ML20093F034
| ML20093F034 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/02/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20093F039 | List: |
| References | |
| TAC-M89739, NUDOCS 9510170244 | |
| Download: ML20093F034 (8) | |
Text
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UNITED STATES g'.
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066H001 t
'+,.....,o HQf0BERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT
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AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 94 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The application for amendment by Northern States Power Company (the licensee) dated June 18, 1994, as superseded April 20, 1995, and supplemented August 18, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),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 tho Act, and the rules and regulations of the Comission; 1
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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, a
and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby amended to read as follows:
9510170244 951002
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~i PDR ADOCK 05000263 P
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l Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94
, 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 NUCl. EAR REGULATORY COMMISSION 4
4 sg%c-Tae Kim, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 2, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE N0. 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 166 166 167 167 168 168 169 169 188 188 1
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L 3.0 LIMITING CONDITIONS FUR OPERATION 4.0 SURVEILLANCE REQUIRENENTS c.
Except for inerting and deinerting operations permitted in (b) above, all containment purging and venting above cold shutdown shall be via a 2-inch purge and vent valve bypass line and the 3
Inerting and deinerting operations may be via the 18-inch purge and vent valves (equipped with 40-degree limit stops) aligned to the Reactor Building plenum and vent.
- 6. If the specifications of 3.7.A cannot be met, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Standby Cas Treatment System B.
- 1. Two separate and independent standby 1.
Once per month, operate each train of gas treatment system circuits shall be the standby gas treatment system for operable at all times when secondary 2:10 continuous hours with the inline containment integrity is required, except as heaters operating.
specified in sections 3.7.B.1.(a) and (b).
a.
After one of the standby gas treatment system circuits is made or found to be inoperable for any reason, reactor l
operation and fuel handling is l
permissible only during the succeeding seven days, provided that all active components in the other standby gas f
treatment system are operable. Within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following the 7 days, the reactor shall be placed in a condition for which the standby gas treatment system is not required in accordance with Specification 3.7.C.2.(a) through (d).
3.7/4.7 166 Amendment No. 66, 77, 166, 94 i
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS b.
If both standby gas treatment system circuits are not operable, within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> the reactor shall be placed in a condition for which the standby gas treatment system is not required in accordance with Specification 3.7.C.2.(a) through (d).
2.
Performance Requirements 2.
Performance Requirement Tests a.
Periedic Requirements a.
At least once per 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation ; or once per operating cycle.
(1)
The results of the in-place but not to exceed 18 months, whichever DOP tests at 3500 cfa (110%)
occurs first; or following painting, on HEPA filters shall show fire, or chemical release in any vent-511 DOP penetration.
11ation zone communicating with the system while the system is operating (2)
The results of in-place halo-that could contaminate the HEPA filters genated hydrocarbon tests at or charcoal adsorbers, perform the l
3500 cfm ( 10%) on charcoal following:
banks shall show $1% penetra-tion.
(1) In-place DOP test the HEPA filter.
banks.
(3)
The results of laboratory carbon sample analysis shall (2) In-place test the charcoal adsorber show 2941 methyl iodine re-banks with halogenated hydrocarbon moval efficiency when tested tracer.
at 309C, 95% relative humidity.
t (3) Remove one carbon test canister from the charcoal adsorber.
Sub-ject this sample to a laboratory analysis to verify methyl iodine removal efficiency.
3.7/4.7 167 Amendment No. 60, 77, 167, 94
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i 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS b.
The system shall be shown to be b.
At least once per operating cycle, but operable with:
not to exceed 18 months, the following conditions shall be demonstrated for each r
(1)
Combined filter pressure standby gas treatment system:
1 drop $6 inches water.
(1) Pressure drop across the combined (2)
Inline heater power output filters of each standby gas treat-218kW.
ment system circuit shall be measured at 3500 cfm (1101) flow l
c.
The system shall be shown to be rate.
operable with automatic initiation upon receipt of the following inputs:
(2) Operability of inline heater at I
nominal rated power shall be l
(a)
Iow low Reactor Water level, verified.
or c.
At least once per operating cycle, 1
(b)
High drywell pressure, or automatic initiation of each standby gas treatment system circuit shall be (c)
Reactor building ventilation demonstrated.
plenum high radiation, or (d)
Refueling floor high radiation 3.
Post Maintenance Requirements
- 3. Post Maintenance Testing l
a.
After any maintenance or testing a.
After any maintenance or testing that could affect the HEPA filter that could affect the leak tight or HEPA filter mounting frame integrity of the HEPA filters,.
leak tight integrity, the results perform in-place DOP tests on the of the in-place DOP tests at 3500 HEPA filters, cfm (1101) on HEPA filters shall show $11 DOP penetration.
b.
After any maintenance or testing that could affect the leak tight integrity
- b. After any maintenance or testing of the charcoal adsorber banks, per-that could affect the charcoal form halogenated hydrocarbon tests adsorber leak tight integrity, the on the charcoal adsorbers.
results of in-place halogenated hydrocarbon tests at 3500 cfm (1101) on charcoal adsorber banks shall show $11 penetration.
168 3.7/4.7 Amendment No. 94
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS C.
Except as specified in 3.7.C.2 and 1.
Secondary containment surveillance shall-3.7.C.3, Secondary Containment Integrity be performed as indicated below:
shall be maintained during all modes of plant operation.
a.
Secondary containment capability to maintain at least a 1/4 inch of water 2.
Secondary Containment Integrity is not vacuum under calm wind (u < 5 mph)
I required when all of the following conditions with a filter train flow conditions are satisfied:
rate of $4,000 sefs, shall be demonstrated at each refueling outage a.
The reactor is subcritical and prior to refueling.
If calm wind Specification 3.3.A is set.
conditions do not exist during this testing, the test data is to be b.
The reactor water temperature is corrected to calm wind conditions.
b.
Verification that each automatic l
c.
No activity is being performed which damper actuates to its isolation can reduce the shutdown margin below position shall be performed:
that specified in Specification 3.3.A l
(1) Each refueling outage.
d.
The fuel cask or irradiated fuel is not being moved within the reactor (2) After maintenance, repair or l
building.
replacement work is performed on the damper or its masociated 3.
With an inoperable secondary containment actuator, control circuit, or isolation damper, restore the inoperable power circuit.
damper to operable status or isolate the affected duct by use of a closed damper or blind flange within eight hours.
4.
If Specifications 3.7.C.1 through 3.7.C.3 cannot be met, initiate a normal orderly shutdown and have the reactor in the Cold Shutdown condition l
within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Alterations of the 3.7/4.7 169 I
Amendment No. 3, 63, 76, 94
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Bases Continued:
l-B.
Standby Cas Treatment System, and C.
i Initiating reactor building isolation and operation of the standby gas treatment system to maintain the design negative pressure within the secondary containment provides an adequate test of the reactor building isolation valves and the standby gas treatment system.
Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment systen operational capability. Secondary Containment Capability Test data obtained under non-calm conditions is to be extrapolated to calm wind conditions using information provided in " Summary Technical Report to the United States Atomic Energy Commission, Directorate of Licensing, on Secondary Containment Leak Rate Test", submitted by letter dated July 23, 1973, and as described in NSP letter to the NRC dated August 18, 1995, with subject, " Revision 2 to License Amendment Request Dated June 8,1994, Standby Cas Treatment'and Secondary Containment Technical Specifications."'
The frequency. of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated.
Standby gas treatment system inplace testing procedures will be established utilizing applicable sections of ANSI N510-1989 standard as a procedural guideline only.
If
'l painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals, or foreign materials, the same tests and sample analysis should be performed as required for operational use.
Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52 Revision 2 (March 1978). The charcoal adsorber efficiency test l
procedures will allow for the removal of a representative sample. The 30"C, 951 relative humidity test per ASTM D 3803-89 is the test method to establish the methyl iodine removal efficiency of the adsorbent. The sample will be at least two inches in diameter and a length equal to the thickness of the bed. If the l
iodine removal efficiency test results are unacceptable, all adsorbent in the system will be replaced. High efficiency particulate filters are installed before and after the charcoal filters to prevent clogging of the carbon adsorbers and to minimize potential release of particulates to the environment. An efficiency of.
991 is adequate to retain particulates that may be released to the reactor building following an accident.
This will be demonstrated by inplace testing with DOP as the testing medium. Any HEPA filters found defective will be replaced with filters qualified pursuant to regulatory guida position C.3.d of Regulatory Guide 1.52 Revision 2 (March 1978). Once per operating cycle demonstration of HEPA filter pressure drop, operability of inline heaters at rated power, automatic initiation of each standby gas treatment system l
circuit, and leakage tests after maintenance or testing which could affect leakage, is necessary to assure system performance capability.
4.7 BASES 188 Amendment No. 94 1
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