ML20128C226
| ML20128C226 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/24/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20128C229 | List: |
| References | |
| DPR-50-A-166 NUDOCS 9212040294 | |
| Download: ML20128C226 (6) | |
Text
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METROPOLITAN EDISON CQ8EMY JERSEY CENTRAL POWER & LIQlT COMPANY EMISYLVANIA ELECTRIC COMPANY Gr'V NUCLEAR CORPORAT.LQH DOCKET N0m50-289 THREE MILE ISLAND N ELEAR STATION. UNIT NO, 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 166 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated December 3, 1991, 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; 8.
The facility wi'il operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reac aable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety c the public, and (ii) that such activities will be conduct.d in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security v to the health and safety of the public; and E.
Tr-issuance of this amendment h in accord nce with 10 CFR Part 51 of the Cornission's regulations and all applicable requirements have been satisfied.
9212040294 921124 DR ADOCK 0500 9
, 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 f acility Operating License No.
DPR-50 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in A)pendix A, as revised through Amendment f.o.166, are here)y incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment ir effective as of its date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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oh
- f. Stolz, Direc r Pr ject Directorate
-4 7 vision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
November 24, 1992 1
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i ATTACHMENT TO LICENSE AMENDMENT NO. 166 fli]11TY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following ) ages of the Appendix A Technical Specifications with the attached pages.
T1e revised pages are identified by amendment number and contain vertical lines indicating the area of change.
RLava loiar_t 1-4 1-4 1-4a 3-40d 3-40d 3-40e 3-40e r
f 4
4 1.5.2 CHANNEL TEST A CHANNEL TEST shall be the inje.; tion of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.
1.5.3 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
1.5.4 CHANNEL CAllBRATION An instrument CHANNEL CALIBRATION is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values.
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.
1.5.5 HEAT BALANCE CHECK A HEAT BALANCE CHECK is a comparison of the indicated neutron power and core thermal power.
1.5,6 HEAT BALANCE CALIBRATION A HEAT BALANCE CALIBRATION is an adjustment of the power range channel amplifiers output based on the core thermal power determination.
I l
l l
l-4 Amendment No. JM*, 157,166 y"m ti.s.
I' 4'
4-TABLE 3.5-3 POST ACCIDENT MONITORING INSTRUMENTATION h
.' E '
cn REQUIRED NUMBER MINIMUM NUMBER FUNCTION INSTRUMENTS OF CHANNELS OF CHANNELS ACTION
'M 1.
High Range Noble Gas Effluent
.g a.
Condenser Vacuum Pump Exhaust (RM-AS-Hi)
I 1
A m
b.
Condenser Vacuum Pump Exhaust (RM-G25) 1 1
A c.
Auxiliary and Fuel Handling 1
1 A
Building Exhaust (RM-A8-HI) d.
Reactor Building Purge Exhaust (RM-A9-Hi) 1 1
A i
e.
Reactor Building Purge Exhaust (RM-G24) 1 1
A f.
Main Steam Lines Radiation 1
1 A
i
-(RM-G26/RM-G27) each OTSG-each OTSG 2.
Containment High Range Radiation 2
2 A
(RM-G22/G-23) wL
'3.
Containment Pressure 2.
I B
!?
4.
Containment Water Level a.
Containment Flood (LT-806/807) 2 1
B b.
Containment Sump (LT-804/805) 1 0
0 5.
Containment Hydrogen 2
1 8
6.
Wide Range Neutron Flux 2
1 A
7.
Reactor Coolant System Cold Leg Water 2
1 A
Temperature (TE-959, 961; TI-959A, %1A) 8.-
. Reactor Coolant System Hot Leg Water 2.
1 A
Temperature (TE-958, 960; TI-958A, %0A) 9..
Reactor Coolant System' Pressure 2
1 A
(PT-949, %3; - PI-949A, 963) '
10.
Steam Generator Pressure (PT-950, 951,l1180, 2/0TSG 1/0TSG A
1184; PI-950A, 951A, 1180, 1184) i
..11.
' Condensate Storage Tank Water Level (LT-1060, 2/ Tank 1/ Tank A
l 1061, 1062, 1063; LI-1060, 1061, 1062, 1063)-
uc2
a TABLE 3.5-3 (Continued)
With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirements:
1.
eitherrestoretheinoperablechannel(s)toOPERABLEstatus within 7 days of the event, or 2.
prepare and submit a Special Report within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
B.
1.
With the number of OPERABLE accident monitoring instrumen-tation channels less than the Required Channels OPERABLE requirements, restoru the inoperable channel (s) to OPERABLE status within 30 days or be in at least 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 />.
2, With the r mber of OPERABLE accident monitoring instrumen-tation chtnnels less than the Minimum Channels OPERABLE requirements, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least 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 />.
C.
Restore the inoperable sump level instrument to OPERABLE status prior to startup following the COLD SHUTDOWN subsequent to its inoperability declaration.
i
(
3-40e Amendment No. 100,166
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