ML20091C393
| ML20091C393 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/22/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091C396 | List: |
| References | |
| NUDOCS 8405300553 | |
| Download: ML20091C393 (18) | |
Text
[(
%j UNITED STATES NUCLEAR REGULATORY COMMISSION Lg
- a. p WASHINGTON, D. C. 20555
\\...../
CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 81 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated August 30, 1982 as supplemented November 5, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment 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; D.
The issuance of this amendment. will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
e405300553 840522 DR ADOCK 05000
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No.
DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B (Environmental Protection Plan), as revised through Amendment No. 81, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION E.
W
~
s Den is M.
utchfield, Chief
- \\
/
s0pe ating Re ctors Branch #5
' 'sion of L1 ensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1984
ATTACHMENT TO LICENSE AMENDMENT N0. 81 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Technical Specifications by removing the following pages and inserting the enclosed pages. The revised pages contains the captioned amendment number and marginal lines indicating the area of
- change.
REMOVE INSERT 11 11 3-40a 3-47 3-47 3-48 3-48 4
3-49 3-49 3-69 3-69 3-70 3-70 4-11 4-11 4-13 4-13 4-15 4-15 4-15a 4-15a 4-15b 4-15b 4-15c 4-15d 4-15e
TABLE OF CONTENTS (Contd)
Section Description
~ Page No 3.0 LIMITING CONDITIONS FOR OPERATION (Contd) 3.10 Control Rods 3-58 3.10.1 Shutdown Margin Requirements 3-58
'3.10.2 Individual Rod Worth 3-58 3.10.3 Part-Length Control Rods 3-58 3.10.4 Misaligned or Inoperable Control Rod or Part-Length Rod 3-60 _
3.10.5
- Regulating Group Insertion Limits 3-60 3.10.6 Shutdown E;d Limits 3-61 3.10.7 Low Power Physics Testing 3-61 3.10.8 Center Control Rod Misalignment 3-61 3.11 Power Distributica Instruments 3-65 3.11.1 Incore Detectors 3-65 3.11.2 Excore Power Distribution Monitoring System 3-66a-3.12 Moderator Temperature Coefficient of Reactivity 3-67 3.13 Containment Building and Fuel Storage Building Cranes 3-69 3.14 Control Room Ventilation 3-70 l
3.15 Reactor Primary Shield Cooling System 3-70 3.16 Engineered Safety Features System Initiation Instrumentation Settings 3-71 3.17 Instrumentation and Control System 3-76 3.18 Secondary Water Chemistry 3-82 3.19 Linear Heat Generation Rate Limits Associated With LOCA Considerations 3-84 3.20 Shock Suppressors (Snubbers) 3-88 3.21 Movement of Heavy Loads Over the Spent Fuel Pool (To Be Submitted) 3-92 3.22 Fire Protection System 3-96 3.22.1 Fire Detection Instrumentation 3-96 3.22.2 Fire Suppression Water System 3-98 3.22.3 Fire Sprinkler System 3-100 3.22.4 Fire Hose Stations 3-101 3.22.5 Penetration Fire Barriers 3-102 3.23 Power Distribution Limits 3-103 l
3.23.1 Linear Heat Rate (LER) 3-103 3.23.2 Radial Peaking Factors 3-110 3.23.3 Quadrant Power T.H - Tq 3-111 4.0 SURVEILLANCE REQUIREMENTS 4-1 4.1 Instrumentation and Control 4-1 4.2 Equipment and Sampling Tests 4-13 4.3 Systems Surveillance 4-16 4.4 Primary Coolant System Integrity Testing 4-24 4.5 Containment Tests 4-25 ii Amendment No. JT, T, I,8 1
3.6.4 Two independent containment hydrogen recombiners shall be operabib when the reactor is at power or at hot standby. With one hydrogen recom-biner system inoperable, restore the inoperable system to operable status within 30 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d i
i Amendment No. 8 1 t
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3.8 REFUELING OPERATIONS (Contd) g.
During reactor vessel head removal and while refueling operations are being performed in the reactor, the refueling boren concentra-tion shall be maintained in the primary coolant system and shall be checked by sampling on each shift.
h.
Direct com=unication between personnel in the control rcom and at the refueling machine shall be available whenever changes in core geometry are taking place.
3.8.2 If any of the conditions in 3.8.1 are not met, all refueling operations shall cease immediately, work shall be initiated to satisfy the required conditions and no operations that may change the reactivity of the core shall be made.
3.8.3 Refueling operation shall not be initiated before the reactor core has decayed for a minimum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the reactor has been operated at power levels in excess of 2'; rated power.
3.8.4 The ventilation system and charcoal filter in the fuel storage building shall be operating whenever irradiated fuel which has decayed less than 30 days is being handled by either. of the following operations:
a.
Refueling operation with the equipment door open, or b.
Fuel handling in the fuel storage building.
If both f ans are unavailable, any fuel movements in progress shall be completed and further fuel movements over the spent fuel storage pool shall be terminated until one f an is returned to service.
l 3.8.5 When spent fuel which has decayed less than one year is placed in the l
tilt pit storage racks, the bulk water temperature in the tilt pit l
storage area must be monitored continuously to assure that the water temperature does not exceed 150*F.
Monitoring will continue for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after any addition of fuel to the main pool or the tilt pit or l
when a failure of the spent fuel pool cooling system occurs.
Basis ite equipment and general procedures to be utilired during refueling are discussed in the FSAR. Detailed instructions, the above specifica-l tiens, and the design of the fuel handling equipment incorporating built-in interlocks and safety features provide assurance that no incident could occur during the refueling operations that would result l
in a hazard to public health and safety.(1) Whenever changes are not being made in core geometry, one flux monitor is sufficient. This l
l 3-47 Amendment No. Jh&,' 81
~
3.8 RETUELING OPERATIONS (Contd)
~
permits maintenance of the instrumentation.
Continuous monitoring of radiation levels snd neutron flux provides immediate indication of an unsafe condition.
The shutdown cooling pu=p is used to maintain a uniform boron concentration.
The shutdown margin as indicated will keep the core subcritical, even if all control rods were withdrawn from the core.
During refueling, the reactor refueling cavity is filled with approximately 250,000 gallons of borated water. The boron concentration of this water (1720 ppm boron) is sufficient to maintain the reactor subcritical by approximately 5% Ap in the cold condition with all rods withdrawn.(2)
Periodic checks of refueling water boron concentration insure the proper shutdown margin.
Communication requirements allow the control room operator to inform the refueling machine operator of any impending unsafe condition detected from the main control board indicators during fuel movement.
In addition to the above engineered safety features, interlocks are utilized during refueling to insure safe handling. An excess weight interlock is provided on the lifting hoist to prevent movement of more than one fuel assembly at a time.
In addition, interlocks on the auxiliary building crane will prevent the trolley from being moved over storage racks containing spent fuel, except as necessary for the handling of fuel.(3) The restriction of not moving fuel in the reactor for a period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the power has been removed from the core takes advantage of the decay of the short half-life fission products and allows any failed fuel to purge itself of fission gases, thus reducing the consequences of a fuel handling accident.
The charcoal filter installed in the fuel handling building exhaust will handle the full (approximately 10,000) cfm capacity of the normal ventilation flow with both exhaust fans operating.(4) The normal mode of operation will require that the ventilation supply f an and one exhaust fan be manually tripped following a radioactivity release with a resulting flow of 7300 cfm through the filter.
Any radioactivity which should inadvertently, during a refueling operation, pass through the normally opened equipment door would be handled by the charcoal filter in the fuel handling building. The several radiation monitors installed in the containment building and the fuel handling building will give adequate warning to the refueling crew if radioactivity is released.
The efficiency of the installed charcoal filters is at least l
90% for inorganic species and 70% for organic species with rated l
, flows.(5) The offsite thyroid dose in the fuel handling accidents analyzed will be less than 15 Rem using these efficiencies should an irradiated fuel bundle be damaged in handling.(5) The fuel handling accident analysis assures that the charcoal adsorbers will perform to remove a minimum of 70% and 90% (organic and inorganic, respectively) iodine activity.
Following a period of 30 days, the I-131 will have decayed by a f actor of 10 and adsorption by charcoal will no longer be 3-48 Amendment No. g 7
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3.8 REFUELING OPERATIONS (Contd)
~
required. Valve alignr.ent check sheets are completed to protect against sources of unForated water or draining of the system.
References (1)FSAR, Section 9.11.
(2)FSAR, Section 3.3.2.
(3)FSAR, Amendment No 17, Item 13.0.
(4)FSAR, Amendment No 17, Item 9.0.
(5)FSAR, Appendix J.
l 3-49 Amendment No.g 1
3.13 CONTAINMENT BUILDING AND FUEL STORAGE BUILDING CRANES Applicability Applies to the use of cranes over the primary coolant system and the spent fuel storage pool.
Objective To specify restrictions on the use of the overhead cranes in the Con-tainment Building and the Fuel Storage Building.
Specifications a.
The containment polar crane shall not be used to transport loads over the primary coolant system if the temperature of the coolant or steam in the pressurizer exceeds 225*F.
b.
The fuel storage building crane shall not be used to move mater'ial past the fuel storage pool unless the crane interlocks are operable or they are bypassed and the crane is under administrative control of a supervisor.
c.
The fuel storage building ventilation shall be operating and 4
discharging through the HEPA and charcoal adsorbers during crane operation with loads in excess of 1300 pounds over the fuel storage pool when irradiated fuel which has decayed less than 90 days is in
.the spent fuel storage pool.
If both fans are inoperable, any crane operations shall be completed and further crane operation with loads in excess of 1300 pounds over the spent fuel storage pool shall be terminated until one fan is returned to service.
Basis l
Loads are not to be allowed over the pressurized primary coolant system l
to preclude dropping objects which could rupture the boundary of the primary coolant system allowing loss of coolant and overheating of the I
core.(1) l The fuel storage building crane is provided with a system of trolley and bridge electrical interlocks that will normally prevent the trolley from moving over the storage pool.(2) This minimizes the possibility of dropping an object on the irradiated fuel stored in the pool and resulting in the release of radioactive products. The interlocks may be bypassed under strict administrative control to allow required' movement of fuel and material over and to the east of the pool. The crane can be used over the equipment batches located in the north and south ends of the Fuel Storage Building without the interlocks operable since a load, even if dropped, could not fall into the storage pool.
References (1) FSAR, Question 2.3.
(2) FSAR, Amendment No. 17, Item 13.
l l
3-69 Amendment No.0 1 l
3,14 CONTROL ROOM VENTILATION Applicability This specification applies to the control room ventilation system.
Objective The operability of the control room ventilation sys. tam ensures,that (1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the ecuipment and instrumentation cooled by this system, and (2) the control room will remain habitable for Operations personnel during and following all credible accidents.
Soecifications a.
If the control room air temperature reaches 120*F, immediate action
~
shall be taken to reduce this temperature or to place the reactor in a hot shutdown condition.
b.
The c'entrol room ventilation system, consisting of two f ans and a filter system, shall be operable. With both f ans inoperable or the filter system inoperable, restore the system to operable status within 3-1/2 days or be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Basis The reactor protective systa= and the engineered safeguards system were designed for and the instrumentation was tested at 120*F.
Therefore, if the temperature of the control room exceeds 120*F, the reactor will be shut down and the condition corrected to preclude failure of components in an untested environment.
The control room ventilation systems are independent except for the charcoal filter and associated equipment. The charcoal filter system is designed to provide filtered makeup air to the control room following a design base accident and is not used during normal operation.
3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM Applicability Applies to the shield cooling system.
Objective To assure the concrete in the reactor cavity does not overheat and l
develop excessive thermal stress.
Specification L
One shield cooling pump and cooling coil shall be in operation whenever
[
cooling is required to maintain the temperature of the concrete below approximately 1650F, 1
l Basis The shield cooling system is used to maintain the concrete temperature below 1650F, thus preventing weakening of the structure through loss of moisture. The structure must remain intact during a DBA to preclude damage to the reactor building sump and the plugging of the suction lines to the engineered safeguards pumps.
One pump and cooling coil is more than adequate to remove the 120,000 Btu /hr heat load at rated power operation. (1)
Reference 3-70 Amendment No. 81 l
(1) FSAR, Section 9.2.1.
MU!.L8 J. 3 t
Minimum f requenclos for Checks, Calibrations and lasting of Hiscellaneous instrismontation and Controls (Contd)
SurvoIIinnce
(:ha nno I _ Do sc r I p l. I on _ _
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8.
Control Rod Drivo System a.
Test R
a.
Voril'y proper operation or all rod drivo Interlocks control system Interlocks, using simulated signa ls where necessa ry.
b.
Test P
b.
Same as Bla) above, Ir not done within three months.
9.
F1 soc-T l'over Compa ra tor a.
Ca l ib ra te R
a.
Uso simulated signals.
b.
Test M
b.
Internal test signal.
10.
Calorimetric Instrumentation a.
Ca l i b ra te( 2 )
R a.
Known dirrorential pressure applied te reedwater flow sensors.
II.
Containment Building stumidity a.
Test R
a.
I) pose sensor to high humidity atmosphere.
Detectors 12.
Interlocks - Isolation Valves a.
Calibrate R
a.
Known pressure applied to s'ensor.
on Shuttlown Cooling Line 1
13.
Service Water Break Detector a.
Test R
a.
l(nown dirrorential pressure applied to in Containment Sensors.
i N
a 3
Q.
Elm 3r+
z
.O l$l (1)During the 1978 refueling outage, item 2.c will only he performed on 7 rods (! per bank).
The secondary rod posi;lon surveillanco (Item 3.c) will be performed in entirety. Additionally, a 20" rod position rhock m
(comparing primary indication to secondary indication) will he conducted on each roJ.
Ir the primary and secondary indications vary more than 2" from each other, corrective action will be taken to restore the proper j
g tolerancos.
I t
i, (2)lho 1981 surveillance function may be deferred until the end or the 1981 reruoling outage.
8s-I l e
4.2 EQUIPMENT AND SAMPLING TESTS Applicability Applies to plant equipment and conditions related to safety.
Obiective To specify the minimum frequency and type of surveillance to be applied to critical plant equipment and conditions.
Specifications Equipment and sampling tests shall be conducted as specified in Tables 4.2.1, 4.2.2 and 4.2.3.
Basis Samuling and Ecuiement Testing The equipment testing and system sampling frequencies specified in Tables 4.2.1, 4.2.2 and 4.2.3 are considered adequate, based upon experience, to maintain the status of the equipment and systems so as to assure safe operation.
Thus, those systems where changes might occur relatively rr.pidly are sampled frequently and those static systems not subject to changes are sampled less frequently.
i l
9 1
4-13 AmenJment No. 24 8 1 l
Table 4.2.2
~
Minimum Frecuencies for Ecuitment Tests FSAR Section Test-Frecuency Reference 1.
Control Rods Drop Times of All Full-Each Re-7.4.1.3 -
Length Rods fueling Shutdown 2.
Control Rods Partial Movement of All Every TLo 7.4.1.3 Rods (Minimum of 6 In)
Weeks 3.
Pressurizer Safety Valves Set Point One Each 7.3.7 Refueling Shutdown 4
Main Steam Safety Valves Set Point Five Each 4.3.4 Refueling Shutdown 5.
Refueling System Inter-Functioning Prior to 9.11.3 locks Refueling Operations 6.
Service Water System Functioning Each Re-9.1.2 Valve Actuation (SIS-CHP) fueling Operation 7.
Fire Protection Pumps Functioning Monthly 9.6.2 and Power Supply 8.
Primary System Leakage Evaluate Daily 4
Amend 15, Ques 4.3.7 9.
Diesel Fuel Supply Fuel Inventory Daily 8.4.1 10.
Critical Headers Service 150 Psig Hydro-Every 9.1.2 Water System static Test Five Years 4-15 Amendment No. 81
Table 4.2.2-(Contd)
Minimum Frequencies for Eculpment Tests 11.
Hydrogen Recombiners Each hydrogen recombiner unit shall be demonstrated operable:
a.
At least once per 6 months by verifying during a recombiner unit functional test that the minimum heater sheath temperature increases to 2 700*F* within 90 minutes and is maintained for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
b.
At least once per refueling cycle by:
1.
Verifying that each of the electrical buses providing recombiner unit power is aligned to receive power from separate diesel gen-erators.
2.
Performing a channel calibration of all recombiner instrumenta-tion and control circuits.
3.
Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners (ie, loose wiring or structural connections, deposits of foreign materials, etc).
4 Verifying during a recombiner unit functiona'l test that the heater sheath temperature increases to 21200*F* within 180 minutes and that the system operates for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
5.
Verifying the integrity of all heater electrical circuits by per-forming a continuity and resistance to ground test immediately following the above required functional test.
The resistance to ground for any heater element shall be 2 1000 ohms.
- As measured by installed or portable temperature measuring instruments.
4-15a Amendment No. g 1
Table 4.2.2-(Contd)
Minimum Frecuencies for Ecuiement Tests 12.
Iodine Removal System The Iodine Removal System shall be Elemonstrated operable:
a.
At least once per 31 days by verifying that each valve (manua1, power operated or automatic) in the flow path that is not locked, sealed or ~
otherwise secured in position, is in its correct position.
b.
At least once per 6 months by:
1.
Verifying that tanks T-102 and T-103 contain the mini =um required volumes.-
2.
Verifying the concentration of hydranine in T-102 and sodium hydroxide in T-103.
c.
At least once per refueling cycle, during shutdown, by verifying that each automatic valve in the flow path actuates to its correct posi-tion.
6 l
l 4-15b Amendment No. %81 4
Table 4.2.3 HEPA FILTER AND CHARCOAL ADSORBER SYSTEMS Control Room Ventilation and Isolation System (Rated flow: 765 cfm) Fuel Storage Area HEPA/ Charcoal Exhaust System (Rated flow:
10,000 cfm, two fans or 7300 cfm, one fan).
The filters in each of the above systems shall be demonstrated operable:
At least once per 31 days by initiating, from the Control Roem, flow a.
through the HEPA filter and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
b.
At least once per refueling cycle or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following major painting, fire or chemical release in any ventilation zone communicating with the system when the HEPA Filter or charcoal adsorbers. are in operation by.:
1.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b. of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of. Regulatory Guide 1.52, Revision 2, March 1978 except that the Fuel Storage Area shall have a methy iodide limit of 94% instead of 99%, or replacing with charcoal adsorbers meeting the specifications of Regulatory Guide 1.52, Position C.6.a, Revision 2, March 1978.
2.
Verifying that the HEPA filter bank removes greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at its rated flow i 20%.
i 3.
Verifying that the charcoal absorber removes greater than or equal to 99% of a hydrogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at its rated flow : 20%.
4-15c Amendment No. 81
Table 4.2.3 (Contd)
HEPA FILTER AND CHARCOAL ADSOREER SYSTEMS c.
At least once per refueling cycle by:
1.
Verifying that the pressure drop across the ce=bined HEPA filter and charcoal adsorber bank is less than (6) inches Water Gauge while operating the system.
2.
Verifying that on a containment high-pressure and high-radiatien test signal, the system automatically switches into a recirculating mode of operation with flow through the HEPA filter and charccal adsorber bank.
(Centrol Room ventilation only.)
3.
Verifying that the system maintains the Centrol Room at a positive pressure of greater than or equal to 0.10 inch WG relative to the viewing gallery (dPIC 1834) during system cperation.
(Control Room ventilation only.)
4.
Verifying that with the ventilation sy. stem exhausting through the HEPA/ Charcoal Filters at its rated flow 20%, the bypass flow through damper 1893 is less than 1% of total flow.
(Fuel Storage Area only.)
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />"(see Note 1) of charcoal adsorber operation by:
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory j
Position C.6.b. of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978 except that the Fuel Storage Area shall have a methy iodide limit of 94% instead of 99%,
or replacing with charcoal adsorbers meeting the specifications of Regulatory Guide 1.52, Position C.6., Revision 2, March 1978.
After each complete or partial replacement of a HEPA filter bank by:
e.
i Verifying that the HEPA filter bank removes greater than or equal to 99% of the DOP when they are tested in place'in accordance with ANSI N510-1975 while operating the syttem at its rated flow i 20%.
l Note 1.
Should the.720-hour limitation occur during a plant operation requiring the use of the HEPA filter and charcoal adsorber - such as-during a refueling - testing may be delayed until the co=pletion of the plant operation or up to 1,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of filter operation whichever occurs first.
.I.
4-15d Amendment No.g i
Table 4.2.3 (Contd)
EEPA Filter and Charcoal Adsorber Systems f.
After each complete or partial replacement of a charcoal adsorber bank by:
Verifying that the charcoal adsorber removes greater than or equal to i
99% of a hydrogenated hydrocarbon refrigerant test gas when they are l
tested in place in accordance with ANSI N510-1975 while operating the system at its rated flow i 20%.
l g.
Verify that the Control Room temperature is < 120*F once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the temperature in the Control Room reaches 105'F.
O O
l 4-15e Amendment No. 81 2
1