ML20247N006
| ML20247N006 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/24/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247N013 | List: |
| References | |
| NUDOCS 8906050223 | |
| Download: ML20247N006 (6) | |
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' UNITED STATES
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NUCLEAR REGULATORY COMMISSION 4-3 j:
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NEBRASKA PUBLIC POWER DISTPICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 130 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebra.ska Public Power District (thelicensee)datedJanuary 27, 1989, 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, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health.
r 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 license amendment will not be inimical to t5e common defensa and security or to the health and safety of the put,lic; 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.
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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
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Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contair:ed in Appendix A, as revised through Amendment No.130, 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
$Y-Fredrick J. HebBon, Director _
Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 24,1989 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 130 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pages of.the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 196 l
197 198 9
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q e-LIMITING CONDITIONS FOR OPERATION -
SURVEILLANCE REQUIREMENTS 3.9.B(cont'dy 4.9.A.4' 250 VDC Unit Batteries-
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_ operable. all core and coritainment.-
a.
Every week, the following parameters cooling systems are operable, reactor
.shall be verified. The actual values.
power level is = reduced to. 25% of the shall be measured and logged:
' rated and NRC is notified within 24 haurs of the situation, the precau-1.
The total batsery terminal tions to be takaa during this period voltage on float charge'shall be-and the plans for. prompt restora-equal to or greater than 250 volcsi tion of incoming power.
2.
The electrolyte level of each b.
Diesel Generators pilot cell is between the minimum and maximum level 1.
From and after the dat's that one of indication marks, the diesel generators or an associ-ated critical bus is made or found 3.
The pilot call voltage is 2.15V-l' to be inoperable for any. reason, minimum and specific gravity continued reactor operation is per-1.195 minimum,' corrected to.77'T 1-missible in accordance with Speci-and electrolyte level, fication 3.5.F.1 if Specification 3.9.A.1 is satisfied.
b.
Every quarter, the following par-aseters shall be verified.' The i
2.
From and after the date that both actual values shall be measured i
diesel ge'nerators are made or.found and logged:
to be inoperable for any reason, continued reactor. operation is per-1.
The electrolyte level of each missible only during the succeeding connected cell is between the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with Speci-minimum and maximum level fication 3.5.F.2 if Specification indication marks.
3.9.A.1'is satisified.
2.
For each connected cell, the 3.
From and after the date that one of voltage is 2.15V minimum and i.
che' diesel generators or associated specific gravity is 1.190'ain-critical buses and either the emer-imum, corrected for 77*F and gency or startup transformer power electrolyte level. The averagd
-source are made er.found to be in.
spec'ific gravity of all operable for any reason, continued connected cells will~be a reactor operation is permissible in minimum of 1.200.
accordance with Specification 3.5.F.1, provided the other off-site source, 3.
The electrolyte temperatures startup transformer or emergency in a representative sample of transformer is available'and cells, consisting of at least capable of automatically supplying every sixth cell, are within power to the 4160V critical buses and 25'F.
l the NRC is notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
of the occurrence and the plans for c.,
Once each operating cycle, the 250V l
restoration of the inoperable compo.
battery charger will be tested to j
nents.
verify that the charger can supply 200 amperes at 250 volts for four hours.
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Amendment No. $6,88,J04, 130
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-196-L d _. _ _ _ - _ _ _ _ _ _ _. _ _ _. _. _ _ _ _ _ _. _ _ _ _ _ _ _ - _.
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t LIMITING CONDITIONS [0R OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.5 (cont'd.)
4.9.A.4 (cont'd) c.
DC Power d.
Once each operating cycle, during shutdown, one of the following ' tests 1.
From and after the date that one of will be performed:
the 125 or 250 volt battery systems is made or found to be inoperable 1.
A battery service test to verify for any reason, continued reactor that battery capacity is adequate operation is permissible during the to supply the emergency load succeeding ten days within electri-profile.
cal safety considerations, prgvided repair work is initiated in the most 2.
A performance discharge test, in expeditious manner to return the lieu of the above service test, failed component to an operable once every five years to verify state, and Specifications 3.5.A.5 that battery capacity is at least and 3.5.F are satisfied. The NRC 85", of the manufacturer's rating.
shall be notified within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> of the situation, the precautions 3.
A performance discharge test, in to be taken during this period and lieu of the above service test, the plans to return the failed when the battery shows signs of components to an operable state.
degradation or has been in service j
seventeen years or longer.
d.
RPS/MG Sets f
5.
Power Monitoring System for RPS System 1.
With one RPS electric, power monitor-ing channel for an inservice RPS MG The above specified RPS power monitor-set or alternate power supply inop-ing system instrumentation shall be arable, restore the inoperable chan-determined operable:
nel to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS a.
At least once per operating cycle MG set or alternate power supply by demonst2ating the operability from service.
of over-voltage, under-voltage l
and under-frequency protective l
2.
With both RPS electric power moni-instrumentation by performance of toring channels for an inservice RPS a channel calibration including MG set or alternate power supply in-simulated automatic actuation of operable, restore at least one to the protective relays, tripping operable status within 30 minutes or logic and output circuit breakers remove the associated RPS MG set or and verifying the following set-alternate power supply from service.
points.
1.
Over-voltage j 132 VAC, with time delay 3 2 sec.
2.
Under-voltage 2 108 VAC, with time delay 1 2 sec.
3.
Under-frequency 2 57 Hz. vich time delay 1 2 sec.
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Amendment No. 32,82,88,JM,130 I
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3.9 RASES ag-The general objective of this Specification is to assure an adequate source of electrical-
. facilities gover to operat's the auxiliaries during plant operation, to operate 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 required for switch.
'g' gear and engineered safety feature systems. This supply consists of two 125V DC and two. 250V.DC batteries and their related chargers. Specification 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 transforme r..
Both of these transformers' are sized to carry 100% of the station auxiliary load. The emergency transformer is-about one third the size of these two transformers and is equal'in size to both emergency diesel generators.
The startup transformer and the emergency transformers are the offsite power Their voltage is monitored by'undervoltage relays which provide, low sources.
voltage protection for the emergency buses. Whenever the voltage seepoint and time delay Itait 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 continus'to operate 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 ta supply auxiliary electric power to the. station.
In the normal mode of operation, the startup and emergency transformers are energized and two diesel generators are operable. One diesel generator may be allowed out of service based on the ava,ilability of power from the startup -
transformer and the fact that one diesel generator carries sufficient engineered safeguards equipment to cover all breakers. With the startup transformer and one diesel generator out of service, the off site transmission line corresponding to the emergency. transformer must be available. Upon the loss of one on-site and one off-site power source, power would be available from the other imm'diate e
- off-site power source and the two operable on-site diesels to carry sufficient
. engineered safeguards equipment to cover all breaks.
In addition to the3e two 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. co carry the full station auxiliary load. The time required to perform this operation is comparable to the time the reactor could remain on RCIC operation before controlled depressurization need be initiated.
Once each operating cycle, during shutdown, either a service test or performance discharge is performed on the 125 V and the 250 V batteries.
l The 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 10% of rated capacity frem its average on previous performance tests, or is below 85% of the manufacturer's rating.
Amendment No. 43,J0#,J22,130
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