ML20199A905
| ML20199A905 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/06/1986 |
| From: | Noonan V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199A909 | List: |
| References | |
| NUDOCS 8606160250 | |
| Download: ML20199A905 (8) | |
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UNITED STATES f t..
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WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION, UNIT 1 AMEN 0 MENT TO FACII.ITY OPERATING l.ICENSE
. Amendment No. 3 License No. NPF-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated March 11, 1986, as supplemented by letter dated April 11, 1986, 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 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.
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8606160250 860606-PDR ADOCK 05000454 P
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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 1.icense No.
NPF-37 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 3, and the Environmental Protection Plan contained in /ppendix 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 Tl4E NUCl. EAR REGUI.ATORY COMMISSION
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Project Directorate #5 Director o PWR I.icensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: g 0 61986 l
ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. NPF-37 DOCKET NO. STN 50-454 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicatir.g the area of change.
Overleaf pages (*) have been provided to maintain document completeness.
REMOVE INSERT IX IX X*
3/4 5-5 3/4 5-5 3/4 5-6*
3/4 5-6a e
1
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 A C C U M U LATO R S.............................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg >-350 F........:..................
3/4 5-3 FIGURE 4.5-1 RESIDUAL HEAT REMOVAL PUMP MINIMUM ACCEPTABLE PERFORMANCE CURVE...................................
3/4 5-6a 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350 F...........................
3/4 5-7 3/4.5.4 REFUELING WATER STORAGE TANK.............................
3/4 5-9 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................
3/4 6-1 Containment Leakage......................................
3/4 6-2 Containment Air Locks....................................
3/4 6-4 Internal Pressure........................................
3/4 6-6 Air Temperature..........................................
3/4 6-7 Containment Vessel Structural. Integrity..................
3/4 6-8 Containment Purge Ventilation System.....................
3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.................................
3/4 6-13 Spray Additive System....................................
3/4 6-14 Containment Cooling System...............................
3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................
3/4 6-16 TABLE 3.6-1 CONTAINMENT ISOLATION VALVES..........................
3/4 6-18 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................
3/4 6-25 Electric Hydrogen Recombiners............................
3/4 6-26 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.......................................
3/4 7-1 BYRON - UNIT 1 IX AMENDMENT NO. 3
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE-p TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP 0PERATION...........................................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 Auxiliary Feedwater System...............................
3/4 7-4 Condensate, Storage Tank..................................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.........................
3/4 7-8 Main Steam Line Isolation Va1ves.........................
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...........................
3/4 7-12 3/4.7.5 U LT I MAT E H E AT S I N K.......................................
3/4 7-13 s_,)
3/4.7.6 CONTROL ROOM VENTILATION SYSTEM..........................
3/4 7-16 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM.......................................
3/4 7-19 3/4.7.8 SNUBBERS.................................................
3/4 7-22 FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST...........
3/4 7-27 3/4.7.9 SEALED SOURCE CONTAMINATION..............................
3/4 7-28 ll BYRON - UNITS 1 & 2 X
EMERGENCY C0,RE COOLING SYSTEMS
- SURVEILLANCE REQUIREMENTS (Continued) 1)
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2)
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1)
Verifying automatic isolation and interlock action of the RHR System from the Reactor Coolant System by ensuring that; a)
With a simulated or actual Reactor Coolant System pressure
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signal greater than or equal to 360 psig the interlocks prevent the valves from being opened, and b)
With a simulated or actual Reactor Coolant System pressure signal greater than or equal to 662 psig the interlocks will cause the valves to automatically close.
2)
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
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At least once per 18 months, during shutdown, by:
e.
1)
Verifying that each automatic valve in the flow path actuates l
to its correct position on a Safety Injection test signal and on a RWST Level-Low-Low test signal, and 2)
Verifying that each of the following pumps s' tart automatically upon receipt of a Safety Injection actuation test signal:
a)
Centrifugal charging pump, b)
Safety Injection pump, and c)
RHR pump.
f.
By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1)
Centrifugal charging pump 1 2396 psid, 2)
Safety Injection pump 3 1412 psid, and 3)
RHR pump In accordance with Figure 4.5-1 BYRON - UNITS 1 & 2 3/4 5-5 AMENDMENT N0. 3
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS-(Continued) g.
By verifying the correct position of each mechanical position stop for the following ECCS throttle valves:
1)
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)
At least once per 18 months.
High Head SI System SI System Valve Number Valve Number SI8810 A,B,C,D SI8822 A,B,C,0
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SI8816 A,B,C,0 h.
By performing a flow balance test, during shutdown, following com-pletion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
1)
For centrifugal charging pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the
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highest flow rate, is greater.than or equal to 330 gpm, and b)
The total pump flow rate is less than or equal to 550 gpm, including a simulated seal injection flow of 80 gpm.
2)
For Safety Injection pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 439 gpm, and b)
The total pump flow rate is less than or equal to 655 gpm.
3)
For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than on equal to 3804 gpm.
BYRON - UNITS 1 & 2 3/4 5-6
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1000 2050 30$0 4dOO 5000 RHR PUMP FLOW (GPM)
FIGURE 4.5-1 RESIDUAL HEAT REMOVAL PUMP MINIMUM ACCEPTABLE PERFORMANCE CURVE BYRON - UNITS 1 & 2 3/4 5-6a AMENDMENT NO. 3