ML20207C193
| ML20207C193 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/29/1988 |
| 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 | |
| ML20207C197 | List: |
| References | |
| RTR-REGGD-01.097, DPR-50-A-144 NUDOCS 8808050109 | |
| Download: ML20207C193 (6) | |
Text
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'o UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION o
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY _
PENNSYLVANIAELECTRICCOMPAg GPU NUCLEAR CORPORATION DOCKET NO. 5_0_-28_9 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. DPR-50 1.
The Nuclear Regulatory Cornission (the Comission) has fuund that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(thelicensee)datedSeptember 15, 1987, complies with the standards and req)uirements of the Atomic Energy Act of 1954, as an. ended (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 the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendnent 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; I
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 E.
The issuance of this anendnent is in accordsnce with 10 CFR Part 51 of the Comission's regulations and all applicable requiren.ents have been satisfied.
8800050109 000729 PDR ADOCK 05000209 P
PNU
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-50 is hereby amended to read as follows:
(2) _ Technical Specifications The Technical S)ecifications contained in Appendix A, as revised tirough Amendr ant No.144, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
...is license amendment is effective as of its date of issuance and shall be implemented within 30 days thereafter.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n ~. Stolz, Directo P/ojpct Directorate I-DfW sion of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 29, 1988 1
ATTACHMENT TO.L._IC.EN_S_E_ AMEN _DMEN.T._NO_.
FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendnent numbers and contain vertical lines indicating the area of change.
Remove Insert 3-40b 3-40b 3-40d 3-40d 4-10a 4-10a
The Emergency Feedwater System is provided with two channels of flow instrumentation on each of the two discharge lines. Local flow indication is also available for the emergency feedwater system.
Although the pressurizer has multiple level indications, the separate indications are selectable via a switch for display on a single display.
Pressurizer level, however, can also be detemined via the patch panel and the computer log.
In addition, a second channel of pressurizer level indication is available independent of the NNI.
j Although the instruments identified in Table 3.5-2 are significant in diagnosing situations which could lead to inadequate core cooling, loss of any one of the instruments in Table 3.5-2 would not prevent continued, safe, l
reactor operation. Therefore, operation is justified for up to 7 days (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for pressurizer level). Alternate indications are available for Saturation Margin Monitors using hand calculations, the PORV/ Safety Valve position monitors using discharge line thermocouple and Reactor Coolant Drain Tank indications, and for EFW flow using Steam Generator level and EFW pump discharge pressure. Pressurizer level has two channels, one channel from NNI (3 D/P instrument strings through a single indicator) and one channel independent of the NNI. Operation with the above pressurizer level channels out of service is pemitted for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Alternate indication would be available through the plant computer.
Monitors for containment pressure, containment water level, containment hydrogen level and various high range radiation monitors are useful to i
evaluate and predict the course of accidents which go beyond the plant design basis (see Table 3.5-3).
These instruments should be maintained for that purpose.
(This capability is consistent with the recommendations of NUREG 0737, II.F.1.) Operability of the additional post-accident monitoring instrumentation identified in Table 3.5-3, ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
(This capability is consistent with the l
recomendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and i
Following an Accident," Rev. 3, May 1983. )
i 3-40b Amendment No. % ISQ. 144
[
TABLE 3.5-3 i
POST ACCIDENT MONITORING INSTRUMENTATION a
f REQUIRED NUPEER MINIMUM NUMBER FUNCTION INSTRUENTS OF CHANNELS OF CHANNELS ACTION s
1.
High Range Noble Gas Effluent
~
- a. Condenser Vacuum Pump Exhaust 1
1 A
5 (RM-AS-Hf)
- b. Condenser Vacuum Pump Exhaust 1
1 A
(RM-G5 )
- c. Auxiliary and Fuel Handling 1
1 A
Building Exhaust (RM-A8-Hi)
- d. Reactor Building Purge Exhaust 1
1 A
(RM-A9-Hi)
- e. Reactor Building Purge Exhaust 1
1 A
(RM-G24)
- f. Main Steam Lines Radiation 1
1 A
(RM-G26/RM-G27) each OTSG each OTSG 2.
Containment High Range Radiation 2
2 A
(RM-G22/G-23)
Y 3.
Containment Pressure 2
1 B
4.
Containment Water Level 2
1 B
5.
Containment Hydrogen 2
1 B
6.
Wide Range Neutron Flux 2
1 A
7.
Reactor Coolant System Cold Leg 2
1 A
Water Temperature (TE-959, %1; TI-959A, %1 A) 1 8.
Reactor Coolant System Hot Leg 2
1 A
Water Temperature (TE-958, %0; TI-958A, %0A) 9.
Reactor Coolant System Pressure 2
1 A
(PT-949, %3; PI-949A, 963) 10.
Steam Generator Pressure 2/0TSG 1/0TSG A
(PT-950, 951, 1180, 1184; PI-950A, 951 A,1180,1184) 11.
Condensate Storage Tank Water Level 2/ Tank 1/ Tank A
(LT-1060, 1061, 1062, 1063; LI-1060, 1061,1062,1063 )
l 2
I l
g TABLE 4.1-4 h
POST ACCIDENT MONITORING INSTRUMENTATION 3
e-g-
FUNCTION INSTRUE NTS CHECK TEST CALIBRATE REMARKS 1.
Noble Gas Effluent E
- a. Condenser Vacuum Pump Exhaust W
M R
(1) Using the installed check (RM-AS-Hf) source when background is less l
g than twice the expected increase in cpm which would result from the check source alone.
Background readings greater than this value are sufficient in themselves to show that this
- b. Condenser Vacuum Pump Exhaust W(1)
M R
(RM-G25)
- c. Auxiliary and Fuel Handling W
M P.
Building Exhaust (RM-A8-Hi)
- d. Reactor Building Purge Exhaust W
M R
(RM-A9-Hf) p
- e. Reactor Building Purge Exhaust W(1)
M R
(RM-G24)
?
- f. Main Steam Lines Radiation W(1)
M R
(RM-G26/RM-G27) 2.
Containment High Range Ra6fation W
M R
(RM-G22/G23) 3.
Containment Pressure W
N/A P
4.
Containoent Water Level W
N/A R
5.
Containment Hydrogen W
M R
6.
Wide Range Neutron Flux W
N/A R
4 7.
Reactor Coolant System Cold Leg W
N/A R
Water Temperature (TE-959, %1; TI-959A, %l A) 8.
Reactor Coolant Systc:a Hot Leg W
N/A R
Water Temperature (T2.-953, 960; TI-958A, 960A) 9.
Reactor Coolant System Pressure W
N/A R
(PT-949, 963; PI-949A, %3) 10.
Steam Generator Pressure W
N/A R
(PT-950 PI-950A,95195IA,1150,1184) 1180 1184; 11.
Condensate Storage Tank Water Level W
N/A R
U158: 1821: 42: 1Mh
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