ML20084N559
| ML20084N559 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/30/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084N562 | List: |
| References | |
| TAC-47494, TAC-47495, TAC-55983, TAC-55984, NUDOCS 8405170095 | |
| Download: ML20084N559 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20556
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confamity 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 an,endment 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 ininical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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8405170095 840430 PDR ADOCK 05000266 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
OPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective upon completion of equipment 1
installation but not later than December 31, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION
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G damesR. Miller, Chief f
Operating Peactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 30, 1984
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'f jg UNITED STATES NUCLEAR REGULATORY COMMISSION r.
j wAsHmGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-?7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 10, 1981, 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 Commission; C.
There is rea*;onable assurance (i) that the activities authorized by this amendment can he 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 cermon defense and security or to the health and safety of the public; and E.
The issuanc of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirerents have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.
OPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and R, as revised through Amendrent No. 88, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, s
3.
This license amendment is effective upon completion of equiprent installation but not later than December 31, 1984.
i FOR.THE NUCLEAR REGULATORY COMMISSION
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' James R. Miller, Chief
' Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 30, 1984
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NO. OPR-27 DOCKET NOS. 50-266 AND 50-301 1
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Revise Appendix A as follows:
Remove Page Insert Page i
15.3.7-1 15.3.7-1 I
15.3.7-2 15.3.7-2 j
15.3.7-3 15.3.7-3 1
15.3.7-4 15.3.7-4 15.3.7-5 15.3.7-5 i
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15.3.7 AUX 1LIARY ELECTRICA1/ SYSTEMS-Applicability Applies to the availabil'ty of off-site and on-site electrical power for plant i
power operation and for the operation of plant auxiliaries.
Ob_iective To define those conditions of electrical power availability necessary (1) to provide for safe reactor operation, and (2) to provide for the continuing availability of engineered safeguards.
4 Specification A.1 Under normal conditions neither one nor both reactors shall be made critical unless the following conditions are met:
j a.
At least-two 345 KV transmission lines are in service.
b.
The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers associated with the reactor (s) to be taken critical are in service; or one 345/13.8 KV station ~ auxiliary transformer' and the associated 13.8/4.16 KV station auxiliary transformer (s) are in service with the gas turbine operating.
c.
480 Volt buses B03 and B04 for the unit (s) to be taken critical are energized.
t d.
4160 Volt bases A03, A04, A05, and A06 for the unit (s) to'be taken critical are energized.
A fuel supply of 11,000 gallons is available; and both diesel 1
e.
generators are operable, f.
All four batteries and their associated DC systems are operabic.
I g.
Four battery chargers are operable with one charger carrying the DC loads of each DC main distribution bus, s
Unit 1 - Amendment No. 84 Unit 2 - Amendment No. 88-15.3.7-1
A.2 Under abnormal conditions including Black Plant startup, one reactor may be made critical providing the following conditions are met:
One 345 KV transmission line is in service; or the gas turbine is a.
operating.
b.
The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers associated with the unit to be taken critical are in service; or the associated 13.8/4.16 KV station auxiliary transformer is in service and the gas turbine is operating.
Reactor power level is limited to 50% rated power until 2 or more c.
transmission lines are restored to service.
d.
480 Volt buses B03 and B04 for the unit to be taken critical are energized.
4160 Volt buses A03, A04, A05, and A06 for the unit to be taken e.
critical are energized.
f.
A fuel supply of 11,000 gallons is available; and both diesel generators are operable.
All four batteries and their associate *d DC systems are operable.
I g.
h.
Four battery chargers are operable with one charger carrying the DC loads of each DC main distribution bus.
B.1 During power operation of one or both reactors, the requirements of 15.3.7.A.1 may be modified to allow the following arrangements of systems and components:
a.
If the 345 KV lines are reduced to only one, any operating reactor (s) must be promptly reduced to, and limited to, 50% power.
If all 345 KV lines are lost, any operating reactor (s) will be reduced to supplying its auxiliary load, until one or more 345 KV transmission lines are again available.
b.
If both 345/13.8 KV auxiliary transformers are out of service and only the gas turbine is operating, only one reactor will remain operating and it will be limited to 50% power. The second reactor will be placed in the hot shutdown condition.
Unit 1 - Amendment No. 84 Unit 2 - Amendment No. 88 15.3.7-2
c.
If the 13.8/4.16 KV auxiliary transformers are reduced to only one, the reactor associated with the out of service transformer j
must be placed in the hot shutdown condition, d.
Either bus A03 or A04 may be out of service for a period not exceed-ing 7 days provided both diesel generators are operable and the associated diesel generator is operating and providing power to the engineered safeguard bus normally supplied by the out of service bus, One diesel generator may be inoperable for a period not exceeding e.
7 days provided.the other diesel generator is tested daily to ensure operability and the engineered safety features associated with this diesel generator shall be operable.
f.
One of the batteries DOS or D06 may be inoperable for a period not i
exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the other three batteries and four battery chargers remain operable with one charger carrying the DC loads of each DC main distribution bus.
g.
One of the batteries D105 or D106 may be inoperable for a period not exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the other three batteries and four battery chargers remain operable with one charger carrying the DC loads of each DC main distribution bus.
a f
Basis This two unit plant has four 345 KV transmission line interconnections. A 20 MW gas turbine generator and two 2850 KW diesel generators are installed at the plant. All of these energy sources will be utilized to provide depth and reliability of service to the Engineered Safeguards equipment through i
j redundant station auxiliary power supply systems.
1 The electrical system equipment is arranged so'that no single contingency can inactivate enough safeguards equipment to jeopardize the, plant safety. The 480-volt equipment is arranged on 4 buses per unit. The 4160-volt equipment is supplied from 6 buses per unit.
Unit Amendment No. 64-Unit 2 - Amendment No. 88 15.3.7-3
Separation is maintained in the 4160-volt system to allow the plant auxiliary equipment to be arranged electrically so that redundant items receive their power from the two different buses.
For example, the safety injection pumps are supplied from the 4160 volt' buses 1-A05 and 1-A06 for Unit No. I and 2-A05 and 2-A06 for Unit No. 2; the six service water pumps are arranged on 480-volt buses as follows:
two on bus 1-B03, one on bus 1-B04, one on bus 2-B03 and two on bus 2-B04; the four containment fans are divided between 480-volt buses 1-B03 and 1-804 for Unit No. 1 and 2-B03 and 2-B04 for Unit No. 2 and so forth.
Redunlant valves are supplied from motor control centers 1-B32 ar.d 1-842 for Unit No. 1 and 2-B32 and 2-B42 for Unit No. 2.
The plant DC electrical system has been modified so that each of the four instrument bus power supplies has its own battery and battery chargers. One battery charger shall be in service on each battery so that the batteries will i
always be at full charge in anticipation of a loss-of-ac power incident. This insures that adequate de power will be availabic for starting the emergency generators and other emergency uses.
The emergency generator sets are General Motors Corporation, Electro-Motive Division, Model 999-20 Units rated at 2850 KW cohtinuous, 0.8 power factor 900 RPM, 4160 volts 3 phase, 60 cycle and consume 205 gallons of fuel per hour. Thus the 11,000 gallon supply in the Emergency Fuel Tank provides sufficient fuel to operate one diesel at design load for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
In addition, it will be normal for Point Beach to keep one, or the equivalent of one, bulk storage tank full at all times (55,000 gal, which is equal to l
about 10 days' supply). They are each capable of providing 3050 kw'for a j
30 minute period. The gas turbine is capable of providing 20,000 kw.
If only one 345KV transmission line is in service to the plant switchyard, a temporary loss of this line would result in a reactor trip (s) if the i
reactor (s) power icvel were greater than 50%. Therefore, in order to maintain continuity of service and the possibility of self sustaining operations, if less than one 345KV transmission line is in service to any operating reactor (s),
the power level of the affected reactor (s) will be limited to 50%.
84 Unit 1 - Amendment No. 26, 88 Unit 2 - Amendment No M,
15.3.7-4
4 If both 345/13.8KV station auxiliary transformers are out of service, only one reactor -
1 be operated. The gas turbine will be supplying power to operate the safeguards auxiliaries of the operating reactor and acts as a backup supply for that unit's normal auxiliaries. Therefore, to prevent overloading the gas turbine in the event of a reactor trip, the maximum power level for the operating reactor will be limited to 50%. These conserv-ative limits are set to improve transmission system reliability only and are not dictated by safety system requirements.
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References FSAR Section 8.
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Unit'1 - Amendment No. 34 Unit 2 - Amendment No. 88 15.3.7-5 I
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