ML20210E560
| ML20210E560 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/06/1987 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20210E446 | List: |
| References | |
| NUDOCS 8702100321 | |
| Download: ML20210E560 (17) | |
Text
- _ _ _ _ _ - _ - - _ . - - _ _ __ .. - - _ _ . _ _ _ _ _ . - - _ _ _ . _ _ _ _ .
ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES February 6, 1987 8702100321 870206 PDR ADOcK0500g5 P 16 Pages IC0287-0289Z-NLO2
CONTENTS (Contd)
Page No 8.0 Research ana Development Program (Deleted) . . .... . . 79 - 91 9.0 Inservice Inspection and Testing . . . . . . . ... . . . 92 - 102 9.1 Applicability . . . . . . . .. . . . . . ... . . 92-9.2 Objective . . . . . . . . . .. . . .. . . .. . .. 92 9.3 Specifications . . . .. . . . . . .. . .. . . . . 92 9.4 Basis . . .. . . . . . . . . . . . .. . ... . .. 92 10.0 (Section 6.0) Administrative Controls . . .. . .. . . . . 103 - 126 6.1 Responsibility .. . . . . . . . . . . . . .. . . . 103 6.2 Organization . .. . . . . . . . . .. . .. . . . . 103 - 106 6.3 Plant Staff Qualifications . . . . . . . .. . . . . 107 6.4 Training .. . .. . . . . . . . . .. . . .. . . . 107 6.5 Review and Audit . . .. . . . . . .. . . .. . . . 107 - 113 6.6 Deleted . . . . .. . . . . . . . . .. . .. . . .. 113 6.7 Safety Limit Violation . . . . .. . . . ... . . . 113 6.8 Procedures . . . . . . . . . . . . .. . ... . . . 113 - 114 6.9 Reporting Requirements . . . . . . . . . ... . . . 114 - 120 6.10 Record Retention . . . . . . . . . . . . . .. . . . 120 - 122 6.11 Radiation Protection Program . . . . . . . .. . . . 122 6.12 High Radiation Area . . . . . . . . . . . . . . . . 123 - 123a 6.13 Environmental Qualification . . . . . . . . .. . . . 124 6.14 Process Control Program . . . . . . . . . . . . . . . 125 6.15 Offsite Dose Calculation Manual (ODCM) . . . . . . . 125 11.0 (Section 3.1.4/4.1.4) Emergency Core Cooling System . . . . 130 - 135 (Section 3.1.5/4.1.5) Reactor Depressurization System . . . 136 - 142 (Section 3.3.4/4.3.4) Containment Spray System ... . . . 143 - 145 (Section 3.5.3/4.5.3) Emergency Power Sources . .. . . . . 146 - 149 12.0 Fire Protection Program .. . . . . . . . . . .. . . . . 150 - 157d t (Section 3.3.3.8/4.3.3.8) Fire Detection Instrumentation . 150 - 151 i (Section 3.7.11.1/4.7.11.1) Fire Suppression Water System . 152 - 153 (Section 3.7.11.2/4.7.11.2) Fire Spray / Sprinkler Systems
. 154 (Section 3.7.11.5/4.7.11.5) Fire Hose Stations . . . . . . 155 (Section 3.7.12/4.7.12) Penetration Fire Barriers . . . . . 156 (Section 3.7.13/4.7.1.3) Alternate Shutdown System . . .. 157 - 157b Bases . . . . .. . . . . . . . . . . . . . . . . . . . . . 157c - 157d l 13.0 Radiological Effluent Technical Specifications . . . . .. 158 - 186 13.1 Radiological Effluent Releases . . . . . ... . . . 158 - 173 13.2 Radiological Environmental Monitoring . . . . . . . . 174 - 186 11 Proposed TSB0985-0289B-NL04
Limiting Conditions for Operation Surveillance Requirements
! 11.3.5.3 EMERGENCY POWER SOURCES 11.4.5.3 EMERGENCY POWER SOURCES Applicability: Applicability:.
1 Applies to the operational status of the Applies to the periodic testing requirements emergency power sources. for the emergency power sources.
{
Objective: Objective:
l To assure the capability of the emergency To assure the operability of.the emergency
! power sources to provide power required for power sources to provide emergency power in i emergency equipment in the event of a Loss of the event of a Loss of Coolant Accident..
j Coolant Accident.
l Specification:
i Specification: '
j A. The emergency power system surveillance l A. For all reactor operating conditions ex- will be performed as indicated below.
i cept cold shutdown, there shall normally In addition, components on which mainte-
] be available one 138 kV line, one 46 kV nance has been performed.will be tested.
! line, one diesel generator system, one, 4
station battery system, four RDS uninterrup- 1. During each operating cycle -
! tible power supplies including batteries and
! one alternate shutdown battery system, (a) Test of automatic initia-
! except as specified below: tion sensors and load test the ,
l emergency diesel to 180-200 kW ,
- 1. Refueling operations and related generator output for at least t j testing may be conducted with the 20 minutes.
138 kV line de-energized.
, (b) Test and' calibrate the follow-
- 2. The 46 kV line or the diesel generator ing instruments'and controls may be out of service for repair for associated with diesel periods up to three (3) days during generator:
- reactor operation and for extended
) periods during refueling or shutdown (1) Fuel oil level.
4 operations.
(2) Oil Pressure tripping.
(3) Water temperature tripping.
j 146 Proposed l
i TSB0985-0289A-NLO4 l
Limiting Conditionn for Op7ratirn Surv1111rnc9 Rrquiremerto 11.3.5.3 EMERGENCY POWER SOURCES (Contd) 11.4.5.3 EMERGENCY POWER SOURCES (Contd)
- 3. The diesel generator fuel supply (4) Overspeed tripping.
shall be adequate for three-day operation. (5) Battery undervoltage alarm.
- 4. If Specifications A.2 or A.3 are not (c) Verify the automatic transfer met, a normal orderly shutdown shall of statica power from the be initiated within one (1) hour and 138 kV line to the 46 kV line, the reactor shall be shut down as described in Section 1.2.5(a) with- (d) Verify the automatic transfer of in twelve (12) hours and shut down power sources for the lY and 2Y as described in Section 1.2.5(a) instrument and control panels, and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During refueling opera- (e) Verify the cells, cell plates, and tions cease all changes which could battery racks show no visual affect reactivity, indication of physical damage or abnormal deterioration for the
- 5. The station battery system and the station battery, the RDS alternate shutdown battery system batteries and the alternate shall be operable under all conditions shutdown battery.
except during cold shutdown. If the station battery or the alternate (f) Verify the cell-to-cell and shutdown battery is inoperable, no terminal connections are clean, actions shall be taken which result in tight, free of corrosion and a reactivity addition, except cooldown, coated with anti-corrcsion or which might result in the primary material for the station battery, coolant system drained. The alternate the RDS batteries and the alternate shutdown battery may be inoperable shutdown battery.
during refueling or shutdown opera-tions as long as containment integrity (g) Verify that the battery charger for the main steam line is established. for the station battery and the RDS batteries will suppy at least
- 6. If Specification A.5 is not met a normal 30 amperes at a minimum of orderly shutdown of the reactor shall be 135 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
initiated within one (1) hour and the reactor shall be shut down as described in Section 1.2.5(a) within twelve (12) hours and shut down as described in Section 1.2.5(a) and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'147 Proposed TSB0985-0289A-NLO4 w u -
1 Limiting Ccnditiens for Operatien Survaillect Riquireme-to l 11.3.5.3 EMERGENCY POWER SOURCES (Contd) 11.4.5.3 EMERGENCY POWER SOURCES (Contd)
- 7. One RDS uninterruptible power supply (h) ' Verify that the capacity of the including battery may be out of service station battery, the RDS batteries
- as described in Section 3.1.5 Action 3. and the alternate shutdown battery is adequate to supply and maintain
- 8. Puring reactor power operation, the in OPERABLE status all of the 138 kV line may be out of service for actual emergency loads for the j repair for periods up-to three (3) days. design time interval when the i battery is subjected to a battery I 9. If Specification A.8 is not met, a normal service test. The design time
! orderly shutdown shall be initiated interval for the RDS batteries is l within one (1) hour and the reactor shall one hour, eight hours for the be shut down as described in Section station battery, and seventy-two
- 1.2.5(a) within twelve (12) hours and hours for the alternate shutdown 4
shut down as described in Section battery.
1.2.5(a) and (b) within the following l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (i) Test and calibrate the 2400 volt j bus undervoltage trip control-
, B. During power.and refueling operations, components as follows:
! the 2400 volt bus undervoltage components shall be operable or placed in the tripped (1) The undervoltage relays
) condition, except during the monthly 127-10XY, XZ and YZ will drop channel functional testing period. out on decreasing voltage of i no lower than 107.1 volts, after a delay of 5.6 seconds.
- (2) The auxiliary timing relay i 162-104 will be' actuated after
! a 10 0.5 second time delay 1 upon receiving a signal from j all three (3) undervoltage i relays.
! 2. Monthly -
t j (a) Test start diesel generator and 1
operate at least the fire pump as a load to 480 V Bus 2B for at least 20 minutes.
l, l 148 ' Proposed l TSB0985-0289A-NLO4 i
a --- r- e
Lisiting Conditions for Operation Survaillanca Requircments 11.4.5.3 EMERGENCY POWER SOURCES (Contd)
(b) Verify that the cell voltage is 22.0 volts and specific gravity is 21.2 of each cell of the i
station battery; and verify that the cell voltage is 26.0 volts l and specific gravity is 21.2 on each cell of the RDS batteries; and verify that the cell voltage l 1s 22.1 volts and specific gravity j is 21.2 of each cell of the <
- alternate shutdown battery.
1 (c) Test operate the rod position
)
motor gererator set.
I (d) Perform a channel functional test of the 2400 volt bus undervoltage trip system.
I
- 3. Weekly -
(a) Verify the electrolyte level of i
each RDS battery pilot cell, the station battery pilot cell and the alternate shutdown battery pilot 1
cell is between the minimum and maximum level indication marks.
1 1 (b) Verify the pilot cell specific j gravity for RLS, station and alternate shutdown batteries
- corrected to 77*F, is 21.2.
(c) Verify the station battery pilot cell voltage is 22.0 volts, the 3
RDS battery pilot cell voltage is 26.0 volts and the alternate shutdown battery pilot cell j voltage 22.1 volts.
l 148a Proposed l
4 TSB0985-0289A-NLO4 1
Limiting Conditions for Operation Surveillance Requirements i
11.4.5.3 EMERGENCY POWER SOURCES (Contd)
(d) Verify the overall battery voltage is 2125 volts for the station battery, the RDS batteries and l the alternate shutdown battery, i
I (e) Test start the diesel generator and run for warm-up period.
(f) Verify that the diesel generator battery electrolyte level above plates and overall battery i voltage is 224 volts.
- 4. Quarterly - Verify the following:
(a) That the specific gravity of the diesel generator battery is appropriate for continued service.
(b) That the diesel generator battery and battery rack show no visual indication of physical damage or j abnormal deterioration; and (c) That the diesel generator battery terminal connections are clean, tight, free of corrosion and coated with anticorrosion material.
i l
t f
148b Proposed 1
l TSB0985-0289A-NLO4
~
Limiting Conditions for Operation Surveillance Requirements 11.4.5.3 EMERGENCY POWER SOURCES (Contd)
- 5. Sixty months - At least once per 60 months during shutdown, verify that the RDS batteries, the alternate shutdown battery and the station battery capacity are at least 80% of the manufacturer's rating when subjected to a-performance discharge test. This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test of Part 11.4.5.3.A.1.(h). .
- 9 148c Proposed TSb0985-0289A-NLO4
.r .. . . -: ,
. k
~
Bases:
Normal station power can be provided by the station turbine generator, the 138 kV transmission _line or the 46 kV line. These sources are adequate to provide emergency a-c power. When none of these sources is available, a single emergency diesel generator. rated at 200 kW starts automatically to provide emergency a-c power to 480 V Bus 2B. The weekly starting test is based on Manufacturer's Bulletin-33743-1 for relubrication protection of moving parts. Diesel generator initiation and output circuit ,
breaker closure is accomplished by two voltage-s'ensors: One to detect loss'of normal power on Bus 2B; and, the other to provide assurance of generator output prior to automatic closure of the generator output breaker. Additional breaker interlocks are provided to assure that the normal Buses 1A and 2A are isolated prior to closing the generator output breaker. This prevents overloading of.the generator during the switching period. An undervoltage trip at 589.25% of normal voltage isolates the 2400 volt bus prior to any postulated equipment degradation. y,
_g.
The operability of the diesel battery-and charger is verified by the weekly starting test of the diesel 4 y
and by the weekly verification of the eler.trolyte level and overall battery voltage. o-o' The diesel fuel oil tank is sized for ten-day full-load operation. Three-day supply is considered n adequate to provide fuel makeup. p A single station battery supplies power for normal station services and is sized. for emergency uses E' g
including valves and controls of Loss of Coolant Accidents. The battery can be charged from the a emergency diesel generator output if normal station power sources are not available. p p
The primary core spray valves and the primary containment spray valve are operated and controlled by p power from the station battery. The backup core spray valves and backup containment spray valve are operated by power from normal station power sources or the emergency diesel generator. 47 RDS uninterruptible power supplies (UPS) A, B, C, and D (each consisting of a battery, battery charger and an inverter) supply each division (except division 5) with electrical power. Each UPS has outputs of 120 V a-c, 60 Hz, and 125 V d-c. One of these batteries supplies control power for the~ emergency diesel generator. Divisions 1 & 2 and 3 & 4 normally receive power from 480 V a-c Buses IA and-2A, respectively. In the event of loss of power to either or both buses, provision is included for supplying input power from 480'V a-c Bus 2B which is tied to the emergency diesel generator. If all 480 V a-c power is lost, the RDS UPS is capabic of sustaining its outputs for one hour. The station battery has adequate capacity to carry normal loads plus an assumed failure (locked rotor current) of the d-c lube-149 Amendment No.~d/, (3, 51 March 8, 1982 TSB0985-0289A-NLO4
Bases (Contd) oil pump for 54 minutes without the battery charger and still provide sufficient power for equipment required to operate during a LOCA. If steps are taken to reduce nonessential loads during a loss of off-site power (such as part of the emergency lights), additional time (up to five hours) can be gained from the time of the loss of the charger until the battery would no longer have sufficient power for equipment required to operare during a LOCA. The station battery and the four (4) RDS batteries will be considered operable if they are essentially fully charged and the battery charger is in service.
Additionally, prior to the startup following the 1977 refueling outage, successful completion of service testing and performance discharge testing within each operating cycle and each sixty months, respectively, will further establish battery reliability.
An alternate shutdown battery supplies power to the main steam isolation valve, the emergency condenser outlet valves and other alternate shutdown equipment. The battery is sized so that loss of the charger does not affect operability of the battery for up to six (6) days at a minimum of 25'F (nine (9) days at a minimum of 40*F).
149a Proposed TSB0985-0289A-NLO4
a TABLE 3.3-8 FIRE DETECTION INSTRUMENTS Minimun Instruments Total Operable Instrument Location Instruments Heat Smoke
- 1. Electrical Equipment Room Zone 1 Elevation 614' 5 -
3 Zone 2 Elevation 603' 2 -
1 Zone 3 Elevation 599' 4 -
2 2, Exterior Cable Penetration Room Zone 1 Elevation 614' 5 -
3
- 3. Interior Cable Penetration Room
< Zone 1 Elevation 614' 6 -
4
- 4. Emergency Diesel Generator Room 2 1 -
- 5. Screenwell and Pump House 4 2 -
- 6. Control Room Zone 1 Elevation 627'-9" 2 -
1 Zone 1 Elevation 626'-0" 3 -
2
- 7. Core Spray Pump Room 2 -
1
- 8. Computer Room 2 -
1
- 9. Condensate Pump Room 2 -
1
- 10. Control Rod Drive Accumulator Room Zone 1 Elevation 599' 2 -
1
- 11. Shutdown Heat Exchanger Room 2 -
1
- 12. Recirculation Pump Room 3 2 -
- 13. Alternate Shutdown Building 2 -
1 Proposed 151 TSB0985-0289B-NLO4 h.
0 PLANT SYSTEMS 3/4.7.12 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION i
3.7.12 All penetration fire barriers including fire doors and fire dampers protecting safety-related areas shall be functional.
- APPLICABILITY
- At all times ACTION:
- a. With one or more of the above required penetration fire barriers non-functional and with the area of the affected barrier (s) monitored by OPERABLE (pursuant to Specification 3.3.3.8) fire detection instrumen-tation, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol and inspect the affected area (s) at least one per hour.
- b. With one or more of the above required penetration fire barriers non-functional and with the arca of the affected barrier (s) not monitored by OPERABLE (pursuant to Specification 3.3.8) fire detection instrumentation,'
establish a continuous fire watch on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required penetration fire barriers shall be verified to be functional by a visual inspection;
- a. At least one per 18 months, and i b. Prior to declaring a penetration fire barrier functional following repairs or maintenance.
l 156 Proposed TSB0985-0289B-NLO4 I
t - _ . . __
PLANT SYSTEMS 3/4.7.13 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.13 The alternate shutdown system (ASD) equipment shown in Table 3.3-9 shall be OPERABLE.
APPLICABILITY During power operation.
ACTION With less than the minimum ASD equipment in Table 3.3-9 OPERABLE, restore the inoperable equipment to OPERABLE within 7 days, or provide equivalent shutdown capability and restore the inoperable equipment to OPERABLE within 60 days, or be shutdown as described in Section 1.2.5(a) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shutdown as described in Section 1.2.5(a) and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
- The #1 control rod drive pump, its associated ASD power source and the two emergency condenser indicating lights are the ASD equipment considered to have equivalent shutdown capability.
SURVEILLANCE REQUIREMENTS 4.7.13.1 The ASD monitoring instruments shall be demonstrated OPERABLE by performing a check and a calibration per Table 4.3-9.
4.7.13.2 Each transfer switch, power supply and control circuit shall be demonstrated OPERABLE at each major refueling shutdown
- by operating each actuated component from both the control room and the remote location.
4.7.13.3 At each major refueling shutdown *, perform a verification to ensure that equipment (alternate power sources) needed to achieve and maintain cold shutdown is available.
4.7.13.4 The ASD battery charger shall be demonstrated OPERABLE by performing a weekly verification that the float voltage is greater than 130 volts.
4.7.13.5 The ASD battery surveillance requirements are contained in Section 11.4.5.3
- But no less than once every 18 months.
157 i Proposed TSB0985-0289B-NLO4 b-
TABLE 3.3-9 ALTERNATE SHUTDOWN SYSTEM EQUIPMENT INSTRUMENT READOUT LOCATION
- 1. Steam Drum Level /LI-6819 Panel C31
- 2. Steam Drum Pressure /PI-6819 Panel C31
- 3. Emergency Conder.ser Low Level Panel C31 Alarm Indicating Light /LS-3550
- 4. Emergency Condenser Firewater Panel C31 Makeup Flow Indicating Light /FS-4947 TRANSFER SWITCHES / POWER SUPPLIES / CONTROL CIRCUITS SWITCH LOCATION
- 1. Emergency Condenser Outlet Valve ASD MO-7053 Motor Control M0-7053* Starter OR Emergency Condenser Outlet Valve ASD M0-7063 Motor Control M0-7063* Starter
- 2. Main Steam Isolation Valve Control MO-7050 Motor M0-7050 Starter
- 3. Emergency Condenser Firewater Makeup Panel C31 Valve Control SV-4947
- 4. Control Rod Drive Pump No. 1 and Equipment Lock associated ASD Power Source i
- Section 3.7.13(a) applies only if the alternate shutdown controls for both emergency condenser outlet valves, M0-7053 and M0-7063, are inoperable at the same time.
NOTE: Alternate Shutdown Battery operability requirements are contained in Section 11.3.5.3 Proposed 157a TSB0985-0289B-NLO4
4 TABLE 4.3.-9 ALTERNATE SHUTDOWN SYSTEM INSTRUMENT SURVEILLANCE REQUIREMENTS INSTRUMENT SURVEILLANCE FREQUENCY METHOD e
- 1. Steam Drum Level. A. Check Weekly compare to known level LI-6819 B. Calibration Every 18 apply known differential months pressures to transmitters
- 2. Steam Drum Pressure, A. Check Weekly compare to known pressure PI-6819 B. Calibration Every 18 apply known pressures to months transmitter
- 3. Emergency Condenser A. Check Monthly initiate flow in line Makeup Line Flow Switch Indicating Light FS-4947
- 4. Emergency Condenser Low A. Check Monthly simulate low level Level Alarm Indicating Light, LS-3550 B. Calibration Every 18 apply known differential (Panel C31) months pressure to switch l
{
i l
Proposed 157b t
TSB0985-0289B-NLO4 E- - . . - --. . , , , _ __
l l
', i 1
BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This I capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In th'e event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
3/4.7.11 FIRE SUPPRESSION SYSTEltS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protaction program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishnent. The penetration fire barriers include active and passive elements in the facility fire protection program which are subject to periodic inspections.
During periods of time when the barriers are not functional, routine fire watch patrols in conjunction with OPERABLE fire detection instrumentation or a continuous fire watch are required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.
157c Proposed TSB0985-0289B-NLO4
- 9 BASES (Contd) 3/4.7.13 ALTERNATE SHUTDOWN SYSTEM The requirements for the Alternate Shutdown System provide assurance that shutdown and cooldown to approximately 212*F can be achieved in the event of major fire in critical areas of the plant. This capability is in accordance with the criteria of Appendix R to 10 CFR 50.
Proposed TSB0985-0289B-NLO4
.- - ... .. . . . ---