ML062690018
| ML062690018 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/21/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | |
| Shared Package | |
| ML062640009 | List: |
| References | |
| TAC MC4070, TAC MC4071, TAC MC4072 | |
| Download: ML062690018 (10) | |
Text
(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 equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 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 renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 steady state reactor core power levels not in excess of 3293 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 260, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.
Renewed License No. DPR-33 Amendment No. 260
Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS N
S------------
- 1.
Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
- 2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION.
92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.
122 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
18 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL 18 months TEST.
SR 3.3.6.1.7 Perform CHANNEL CALIBRATION.
24 months BFN-UNIT 1 3.3-57 Amendment No.-2,34, 260
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 3.
HPCI System Isolation (continued)
- e. HPCI Steam Line Space Torus Area (Exit)
Temperature - High
- f.
HPCI Steam Line Space Torus Area (Midway)
Temperature - High
- g. HPCI Steam Line Space Torus Area (Entry)
Temperature - High
- 4.
Reactor Core Isolation Cooling (RCIC) System Isolation
- a. RCIC Steam Line Flow High
- b. RCIC Steam Supply Line Pressure - Low
- c.
RCIC Turbine Exhaust Diaphragm Pressure - High
- e. RCIC Steam Line Space Torus Area (Exit)
Temperature - High
- f.
RCIC Steam Line Space Torus Area (Midway)
Temperature - High
- g.
RCIC Steam Line Space Torus Area (Entry)
Temperature - High 1,2,3 1,2,3 1,2,3 1,2,3
.2 2
2 2
F SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR. 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7
!5200*F
- g 180*F
!g 180*F
- 5 180*1F I I I I 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7
_< 450" H20
>_ 50 psig
_< 20 psig
!: 0BOF
- 180*F
- 5 180*F
- 5 180*F I
(continued)
BFN-UNIT 1 3.3-59 Amendment No.-2-,47 260
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Main Steam Valve Vault Area Temperature - High
- b. Pipe Trench Area Temperature - High
- c. Pump Room A Area Temperature - High
- d. Pump Room B Area Temperature - High
- e. Heat Exchanger Room Area (West Wall)
Temperature - High
- f. Heat Exchanger Room Area (East Wall)
Temperature - High
- g. SLC System Initiation
- h. Reactor Vessel Water Level - Low, Level 3
- 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome Pressure - High
- b. Reactor Vessel Water Level - Low, Level 3
- c. Drywell Pressure - High 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2 1,2,3 2
2 2
2 2
2 1(a) 2 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 F
SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.7 H
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- 5201 *F
!5 135*F 5 152*F 5 152*F I
I I I
- 170°F
- 5 143°F NA
- 528 inches above vessel zero 1,2,3 3,4,5 1,2,3 I
.2 (b) 2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
!5 115 psig
> 528 inches above vessel zero
_< 2.5 psig F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 (a) One SLC System Initiation signal provides logic input to close both RWCU valves.
(b) Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 1 13.3-60 Amendment No. 234, 268, 260 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 equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 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 renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission.regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 steady state reactor core power levels not in excess. of 3458 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 297, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 253.
(3)
The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's Renewed License No. DPR-52 Amendment No. 297
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 3. HPCI System Isolation (continued)
- e. HPCI Steam Line Space Torus Area (Exit)
Temperature - High
- f.
HPCI Steam Line Space Torus Area (Midway)
Temperature - High
- g.
HPCI Steam Line Space Torus Area (Entry)
Temperature - High
- 4. Reactor Core Isolation Cooling (RCIC) System Isolation
- a. RCIC Steam Line Flow High
- b. RCIC Steam Supply Line Pressure - Low
- c.
RCIC Turbine Exhaust Diaphragm Pressure - High
- e. RCIC Steam Line Space Torus Area (Exit)
Temperature - High
- f.
RCIC Steam Line Space Torus Area (Midway)
Temperature - High
- g. RCIC Steam Line Space Torus Area (Entry)
Temperature - High 1,2,3 1,2,3 1,2,3 1,2,3 2
2 2
2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- ý200*F
<- 180*F
- 5 180*F
!5 180*F I
1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1
3 3
2 2
2 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
< 450" H20
> 50 psig
< 20 psig
- 1O0*F
- 5 180*F
- 5 180*F
- ý 180'F (continued)
BFN-UNIT 2 3.3-60 Amendment No.-2-37 297
Primary.Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Main Steam Valve Vault Area Temperature - High
- b. Pipe Trench Area Temperature - High
- c. Pump Room A Area Temperature - High
- d. Pump Room B Area Temperature - High
- e. Heat Exc~hanger Room Area (West Wall)
Temperature - High
- f.
Heat Exchanger Room Area (East Wall)
Temperature - High
- g. SLC System Initiation
- h. Reactor Vessel Water Level - Low, Level 3
- 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome Pressure - High
- b. Reactor Vessel Water Level - Low, Level 3
- c. Drywell Pressure - High 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2 1,2,3 2
2 2
2 2
1(a) 2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5
.SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 H
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
< 188°F
_< 135°F
_< 152°F
_ 152'F
_ 143°F
_ 170°F I
NA
> 528 inches above vessel zero 1,2,3 3,4,5 1,2,3 1
2 (b) 2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
_s 115 psig
_Ž528 inches above vessel zero
< 2.5 psig (a) One SLC System Initiation signal provides logic input to close both RWCU valves.
(b)
Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 2 3.3-61 Amendment No. 297
,Amcndmcnt No. 253, 254, 260, 277 (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 equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 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 renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 steady state reactor core power levels not in excess of 3458 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 255, except for Amendment No. 248, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 212 to Facility Operating License DPR-68, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment 212, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 212.
Renewed License No. DPR-68 Amendment No. 255
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 3.
HPCI System Isolation (continued)
- e. HPCI Steam Line Space Torus Area (Exit)
Temperature - High
- f.
HPCI Steam Line Space Torus Area (Midway)
Temperature - High
- g. HPCI Steam Line Space Torus Area (Entry)
Temperature - High
- 4. Reactor Core Isolation Cooling (RCIC) System Isolation
- a. RCIC Steam Line Flow High
- b. RCIC Steam Supply Line Pressure - Low
- c.
RCIC Turbine Exhaust Diaphragm Pressure - High
- d.
RCIC Steam Line Space RCIC Pump Room Area Temperature - High
- e. RCIC Steam Line Space.
Torus Area (Exit)
Temperature - High
- f.
RCIC Steam Line Space Torus Area (Midway)
Temperature - High
- g.
RCIC Steam Line Space Torus Area (Entry)
Temperature - High 1,2,3 1,2,3 1,2,3 1,2,3 2
2 2
2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- 5 200*F
- 5180'F
- 5 180'F
!* 180*F I
1,2,3 1,2,3 12,3 1,2,3
.1,2,3 1,2,3 1,2,3 1
3 3
2 2
2 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
_< 450" H20
_ 50 psig 20 psig f: 180*F
- 180*F
- 5 180*F 5 180*F (continued)
BFN-UNIT 3 3.3-60 Amendment No.-2-1-, 255
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Main Steam Valve Vault Area Temperature - High
- b. Pipe Trench Area Temperature - High
- c. Pump Room A Area Temperature - High
- d. Pump Room B Area Temperature - High
- e. Heat Exchanger Room Area (West Wall)
Temperature - High
- f.
Heat Exchanger Room Area (East Wall)
Temperature - High
- g. SLC System Initiation
- h. Reactor Vessel Water Level - Low, Level 3
- 6.
Shutdown Cooling System Isolation
- a. Reactor Steam Dome Pressure - High
- b. Reactor Vessel Water Level - Low, Level 3
- c. Drywell Pressure - High 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2 1,2,3 2
2 2
2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
-ý201°*F
_< 135°F
_< 152°F
!g 152°F I
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 2
2 1(a) 2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 H
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
_< 143°F
!5 170°F NA
Ž 528 inches above vessel zero 1,2,3 3,4,5 1,2,3 1
2 (b) 2 F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 115 psig
>_ 528 inches above vessel zero
_< 2.5 psig F
SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 (a) One SLC System Initiation signal provides logic input to close both RWCU valves.
(b)
Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 3 3.3-61 Amendment No. 255 Amondme-t No. 214,2, 213, 219, 236