ML17056C187
| ML17056C187 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/17/1992 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056C188 | List: |
| References | |
| NUDOCS 9212300360 | |
| Download: ML17056C187 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMM1SSION WASHINGTON, D.C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 136 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated September 17,
- 1992, 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
'hapter 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 th'is 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-63 is hereby amended to read as follows:
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PDR ADQCK 05000220 P
PDRJ
(2)
Technica S ec'cat'o s
The Technical Specificatiorts contained in Appendices A and B,
as revised through Amendment No. 136, 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 to be implemented prior to startup from the next refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 17, 1992 Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
1H
TACHMEN TO LICENSE AMENDMENT AMENDMENT NO. >36 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es iiia 24liil 24lii2 241 ii3 Insert Pa es iiia 24liil 241 i i2 241i i3
SECTION DESCRIPTION PAGE 3.6.5 Radioactive Material Sources 3.6.6 3.6.7 3.6.8 3.6.9 (Deleted)
(Deleted)
(Deleted)
(Deleted) 3.6.12 Reactor Protection System and Reactor Trip System Power Supply Monitoring 3.6.10 (Deleted) 3.6.11 Accident Monitoring Instrumentation 4.6.5 4.6.6 4.6.7 4.6.8 4.6.9 4.6.10 4.6.11 4.6.12 Radioactive Material Sources (Deleted)
(Deleted)
(Deleted)
(Deleted)
(Deleted)
Accident Monitoring Instrumentation Reactor Protection System and Reactor Trip System Power Supply Monitoring 241k 241ee 241iil 3.6.13 Remote Shutdown Panels 4.6.13 Remote Shutdown Panels 241ii4 3.6.14 Radioactive Effluent Instrumentation 4.6.14 Radioactive Effluent Instrumentation 241j) 3.6.15 Radioactive Effluents 4.6.15 Radioactive Effluents 241ww 3.6.16 Radioactive Effluent Treatment Systems 4.6.16 Radioactive Effluent Treatment Systems 241qqq 3.6.17 Explosive Gas Mixture 3.6.18 Mark I Containment 3.6.19 Liquid Waste Holdup Tanks 3.6.20 Radiological Environmental Monitoring Program 4.6.17 Explosive Gas Mixture 4.6.18 4.6.19 Mark I Containment Liquid Waste Holdup Tanks 4.6.20 Radiological Environmental Monitoring Program 241ttt 241vvv 24lxxx 24lzzz 3.6.21 Interlaboratory Comparison Program 3.6.22 Land Use Census
- 4. 6.21 4.6.22 Interlaboratory Comparison Program Land Use Census 2411111 241nnnn Amendment No.~~,p2~~~g, 136 iiia
LIMITINGCONDITION FOR OPERATION 3.6.12 REA R PR TE I
Y TEM D REA R
TRIP Y
EM P WER PPLY IT RIN SURVEILLANCEREQUIREMENT 4.6.12 REA R PR TE N
Y TEM AND REA R
T IP TEM P WER PPLY M NIT RIN
~y+iglhllly:
+gllig~ili Applies to the operability of instrumentation that provides protection of the reactor protection system and reactor trip system.
Applies to the surveillance of instrumentation that provides protection of the reactor protection system and reactor trip system.
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To assure the operability of the instrumentation monitoring the power to the reactor protection system and reactor trip system.
To verify the operability of protection instrumentation monitoring the power to the reactor protection and reactor trip buses.
/rifipion:
$~ecifi quinn:
a.
Except as specified in specifications b and c below, two protective relay systems shall be operable for each power supply.
a.
I nc ev ixm nth Demonstrate operability of the overvoltage, under-voltage and underfrequency protective instrumentation by performing an instrument channel test.
This instrument channel test willconsist of simulating abnormal power conditions by applying from a test j
source, an overvoltage signal, an undervoltage signal and an underfrequency signal to verify that the tripping logic up to but not including the output contactors functions properly.
Amendment No.g, 136 241ii1
le<<
LIMITINGCONDITION FOR OPERATION 3.6.12 RE R PR TE I N Y TEM AND REA TRIP Y TEM P WER PPLY M NIT RIN (cont'd)
SURVEILLANCEREQUIREMENT 4.6.12 EA R PR TE NSY TEM AND REA TRIP Y TEM P WER PPLY M NIT RIN (con".d)
$~~ific<~in: (cont'd)
~ecific ion: (cont'd)
- b. With one protective relaying system inoperable, restore the inoperable system to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the power supply from service.
- c. With both protective relaying systems inoperable, restore at least one to an operable status within 30 minutes or remove the power supply from service.
b.
Iea nce er r el in cl Demonstrate operability of the overvoltage, undervoltage and underfrequency protective instrumentation by performing an instrument channel test.
This instrument channel test willconsist of simulating abnormal power conditions by applying from a test source an overvoltage signal, an undervoltage signal and an underfrequency signal to verify that the tripping logic including the output contactors functions properly at least once.
In addition, a sensor calibration willbe performed to verify the following setpoints.
- i. Overvoltage
< 132 volts, < 4 seconds ii. Undervoltage
> 108 volts, < 4 seconds iii. Underfrequency 57 hertz, < 2 seconds Amendment No.g, 136 241ii2
BA F
R 2A D4 12REA RPR TE NIT RIN Y
M D REA R TRI Y
W PLY To eliminate the potential for undetectable single component failure which could adversely affect the operability of the reactor protection-system and reactor trip system, protective relaying schemes are installed on Motor Generator Sets 131 and 141, Static Uninterruptible Power Supply Systems 162 and 172, and maintenance bus 130A. This provides for overvoltage, undervoltage and underfrequency protection.
Amendment No.
241ii3