ML19341B336
| ML19341B336 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/14/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341B334 | List: |
| References | |
| NUDOCS 8101300752 | |
| Download: ML19341B336 (12) | |
Text
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UNITED STATES
'g NUCLEAR REGULATORY COMMISSION y
WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT 1 A'4ENDMENT TO FACILITY O!'ERATING LICENSE Amendment No. 60 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The applications for amendment by Commonwealth Edison Company (the licensee) dated October 31, 1977, December 22, 1978, and October 24, 1980 comply 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 applications, the provisions of the Act, and the rules ad regulations of the Connission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safaty 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 tne 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.
101300 3
4
_2-2.
Ascordingly, 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, 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.
FC$ THE NUCLEAR REGU ATORY COMMISSION
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,' C i Operating Reactors Branc,1 Division of Licensing i
Attachment:
Changes to the Technical Specifications Date of Issuance: January 14, 1981 i
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O' UNITED STATES
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j, NUCLEAR REGULATORY COMMISSION I #'
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T 4,.....P COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-304 ZION STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Commonwealth Edison Company (the licensee) dated October 31, 1977, December 22, 1978, and October 24, 1980 comply 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 applications, 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.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as inJ eated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective as of the date of its issuance.
FOR THE NUCLE REG TORY COMMISSION T
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even A. Virga, Ch, ef f Operating Reactors Brancti 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 14, 1981 9"
i 1
4 ATTACllMENT TO LICENSE AMENDMENTS AMENDMENT NO. 60 TO FACILITY OPERATING LICENSE NO. OPR-39 AMENDMENT NO. 57 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 i
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Revise Appendix A as follows:
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Remove Pages Insert Pages 4
35 35 i
38 38 140 140
[
205 205 t
206 206 Revise Appendix 8 as follows:
+
Remove Pages Insert Pages 9
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Reactor Trip Channel Channel Channel Channel Description Check Calibration Function Test Remarks
~
l'.
Manual S/U(1)
(1) If not done in previous week.
S/U(4)]
(1) Heat Bilance Calibration l
2.
Power Range Neutron Flux S
(Low Setpoint)
(2) Recal ibrate D(1 )
M (3) Comoare incore to excore axial imbalar.ce.
3.
Power Range Neutron Flux S
g(p)
Recalibrate as Der specification 3.2.2.'.1 i
'i EFPM(3) 4 Power Range Positive Flux Rate N.A.
M I
if difference >l%.
l 5.
Power Range Negative Flux Rate N. A.)
M (a) Once per month when in-service. Not I
i required if performed within the previous i
1 7 days.
i
{.
6 Source Range Neutron Flux S(1)
N.A.
S/U(1)
(1 ) Once/ Shift when in-service.
i 7.
Intermediate Range Neutron S(l)
N.A.
S/U(2)
(?) Not required if performed within the previous 7 days.
t 8.
Overtemperature LT S-
'R M
i
- Overpower aT S
R M
4 l
I
- 10. Pressurizer Low Pressure S
R M
t
'll.
S R
M Pressurizer High Pressure J.
- 12. Pressurizer High level S
R M
4
- 13. Low Primary Coolant Flow S_
R M
14 RCP Bus Un'dervoltage N.A.
R R
- 15. RCP Bus Underfrequency N.A.
R R
- 16. RCP Breaker Trip N.A.
N.A.
R 4
TABLE 4.1-1 Reactor Protection System Testing and Calibration Pequirements*
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35 Amendment No. 60, Unit 1 Amendment No. 57, Unit 2 i
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Bases:
4.1 The bases for Tables 3.1-1 and 4.1-1 such signals would generally be originated is an analysis of the reactor pro-by more than one functional unit.
There-tection and control instrumentation fore, from the standpoint of accomplishing systems.
Conservative failure rates the required trip or actuation, far greater for the individual channels were em-redundancy exists than is credited in esta-ployed based on published data typical blishing the specification tables.
for individual components in the channels.
The test and calibration frequencies are The Power Range Neutron Flux (Low Setpoint) therefore quite conservative.
channel function test is not performed continually above 25% power levels due to Considerable added conservatism is in-the possibility of inducing inadvertent i
herent in the analysis since no credit reactor trips.
trio is a redundant -
was established for the fact that there trip at low power and the test is to be i
exists a wide margin of diversity in performed at startup and as soon as is trip signal origin.(1) Should a situa-practical on controlled shutdown if the tion develop which would require a trip, power is to remain at low levels (below 10%)
for any extended periods of time.
l (1)
FSAR Section 7.2 l
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38 Amendment No. 60, Unit 1 Amendment No. 57, Unit 2
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Continuity Chec A to Fina?
Device Actuation Actuating Device
(
G) Service Water Pump Starts and' System Isolation (cont.)
Component OM0V-SW0005 X
OMOV-SWOOO8 X
OFCV-SW54 X
Service Water Pump 1C (2C)
X j'
MOV-SW0002 X
2 MOV-500115 X
X OMOV-SW0007 X
OMOV-SWOO10 OMOV-SW0009 X
H) Containment Isolation Phase "A" & Isolation Valve Seal Water Component i
A0V-VC8149 A X
A0V-DT9159A X-A0V-DT9160A X
LCV-DT1003 X
Reactor Coolant Drain' Pump 1 A (2A)
X Reactor Coolant Drain Pump 1B (2B)
X FCV-SS9354A X
-FCV-SS9355A X
i FCV-SS9356A X
FCV-SS9357A X
X FCV-1A01A FCV-PR24A X
X FCV-FP08 FCV-SS02 X
FCV-SS03 X
)
X FCV-SSO4 l
FCV-SS05
.X ACV-VC8149C X.
Engineered Safeguards Equipment Actuation Test TABLE 4.4-2 (Sheet 5 of 8)
Amendment No. 60, Unit 1 Amen 6nent N. 57, '5it ?
140 i
Valve Service Valve Service MOV-VC8100 R.C. pump seal 'iater return A0V-BD0001 Blowdown from steam genermor (double disc)
& FCV-3D17 MOV-CC9414 Cooling water return from R.C.
A0V-BD0002 Blowdown from steam generator (double disc) puans
&FCV-BD17 MOV-CC9413 A&B Cooling water supply to R. C.
AOV-BD0003 Blowdown from steam generator pumps
& FCV-BD17 A0V-CC9437 Cooling water return from ex-AOV-BD0004 Blowdown from steam generator cess letdown heat exchanger
& FCV-BD17 C09500 Cooling water supply to excess A0V-BD0005 Blowdown from steam generator letdown heat exchanger
& FCV-BD17 MOV-CC9438 &
Cooling water return from ex-A0V-BD0006 Blowdown fror steam generator FCV685 cess letdown heat exchanger
& FCV-BD17 FCV-FP08 Fire protectio'n to containment AOV-BD0007 Blowdown from steam generator
& FCV-BD17 CS0052 &
Containment pressure sensor CS0053 inlet A0V-BD0008 Blowdown from stean generator
& FCV-BD17 CSOO54 &
Containment pressure sensor CS0055 inlet FCV-SS02 Blowdown fror. stean generator CS0056 &
Containment pressure sensor CS0057 inlet FCV-SS03 Blowdown from steam generator sample CS0058 &
Containment pressure sensor CS0059 inlet mend "t
o.
6, Un t Containment Isolation valves dmen 9
gn TABLE 4.9-3 205
Valve Service Valve Service
?CV-SSO4 Blowdown fror steam generator A0V-VC8152 &
Letdown to regenerative heat sample VC8153 exchanger FCV-SSOS Blowdown from steam generator SF8787 &
Purification puma to refueling SFOO10 cavity sample FCV 'dD17 A & B Discharge from containment SF8767 &
defueling cavity drain OSF0011(Unit 1) sump oumps OSFOO12(Unit 2)
VC8369A &
R.C. seal water sunply FCV-VK02 A & B Non-filtered vents from containment VC8372A
'vC8369B &
H.C. seal water supply FCV-VF01 A&B Filtered vents from containment VC8372B FCV-PR19 A & B Reactor vessel leak detection
.VC83690 &
R.C. seal water supply FCV-PR2O A & B Reactor vessel leak detection VC8372C VC8369D &
R.C. seal water supply FCV-PR21 A&B Reactor vessel leak detection VC8372D FCV-PR22 A & B Reactor vessel leak detection AOV-RC8025 &
Pressurizer relief tank to RC8026 waste gas analyzer FCV-PH23 A & B Reactor vessel leak detection reference AOV-ItC8028 &
Prir.ary water to press. relief FCV-PR24 A & B Containment air carticulate + gas RC6029 tank monitor inlet A0V-RC8024 &
Nitrogen nanifold to press.
Containment air particulate & gas RC8033 relief tank
'PR0029 &
T30030 monitor outlet l
VC848 0 A &. B R.C. loop fill header Containment air sampling inlet Pil0007 &
M0/-VCB105 k.
Charging to regenerative heat PROOO8 VCB106 exchanger Containment Isolation Valves Amendment No. 60 Un't TABLE 4.9-3 (Cont.)
AmendmentNo.57,*Unt) 206
?.40NITORING REQUIREMENTS ENVIRONMENTAL PROTECTION CONDITIONS 2.3 CHEMICAL EFFLUENTS (Cont'd) 1.3 CIIEMICAL EFFLUENTS (Cont'd)
B.2 (a)
The results of the monitoring program under Section 2.3.B.l(a) above shall be reported in accordance with Section 3.0.
If the discharge of a chemical is greater than that addressed in the FES or subsequent NRC Environmental Impact Appraisals, an evalua-tion of the environmental impact of the discharge shall be included in the annual report.
B.2 (b)
The information documented in the monitoring program in Section 2.3.B.1 (b) above will be maintained in station records and reported with evaluations provided in the l
annual report as required by 3ection 2.3.B.2(a) above.
l C.
N.A.*
C.
N.A.*
D.
N. A.*
D.
Sanitary Wastes All sanitary wastes are discharged
- Not Applicable to th'c North Shore Sanitary District for treatment.
9 Anendment No. 60. Unit 1 Anendment No. 57, Unit 2
_