ML20036A775
| ML20036A775 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/04/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036A774 | List: |
| References | |
| NUDOCS 9305140187 | |
| Download: ML20036A775 (5) | |
Text
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UNITED STATES
[ ' dZl? ) j NUCLEAR REGULATORY COMMISSION g
W AsWNGTON. D.C. 205064m l
i COMMONWEALTH EDISON COMPANY i
DOCKET NO. 50-295 i
ZION NUCLEAR POWER STATION. UNIT 1
[
AMENDMENT TO FACILITY OPERATING tICENSE Amendment No. 145 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 3, 1993, 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; 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 this 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. OPR-39 is hereby amended to read as follows:
i 9305140187 930504
~
PDR ADDCK 05000295 P
i i
- i 4
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145
, are hereby incorporated in the license. The licensee shall operate the facility in i
accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
[
FOR THE NUCLEAR REGULATORY COMMISSION MSC f.
OV James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Reguation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 4, 1993 i
6
ATTACHMENT TO llCENSE AMENDMENT f
AMENDMENT NO. 145 TO FACILITY OPERATING LICENSE NO. DPR-39
.t DOCKET NO. 50-295
[
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 192b 192b 192c 192c e
i s
i t
j l
j l
s l
I
.m 1.
2.
-3.
TOTAL NO.
REQUIRED NO.
MfNIMUM OPERABLE
.IN11RUMENT (PARAMETERJ OF_ CHANNELS OLClLANNELS CHANNEL,5 12.
PZR PORV Position Indicator
- 1/ valve 1/ valve
- 1/ valve
- 13.
PZR PORV Block Valve Position Indicator
- 1/ valve 1/ valve
- 1/ valve
- 14.
PZR Safety Valve Position Indicator **(Primary: Temperature Detectors) 3-(1/ valve) 1/ valve 1/ valve 15.
PZR Safety Valve Position Indicator (Backup:
Acoustic Monitors) 3-(1/ valve) 1/ valve N/A 16.
2 1
17.
Containment Recirculation Sump level 2
2 1
18.
Containment Hater level (Hide Range) 2 2
1 19.
Reactor Vessel Hater Level (Hide Range)
[At least one RCP running]
2 2
1 20.
Reactor V60sel Hater level (Narrow Range)
[All RCPs stopped]
2 2
1 21.
Condensate Storage Tank Level 2
2 1
22.
Neutron Flux Monitoring +++
2 2
1 23.
Containment Isolation Valve Position Indicators +
1/ valve 1/ valve +
1/ valve +
E 3
Not required if the PZR PORV Block Valve is closed and de-energized in accordance with Specification 3.3.1.F.
EI Direct Indication of PZR Safety Valve Position - NUREG 0578, Item 2.1.3.a.
8 An OPERABLE channel consists of at least-2 core exit thermocouples per core quadrant.
Not required for isolation valves whose associated penetration is isolated.
l
+
@i Neutron Flux Monitoring instrumentation is not required until startup from refueling outage Z1R13 for Unit 1
+++
and Z2R13 for Unit 2.
A c cid entJon_i_t o r_in5LIntt r ume n ta tion _1 Con tin u e dl Table 3.8.9-1 (Continued) 192b
CHANNEL CHANNEL'
[NSIRUMENT (PARAMETER 1
_ CHECK _
CALIBRATI_QN
- 1. Containment Pressure (Hide Range)
H R
- 2. Reactor Coolant Outlet Temperature - THOT (Hide Range)
M R
- 4. Reactor Coolant Pressure (Hide Range) COLD (Hide Range)
- 3. Reactor Coolant Inlet Temperature - T M
R M
R
- 5. Steam Line Pressure M
R
- 6. Pressurizer Hater Level M
R
- 7. Steam Generator Water Level (Narrow Range)
M R
- 8. Steam Generator Water level (Hide Range)
M R
- 9. Refueling Water Storage Tank Level M
R
- 10. Auxiliary Feedwater Flow Rate M
R 11 Reactor Coolant System Subcooling Margin M
R
- 12. PZR PORV Position Indicator M
R 13.-PZR PORV Block Valve Position Indicator M
R
- 14. PZR Safety Valve Position Indicator **(Primary: Temperature Detectors)
M R
- 15. PZR Safety Valve Position Indicator (Backup: Acoustic Monitors)
M R
- 16. Core Exit Thermocouples M
R
- 17. Containment Recirculation Sump Level M
R+
l
- 18. Containment Hater level (Hide Range)
M R
- 19. Reactor Vessel Water Level (Hide Range)
M R
- 20. Reactor Vessel Hater Level (Narrow Range)
H R
- 21. Condensate Storage Tank Level M
R
- 22. Neutron Flux Monitoring H++
R++
- 23. Containment Isolation Valve Position Indicators M
R (excluding check valves) g Direct indication of PZR Safety Valve Position - NUREG 0578. Item 2.1.3.a.
g.
+
The specified 18 month frequency for Containment Recirculation Sump Level instrumentation may cy be extended for Unit i until the end of refueling outage ZlR13.
Surveillance requirements for Neutron Flux Monitoring instrumentation are not required untti startup from g
++
refueling outage ZlR13 for Unit I and Z2R13 for Unit 2.
r+
5 I,
u kcid ea t_ffonitor i n a jnit_r_umentatinn_Satv ejllanc.e_Re_quite meat 1 n
r Table 4.8.9-1 l
192c l
L
.