ML062550046
| ML062550046 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/08/2006 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML062340434 | List: |
| References | |
| TAC MC6221, TAC MC6222, TAC MC6223, TAC MC6224 | |
| Download: ML062550046 (22) | |
Text
(4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulation set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 147And 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)
Deleted.
(4)
Deleted.
(5)
Deleted.
(6)
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report, and as approved in the SER dated February 1987 through Supplement No. 8, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 14 7 (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulation set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1 113), as revised through Amendment No.147, 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. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
(4)
Deleted.
(5)
Deleted.
Amendment No. 14 7
Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 T-AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE (ESF)
RESPONSE
TIME DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.
The dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or those listed in Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977, or ICRP 30, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or Federal Guidance Report 11 "Limiting Valves of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion", 1988; (Table 2.1, Exposure-To-Dose Conversion Factors for Inhalation).
Wshall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies (in MeV) per disintegration for non-iodine isotopes, with half lives > 10 minutes, making up at least 95% of the total non-iodine activity in the coolant.
The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
imes shall include diesel generator starting and sequence loading delays, where applicable.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
II BYRON - UNITS 1 & 2 1.1 - 3 Amendment 147
Definitions 1.1 1.1 Definitions PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
QUADRANT POWER TILT RATIO (QPTR)
RATED THERMAL POWER (RTP)
REACTOR TRIP SYSTEM (RTS)
RESPONSE
TIME RECENTLY IRRADIATED FUEL The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits including heatup and cooldown rates, and the pressurizer Power Operated Relief Valve (PORV) lift settings for the current reactor vessel fluence period.
These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6.
Unit operation within these limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," and LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)
System."
QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3586.6 MWt.
The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
Fuel that has occupied part of a critical reactor core within the previous 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Note that all fuel that has been in a critical reactor core is referred to as irradiated fuel.
BYRON - UNITS 1 & 2 1.1 -6 Amendment 147
VC Filtration System Actuation Instrumentation 3.3.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Suspend movement of Inmnediately associated Completion irradiated fuel Time of Condition A assemblies.
or B not met during movement of irradiated fuel assemblies.
E. Required Action and E.1 Initiate action to Immediately associated Completion restore one VC Time of Condition A Filtration System or B not met in MODE 5 train to OPERABLE or 6.
status.
I SURVEILLANCE REQUIREMENTS
NOTE -
Refer to Table 3.3.7-1 to determine which SRs apply for each VC Filtration System Actuation Function.
SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.7.2 Perform COT.
92 days SR 3.3.7.3 Perform CHANNEL CALIBRATION.
18 months BYRON - UNITS 1 & 2 3.3.7 - 2 Amendment 147
VC Filtration Systen' Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)
VC Filtration System Actuation Instrumentation APPLICABLE MOOES OR OTHER SURVEILLANCE TRIP SETPOINT FUNCTION SPECIFIED REQIRED CHANNELS RECUIREMENTS CONDITIONS
- 1.
Control Room 1,2,3,4,5,6,(a) 2 per train SR 3.3.7.1
- 2 mn/hr Radiation-Gaseous SR 3.3.7.2 SR 3.3.7.3 *
- 2.
Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.
(a)
During movement of irradiated fuel assemblies.
BYRON -
UNITS 1 & 2 3.3.7 -
3 Amendment 147
FHB Ventilation System ActuationInstrumentation 3.3.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Place in emergency Inmediately associated Completion mode one FHB Time not met.
Ventilation System train capable of OR being powered by an OPERABLE emergency Two channels power source.
OR B.2.1 Suspend movement of Immediately RECENTLY IRRADIATED FUEL assemblies in the fuel handling building.
AND B.2.2 ---------NOTE --------
Only required with equipment hatch not intact.
Suspend movement of Irmediately RECENTLY IRRADIATED FUEL assemblies in the containment.
I I
BYRON -
UNITS 1 & 2 3.3.8-2 Amendment 147
FHB Ventilation System Actuation Instrumentation 3.3.8 Table 3.3.8-1 (page I of 1)
FHB Ventilation System Actuation Instrumentation APPLICABLE FUNCTION MODES OR OTHER SURVEILLANCE TRIP SETPOINT SPECIFIED REQUIRED CiINELS REQUIREMENTS CCNDITIONS
- 1. Fuel Handling Building (a),(b) 2 SR 3.3.8.1
- 5 mRWhr Radiation SR 3.3.8.2 SR 3.3.8.3
- 2.
Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.
(a)
During movement of RECENTLY IRRADIATED FUEL assemblies in the fuel handling building.
(b)
During movement of RECENTLY IRRADIATED FUEL assemblies In the containment with the equipment hatch not intact.
I II BYRON - UNITS 1 & 2 3.3.8-4 Anlendment 147
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1.1 Place OPERABLE VC Immnediately associated Completion Filtration System Time of Condition A train in emergency not met in MODE 5 mode.
or 6, or during movement of irradiated AND fuel assemblies.
C.1.2 Verify OPERABLE VC Immnediately Filtration System train is capable of being powered by an OPERABLE emergency power source.
OR C'2.1 Suspend movement of Imtnediately irradiated fuel assemblies.
AND C.2.2 Suspend positive Immnediately reactivity additions.
(continued)
I BYRON - UNITS 1 & 2 3.7.10 - 2 Amendment 147
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Two VC Filtration D.1 Suspend movement of Irmmediately System trains irradiated fuel inoperable in MODE 5 assemblies.
or 6, or during movement of irradiated AND fuel assemblies.
D.2 Suspend positive Immediately reactivity additions.
E. Two VC Filtration E.1 Enter LCO 3.0.3.
Immediately System trains inoperable in MODE 1, 2, 3, or 4.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each VC Filtration System train 31 days with:
- a.
Flow through the makeup system filters for >_ 10 continuous hours with the heaters operating; and
- b.
Flow through the recirculation charcoal adsorber for > 15 minutes.
(continued)
I BYRON - UNITS 1 & 2 3.7.10 - 3 Amendment. 147
VC Temperature Control System 3.7.11 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1.1 Place OPERABLE VC Immediately associated Completion Temperature Control Time of Condition A System train in not met in MODE 5 operation.
or 6, or during movement of irradiated AND fuel assemblies.
C.1.2 Verify OPERABLE VC Immnediately Temperature Control System train is capable of being powered by an OPERABLE emergency power source.
OR C.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND C.2.2 Suspend positive Immediately reactivity additions.
(continued)
BYRON - UNITS 1 & 2 3.7.11 - 2 Amendment 147
VC Temperature Control System 3.7.11 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Two VC Temperature D.1 Suspend movement of Immrediately Control System trains irradiated fuel inoperable in MODE 5 assemblies.
or 6,.or during movement of irradiated AND fuel assemblies.
D.2 Suspend positive Irmmediately reactivity additions.
E. Two VC Temperature E.1 Enter LCO 3.0.3.
Immediately Control System trains inoperable in MODE 1, 2, 3, or 4.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify control room temperature 5 900F.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.7.11.2 Verify each VC Temperature Control System 18 months train has the capability to remove the required heat load.
BYRON - UNITS 1 & 2 3.7.11 - 3 Amendment 147
FHB Ventilation System 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System LCO 3.7.13 APPLICABILITY:
Two FHB Ventilation System trains shall be OPERABLE.
During movement of RECENTLY IRRADIATED FUEL assemblies in the fuel building, During movement of RECENTLY IRRADIATED FUEL assemblies in the containment with the equipment hatch not intact.
II I
ACTIONS
NOTE-LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One FHB Ventilation A.1 Restore FHB 7 days System train Ventilation System inoperable, train to OPERABLE status.
B. Required Action and B.1.1 Place OPERABLE FHB Immediately associated Completion Ventilation System Time not met.
train in emergency mode.
AND B.1.2 Verify OPERABLE FHB Inmediately Venti 1 ation System train is capable of being powered by an OPERABLE emergency power source.
OR I_
'(continued)
BYRON -
UNITS 1 & 2 3.7.13 - I Amendment 14 7
FHB Ventilation System 3.7.13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued)
B.2.1 Suspend movement of Immediately RECENTLY I RRADIATED FUEL assemblies in the fuel handling building.
AND B.2.2 -------- NOTE------
Only required with equipment hatch not intact.
Suspend movement of Immrediately RECENTLY IRRADIATED FUEL assemblies in the containment.
(continued)
BYRON - UNITS 1 & 2 3.7.13 -
2 Amendment* 14 7
FHB Ventilation System 3.7.13 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
Two FHB Ventilation C.1 Suspend movement of Immediately System trains RECENTLY IRRADIATED inoperable.
FUEL assemblies in the fuel handling building.
AND C.2
NOTE------
Only required with equipment hatch not intact.
Suspend movement of Irmnediately RECENTLY IRRADIATED FUEL assemblies in the containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each FHB Ventilation System train 31 days for Ž 15 minutes.
(continued)
I.
BYRON - UNITS I & 2 3.7.13 - 3 Amendment 14 7
FHB Ventilation System 3.7.13 ACTIONS (continued)
SURVEILLANCE FREQUENCY SR 3.7.13.2 Perform required FHB Ventilation System In accordance filter testing in accordance with the with the VFTP Ventilation Filter Testing Program (VFTP).
SR 3.7.13.3 ----------------
NOTE Only required during movement of RECENTLY IRRADIATED FUEL assemblies with the equipment hatch not intact.
Verify one FHB Ventilation System train can 7 days on a maintain a pressure *_
-0.25 inches water STAGGERED TEST gauge relative to atmospheric pressure BASIS during the emergency mode of operation.
SR 3.7.13.4 Verify each FHB Ventilation System train 18 months actuates on an actual or simulated actuation signal.
SR 3.7.13.5 ----------------
NOTE--
Only required during movement of RECENTLY IRRADIATED FUEL assemblies in the fuel handling building with the equipment hatch intact.
Verify one FHB Ventilation System train can 18 months on a maintain a pressure _< -0.25 inches water STAGGERED TEST gauge relative to atmospheric pressure BASIS during the emergency mode of operation at a flow rate < 23,100 cfm.
BYRON - UNITS 1 & 2 3.7.13 - 4 Amendment 147
Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following status:
- a.
One door in the personnel air lock closed and the equipment hatch held in place by >_ 4 bolts;
- b.
One door in the emergency air lock closed; and
- c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
- 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or
- 2. Capable of being closed by an OPERABLE Containment Ventilation Isolation System.
NOTE LCO 3.9.4.a is not required to be met when in compliance with LCO 3.7.13, "Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System," or its associated Conditions and Required Actions.
APPLICABILITY:
During movement of RECENTLY IRRADIATED FUEL assemblies within containment.
BYRON - UNITS 1 & 2 3.9.4 - 1 Amendment 14 7
Containment Penetrations 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Suspend movement of Inmmediately containment RECENTLY IRRADIATED penetrations not in FUEL assemblies required status.
within containment.
SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.9.4.1 Verify each required containment 7 days penetration is in the required status.
SR 3.9.4.2 Verify each required containment purge 18 months valve actuates to the isolation position on an actual or simulated actuation signal.
SR 3.9.4.3 Verify the isolation time of each required In accordance containment purge valve is within limits, with the Inservice Testing Program BYRON - UNITS 1 & 2 3.9.4 - 2 Amendment.147
Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Cavity Water Level LCO 3.9.7 Refueling cavity water level shall be maintained > 23 ft above the top of reactor vessel flange.
APPLICABILITY:
During movement of containment.
irradiated fuel assemblies within I
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend movement of Immediately level not within irradiated fuel limit.
assemblies within containment.
SURVEI LLANCE REQU I REMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling cavity water level is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
> 23 ft above the top of reactor vessel flange.
I BYRON - UNITS 1 & 2 3.9.7 - 1 Amendment 147
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testinq Program (VFTP)
(continued)
- b.
Demonstrate for each of the ESF filter systems that an inplace test of the charcoal adsorber shows a bypass specified below when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below.
Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and.3.7.13.5, as applicable:
ESF Ventilation System Flow Rate Bypass
< 1%
VC Filtration System (makeup)
VC Filtration System (reci rcul ation, charcoal bed after complete or partial replacement).
VC Filtration System (reci rcul ation for reasons other than complete or partial charcoal bed repl acement)
Nonaccessi bl e Area Exhaust Filter Plenum Ventilation System (after structural maintenance of the charcoal adsorber housings)
Nonaccessible Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the charcoal adsorber housings)
FHB Ventilation System e 5400 cfm and
- 6600 cfm
Ž 44,550 cfm and
- 54,450 cfm
Ž 44,550 cfm and 54,450 cfm 55,669 cfm and
- 68,200 cfm per train, and
, 18,556 cfm and
< 22,733 cfm per bank 55,669 cfm and 68,200 cfm per train 18,900 cfm and
- 23,100 cfm per train
< 0.1%
< 2%
< 1%
< 1%
< 1%
BYRON - UNITS 1 & 2 5.5 -
17 Amendment 147
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testinq Program (VFTP)
(continued)
- c.
Demonstrate for each of the ESF filter systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested. in conformance with Regulatory Guide 1.52, Revision 2, ANSI N510-1980, and ASTM D3803-1989, with any exceptions noted in Appendix A of the UFSAR, at a temperature of 300C and a Relative Humidity (RH) specified below:
ESF Ventilation System Penetration RH VC Filtration System 2.0%
70%
(makeup)
VC Filtration System 4%
70%
(recirculation)
Nonaccessible Area 4.5%
70%
Exhaust Filter Plenum Ventilation System FHB Ventilation System 10%
95%
- d.
Demonstrate for each of the ESF filter systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is < 6 inches of water gauge when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below.
Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and 3.7.13.5, as applicable:
ESF Ventilation System Flow Rate VC Filtration System
> 5400 cfm and < 6600 cfm (makeup)
Nonaccessible Area 55,669 cfm and Exhaust Filter Plenum
_< 68,200 cfm per train Ventilation System FHB Ventilation System
> 18,900 cfm and
_< 23,100 cfm BYRON - UNITS 1 & 2 5.5 - 18 Amendment 147
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP)
(continued)
The SFDP identifies where a loss of safety function exists.
If a loss of safety function is determined to exist by this program, the appropriate Conditions and.Required Actions of the LCO in which the loss of safety function exists are required to be entered.
5.5.16 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, September 1995 and NEI 94-01, Revision 0.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 42.8 psig for Unit 1 and 38.4 psig for Unit 2.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.20% of containment air weight per day.
Leakage Rate acceptance criteria are:
- a.
Containment leakage rate acceptance criterion is
- 1.0 La.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are
< 0.60 La for the Type B and C tests and < 0.75 La for Type A tests; and BYRON - UNITS 1 & 2 5.5 - 24 Amendment147