ML20072U069
| ML20072U069 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/09/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072U071 | List: |
| References | |
| NUDOCS 9409160103 | |
| Download: ML20072U069 (6) | |
Text
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S UNITED STATES l
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NUCLEAR REGULATORY COMMISSION t,, v j#
WASHINGTON, D.C. 2055MMX)1 NORTHERN STATES POWER COMPANY DOCKET N0. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9i License No. DPR-22
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Northern States Power Company (the licensee) dated March 28, 1994, 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, 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 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 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 regulations and all applicable requirements have been satisfied.
- 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 Facility Operating License No. DPR-22 is hereby amended to read as follows:
1 9409160103 940909 l.
PDR ADOCK 05000263 i
P PDR L
i
_2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, are hereby incorporated in the license.
The licensee l
shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance.
j FOR THE NUCLEAR REGULATORY COMMISSION l
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Ledyard B. Marsh, Director l
Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 9,1994 l
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i ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET N0. 50-263 i
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 59 59 62 62 70 70 i
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i Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation And Standby Gas Treatment System Initiation Min. No. of Operable Total No. of Instru-or Operating Instrument ment Channels Per Trip Channels Per Trip Required j
Function Trio Settines System System (Notes 1. 21 Conditions
- t 1.
Low Low Reactor 26'-6", 56'-10" 2
2 A. or B.
Water Level (Note 3) 2.
High Drywell Pres-52 psig 2
2 A. or B.
sure (Note 3) 3.
Reactor Building 5100 mR/hr 1
1 (Note 4)
A, or B.
Plenum Radiation Monitors 4.
Refueling Floor
$100 mR/hr 1
1 (Note 4)
A. or B.
Radiation Monitors There shall be two operable or tripped trip systems for each function with two instrument channels per trip system Notes:
(1) and there shall be one operable or tripped trip system for each function with one instrument channel per trip system.
Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels (2) are not satisfied action shall be initiated to:
Satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (a)
Place the plant under the specified required conditions using normal operating procedures.
(b)
(3) Need not be operable when primary containment integrity is not required.
(4) One of the two monitors may be bypassed for maintenance and/or testing.
- Required Conditions when minimum conditions for operation are not satisfied.
The reactor building ventilation system isolated and the standby gas treatment system operating.
A.
Establish conditions where secondary containment is not required.
B.
59 3.2/4.2 REV Amendment No. G6, J(, 91
Minimum Test and Calibration Frequency For Core Cooling Rod Block and Isolation Instrumentation Instrument Channel Test (3)
Calibration (3)
Sensor Check (3) 3.
Steam Line Low Pressure Once/3 months once/3 months-None 4.
Reactor Low Low Water Level Once/3 months f, Note 5) Every Operating Cycle-Once/ shift Transmitter Once/3 Months-Trip Unit CONTAINMENT IS01ATION (CROUPS 2 & 3) 1.
Reactor Imv Vater Level (Note 10) 2.
Drywell High Pressure (Note 10)
HPCI (GROUP 4) ISOLATION 1.
Steam Line High Flow Once/ month once/3 months-None 2.
Steam Line High Temperature Once/ month once/3 months None RCIC (CROUP 5) IS01ATION 1.
Ste'au Line High Flow Once/ month Once/3 months None 2.
Steam Line High Temperature Once/ month Once/3 months None REACTOR BUILDING VENTIIATION & STANDBY GAS TREATMENT 1.
Reactor law Imv Unter IAvel Once/3 months (Note 5) Every Operating Cycle -
Once/ shift Transmitter once/3 months - Trip Unit 2.
Drywell High Pressure (Note 10)
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3.
Radiation Monitors (Plenum)
Once/ month once/3 months once/ day 4.
Radiation Monitors (Refueling Floor)
Once/ month Once/3 months Note 4 RECIRCUIATION PUHF. TRIP AND ALTERNATE ROD INJECTION 1.
Reactor High Pressurn Once/ month (Note 5)
Once/ Operating Cycle-Once/ Day Transmitter Once/3 Months-Trip Unit 2.
Reactor law law Water Level Once/ month (Note 5)
Once/ Operating Cycle-Once/ shift-Transmitter Once/3 Months-Trip Unit SHUTDOWN COOLING SUPPLY.IS01ATION i
1.
Reactor Pressure Interlock.
Once/ month Once/3 Months None l
3.2/4.2 62 REV Amendment No. J(, F, pa', 91
Trio Function Deviation Reactor Building Ventilation Isolation and Reactor Building Vent
+5 mR/hr Standby Cas Treatment System Initiation Plenum Monitors Specification 3.2.E.3 and Table 3.2.4 Refueling Floor
+5 mR/hr Radiation Monitors
- Low Low Reactor Water Level
-3 inches l
High Drywell Pressure
+1 psi I
- Low Low Vater Level
-3 inches Primary Containment Isolation Functions Table 3.2.1 High Flow in Main Steam Line
+21 High Temp. In Main Steam
+10*F Line Tunnel Low Pressure in Main Steam
-10 psi Line High Drywell Pressure
+1 psi
- Low Reactor Water Imvel
-6 inches l
HPCI High Steam Flow
+7,500 lb/hr HPCI Steam Line Area High
+2*F Temp.
RCIC High Steam Flow
+2250 lb/hr RCIC Steam Line Area High Temp
+2*F Shutdown Cooling Supply ISO
+7 psi i
t 70 3.2 BASES REV a
Amendment No. 20, 46, ft, 91 I
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