ML20154F503
| ML20154F503 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 10/06/1998 |
| From: | John Hickman Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20154F506 | List: |
| References | |
| NPF-37-A-104, NPF-66-A-104, NPF-72-A-096, NPF-77-A-096 NUDOCS 9810090248 | |
| Download: ML20154F503 (16) | |
Text
. -...
- -..-.~.
...~.._ -....-.. --..
pnerg y
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o,
WASHINGTON, D.C. 20066-0001 I
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 Licensa No. NPF-37 1.
Tha Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 30,1997, 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) i that such activities will be conducted in compliance with the Commission's regulations; j
D.
The issuance of this amendment will not be inimical to the common defense end I
security or to the health and safety of the public; and 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and tr.pplicable requirements have been satisfied.
2.
Accordingly, 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. NPF-37 is hereby amended to read as follows:
1 9810090248 981006 l
4 s-
,,2 m
rg
.,-w,-
a-
,eg, m
. t (2) Technical Specificatjigng The Technical Specifications contained in Appendix A as revised through Amendment No.104 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The 1.censee 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 i
John B. Hickman, Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 6, 1998
.. ~.
e t
UNITED STATES g
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566-0001 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILl7 OPERATING LICENSE Amendment No.104 License No. NPF-66 1.
The Nuclear Reguiatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 30,1997, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the nJtes 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 Cornmission's regulations; D.
The issuance of this amendment will n]t 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 Specifications 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:
t
. (2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.104 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 tweby 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 n 8. Hickman, Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
Octcber 6, 1998
=.
ATTACHMENT TO LICENSE AMENDMENT NOS.104 AND 104 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 i
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 marginallines indicating 'he area of change.
Remove Paaes Insert Paaes l
3/4 3-27 3/4 3-27 3/474 3/474 B 3/4 7-2 B 3/4 7-2 l
l
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP ALLOWABLE FUNCTIONAL UNIT SETPOINT VALUE
- 6. Auxiliary Feedwater (Continued) f.
Division 11 for Unit 1 (Division 21 for Unit 2)
ESF Bus Undervoltage-Start Motor-Driven Pump 2870 volts 2730 volts g.
Auxiliary Feedwater Pump Suction Pressure-Low (Transfer to i
Essential Service Water) 218.1 psia 217.4 psia
- 7. Automatic Opening of Containment Sump Suction isolation Valves a.
Automatic Actuation Logic and Actuation Relays N.A.
N.A.
b.
RWST Level-Low-Low Coincident with Safety injection See item 1. above for Safety injection Trip Setpoints and Allowable Values.
BYRON - UNITS 1 & 2 3/4 3-27 AMENDHENT NO.104; 104
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank (CST) shall be OFERABLE with a contained water level of at least 60%* (75%**).
l APPLICABILITY.: MODES 1,2, and 3.
ACTION:
With the CST inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
a.
Restore the CST to OPERABLE status 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 />, or b.
Demonstrate the OPERABILITY of the Essential Service Water System as a backup supply to the auxiliary feedwater purnps and restore the CST to OPERABLE status within 7 days 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 />.
SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The CST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water level is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The Essential Service Water Syatem shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by performing the surveillance specified in Specification 4.7.4a. whenever the Essential Service Water System is the supply source for the auxiliary feedwater pumps.
- App!icable to Unit 1 and to Unit 2 after Cycle 7.
- Not applicable to Unit 1. Applicable to Unit 2 through Cycle 7.
BYRON - UNITS 1 & 2 3/4 7-6 AMENDMENT NO.104,' 104
- ~ _-.-
.._-__-.-.~.~.~-.- -
3/4.7 PLANT SYSTEM 1 BASES l-3/4.7.1.1 SAFETY VALVES (Continued) h, Heat of vaporization for steam at the highest MSSV opening pressure
=
including tolerance and accumulation, as appropriate, in BTU /lbm.
N
=
Number of loops in the plant (=4).
The values calculated from this algorithm were adjusted lower for use in Technical Specification 3.7.1.1 to account for instrument and channel uncertainties (g% power).
3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a totalloss-of-offsite power.
The motor-driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 740 gpm at a pressure of 1450 psig to the entrance of the steam generators. The diesel-driven auxiliary feedwater pump is capable of delivering a toi.al feedwater flow of 740 gpm at a pre.sure of 1450 psig to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coo: ant Gystem temperature to less than 350*F when the RHR System rnay be placed into operation.
3/4.7.1.3 CONDENSATE STORAGE TANK The minimum water level required for OPERABILITY in the condensate storage tank (CST) provides 200,000 gallons of useable water to the suction of the auxiliary feedwater (AF) system. This amount ensures that su#icient water is available to: (1) maintain the reactor coolant system at HOT STANDBY conditions for g hours with steam discharge to the atmosphere concurrent with a total loss-of-offsite power, and (2) maintain a unit in HOT STANDBY for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following a reactor trip, followed by a cooldown to 350*F in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, at which time the residual heat removal system can be put into service.
Additionally, the minimum CST requirement provides's high probability that switchover to the essential service water (SX) supply will not occur as long as the CST water supply remains available. This design featura helps maintain the long term reliability anri availability of the steam generators by supplying higher quality condensate water to the steam generators except for circumstances where the safety-related SX water supp!y is required due to the unavailability of the CST. The minimum CST level includes an allowance for water that may not be usable because of tank discharge line location, dynamic head loss considerations, fluid vortexing in the tank, AF pump startup suction pressure considerations, and instrument uncertainties for the CST level and the AF suction switchover instruments.
3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a stcam line break. This dose also includes the effects of a coincident 1 gpm reactor to secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.
BYRON - UNITS 1 & 2 B 3/4 7-2 AMENDMENT NO.104,104
I
[ fun u
N1 UNITED STATES NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. 2066& 0001 os...../
l I
COMMONWEALTH EDISON COMPANY i
l DOCKET NO. STN 50-456 i
I BRAIDWOOD STATION. LINIT NO.1 AMENDMENT TO FACILITY OPE, ', TING LICENSE Amendment No. 96 i
License No. NPF-72
]
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The app;:.ation for amendment by Commonwealth Edison Company (the licensee) dated December 30,1997, complies with the standards and l
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 i
Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities auD 1rized by this amendment can be conducted without endangeiing the health and safety of the public. and (ii) that such activities will be conducted in compliance with the Commission's I
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 Specifications as indica *9d in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereoy amended to read as follows:
I
~. -
2-(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 96 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 ameencnt is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Stewart N. Bailey, Pro,i e anager Project Directorate l's-2 Division of Reactor Projects - til/IV i
Office of Nuclear Reactor Regulation l
Attachment-Changes to the Technical Specifications Date of issuance:
October 6, 1998 l
l i
l i
I l
i
7 pmuq p
1 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001 o
%.....,o I
1 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATIGil. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendmeni No. 96 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 December 30,1997, 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
^ setivif'es will be anducted in compliance with the Commission's regut
.es; D.
The issuance of this amendment will not be inimical to the common defense and sec :rity 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.
AccoMngly, the license is smended 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 NPF-77 is hereby amended to read as follows:
l l
. (2)
Technical SpeciCcations The Technical Specifications contained in Appendix A cs revised through Amendment No. 96 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 and shall be impternented within 30 days.
I FOR THE NUCLEAR REGULATORY COMMISSION
/
Stewart N. Bailey, P ject Ma er
^
Project Directorate I Civision of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changeslo_the_ Technical Specifications Date of issuance: October 6, 1998 1
=
\\
i 1
4 J
y
ATTACHMENT TO LICENSE AMENDMENT NOS. 96 AND 96 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 OOCKET 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 verticallines indicating the area of change, Remove Paaes Insert Paaes 3/4 3-27 3/4 3-27 3/4 7-6 3/4 7-6 8 3/4 7-2 B 3/4 7-2
1 i
l 1
4
)
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS i
TRIP ALLOWABLE FUNCTIONAL UNIT SETPOINT VALUE 1
l 6.
Auxiliary Feedwater(Continued) l f.
Division 11 for Unit 1 i
(Division 21 for Unit 2) 3 ESF Bus Undervoltage-Start Motor-Driven Pump 2870 volts 2730 volts i
g.
Auxiliary Feedwater Pump Suction Pressure-Low (Transfer to Essential Service Water) 218.1 psia 217.4 psia j
j 7.
Automatic Opening of i
Containment Sump Suchon Isolation Vaives i
a.
Automatic Actuation N.A.
N.A.
Logic and Actuation Relays I
h.
RWST Level-Low-Low 46.7 %
44.7 %
Coincident with Safety injection See item 1. above for Safety injectxm Trip Setpoints and Allowable Values.
i i
I BRAIDWOOD-UNITS 1 & 2 3/4 3-27 AMENDMENT NO. 96; 96
SAliT SYSTEMS QONDENSATE STORAGE TANK j
LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank (CST) shall be OPERABLE with a contained water level of at least 57%* (66%**) {80%*"}.
l APPLICABILITY: MODES 1,2, and 3.
ACTION-With the CST inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either, a.
Restore the CST to OPERABLE status 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 />, or b.
. Demonstrate the OPERABILITY of the Essential Service Water System as a backup supply to the auxiliary feedwater pumps and restore the CST to OPERABLE status within 7 days 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 />.
4 SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The CST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water level is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The Essential Service Water System shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by performing the surveillance specified in Specification 4.7.4a. whenever the Essential Service Water System is the supply source for the auxiliary feedwater pumps.
- Applicable to Unit 1 after Cycle 8 and to Unit 2 after Cycle 8.
" Applicable to Unit 1 after Cycle 7. Applicable to Unit 2.
- " Applicable to Unit 1 through Cycle 7. Not applicable to Unit 2.
BRAIDWOOD - UNITS 1 & 2 3!4 7-6 AMENDMENT NO. 96', 96
3/4.7 PLANT SYSTEMS BASES 3/4.7.1.1 SAFETY VALVES (Continued)
Heat of vaporization for steam at the highest MSSV opening pressure h,
=
including tolerance and accumulation, as appropriate, in BTU /lbm.
N
=
Number of loops in the plant (=4).
The values calculated from this algorithm were adjusted lower for use in Technical Specification 3.7.1.1 to account for instrument and channel uncertainties (9% power).
3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a totalloss-of-offsite power.
The motor-driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 740 gpm at a pressure of 1450 psig to the entrance of the steam generators. The diesel-driven auxiliary feedwater pump it capable of delivering a total feedwater flow of 740 gpm at a pressure of 1450 psig to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant Syeem temperature to less than 350*F when the RHR System may be placed into operatior.
3/4.7.
^ONDENSATE STORAGE TANK 1 he minimum water level required for OPERABILITY in the condensate storage tank (CST) provides 200,000 gallons of useable water to the suction of the auxiliary feedwater (AF) system. This amount ensures that sufficient wateris available to: (1) maintain the reactor coolant system at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with a total loss-of-offsite power, and (2) maintain a unit in HOT STANDBY for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following a reactor trip, followed by a cooldown to 350'F in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, at which time the residual heat removal system can be put into service.
Additionally, the minimum CST requirement provides a high probabi'ity that switchover to the essential service water (SX) supply will not occur as long as the CST water supply remains available. This design feature helps maintain the long term reliability and availability of the steam generators by supplying higher quality condensate water to the steam generators except for circumstances where the safety-related SX water supply is required due to the unavailability of the CST. The minimum CST levelincludes an allowance for water that may not be usable because of tank discharge line location, dynamic head loss considerations, fluid vortexing in the tank, AF pump startup suction pressure considerations, and instrument uncertainties for the CST level and the AF suction switchoverinstruments.
3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line break. This dose also includes the effects of a coincident 1 gpm reactor to secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.
BRAIDWOOD - UNITS 1 & 2 B 3/4 7-2 AMENDMENT NO.96; 96