ML20247K144
| ML20247K144 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/16/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247K149 | List: |
| References | |
| NUDOCS 8906010228 | |
| Download: ML20247K144 (12) | |
Text
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. UNITED STATES -
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g NUCLEAR REGULATORY COMMISSION 4 5 1j
. WASHINGTON, D. C. 20555 '
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UNION. ELECTRIC. COMPANY CALLAWAY. PLANT,. UNIT 1 DOCKET.NO..STN.50-483 AMENDMENT TO FACILITY OPERATING. LICENSE Amendment No. 45 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, the licensee) dated January 14, 1986 as supplemented by letter dated April 14 and May 5, 1989 complies with the standards and requirements
'of the Atomic Energy Act of 1954, as ame.nded'(the Act), and the Comission'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 Com-mission; 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 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 amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
i i
8906010228 890516
)
PDR ADOCK 05000483 i
P PDC I
1-t.-
2 (2) Technical Specifications.and Environmental. Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 45, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective upon issuance and shall be_ implemented within 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
John N.Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation i
Attachment:
' Changes to the Technical Specifications Date of Issuance: May 16, 1989 l
l
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 45 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified 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 reintain document completeness.
REMOVE INSERT X
X XVI XVI 3/4 3-49 3/4 3-49 3/4 7-9b B 3/4 7-3 8 3/4 7-3 B 3/4 7-3a l
i 1
INDEX L
LIM 111NG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE
, EMERGENCY CORE COOLING SYSTEMS (Continued) 3/4.5.5 REFUELING WATER STORAGE TANK...............
3/4 5-10 3/4.6 CONTAINMENT SYSTEMS
.3/4.6.1 PRIMARY CONTAINMENT Containment Integrity...................................
3/4 6-1 Containment Leakage......................................
3/4 6-2 Containment Air Locks....................................
3/4 6-4 Internal Pressure........................................
3/4 6-6 A i r T emp e ra t u re..........................................
3/4 6-7 Containment Vessel Structural Integrity..................
3/4 6-8 Containment Ventilation System...........................
3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.................................
3/4 6-13 Spray Additive System....................................
3/4 6-14 j
Containment Cooling System..........
3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................
3/4 6-16 TABLE 3.6-1 CONTAINMENT ISOLATION VALVES............
3/4 6-18 3/4.6.4 COMBUSTIBLE GAS CONTROL 3/4 6-31 Hydrogen Analyzers..............................
3/4 6-32 llydrogen Control Systems.................................
,3/4. / PLANI SYSTEMS 3/4. 7.1 TURBINE CYCLE 3/4 7-1 Safety Valves.........................................
IABil 3,7-I MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION...................
3/4 7-2 CALIAWAY - UNIT 1 IX
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE PLANT SYSTEMS (Continued)
TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 Auxili ary Feedwater Sys tem...............................
3/4 7-4 Condensate Storage Tank..................................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.........................
3/4 7-8 Main Steam Li ne Isolation Va1 ves.........................
3/4 7-9 Main Feedwater System....................................
3/4 7-9a Steam Generator Atmospheric Steam Dump Valves............
3/4 7-9b 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... 3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...........................
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK.......................................
3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................
3/4 7-14 3/4.i.7 EMERGENCY EXHAUST SYSTEM................................. 3/4 7-17 i
3/4.7.8 SNUBBERS.................................................
3/4 7-19 FIGURE 4.7-1 SAMPLING PLAN 2) FOR SNUBBER FUNCTIONAL TEST.........
3/4 7-24 3/4.7.9 SEAL ED SOURC E CONTAMINATION..............................
3/4 7-2S 3/4.7.10 Deleted 3/4.7.11 Deleted 3/4.7.12 AREA TEMPERATURE MONITORING..............................
3/4 7-37 I
TABLE 3.7-4 AREA TEMPERATURE MONITORING........................... 3/4 7-38
)
CALLAWAY - UNIT 1 X
Amendment No. E, 45 I
l 1
a
INDEX
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i BASES SECTION PAGE REACTOR COOLANT SYSTEM (Continued) 3/4.4.5 STEAM GENERATORS.........................................
B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...........................
B 3/4 4-4 3/4.4.7 CHEMISTRY................................................
B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY........................................
B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..............................
B 3/4 4-6 TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS..........................
B 3/4 4 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE........................
B 3/4 4-12 FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER ON SNIFT OF RTNDT FOR REACTOR VESSEL STEELS EXPOSED TO IRRADIATION AT 550'F...........................
B 3/4 4-13 3/4.4.10 STRUCTURAL INTEGRITY.....................................
B 3/4 4-17 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................
B 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.............................................
B 3/4 5-1 3/4.5.2, 3/4.5.3, and 3/4.5.4 ECCS SUBSYSTEMS.....................
B 3/4 5-1 3/4.5.5 REFUELING WATER STORAGE TANK.............................
B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT......................................
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.....................
B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATI0H VALVES.............................
B 3/4 6-4 3/4.6,4 COMBUSTIBLE GAS CONTR0L..................................
B 3/4 6-4 CALLAWAY - UNIT 1 XV
INDEX BASES SECTION
.PAGE 1
3/4.7 PLANT SYSTEMS 1
3/4.7.1 TURBINE CYCLE........................................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION......... B 3/4 7-3a 3/4.7.3 COMPONENT COOLING WATER SYSTEM.......................... B 3/4 7-3a 3/4.7.4 ES 3ENTI AL SERVICE WATER SYSTEM.......................... B 3/4 7-3a 3/4.7.5 ULTIMATE HEAT SINK...................................... B 3/4 7-3a 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...............
B 3/4 7-4 3/4.7.7 EMERGENCY EXHAUST SYSTEM................................ B 3/4 7-4 3/4.7.6 S NU B B E R S................................................ B 3 / 4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION............................. B 3/4 7-6 3/4.7.10 Deleted 3/4.7.11 Deleted 3/4.7.12 AREA TEMPERATURE MONITORING............................. B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8. 2., and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION......................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................. B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4. 9.1 BORON CONCENTRATION..................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 3/4.9.3 DE C AY T I ME............................................... B 3/ 4 9 - 1 3/4.9.4 CONTAINME NT BUILDING PENETRATIONS....................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS.......................................... B 3/4 9-1 CALLAWAY - UNIT 1 XVI Amendment No. 30, 45
INSTRUMENTATION REMOTE SHUTDOWP INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels given in Table 3.3-9 and the auxiliary shutdown panel (ASP) controls shall be OPERABLE with readouts displayed external to the control room.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With the number of OPERABLE remote shutdown monitoring channels less than the Minimum Channels OPERABLE as required by Table 3.3-9, restore the inoperable channel (s) to OPERABLE status within 7 days; otherwise, be in at least HOT STANDBY within the text 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 />.
b.
With the ASP controls inoperable, restore the inoperable ASP controls to OPERABLE status within 7 days; otherwise, 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 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 />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies given in Table 4.3-6.
4.3.3.5.2 The ASP controls shall be demonstr?ted OPERABLE at least once per 18 months by operating each actuated component from the ASP.
4.3.3.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven auxiliary feedwater pump or the atmospheric steim dump valves.
l CALLAWAY - UNIT 1 3/4 3-49 Amendment No. 45
4 TABLE 3.3-9 REMOTE SHUTOOWN MONITORING INSTRUMENTATION TOTAL NO.
MINIMUM READOUT OF CHANNELS INSTRUMENT LOCATION CHANNELS OPERABLE 1.
- 2 1
2.
Reactor Coolan', Temperature-Cold Leg ASP
- 4 1
3.
Scurce Range, Neutron Flux #
- 2 1
4.
Reactor Trip Breaker Indication RTS**
1/ trip breaker 1/ trip breaker 5.
Reactor Coolant Temperature -
- 2 1
Hot Leg 6.
Reactor Coolant Pump Breakers 1/ pump 1/ pump 7,
Pressurizer Pressure ASP
- 1 1
8.
Pressurizer Level ASP
- 2 1
9.
Steam Generator Pressure ASP
- 2/stm. gen.
1/stm. gen.
10.
Steam Generator Level ASP
- 2/stm. gen.
1/stm. gen.
11.
Auxiliary Feedwater Flow Rate ASP
- 4 1
- 12. Auxiliary Feedwater Suction Pressure ASP
- 3 1
" Auxiliary Shutdown Panel
- Reactor Trip Switchgear
- 13.8 kV Switchgear
- Not required OPERABLE in MODE 1 or in iLDE 2 above P-6 setpoint.
CALLAWAY - UNIT 1 3/4 3-50 l
t _.
L PLANT SYSTEMS STEAM GENERATOR ATMOSPHERIC STEAM DUMP VALVES LIMITING CONDITION FOR OPERATION I
3.7.1.7 At loast three steam generator atmospheric steam dump valves (ASD's) shall be OPERABLE.
APPLICABILITY: Modes 1, 2 and 3.
ACTION:
a.
With one of the required ASD's inoperable due to causes other than excessive seat leakage, within 7 days restore the ASD to OPERABLE status, or be in HOT STANDBY within 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 />, b.
With more than one of the required ASD's inoperable due to causes other than excessive seat leakage, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore at least two of the required ASD's to OPERABLE status or be in-H0T 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 />.
c.
With one or more of the required ASD's inoperable because of excessive seat leakage, close the associated block valve (s) and restore the ASD to OPERABLE status within 30 days, or be in HOT STANDBY within 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 />.
d.
The provisions of Specification 3.0.4 are not anplicable.
SURVEILLANCE REQUIREMENTS 4.7.1.7 No additional requirements other than those required by Specification 4.0.5.
CALLAWAY - UNIT 1 3/4 7-9b Amendment No. 45
)
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 "ill blow down in the event of. a steam line rupture.
This restriction is required to:
(1)minimizethepositive 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 rupture occurs within containment.
The OPERABILITY
.of the main steam line isolation 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.
3/4.7.1.7 STEAM GENERATOR ATMOSPHERIC STEAM DUMP VALVES
.The OPERABILITY of the steam generator atmospheric steam dump valves (ASD's) ensures that the reactor decay heat can be dissipated to the atmosphere in the event of a steam generator tube rupture and loss of off-site power and that the Reactor Coolant System can be cooled down for Residual Heat Removal System operation.
The number of required ASDis assures that the subcooling can be achieved,' consistent wit! the assump-tions used in the steam generator tube rupture analysis, to facilitate equalizing pressures between the Reactor Coolant System and the faulted steam generator.
For cooling the plant to RHR initiation conditions, only one ASD is requireds. In this case, with three ASD's OPERABLE, if the single failure of one ASD occurs and another ASD is assumed to be associated with the faulted steam generator, one ASD remains available for required heat removal.
Each ASD is equipped with a manual block valve (in the auxiliary building) to provide a positive shutoff capability should an ASD develop leakage.
Closure of the block valves of all ASD's because of excessive seat leakage does not endanger the reactor core; consistent with plant CALLAWAY - UNIT 1 B 3/4 7-3 Amendment No. JB 45
PLANT SYSTEMS.
BASES 3/4.7.1.7 STEAM GENERATOR ATMOSPHERIC' STEAM DUMP VALVES (Continued) accident and transient analyses, decay heat can be dissipated with the main steamline safety valves or a block valve can be opened manually in the auxGiary building and the ASD can be used to control release of steam to the atmosphere.
For the steam generator tube rupture event, primary to secondary leakage can be terminated by depressurizing the Reactor Coolant System with the pressurizer power operated relief valves.
3/4.7.2 STEAM GENERATOR PRESSURE /TEMPERATJJRE LIMITATION The limitation on' steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70'F and 200 psig are based on a steam generator RT f 60 F and are NDT sufficient 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 OPERABILITY 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 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) mitigete the effects of accident conditions within acceptable limits l
CALLAWAY - UNIT 1 B 3/4 7-3a Amendment No. 45
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