open the breaker for the D Recirculation Loop Discharge Valve, V-37-43 on MCC I B21A.

Remove the control power fuse for D Recirculation Loop Discharge valve, V-37-43.

1 Removed By:

Verified By:

Lift the following leads for the V-37-43 closed limit switch from the terminal strip in Unit A04 (cable 22-385).

4.1.3 TB-I Removed By:

Verified By:

TB-60 Removed By:

Verified By:

4.1.4 Check for no continuity through the V-37-43 closed limit switch lifted leads which indicates V-37-43 is open.

Open Not Open 4.1.5 V-37-43 is open, THEN check that the D Recirculation Loop Suction valve, V-37-42 is open.

4.1.6 E

V-37-43 is not open, THEN check a different recirculation loop for open suction and discharge valves.

161.O

OYSTER CREEK GENERATING Ah E X C h C0mFdn)t STATION PROCEDURE

--I Number ABN-29 ATTACHMENT ABN-29-2 (continued)

DETERMINING OPEN RECIRCULATION LOOP ISOLATION VALVES 4.2 V-37-42. D Recirculation LOOD Suction valve in MCC 1B21A, Unit A02

{ref. GE 157B6350 Sh 346) 4.2.1 Open the breaker for the D Recirculation Loop Suction Valve, V-37-42 on MCC 1 B21A.

4.2.2 Remove the control power fuse for D Recirculation Loop Suction valve, V-37-42.

Removed By:

Verified By:

Lifi the following leads for the V-37-42 closed limit switch from the terminal strip in Unit A02 (cable 22-383).

4.2.3 TB-1 Removed By:

Verified By:

TB-60 Removed By:

Verified By:

4.2.4 Check for no continuity through the V-37-42 closed limit switch lifted leads which indicates V-37-42 is open.

Open Not Open 4.2.5 V-37-42 is open, THEN no further action is required in this attachment.

4.2.6 E

V-37-42 is not open, THEN check a different recirculation loop for open suction and discharge valves.

162.0

ML063070146

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ML063070146

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