ML20151D996
| ML20151D996 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/22/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20151E001 | List: |
| References | |
| NPF-37-A-015, NPF-66-A-015, NPF-72-A-006, NPF-75-A-006 NUDOCS 8804140543 | |
| Download: ML20151D996 (18) | |
Text
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@ Ltoy jo UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION 5
-l W ASHINGTO N, D. C, 205$5 o
COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.15 License No. NPF-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Conmonwealth Edison Company (the licensee) dated February 18, 1987, supple:nented November 17, 1987 i
and January 8,1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
- e facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission-i 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 r.neCJcted i
in compliance with the Comission's regulations; 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 amendment is in accordance with 10 CFR Part 51 i
of the Comission's regulations and all applicable rectirements have been satisfied.
2.
Accordingly, the license is amenced by changes to the Technical Specifica-tion 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:
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2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendmnt No.15 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.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications i
Date of Issuance: March 22, 1988
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UNITED STATES
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ij WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 t
BYRON STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 15 License No. NPF-66 j
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated February 18, 1987, supplemented November 17, 1987 and January 8, 1988, 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 It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonablesssurance(1)thattheactivitiesauthorizedby 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 Specifica-tions 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:
J
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(2) Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.15 and revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which are 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 Pictection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 22,1988 4
s J
ATTACHMENT TO LICENSE AMEN 0 MENT NOS.15 AND 15 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66
_ DOCKET N05. STN-50-454 AND STN 50-455 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-58 3/4 3-58 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 11-2 3/4 11-2 i
L I
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1
TABLE 3.3-12
.5g RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION h
MINIMUM CHANNELS g
INSTRUMENT OPERABLE ACTION
[
1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release m
a.
Liquid Radwaste Effluent Line (ORE-PR001) 1 31 b.
Fire and Oil Sump Discharge (ORE-PR005) 1 34 c.
Condensate Polisher Susp Discharge (ORE-PR041) 1 34 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.
Essential Service Water E
Station Blowdown Line (ORE-PRO 10) 1 32 3.
Flow Rate Measurement Devices E
a.
Liquid Radwaste Effluent Line (Loop-WX001) 1 33 5
b.
Station Blowdown Line (Loop-CWO32) 1 33
i t
i TABLE 3.3-12 (Continued)
ACTION STATEMENTS l
ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior l
to initiating a release:
a.
At least two independent samples are analyzed in accordance t
with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the facility i
staff independently verify the release rate calculations and 1
discharge line valving.
l Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 10 7 microcurie /ml.
ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this l
pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.
ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this i
pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table 4.11-1:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE i
EQUIVALENT I-131, or b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOS EQUIVALENT I-131.
d BYRON - UNITS 1 & 2 3/4 3-59 AMENDMENT NO. 15
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TABLE 4.3-8
- f, RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
DIGITAL ANALOG CHANNEL CHANNEL cz CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL g
INSTRUMENT CHECK CHECK CALIBRATION TEST TEST
[
1.
Radioactivity Monitors Providing Alarm and Autoatic Temination of Release I
a.
Liquid Radwaste Effluent Line (ORE-PR001) D P
R(3)#
Q(1)
N.A.
b.
Fire and Oil Sump Discharge (ORE-PR005)
D M
R(3)
Q(1)
N.A.
c.
Condensate Polisher Sump Discharge (ORE-PR041)
D M
R(3)
Q(1)
N.A.
2.
Radioactivity Monitors Providing Alam but Not Providing Automatic Temination 1
of Release w
a.
Essential Service Water m
- 1) Unit 1 a) RCFC 1A and 1C Outlet (IRE-PR002)
D M
R(3)
Q(2)
N.A.
b) RCFC IB and ID Outlet (1RE-PR003)
D M
R(3)
Q(2)
N.A.
- 2) Unit 2 R(3)#
Q(2)
N.A.
a) RCFC 2A and 2C Outlet (2RE-PR002)
D M
b) RCFC 28 and 2D Outlet (2RE-PR003)
D M
R(3),
Q(2)
N.A.
b.
Station Blowdown Line (ORE-PRO 10)
D M
R(3)#
Q(2)
N.A.
g E
3.
Flow Rate Measurement Devices M
E a.
Liquid Radwaste Effluent Line g
(Loop-WX001)
D(4)
N.A.
R N.A.
Q b.
Station 810wdown Line (Loop-CWO32)
D(4)
M.A.
R N.A.
Q g
l TABl.E 4.11-1 RADIOACTIVE LMulu WASTE SAMPLING _AND_ ANALYSIS PROGRAM
! LOWER LIMIT OF DETECTION HINIMUM LIQUID RELEASE SAMPLING
, ANALYSIS TYPE OF ACTIVITY (LLD)CI) s TYPE FREQUENCY
' FREQUENCY MiA' YSIS (pCi/al)
- 1. Batch P
P 7
Release Each Batch Each Ratch Principal Gama 5x10 Tanks (2)
Emitters (3)
-6 I-121 1x10 P
M Dissolved and 1x10 One Batch /M Entrained Gases (Gama Emittera)
-5 P
M H-3 1410 Each Batch Composite (4)
~~~
q 1
Gross Alpha 1x10
-8 P
Q Sr-39, Sr-90 5x10 Each Batch Composite (4) l
-6 Fe-55 1x10 1
- 2. Continuous W
Princiv>al Gamma 5x10'7
[
g,j,,,,,(5)
Continuous (6) Composite (G)
Cmitters(3)
{
b131 1x10 1
- a. Circulating
~
Water
-5 1
Blowdown M
M Oissolved and 1x10 Grab Sampin Entrained Gases (Gama Emitters)
- b. Waste Water Treatment
-5 System M
H-3 1x10 Discharge Continuous (6) Compositel0) to Flume Gross Alpha 1x10-7 j
.< l
- c. Condensate Continuous (6) Comp site (N Polisher
-6 Sump Fe-55 1x10 Discharge BYRON - UNITS 1 & 2 3/4 11-2 AMENDMENT NO.15
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NUCl. EAR REGULATORY COMMISSION p
WASHING 10N, D. C. 206M g
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,C_C@NWEALTHEDIS0h_ COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. NPF-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated February 18, 1987, supplemented November 17, 1987 i
arid January 8.1988, corr. plies with the standards and requirements of i
theAtomicEnergyActof1954,asacanded(theAct)andthe i
Commission's rules and regulations het 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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this arrendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted i
in corrpliance with the Comission's regulations; 3
D.
The issuance of this arnendment will not be inimical to the common i
defense and sec'Irity or to the health and safety of the publict and E.
The issuance of this amendment is ir accardance with 10 CFR Part 51 of the Comission's regulations and all applic.able requirements have been satisfied.
1 1
2.
Accordingly, the license is amended by chcnges to the Technical Specifica-j tion as indicated in the attachment to this license amendment, and paragroph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
4 1
1 4
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2 r
(2) Technical Specifications The Technical Specifications contained in Appendix A as revisad i
through Amendnent No. 6 and the Environmental Protection Plan contained in Appendix B, both of which ars attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmentel Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION A 4.hA ror Dante' R. Muller, Director Project Directorate III-2 Livision of Reactor Projects - !!!,
!Y, Y and Special Projects
Attachment:
Changes to the Technical Soecifications Date of Issuance:
March 22, 1988 i
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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,f WASHING TON, D, C. 206H g,.... j COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE _
Amendment No. 6 License No. NPF-75 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amndment by Comonwealth Edison Company (the licensee) dated February 18, 1987, supplemented November 17, 1987 and January 8,1988, complies with the standards and requirements of l
theAtomicEnergyActof1954,asamended(theAct)andthe l
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 Comission; j
C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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; 1
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 Specifica-tion as indicated in the attachment to this license amendment, and psra-graph 2.C.(2) of Facility Operating License No. NPF-75 is hereby amended to read as follows:
4 l
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2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 6 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. Attachment 2 contains revisions to Appendix A which 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 anandment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-[4 Awl.
A for Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Spe:ial Projects Attachnent:
Changes to the Technical Specifications Date of Issuance: March 22, 1988
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ATTACHMENT TO LICENSE AMEN 0 MENT NOS. 6 AND 6 AND FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-75 DOCKET NOS. STN-50-456 AND STN 50-457 9evise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 11-2 3/4 11-2 i
1 i
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4 l
i 4
e
TABLE 3.3-12
.5g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 68 MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION c.5 31 1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release g
[
a.
Liquid Radwaste Effluent Line (ORE-PR001) 1 31 b.
Fire and Oil Sump (ORE-PR005) 1 34 c.
Condensate Polisher Sump Discharge (ORE-PR041) 1 34 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release mk a.
Essential Service Water
Station Blowdown Line (ORE-PR010) 1 32
[
3.
Flow Rate Measurement Devices O
h a.
Liquid Radwaste Effluent Line (Loop-WX001) 1 33 b.
Station Blowdown Line (Loop-CWO32) 1 33
TABLE 3.3-12 (Continued)
ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 10 7 microcurie /ml.
ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.
ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table 4.11-1:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of j
the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
BRAIDWOOD - UNITS 1 & 2 3/4 3-61 Amendment No. 6 1
4 TABLE 4.3-8
.5g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 6g DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL cz INSTRUMENT CHECK CHECK CALIBRATION TEST TEST
.-e
[
1.
Radioactivity Monitors Provid'.ng Alarm and Automatic Termination of Release a.
Liquid Radwaste Effluent Line (ORE-PR001) D P
R(3)#
Q(1)
N.A.
b.
Fire and Oil Sump Discharge (ORE-PR005)
D M
R(3)
Q(1)
N.A.
c.
Condensate Polisher Sump Discharge (ORE-PR041)
D M
R(3)
Q(1)
N.A.
{
2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination 4
of Release N
a.
Essential Service Water
D M
R(3)#
Q(2)
N.A.
b) RCFC IB and ID Outlet (1RE-PR003)
D M
R(3)#
Q(2)
N.A.
D M
R(3)#
Q(2)
N.A.
D M
R(3)#
Q(2)
N.A.
g-b.
Station Blowdown Line (ORE-PR010)
D M
R(3)#
Q(2)
N.A.
5 3.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line (Loop-WX001)
D(4)
N.A.
R#
N.A.
Q m
b.
Station Blowdown Line (Loop-CWO32)
D(4)
N.A.
R N.A.
Q
TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT 0F DETECTION MINIMUM LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)(1)
TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)
- 1. Batch P
P
_7 Pelease Each Batch Each Batch Principal Gamma 5x10 Tanks (2)
Emitters (3)
-6 I-131 1x10
-5 P
M Dissolved and 1x10 One Batch /M Entrained Gases (Gamma Emitters)
-5 P
M H-3 1x10 Each Batch Composite (4) g P
Q Sr-89, Sr-90 5x10 Each Batch Composite (4)
-6 Fe-55 1x10
-7
- 2. Continuous Principal Gamma 5x10 Releases (5)
Continuous (6) Composite (6)
Emitters (3)
-6
- a. Circulating I-131 1x10 Water
-5 Blowdown M
M Dissolved and 1x10 j
Grab Sample Entrained Gases
- b. Waste Water (Gamma Emitters)
Treatment
-5 Discharge to M
H-3 1x10 Circulating Continuous (6) Composite (6)
Water Discharge Gross Alpha 1x10-7
- c. Condensate Polisher Sump
-8 Discharge 0
Sr-89, Sr-90 5x10 Continuous (6) Composite (6) l
-6 Fe-55 1x10
~
j BRAIDWOOD - UNITS 1 & 2 3/4 11-2 Amendment No. 6
_