ML023240343

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Technical Specifications, Replace Current Accident Source Term Used in Design-Basis Radiological Analyses for Control Room Habitability with Alternative Source Term (AST) Pursuant to 10 CFR 50.67, Accident Source Term
ML023240343
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 11/14/2002
From:
NRC/NRR/DLPM/LPD3
To:
References
TAC MB5318, TAC MB5319
Download: ML023240343 (6)


Text

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS (Continued) 314.6.5 ICE CONDENSER Ice Bed ................................................................................................... 3/4 6-35 Ice Bed Temperature Monitoring System ........................................................... 3/4 6-37 Ice Condenser Doors ................................................................................... 3/4 6-39 Inlet Door Position Monitoring System ............................................................. 3/4 6-42 Divider Barrier Personnel Access Doors and Equipment Hatches ............................................................................. 3/4 6-43 Containment Air Recirculation Systems ............................................................. 3/4 6-44 Floor Drains ............................................................................................. 3/4 6-45 Refueling Canal Drains ................................................................................ 3/4 6-46 Divider Barrier Seal ............................................................... . . ........... 3/4 6-47 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves ............................................................................................ 3/4 7-1 Auxiliary Feedwater System .......................................................................... 3/4 7-5 Condensate Storage Tank .............................................................................. 3/4 7-7 Activity ................................................................................................... 3/4 7-8 Steam Generator Stop Valves ......................................................................... 3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION ...................... 3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM ................................................... 3/4 7-12 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM ....................................................... 3/4 7-13 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM Control Room Emergency Ventilation System ..................................................... 3/4 7-14 Control Room Air Conditioning System ............................................................ 3/4 7-16b 3/4.7.6 ESF VENTILATION SYSTEM ...................................................................... 3/4 7-17 3/4.7.7 SNUBBERS .............................................................................................. 3/4 7-20 3/4.7.8 SEALED SOURCE CONTAMINATION .......................................................... 3/4 7-34 COOK NUCLEAR PLANT-UNIT 2 VIII AMENDMENT 4-6, 407, 252

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.5.1 The control room emergency ventilation system shall be demonstrated OPERABLE:

a. Deleted
b. At least once per 31 days on a STAGGERED TEST BASIS by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the system operates for at least 15 minutes.
c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
1. Verifying that the charcoal adsorbers remove >_ 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm +/- 10%.

2 Verifying that the HEPA filter banks remove > 99 % of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm +/- 10%.

3. Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the sample is tested in accordance with ASTM D3803-1989, 30'C, 95% R.H. The carbon samples not obtained from test canisters shall be prepared by either:

a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

4. Verifying a system flow rate of 6000 cfm +/- 10% during system operation when tested in accordance with ANSI N510-1975.

AMENDMENT 240, 252 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-15

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

e. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
2. a. Verifying that on a Safety Injection Signal from Unit 1, the system automatically operates in the pressurization/cleanup mode.
b. Verifying that on a Safety Injection Signal from Unit 2, the system automatically operates in the pressurization/cleanup mode.
3. Verifying that the system maintains the control room envelope/pressure boundary at a positive pressure of greater than or equal to 1/16 inch W. G.

relative to the outside atmosphere at a system flow rate of 6000 cfm plus or I

minus 10% with a makeup air flow rate of < 1000 cfm that the

f. After each complete or partial replacement of a HEPA filter bank by verifying to 99% of the DOP when they are HEPA filter banks remove greater than or equal tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

bank by verifying

g. After each complete or partial replacement of a charcoal adsorber that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

Page 3/4 7-16a AMENDMENT 9-7, 4-34, 4-58, 202, COOK NUCLEAR PLANT-UNIT 2 2-2-4, 252

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS CONTROL ROOM AIR CONDITIONING SYSTEM LIMITING CONDITION FOR OPERATION and 3.7.5.2 The Control room air conditioning system (CRACS) shall be OPERABLE with two heating cooling systems.

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

ACTION:

status within 7 With one heating and cooling system inoperable, restore the inoperable system to OPERABLE SHUTDOWN within the following 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 COLD 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS least once per 4.7.5.2 The control room air conditioning system shall be demonstrated OPERABLE at 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 95°F.

Page 3/4 7-16b AMENDMENT 252 COOK NUCLEAR PLANT-UNIT 2

314 BASES 3/4.7 PLANT SYSTEMS ROOM AIR CONDITIONING 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION AND CONTROL SYSTEMS ensures that the control room The OPERABILITY of the control room emergency ventilation system (CREVS) all credible accident conditions. In MODES will remain habitable for operations personnel during and following to take the actions necessary to mitigate the 1-4, the CREVS provides radiological protection to allow operators to be OPERABLE for operations involving consequences of a design basis accident. The CREVS is also required has from a fuel handling accident. The CREVS the movement of irradiated fuel assemblies to provide protection intake air of a pressurization fan, normal two pressurization trains with each pressurization train consisting The charcoal and maintain flow to the control room.

damper, and emergency intake air damper available to align filter, and filter housing. The adsorber/HEPA filter unit consists of the prefilter, charcoal adsorbers, HEPA room design provisions is based on limiting the OPERABILITY of this system in conjunction with control room to less than or equal to 5 rem Total Effective Dose radiation exposure to personnel occupying the control (GDC) 19 of the requirements of General Design Criteria Equivalent, TEDE. This limitation is consistent with Jkppendix "A", 10 CFR 50.

the control room HVAC equipment The control room envelope/pressure boundary consists of the control room, is modified by a Note allowing room, and the plant process computer room. The Limiting Condition for operation to be opened intermittently under administrative controls. For entry the control room envelope/pressure boundary is performed by the person(s) and exit through doors to the control room, the administrative control of the opening of stationing a dedicated individual at the entering or exiting the area. For other openings, these controls consist will have a method to rapidly opening who is in continuous communication with the control room. This individual isolation is indicated.

close the opening when a need for control room envelopelpressure boundary 3, and 4, the CREVS trains cannot If the control room envelope/pressure boundary is inoperable in MODES 1, 2, perform their intended functions. Actions must be taken to restore an OPERABLE control room room envelope/pressure boundary envelope/pressure boundary within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the period that the control of GDC 19) should be utilized to is inoperable, appropriate compensatory measures (consistent with the intent contamination, smoke, temperature and protect control room operators from potential hazards such as radioactive be available to address these concerns for relative humidity, and physical security. Preplanned measures should completion time is reasonable based on the low intentional and unintentional entry into the condition. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> measures.

period, and the use of compensatory probability of a design basis accident occurring during this time test most diagnose, plan and possibly repair, and The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time is a typically reasonable time to problems with the control room envelope/pressure boundary.

automatically on a Safety Injection (SI)

The Unit 2 control room emergency ventilation system aligns and operates Procedures direct realignment Signal from either Unit 1 or Unit 2. Both pressurization fans start on the SI signal.

hours after receiving the SI signal. The automatic start from Unit of the CREVS to single fan operation within two in modes 1 through 4 in Unit 1.

1 is normally only available when the Unit 1 ESF actuation system is active heating and cooling systems. Each The Limiting Condition for Operation requires two independent control room water supply. Cooling water is cooling system requires a functional air handling unit and associated cooling water (ESW) supply temperature of provided from a chilled water unit. At the design maximum essential service 86 0F, a chilled water unit will maintain the control room temperature below 951F. Cooling water may also be 0

supplied directly by ESW when ESW supply temperature is < 65 F.

Page B 3/4 7-4a AMENDMENT 143, 202, COOK NUCLEAR PLANT-UNIT 2 Revised 05/31-00, 252

3/4 BASES 3/4.7 PLANT SYSTEMS 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION AND CONTROL ROOM AIR CONDITIONING SYSTEMS (Continued)

The control room air conditioning system (CRACS) normally maintains the control room at temperatures at which I control room equipment is qualified for the life of the plant. Continued operation at the Technical Specification the limit is permitted since the portion of time the temperature is likely to be elevated is small in comparison to qualified life of the equipment at the limit.

0 with Each control room cooling system can maintain control room temperature 5 102 F during accident conditions 0 control room equipment remains within the control room isolated. At control room temperatures of < 102 F, vital its manufacturer's recommended operating temperature range.

Page B 3/4 7-4b AMENDMENT Revised 05!31, COOK NUCLEAR PLANT-UNIT 2 252