ML070470474

Seabrook Station Unit 1, Technical Specifications, Issuance of Amendment Mode Change Limitations (TAC No. MD1515)

ML070470474
Person / Time
Site:	Seabrook
Issue date:	02/09/2007
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
References
TAC MD1515
Download: ML070470474 (26)

Text

-3-(4) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;(5) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein; and (7) DELETED C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level FPL Energy Seabrook, LLC, is authorized to operate the facility at reactor core power levels not in excess of 3648 megawatts thermal (100% of rated power).(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 114 *, and the Environmental Protection Plan contained in Appendix B are incorporated into the Facility License No. NPF-86.FPL Energy Seabrook, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.(3) License Transfer to FPL Energy Seabrook, LLC a. On the closing date(s) of the transfer of any ownership interests in Seabrook Station covered by the Order approving the transfer, FPL Energy Seabrook, LLC, shall obtain from each respective transferring owner all of the accumulated decommissioning trust funds for the facility, and ensure the deposit of such funds and additional funds, if necessary, into a decommissioning trust or trusts for Seabrook Station established by FPL Energy Seabrook, LLC, such that the amount of such funds deposited meets or exceeds the amount required under 10 CFR 50.75 with respect to the interest in Seabrook Station FPL Energy Seabrook, LLC, acquires on such dates(s).* Implemented AMENDMENT NO. 114 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met, except as provided in Specification 3.0.5.3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals, except as provided in Specification 3.0.5. If the Limiting Condition for Operation is restored prior to-expiration of the specified time intervals, completion of the ACTION requirements is not required.3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: a. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made: a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or SEABROOK -UNIT 1 3/4 0-1 Amendment No. &-7, 114 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.4 (Continued)

c. When an allowance is stated in the individual value, parameter or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.

This is an exception to Specifications 3.0.1 and 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

SURVEILLANCE REQUIREMENTS

4.0.1 Surveillance

Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limiting Condition for Operation.

Failure to perform a Surveillance within the specified surveillance interval shall be failure to meet the Limiting Condition for Operation except as provided in Specification

4.0.3. Surveillances

do not have to be performed on inoperable equipment or variables outside specified limits.4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.4.0.3 If it is discovered that a Surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified surveillance interval, whichever is greater. This delay period is permitted to allow performance of the Surveillance.

A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be entered.When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be entered.SEABROOK -UNIT 1 3/4 0-2 Amendment No. 69,,87, 114 APPLICABILITY SURVEILLANCE REQUIREMENTS

4.0.4 Entry

into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Specification 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with Specification 3.0.4.This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows: a. Inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i).

Inservice testing of ASME Code Class 1, 2, and 3 components shall be performed in accordance with the Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(f), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(f)(6)(i).

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and the ASME OM Code including applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and the ASME OM Code including applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and the ASME OM Code including applicable Addenda terminology for inservice inspection and testing activities Weekly Monthly Semi-quarterly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years Required frequencies for performing service Inspection and testing activities.

At least once per 7 days At least once per 31 days At least once per 46 days At least once per 92 days At least once per 184 days At least once per 276 days At least once per 366 days At least once per 731 days SEABROOK -UNIT 1 3/40-3 Amendment No. 69,11:4.

APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.5 (Continued)

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities;

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements; and e. Nothing in the ASME Boiler and Pressure Vessel Code or the ASME OM Code shall be construed to supersede the requirements of any Technical Specification.

SEABROOK -UNIT 1 314 0-4 Amendment No. 114 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE 2 1 2 2 1 2 FUNCTIONAL UNIT 1. Manual Reactor Trip APPLICABLE MODES 1,2 3*, 4*, 5*ACTION 1 10 2. Power Range, Neutron Flux a. High Setpoint b. Low Setpoint 3. Power Range, Neutron Flux High Positive Rate 4. (NOT USED)5. Intermediate Range, Neutron Flux 6. Source Range, Neutron Flux a. Startup b. Shutdown c. Shutdown 7. Overtemperature AT 8. Overpower AT 9. Pressurizer Pressure--Low

10. Pressurizer Pressure--High

11. Pressurizer Water Level--High 4 4 4 2 2 2 2 2 2 2 4 4 4 4 3 1 1 0 1 2 2 2 2 2 1,2 1##, 2 1,2 1##, 2 2#3,4,5 3*, 4*, 5*1,2 1,2 1 **1,2 1 **2 2 2 3 4 5 10 6 6 6 6 6 SEABROOK -UNIT 1 3/4 3-2 Amendment No. 6,6-91-, 114 TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TOTAL NO.OF CHANNELS FUNCTIONAL UNIT 12. Reactor Coolant Flow-Low a. Single Loop (Above P-8)3/loop 3/loop b. Two Loops (Above P-7 and below P-8)13. Steam Generator Water Level--Low--Low 4/stm. gen.CHANNELS TO TRIP 2/loop in any oper-ating loop 2/loop in two oper-ating loops 2/stm. gen.in any oper-ating stm.gen.2-1/bus 2-1/bus 2 4 1 1 14. Undervoltage--Reactor Coolant Pumps 15. Underfrequency--Reactor Coolant Pumps 16. Turbine Trip a. Low Fluid Oil Pressure b. Turbine Stop Valve Closure 17. Safety Injection Input from ESF 18. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 4-2/bus 4-2/bus 3 4 2 2 MINIMUM CHANNELS APPLICABLE OPERABLE MODES 2/loop in each oper-ating loop 2/loop each oper-ating loop 3/stm. gen.each oper-ating stm.gen.2 on one bus 2 on one bus 2 4 2 2 ACTION 6 1,2 6 I I 6 1 **6 6 1, 1,2 6 11 7 8 SEABROOK -UNIT 1 3/4 3-3 Amendment No. 36, 114 TABLE 3.3-1 (Continued)

TABLE NOTATIONS*When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

• • Trip function automatically blocked or bypassed below the P-7 (At Power)Setpoint.Trip function automatically blocked below the P-9 (Reactor Trip/Turbine Trip Interlock)

Setpoint.# Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint.# # Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock)

Setpoint.ACTION STATEMENTS ACTION 1 -ACTION 2 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable Channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.SEABROOK -UNIT 1 3/4 3-5 Amendment No. 6, 114 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES FUNCTIONAL UNIT ACTION 1. Safety Injection (Reactor Trip, Feedwater Isolation, Start Diesel Generators, Phase "A" Isolation, Containment Ventilation Isolation, Emergency Feedwater, Service Water to Secondary Component Cooling Water Isolation, CBA Emergency Fan/Filter Actuation, and Latching Relay).a. Manual Initiation

b. Automatic Actuation Logic and Actuation Relays c. Containment Pressure--Hi-1

d. Pressurizer Pressure--Low 2 2 3 4 2 2 2 2 2 3 1,2,3,4 1,2,3,4 1,2,3 1,2, 3#17 13 18 18 18 e. Steam Line Pressure--Low SEABROOK -UNIT 1 3/steam line 2/steam line any steam line 2/steam line 1, 2, 3#3/4 3-16 3Amendment No. 36,114 TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TOTAL NO. CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES FUNCTIONAL UNIT 4. Steam Line Isolation (continued)

b. Automatic Actuation Logic and Actuation Relays c. Containment Pressure--

Hi-2 ACTION 2 3 1 2 1,2,3 1,2,3 2 2 20 18 18 18 d. Steam Line Pressure-Low

e. Steam Generator Pressure -Negative Rate-High 3/steam line 3/steam line 2/steam line any steam line 2/steam line any steam line 2/steam line 1, 2, 3#2/steam line 3*5. Turbine Trip a. Automatic Actuation Logic and Actuation Relays b. Steam Generator Water Level--High-High (P-14)6. Feedwater Isolation a. Steam Generator Water Level--High-High (P-14)b. Safety Injection 2 1 2 1,2 22 4/stm. gen.2/stm. gen.3/stm. gen.1,2 18 4/stm. gen.2/stm. gen.3/stm. gen.1,2 18 See Item 1. above for all Safety Injection initiating functions and requirements.

SEABROOK -UNIT 1 3/4 3-19 Amendment No. 45,114 TABLE 3.3-3 (Continued)

TABLE NOTATIONS#Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock)

Setpoint.* Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.ACTION STATEMENTS ACTION 13 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.ACTION 14 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and b. The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypased for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.ACTION 15 -With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.ACTION 16 -With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.ACTION 17 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.ACTION 18 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

SEABROOK -UNIT 1 3/4 3-22 Amendment No. 36,114 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS MINIMUM CHANNELS CHANNELS APPLICABLE ALARM/TRIP FUNCTIONAL UNIT TO TRIP/ALARM OPERABLE MODES SETPOINT ACTION 1. Containment

a. Containment-Post LOCA -1 2 All 10 R/h 27 Area Monitor b. RCS Leakage Detection 1) Particulate Radioactivity N.A. 1 1, 2, 3, 4 N.A. 26 2) Gaseous Radioactivity N.A. 1 1, 2, 3, 4 N.A. 26 2. Containment Ventilation Isolation a. On Line Purge Monitor 1 2 1,2,3,4

• 23 b. Manipulator Crane Area Monitor 1 2 6#** 23 3. Main Steam Line 1/steam line 1/steam 1,2, 3,4 N.A. 27 line 4. Fuel Storage Pool Areas a. Fuel Storage Building Exhaust Monitor N.A. 1* *** 25 5. Control Room Isolation a. Air-Intake-Radiation Level 1) East Air Intake 1/intake 2/intake All **** 24 2) West Air Intake 1/intake 2/intake All **** 24 6. Primary Component Cooling Water a. Loop A 1 1 All 2 x 28 Background

b. Loop B 1 1 All < 2 x 28 Background TABLE NOTATIONS*Two times background; purge rate will be verified to ensure compliance with ODCM Control C.7.1.1 requirements

• • Two times background or 15 mR/hr, whichever is greater.***With irradiated fuel in the fuel storage pool areas.****Two times background or 100 CPM, whichever is greater.#During CORE ALTERATIONS or movements of irradiated fuel within the containment.

SEABROOK-UNIT 1 3/4 3-37 Amendment No. 66, 114 INSTRUMENTATION MONITORING INSTRUMENTATION REMOTE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.5 The Remote Shutdown System transfer switches, power, controls and monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE.APPLICABILITY:

MODES 1, 2, and 3.ACTION: a. With the number of OPERABLE remote shutdown monitoring channels less than the Minimum Channels OPERABLE as required by Table 3.3-9, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in 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 />.b. With the number of OPERABLE remote shutdown monitoring channels less than the Total Number of Channels as required by Table 3.3-9, within 60 days restore the inoperable channel(s) to OPERABLE status or, pursuant to Specification 6.8.2, submit a Special Report that defines the corrective action to be taken.c. With one or more Remote Shutdown System transfer switches, power, or control circuits inoperable, restore the inoperable switch(s)

/ circuit(s) to OPERABLE status within 7 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel in Table 3.3-9 shall be demonstrated OPERABLE: a. Every 31 days by performance of a CHANNEL CHECK, and b. Every 18 months by performance of a CHANNEL CALIBRATION.

4.3.3.5.2 Each Remote Shutdown System transfer switch, power and control circuit listed in Table 3.3-9, including the actuated components, shall be demonstrated OPERABLE at least once per 18 months.SEABROOK -UNIT 1 3/4 3-46 Amendment No. 114 TABLE 3.3-9 (Continued)

INSTRUMENTATION MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.APPLICABILITY:

MODES 1, 2, and 3...........................................................

N O T E ........................................................

A separate ACTION entry is allowed for each INSTRUMENT listed in Table 3.3-10...,...ooo... ,o.. ...........

.o.............

,....... °. o,, ...... ,°.... .. ..... .....°. ,. , ...... *...... *...... o,,..................

ACTION: a. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel(s) to OPERABLE status within 30 days, or submit a Special Report to the Commission pursuant to Specification

6.8.2 within

the next 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation to OPERABLE status.b. With the number of OPERABLE accident monitoring instrumentation channels except the containment POST-LOCA high range area monitor, less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable channel(s) to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.c. With the number of OPERABLE channels for the containment Post-LOCA high range area monitor less than required by the Minimum Channels OPERABLE requirements, initiate an alternate method of monitoringthe appropriate parameter(s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and either restore the inoperable channel(s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission, pursuant to Specification 6.8.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status.SEABROOK -UNIT 1 3/4 3-49 Amendment No. 34, INSTRUMENTATION MONITORING INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.APPLICABILITY:

As shown in Table 3.3-13.ACTION: a. With an explosive gas monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification declare the channel inoperable and take the ACTION shown in Table 3.3-13.b. With the number of OPERABLE explosive gas monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.8.2 to explain why this inoperability was not corrected in a timely manner.c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.SEABROOK -UNIT 1 3/4 3-60 Amendment No. 22,-66, 114 REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 Both power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.APPLICABILITY:

MODES 1, 2, and 3.ACTION: a. With one or both PORV(s) inoperable, because of excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s);otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b. With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.c. With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or close each associated block valve and remove power from the block valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.d. With one or both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve(s) to OPERABLE status or place its associated PORV(s) control switch to"CLOSE". Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable; restore any remaining inoperable block valve 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.SEABROOK -UNIT 1 3/4 4-11 Amendment No. 4-6, 11.4 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the reactor coolant shall be limited to: a. Less than or equal to 1 microCurie per gram DOSE EQUIVALENT 1-131, and b. Less than or equal to 1OOI/ microCuries per gram of gross radioactivity.

APPLICABILITY:

MODES 1, 2, 3, 4, and 5.ACTION:---------------------

NOTE ----------------------

LCO 3.0.4.c is applicable to DOSE EQUIVALENT 1-131.MODES 1,2, and 3*: a. With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with Tavg less than 500OF within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and b. With the specific activity of the reactor coolant greater than 1 00/P microCuries per gram, be in at least HOT STANDBY with Tavg less than 500OF within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.MODES 1,2, 3, 4, and 5: With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT 1-131 or greater than 1 00/r microCuries per gram, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-3 until the specific activity of the reactor coolant is restored to within its limits.SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-3.*With Tavg greater than or equal to 500 0 F.SEABROOK -UNIT 1 3/4.4-27 Amendment No. 114 REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 The following Overpressure Protection Systems shall be OPERABLE: a. In MODE 4 when the, temperature of any RCS cold leg is less than or equal to 290°F; and in MODE 5 and MODE 6 with all Safety Injection pumps inoperable at least one of the following groups of two overpressure protection devices shall be OPERABLE when the RCS is not depressurized with an RCS vent area of greater than or equal to 1.58 square inches: 1) Two residual heat removal (RHR) suction relief valves each with a setpoint of 450 psig +0, -3 %; or 2) Two power-operated relief valves (PORVs) with lift setpoints that vary with RCS temperature which do not exceed the limit established in Figure 3.4-4, or 3) One RHR suction relief valve and one PORV with setpoints as required above.b. In MODE 5 and MODE 6 with all Safety Injection pumps except one inoperable:

1) The Reactor Coolant System (RCS) depressurized with an RCS vent area equal to or greater than 18 square inches, or 2) The RCS in a reduced inventory condition*.

APPLICABILITY:

MODE 4 when the temperature of any RCS cold leg is less than or equal to 290°F; MODE 5 and MODE 6 with the reactor vessel head on and the vessel head closure bolts not fully detensioned.

• A reduced inventory condition exists whenever reactor vessel (RV) water level is lower than 36 inches below the RV flange.SEABROOK -UNIT 1 3/4 4-34 Amendment No. 3, 5, 16, 74,9 89, 114 REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 ACTION:---------------------

NOTE -----------------------------------------

LCO 3.0.4.b is not applicable when entering MODE 4.a) In MODE 4 with all Safety Injection pumps inoperable and with one of the two required overpressure protection devices inoperable, either restore two overpressure protection devices to OPERABLE status within 7 days or within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (a) depressurize the RCS and (b) vent the RCS through at least a 1.58-square-inch.vent.

b) In MODE 5 and MODE 6 with all Safety Injection pumps inoperable and with one of the two required overpressure protection devices inoperable, restore two overpressure protection devices to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (a) depressurize the RCS and (b) vent the RCS through at least a 1.58-square-inch vent.c) In MODE 4, MODE 5 and MODE 6 with all Safety Injection pumps inoperable and with both of the two required overpressure protection devices inoperable, within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (a) depressurize the RCS and (b) vent the RCS through at least a 1.58-square-inch vent.d) In the event the PORVs, or the RHR suction relief valves, or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification

6.8.2 within

30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, or the RHR suction relief valves, or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence.

e) In MODE 5 and MODE 6 with all Safety Injection pumps except one inoperable and with the RCS vent area less than 18 square inches or RCS water level not in a reduced inventory condition, immediately restore all Safety Injection pumps to inoperable status.SEABROOK -UNIT 1 3/4 4-34a Amendment No. 6, 114 EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS

-Tava GREATER THAN OR EQUAL TO 350OF LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of: a. One OPERABLE centrifugal charging pump, b. One OPERABLE Safety Injection pump, c. One OPERABLE RHR heat exchanger, d. One OPERABLE RHR pump, and e. An OPERABLE flow path* capable of taking suction from the refueling water storage tank on a Safety Injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODES 1, 2, and 3"*.ACTION: a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification

6.8.2 within

90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.*During MODE 3, the discharge paths of both Safety Injection pumps may be isolated by closing for a period of up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform surveillance testing as required by Specification 4.4.6.2.2.

• • The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the centrifugal charging pump and the Safety Injection pumps declared inoperable pursuant to Specification 4.5.3.1.2 provided the centrifugal charging pump and the Safety Injection pumps are restored to OPERABLE status within at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs exceeding 375 0 F, whichever comes first.SEABROOK -UNIT 1 3/4 5-4 Amendment No. 114 EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS

-Tag LESS THAN 350°F LIMITING CONDITION FOR OPERATION 3.5.3.1, As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE: a. One OPERABLE centrifugal charging pump, b. One OPERABLE RHR heat exchanger, c. One OPERABLE RHR pump, and d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODE 4.ACTION:----------------------

NOTE --------------------------------------

LCO 3.0.4.b is not applicable to the ECCS high head subsystem.

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or RHR pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System Tavg less than 350*F by use of alternate heat removal methods.c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification

6.8.2 within

90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.SEABROOK-UNIT 1 3/4 5-8 Amendment No. 114 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT CONTAINMENT AIR-LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE in accordance with the Containment Leakage Rate Testing Program.APPLICABILITY:

MODES 1,2, 3, and 4.ACTION: a. With one containment air lock door inoperable:

1. Maintain at least the OPERABLE air lock door closed* and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed, 2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3. Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.*Except during entry to repair an inoperable inner door, for a cumulative time not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per year.SEABROOK -UNIT 1 3/4 6-7 Amendment No. 49, 114 PLANT SYSTEMS TURBINE CYCLE AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with: a. One motor-driven emergency feedwater pump, and one startup feedwater pump capable of being powered from an emergency bus and capable of being aligned to the dedicated water volume in the condensate storage tank, and b. One steam turbine-driven emergency feedwater pump capable of being powered from an OPERABLE steam supply system.APPLICABILITY:

MODES 1, 2, and 3.ACTION:-----------------------------

NOTE -------------------------

1. LCO 3.0.4.b is not applicable to the EFW pumps when entering MODE 1.2. LCO 3.0.4.b is not applicable to the startup feedwater pump.a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b. With two emergency feedwater pumps inoperable, restore at least one emergency feedwater pump to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore both emergency feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.c. With one emergency feedwater pump and the startup feedwater pump inoperable, restore both emergency feedwater pumps to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and all three pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.d. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.SEABROOK -UNIT 1 3/4 7-3 Amendment No. ,4, 114 PLANT SYSTEMS TURBINE CYCLE AUXILIARY FEEDWATER SYSTEM SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a. At least once per 31 days by: 1) Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position;2) Verifying that each automatic valve in the flow path is in the fully open position whenever the Auxiliary Feedwater System is placed in automatic control or when above 10% RATED THERMAL POWER;and 3) Verifying that valves FW-1 56 and FW-1 63 are OPERABLE for alignment of the startup feedwater pump to the emergency feedwater header.b. At least once per 92 days on a STAGGERED TEST BASIS by verifying the following pumps develop the required discharge pressure and flow as specified in the Technical Requirements Manual: 1) The motor-driven emergency feedwater pump;2) The steam turbine-driven emergency feedwater pump when the secondary steam supply pressure is greater than 500 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3;3) The startup feedwater pump, c. At least once per 18 months during shutdown by: 1) Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an Emergency Feedwater System Actuation test signal;2) Verifying that each emergency feedwater pump starts as designed automatically upon receipt of an Emergency Feedwater Actuation System test signal;SEABROOK -UNIT 1 3/4 7-4 Amendment No. 3,,-9, 114 PLANT SYSTEMS TURBINE CYCLE AUXILIARY FEEDWATER SYSTEM SURVEILLANCE REQUIREMENTS 4.7.1.2.1

c. (Continued)

3) Verifying that with all manual actions, including power source and valve alignment, the startup feedwater pump starts within the required elapsed time; and 4) Verifying that each emergency feedwater control valve closes on receipt of a high flow test signal.4.7.1.2.2 Auxiliary feedwater flow paths to each steam generator shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days, or after maintenance on an auxiliary feedwater pump that could have an effect upon pump performance, prior to entering MODE 2 by verifying normal flow to each steam generator from: a. Each emergency feedwater pump, and b. The startup feedwater pump via the main feedwater flow path and via the emergency feedwater header.SEABROOK-UNIT 1 3/4 7-5 Amendment No. 114 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E Distribution System, and b. Two separate and independent diesel generators, each with: 1) A separate day fuel tank containing a minimum fuel volume fraction of 3/8 (600 gallons), 2) A separate Fuel Storage System containing a minimum volume of 62,000 gallons of fuel, 3) A separate fuel transfer pump, 4) Lubricating oil storage containing a minimum total volume of 275 gallons of lubricating oil, and 5) Capability to transfer lubricating oil from storage to the diesel generator unit.APPLICABILITY:

MODES 1, 2, 3, and 4.ACTION:---------------------

NOTE -------------------------------------

LCO 3.0..4.b is not applicable to the diesel generators.

a. With an offsite circuit of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. source by performing Specification 4.8.1.1.1a.

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.SEABROOK -UNIT 1 3/4 8-1 Amendment No. 30, 54,80, 114