ML20128D336

Amends 88 & 78 to Licenses DPR-39 & DPR-48,respectively, Changing Tech Specs to Revise Actions Required in Event of Inoperable Rod Due to Rod Urgent Failure

ML20128D336
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	05/13/1985
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20128D329	List: ML20128D324 ML20128D336 ML20128D343
References
NUDOCS 8505280566
Download: ML20128D336 (7)

Text

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WASHINGTON, D. C. 20655

%, .. . . . jl COPE 0NWEALTH EDIS0N Cl,MPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.88 License No. DPR-39

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Comonwealth Edison Company (the licensee) dated February 5,1985, 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 I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. T H e 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 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 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. OPR-39 is hereby amended to read as follows:

8505280566 850513 PDR ADOCK 05000295 P PDR

-2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.88 , 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 its issuance.

FOR THE NUCLE / REGULATORY COMMISSION

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t k 5t'!ven A. Varga, C ief Operating Reacto Branch #1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 13, 1985

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. OPR-48

1. The Nuclear Regulatory Comission (the 'Comission) has found that:

A. The application for amendment by Commonwealth Edison Company (the licensee) dated February 5, 1985, 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 I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 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-48 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78 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 its issuance.

FOR THE NUCLEAR ULATORY COMISSION

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A Sfb . ha e Operating Reacto ranch #1 Division of Licen g

Attachment:

Changes to the Technical Specifications Date of Issuance: May 13, 1985 l

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0. 88 FACILITY OPERATING LICENSE N0. DPR-39 AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 P

Revise Appendix A as follows:

Remove Pages Insert Pages 52 52 53 53 i-I i

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.3.8 2. Not more than one inoperable control rod 4.2.3.B Not Applicable shall be permitted during power operation. l If more than one rod is determined to be inoperable, the reactor shall be placed l in MODE 3 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l 3. If more than one control red is l inoperable because of a Rod Urgent Failure in the rod control system, the provisions of Specifications 3.2.3.B.1 and 3.2.3.8.2 above shall not apply. If the affected assemblies cannot be l returned to service within twenty-four -

hours, the reactor shall then be placed in MODE 3 within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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4. If an inoperable full-length rod is located above the 200 step level and is - -  !

capable of being tripped, then the insertion limits in Figure 3.2-2 for Unit I and Figure 3.2-4 for Unit 11 shall apply for:4 loop operation and the insertion limits on Figure 3.2-3 for Unit I and Figure 3.2-5 for Unit II shall apply for 3 loop operation.

Amendment No. 88 and 78 i

07500/01510 52 l

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LIMITING CONDITION FOR OPERATION SUNVEILLANCE REQUIREMENT i

i l3.2.3.8 5. If an inoperable full-length rod is 4.2.3.8. 5. Not Applicable

located below the 200 step level, power l operation may continue provided that

An t

analysis of the potential ejected rod I worth is performed within 3 days and the

} rod worth is determined to be less than l or equal to 0.88% Ak at zero power and '

l 1ess than or equal to 0.19% Ak at RATED . .

l THERMAL POWER for the remainder of the j fuel cycle, and a) reactivity required to i provide the design value of available i shutdown as shown in Figure 3.2-1 shall j be verified every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;.or b) the thermal power level is reduced to less l

j than or equal to 75% of rated thermal

! power within one hour and within the next 1 four hours the, high neutron flux trip

! I setpoint is reduced to less than or equal l l to 85% of rated thermal power; or c) the '

! remainder of the rods in the group with i the inoperable rod are aligned to within i l l plus or minus 24 steps of the inoperable

{ rod within one hour while maintaining rod j sequence and insertion limits.

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! 07500/07510 53 Amendment No. 88 and 78 i  ;