ML20115G132
| ML20115G132 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/15/1996 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20115G135 | List: |
| References | |
| NUDOCS 9607180265 | |
| Download: ML20115G132 (5) | |
Text
._
[Y " %,t UNITED STATES l
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. soesset o
- j' UNION ELECTRIC COMPANY GALLAM.aY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE r
Amendment No. 114 License No. NPF-30 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Union Electric Company (UE, the licensee) dated January 2, 1996, as supplemented by letter dated April 12, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 's amended by changes to the Technical Speci-fications 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 9607180265 960715 PDR ADOCK 05000483 P
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 114 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
l[>,, k,a D% l \\ W (W 4-Kristine M. Thomas, Project Manager i
Project Directorate IV-2 Division of Reactor Projects III/IV j
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 15, 1996 4
n 3
4 j
i
ATTACHMENT TO LICENSE AMENDMENT o
AMENDMENT NO.114 TO FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-481 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.
REMOVE INSERT 3/4 9-4 3/4 9-4 8 3/4 9-1 B 3/4 9-1 i
i i
A 4
1 E
4 i
1 i
i i
i.
REFUELING OPERATIONS l
l.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS I
LINITING CONDITION FOR OPERATION j
3.9.4 The containment building penetrations shall be in the following status:
4 a.
The equipment door closed and held in place by a minimum of four
- bolts, I
b.
A minimum of one door in the emergency airlock is closed and one door in the personnel airlock is capable of being closed *, and i
1 c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
j 1)
Closed by an isolation valve, blind flange, or manual valve, or f
2)
Be capable of being closed by an OPERABLE automatic containment purge isolation valve.
4 APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within 4
the containment.
I a
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.
SURVEILLANCE RE0VIREMENTS 4.9.4.1 Each of the above required containment building penetrations shall be determined to be either in its required condition or capable of being closed by I
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 A'.TERATIONS or movement of irradiated fuel in the containment building by:
a.
Verifying the penetrations are in their required condition, or l
b.
Testing the containment purge isolation valves per the applicable portions of Specification 4.6.3.2.
4 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.
- Administrative controls ensure that:
- 1) Appropriate personnel are aware that both personnel airlock doors are
- open,
- 2) A specified individual (s) is designated and available to close the airlock following a required evacuation of containment, and
~
- 3) Any obstruction (s) (e.g., cables and hoses) that could prevent closure of an open airlock can be quickly removed.
CALLAWA) - UNIT 1 3/4 9-4 Amendment No. 40,114
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION Tne limitations on reactivity conditions during REFUELING ensure 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 no greater thm 0.95 is sufficient to prevent reactor criticality durin,,, of g
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 via the CVCS blending tee. This action prevents flow to the RCS of unborated water by closing all automatic flow paths from sources of unborated water. Administrative controls will limit the volume of unborated water which can be added to the refueling pool for decontamination activities in order to prevent diluting the refueling pool below the limits specified in the LCO.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.
3/4.9.2 INSTRUMENTATION j
The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the i
reactivity condition of the core.
3/4.9.3 DECAY TIME I
The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time j
has elapsed to allow the radioactive decay of the short-lived fission products.
This decay time is consistent with the assumptions used in the fuel j
handling accident radiological consequence and spent fuel pool thermal-hydraulic analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material from containment will be minimized.
The OPERABILITY and closure restrictions are sufficient to 4
restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
Both containment personnel airlock doors may be open during movement of l
irradiated fuel or during CORE ALTERATIONS provided one airlock door is capable of being closed.
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 containment 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 rod activity, except for 0.3% of the Kr-85 rod activity. The setpoint concentration of SE-3 pCi/cc is equivalent to approximately 150 mR/hr submersion dose rate.
CALLAWAY - UNIT 1 B 3/4 9-1 Amendment No. 20,54,97,103, 114 February 1, 1996
.