Text

Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity.
	ML072390190
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Site:	Seabrook
Issue date:	08/23/2007
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	Miller G, NRR/DORL, 415-2481
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FPL ENERGY SEABROOK, LLC, ET AL.*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-86

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for a license complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations s~t forth in 10 CFR Chapter I; and all required notifications to other agencies or bodies have been duly made; B. Construction of the Seabrook Station, Unit No. 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-135 and the application, as amended, the provisions of the Act, and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D below);

D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D below);

E. FPL Energy Seabrook, LLC, is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F. The licensees have satisfied the applicable provisions of 10 CFR 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;

FPL Energy Seabrook, LLC, is authorized to act as agent for the: Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, and Taunton Municipal Lighting Plant and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

AMENDMENT NO. 86,116

(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. 116 *, 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. 1r6

J. Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 116, are hereby incorporated into this license. FPL Energy Seabrook, LLC, shall operate the facility in accordance with the Additional Conditions.

K. Inadvertent Actuation of the Emergency Core Cooling System (ECCS)

Prior to startup from refueling outage 11, FPL Energy Seabrook commits to either upgrade the controls for the pressurizer power operated relief valves (PORV) to safety-grade status and confirm the safety-grade status and water-qualified capability of the PORVs, PORV block valves and associated piping or to provide a reanalysis of the inadvertent safety injection event, using NRC approved methodologies, that concludes that the pressurizer does not become water solid within the minimum allowable time for operators to terminate the event.

3. This license is effective as of the date of issuance and shall expire at midnight on March 15, 2030.

FOR THE NUCLEAR REGULATORY COMMISSION (Original signed by:

Thomas E. Murley)

Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments/Appendices:

1. Appendix A - Technical Specifications (NUREG-1 386)

2. Appendix B - Environmental Protection Plan

3. Appendix C - Additional Conditions Date of Issuance: March 15, 1990 AMENDMENT NO. 86, 91,101,19, 112,116

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 3/4 12-3 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 3/4 12-5 3.0/4.0 BASES Refer to Bases Section Index 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EX C LUSIO N A REA ................................................................................................... 5-1 5.1.2 LOW POPULA TION ZONE ....................................................................................... 5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS ............................. 5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA BOUNDARY 5-3 FIGURE 5.1-2 LOW POPULATION ZONE 5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION 5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE 5-9 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES 5-9 5.3.2 CONTROL ROD ASSEMBLIES................................. 5-9 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE 5-9 5.4.2 VOLUME................................................. 5-9 5.5 (THIS SPECIFICATION NUMBER IS NOT USED) ............................. 5-9 5.6 FUEL STORAGE 5.6.1 CRITICALITY.............................................. 5-10 5.6.2 DRAINAGE................................................ 5-10 5.6.3 C A PA C ITY.................................................................................................................. 5-10 SEABROOK - UNIT 1 X Amendment No. 50,66,74, 89, 93,4-4-5,116

INDEX 5.0 DESIGN FEATURES SECTION PAGE 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-10 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS ..............

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6-1 6.2 R G A N ZAT I N...... ...............................................................................................

6.2 ORGANIZATION 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS 6-1 6.2.2 STATION STAFF........................................... 6-2 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION .................... 6-3 6.2.3 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.2.4 SHIFT TECHNICAL ADVISOR................................. 6-4 6.3 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.4 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.5 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.6 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.7 PROCEDURES AND PROGRAMS 6-5 6.8 REPORTING REQUIREMENTS 6.8.1 ROUTINE REPORTS ......................................... 6-14 Startup Report ............................................................................................................ 6-14 A nnual R eports ........................................................................................................... 6-15 Annual Radiological Environmental Operating Report ......................................... 6-15 Annual Radioactive Effluent Release Report ........................................................ 6-15 CORE OPERATING LIMITS REPORT............................ 6-16 Steam Generator Tube Inspection Report ............................................................. 6-21 SEABROOK - UNIT 1 xi Amendment No. 56,693 ,116

INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6.8.2 SPECIAL REPORTS .......................................... 6-21 6.9 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-21 6.10 RADIATION PROTECTION PROGRAM 6-22 6.11 HIGH RADIATION AREA 6-22 6.12 PROCESS CONTROL PROGRAM (PCP) ............................................................ 6-23 6.1.3 OFFSITE DOSE CALCULATION MANUAL (ODCM) ................... 6-23 6.14 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS 6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM 6-25 SEABROOK - UNIT 1 xii Amendment No. 6, 66, 95, 91,116

TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM TOTAL NO. MINIMUM OF CHANNELS INSTRUMENT LOCATION CHANNELS OPERABLE

1. Intermediate Range Neutron Flux CP-108 A and B 2 1

2. Source Range Neutron Flux CP-1 08 A and B 2

3. Reactor Coolant Temperature -

Wide Range for Loops 1 and 4

a. T, CP-108 A and B 2 2

b. TH CP-108 A and B 2 2

4. Pressurizer Pressure CP-1 08 A and B 2 2

5. Pressurizer Level CP-108 A and B 2 2

6. Steam Generator Pressure CP-1 08 A and B 1/stm. gen. 1/stm. gen.

7. Steam Generator Water Level CP-1 08 A and B l/stm. gen. 1/stm. gen.

8. Steam Generator-Emergency Feedwater Flow Rate CP-108 A and B 1/stm. gen. l/stm, gen.

9. Boric Acid Tank Level CP-1 08 A and B 1/tank 1/tank TRANSFER SWITCHES/CONTROL CIRCUITS LOCATION

1. Emergency Feedwater Pump Steam Supply Valves MS-V-393 CP-1 08 A

2. Emergency Feedwater Pump Steam Supply Valves MS-V-394 CP-108 B

3. Emergency Feedwater Pump Steam Supply Valves MS-V-395 CP-108 A and B

4. Emergency Feedwater Pump FW-P-37B Bus 6 SWGR

5. Emergency Feedwater Recirculation Valve FW-V-346 CP-108 A

6. Emergency Feedwater Recirculation Valve FW-V-347 CP-108 B

7. SG A EFW Control Valve FW-FV-4214 A CP-108 A

8. SG A EFW Control Valve FW-FV-4214 B CP-108 B

9. SG B EFW Control Valve FW-FV-4224 A CP-108 A

10. SG B EFW Control Valve FW-FV-4224 B CP-108 B

11. SG C EFW Control Valve FW-FV-4234 A CP-108 A

12. SG C EFW Control Valve FW-FV-4234 B CP-108 B

13. SG D EFW Control Valve FW-FV-4244 A CP-108 A

14. SG D EFW Control Valve FW-FV-4244 B CP-108 B

15. SG A Atmospheric Relief Valve MS-PV-3001 CP-108 A

16. SG B Atmospheric Relief Valve MS-PV-3002 CP-1 08 B

17. SG C Atmospheric Relief Valve MS-PV-3003 CP-1 08 A SEABROOK - UNIT 1 3/4 3-47 Amendment No. 116

REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 ACTION: (Continued) f) With more than one charging pump capable of injecting into the RCS, immediately initiate action to restore a maximum of one charging pump capable of injecting into the RCS.

SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE when the'PORV(s) are being used for overpressure protection by:

a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, at least once per 31 days thereafter when the PORV is required OPERABLE; and

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and

c. Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when the RHR suction relief valve(s) are being used for overpressure protection as follows:

a. For RHR suction relief valve RC-V89 by verifying at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months that RHR suction isolation valves RC-V87 and RC-V88 are open.

b. For RHR suction relief valve RC-V24 by verifying at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months that RHR suction isolation valves RC-V22 and RC-V23 are open.

c. Testing pursuant to Specification 4.0.5.

4.4.9.3.3 The RCS vent(s) shall be verified tobe open at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s** when the vent(s) is being used for overpressure protection.

- Except when the vent pathway is provided with a valve(s) or device(s) that is locked, sealed, or otherwise secured in the open position, then verify this valve(s) or device(s) open at least once per 31 days.

SEABROOK - UNIT 1 3/4 4-28 Amendment No. 3, 5, 16, 74, 115, 116

REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS OVERPRESSURE PROTECTION SYSTEMS SURVEILLANCE REQUIREMENTS 4.4.9.3.4 The reactor vessel water level shall be verified to be lower than 36 inches below the reactor vessel flange at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reduced inventory condition is being used for overpressure protection.

4.4.9.3.5 All charging pumps, excluding one OPERABLE pump, shall be demonstrated inoperable*** by verifying that the motor circuit breakers are secured in the open position**** at least once per 31 days, except when the reactor vessel head closure bolts are fully detensioned or the vessel head is removed.

An additional pump may be made capable of injecting under administrative control for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during pump-swap operation, except during RCS water-solid conditions.

Additionally, an inoperable pump may be energized for testing provided the discharge of the pump has been isolated from the RCS by a closed isolation valve with power removed from the valve operator, or by a manual isolation valve secured in the closed position.

An alternate method to assure pump inoperability may be used by placing the control room pump-control switch in the Pull-to-Lock position and isolating the discharge flow path of the pump from the RCS by a least one closed isolation valve. Use of the alternative method requires inoperability verification at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SEABROOK - UNIT 1 3/4 4-29 Amendment No. 9O 115, 116

'VALID FOR THE FIRST 20 EFPY, SETPOINT CONTAINS MARGIN OF 50OF FOR TRANSIENT EFFECTS T

200.OF, P = 561.0 PSIG; 200.O°F < T - 230.5 0 F, P = 12.1*(T-200.0) + 926.0 PSIG; 230.5 0F < T : 255.0 0F, P = 23.15*(T-230.5) + 1295.05 PSIG; T > 255.0°F, P = 34.5*(T-255.0) + 1862.225 PSIG 2500 2250 ............................................ .................................. ......... .........

2000 ........................... ... .......................................... ..................................

1750 ................. ..... ............................................ .......................................... ............ ....... .......

O 1500. .......................

................... i ................ ........... ............. ...........

D_

1250 .... ... .... ..................... ........ ............. .................... ............................................................ ............

E 0

C-1000 ............................................ ............................................ ...................

750 ............................................ ................. .......................... ...........................

500 ............................................ ................... ....................... .......

250 ....................... ............. .. ... . ....... ..... . . .. .............. ......... .... ............................. ....... .............. ............................. ....................... ........ ...... . .............. ...........................

0 500 100 150 200 25( 0 300 350 RCS TEMPERATURE (DEG. F)

FIGURE 3.4-4 RCS COLD OVERPRESSURE PROTECTION SETPOINTS SEABROOK - UNIT 1 3/4 4-30 Amendment No. 8,--1-5, 1 6

REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1,2, and 3 components shall be maintained in accordance with Specification 4.4.10.

APPLICABILITY: All MODES.

ACTION:

a. With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50°F above the minimum temperature required by NDT considerations.

b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 2001F.

c. With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.

SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected at least once every 10 years. This inspection shall be by either of the following examinations:

a. An in-place examination, utilizing ultrasonic testing, over the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or

b. A surface examination, utilizing magnetic particle testing and/or penetrant testing, of the exposed surfaces of the disassembled flywheel.

SEABROOK - UNIT 1 3/4 4-31 Amendment No. 79,, 11-,,116

REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one Reactor Coolant System vent path consisting of one vent valve and one block valve powered from emergency busses shall be OPERABLE and closed*at each of the following locations:

a. Reactor vessel head, and

b. Pressurizer steam space.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one of the above Reactor Coolant System vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the vent valves and block valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With both Reactor Coolant System vent paths inoperable; maintain the inoperable vent path closed with power removed from the valve actuators of all the vent valves and block valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.11.1 Each Reactor Coolant System vent path block valve not required to be closed by ACTION a. or b., above, shall be demonstrated OPERABLE at least once per COLD SHUTDOWN, if not performed within the previous 92 days, by operating the valve through one complete cycle of full travel from the control room.

4.4.11.2 Each Reactor Coolant System vent path shall be demonstrated OPERABLE at least once per 18 months by:

a. Verifying all manual isolation valves in each vent path are locked in the open position,

For an OPERABLE vent path using a power-operated relief valve (PORV) as the vent path, the PORV block valve is not required to be closed.

SEABROOK - UNIT 1 3/4 4-32 Amendment No. 3-0, 15, 116

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS SURVEILLANCE REQUIREMENTS 4.4.11.2 (Continued)

b. Cycling each vent valve through at least one complete cycle of full travel from the control room, and

c. Verifying flow through the Reactor Coolant System vent paths during venting.

SEABROOK - UNIT 1 3/4 4-33 Amendment No. -145,116 I

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM/ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.4 The Service Water System shall be OPERABLE with:

a. An OPERABLE service water pumphouse and two service water loops with one OPERABLE service water pump in each loop,

b. An OPERABLE mechanical draft cooling tower and two cooling tower service water loops with one OPERABLE cooling tower service water pump in each loop, and

c. A portable cooling tower makeup system stored in its design operational readiness state.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one service water loop inoperable, return the loop to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one cooling tower service water loop or one cooling tower cell inoperable, return the affected loop or cell to OPERABLE status within 7 days, or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With two cooling tower service water loops or the mechanical draft cooling tower inoperable, return at least one loop and the mechanical draft cooling tower to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With two loops (except as described in c) or the service water pumphouse inoperable, return at least one of the affected loops and the service water pumphouse to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

e. With the portable tower makeup pump system not stored in its design operational readiness state, restore the portable tower makeup pump system to its required condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or continue operation and notify the NRC within the following 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of actions to ensure an adequate supply of makeup water for the service water cooling tower for a minimum of 30 days.

SEABROOK - UNIT 1 3/4 7-13 Amendment No. 32,116

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM/ULTIMATE HEAT SINK SURVEILLANCE REQUIREMENTS 4.7.4.1 Each service water loop shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation test signal.

4.7.4.2 Each service water cooling tower loop shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and

b. At least once per 18 months during shutdown, by verifying that:

1) Each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation test signal,

2) Each automatic valve in the flowpath actuates to its correct position on a Tower Actuation (TA) test signal and

3) Each service water cooling tower pump starts automatically on a TA signal.

4.7.4.3 The service water pumphouse shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the water level to be at or above 25.1' (-15.9' Mean Sea Level).

4.7.4.4 The mechanical draft cooling tower shall be demonstrated OPERABLE:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the water in the mechanical draft cooling tower basin to be at a level of greater than or equal to 42.15* feet.

b. At least once per week by verifying that the water in the cooling tower basin to be at a bulk average temperature of less than or equal to 70 0 F.

With the cooling tower in operation with valves aligned for tunnel heat treatment, the tower basin level shall be maintained at greater than or equal to 40.55 feet.

SEABROOK - UNIT 1 3/4 7-13A Amendment No. 32,116

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM SUBSYSTEMS AIR CONDITIONING LIMITING CONDITION FOR OPERATION 3.7.6.2 Two independent Control Room Air Conditioning Subsystems shall be OPERABLE.

APPLICABILITY: All MODES ACTION:

MODES 1, 2, 3 and 4:

With one Control Room Air Conditioning Subsystem inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6:

a. With one Control Room Air Conditioning Subsystem inoperable, restore the inoperable system to OPERABLE status within 30 days or initiate and maintain operation of the remaining OPERABLE Control Room Air Conditioning Subsystem or immediately suspend all operations involving CORE ALTERATION.

b. With both Control Room Air Conditioning Subsystems inoperable, or with the OPERABLE Control Room Air Conditioning Subsystem unable to maintain temperature below the limiting equipment qualification temperature in the control room area, suspend all operations involving CORE ALTERATIONS.

SURVEILLANCE REQUIREMENTS 4.7.6.2 Each Control Room Air Conditioning Subsystem shall be demonstrated OPERABLE at least once per 92 days by verifying the ability to maintain temperature in the control room area below the limiting equipment qualification temperature for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SEABROOK - UNIT 1 3/4 7-18a Amendment 56, 62,64, 116

ADMINISTRATIVE CONTROLS 6.2.3 (THIS SPECIFICATION NUMBER IS NOT USED) 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Control Room Commander in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the station.

6.3 (THIS SPECIFICATION NUMBER IS NOT USED) 6.4 (THIS SPECIFICATION NUMBER IS NOT USED) 6.5 (THIS SPECIFICATION NUMBER IS NOT USED) 6.6 (THIS SPECIFICATION NUMBER IS NOT USED)

SEABROOK - UNIT 1 6-4 Amendment No. 6 4n04, 1*-, 116

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS 6.7.6 (Continued)

g. Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to ten times the concentration values in Appendix B, Table 2, Column 2, to 10 CFR 20.1001-20.2402,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5) Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contribution from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days,

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, SEABROOK - UNIT 1 6-8 Amendment No. 34, 55, 70, 79, .8, 101, 116

APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-86 FPL Energy Seabrook, LLC, shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation Number- Date 50 NAESCO is authorized to relocate certain technical The amendment specification requirements to licensee-controlled shall be documents. Implementation of this amendment shall implemented within include the relocation of these technical specification 60 days from requirements to the appropriate documents, as March 12, 1997 described in the licensee's application dated October 17, 1996, and evaluated in the staffs Safety Evaluation attached to this amendment.

112 FPLE Seabrook, LLC shall maintain the operational This amendment limit of primary-to-secondary leakage at 150 gallons shall be per day per Steam Generator and if this limit is implemented within exceeded, FPLE Seabrook, LLC will take the 90 days from appropriate actions in accordance with TS 3.4.6.2, September 29, "Reactor Coolant System Leakage." 2006 1 AMENDMENT NO. 96,94,142,116

v t e Letter Sequence Other
TAC:MD2791, (Approved, Closed)
Initiation Request Acceptance... Administration Questions 3 May 2007 22 November 2006 7 March 2008 Answers 22 January 2007 7 August 2007 18 June 2008 Results Approval Other: ML072390190
MONTHYEAR2007-05-03 [Table View]

ML072390190

Text

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