ML20072K520
| ML20072K520 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/25/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072K524 | List: |
| References | |
| NUDOCS 9408300134 | |
| Download: ML20072K520 (10) | |
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E UNITED STATES i
l a-NUCLEAR REGULATORY COMMISSION q
WASHINGTON, D.C. 2055MKioi
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NORTHERN STATES POWER COMPANY j
DOCKET NO. 50-263 l
MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 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 November 30, 1993, as supplemented June 30,-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; j
l B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i
safety of the_ public, and (ii) that such activities will be conducted in compliance with the Commission's regul_ations; 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 i
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:
l i
i 9408300134 940825
.yDR-ADOCK 05000263 PDR
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- Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 89, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N{
Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 25, 1994 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 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 48 48 60e 60e 63 63 69a 69a 229u 229u 229v 229v 229y 229y r
3
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS F.
Recirculation Pump Trip and Alternate Rod Injection Initiation Whenever the reactor is in the RUN mode, the Limiting Conditions for Operation for the instrumentation listed in Table 3.2.5 shall be met.
G.
Safeguards Bus Voltage Protection Whenever the safeguards auxiliary electrical power system is required to be operable by Specification 3.9, the Limiting Conditions for Operation for the Instrumentation listed in Table 3.2.6 shall be met.
H.
Instrumentation for Safety / Relief Valve Low-Low Set Logic Whenever the safety / relief valves are required to be operable by Specification 3.6.E, the Limiting Conditions for Operation for the Instrumentation listed in Table 3.2.7 shall be i
met.
I.
Instrumentation for Control Room Habitability Protection 1.
Whenever.the emergency filtration system is required to be operable by Specification 3.17.B. the Limiting Conditions for Operation for the radiation instrumentation listed in Table 3.2.9 shall be met.
3.2/4.2 48 Amendment No. J8r, }6, E5, 89
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l Table 3.2.9 Instrumentation for Control Room Habitability Protection Total No. of Minimum No. of Operable Instrument or-operating Minimum No.
Required Trip Channels per Instrument Channels of Conditions
- Function Bettines Trio System oer Trio System (1)
Trio Systems Radiation 52 mR/hr 1
1 2
A or B Notes:
(1)
An instrument channel may be bypassed for testing or preventative maintenance for up to eight hours.
Required conditions when minimum conditions for operation are not satisfied.
A) Within I hour initiate and maintain operation of the control room emergency filtration system subsystem in the pressurization mode of operation.
B) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reduce reactor water temperature to below 212'F.
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3.2/4.2 60e Amendment No. h5, 89
O.
Table 4.2.1 - Continued Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation Instrument Channel Test (3)
Calibration (3)
Sensor Check (3) 1 SAFEGUARDS BUS VOLTAGE 1.
Degraded Voltage Once/ month Quarterly Not applicable Protection 2.
Loss of Voltage Once/ month once/ Operating Cycle Not applicable Protection SAFETY / RELIEF VALVE LOW-LOW SET IDCIC 1.
Reactor Scram Sensing Once/ Shutdown (Note 8) 2.
Reactor Pressure - Opening Once/3 months (Note 5) Once/ Operating Cycle Once/ day 3.
Reactor Pressure - Closing Once/3 months (Note 5) Once/ Operating Cycle Once/ day 4
Discharge Pipe Pressure once/3 months (Note 5) See Table 4.14.1 See Table 4.14.1 5.
Inhibit Timer once/3 months (Note 5) Once/ Operating Cycle CONTROL ROOM HABITABILITY PROTECTION 1.
Radiation Monthly (Note 5) 18 months Daily 3.2/4.2 63 Amendment No. fa, H. M, 89
D Bases Continued:
3.2 open and instrumentation drift has caused the nominal 80-psi blowdown range to be reduced to 60 psi.
Maximum water leg clearing time has been calculated to be less than 6 seconds for the Monticello design.
Inhibit timers are provided for each valve to prevent the valve from being manually opened l
1ess than 10 seconds following valve closure. Valve opening is sensed by pressure switches in the l
valve discharge line.
Each valve is provided with two trip, or actuation, systems.
Each system la l
provided with two channels of instrumentation for each of the above described functions. A two-out-of-two-once logic scheme ensures that no single failure will defeat the low-low set function and no single failure will cause spurious operation of a safety / relief valve. Allowable deviations are provided for each specified instrument setpoint. Setpoints within the specified allowable i
deviations provide assurance that subsequent safety / relief valve actuations are sufficiently spaced to allow for discharge line water leg clearing.
l Control room habitability protection instrumentation assures that the control room operators will be adequately protected against the effects of accidental releases of radioactive leakage which may bypass secondary containment following a loss of coolant accident or radioactive releases from a steam line break accident, thus assuring that the Monticello Nuclear Generating Plant can be operated or shutdown safely.
Although the operator will set the setpoints within the trip settings specified in Tables 3.2.1 through 3.2.9, the actual values of the various set points can differ appreciably from the value the operator is attempting to set.
The deviations could be caused by inherent instrument error, operator setting error, drift of the set point, etc.
Therefore, these deviations have been accounted for in the various transient analyses and the actual trip settings may vary by the following amounts:
- 3. 2 BAS ES 69a Amendment No. 55, 70', 89
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.17 CONTROL ROOM HABITABILITY 4.17 CONTROL ROOM HABITABILITY Applicability:
Applicability:
Applies to the control room ventilation Applies to the periodic testing requirements system equipment necessary to maintain of systems regulred to maintain control room habitability.
habitability.
Oblectives:;
Oblectives:
To assure the control room is habitable both To verify the operability of equipment under normal and accident conditions.
related to control room habitability.
Specification:
Specification:
A. Control Room Ventilation System A.
Control Room Ventilation System 1.
Except as specified in 3.17.A.2 and 1.
At least once per shift, check 3.17.A.3 below, both trains of the control room temperature.
control room ventilation system shall be operable, whenever irradiated fuel is in the reactor vessel and reactor coolant temperature is greater than 212*F, or during movement of irradiated fuel assemblies in the secondary containment, core alterations or activities having the potential for draining the reactor vessel.
2.a With one control room ventilation train inoperable, restore the inoperable train to operable status within 30 days.
2.b If 2.a is not met, then be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following the 30 days and in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.c If 2.a is not met during movement of irradiated fuel assemblies in the secondary containment, core alterations or activies having the potential for draining the reactor vessel then immediately place the operable control room ventilation train in operation or immediately suspend these activities.
3.17/4.17 229u Amendment No. 65. 89
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEIL 1 RICE REQUIREMENTS 3.a With both control room ventilation trains inoperable, restore at least one train to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.b If 3.a is not met, then be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.c If 3.a is not met during movement of irradiated fuel assemblies in the secondary containment, core alterations, or activities having the potential for draining the reactor vessel then inurediately suspend these activities.
B.
Control Room Emergency Filtration System B.
Control Room Emergency Filtration System 1.
Except as specified in 3.17.8.1.a or 1.
At least once per month, initiate from 3.17.B.1.b below, two control room the control room 1000 cfm (1101) flow emergency filtration system filter trains through both trains of the emergency shall be operable whenever irradiated filtration treatment system. The system fuel is in the reactor vessel and reactor shall operate for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with coolant temperature is greater than the heaters operable.
212*F.
When one control room emergency a.
filtration system filter train is made or found to be inoperable, for any reason, restore the inoperable train to operable status within seven days or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following the seven days and either reduce the reactor coolant temperature to below 212*F or initiate and maintain the operable emergency filtration system filter train in the pressurization mode within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.17/4.17 229v n mon,unn + un c.c on
3.17 Bases A.
Control Room Ventilation System The Control Room Ventilation System provides air conditioning and heating as required to maintain a suitable environment in the main control room and portions of the first and second floors of the Emergency Filtration Train (EFT) building.
The main control room is normally slightly pressurized and it is possible to have O to 100% recirculation of conditioned air.
The system is designed to maintain a nominal temperature of 78*F dry bulb and 50% nominal relative humidity in the main control room in the summer and a nominal temperature or 72*F in the winter. The Control Room Ventilation System may be isolated from unfiltered external air supply by manual action.
All toxic substances which are stored on site or stored / shipped within a 5 mile radius of the plant have been analyzed for their affect on the control room operators.
It has been concluded that the operators will h' ave at least two minutes to don protective breathing apparatus before incapacitation limits are exceeded.
For toxic substance which are transported on highways within 5 miles of the plant, it has been determined that the probability of a release from the plant due to incapacitation of the operators caused by a spill is sufficiently low that this scenario may be excluded.
Protection for toxic chemicals is provided through operator training.
B.
Control Room Emergency Filtration System The Control Room Emergency Filtration System assures that the control room operators will be adequately protected against the effects of radioactive leakage which may by-pass secondary containment following a loss of coolant accident or radioactive releases from a steam line break accident. The system is designed to isolate and slightly pressurize the control room on a radiation signal in the ventilation air.
Two completely redundant trains are provided.
Each train has a filter unit consisting of a prefilter, HEPA filters, and charcoal adsorbers. The HEPA filters remove particulates from the Control Room pressurizing air and prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to remove any radiolodines form the pressurizing air.
The in-place test results should indicate a HEPA filter leakage of less than 1% through DOP testing and a charcoal adsorber leakage of less than II through halogenated hydrocarbon testing. He laboratory carbon sample results should indicate a radioactive methyl iodide removal efficiency of a least 98% under test conditions similar to expected accident conditions.
System flows should be near their design values. The verification of these performance parameters combined with the qualification testing conducted on new filters and adsorbers provide a high level of assurance that the Emergency Filtration System will perform as predicted in reducing doses to plant personnel below those level stated in Criterion 19 of Appendix A to 10 CFR 50.
Dose calculations have been performed for the Control Room Emergency Filtration System which show that, assuming 90% standby gas treatment system adsorption and filtration efficiency and 90% control room emergency filtration system adsorption and filtration efficiency and radiolodine plateout, whole body and organ doses remain within the NRC guidelines of 5 rem and 30 rem, respectively.
3.17 BASES 229y Amendment No. JMI, 89
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