ML20150F049
| ML20150F049 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/28/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150F023 | List: |
| References | |
| NUDOCS 8804040248 | |
| Download: ML20150F049 (9) | |
Text
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%di,?gg UNITED STATES
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s "/ j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 qo/.....
COMMONWEALTH EDISON COMPANY 00CKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. OPR-39
- 1. The Nuclear Regulatory Comission (the Commission) has found that:
i A. The applications for amendment filed by the Commonwealth Edison l Company (the licensee), dated December 9,1987 and supplemented '
February 11, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 regulations of the Commission; C. Thereisreasonableassuiance: (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 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 Specif1-cations as indicated in the enclosure to this license amendment and para-graph 2,C.(2) of the Facility Operating License No. OPR-39 is hereby amended to read as follows:
8804040248 880328 PDR ADOCK 05000295 P PDR
~ . . . . - . .- - - - ______ __________
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendnent ho. 109, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
_! k kf Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Changes to the Technical Specifications Oate of Issuance: March 28,1988 i
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g UNITED STATES NUCLEAR REGULATORY COMMISSION l
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WASHINGTON, D. C. 20555 o, .
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l COMMONWEALTH EDIS0N COMPANY 00CKET N0. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. OPR-48
- 1. The Nuclear Regulatory Conrnission (the Comission) has found that:
A. The application for amendment filed by the Commonwealth Edison Company (the licensee), dated December 9,1987 and supplemented February 11, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 regulations of the Commission; 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 conducteo in compliance with the Comission's regulations;
- 0. The issuance of this amendment will not be inimical to the common i 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 Specif1- i cations as indicated in the enclosure to this license amendment and para- j graph 2.C.(2) of the Facility Operating License No. OPR-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. 98 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with i the Technical Specifications.
- 3. This amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
k^.,s4,4 Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: March 28,1988 1
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I ATTACHMENT TO LICENSE AMENDMENTS I AMENDMENT N0. 10h FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 98 FACILITY OPERATING LitiNSE NO. DPR-48 DOCKET N05. 50-295 AND 50-304 _
Revise Appendix A as follows:
REMOVE INSERT 262 262 262 A 263 263 274 274 1
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.1.E. 4.15.1.E.3. with previous data does not indicat?
evidence of abnormal degradation of the batteries.
4.15.1.E.4. During each refueling outage the following tests and inspections shall be conducted on the unit batteries and the common battery except as specified in section 4.15.1.E.4.f.
- a. A detailed visual inspection of the cells shall include the cells, cell plates, and the battery rack. The inspection shall be cont.idered satisfactory, if there are no signs of physical damage or deteriorations.
- b. Cell-to-cell and terminal connections shall be checked for corrosion and tightness. The connections shall be cleaned, tightened, and anti-corrosion coating shall be applied as required.
- c. Verify that the battery capacity is
. adequate to supply and maintain, in an OPERABLE status, all of the actual or simulated emergency loads for 240 minutes when the battery is subject to a battery service test.
The performance discharge test reqLired by specification i 4.15.1.E.5 may be performed in lieu of this requirement.
11760/11770 262 Amendment Nos. 109, 98
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT f
- d. A performance discharge test of I
battery caprcity shall be conducted on any battery that shows signs of degradation or has reached 85% of the service life expected for the application.
Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.
. e. A performance test shall be conducted on the battery charger.
This test shall be considered satisfactory if the charger can supply a load of at least 175 amperes for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> without exceeding the design temperature rise of the hattery charger.
- f. These tests need not be conducted on the common battery if they have been performed in conjunction with the previous refueling outage of the other unit.
262A Amendment Nos. 109, 98 11760/11770
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LIMITING CONDITION FOR OPERATION SURVEILLANCE hEQUIREMENT 3.15.1.E. 4.15.1.E.S At least once per 60 mon ~hs, during shutdown, verify that the battery capacity is at least 80% of the msnufacturer's rating when subjected to a performance discharge test. This performance discharge test may be performed in lieu of the battery service test required by Specification 4.15.1.E.4.c.
4.15.1.F. The status of the instrument inverters 3.15.1.F. All four unit 120-volt AC instrument buses shall be checked daily.
(111, 112, 113 and 114 for Unit 1- 211, 212, 213 and 214 for Unit 2) are in service. At least three of the four buses must be supplied by their respective instrument inverters.
l 11760/11770 263 Amendment Nos.109, 98
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4.15 Diesel Generators The qualification testing of the diesel generator is designed to establish a 0.99 reliability with a confidence level of 957.. This test ing is described in response t o Question 8.72 of the FSAN anad has been accepted by the Directorate of Licensing. (1) The monthly testing of the diesel generators is conducted to meet the intent of Section 6.4.1 of IEEE Trial Use Statdard 381 1912 and demonst rates the continued availability of the diesel generators. The diesel generator will be manually started and loaded to 4000 KW as reconnended by the manuf acturer; this load will be maintained unt il operating temperatures are normalized. In conjunction wit h this test ing, the diesel st art ing air compressors and the dicsci oil transfer pumps are also tested to demonstrate their cont inued availabilit y.
The refueling outage testing is conducted to meet the intent of Section 6.4.2 of IEEE Trial-Use Standard 387-1912 and demonstrates the continued capability of the diesel generators to perform their functions. In conjunction with this testing, tests are also performed on the diesel, starting air compressors and the diesel oil transfer pumps to demonstrate their continued capability to perform their functions. The performance criteria for the air compressors is based on the acceptance standards for the system; the criteria for the diesel oil transfer pumps is based upon supplying fuel at a rate greater than the maximum rate of consumption of the diesel.
Batteri_ej Station batteries crn 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 unserviceable long before it fails. The periodic equalizing charge will ensure that the ampere-hour capacity of the batteries is maintained.
Each refoeling 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 varify 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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(1) Section 8.3.1 of Safety Evaluation by the Directorate of Licensing, U.S.A.E.C., in the Matter of Commonwealth Edison Company Zion 7Jclear Power Station Units 1 and 2 Docket Nos 50-295 and 50-304, dated October 6, 1972 (2) FSAR Section 8.A.1.4 274 Amendment flos.109, 98 4223K
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