ML20149B756
| ML20149B756 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood |
| Issue date: | 07/10/1997 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149B760 | List: |
| References | |
| NPF-37-A-091, NPF-66-A-090, NPF-72-A-084, NPF-77-A-083 NUDOCS 9707150033 | |
| Download: ML20149B756 (18) | |
Text
..
[* '%,4 UNITED STATES g-g j
NUCLEAR REGULATORY COMMISSION
- ~ '
4 WASHINGTON, D.C. 30666-0001
~ _ _ _
Y+9....,d COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 20, 1997, 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 (1) 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
9707150033 970710 DR ADOCK 050004 4
i
)
i (2)
Igghnical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 91 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Geo F. Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance: July 10, 1997
pw0 g,
t UNITED STATES y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON. D.C. 3066H001 e
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. NPF-66 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
)
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 20, 1997, 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 1; 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 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; j
i 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
1 i
4 (2)
Technical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 90 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications. and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Geor F. Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
^
Attachment:
Changes to the Technical Specifications i
l Date of Issuance: July 10, 1997 l
l li i
.n..
ATTACHMENT TO LICENSE AMENDMENT NOS. 91 AND 90 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 1
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 3/4 6-21 3/4 6-21 3/4 6-22 3/4 6-22 3/4 6-23 3/4 6-23 3/4 6-24 3/4 6-24 i
TABLE 3.6-1 (Continued) i CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SFM 6.
Maj.n., Steam Isolation (Continued) 85 MS101B*
86 MS101C*
7.
Feedwater Isolation 76 FWOO9D*
Main Feedwater 5
76 FWO43D*##
Main Feedwater 6
l 79 FWOO9A*
Main Feedwater 5
79 FWO43A*##
Main Feedwater 6
l 84 FWOO9B*
Main Feedwater 5
84 FWO43B*##
Main Feedwater 6
l 87 FWOO9C*
Main Feedwater 5
87 FWO43C*##
Main Feedwater 6
99##(76)***
FWO350*
Main Feedwater 6
99##(76)***
FWO39D*
Main Feedwater 6
100##(79)*** FWO35A*
Main Feedwater 6
100##(79)*** FWO39A*
Main Feedwater 6
10l##(84)*** FWO35B*
Main Feedwater 6
10l##(84)*** FWO39B*
Main Feedwater 6
102##(87)*** FWO35C*
Main Feedwater 6
102##(87)*** FWO39C*
Main Feedwater 6
8.
Remote Manual 68 RH8701A*,#
RH Suction N.A.
68 RH3701B*,#
RH Suction N.A.
75 RH8702A*,#
RH Suction N.A.
75 RH8702B*,#
RH Suction N.A.
59 SI8881*
Hot Leg Safety Injection N.A.
73 SI8824*
Hot Leg Safety Injection N.A.
66 S18825*
Hot Leg RH Injection N.A.
60 SI8823*
Cold Leg Safety Injection N.A.
50 SI8890A*
Cold Leg RH Injection N.A.
51 SI8890B*
Cold Leg RH Injection N.A.
26 SI8843*
Cold Leg Safety Injection N.A.
33 CV8355A*
RCP Seal Injection N.A.
33 CV83550*
RCP Seal Injection N.A.
53 CV83556*
RCP Seal Injection N.A.
53 CV8355C*
RCP Seal Injection N.A.
BYRON - UNITS 1 & 2 3/4 6-21 AMENDMENT NO. 91 & 90
TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SEC) 8.
Remote Manual (Continued) 59 SI8802A*
Hot Leg Safety Injection N.A.
73 SI88028*
Hot Leg Safety Injection N.A.
60 518835*
Hot Leg Safety Injection N.A.
50 SI8809A*
RH Cold Leg Injection N.A.
51 SI8809B*
RH Cold Leg Injection N.A.
66 S18840*
Hot Leg Safety Injection N.A.
100##(79)*** AF013A*
Feedwater N.A.
1 100##(79)*** AF013E*
Feedwater N.A.
10l##(84)*** AF013B*
Feedwater N.A.
10l##(84)*** AF013F*
Feedwater N.A.
102##(87)*** AF013C*
Feedwater N.A.
4 102##(87)*** AF013G*
Feedwater N.A.
99##(76)***
AF013D*
Feedwater N.A.
99##(76)***
AF013H*
Feedwater N.A.
9.
Manual 37 CV8346*
RCS Loop Fill N.A.
1 13 VQOl6 Instrument Penetration N.A.
13 VQ017 Instrument Penetration N.A.
I3 VQ018 Instrument Penetration N.A.
13 VQ019 Instrument Penetration N.A.
15 RYO75 Instrument Penetration N.A.
30 WM190 Make-Up Demin N.A.
57 FC009 Spent Fuel Pool Cleaning N.A.
57 FC010 Spent Fuel Pool Cleaning N.A.
32 FC011 Spent Fuel Pool Cleaning N.A.
32 FC012 Spent Fuel Pool Cleaning N.A.
77 MS021D*,#
Main Steam N.A.
78 MS021A*,#
Main Steam N.A.
85 MS021B*,#
Nain Steam N.A.
i 86 MS021C*,#
Main Steam N.A.
AL PR002E#
Process Radiation N.A.
AL PR033A#
Process Radiation N.A.
AL PR033Bf Process Radiation N.A.
AL PR002F#
Process Radiation N.A.
AL PR033C#
Process Radiation N.A.
AL PR0330#
Process Radiation N.A.
8YRON - UNITS 1 & 2 3/4 6-22 AMENDMENT NO. 91 & 90 4
f TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SEC) 9.
Manual (Continued) 99 FW015D*,f Feedwater## cit s.n.r tor a.circut. tion >***
N.A.
100 FWO15A*,i Feedwater## cat senerator a.circut. tion >***
N.A.
101 FWO158*,#
Feedwater## cit s.n.r tor a.circut. tion >***
N.A.
102 FWO15C*,#
Feedwater## cat s.nerator a.circut. tion >***
N.A.
- 10. Check 28 CV8113 RCP Seal Water Return N.A.
37 CV8348*
RCS Loop Fill N.A.
6 W9007A Chilled Water N.A.
10 Wp0078 Chilled Water N.A.
21 CC9534 RCP Mtr Brng Return N.A.
24 CC9518 RCP Thermal Barrier Return N.A.
25 CC9486 RCP Cooling Wtr Supply N.A.
1 CS008A Containment Spray N.A.
16 CS008B Containment Spray N.A.
39 IA091 Instrument Air N.A.
30 WM191 Make-Up Demin N.A.
i l
52 PR032 Process Radiation N.A.
AL PR002G Process Radiation N.A.
AL PR002H Process Radiation N.A.
12 PS231A Hydrogen Monitor N.A.
31 PS231B Hydrogen Monitor N.A.
44 RY8046 PRT Make-Up N.A.
26 S18815*
Safety Injection N.A.
50 SI881PL Gafety Injection N.A.
50 S188180*
Safety Injection N.A.
51 S188188*
Safety Injection N.A.
51 SI8818C*
Safety Injection N.A.
59 SI8905A*
Safety Injection N.A.
59 SI8905D*
Safety Injection N.A.
60 SI8819A*
Safety Injection N.A.
60 SI8819B*
Safety Injection N.A.
BYRON - UNITS 1 & 2 3/4 6-23 AMENDMENT NO. 91 8 90
TABLE 3.6-1 (Continued) l CONTAINMENT ISOLATION VALVES i
MAXIMUM PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SEC)
- 10. Check (Continued) 60 SIB 819C*
Safety Injection N.A.
60 SIB 819D*
Safety Injection N.A.
66 SI8841A*
Safety Injection N.A.
66 SI88418*
Safety Injection N.A.
73 SI8905B*
Safety Injection N.A.
73 SI8905C*
Safety Injection N.A.
55 SI8968 Safety Injection N.A.
34 FP345*
Fire Protection N.A.
33 CV8368A*
RCP Seal Injection N.A.
33 CV83680*
RCP Seal Injection N.A.
53 CV8368B*
RCP Seal Injection N.A.
53 CV8368C*
RCP Seal Injection N.A.
- 11. S/G Safeties /PORVs 77 MSOF;D*
Main Steam N.A.
77 MS014D*
Main Steam N.A.
77 MS0150*
Main Steam N.A.
77 MS0160*
Main Steam N.A.
77 MS017D*
Main Steam N.A.
78 MS013A*
Main Steam N.A.
78 MS014A*
Main Steam N.A.
78 MS015A*
Main Steam N.A.
78 MS016A*
Main Steam N.A.
78 MS017A*
Main Steam N.A.
85 MS013B*
Main Steam N.A.
85 MS0148*
Main Steam N.A.
85 MS015B*
Main Steam N.A.
85 MS016B*
Main Steam N.A.
85 MS017B*
Main Steam N.A.
86 MS013C*
Main Steam N.A.
86 MS014C*
Main Steam N.A.
86 MS015C*
Main Steam N.A.
86 MS016C*
Main Steam N.A.
86 MS017C*
Main Steam N.A.
77 MS0180*
Main Steam 20 78 MS018A*
Main Steam 20 85 MS0188*
Main Steam 20 86 MS018C*
Main Steam 20
- Not subject to Type C leakage tests.
- Proper valve operation will be demonstrated by verifying that the valve j
strokes to its required position.
- Not applicable to Unit 2. Appliable to Unit I after Cycle 8.
l
- May be opened on an intermittent basis under administrative control.
HApplicable to Unit I through Cycle 8 and to Unit 2.
l BYRON - UNITS 1 & 2 3/4 6-24 AMENDMENT NO. 91 & 90
__ _.________ _ __ ___ __j
gA Qiu t
m m s w as g
j NUCLEAR RECULATORY COMMISSION
~t WASHINGTON. D.C. 2006HOO1
\\*****/
i COMMONWEALTH EDIS0N COMPANY DOCKET NO STN 50-456 BRAIDWOOD STATION. UNIT NO 1 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 20, 1997, 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
e *
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 84 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Geo
. Dick, Senior Project Manager 1
Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 10, 1997 3
i
pMk p
UNITED STATES g
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006H001
'+4.....,o LOMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 20, 1997, 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 1-B.
The facility will operate in conformity with the application, the i
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 Specifi-cations as indicated in the attachment to this license amendment, and '
paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
- (2) lechnical Soecificationi The Technical Specifications contained in Appendix A as revised through Amendment No. 83 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Pl an.
3.
This license amendment is effective as of the date if its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
'l Geor
. Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 10, 1997 J
w' b
...~.
d ATTACHMENT TO LICENSE AMENDMENT NOS. 84 AND 83 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 4
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 6-21 3/4 6-21 3/4 6-22 3/4 6-22 3/4 6-23 3/4 6-23 3/4 6-24 3/4 6-24 4
1 l
4 i
1 4
I 4
~
TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SEC) 6.
Main Steam Isolation (Continued) 85 MS101B*
86 MS101C*
7.
Feedwater Isolation 76 FW009D*
Main Feedwater 5
76 FWO43D*##
Main Feedwater 6
l 79 FW009A*
Main Feedwater 5
79 FWO43A*ff Main Feedwater 6
l 2
84 FW009B*
Main Feedwater 5
84 FWO438*##
Main Feedwater 6
l 87 FWOO9C*
Main Feedwater 5
87 FWO43C*##
Main Feedwater 6
99##(76)***
FWO350*
Main Feedwater 6
99##(76)***
FWO39D*
Main Feedwater 6
100##(79)*** FW035A*
Main Feedwater 6
100ff(79)*** FWO39A*
Main Feedwater 6
10l##(84)*** FWO358*
Main Feedwater 6
10l##(84)*** FWO39B*
Main Feedwater 6
102##(87)*** FWO35C*
Main Feedwater 6
102##(87)*** FWO39C*
Main Feedwater 6
8.
Remote Manual 68 RH8701A*,#
RH Suction N.A.
68 RH8701B*,#
RH Suction N.A.
75 RH8702A*,#
RH Suction N.A.
75 RH87028*,#
RH Suction N.A.
59 SI8881*
Hot Leg Safety Injection N.A.
73 SIB 824*
Hot Leg Safety Injection N.A.
4 66 SIB 825*
Hot Leg RH Injection N.A.
60 SI8823*
Cold Leg Safety Injection N.A.
50 S!8890A*
Cold Leg RH Injection N.A.
4 51 SIB 890B*
Cold Leg RH Injection N.A.
26 SIB 843*
Cold Leg Safety Injection N.A.
33 CV8355A*.
RCP Seal Injection N.A.
33 CV8355D*
RCP Seal Injection N.A.
53 CV8355B*
RCP Seal Injection N.A.
53 CV8355C*
RCP Seal Injection N.A.
l BRAIDWOOO - UNITS 1 & 2 3/4 6-21 AMENDMENT NO. 84 & 83 L
TABLE 3.6-1 (Continued)
[0NTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SEC) 8.
Remote Manual (Continued) 59 SIB 802A*
Hot Leg Safety Injection N.A.
73 S18802B*
Hot Leg Safety Injection N.A.
60 SI8835*
Hot Leg Safety Injection N.A.
50 SI8809A*
RH Cold Leg Injection N.A.
51 SI8809B*
RH Cold Leg Injection N.A.
66 SI8840*
Hot Leg Safety Injection M.A.
100f#(79)*** AF013A*
Feedwater N.A.
100ff(79)*** AF013E*
Feedwater N.A.
101##(84)*** AF013B*
Feedwater N.A.
10l##(84)*** AF013F*
Feedwater N.A.
102##(87)*** AF013C*
Feedwater N.A.
102##(87)*** AF013G*
Feedwater N.A.
99##(76)***
AF013D*
Feedwater N.A.
99##(76)***
AF013H*
Feedwater N.A.
9.
Manual 37 CV8346*
RCS Loop Fill N.A.
13 VQOl6 Instrument Penetration N.A.
13 VQ017 Instrument Penetration N.A.
13 VQ018 Instrument Penetration N.A.
I3 VQ019 Instrument Penetration N.A.
15 RYO75 Instrument Penetration N.A.
30 WM190 Make-Up Demin N.A.
57 FC009 Spent Fuel Pool Cleaning N.A.
57 FC010 Spent Fuel Pool Cleaning N.A.
32 FC011 Spent Fuel Pool Cleaning N.A.
32 FC012 Spent Fuel Pool Cleaning N.A.
77 MS021D*,#
Main Steam N.A.
78 MS021A*,#
Main Steam N.A.
85 MS021B*,#
Main Steam N.A.
86 MS021C*,#
Main Steam N.A.
AL PR002E#
Process Radiation N.A.
AL PR033Af Process Radiation N.A.
AL PR033Bf Process Radiation N.A.
AL PR002F#
Process Radiation N.A.
AL PR033C#
Process Radiation N.A.
AL PR033D#
Process Radiation N.A.
BRAIDWOOD - UNITS 1 & 2 3/4 6-22 AMENDMENT NO. 84 & 83
i TABLE 3.6-1 (Continued) i s
CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION 1ALVE NO.
FUNCTION ISOLATION TIME (SEC) 9.
Manual (Continued) 99 FWO15D*,#
Feedwater## cst s.nw.tw s.circut. tion >*** N. A.
100 FWO15A*,f Feedwater## cst s nw tw n.eircut tion)*** N.A.
101 FW015B*,#
Feedwater## cst s.nw.tw a.circut tion >*** N. A.
102 FWO15C*,i Feedwater## cst s nw. tor a.ctreutetten>*** N. A.
- 10. Check 28 CV8113 RCP Seal Water Return N.A.
37 CV8348*
RCS Loop Fill N.A.
6 W9007A Chilled Water N.A.
10 W90078 Chilled Water c N.A.
21 CC9534 RCP Mtr Brng Return N.A.
24 CC9518 RCP Thermal Barrier Return N.A.
25 CC9486 RCP Cooling Wtr Supply N.A.
1 CS008A Containment Spray N.A.
16 CS0088 Containment Spray N.A.
39 IA091 Instrument Air N.A.
30 WM191 Make-Up Demin N.A.
5'2 PR032 Process Radiation N.A.
i AL PR002G Process Radiation N.A.
AL PR002H Process Radiation N.A.
12 PS231A Hydrogen Monitor N.A.
31 PS2318 Hydrogen Monitor N.A.
44 RY8046 PRT Make-Up N.A.
26 SI8815*
Safety Injection N.A.
50 SI8818A*
Safety Injection N.A.
50
$188180*
Safety Injection N.A.
51 SI88188*
Safety Injection N.A.
51 SI8818C*
Safety Injection N.A.
59 SI8905A*
Safety Injection N.A.
59 SI8905D*
Safety Injection N.A.
60 SI8819A*
Safety Injection N.A.
60 SI8819B*
Safety Injection N.A.
BRAIDWOOD - UNITS 1 & 2 3/4 6-23 AMENDMENT NO. 84 & 83 1
TABLE 3.6-1 (Continued) i CONTAINMENT ISOLATION VALVES MAXIMUM j
PENETRATION VALVE NO.
FUNCTION ISOLATION TIME (SEC) i i
i
- 10. Check (Continued) 60 SI8819C*
Safety Injection N.A.
60 518819D*
Safety Injection N.A.
66 SIS 841A*
Safety Injection N.A.
66 SI8841B*
Safety Injection N.A.
73 SI8905B*
Safety Injection N.A.
73 SI8905C*
Safety Injection N.A.
55 SI8968 Safety Injection N.A.
34 FP345*
Fire Protection N.A.
33 CV8368A*
RCP Seal Injection N.A.
1 33 CV83680*
RCP Seal Injection N.A.
53 CV83688*
RCP Seal Injection N.A.
53 CV8368C*
RCP Seal Injection N.A.
j
- 11. S/G Safeties /PORVs l
77 MS013D*
Main Steam N.A.
77 MS014D*
Main Steam N.A.
77 MS0150*
Main Steam N.A.
4 77 MS0160*
Main Steam N.A.
77 MS017D*
Main Steam N.A.
78 MS013A*
Main Steam N.A.
i 78 MS014A*
Main Steam N.A.
78 MS015A*
Main Steam N.A.
l 78 MS016A*
Main Steam N.A.
78 MS017A*
Main Steam N.A.
85 MS013B*
Main Steam N.A.
85 MS014B*
Main Steam N.A.
85 MS015B*
Main Steam N.A.
85 MS0168*
Main Steam N.A.
85 MS017B*
Main Steam N.A.
86 MS013C*
Main Steam N.A.
86 MS014C*
Main Steam N.A.
i 86 MS015C*
Main Steam N.A.
86 MS016C*
Main Steam N.A.
86 MS017C*
Main Steam N.A.
77 MS0180*
Main Steam 20 78 MS018A*
Main Steam 20 85 MS0188*
Main Steam 20 86 MS018C*
Main Steam 20 l
- Not subject to Type C leakage tests.
- Proper valve operation will be demonstrated by verifying that the valve strokes to its required position.
- Not applicable to Unit 2.
Applicable to. Unit 1 after Cycle 7.
l
- May be opened on an intermittent basis under administrative control.
'HApplicable to Unit I through Cycle 7 and to Unit 2.
l l
BRAIDWOOD - UNITS 1 & 2 3/4 6-24 AMENDMENT NO. 84 & 83 l
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