ML20207S512
| ML20207S512 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/10/1987 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207S513 | List: |
| References | |
| NUDOCS 8703190588 | |
| Download: ML20207S512 (14) | |
Text
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UNION ELECTRIC COMPANY CAllAWAY PLANT, UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICFNSE Amendment No. 18 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Callaway Plant, Unit 1 (the facility) Facility Operating License No NPF-30 filed by Union Electric Company (the licenseel dated September 29, 1986, and supplemented February 26, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter It l
0.
The facility will operate in conformity with the acolication, l
the provisions of the Act, and the rules and regulations of the i
Comissions C.
There is reasonable assurance (1) that the activities authorized l
by this amendment can be conducted without endangering the health i
and safety of the publict 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 publict 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 amended by changes to the Technical Speciff-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
1 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.18, and the Environmental Protection Plan 1
8703190588 870310 PDR ADOCK 05000403 Y
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F contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. Union Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Paul O'Connor, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 10, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 18 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identitied below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Corresponding overleaf pages are provided to maintain document completeness.
Amended Page Overleaf Page 3/4 3-29 3/4 3-30 3/4 3-31 3/4 3-32 3/4 6-30 3/4 6-29 3/47-9a(newpage) 3/4 7-9 3/4 7-10 B3/4 7-3 B3/4 7-4 0
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TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING $1GNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.
Manual Initiation a.
Safety Injection (ECCS)
N.A.
b.
Containment Spray N.A.
c.
Phase "A" Isolation N.A.
d.
Phase "B" Isolation N.A.
e.
Containment Purge Isolation N.A.
f.
Steam Line Isolation N.A.
g.
Feedwater Isolation N.A.
h.
Auxiliary Feedwater N.A.
i.
Essential Service Water N.A.
j.
Containment Cooling N.A.
k.
Control Room Isolation N.A.
1.
Reactor Trip N.A.
m.
Emergency Diesel Generators N.A.
n.
Component Cooling Water N. A.
o.
Turbine Trip N.A.
2.
Containment Pressure-Nigh-1 a.
Safety Injection (ECCS) 1 29(1)/12I4)
- 1) Reactor Trip 12
- 2) Feedwater Isolation 1 2(5)
- 3) Phase "A" Isolation 1 1.5(5)
- 4) Auxiliary Feedwater 1 60
- 5) Essential Service Water
< 60(1)
- 6) Containment Cooling 1 60(1) i
- 7) Component Cooling Water N.A.
- 8) Emergency Diesel Generators 1 14(6)
- 9) Turbine Trip N.A.
CALLAWAY - UNIT 1 3/4 3-29 Amendment No. 18
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.
Pressurizer Pressure-Low a.
Safety Injection (ECCS) 5 29(1)/12(4)
- 1) Reactor Trip
<2
- 2) Feedwater Isolation 2(5) l
- 3) Phase "A" Isolation
{2(5)
< 60
- 5) Essential Service Water 7 60(1)
- 6) Containment Cooling h60(1)
- 7) Component Cooling Water N.A.
1
- 8) Emergency Diesel Generators i 14(6)
- 9) Turbine Trip N.A.
4.
Steam Line Pressure-Low 1
a.
Safety Injection (ECCS) 5 24(3)/12(4) 1)
<2 2)
Feedwater Isolation 2(5) h2(5) 3)
Phase "A" Isolation 4)
Auxiliary Feedwater 1 60 5)
Essential Service Water
< 60(1) 6)
Containment Cooling h60(1) 7)
Component Cooling Water N.A.
8)
Emergency Diesel Generators 1 14(0) 9)
Turbine Trip N.A.
b.
Steam Line Isolation 1 2(5)
CALLAWAY - UNIT 1 3/4 3-30 Amendment No. 18
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 5.
Containment Pressure-High-3 a.
Containment Spray 5 32(1)/20(2) b.
Phase "B" Isolation i 31.5 6.
Containment Pressure-High-2 Steam Line Isolation i 2(5) 7.
Steam Line Pressure-Negative Rate-High Steam Line Isolation i 2(5) 8.
Steam Generator Water Level-High-High a.
Feedwater Isolation i 2(5) b.
Turbine Trip i 2.5 9.
Steam Generator Water Level-Low-Low a.
Start Motor-Driven Auxiliary Feedwater Pumps 1 60 b.
Start Turbine-Driven Auxiliary Feedwater Pump i 60 10.
Loss-of-Offsite Power Start Turbine-Driven Auxiliary Feedwater Pump N.A.
I 11.
Trip of All Main Feedwater Pumps Start Motor-Driven Auxiliary Feedwater Pumps N.A.
l CALLAWAY - UNIT 1 3/4 3-31 Amendment No. 18
TABLE 3.3-5 (Continued)
.]
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 12 Auxiliary Feedwater Pump Suction Pressure tow Transfer to Essential Service Water N.A.
13.
RWST Level-Low-Low Coincident with Safety Injection Automatic Switchover to Containment
~< 60 Sump 14.
Loss of Power a.
4 kV Bus Undervoltage-
~< 14 Loss of Voltage b.
4 kV Bus Undervoltage-
-< 144 Grid Degraded Voltage 15.
Phase "A" Isolation
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a.
Control Room Isolation N.A.
b.
Containment Purge Isolation
< 2(5)
TABLE NOTATIONS (1) Diesel generator starting and sequence loading delays included.
(2) Diesel generator starting delay not included. Offsite power available.
(3) Diesel generator starting and sequence loading delay included.
RHR pumps not included.
(4) Diesel generator starting and sequence loading delays not included.
Offsite power available. RHR pumps not included.
(5) Does not include valve closure time.
(6) Includes time for diesel to reach full speed.
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9 TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM TYPE LEAK ISOLATION TIME PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) 8.
Hand-Operated and Check Valves - (Continued)
P-58 EM V-006 Accumulator Fill Line C
N.A.
From SI Pumps P-49 EM V-010 SI Pump Disch to Cold A
N.A.
Leg 1 P-49 EM V-020 SI Pump Disch to Cold A
N.A.
Leg 2 P-49 EM V-030 SI Pump Disch to Cold A
N.A.
Leg 3 P-49 EM V 040 SI Pump Disch to Cold A
N.A.
Leg 4 P-88 EM 8815 BIT to RCS Cold Leg A
N.A.
Injection P-89 EN V-013 CTMT Spray Pump A A
N.A.
to CTMT Spray Nozzles P-66 EN V-0.7 CTMT Spray Pump B A
N.A.
to CTMT Spray Nozzles P-45 EP V-046 Accumulator Nitrogen C
N.A.
i Supply Line P-43 HD V-016 Auxiliary Steam to C
N.A.
Decon System-P-43 HD V-017 Auxiliary Steam to C
N.A.
Decon System l
P-63' KA V-039 Rx Bldg Service Air C
N.A.
l Supply P-63 KA V-118 Rx Bldg Service Air C
N.A.
Supply P-30 KA V-204 Rx Bldg Instrument C
N.A.
Air Supply 8'-98 Kii V-001 Breathing Air Supply C
N.A.
to Et ildg.
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TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM TYPE LEAK ISOLATION TIME PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) 8.
Hand-Operated and Check Valves - (Continued)
P-98 KB V-002 Breathing Air Supply C
N.A.
to Rx Bldg.
P-67 KC V-478 Fire Protection C
N.A.
Supply to RX Bldg P-57 SJ V-111 Liquid Sample from A,C N.A.
PASS to RCOT 9.
Other Automatic Valves P-1 AB-HV-11***
Mn. Stm. Isol.
A N.A P-2 AB-HV-14***
Mn. Stm. Isol.
A N.A P-3 AB-HV-17***
Mn. Stm. Isol.
A N.A.
P-4 AB-HV-20***
Mn. Stm. Isol.
A N.A.
P-5 AE-FV-42***
Mn. FW Isol.
A N.A.
P-6 AE-FV-39***
Mn. FW Isol.
A N.A.
P-7 AE-FV-40***
Mn. FW Isol.
A N.A.
P-8 AE-FV-41***
Mn. FW Isol.
A N.A.
P-9 BM-HV,4**
SG Blowdn. Isol.
A 10 P-10 EP-HV-1**
SG Blowdn. Isol.
A 10 P-11 BM-HV-2**
SG Blowdn. Isol.
A 10 P-12 BM-IIV-3**
SG Blowdn. Isol.
A 10
- The provisions of Specification 3.0.4 are not applicable.
- These valves are included only for table completeness. The requirements of Specification 3.6.3 do not apply; instead, the requirements of Specifica-tions 3.7.1.5 and 3.7.1.6 apply to the Main Steam Isolation Valves and Main Feedwater Isolation Valves, respectively.
CALLAWAY - UNIT 1 3/4 6-30 Amendment Nc.
18
PLANT SYSTEMS MAIN S1 LAM LINE ISOLATION VALVES
- LIMillNG CONDlil0N FOR OPERATION 3.7.1.5 Each main steam line isolation valve (MSLIV) shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
MODE 1:
With one MSLIV inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise be in 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 2 and 3:
With one MSLIV inoperable, subsequent operation in MODE 2 or 3 may proceed provided the isolation valve ~is maintained closed. Otherwise, be in 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 HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 7.1. 5 Each MSLIV shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
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PLANT SYSTEMS MAIN FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.6 Each main feedwater isolation valve (MFIV) shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
MODES 1 and 2: With one MFIV inoperable but open, operation may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise be in 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 />.
MODE 3:
With one MFIV inoperable, subsequent operation in Mode 3 may proceed provided the isolation valve is maintained closed.
Otherwise, be in HOT SHUTDOWN with the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.6 Each MFIV shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.
The provisions of specification 4.0.4 are not applicable for entry into MODE 3.
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l CALLAWAY - UNIT 1 3/4 7-9a Amendment No. 18
PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRE 55URE/ TEMPERATURE LIMITATION LIMITING COND1110N FOR OPERATION 3.7.2 The temperatures of both the reactor and secondary coolants in the steam generator shall be greater than 70 F when the pressure of either coolant in the steam generator is greater than 200 psig.
APPLICABILITY: At all times.
ACTION:
With the requirements of the above specification not satisfied:
a.
Reduce the steam generator pressure of the applicable side to less than or equal to 200 psig within 30 minutes, and b.
Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200 F.
SURVEILLANCE REQUIREMENTS
)
4.7.2 The pressure in each side of the steam generator shall be determined to be less than 200 psig at least once per hour when the temperature of either the reactor or secondary coolant is less than 70*F.
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PLANT SYSTEMS BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blow down in the event of a steam line rup-ture. This restriction is required to:
(1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rup-ture occurs within containment.
The OPERABILITY of the main steam line isola-tion valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analyses.
3/4.7.1.6 FEEDWATER ISOLATION VALVES The OPERABILITY of the feedwater isolation valves:
- 1) provides a pressure boundary to permit auxiliary feedwater addition in the event of a main steam or feedwater line break inside containment; and 2) ensure that no more than one steam generator will blow down in the event of a steam line rupture which a) minimizes the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and b) limits the pressure rise within containment.
The OPERABILITY of the feedwater isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analysis.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum j
allowable fracture toughness stress limits.
The limitations of 70 F and 200 psig are based on a steam generator RT of 60 F and are sufficient NDT to prevent brittle fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
Each independent CCW loop contains two 100% capacity pumps and, therefore, the failure of one pump does not affect the CPERABILITY of that loop.
3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM The OPERABILITY of the Essential Service Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.5 ULTIMATE HEAT SINK l
The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available either to:
(1) provide normal cooldown of the facility, or (2) mitigate the effects of accident conditions within acceptable limits.
CALLAWAY - UNIT 1 B 3/4 7-3 Amendment No. 18
1 PLANI SYSilMS IIASI $
ULTIMAll HE Al SINK (Cont inued)
The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis temperature and are consistent with the recommenda-tions of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants,"
March 1974.
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the Control Room Emergency Ventilation System ensures that:
(1) the ambient air temperature does not exceed the allowable tempera-ture for continuous-duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions. Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the charcoal adsorbers and HEPA filters. The OPERABILITY of this system in conjunction with Control Room design provisions is based un limiting the radiation exposure to personnel occupying the control room
-to b rems or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.7 EMERGENCY EXHAUST SYSTEM The OPERABILITY of the Emergency Exhaust System assures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. Operation of the system with the heaters operating to maintain low humidity using automatic control'for at least 10 continuous hours in a 31-day period is sufficient to reducy the buildupofmoistureonthecharcoalac{orbersandHEPAfilters. The ojeration of this system and the resultant ef fec., on offsite dosage calculations ;vas assumed in the safety analyses. ANSI W510-1975 will be used as a proc (dural sluide for surveillance testing.
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