ML20088A839
| ML20088A839 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/29/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20088A840 | List: |
| References | |
| NUDOCS 8404130208 | |
| Download: ML20088A839 (2) | |
Text
.
n terg*o UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION 3.g
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WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0UOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. DPR-77
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The applications for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated July 1, July 21, October 24, and November 28, 1983, comply with the standards and' requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I';
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The facility will operate in confo'rmity with the license, as amended, B.
the provisions of.the Act, and the rules and regulations of the Com-mission; C.
There is reasonable assurance (1) that the activities authorized by
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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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, are hereby incorporated into the license.
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8404130208 840329 PDR ADOCK 05000327 e
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-PDR A
2-Thelicenseeshalloperatethefacilityinaccordanchwiththe Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION en-Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance: March 29, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 33,"
FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 3/4 2-19 3/4 3-27a
'3/4 6-25a 3/4 8-34 3/4 8-35 3/4 8-36 3/4 8-37 B3/4 8-2
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TABLE 3.2-l' w
.mi DNB PARAMETERS S
E LIMITS C;i'i 4 Loops In 3 Loops in
[
PARAMETER Operation Operation **
Reactor Coolant System T,yg F 583*F Pressurizer Pressure J 2220 psia *
^ Limit not applicable during either a THERMAL POWER ramp in excess of 5% RATED THERMAL POWER w>
per minute or a. THERMAL POWER step in excess of 10% RATED THERMAL POWER, physics test, or performance of surveillance requirement 4.1.1.3.b.
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- Limits pending NRC approval of 3 loop operation.
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TABLE 3.3-4 (Continued)
.E iE ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION TRIP SETPOINTS c!
3 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
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E
- b.
6.9 kv Shutdown Board-Degraded il Voltage s
1.
Voltage Sensors 6560 volts 6560 volts + 33 volts 2.
Diesel Generator Start and
' Load Shed Timer 300 seconds 300 seconds + 30 seconds 3.
SI/ Degraded Voltage Logic Enable Timer 10 seconds 10 seconds _+ 0.5 seconds 8.
ENGINEERED SAFETY FEATURE
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ACTUATION SYSTEM INTERLOCKS I
'Y a.
Pressurizer Pressure O
Manual Block of Safety Injection P-1151970 psig 5 1980 psig O
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- NOTE:
This technical specification is to.be implemented at the startup following the 2nd refueling r*
outage or following completion of the modification, whichever is earlier.
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HYDROGEN MITIGATION SYSTEM e
LIMITING CONDITION FOR OPERATION 3.6.4.3 The primary containment hydrogen mitigation system shall be operable.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one train of hydrogen mitigation system inoperable, restore the inoperable train to OPERABLE status within 7 days or increase the surveillance interval of S.R. 4.6.4.3 from 92 days to 7 days on the operable train until the inoperable train is returned to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.6.4.3 The hydrogen mitigation system shall be demonstrated OPERABLE:
At least once per 92 days by energizing the~ supply breakers and a.
verifying that at least 66 of 68 igniters are energized."
g-b.
At least once per.18 months by verifying the temperature of each igniter is a minimum of 1700*F.
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- Inoperable igniters must not be on corresponding redundant circuits which provide coverage for the same region.
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SEQUOYAH, UNIT 1 3/4 6-25a Amendment No.33 o
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ELECTR1 CAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION 3.8.3.2 The thermal overload protection devices, integral with the motor starter, of each valve listed in Table 3.8-2 shall be OPERABLE.
APPLICABILITY: Whenever the motor operated' valve is required to be OPERABLE.
y ACTION:
With one or more of the thermal overload protection devices inoperable, declare the affected valve (s) inoperable and apply the ACTION Statement to the affected valve (s).
SURVEILLANCE REQUIREMENTS
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4.8.3.2 The above required thermal overload protection devices shall be
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demonstrated OPERABLE:
a.
At least once per 18 months by the performance of a CHANNEL CALIBRA-TION of a representative sample of at least 25% of all thermal overload devices which are not bypassed, such that each non-bypassed device is calibrated at least once per 6 years.
i SEQUOYAH.- UNIT 1.
3/4 8 Amendment No.33 l
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I TABLE 3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTEC ION Valve No.
Function 1-FCV-62-63 Isolation for Seal Water Filter 1-FCV-62-138 Safe Shutdown Redundancy (CVCS) 1-FCV-62-98 ECCS Operation 1-FCV-62-99 ECCS Operation 1-FCV-62-90 ECCS Operation 1-FCV-62-91 ECCS Operation 1-FCV-62-61 Cont. Isolation 3
1-LCV-62-132 ECCS Operation 1-LCV-62-133 ECCS Operation 1-LCV-62-135 ECCS Operation 1-LCV-62-136 ECCS Operation 1-FCV-74-1 Open for Normal Plant Cooldown 1-FCV-74-2 Open for Normal Plant Cooldown 1-FCV-74-3 ECCS Operation 1-FCV-74-21 ECCS Operation 1-FCV-74-12 RHR Pump, Mini-flow Protects Pump 1-FCV-74-24 RHR Pump, Mini-flow Protects Pump l
1-FCV-74-33 ECCS Operation
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1-FCV-74-35 ECCS Operation 1-FCV-63-7 ECCS Operation 1-FCV-63-6 ECCS Operation i
1-FCV-63-156 ECCS Flow Path 1-FCV-63-157 ECCS Flow Path
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1-FCV-63-39 BIT Injection l
1-FCV-63-40 BIT Injection 1-FCV-63-25 BIT Injection 1-FCV-63-26 BIT Injection 1-FCV-63-118 RCS. Pressure Boundary l
1-FCV-63-98
~RCs Pressure Boundary l
1-FCV-63-80 RCS Pressure Boundary 1-FCV-63-67
' RCS Pressure Boundary 1-FCV-63-1 ECCS Operation 1-FCV-63-72 ECCS Flow Path from Cont. Sump 1-FCV-63-73 ECCS Flow Path from Cont. Sump 1-FCV-63-8 ECCS Flow Path 1-FCV-63-11 ECCS Flow Path 1-FCV-63-93 ECCS Cooldown Flow Path 1-FCV-63-94.
ECCS Cooldown Flow Path 1-FCV-63-172 ECCS Flow Path 1-FCV-63-5 ECCS Flow Path 1-FCV-63-47 Train Isolation 1-FCV-63-48 Train Isolation 1-FCV-63-4 SI Pump Mini-flow 1-FCV-63-175 SI Pump Mini-flow SEQUOYAH - UNIT 1 3/4 8-35 Amendme'nt No. 33 s
l TABLE 3.8-2 (Continued)
)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION l
Valve No.
Function l
l 1-FCV-63-3 SI Pump Mini-flow i
1-FCV-63-152 ECCS Recirc 1-FCV-63-153 ECCS Recirc 1-FCV-63-22 ECCS Recirc 1-FCV-3-33 Quick Closing Isolation 1-FCV-3-47 Quick Closing Isolation 1-FCV-3-87 Quick Closing Isolation 1-FCV-3-100 Quick Closing Isolation 1-FCV-1-15 Stm Supply to Aux FWP turbine 1-FCV-1-16 Stm Supply to Aux FWP turbine 1-FCV-3-179A ERCW Sys Supply to Pump 1-FCV-3-1798 ERCW Sys Supply to Pump 1-FCV-3-136A-ERCW Sys Supply to Pump 1-FCV-3-1368 ERCW Sys Supply to Pump 1-FCV-3-116A ERCW Sys Supply to Pump 1-FCV-3-1168 ERCW Sys Supply to Pump 1-fCV-3-126A ERCW Sys Supply to Pump 1-FCV-3-126B ERCW Sys Supply to Pump 1-FCV-70-133 Isolation for RCP Oil Coolers & Therm B
'_".^ ':
l 1-FCV-70-139 Isolation for RCP Oil Coolers & Therm B l
1-FCV-70-4 Isolation for Non-Essential Loads l.
1-FCV-70-143
-Isolation for Excess Letdown Ht Xchngr.
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1-FCV-70-92 Isolation for RCP 011 Coolers & Therm B 1-FCV-70-90 Isolation for RCP Oil Coolers & Therm B 1-FCV.70-87 Isolation for RCP Oil Coolers & Therm B 1-FCV-70-89 Isolation for RCP Oil Coolers & Therm B 1-FCV-70-140 Isolation for RCP Oil coolers & Therm B 1-FCV-70-134 Isolation for RCP Oil Coolers & Therm B 1-FCV-67-67*
DG St Ex
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2-FCV-67-65*
DG Ht Ex 1-FCV-67-66*
DG Ht Ex 2-FCV-67-68*
DG Ht Ex 1-FCV-67-123 CSS Ht Ex Supply
'l-FCV-67-125
_ CSS Ht Ex Supply 1-FCV-67-124 CSS Ht Ex Discharge 1-FCV-67-126 CSS Ht Ex Discharge 0-FCV-67-151*
CCW Ht Ex Throttling 0-FCV-67-152*-
CCW Ht Ex Throttling 2-FCV-67-146 CCW Ht Ex Throttling.
l 2-FCV-67-223 Isolation of 1B/2A HDR's i
1-FCV-67-83 Cont.~ Isol. Lower 1-FCV-67-88 Cont. Isol. Lower l
1-FCV-67-87 Cont. Isol. Lower i
1-FCV-67-424*
.CCW Ht Ex Isolation
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1-FCV-67-478*
- Common.to Units 1 & 2 SEQUOYAH - UNIT'1 3/4 8-36 Amendment No. 33
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TABLE 3.8-2 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION Valve No.
Function 1-FCV-67-95 Cont. Isol. Lower 1-FCV-67-96 Cont. Isol. Lower 1-FCV-67-91 Cont. Isol. Lower 1-FCV-67-103 Cont. Isol. Lower 1-FCV-67-104 Cont. Isol. Lower 1-FCV-67-99 Cont. Isol. Lower 1-FCV-67-111 Cont. Isol. Lower 1-FCV-67-112 cont. Isol. Lower T
1-FCV-67-107 Cont. Isol. Lower 1-FCV-67-130 Cont. Isol. Upper 1-FCV-67-131 Cont. Isol. Upper 1-FCV-67-295 Cont. Isol. Upper 1-FCV-67-134 Cont. Isol. Upper 1-FCV-67-296 Cont. Isol. Upper 1-FCV-67-133 Cont. Isol. Upper 1-FCV-67-139 Cont. Isol. Upper 1-FCV-67-297 Cont. Isol. Upper 1-FCV-67-138 Cont. Isol. Upper
- + -
1-FCV-67-142 Cont. Isol. Upper
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1-FCV-67-298 Cont. Isol. Upper 1-FCV-67-141 Cont. Isol. Upper 1-FCV-72-21 Cont. Spray Pump Suction
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1-FCV-72-22 Cont. Spray Pump Suction 1-FCV-72-20 Cont. Spray Pump Suction 1-FCV-72-23 Cont. Spray Pump Suction 1-FCV-72-2 Cont. Spray Isol.
1-FCV-72-39 Cont. Spray Isol.
1-FCV-72-40 RHR Cont. Spray Isol.
1-FCV-72-41 RHR-Cont. Spray Isol.
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SEQUOYAH - UNIT 1
'3/4 8-37 Amendment No. 33 k.
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ELECTRICAL POWER SYSTEMS l
BASES A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS (Continue'd) limits for each connected cell for float voltage and specific g'ravity, greater than 2.13 volts and not more than.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than.010 below the manufacture's full charge specific gravity, ensures the OPERABILITY and capability of the battery.
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8-2 is permitted for up to 7 i
days.
During this 7 day period:
(1) the allowable values for electrolyte 3
level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than.020 below the manufacturer's recommended full charge specific gravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity, ensures that an individual cell's specific gravity i
will not be more than.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual-cgil's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
q.7
^m 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors aYe-protected by either de-energizing circuits not required during reactor operation or by-demonstrating the OPERABILITY of primary and backup overcurrent protection
' circuit breakers during periodic surveillance.
The surveillance requirements applicable to lower voltage circuit breakers i
and fuses provides assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturers brand of circuit breakers and/or fuse.
Each manufacturer's molded case and-metal case circuit breakers and/or fuses are grouped into representative samples which are then tested on' a rotating basis to ensure that all breakers and/or fuses are tested.
If a wide variety exists within any manufacturer's brand of circuit breakers and/or fuses, it.is necessary to divide that manufacturer's breakers and/or fuses into groups,and treat each group as a separate type of breaker of fuses for l
surveillance purposes.
The OPERABILITY of the motor operated valves thermal _ overload protection j
ensures that the thermal overload protection devices will not prevent safety related valves from performing their-function.
The Surveillanca Requirements for demonstrating the OPERA 8ILITY of these devices are in accor1ance with Regulatory Guide 1.106 " Thermal Overload Protection for Electri.: Motors on Motor Operated Valves",' Revision.1, March 1977.-
Circuit breakers actuated by fault currents are usecJ as isolation devices in this' plant.
The.0PERABILITY of these circuit breakers ensures that the 1E busses will be protected in the event of faults'in nonqualified. loads powered by the busses.
-SEQUOYAH - UNIT 1 B 3/4 8-2
' Amendment No. 33
dN UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION g
l WASHINGTON, D. C. 20555 k*****,/
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.'25 License No. DPR-79 l
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated July 1, July 21, October 24, and November 28, 1983, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with.the license, as amended,
- -- - e the provisions of the Act, and the rules and regulations of the.Com-mission; C.
There is reasonable assurance (i) that the activities authorized by
~ ~
1 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby-amended by page changes to-the Appendix A l
Technical Specifications as indicated in the attachment to this license amend-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 25, are hereby incorporated into the license.
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7-l The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief g
Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance: March 29, 1984 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
h Amended Page 3/4 2-17 3/4 3-27a 3/4 6-10 3/4 8-33 3/4 8-34 3/4 8-35 l
3/4 8-36 B3/4 8-3 p -
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TABLE 3.2-1 NIS DNB PARAMETEh5 S!?
LIMITS C5 4 Loops In 3 Loops In Opera-PARAMETER Operation tion to Reactor Coolant System T,yg
< 583 F Pressurizer Pressure,
> 2220 psia
- 1 1
R*
7 C
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" Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL g
POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER, physics test, or performance of surveillance requirement 4.1.1.3.b.
c+
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- Limits pending NRC approval of 3 loop operation.
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TABLE 3.3-4 (Ccntinued)
Xl ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS S
o g
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- b.
6.9 kv Shutdown Board-Degraded E
Voltage 4
m 1.
Voltage Sensors 6560 volts 6560 volts i 33 volts 2.
Diesel Generator Start ind Load Shed Timer 300 seconds 300 seconds i 30 seconds 3.
SI/ Degraded Voltage Logic Enable Timer 10 seconds 10 seconds 1 0.5 seconds 8.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS-R*
a.
Pressurizer Pressure Y
Manual Block of Safety Injection P-1151970 psig 5 1980 psig ti e
1
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$e
. 2F
- NOTE:
This technical specification.is to be implemented during the startup following the 1st refueling g.
- outage.
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CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment ~ average air temperature shall be maintained:
between 85'F* and 105'F in the containment upper compartment, and a.
b.
between 100*F* and 125'F in the containment lower compartment.
APPLICABILITY:
MODES 1, 2, 3 and 4.
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ACTION:
With the containment average air temperature not conforming to the above limits, restore the air temperature to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
' SURVEILLANCE REQUIREMENTS
'^'-
4'.6.1.5.1 The primary containment upper compartment average air. temperature
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shall be the weighted average ** of all ambient air temperature monitoring stations located in the upper compartment.
As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the following locations:
Location a.
-Elev. 743 ft.
b.
Elev. 786 ft.
c.
Elev. 786 or 845 ft.
4.6.1.5.2 The primary co'ntainment lower compartment average air tedperature shall be the weighted average ** of all-ambient air temperature monitoring stations located in the lower compartment.
As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the following locations:
Location-a.
Elev. 722 ft.
b.
Elev. 700 ft.
c.
Elev. 685 or 703 ft.
Lower limit may be reduced to 60*F in MODES 2, 3 and 4.
- The weighted average is the sum of each temperature multiplied by its respectivo containment volume fraction.
In the event of inoperable
. temperature'senso,r(s), the weighted average shall be taken as the reduced
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total divided by one minus the volume fraction represented by the sensor (s)
L out of service.
s SEQUOYAH - UNIT 2 3/4 6-10 Amendment No. 25 L
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ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION T
LIMITING CONDITION FOR OPERATION 3.8.3.2 The thermal overload protection devices, integral with the motor starter, of each valve listed in Table 3.8-2 shall be OPERABLE.
APPLICABILITY:
Whenever the motor operated valve is required to be OPERABLE.
ACTION:
With one or more of the thermal overload protection devices inoperable, declare the affected valve (s) inoperable and apply the ACTION Statement to the affected valve (s).
SURVEILLANCE REQUIREMENTS 4.8.3.2 The above required thermal overload protection devices shal'1 be demonstra.ca OPERABLE:
At least once per 18 months by the perform ~ance 'of'a CHANNEL a.
' ~ ' "
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CALIBRATION of a representative sample of at least 25% of all thermal overload devices which are not bypassed, such that each non-bypassed device is calibrated at least once per 6 years.
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SEQUOYAH - UNIT 2 3/4 8-33 Amendment No.25 a
TABLE 3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION Valve No.
Function 2-FCV-62-63 Isolation for Seal Water Filter 2-FCV-62-138 Safe Shutdown Redundancy (CVCS) 2-FCV-62-98 ECCS Operation 2-FCV-62-99 ECCS Operation 2-FCV-62-90 ECCS Operation 2-FCV-62-91 ECCS Operation 2-FCV-62-61 Cont. Isolation 2-FCV-62-132 ECCS Operation 2-FCV-62-133 ECCS Operation 2-LCV-62-135 ECCS Operation 2-LCV-62-136 ECCS Operation 2-FCV-74-1 Open for Normal Plant Cooldown 2-FCV-74-2 Open for Normal Plant Cooldown 2-FCV-74-3 ECCS Operation 2-FCV-74-21 ECCS Operation 2-FCV-74-12 RHR Pump, Mini-flow Protects Pump 2-FCV-74-24 RHR Pump, Mini-flow Protects Pump 2-FCV-74-33 ECCS Operation es r 2-FCV-74-35 ECCS Operation 2-FCV-63-7 ECCS Operation 2-FCV-63-6 ECCS Operation 2-FCV-63-156 ECCS Flow Path
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2-FCV-63-157 ECCS Flow Path 2-FCV-63-39 BIT Injection.
2-FCV-63-40 BIT Injection 2-FCV-63-25 BIT Injection 2-FCV-63-26 BIT Injection 2-FCV-63-118 RCS Pressure Boundary 2-FCV-63-98 RCS, Pressure Boundary 2-FCV-63-80 RCS Pressure Boundary
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2-FCV-63-67 RCS Pressure Boundary l
2-FCV-63-1 ECCS Operation l
2-FCV-63-72 ECCS Flow Path from Cont. Sump l
2-FCV-63-73 ECCS Flow Path from Cont. Sump 2-FCV-63-8 ECCS Flow Path 2-FCV-63-11 ECCS Flow Path 2-FCV-63-93 ECCS Cooldown Flow Path 2-FCV-63-94 ECCS Cooldown Flow Path 2-FCV-63-172 ECCS Flow Path 2-FCV-63-5 ECCS Flow Path 2-FCV-63-47 Train Isolation 2-FCV-63-48 Train Isolation 2-FCV-63-4 SI Pump Mini-flow 2-FCV-63-175
.SI Pump Mini-flow
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SEQUOYAH - UNIT 2 3/4 8-34' Amendment No.25
I TABLE 3.8-2 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION Valve No.
Function 2-FCV-63-3 SI Pump Mini-flow 2-FCV-63-152 ECCS Recirc 2-FCV-63-153 ECCS Recirc 2-FCV-63-22 ECCS Recirc 2-FCV-3-33 Quick Closing Isolation 2-FCV-3-47 Quick Closing Isolation 2-FCV-3-87 Quick Closing Isolation
.2-FCV-3-100 Quick Closing Isolation 2-FCV-1-15 Stm Supply to Aux FWP turbine 2-FCV-1-16 Stm Supply to Aux FWP turbine 2-FCV-3-179A ERCW Sys Supply to Pump 2-FCV-3-179B ERCW Sys Supply to Pump 2-FCV-3-136A ERCW Sys Supply to Pump 2-FCV-3-136B ERCW Sys Supply to Pump 2-FCV-3-116A ERCW Sys Supply to Pump 2-FCV-3-1168 ERCW Sys Supply to Pump 2-FCV-3-126A ERCW Sys Supply to Pump 2-FCV-3-126B ERCW Sys Supply to Pump 2-FCV-70-133 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-139 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-4 Isolation for Non-Essential Loads 2-FCV-70-143 Isolation for Excess Letdown Ht Xchngr 2-FCV-70-92 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-90 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-87 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-89 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-140 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-134 Isolation for RCP Oil Coolers & Therm B 1-FCV-67-67*
.DG Ht Ex 2-FCV-67-65*
DG Ht Ex l
1-FCV-67-66*
DG Ht Ex l
2-FCV-67-68*
DG Ht Ex l
2-FCV-67-123 CS Ht Ex Supply 2-FCV-67-125 CS Ht Ex Supply 2-FCV-67-124 CS Ht Ex Discharge 2-FCV-67-126 CS Ht Ex Discharge-i 0-FCV-67-151*
CCW Ht Ex Throttling 0-FCV-67-152*
CCW Ht Ex Throttling 2-FCV-67-146 CCW Ht Ex Throttling 1-FCV-67-424*
CCW Ht Ex Isolation 1-FCV-67-478*
Isolation of IB ERCW HDR 2-FCV-67-223 Isolation of 1B/2A HDR's 2-FCV-67-83 Cont. Isol. Lower 2-FCV-67-88 Cont. Isol. Lower 1
2-FCV-67-87 Cont. Isol. Lower
^ Common to Units 1 & 2.
SEQUOYAH - UNIT 2 3/4 8-35 Amendment No. 25 '
I TABLE 3.8-2 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION Valve No.
Function l
2-FCV-67-95 Cont. Isol. Lower 2-FCV-67-96 Cont. Isol. Lower 2-FCV-67-91 Cont. Isol. Lower 2-FCV-67-103 Cont. Isol. Lower 2-FCV-67-104 Cont. Isol. Lower 2-FCV-67-99 Cont. Isol. Lower 2-FCV-67-111 Cont. Isol. Lower i
2-FCV-67-112 Cont. Isol. Lower l'
2-FCV-67-107 Cont. Isol. Lower 2-FCV-67-130 Cont. Isol. Upper 2-FCV-67-131 Cont. Isol. Upper 2-FCV-67-295 Cont. Isol. Upper 2-FCV-67-134 Cont. Isol. Upper l
2-FCV-67-296 Cont. Isol. Upper 2-FCV-67-133 Cont. Isol. Upper 2-FCV-67-139 Cont. Isol. Upper 2-FCV-67-297 Cont. Isol. Upper 2-FCV-67-138 Cont. Isol. Upper 2-FCV-67-142 Cont. Isol. Upper
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l 2-FCV-67-298 Cont. Isol. Upper 2-FCV-67-141 Cont. Isol. Upper 2-FCV-72-21 Cont. Spray Pump Suction 2-FCV-72-22 Cont. Spray Pump Suction 2-FCV-72 Cont. Spray Pump Suction l
2-FCV-72-23 Cont. Spray Pump Suction 2-FCV-72-2 Cont. Spray Isol.
2-FCV-72-39 Cont. Spray Isol.
2-FCV-72-40 RHR Cont. Spray Isol.
2-FCV-72-41
.RHR, Cont. Spray Isol.
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SEQUOYAH - UNIT 2-3/4 8-36 Amendment No. 25
BASES T
ELECTRICAL EQUIPMENT PROTECTIVE DEVICES (Continued)
The OPERABILITY of the motor operated valves thermal overload protection ensures that the thermal overload protection devices will not prevent safety related valves from performing their function.
The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106 " Thermal Overload Protection for Electric Motors on Motor Operated Valves", Revision 1, March 1977.
Circuit breakers actuated by fault currents are used as isolation devices in this plant, ihe OPERABILITY of these circuit breakers ensures that the IE busses will be protected in the event of faults in non qualified loads powered by the busses.
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I SEQUOYAH - UNIT 2 B 3/4 8-3 Amendment No. 25 i