ML20237A759
| ML20237A759 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 12/08/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20237A762 | List: |
| References | |
| NPF-37-A-013, NPF-66-A-013, NPF-72-A-003 NUDOCS 8712150233 | |
| Download: ML20237A759 (19) | |
Text
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o UNITED STATES
),
g NUCLEAR REGULATORY COMMISSION j
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,d COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.13 i
License No. NPF-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
{
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 30, 1987, supplemented October 30, 1987, 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 (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 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 f
of the Comission's regulations and all applicable requirements have i
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 paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.13 and the Environment 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 kY Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: December 8, 1987 4
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NUCLEAR REGULATORY COMMISSION
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i COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 13 License No. NPF-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (thelicensee)datedSeptember 30, 1987, supplemented October 30, 1987, complies with the standards and requirements of the Atomic Energy 4
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 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 1
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 of the Comission'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:
t 4 1 (2) Technical Specifications The Technical Specifications contained in Appendix (NUREG-1113), as revised through Amendment No.13 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 Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSI N Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: December 8, 1987 1
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ATTACHMENT TO LICENSE AMENDMENT NOS.13 AND 13 FACILITY OPERATING LICENSE N05. NPF-37 AND NPF-66 DOCKET NOS. STN-50-454 AND STN 50-455 Revise Appendix A as follows:
Remove Pages Insert Pages j
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TABLE NOTATIONS 1
- With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.
- These channels also provide inputs to ESFAS.
The Operational Test Frequency.
for these channels in Table 4.3-2 is more conservative and, therefore, controlling.
- A Reactor trip on Turbine trip is enabled above P-7 (10%) until the modifica-tion is implemented which enables Reactor trip on Turbine trip above P-8 (30%).
- The specified 18 month interval may be extended to 32 months for Cycle 1 only.
- Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Pcwer Range Neutron Flux Interlock) Setpoint.
(1) If not performed in previous 7 days.
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.
Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.
The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1.
(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.
Recalibrates if the absolute difference is greater than or equal to 3%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(Sa) Initial plateau curves shall be measured for each detector.
Subsequent plateau curves shall be obtained, evaluated and compared to the initial For the Intermediate Range and Power Range Neutron Flux channels curves.
the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(5b) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector.
Subsequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.
(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
The provi-sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
j (7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
i (8) With power greater than or equal to the interlock Setpoint the required i
ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator window.
(9) Surveillance in MODES 3*, 4*, and 5* shall also include verification that 1
permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
Surveil-lance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.
BYRON - UNITS 1 & 2 3/4 3-12 AMENDMENT NO. 13
LIMITING SAFETY SYSTEM SETTINGS BASES Turbine Trip #
,l A Turbine trip initiates a Reactor trip.
On decreasing power the Turbine trip is automatically blocked by P-7 or P-8 (a power level of approximately 10%
(P-7) or 30% (P-8) of RATED THERMAL POWER with a turbine impulse chamber pres-sure at approximately 10% (P-7) or 30% (P-8) of full power equivalent); and on increasing power, reinstated automatically by P-7 or P-8.
1 Safety Injection Input from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which initiates a Safety Injection.
The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.
Reactor Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position trips are anticipatory trips which provide core protection against DNB.
The Open/Close Position trips assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached.
No credit was taken in the accident analyses for operation of-these trips.
Their functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Trip System.
Above P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10% of full power equivalent) an automatic Reactor trip will occur if more than one reactor coolant pump breaker is opened.
Below P-7 the trip function is automatically blocked.
- A Reactor trip on Turbine trip is enabled above P-7 (10%) until the modifi-cation is implemented which enables Reactor trip on Turbine trip above P-8 (30%).
BYRON - UNITS 1 & 2 B 2-8 Amendment No.13
LIMITING SAFETY SYSTEM SETTINGS BASES Reactor Trip System Interlocks The Reactor Trip System Interlocks perform the following functions:
P-6 On increasing power, P-6 allows the manual block of the Source Range Reactor trip (i.e., prevents premature block of Source Range trip),
provides an automatic backup block for Source Range Neutron Flux doubling, and the manual block that de-energizes the high voltage to the Source Range detectors.
On decreasing power, Source Range Level trips and Neutron Flux doubling circuits are automatically reacti-vated and high voltage restored.
P-7# On increasing power, P-7 automatically enables Reactor trips on low l
flow in more than one reactor coolant loop, more than one reactor coolant pump breaker open, reactor coolant pump bus undervoltage and underfrequency, Turbine trip, pressurizer low pressure and pressurizer high level.
On decreasing power, the above listed trips are auto-matically blocked.
P-8# On increasing power, P-8 automatically enables Reactor trips on low flow in one or more reactor coolant loops and Turbine trip.
On de-creasing power, the P-8 automatically blocks the single loop low flow trip and Turbine trip.
P-10 On increasing power, P-10 allows the manual block of the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip; and automatically blocks the Source Range Reactor trip and provides an automatic backup function to de-energize the Source Range high voltage power.
On decreasing power, the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip are automatically reactivated and Source Range high voltage to the detectors is restored if power decreases below the P-6 setpoint.
Provides input to P-7.
P-13 Provides input to P-7.
i
- A Reactor trip on Turbine trip is enabled above P-7 (10%) until.the modifi-cation is implemented which enables Reactor trip on Turbine trip above P-8 (30%).
BYRON - UNITS 1 & 2 B 2-9 Amendment No.13
COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
~
Amendment No.3 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 September 30, 1987, supplemented October 30, 1987, 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 Specifica-tion as indicated in the attachment to this license amenonent, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
i I
. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 3 and the Environment Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility ir, accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, l
FOR THE NUCLEAR REGULATORY COMM SSION J / ???
Daniel R. Muller, Director
{
Project Directorate III-2
]
Division of Reactor Projects - III, i
IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: December 8, 1987 i
l
ATTACHMENT TO LICENSE AMENDMENT l10. 3 FACILITY OPERATING LICENSE N0. NPF-72 DOCKET N0. STN-50-456 Revise Appendix A es follows:
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O LIMITING SAFETY SYSTEM SETTINGS BASES Turbine Trip #
A Turbine trip initiates a Reactor trip.
On decreasing power the Turbine trip is automatically blocked by P-7 or P-8 (a power level of approximately 10% (P-7) or 30% (P-8) of RATED THERMAL POWER with a turbine impulse chamber pressure at approximately 10% (P-7) or 30% (P-8) of full power equivalent);
and on increasing power, reinstated automatically by P-7 or P-8.
Safety Injection Input from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which initiates a Safety Injection.
The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.
Reactor Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position trips are anticipatory trips which provide core protection against DNB.
The Open/Close Position trips assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached.
No credit was taken in the accident analyses for operation of these trips.
Their functional capabiiity at the open/close position settings is required to enhance the overall reliability of the Reactor Trip System.
Above
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P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10% of full power equivalent) an automatic Reactor trip will occur if more than one reactor coolant pump breaker is opened.
Below P-7 the trip function is automatically blocked.
- A Reactor trip on Turbine trip is enabled above P-7 (10)% until the modification is implemented which enables Reactor trip on Turbine trip above P-8 (30%).
BRAIDWOOD - UNITS 1 & 2 B 2-8 AMENDMENT N0. 3
O LIMITING SAFETY SYSTEM SETTINGS BASES i
Reactor Trip System Interlocks The Reactor Trip System Interlocks perform the following functions:
P-6 On increasing power, P-6 allows the manual block of the Source Range Reactor trip (i.e., prevents premature block of Source Range trip),
provides an automatic backup block for Source Range Neutron Flux doubling, and the manual block that de energizes the high voltage to the Source Range detectors.
On decreasing power, Source Range Level trips and Neutron Flux doubling circuits are automatically reactivated and high voltage restored.
1 P-7 On increasing power, P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, more than one reactor coolant pump breaker open, reactor coolant pump bus undervoltage and i
underfrequency, Turbine trip, pressurizer low pressure and pressurizer high level.
On decreasing power, the above listed trips are automatically blocked.
P-8 On increasing power, P-8 automatically enables Reactor trips on low flow in one or more reactor coolant loops and Turbine trip.
On de-creasing ~ power, the P-8 automatically blocks the single loop low flow trip and Turbine trip.
P-10 On increasing power, P-10 allows the manual block of the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip; I
and automatically blocks the Source Range Reactor trip and provides an j
automatic backup function to de energize the Source Range high voltage i
power.
On decreasing power, the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip are automatically reactivated and Source Range high voltage to the detectors is restored if power decreases below the P-6 setpoint.
Provides input to P-7.
P-13 Provides input to P-7.
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- A Reactor trip on Turbine trip is enabled above P-7 (10%) until the modifica-tion is implemented which enables Reactor trip on Turbine trip above P-8 (30%).
4 BRAIDWOOD - UNITS 1 & 2 B 2-9 AMENDMENT NO. 3
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