ML20196A952
| ML20196A952 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/16/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196A955 | List: |
| References | |
| NUDOCS 8806300162 | |
| Download: ML20196A952 (5) | |
Text
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UMTED STATES
[" > e P[ g NUCLEAR REGULATORY COMMISSION g
y W ASWNGTON, D. C. 20555 e
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NEBRASKA PUBLIC POWER DISTRICT E K!.T NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No.122 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebraske Public Power District (the licensee) dated March 25, 1988, complies with the standards and ren,uirements 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, as amended, the provisions of the Act, and the rules and reCulations of the Commission; C.
There is reasonable assurance:
(1) that the activities authori:ed by this amendment can be conducted without endangering the health and safety of the public, ard (ii) that such activities will be cenducted in compliance with the Comission's regulations; D.
The issuance of this license 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 Comission's regulations and all applicable requirements have i
been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraoh 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follois:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.122, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d
($.6s4 Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Reculation
Attachment:
Changes to the Technical Specifications Date of Issuance: Jane 16,1088
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ATTACHMENT TO LICENSE AMENDMENT NO 122 FACILITY OPERATING LICENSE NO. DPR-46 00CKET NO. 50-?98 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 195
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198 a
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h LIMITING CONDITIO'.4S FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A 4.9.A (cont'd.)
3.
The pilot cell voltago is 2.15V minimum and specific gravity 1.195 minimum, corrected for.7'F and electrolyte level.
b.
Every quarter, the following para-meters shall be verified. The actual values shall be measured and logged:
1.
The electrolyte level of each connected cell is between the minimum and maximum level in-dication marks.
2.
For each connected cell, the voltage is 2.15V minimu= and specific gravity is 1.190 minimum, corrected for 77'F and electrolyte level. The average specific gravity of B. Operation with Inoperable Equipment all connected cells will be a minimum of 1.200.
- 1. Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a 3.
The electrolyte temperatures Cold Condition, the availability'of in a representative sa:ple of electric power shall be as specified cells, consisting of at least in 3.9.A.1, except as specified in every sixth cell, are within 3.9.B.1.
tS'F.
- a. Ince=ing Power Once each operating cycle the 125V c.
battery charger will be tested to
- 1. From and after the date ince=ing power verify that the charger can supply is not available fro = a startup or emer-200 Amperes at 125V for four hours.
l gency transfor:er, continued reactor operation is permissible under this d.
Once each operating cycle, during condition for seven days. At the end shutdown, one of the followins tests of this period, provided the second will be performed:
source of incoming power has not been i
made ic=ediately available, the NRC 1.
A battery service test to verify must be notified of the event and the thac battery capacity is adequate plan to restore this second source.
to supply the emergency load During this period, the two diesel profile.
generators and associated critical buses must be demonstrated to be 2.
A performance discharge test, in operab le.
lieu of the above service test, once every five years to verify
- 2. From and after the date that incoming that battery capacity is at least power is not available from both start-85% of the manufacturer's rating, up and emergency transformers (i.e.,
both failed), continued operation is 3.
A performance discharge test, in permissible, provided the two diesel lieu of the above service test, generators and associated critical when the battery shows signs of buses are demonstrated to be degradation or has been in service seventeen years or longer.
Amendment No. 80, 82, BB,104,122
-195-
3.9 EASES The general objective of this Specification is to assure an adequate source of l
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electrical power to operate the auxiliaries during plant operation, to operate facilities to cool and lubricate the plant during shutdown and to operate the engineered safeguards following the accident.
There are three sources of ac electrical energy available; namely, the startup transformer, the emergency transformer and two diesel generators. The de supply is tequired for switch gear and engineered safety feature systems. This supply consists of two 125V DC and two 250V DC batteries and their related chargers. Spscification 3.9.A states the required availability of ac and de power; i.e., active off site ac sources and the required amount of on site ac and de sources.
Auxiliary power for CNS is supplied from the startup transformer and the normal transformer.
Both of these transformers are sized to carry 100% of the station auxiliary load. The emergency transformer is about one third the si:e of these two transformers and is equal in si:e to both emergency diesel generators.
The startup transformer and the e=ergency transfermers are the offsite power sources. Their vo,1tage is monitored by undervoltage relays which provide icw voltage protection for the emergency buses, khenever the voltage setpoint and ti=e delay limit for the undervoltage relays have been exceeded, the emergency buses are automatically disconnected from the offsite power source.
If the startup or emergency transformer is lost, the unit can continue to operate l
since the unit auxiliary transformer is in service, and the emergency or startup transformer and the diesels are available.
If both the startup and emergency transformers become inoperable, the power level must be reduced to a value where by the unit can safely reject the load and continue to supply auxiliar; electric power to the station.
In the normal mode of eperation, the startup and emergency transformers are energi:ed and two diesel generators are operable. One diesel generator may be allowed out of service based on the availability of power from the startup transformer and the fact that one diesel generator carries sufficient engineered 3
safeguards equipment to cover all breakers. With the startup transformer and one diesel generator out of service, the off site transmission line corresponding j
to the e=ergency transformer must be available, ypon the loss of one on site and one off site power source, power would be available from the other iemediate off site power source and the two operable on site diesels to carry sufficient engineered safeguards equipment to cover all breaks.
In addition to these two i
power sources, removal of the Isolated Phase Bus "quick" disconnect links would allow backfeed of power through the main transformer to the unit auxiliary transformer and provide power to carry the full station auxiliary locd. The time required to perform this operation is comparable to the time the reactor could remain on RCIC operation before controlled depressurization need be f
initiated.
Once each operating cycle, during shutdown, either a service test or performance discharge is performed on the 125 volt batteries.
Thi j
performance discharge test is performed in lieu of the service test when a battery shows signs of degradation.
Degradation is indicated when battery capacity drops more than 104 of rated capacity from its average on previous performance tests, or is below 85% of the manufacturer's rating.
Amendment No, g, Jg,122 198-
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