ML20209D961
| ML20209D961 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/02/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209D949 | List: |
| References | |
| NUDOCS 8609090556 | |
| Download: ML20209D961 (8) | |
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U;!TED TATE 3 f
NUCLEAR REGULATORY COMMISSION n
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WASHINGTON. D. C. 20555 e
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DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE ROILING WATER REACTOR AMENDMENT TO PPOVISIONAL OPERATING LICENSE Amendment No.52 License No. DPR-45 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated February 21, 1986, as clarified July 29, 1986, 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 reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health i
l and safety of the public; and (ii) that such activities will be
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conducted in compliance with the Commission's rAgulations; 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 reoulations and all applicable requirements have been satisfied.
8609090556 e60902 PDR ADOCK 05000409 P
. 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 Provisional Operating License No. DPR-45 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment Nn. 52, 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 E NilCLEAR REC ATORY COMMISSION A
w1 Joh A. Zwolinski, Director RWR roject Directorate #1 Division of RWR Licensing
Attachment:
Chanaes to the Technical Specifications Date of Issuance: September 2,1986 l
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ATTACHMENT TO LICENSE AMENDMENT NO.52 PROVISIONAL OPERATING LICENSE N0. nPP-45 DOCKET NO. 50-409 Revise Appendix A Technical Specifications by renoving the pages identified below and inserting the attached paces. The revised pages are identified by the captioned amendment number and contain marginal 1,ines indicating the area of change.
REMOVE INSERT i
i 12 12 13 13 13a 32r/61 32rl7)
4 TABLE OF CONTENTS 3
Page 1.
SITE,............................
I 1.1 LOCATION I
1.2 EXCLUSION AND RESTRICTED AREAS I
1.3 PRINCIPAL ACTIVITIES 1
2.
DESIGN AND PERFORMANCE REQUIREMENTS 1
2.1 REACTOR BUILDING 1
2.2 REACTOR VESSEL 3
2.3 FORCED CIRCULATION SYSTEM................
4 2.4 REACTOR AUXILIARY SYSTEMS................
6 2.5 MAIN STEAM AND FEEDWATER LOOP..............
11 2.6 DELETED 2.7 REACTOR CORE AND VESSEL INTERNALS............
2.8 CONTROL R0D DRIVE SYSTEM 16 2.9 CONTROL SYSTEMS.....................
17 "
2.10 SAFETY AND MONITORING SYSTEMS..............
18
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2.11 WASTE DISPOSAL 21 2.12 FUEL STORAGE AND HANDLING................
22 3.
APPLICABILITY 23 4
OPERATING LIMITATIONS 27d 4.0.1 DEFINITIONS.......................
27d 4.1 GENERAL..................
28 4.2 OPERATIONS LIMITS....................
28 4.3 RADI0 ACTIVE EFFLUENTS..................
38 5.
MAINTENANCE 5.1 5.1 GENERAL 5.1 5.2 TESTING.........................
5.2 i
Anerdment No. 25, 36,52 l
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2.5.3 Turbine Main Steam Bypass Valve The turbine main steam bypass valve shall be capable of bypassing at least 100 percent of rated steam flow directly to the condenser. It shall be hydraulically operated and shall have a maximum full stroke opening time of 1.5 sec. It shall be capable of automatic or remote manaal operation.
2.5.4 Main Turbine Condenser System 2.5.4.1 The main turbine condenser system shall have sufficient capacity to condense full rated steam flow of the reactor while the turbine is being bypassed.
2.5 4.2 Loss of vacuum shall cause safety actions to be initiated as specified in Table 1, or as a result of turbine trip.
2.5.5 condensate Demineralization System The condensate demineralization system shall be espable of removing soluble and insoluble impurities from the turbine condensate by ion exchange and filtration.
u 2.5.6 Feedwater System, 2.5.6.1 The feedwater system shall be capable of returning condensate through a high pressure feedwater heater to the forced circulation pump suction header by either of two centrifugal pumps.
2.5.6.2 The pumps shall be driven by constant speed motors through variable speed fluid couplings and shall be capable of either manual control or automatic control of a three-element feedwater control system.
2.5.6.3 The feedwater line shall have a check valve within the reactor l
building and a remote manually-controlled shutoff valve within the turbine building.
i 2.6 Deleted 2.7 REACTOR CORE AND VESSEL INTERNALS 2.7.1 Vessel Internals and Core Structure 2.7.1.1 The vessel internals shall include a thermal shield, a core support skirt, a plenum separator plate, a bottom grid assembly, internal steam separators, a thermal shock shield, a baffle plate structure with a peripheral lip, steam dryer with support structure, emergency core spray tube bundle structure combined with fuel hold-down mechanism, and the reactor core structure.
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4.2.3 ELECTRICAL POWER SYSTEMS The OPERABILITY of the normal and backup electrical power systems ensures that s
sufficient power will be available to supply necesary plant equipment during normal operation and following a loss of offsite power event.
i For normal operation, all power for reactor and turbine auxiliary equipment is supplied by the main generator through the unit auxiliary transformer or the reserve auxiliary transformer. During startup or shutdown, or in the event of
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f 411ure of power from the unit auxiliary transformer, power is supplied by a connection to the external grid via the reserve auxiliary transformer.
The onsite power distribution system is divided between two independent 2400 volt buses, and each component of duplicated equipment is supplied by a different bus. The duplicated equipment includes the primary system forced circulation pumps, the reactor feedwater pumps, the condensate pumps, and the condenser circulating water pumps. Each 2400 volt bus also supplies power to a 480 volt bus.
If the supply to either 480 volt bus fails, a connection may l
be manually made from the other 480 volt bus using a control switch in the
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Qon'troleroom. Duplicate equipment is also supplied by the 480 volt buses.
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Each 480 volt bus normally supplies power to its associated essential bus.
The 480 volt Bus lA supplies the 480 volt Essential Switchgear Bus lA.
The 480 volt Essential Switchgear Bus lA supplies high pressure core spray pump 1A 4
and Turbine Building Motor Control center lA which supplies the Turbine Building 120, volt Bus,which in turn supplies the Turbine Building 120 volt Regulated Bus. Diesel Generator 1A serves as the backup power supply for the l
480 volt'Epery.ialSwitchgearBuslA.
Turbine $,uildingMotorControlCenter1AsuppliespowerfortheReactorPlant Battery Charter. hhe Reactor Plant Battery Charger carries the load and
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charges the.batteriea on the Reactor Plant 125 volt DC Bus.
The Reactor Plant i_
125 volt DC Bus normally supplies power for Static Inverter lA which supplies power to essential reactor instrumentation and control circuits connected to
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120 volt AC Non-Interruptible Bus lA.
In case of Static Inverter lA trouble,
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a transfer swit;h located in Static Inverter lA automatically transfers to its p,
.g alternate power supply which is Turbine Building 120 volt Regulated Bus.
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j' The 480 volt BusilB supplies power to the 480 volt Turbine Building Motor l
Control Center ID.
7urbine Building Motor Control Center ID is the normal l
supply for the Generator Plant 125 volt DC Bua through the Generator Plant Battery Charger.
The Genera *:or PI mt 125 volt DC Bus normally supplies power to a Generator Plant 125 Volt DC di ribution panel which supplies power to essential reactor instrumentation a control circuits connected to 120 Volt jfK'
. AC Non-Interrupt.ible Bus 16.
The static switch of the Static Inverter 1C is capable of supplying power from Static Inverter 1C or its reserve 120 Volt AC power source. IncaseokStaticInverter1Ctrouble,thestaticswitchwill lf f.el 3*,
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Amendment No. 52 1s s
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d automatically transfer from the output of Static Inverter IC to the reserve transformer which is supplied from Turbice Bailding Motor Control Center lA.
The Reactor.?lant 125 Volt DC Bus is capable of providing power to the Generator Plant 125 Volt DC Bus through a normally open tie breaker.
The Diesel Building 480 volt Essential Switchgear Bus 1B supplies high pressure core spray pump 1B, seal injection pump 1B, Reactor Building Motor Control Center 1A and Diesel Building 480 volt Motor Control Center. Diesel Generator 1B is the emergency power supply for the Diesel Building 480 volt Essential Switch ear Bus 1B.
The Diesel Building 480 volt Motor Control E
Center supplies power for the Piesel Building Battery Charger.
The Diesel Building Battery Charger carries the load of and charges the batteries on the Diesel Building 125 volt DC Bus.
The Diesel Building 125 Volt DC Bus is the normal power supply for Static Inverter 1B which supplies power to essential reactor instrumentation and control circuits connected to 120 Volt AC Non-Interruptible Bus 1B.
In case of Static Inverter 1B trouble, its static switch can automatically transfer from the output of Static Inverter IB to the output of its reserve transformer which is supplied by the Diesel Building 480 volt Motor Control Center. The Turbine Building 170 volt Regulated Bus is the reserve feed for the 120 Volt a
AC Non-Interruptibba Bus IB.
The normally open reserve tie breaker is administrative 1y controlled as are other tie breakers.
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Amendment No. 52 WPl.6.9 s__