ML17332A852
| ML17332A852 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/12/1995 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17332A853 | List: |
| References | |
| NUDOCS 9507180451 | |
| Download: ML17332A852 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 197 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated March 31,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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; 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
P507i8045i 9507i2 PDR ADOCK 050003i5 P,
PDR ':
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended
'to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 197
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~ohn B. Hickman, Project Hanager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachment=
Changes to the Technical Specifications Date of Issuance:
July 12, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 197 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical'lines indicating the area of change.
REMOVE 3/4 9-4 B 3/4 9-1 INSERT 3/4 9-4 B 3/4 9-1
t 3/4 LIMITINGCO ITIONS FOR OPERATION AND SURVEILLANCEREQUIREi>IEitTS 3/4.9 REFUELING OPERATIONS CONTAINMENTBUILDINGPENETRATIONS LIMITINGCONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
ao b.
The equipment door closed and held in place by a minimum of four bolts, The airlock doors are controlled in the following manner:
1.
A minimum of one door in each airlock is closed, or 2.
Both airlock doors may be open provided:
a.
One door in each airlock is OPERABLE, b.
Refueling cavity level is greater than 23 feet above the fuel, and c.
A designated individual is available at all times to close the airlock ifrequired.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
Closed by an isolation valve, blind fiange, or manual valve, or Be capable ofbeing closed by an OPERABLE automatic Containment Purge and Exhaust isolation valve.
APPLICABILITY:
ACTION:
During CORE ALTERATIONSor movement of irradiated fuel within the containment.
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONSor movement of irradiated fuel in the containment building. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCERE UIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed/isolated condition or capable of being closed by an OPERABLE automatic Containment Purge and Exhaust 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 ALTERATIONSor movement of irradiated fuel in the containment building by:
b.
Verifying the penetrations are in their closed/isolated condition, or Testing the Containment Purge and Exhaust isolation valves per the applicable portions of Specification 4.6.3.1.2.
For the purpose of this Specification, an OPERABLE airlock door is a door that is capable of being closed and secured.
Cables or hoses transversing the airlock shall be designed to allow for removal in a timely manner (e.g., quick disconnects).
COOK NUCLEAR PLA.iT-UMT I Page 3/4 94 Ai>IEiii1)MENT
3/4 BASES 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: I) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron conceatration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
The value of 0.95 or less for K,< includes a 1
percent delta k/k conservative allowance for uncertainties.
Similarly, the boron concentration value of 2000 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron.
The boron concentration requirement of specification 3.9.1.b has been conservatively increased to 2400 ppm to agree with the minimum concentration of the RWST.
/4.9.2 INSTRUMENTATION The OPERABILITYof the source range neutron fiux 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 pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consisteat with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENTBUILDINGPENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment wfil be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element tupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
The specific guidelines to allow both airlock doors to remain open during CORE ALTERATIONSwere developed to ensure that the assumptions for restricting radioactive leakage to the environment remained valid. The guidelines established for maintaining both airlock doors open include:
I) one door in each airlock is OPERABLE,
- 2) refueling cavity level is greater than 23 feet above the fuel, and 3) a designated individual is continuously available to close an airlock door (ifrequired).
An OPERABLE airlock door consists of a door capable of being closed and secured.
Additionally, cables or hoses transversing the airlock must be designed in a manner that allows timely removal (e.g., quick disconnects).
The requirement that the refueling cavity level is greater than 23 feet above the fuel ensures consistency with the assumptioas of Specifications 3/4.9.10 and 3/4.9.11.
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 during CORE ALTERATIONS.
COOK NUCLEARPLANT-UiiIT1 Page B 3/4 9-1 AXIEND~IENT~,
197 I
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
182 License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated March 31,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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; 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
182
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 12, 1995 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
182 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 9-4 B 3/4 9-1 INSERT 3/4 9-4 B 3/4 9-1
3/4 LIMITINGCO ITIONS FOR OPERATION AND SURVEIL ANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS CONTAINMENTBUILDINGPENETRATIONS LIMITINGCONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
b.
The equipment door closed and held in place by a minimum of four bolts, The airlock doors are controlled in the following manner.
1.
A minimum of one door in each airlock is closed, or 2.
Both airlock doors may be open provided:
a.
One door in each airlock is OPERABLE, b.
Refueling cavity level is greater than 23 feet above the fuel, and c.
A designated individual is available at all times to close the airlock ifrequired.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
I.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Be capable ofbeing closed by an OPERABLE automatic Containment Purge and Exhaust isolation valve.
APPLICABILITY:
During CORE ALTERATIONSor movement of irradiated fuel within the containment.
ACTION:
With the requirements ofthe above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONSor movement of irradiated fuel in the containment building. The provisions ofSpecification 3.0.3 are not applicable.
SURVEILLANCERE UIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed/isolated condition or capable ofbeing closed by an OPERABLE automatic Containment Purge and Exhaust 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 ALTERATIONSor movement of irradiated fuel in the containment building by:
a.
Verifying the penetrations are in their closed/isolated condition, or b.
Testing the Containment Purge and Exhaust isolation valves per the applicable portions of Specification 4.6.3.1.2.
For the purpose of this Specification, an OPERABLE airlock door is a door that is capable ofbeing closed and secured.
Cables or hoses transversing the airlock shall be designed to allow for removal in a timely manner (e.g., quick disconnects).
COOK i>UCLEAR PLANT-UNIT2 Page 3/4 9A AMENDMENTK, 434 182
~
3/4 BASES 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: I) 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.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in thc accident analyses.
The value of 0.95 or less for K,rr includes a
I percent delta k/k coaservative allowance for uncertainties.
Similarly, the boron concentration value of2000 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron.
The boron concentration requirement of specification 3.9.1.b has been conservatively increased to 2400 ppm to agree with the minimum concentration of the RWST.
3/4.9.2 INSTRUMENTATION The OPERABILITYof the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAYTIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consisteat with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENTBUILDINGPENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment willbe restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficieat to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
The specific guidelines to allow both airlock doors to remain open during CORE ALTERATIONSwere developed to ensure that the assumptions for restricting radioactive leakage to the environment remained valid. The guidelines established for maintaining both airlock doors open include:
I) oae door in each airlock is OPERABLE,
- 2) refueling cavity level is greater than 23 feet above the fuel, and 3) a designated individual is continuously available to close an airlock door (ifrequired).
An OPERABLE airlock door consists of a door capable of being closed and secured.
Additionally, cables or hoses transversing the airlock must be designed ia a manner that allows timely removal (e.g., quick disconnects).
The requirement that the refueling cavity level is greater than 23 feet above the fuel ensures consistency with the assumptioas of Specifications 3/4.9. 10 and 3/4.9.11.
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 during CORE ALTERATIONS.
COOK NUCLEARPL&iT-UNIT2 Page B 3/4 9-1 AIIENDKIEiNT4%
182