ML20042F163
| ML20042F163 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/19/1989 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042F164 | List: |
| References | |
| NUDOCS 9005070307 | |
| Download: ML20042F163 (8) | |
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UNITED $TATES NUCLEAR REGULATORY COMMISSION '-
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, NORTHERN STATES POWER COMPANY-DOCKET NO. 50_-263 MONTICELLO NUCLEAR GENERATING PLANT.
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.:71 License No. DPR-22~
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated August 2, 1989, 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 101CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by.
this anendment'can be conducted without endangering the health and
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. safety of the public, and (ii) that such activities will.be conducted in compliance with the Comission's regulations; D.
The issuance of this amendirent will not be inimical to the comon defense and security or to-the-health and safety of-the public; and l
E.
'The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission2s 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:
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Technical Specifications '
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The Technical Specifications contained in Appendix A, as-revised through Amendment No. 71, 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 THE NUCLEAR REGULATORY COMMISSION l
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John 0.>Thoma, Acting Director i
Project Directorate III Division of Reactor Projects - III, q
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IV, V & Special Projects-Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications l
i Date of Issuance: October 19, 1989
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4 ATTACHMENT TO LICENSE AMENDMENT NO.' 71 FACILITY OPERATING LICENSE NO. DPR-22 i
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DOCKET NO 50-263 L
Revise Appendix A Technical Specifications by removing the pages. identified-I
" below and inserting the attached pages.
The revised pagesiare identified by-amendment number and contain marginal; lines indicating the area of change.
l REMOVE INSERT 11 ii vi vj 170 170 171 171 171a 172 172 173 174 182 182 k
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O Page-I 3.4 and 4.4 Standby Liquid control Systes 93 A.
Normal Operation 93 B.
Operation with Inoperable Components 94 C..
Volume Concentration Requirements 95 3.4 and 4.4 Bases 99 J
3.5 and 4.5 Core and containment Cooling Systems 101 A.
Core Spray System 101-B.
LPCI Subsystem 103 C.
RHR Service Water System 106 D.
HPCI System 108 E.
Automatic Pressure Relief System 109 F.
RCIC System 111 g
C.
Minimum Core and Containment Cooling Systes Availability 112 H.
Recirculation System 114 I.- Deleted 3.5 Bases 115 4.5 Bases 120 3.6 and 4.6 Primary System Boundary 121' A.
Reactor Coolant Heatup and Cooldown 121:
,I B.
Reactor Vessel Temperature and Pressure-122.
C.
Coolant Chemistry 123-D.
Coolant Laakage 126 E.
Safety / Relief Valves 127 F.
Deleted l
G.
Jet Pumps 128 H.
Snubbers 129 3.6 and 4.6 Bases 144 3.7 and 4.7 Containment Systems 156 A.
156 i
B.
Standby Cas Treatment System 166 L
C.
Secondary Containment 169 D.
Primary Containment-Isolation Valves 170~
L E.
Combustible Cas Control' System 172 3.7 Bases 175
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4.7 Bases 183 i
Amendment flo. 9,35,A7,71 i
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LIST OF TABi2S.
Table No.
f.A&R 3.1.1 Reactor Protection System (Scram) Instrument Requirements 28 4.1.1-Scram Instrument Funetional Tests Minimus Funetional 32 Test Frequencies for Safety Instrumentation and Control Circuits 4.1.2 Scram Instrument Calibration - Minimum Calibration 34 Frequencies for Reactor Protection Instrument Channels 3.2.1 Instrumentation that Initiates Primary Containment 49 Isolation Functions 3.2.2 Instrumentation that Initiates Emergency Core cooling Systems 52 i
3.2.3 Instrumentation that Initiates Rod Block 57 3.2.4 Instrumentation that Initiates Reactor Building Ventilation 59 Isolation and Standby Cas Treatment System Initiation 3.2.5 Instrumentation that Initiates a Recirculation Pump Trip 60 and Alternate Rod Injection 3.2.6 Instrumentation for Safeguards' Bus Degraded Voltage and -
60a Loss of Voltage Protection
-l 3.2.7 Instrumentation for Safety / Relief Valve Low-Low Set Logic 60b 3.2.8 other Instrumentation-60d 3.2.9 Instrumentation for Control Room Habitability Protection 60e
- I 4.2.1 Minimum Test and Calibration Frequency for Core Cooling, Rod 61 Block and Isolation Instrumentation j
3.8.1 Radioactive Liquid Effluent Monitoring Instrumentation 1891 3.8.2 Radioactive Caseous Effluent Monitoring Instrumentation 198k 4.8.1 Radioactive Liquid Effluent Monitoring Instrumentation 198m Surveillance Requirements 4.8.2 Radioactive Caseous Effluent Monitoring Instrumentation 198n Surveillance Requirements 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 198p 4.8.4 Radioactive Caseous Waste Sampling and Analysis Program 198s
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vi Amendment flo. 37,39,4A,45,65,71 2_-
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIRENENTS reactor core, operations with a potential for reducing the shutdown margin below that specified in specification 3.3.A, and handling of irradiated fuel or the fuel cask in the secondary containment are to be immediately suspended if. secondary containment. Integrity is not main-tained.
D.
Primary Containment Automatic' Isolation Valves D.
Primary Containment Automatic Isolation Valvas 1.
During reactor power operating conditions, 1.
The primary containment automaticisolation valve all Primary Containment automatic isolation surveillance shall'be performed as follows:
valves and all primary system instrument line flow check valves shall be operable except a.
At least once per operating cycle the as specified in 3.7.D.2.
operable isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure times.
b.
At least once per operating cycle the primary system instrusent line flow check valves shall be tested for proper operation.
c.
At least once per quarter (1) All normally open power-operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully
. closed and reopened.
e 3.7/4.7 170 t
Amendment No. 3,71 n
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS c.
At least once per quarter - Continued
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(2) With the reactor power less than f
75% of rated, trip main steam isolation valves (one at a time) and verify closure time.
d.
At least once per week the main steam-line power-operated isolation _ valves shall be exercised by partial closure and subsequent reopening.
2.
In the event any Primary Containment automatic 2.
Whenever a Primary Containment automatic isolation valve becomes inoperable, reactor isolation valve is inoperable, the position of f
operation in the run mode may-continue-at least one fully closed valve in each line prov Med at least one valve in each line-.
having an inoperable valve.shall be recorded havicg an inoperable valve is closed.
daily.
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3.
If Specification 3.7.D.1 and 3.7.D.2 cannot 3.
A Primary Containment automatic isolation valve be met, initiate normal orderly shutdown shall be demonstrated Operable prior to and have reactor in the cold shutdown returning the valve to service after maintenance,
'i condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit by performance of a cycling test and verification of operating time.
4.
The seat seals of the drywell and suppression.
chamber 18-inch purge and vent valves shall be replaced at least once every five years.
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}l 3.7/4.7 171.
l Amendment No. 64,71 I
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3.0 LIMITING CAS CONTROL SYSTEM 4.0 SURVEILIANCE REQUIREMENTS E.
Combustible Gas Control System E.
Combustible Gas Control System
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1.
Two separate and independent Combustible 1.
At least once an operating cycle, Cas Control System trains shall be operable perform the following:
at all times whenever the reactor is in the run code except as specified in a.
Calibrate the following instrumentation Section 3.7.E.2 and 3.7.E.3 below, and control circuits 2.
After one of the Combustible Gas Control 1.
Inlet flow indicator System train (s).is made or found to be 2.
Total Flow indicator inoperable for any reason,' restore the 3.
Return gas high temperature inoperable train to operable status 4.
High reaction chamber temperature within 30 days or submit a special report to the Commission within the next 30 days which b.
Perform a resistance to ground test includes the following information:
on all heater electrical circulta
- 1) Identification of the inoperable equipment c.
Verify through a visual esamination that or subsystems and the reason for inoperability, there is no evidence of abnormal conditions.
- 2) Action (s) to be taken to restore equipment 2.
At least once every six months verify the to operable status, and recombiner reaction chamber operability by verifying that the outlet temperature exceeds
- 3) Summary description of action (s) taken to 600*F within one hour and that heater current prevent recurrence.
- is within Se of rated current when the power setting is increased to manianas.
3.
With both of the Combustible Gas Control System trains inoperable for any 3.
The leak tightness of the receabiners and reason, restore at least one train to operable associated piping shall be verified during each status within 30 days or initiate an orderly shutdown when a Type A overall integrated shutdown of the reactor and be in the cold containment leakage test is required by either:
shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a.
Venting the recombiner trains to the containment.during~the Type A test, or b.
Performing a separate leakage test of both recombiner trains end. adding the results to the Type A test leakage.
l 3.7/4.7 172 Next Page is 175 Amendnent No. M,71 l
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Bes's Continued:
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While only a small amount of particulates are released from the primary contefament as a result of the loss of coolant accident, high-efficiency particulste filters before and after the cherceal filters are specified to minimize potential particulate release to the environment and to prevent l
clogging of the charcoal adsorbers. W charreal adsorbers are installed to reduce the potential release of radiotodine to the environment. h in-place test results should indicate a system leak tightness of less than 14 bypass leakage for the charcoal adsorbers using halogensted hydro-carbon and a HEFA filter ef ficiency of at least 994 removal of DOF particulates. Leberatory enbon sample test results indicate a radioactive methyl lodide removal efficiency for expected
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accident conditions. Operation of the standby gas treatment circuits sigreificantly different i
frna the design flow will change the removal efficiency of the NEPA filters and chercoal adsorbers.
If the performance requirements are met as specified, the calculated doses would be less then the guidelines stated in 10 CFR 100 for the accidents analyzed.
D.
Primary Containment Isolation valves
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Double isolation valves are provided on lines penetrating the primary containment. Cleeure of one of the valves in each line would be sufficient to meintain the integrity of the Primary Containment. Automatic initiation is required to minimize the potential leakage paths from the containment in the event of a loss-of-coolant accident. Details of the Primary Containment isolation valves are discussed in Section 5.2 of the USAR. A listing of all Friaery h=1suneet j
j automatic isolation valves including maximum operating time is given in USAR Tai >1 5.2-3b.
E.
Combustible cas Control System h function of the Combustible Gas Control System (CGCS) is to maintain oxygen concentrations in the post-accident containment atmosphere below combustible concentrations. Oxygen may be generated l
l In the hours following a loss of coolant accident from radietysis of reactor coolant.
r h Technical Specifications limit oxygen concentrations during operation to less taan four percent by volume during operation. h maintenence of an inert strere during operation precludes the i
l build-up of a combustible mixture due to a fuel metal-meter reaction. h other potential mecheaisa for generation of combustible mixtures is radiolysis of coolant which has been found to be smell.
P A special report is required to be submitted to the Commission to outline CGC5 equipment fallsres and corrective actions to be taken if inoperability of one train exceeds thirty days. In additlen, if both trains are inoperable for more than 30 days, the plant is required to shutdown until repairs can be made.
t 3.7 BASES 182 i
l Amendment No. 35,71 i
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