ML20065L654
| ML20065L654 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/18/1994 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20065L658 | List: |
| References | |
| NPF-37-A-061, NPF-66-A-061, NPF-72-A-049, NPF-77-A-049 NUDOCS 9404210210 | |
| Download: ML20065L654 (16) | |
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6 f UNITED STATES NUCLEAR REGULATORY COMMISSION S.....,/
gs, WA$HINGTON, D.C. 20555 4 301 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454_
BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE, Amendment No. 61 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Compan licensee) dated March 21, 1994, as supplemented on March Act of 1954, as amended (the Act) and the Com 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 author 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,ssuance 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 amended to read as follows: paragraph 2.C.(2) of Facility Operating Licen 4
9404210210 940418 PDR ADOCK 05000454 p
. 4 (2)
Technical Specifications s
The Technical Specifications contained in Appendix A.as revised through Amendment No. 61 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 j[,
~~.117 ames E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18, 1994 1
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WASHINC: TON, D.C. 20$5 MOO 1 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATIl0G LICENSE Amendment No. 61 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Compa licensee) dated March 21, 1994, as supplemented on March 24 Act of 1954, as amended (the Act) and the Com 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 auth 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 w,ith the Comission's regulations; l
D.
The issuance of this amendment will not be inimical to th defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CF 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 Speci i
cations as indicated in the attachment to this license amendment, and amended to read as follows: paragraph 2.C.(2) of Facility Operating Lic i
. ~...
. (2) le m ical Specifications The Technical Specifications contained in Appendix A (NUREG-lll3),
as revised through Amendment No. 61.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.
FOR THE NUCLEAR REGULATORY COMMISSION
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James E. Dyer,. Director Project Directorate III Division of Reactor. Projects - III/IV Office of. Nuclear Reactor. Regulation-
Attachment:
Changes.to the Technical Specifications Date of Issuance: April 18, 1994 J
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3 ATTACHMENT TO LICENSE AMENDMENT NOS. 61 AND 61 FACILITY OPERATING LICENSE N05. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 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 Paoes 1prort Paoes 3/4 7-3 3/4 7-3 e
TABLE 3.7-2 STEAM tlNE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING (11%)*#
ORIFICE SIZE MS013(A-D) 1235 psig 16 in' HS014(A-D) 1220 psig 16 in z MS015(A-D) 1205 psig 16 inz MS016(A-D) 1190 psig 16 in z MS017(A-D) 1175 psig 16 in2
- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
- Main Steam line Code safety valve lift settings may have a f3% tolerance until May 9,1994, by which time the lift settings will be reset to il%.
BYRON - UNITS 1 & 2 3/4 7-3 AMENDMENT NO. 61
PL_ ANT SYSTEMS A_UXILIARY FEEDWATER SYSTEM
_ LIMITING CONDITION FOR OPERATION 3.7.1.2 At least two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
One motor-driven auxiliary feedwater pump capable of being a.
powered from an ESF Bus, and b.
One direct-driven' diesel auxiliary feedwater pump capable of being powered from a direct-drive diesel engine and an OPERABLE Diesel Fuel Supply System consisting of a day tank containing a minimum of 420 gallons of fuel.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION.
With one auxiliary feedwater pump inoperable, restore the required a.
auxiliary feedwater pumps to.0PERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With both auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by:
a.
1)
Verifying that the pump develops a differential pressure of greater than or equal to 1825 psid at a flow of greater than or equal to 85 gpm on the recirculation flow when tested pursuant to Specification 4.0.5; 3
e BYRON - UNITS 1 & 2 3/4 7-4 AMENDMENT NO. 4
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s-WASHINGTON. D.C. 20555-0001 COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amen 6nent by Commonwealth Edison Company (the licensee) dated March 21,1994, as supplemented on March 24, 1994, 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:
i 1
. (2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 49 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
the facility in accordance with the Technical Specifications andT the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance FOR THE NUCLEAR REGULATORY COMMISSION
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- 06c-Jsmes E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18, 1994
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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- .... j" WASHINGTON, D.C. 20555 0001 COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found A.
The application for amendment by Commonwealth Edison licensee dated March 21, 1994, as supplemented on March 2 complies)with the standards and requireme Act of 1954, as amended (the Act) and the Commission's rules regulations set forth in 10 CFR Chapter 1; B.
provisions of the Act, and the rules and regul Comission; C.
There is reasonable assurance (i) that the activities by this amendment can be conducted without endangering the i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; J
D.
defense and security or to the health and s
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and E.
Part 51 of the Commission's regulations and a requirements have been satisfied.
2.
cations as indicated in the attachment to this li paragraph 2.C.(2) of facility Operating License No. NPF-77 is hereb amended to read as follows:
, (2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 49 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 Plan.
3.
This license amendment is effective as of the date if its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance:
April 18,1994 9
ATTACHMENT TO LICENSE AMENDMENT NOS. 49 AND 49 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 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 Paoes Insert Paaes 3/4 7-1 3/4 7-1 3/4 7-3 3/4 7-3 y
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBLNE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With four reactor coolant loops and associated steam generators in a.
operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable.
SUR_VEILLANCE RE0VIREMENTS t
4.7.1.1 No additional requirements other than those required by Specification 4.0.5.
Unit 1, Cycle 5, until the initial entry into MODE 2.The provisions o
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O BRAIDWOOD - UNITS 1 & 2 3/4 7-1 AMENDMENT N0. 49
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_ TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRO INOPERABLE STEAM LINE SAFETY VALVES D MAXIMUM NUMBER OF INOPERABLE SAFETY VALVES ON ANY MAXIMUM ALLOWABLE POWER RANGE
__0PERATING STEAM GENERATOR HEUTRON FLUX HIGH SETPOINT (PERCENTOFRATEDTHERMALPOWER I
87 65 3
43 BRAIDWOOD - UNITS 1 & 2 3/4 7-2
TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP _
VALVE NUMBER LIFT SETTING (fl%)**
ORIFICE SIZE MS013(A-D) 1235 psig 16 in' MS014(A-D) 1220 psig 16 in' MS015(A-D) 1205 psig z
16 in HS016(A-D) 1190 psig 2
16 in MS017(A-D) 1175 psig z
16 in
- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
- Main steam line Code safety valve lift settings may have a 13% tolerance until May 9,1994, by which time the lift settings will'be reset to 11%.
BRAIDWOOD - UNITS 1 & 2 3/4 7-3 AMENDMENT NO. 49
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 pumps and associated flow paths shall be OPERAB water One motor-driven auxiliar a.
powered from an ESF Bus, y feedwater pump capable of being and b.
One direct-driven diesel auxiliary feedwater pump capabl Supply System consisting of a day tank conta e of being esel Fuel 420 gallons of fuel.
um of
_ APPLICABILITY: MODES 1, 2. and 3.
ACTION:
With one auxiliary feedwater pump inoperable a.
at least HOT STANDBY within the next 6
, restore the required e in within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With both auxiliary feedwater pumps inoperable STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
owing SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPE At least once per 31 days on a STAGGERED TEST BASIS by a.
1)
Verifying that the pump develops a differential pressure of equal to 8S gpm on the recirculation flow w to Specification 4.0.5; BRAIDWOOD - UNITS 1 & 2 3/4 7-4