ML20155K618
| ML20155K618 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/10/1988 |
| From: | Norrholm L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155K623 | List: |
| References | |
| NUDOCS 8806210304 | |
| Download: ML20155K618 (7) | |
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UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
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- j WASHINGTON, D. C. 20666
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated June 2, 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 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.
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 Comission'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 Comission's regulations anti all applicable requirements liave been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachmsnt to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 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 Amendment No. 9 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 was effective as of June 2, 1988.
FOR THE NUCLEAR REGULATORY COMMISSION Y
wt Le J. Norrho m, eting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: June 10,1988 l
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20655
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amen &ent No. 9 License No. NPF-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated June 2, 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.
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 (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 Comission'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 Comission'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 para-graph 2.C.(2) of Facility Operating License No. NPF-77 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 Amendment No. 9 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 amendment was effective as of June 2,1988.
FOR THE NUCLEAR REGULATORY COMMISSION et-Le
. Norrho m, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 10,1983
ATTACHMENT TO LICENSE AMENDMENT NOS. 9 AND,9_
ANDFACILITYOPERATINGLICENSENOS.NPF-72fNDNPF-77 DOCKET NOS.-STN-50-456 AND STN 50-457 Revise Appendix A as follows:
l Remove Pages Insert Pages 3/4 3-9 3/4 3-9 3/4 3-12a 3/4 3-12a
TABLE 4.3-1
,:=D REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o
TRIP 7
ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH E
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE
] FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
[
1.
Manual Reactor Trip N.A.
N.A.
N.A.
R N.A.
1, 2, 3*, 4*, 5*
2.
Power Range, Neutron Flux a.
High Setpoint S
D(2, 4),
Q N.A.
N.A.
1, 2 M(3, 4, 14) l Q(4, 6),
R(4, Sa)#
b.
Low Setpoint S
R(4)#
Q N.A.
N.A.
1###, 2
,s#
3.
Power Range, Neutron Flux, N.A.
R(4)#
Q N.A.
N.A.
1, 2 High Positive Rate 1
1 4.
Power Range, Neutron Flux, N.A.
R(4)#
Q N.A.
N.A.
1, 2 High Negative Rate 5.
Intermediate Range, S
R(4, Sa)#
Q N.A.
N.A.
1###, 2 Neutron Flux 6.
Source Range, Neutron Flux 5
R(4, 5b, 12)# Q(9)
N.A.
N.A.
2##, 3, 4, 5' 7.
Overtemperature AT S
R(13)#
Q N.A.
N.A.
1, 2 8.
Overpower AT S
R#
Q N.A.
N.A.
1, 2 E
9.
Pressurizer Pressure-Low 5
R#
Q**
N.A.
N.A.
1 3
(Above P-7) 5 10.
g Pressurizer Pressure-High S
R#
Q N.A.
N.A.
1, 2 11.
Pressurizer Water Level-High S
R#
Q N.A.
N.A.
1 a
(Above P-7)
L TABLE 4.3-1 (Continued)
TABLE NOTATIONS (12) At least once per 18 months during shutdown verify that on a simulated Boron Dilution Doubling test signal CVCS valves 1120 and E open and 1128 and C close within 30 seconds.
(13) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.
(14) On a one-time basis only, through June 15, 1988, the periodicity of this surveillance for Unit 1 only may be extended from 31 days (monthly) to 41 days.
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BRAIDWOOD - UNITS 1 & 2 3/4 3-12a l
Amendment No. 9