ML20045G998
| ML20045G998 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/12/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045G995 | List: |
| References | |
| NUDOCS 9307160226 | |
| Download: ML20045G998 (7) | |
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UNITED STATES 7ij
,I NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 2055 50001 g
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIT i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-39 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 26, 1993, 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 Ccmmission; 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-39 is hereby amended to read as follows:
9307160226 930712 PDR ADOCK 05000295 p
. (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.147 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 REGULATORY COMMISSION UfA.
OV James E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Char.ges to the Technical Specifications Date of Issuance:
July 12, 1993 o
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NUCLEAR REGULATORY COMMISSION
%['.'.N W ASHINGTON D.C. 20555-0001 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 26, 1993, 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-48 is hereby amended to read as follows:
- )
i (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.135, 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 REGULATORY COMMISSION
($AL James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 12,1993 3
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.147 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT N0.135 TO FACILITY OPERATING LICENSE NO. OPR-48 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 261 261 274a 274a P
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l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.1.D 4.15.1.0 E.
The unit 125-volt batterles (111 and E.
Station 125-volt batteries (Ill, 112 for Unit 1 - 211 and 212 for Unit 2) 112 and 011 for Unit 1 - 211, 212 and the common battery (011) are charged and 011 for Unit 2) and in service and their respective battery
. chargers and 125-volt DC control buses are 1.
Every week the specific gravity energized.
and voltage of the pilot cell and temperature of adjacent cells and overall battery voltage shall be measured and recorded. Overall battery voltage shall be vertfled to be at least 125 volts.
2.
Every quarter the measurements shall be made of voltage of each cell to the nearest 0.01 volt, specific gravity of each cell, and temperature of every fifth cell.
The electrolyte height will be checked and adjusted as required.
All data shall be recorded including the amount of water added to any cell.
I 3.
Tests 4.15.1.E.1 and 4.15.1.E.2 are acceptable if comparison 261 Amendment Nos. 147 and 135
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Bases:
4.15 Batteries Station batteries can be expected to deteriorate with time but precipitous failure is extremely unlikely.
The type of weekly and quarterly surveillance specified has demonstrated over the years the ability to detect indications of a cell becoming irregular or unservicable long before it falls.
l Each refueling outage the batteries are visually inspected and subjected to a discharge performance test or service test as recommended by IEEE Std. 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," to ensure that the battery has maintained its required capacity.
Following this discharge test the battery is restored to the fully charged condition.
In addition, a performance test is conducted on the battery charger to verify its ability to supply sufficient amperage to recharge a battery and also supply normal loads.
(2)
The tests described above are proven power plant practice and will ensure the continued availability of the battery as well as its continued capability to carry design load.
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l (2) FSAR Section 8.4.1.4 274a Amendment Nos. 147 and 135 4
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