ML20206K059
| ML20206K059 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/10/1987 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206K065 | List: |
| References | |
| NUDOCS 8704160254 | |
| Download: ML20206K059 (9) | |
Text
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' o uc jog UNITED STATES g
NUCLEAR REGULATORY COMMISSION g
y WASHINGTON, D. C. 20555
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UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1
_ DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE-j Arnendment No. 20 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Comission) 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 licensee) dated December 30, 1986, and supplemented March 13, 1987, complies with the standards and "y"
g 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 I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; s
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C.
There is reasonable assurance (1) 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 como defense and security or to the health and safety of the public; and E.
The issuance of this amendoent is in accordance with 10 CFR of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-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:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, and the Environmental Protection Plan 8704160254 870410 PDR ADOCK 05000483 P
, contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license, llnton Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
t 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
L Paul O'Connor, Project Manager i
PWR Project Directorate #4 I
Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1987 4
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ATTACHMENT TO LICENSE AMENDMENT N0.20 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 9 ages are provided to maintain document completeness.
Amended Page Overleaf Page 3/4 3-39 3/4 3-40 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 9-4 3/4 9-3 B 3/4 9-1 B3/4 9-2 is N1 1 "
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TABLE 3.3-6
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RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS E
N MINIMUM CHANNELS CHANNELS APPLICABLE
' ALARM / TRIP FUNCTIONAL UNIT e
TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION E
1.
Containment Gaseous Radioactivity-a.
RCS Leakage Detection N.A.
1 1,2,3,4 N. A.
29 (GT-RE-31 & 32) b.
Particulate N. A.
1 1,2,3,4 N.A.
29 l
Radioactivity-RCS Leakage Detection (GT-RE-31 & 32) 2.
Fuel Building w1 a.
Fuel Building Exhaust-Gaseous Radioactivity-1 2
w g
High (GG-RE-27 & 28) 30 b.
Criticality-High Radiation Level
- 1) Spent Fuel Pool 1
1 (SD-RE-37 or 38)
-< 15 mR/h 28
- 2) New Fuel Pool 1
1 (SD-RE-35 or 36)
-< 15 mR/h 28 p
3.
Control Room E
Air Inteke-Gaseous P.
Radioactivity-High 1
2 All 27 5
(GK-RE-04 & 05)
?
TABLE 3.3-6 (Continued)
TABLE NOTATIONS
- With fuel in the respective fuel storage pool.
- With irradiated fuel in the fuel storage areas or fuel building.
- Trip Setpoint concentration value (pCi/cm ) is,to be established such that 8
the actual submersion dose rate would not exceed 2 mR/h in the control room
- Trip Setpoint concentration valus (pCi/cin ) is to be established such that 3
the actual submersion dose rate would not exceed 4 mR/h in the fuel building.
ACTION STATEMENTS ACTION 26 - Deleted.
ACTION 27 - With the number of OPERABLE channels one less than the Minim Channels OPERABLE requirement, within I hour isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode.
ACTION 28 - With less than the Minin:um Channels OPERABLE requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel area.
Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel building.
ACTION 29 - Must satisfy the ACTION requirement for Specification 3.4.6.1.
ACTION 30 - With the number of OPERABLE channels one less than the Min Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the Fuel Building Ventilation System and initiate operation of the Emergency Exhaust S negative pressure. ystem to maintain the fuel building at a 1
1 CALLAWAY - UNIT 1 3/4 3-40 Amendment No.
20
TABLE 3.3-13 RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION r-C5 MINIMUM CHANNELS 7
INSTRUMENT OPERABLE APPLICABILIT(
ACTION E
1.
WASTE GAS HOLDUP SYSTEM Explosive Gas Q
Monitoring System s
a.
Hydrogen Monitors 1/recombiner 44 b.
Oxygen Monitor 2/recombiner 42 2.
Unit Vent System a.
Noble Gas Activity Monitor-1 40 Providing Alarm (GT-RE-21)
{
b.
Iodine Sampler 1
43 Y
c.
Particulate Sampler 1
43 d.
Flow Rate 1
45 e.
Sampler Flow Rate Monitor 1
39 3.
Containment Purge System a.
Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (GT-RE-22,GT-RE-33) 2 41 F
b.
Iodine Sampler 1
43 c.
Particulate Sampler 1
43 d.
Flow Rate N.A.
5 45 e.
Sampler Flow Rate Monitor 1
39 E$
1
TABLE 3.3-13 (Continued)
TABLE NOTATIONS At all times.
- During WASTE GAS HOLD UP SYSTEM operation.
ACTION STATEMENTS ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:
a.
At least two independent samples of the tank's contents are analyzed, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 39 - With the number of channe)s OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated based on fan status and operating curves or actual measurements at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 41 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, PURGING of radioactive -
effluents via this pathway may continue for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both channels inoperable, immediately suspend PURGING of radicactive effluents via this pathway, g
ACTION 42 - With the Outlet Oxygen Monitor channel inoperable, operation of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both oxygen channels or both the inlet oxygen and inlet hydrogen monitors inoperable, suspend oxygen supply to the recombiner. Addition of waste gas to the system may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.
ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
ACTION 44 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.
ACTION 45 - Flow rate for this system shall be based on fan status and operating i
curves or actual measurements.
CALLAWAY - UNIT 1 3/4 3-71 Amendment No. 20
6 REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS l
4 LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
The equipment door closed and held in place by a minimum of four a.
- bolts, b.
A minimum of one door in each airlock is closed, and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1)
Closed by an isolation valve, blind flange, or manual valve, or 2)
Be capable of being closed by an OPERABLE automatic containment purge isolation valve.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
SD2VEILLANCE REQUIREMENTS 4
4.9.4.1 Each of the above required containment building penetrations shall be l
determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:
Verifying the penetrations are in their closed / isolated condition, a.
i or b.
Testing the containment purge isolation valves per the applicable portions of Specification 4.6.3.2.
4.9.4.2 Verify the trip setpoint concentration value for Containment Purge Monitors (GT-RE-22, GT-RE-33) is set at less than or equal to SE-3 pCi/cc during CORE ALTERATIONS or movement of irradiated fuel within the containment.
i CALLAWAY - UNIT 1 3/4 9-4 Amendment No. 20
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3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING onsure that:
(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
The limitation on K of no greater than 0.95 is sufficient to prevent reactor criticality durin$ff refueling operations.
The locking closed of the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portions of the Reactor Coolant System.
This action prevents flow to the RCS of unborated water by closing flow paths from sources of unborated water.
These limitations are consistent with the initial conditions assumed for the baron dilution incident in the safety analyses.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron FILx Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.
This decay time is consistent with the assumpticas used in the safety analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
1 The OPERABILITY of this system ensures the containment purge penetrations will be automatically isolated upon detection of high radiation levels within containment.
The OPERABILITY of this system is required to restrict the release of radioactive materials from the containmeat atmosphere to the environment.
The restriction on the setpoint for GT-RE-22 and GT-RE-33 is based on a fuel handling accident inside the Containment Building with resulting damage to one fuel rod and subsequent release of 0.1% of the noble gas gap activity, except for 0.3% of the Kr-85 gap activity.
The setpoint concentration of SE-3 uCi/cc is equivalent to approximately 150 mR/hr submersion dose rate.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions durirg CORE ALTERATIONS.
CALLAWAY - UNIT 1 B 3/4 9-1 Amendment No.
20
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