ML17191A393

Pseg Handouts for July 13, 2017 Public Meeting on TSTF-542 Proposed License Amendment Request

ML17191A393
Person / Time
Site:	Hope Creek
Issue date:	07/10/2017
From:	Public Service Enterprise Group
To:	Regner L M Plant Licensing Branch 1
Regner L, NRR/DORL/LPL1, 415-1906
References
Download: ML17191A393 (45)

Text

INSERT 1 DRAIN TIME 1.11.1The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a) The water inventory above the TAF is divided by the limiting drain rate; b) The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single human error), for all penetration flow paths below the TAF except:

1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or

3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power. c) The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory;

d) No additional draining events occur; and e) Realistic cross

-sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in lieu of a calculated value.

TABLE 3.3.2-1 TRIP FUNCTION 1. PRIMARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level 1) Low Low, Level 2 2) Low low Low, Level 1 ISOLATION ACTUATION INSTRUMENTATION VALVE TION GROUPS MINIMUM OPERATED BY OPERABLE CHANNELS SIGNAL PER TRIP SYSTEM (a) 2, 8, 9, 12,13, 15,17,18 10, 11, 15, 16 2 2 APPLICABLE OPERATIONAL CONDITION 1,2.3 1.2,3 ACTION 20 20 b. Drywell Pressure -High 8,9, 10, 11,12,13, 14,15.16.

17.18 20) 1,2,3 20 c. Reactor Building Exhaust Radiation

-High 8. 9, 12 13.14.15, 17,18 3 1.2.3 28 2. d. Manual Initiation SECONDARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level -Low Low. Level 2 8, 9, 10 11.12.13.

14.15.16.

17.18 19(C) 1 2 1,2,3 1.2,3 and

• 24 26 b. Drywell Pressure -High 19(C l 20) 1,2.3 26 c. Refueling Floor Exhaust Radiation

-High 1 3 1,2,3 and

• 29 d. Reactor Building Exhaust Radiation

-High 19(C) 3 1,2.3 and

• 28 e. Manual Initiation 19(C) 1,2,3 and

• 26 HOPE CREEK 3/43-11 Amendment No. 193

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

• ** (a) (b) (c) When handling recently irradiated fuel in the secondary containment and during operations with a potential for draining the reactor vessel. When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.

Manual initiation switches shall be tested in accordance with the Surveillance Frequency Control Program. All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST in accordance with the Surveillance Frequency Control Program as part of circuitry required to be tested for automatic system isolation.

Each train or logic channel shall be tested in accordance with the Surveillance Frequency Control Program. Frequencies are specified in the Surveillance Frequency Control Program unless otherwise noted in the table. HOPE CREEK 3/4 3-31 Amendment No. 187

• • • TABLE 3.3.3-1 EMERGENCY CORE COOlING SYSTEM ACTUATION INSTRUMENTATION

I: 0 MINIMlIt OPERABLE"V m.CHANNELS PER APPLICABLE n TRIP OPERATIONAL

D m TRIP FUNCTION FUNCTION(a)

CONDITIONS ACTION'"------1.CORE*SPRAY SYSTEM a.Reactor Vessel Water level-low low low, level 1 2(b)(e)I, 2, 3,4*, 5*30 b.Drywell Pressure-High 2(b)(e)1,.2, 3.30 c.Reactor Vessel Pressure-low (Perllissive) 4/div.ision(f) 1,2, 3 31 Core Spray Pu.p Discharge Flow-low (Bypass)4*,5*32 d.l/subsyste.

I, 2, 3, 4*, 5*37 e.Core Spray P.-p Start Ti.Delay-NonNl Power l/subsyste.

I, 2, 3, 4*, 5*31 f.Core Spray Pu.p Start Ti.Delay-Power l/subsystell 1.2.3.4*, 5*31 g.Manual Initiation l/division(b)(g)

I, 2, 3.4*.5*33 2.LOW PRESSURE COOLANT INJECTION MOOEOFRHR SYSTEM w Reactor Vessel Water level-Low Low low.level 1......a.2/valve 1, 2, 3.4*, 5*30....w b.Drywell Pressure-High 2/valve I, 2, 3 30*c.Reactor Vessel Pressure-Low (Perlliss;ve) lIvalve 1,2.3 31 w w 4*, 5*32 d.lPCIPu-p Discharge Flow-Low (Bypass)lIPUllp(i) 1.2.3.4*, 5*37 e.lPCI Pu.p Start Ti.Delay- Power l/ptllp I, 2, 3.4*, 5*31 f.Manual Initiation l/subsyste.

1, 2, 3, 4*.5*33 3.HIGH PRESSURE COOlANT INJECTION a.Reactor Vessel Water level-low low Level 2 4 I, 2, 3 34 b.

Pressure-High 4(c)1.2, 3 34 c.Condensate Storage Tank level-Low 2(e)I, 2, 3 35.--'d.Suppression Pool Water level-High 2(d)I, 2,3 35 e.Reactor Vessel.Water

-High.level 8 4 I, 2, 3 31 f.HPCI PUIIIP Discharge Flo.J-low (Bypass)1 1,2, 3 31 g.Manual Initiation l/systH 1, 2, 3 33 4.AUTOMATIC DEPRESSURIZATION SYSTEMIf-a.Reactor Vessel Water level-Low low low, level 1 4 I, 2.3 30.b.Drywell Pressure-High 4 1.2, 3 30 c.ADS Tiller Z I.2.3 31 d.Core Spray Pump Discharge Pressure-H6ghI, Z, 3 31

INSTRUMENTATION 3/4.3.3.1 RPV WATER INVENTORY CONTROL INSTRUMENTATION LIMITING CONDITION FOR OPERATION

3.3.3.1 The RPV Water Inventory Control (WIC) actuation instrumentation channels shown in Table 3.3.3.1-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3

.1-2. APPLICABILITY: As shown in Table 3.3.3.1-1 ACTION: a. With an RPV Water Inventory Control actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value. b. With one or more channels inoperable, take the ACTION referenced in Table 3.3.3.1-1 for the channel immediately.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each RPV Water Inventory Control (WIC) actuation instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and LOGIC SYSTEM FUNCTIONAL TEST at the frequencies shown in Table 4.3.3.1.1-1.

HOPE CREEK 3/4 3-40a Amendment No. XXX TABLE 3.3.3.1-1 RPV WATER INVENTORY CONTROL INSTRUMENTATION MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL FUNCTION CONDITIONS ACTIONS TRIP FUNCTION ACTION 1. CORE SPRAY SYSTEM

a. Reactor Vessel Pressure - Low (Permissive) 4/division(c) 4, 5 83 b. Core Spray Pump Discharge Flow - Low (Bypass) 1/subsystem(a) 4, 5 84 c. Manual Initiation 1/subsystem(a) 4, 5 84 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a. Reactor Vessel Pressure-Low (Permissive) 1/valve 4, 5 83 b. LPCI Pump Discharge Flow - Low (Bypass) 1/pump(a) 4, 5 84 c. Manual Initiation 1/subsystem(a) 4, 5 84 3. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

a. Reactor Vessel Water Level Low - Level 3 2 (b) 85 4. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. Reactor Vessel Water Level - Low Low, Level 2 2 (b) 85

___________________________

(a) (b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

(c) Division 1 and 2 only.

HOPE CREEK 3/4 3-40b Amendment No. XXX

TABLE 3.3.3.1-1 (Continued) RPV WATER INVENTORY CONTROL INSTRUMENTATION ACTIO N ACTION 83 - Place the channel in trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Otherwise, immediately declare the associated low pressure ECCS injection/spray subsystem inoperable.

ACTION 84 - Restore the channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, immediately declare the associated low pressure ECCS injection/spray subsystem inoperable.

ACTION 85 - Declare the associated flow path(s) incapable of automatic isolation and calculate DRAIN TIME immediately.

HOPE CREEK 3/4 3-40c Amendment No.XXX

TABLE 3.3.3.1-2 RPV WATER INVENTORY CONTROL INSTRUMENTATION SETPOINTS TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE 1. CORE SPRAY SYSTEM

a. Reactor Vessel Pressure Low (Permissive) 4 61 psig 4 81 psig b. Core Spray Pump Discharge Flow

- Low (Bypass) 775 gpm 650 gpm c. Manual Initiation N.A. N.A. 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Reactor Vessel Pressure Low (Permissive)

< 45 0 psig 4 40 psig, b. LPCI Pump Discharge Flow Low (Bypass) 1250 gpm , 1100 gpm c. Manual Initiation N.A. N.A. 3. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

a. Reactor Vessel Water Level Low - Level 3 12.5 inches* 11.0 inches 4. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. Reactor Vessel Water Level - Low, Low, -

Level 2 -38 inches* -45 inches

• See Bases Figure B 3/4.3-

1.

HOPE CREEK 3/4 3-40d Amendment No. xxx

TABLE 4.3.3.

1.1-1 RPV WATER INVENTORY CONTROL INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP FUNCTI ON CHANNEL CHECK(a) CHANNEL FUNCTIONAL TEST (a) LOGIC SYSTEM FUNCTIONAL TEST (a) OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1. CORE SPRAY SYSTEM

a. Reactor Vessel Pressure Low (Permissive)

N.A. 4, 5 b. Core Spray Pump Discharge Flow - Low (Bypass) N.A. 4, 5 c. Manual Initiation N.A. N.A. 4, 5 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Reactor Vessel Pressure Low (Permissive)

N.A. 4, 5 b. LPCI Pump Discharge Flow Low (Bypass) N.A. 4, 5 c. Manual Initiation N.A. N.A. 4, 5 3. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a. Reactor Vessel Water Level Low - Level 3 N.A. (b) 4. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. Reactor Vessel Water Level

- Low, Low - Level 2 N.A. (b) (a) Frequencies are specified in the Surveillance Frequency Control Program unless otherwise noted in the table.

(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

HOPE CREEK 3/4 3-40e Amendment No. xxx

TABLE RADIATION MONITORING INSTRUMENTATION SURVEILLANCE INSTRUMENTATION CHANNEL CHECK (a) CHANNEL FUNCTIONAL TEST (a) CHANNEL CALIBRATION (a) OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1. Control Room Ventilation Radiation Monitor 1,2,3, and

• 2. Area Monitors a. Criticality Monitors 1) New Fuel Storage Vault # 2) Spent Fuel Storage Pool ## b. Control Room Direct Radiation Monitor At all times 3. Reactor Auxiliaries Cooling Radiation Monitor At all times 4. Safety Auxiliaries Cooling Radiation Monitor At all times 5. Offgas Pre-treatment Radiation Monitor ** HOPE CREEK 3/43-66 Amendment No 187.

INSERT 2 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND RPV WATER INVENTORY CONTROL LIMITING CONDITION FOR OPERATION (Continued)

ACTION: c. With , within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:

1. Verify secondary containment boundary is capable of being established in less than the DRAIN TIME, AND 2. Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME , AND 3. Verify one Filtration, Recirculation and Ventilation (FRVS) ventilation unit is capable of being placed in operation in less than the DRAIN TIME.

Otherwise, IMMEDIATELY initiate

d. With DRAIN TIME < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, IMMEDIATELY:

1. Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water *** AND, 2. Initiate action to establish secondary containment boundary, AND 3. Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room, AND 4. Initiate action to verify one FRVS ventilation unit is capable of being placed in operation.

e. With DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, IMMEDIATELY initiate action to restore

_________________

• • • Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.

INSERT 3 Program. 4.5.2.2 Verify, for a required low pressure coolant injection (LPCI) subsystem, the suppression chamber indicated water level is > 5.0 inches in accordance with the Surveillance Frequency Control Program.

4.5.2.3 Verify, for a required Core Spray (CS) subsystem, the Suppression chamber indicated water level is > 5.0 inches or condensate storage tank contains at least 135,000 available gallons of water in accordance with the Surveillance Frequency Control Program.

4.5.2.4 Verify, for the required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve in accordance with the Surveillance Frequency Control Program.

4.5.2.5 Verify, for the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position, in accordance with the Surveillance Frequency Control Program. #

4.5.2.6 Operate the required ECCS injection/spray subsystem through the recirculation line for , in accordance with the Surveillance Frequency Control Program.

4.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal, in accordance with the Surveillance Frequency Control Program 4.5.2.8 Verify the required ECCS injection/spray subsystem actuates on a manual initiation signal, in accordance with the Surveillance Frequency Control Program.

1. 1. _______________

1. Except that an automatic valve capable of automatic return to its ECCS position when an ECCS signal is present may be in position for another mode of operation.

1. 1. Vessel injection/spray may be excluded.

CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR QPERATION 3.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be APPLICABILITY:

OPERATIONAL CONDITIONS 1,2,3 and Without SECONDARY CONTAINMENT

a. In OPERATIONAL CONDITION 1,2 or 3, restore SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. b. In Operational Condition

• , suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.

4.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by: Verifying in accordance with the Surveillance Frequency Control Program that the reactor building is at a negative pressure. Verifying in accordance with the Surveillance Frequency Control Program that: All secondary containment equipment hatches and blowout panels are closed and sealed. a. For double door arrangements, at least one door in each access to the secondary containment is closed. For single door arrangements, the door in each access to the secondary containment is closed except for routine entry and exit. All secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic isolation dampers/valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers/valves secured in position. When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel. HOPE 3/46-47 Amendment No. 187 CONTAINMENT SYSTEMS SECONDARY CONTAI NM ENT AUTOMATIC ISOLATION DAMPERS LIMITING CONDITION FOR OPERATION 3.6.5.2 The secondary containment ventilation system (RBVS) automatic isolation dampers shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.5.2-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *. ACTION: With one or more of the secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.2-1 inoperable, maintain at least one isolation damper OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either: a. Restore the inoperable dampers to OPERABLE status, or b. Isolate each affected penetration by use of at least one deactivated damper secured in the isolation position, or c. Isolate each affected penetration by use of at least one closed manual valve or blind flange. Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, in Operational Condition

• , suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.5.2 Each secondary containment ventilation system automatic isolation damper shown in Table 3.6.5.2-1 shall be demonstrated OPERABLE: Prior to returning the damper to service after maintenance, repair or replacement work is performed on the damper or its associated actuator, control or power circuit by cycling the damper through at least one complete cycle of full travel and verifying the specified isolation time. In accordance with the Surveillance Frequency Control Program by verifying that on a containment isolation test signal each isolation damper actuates to its isolation pOSition. By verifying the isolation time to be within its limit in accordance with the Surveillance Frequency Control Program.

• When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel. HOPE 3/46-49 Amendment No. 187 CONTAINMENT SYSTEMS 3.6.5.3 FILTRATION, RECIRCULATION AND VENTILATION SYSTEM (FRVS) FRVS VENTILATION SUBSYSTEM LIMITING CONDITIONFQR OPERATION 3.6.5.3.1 Two FRVS ventilation units shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *. ACTION: With one of the above required FRVS ventilation units inoperable, restore the inoperable unit to OPERABLE status within 7 days, or: In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In Operational Condition

• , place the OPERABLE FRVS ventilation unit in operation or suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable. With both ventilation units inoperable in Operational Condition

• , suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3. are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.5.3.1 Each of the two ventilation units shall be demonstrated OPERABLE: In accordance with the Surveillance Frequency Control Program by verifying that the water seal bucket traps have a water seal and making up any evaporative losses by filling the traps to the overflow. In accordance with the Surveillance Frequency Control Program by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 15 minutes.

• When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel. HOPE 3/46-51 Amendment No. 187 CONTAI NIVIENT 3.6.5.3 FILTRATION, RECIRCULATION AND VENTILATION SYSTEM (FRVS) FRVS RECIRCULATION SUBSYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.3.2 Six FRVS recirculation units shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *. ACTION: With one or two of the above required FRVS recirculation units inoperable, restore all the inoperable unit(s) to OPERABLE status within 7 days, or: In OPERATIONAL CONDITION 1,2, or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In Operational Condition*, suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable. With three or more of the above required FRVS recirculation units inoperable in Operational Condition

• , suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable. With three or more of the above required FRVS recirculation units inoperable in OPERATIONAL CONDITION 1,2, or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. SURVEILLANCE REQUIREMENTS 4.6.5.3.2 Each of the six FRVS recirculation units shall be demonstrated OPERABLE: In accordance with the Surveillance Frequency Control Program by verifying that the water seal bucket traps have a water seal and making up any evaporative losses by filling the traps to the overflow. In accordance with the Surveillance Frequency Control Program by initiating, from the control room, flow through the HEPA filters and verifying that the subsystem operates for at least 15 minutes. When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel. HOPE 3/46-52a Amendment No. 187 PLANT SYSTEMS 3/4.7.2 CONTROL ROOM SYSTEMS

CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2.1 Two control room emergency filtration system subsystems shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and *.

ACTION: a. In OPERATIONAL CONDITION 1, 2 or 3

1. With one control room emergency filtration subsystem inoperable for reasons other than Condition a.2, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. With one or more control room emergency filtration subsystems inoperable due to an inoperable control room envelope (CRE) boundary##, a. Immediately, initiate action to implement mitigating actions; and

b. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, verify mitigating actions ensure CRE occupant exposures to radiological and chemical hazards will not exceed the limits and actions to mitigate exposure to smoke hazards are taken; and

c. Within 90 days, restore the CRE boundary to operable status; Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERATIONAL CONDITION *:

1. With one control room emergency filtration subsystem inoperable for reasons other than Condition b.3, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the pressurization/recirculation mode of operation.

• When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel.

1. 1. The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

HOPE CREEK 3/4 7-6 Amendment No. 191 PLANT SYSTEMS CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION (continued)

2. With both control room emergency filtration subsystems inoperable for reasons other than Condition b.3, suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. 3. With one or more control room emergency filtration subsystems inoperable due to an inoperable CRE boundary##, immediately suspend handling of recently irradiated fuel and operations with a potential for draining the vessel. c. The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION*.

SURVEILLANCE REQUIREMENTS 4.7.2.1.1 Each control room emergency filtration subsystem shall be demonstrated OPERABLE:

• ## a. DELETED b. In accordance with the Surveillance Frequency Control Program by verifying that the subsystem operates for at least 15 continuous minutes with the heaters on. When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel. The main control room envelope (CRE) boundary may be opened intermittently under administrative control. HOPE CREEK 3/4 7-6a Amendment No. 199 PLANT SYSTEMS CONTROL ROOM AIR CONDITIONING (AC) SYSTEM

LIMITING CONDITION FOR OPERATION 3.7.2.2 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and *.

ACTION:

a. In OPERATIONAL CONDITION 1, 2 or 3:

1. With one control room AC subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. With two control room AC subsystems inoperable:

a. Verify control room air temperature is less than 90°F at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and

b. Restore one control room AC subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERATIONAL CONDITION *:

1. With one control room AC subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days; or place the OPERABLE control room AC subsystem in operation; or immediately suspend movement of recently irradiated fuel assemblies in the secondary containment and initiate action to suspend operations with a potential for draining the reactor vessel. 2. With two control room AC subsystems inoperable, immediately suspend movement of recently irradiated fuel assemblies in the secondary containment and initiate action to suspend operations with a potential for draining the reactor vessel.

3. The provisions of Specification 3.0.3 are not applicable in Operational Condition *.

• When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel.

HOPE CREEK 3/4 7-8a Amendment No.191

\*ELECTRICAL POWER SYSTEMS A.C.SOURCES-SHUTDOW}T LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C.electrical power sources shall be OPERABLE: a.One circuit the transmission network and the onsite Class IE distribution system, and b.Two diesel generators, one of which shall be diesel generator A or diesel generator a, each with: 1.2.3.A separate fuel oil day tank containing a minimum of 360 gallons of fuel.A fuel storage system consisting of two storage tanks containing a minimum of 44,800 gallons of fuel.A separate fuel transfer pump for each storage tank.*APPLICABILITY:

OPERATIONAL CONDITIONS 4, 5 and*ACTION: a.With less than the above required A.C.electrical power sources OPERABLE, suspend CORE ALTERATIONS, handling of recently irradiated fuel in the'secondary containment,'

operations with a potential for draining the reactor vessel and crane operations over the spent fuel storage pool when fuel assemblies are stored therein.In addition, when in OPERATIONAL CONDITION 5 with the water level than 22'-2" above the reactor pressure vessel flange, immediately initiate corrective action to restore the required power sources to OPERABLE status as soon as practical.

b.The provisions of Specification 3.0.3 are not applicable:

c.With one fuel oil transfer pump inoperable, realign the flowpath of the affected tank to the tank with the remaining operable fuel oil transfer pump within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and restore the inoperable transfer pump to OPERABLE status within 14 days, otherwise declare the affected emergency diesel generator (EDG)inoperable.

This variance may be applied to only one EDG at a time.SURVEILLANCE REQUIREMENTS 4.8.1.2 At least the above required A.C.electrical power sources shall be demonstrated OPERABLE per Surveillance Requirements 4.8.1.1.1, 4.8.1.1.2, and 4.8.1.1.3, except for the requirement of 4,8.1.1.2.a.5.

• When handling recently irradiated fuel in the secondary containment

.*HOPE CREEK 3/4 8-11 Amendment No.170

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ELECTRICAL POWER SYSTEMS D.C.SOURCES-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, two of the following four channels of the D.C.electrical power sources, one of which shall be channel A or channel B, shall be OPERABLE with: a.Channel A, consisting of: 1.125 volt battery 1AD411 2.125 volt full capacity charger#1AD413 or 1AD414 b.Channel B, consisting of: 1.125 volt battery 1BD411 2.125 volt full capacity charger#1BD413 or 1BD414.c.Channel C, consisting of: 1.125 volt battery 1CD411 2.125 volt full capacity charger#1CD413 or 1CD414 3.125 volt battery 1CD447 4.125 volt full capacity charger 1CD444 d.Channel D, consisting of: 1.125 volt battery 1DD411 2.125 volt full capacity charger#1DD413 or 1DD414 3.125 volt battery 1DD447 4.125 volt full capacity charger 1DD444 APPLICABILITY:

OPERATIONAL CONDITIONS 4, 5 and*ACTION: a.with less than two channels of the above required D.C.electrical power sources OPERABLE, suspend CORE ALTERATIONS, handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.b.The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.8.2.2 At least the above required battery and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.1.*When handling recently irradiated fuel in the secondary containment.

1. Only one full capacity charger per battery is required for the channel to be OPERABLE.HOPE CREEK 3/4 8-17 Amendment No.170

• ELECTRICAL POWER SYSTEMS DISTRIBUTION

-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, 2 of the 4 channels, one of which shall be channel A or channel B, of the power distribution system shall be energized with: a.A.C.power distribution:

• • 1.2.3.Channel At consisting of: a)4160 volt A.C.switchgear bus b)480 volt A.C.load centers c)480 volt A.C.MCCs d)208/120 volt A.C.distribution panels e)120 volt A.C.distribution panels Channel B t consisting of: a)4160 volt A.C.switchgear bus b)480 volt A.C.load centers c)480 volt A.C.MCCs d)208/120 volt A.C.distribution panels e)120 volt A.C.distribution panels Channel C, consisting of: a)4160 volt A.C.switchgear bus b)480 volt A.C.load centers c)480 volt A.C.MCCs d)208/120 volt A.C.distribution panels lOA401 108410 108450 108212 108411 108451 108553 10Y401(source:10B411) 10Y411(source:lOB451) 10Y501(source:lOB553) lAJ481 1YF401(source:1AJ481) lAJ482 10A402 108420 108460 108222 108421 10B461 108563 10Y402(source:10B421) 10Y412(source:10B461) 10YS02(source:l0B563) 1BJ481 1YF402(source:lBJ481) 18J482 10A403 108430 108470 108232 10B431 108471 10B573 10Y403(source:108431) 10Y413(source:l08471) 10Y503(source:lOB573)

HOPE CREEK 3/4 8-21 ELECTRICAL POWER SYSTEMS*LIMITING CONDITION FOR OPERATION (Continued) e)120 volt A.C.distribution panels 1CJ481 lYF403(source:lCJ481) lCJ482 4.Channel 0, consisting of: a)4160 volt A.C.switchgear bus lOA404 b)480 volt A.C.load centers 108440 108480 c)480 volt A.C.MCCs 10B242 108441 108481 108583 d)208/120 volt A.C.distribution panels lOY404(source:l08441) lOY414(source:lOB481) 10Y504(source:lOB583) e)120 volt A.C.distribution panels ID.JMn 1YF404(source:10J481)

IDJ482 b.D.C.power distribution:

1.Channel A, consisting of:*a)125 volt D.C.switchgear 100410 b)125 volt D.C.fuse box 1AD412 c)125 volt D.C.distribution panel 1AD417 2.Channel B, consisting of: a)125 volt D.C.switchgear 100420 b)125 volt D.C.fuse box 180412 c)125 volt D.C.distribution panel 1BD417 3.Channel C, consisting of: a)125 volt D.C.switchgear 100430 100436 b)125 volt D.C.fuse boxes lCD412 lCD448 c)125 volt D.C.distribution panel 1CD417 4.Channel D.consisting of: a)125 volt D.C.switchgear 100440 100446 b)125 volt D.C.fuse box 100412 100448 c)125 volt D.C.distribution panel 100417*HOPE CREEK 3/4 8-22 ELECTRICAL POWER LIMITING CONDITION FOR OPERATION APPLICABILITY:

OPERATIONAL CONDITIONS 4, 5 and With less than two channels of the above required A.C. distribution system energized, suspend CORE ALTERATIONS, handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. With less than two channels of the above required D.C. distribution system energized, suspend CORE ALTERATIONS, handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.8.3.2 At least the above required power distribution system channels shall be determined energized in accordance with the Surveillance Frequency Control Program by verifying correct breaker/switch alignment and voltage on the busses/MCCs/panels.

• When handling recently irradiated fuel in the secondary HOPE CREEK 3/48-23 Amendment No. 187