ML062750565

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Technical Specification Power Range Neutron Monitor Upgrade (TAC MC1330) (TS-430)
ML062750565
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 09/27/2006
From: Chernoff M
NRC/NRR/ADRO/DORL/LPLII-2
To:
Chernoff Margaret H. NRR/DORL 415-4041
Shared Package
ML062280009 List:
References
TAC MC1330
Download: ML062750565 (15)
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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. 262, 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. 262

TABLE OF CONTENTS Section Paoe No.

1.0 USE AND APPLICATION ................................................................. 1.1-I 1.1 D efin ition s .................................................................................. 1.1-1 1.2 Logical Connectors .................................................................... 1.2-1 1.3 Completion Times ..................................................................... 1.3-1 1.4 Frequency .................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs) ...................................................................... 2.0-1 2.1 S Ls ........................................................................................... 2 .0-1 2.2 SL Violations ............................................................................ 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY ......................................................................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................ 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ......................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) ............................................. 3.1-1 3.1.2 Reactivity Anomalies ........................................................... 3.1-5 3.1.3 Control Rod OPERABILITY .................................................. 3.1-7 3.1.4 Control Rod Scram Times .................................................... 3.1-12 3.1.5 Control Rod Scram Accumulators ........................................ 3.1-16 3.1.6 Rod Pattern Control ............................................................. 3.1-20 3.1.7 Standby Liquid Control (SLC) System ................................. 3.1-23 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves..... 3.1-28 3.2 POWER DISTRIBUTION LIMITS .................... 3.2-1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........................................................... 3.2-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) ......... 3.2-3 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) ..................... 3.2-5 3.3 INSTRUMENTATION ................................................................ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation .............. 3.3-1 3.3.1.2 Source Range Monitor. (SRM) Instrumentation .................... 3.3-9 3.3.2.1 Control Rod Block Instrumentation ...................................... 3.3-15 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation ..................... :............................... 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ................. 3.3-23 3.3.3.2 Backup Control System ........................ 3.3-27 (continued)

BFN-UNIT I i Amendment No.-2 262

Definitions 1.1 1.1 Definitions (continued)

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a FUNCTIONAL TEST test of all required logic components (i.e., all required relays and contacts, trip units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL The MCPR shall be the smallest critical power ratio I

POWER RATIO (MCPR) (CPR) that exists in the core. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

(continued)

BFN-UNIT 1 1.1-5 Amendment No.-234-, 262

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> channels inoperable.

OR A.2 ------- NOTE----- 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Not applicable for Functions 2.a, 2.b, 2.c, or 2.d.

Place associated trip system in trip.

B. NOTE-....... B.1 Place channel in one trip 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Not applicable for system in trip.

Functions 2.a, 2.b, 2.c, or 2.d. OR One or more Functions B.2 Place one trip system in 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> with one or more required trip.

channels inoperable in both trip systems.

(continued)

BFN-UNIT 1 3.3-1 Amendment No.-234- 262

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore RPS trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with RPS trip capability capability.

not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, B, or Table 3.3.1.1-1 for the C not met. channel.

E. As required by Required E.1 Reduce THERMAL 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Action D.1 and referenced POWER to < 30% RTP.

in Table 3.3.1.1-1.

F. As required by Required F.1 Be in MODE 2. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action D.1 and referenced in Table 3.3.1.1-1.

G. As required by Required G.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by Required H.1 Initiate action to fully Immediately Action D.1 and referenced insert all insertable control in Table 3.3.1.1-1. rods in core cells containing one or more fuel assemblies.

BFN-UNIT 1 3.3-2 Amendment No.-24-. 262

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

NOTES----

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS 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 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.1.1.2 Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after THERMAL POWER Ž 25% RTP.

Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power is

< 2% RTP while operating at > 25% RTP. II l

SR 3.3.1.1.3 ---------- NOTE--.........

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued)

BFN-UNIT 1 3.3-3 Amendment No.-234, 262

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.5 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing overlap. SRMs from the fully inserted position SR 3.3.1.1.6 ---------- NOTE ....---------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. 7 days SR 3.3.1.1.7 Calibrate the local power range monitors. 1000 MWD/T average core exposure SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1.9 ------------ NOTES --.......------------

1. Neutron detectors are excluded.
2. For Function 1, not required to be performed when entering MODE 2 from I

MODE 1 until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after entering MODE 2.

Perform CHANNEL CALIBRATION. 92 days (continued)

BFN-UNIT 1 3.3-4 Amendment No.-2-4-, 262

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. 184 days SR 3.3:1.1.11 (Deleted)

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.1.1.13 ----- NOTE Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL 18 months TEST.

SR 3.3.1.1.15 Verify Turbine Stop Valve-Closure and 18 months Turbine Control Valve Fast Closure, Trip Oil Pressure--Low Functions are not bypassed when THERMAL POWER is > 30% RTP.

SR 3.3.1.1.16 --- -...-------------......

For Function 2.a, not required to be performed when entering MODE 2 from MODE I until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 184 days BFN-UNIT 1 3.3-5 Amendment No.-234-, 262

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

1. Intermediate Range Monitors
a. Neutron Flux - High 2 3 G SR 3.3.1.1.1 _ 120/125 SR 3.3.1.1.3 divisions of full SR 3.3.1.1.5 scale SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.14 5 (a) 3 H SR 3.3.1.1.1 < 120/125 SR 3.3.1.1.4 divisions of full SR 3.3.1.1.9 scale SR 3.3.1.1.14
b. Inop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.14 5 (a) 3 H SR 3.3.1.1.4 NA SR 3.3.1.1.14
2. Average Power Range Monitors 2 3 (b) G SR 3.3.1.1.1 _ 15% RTP
a. Neutron Flux -, High, SR 3.3.1.1.6 Seldown SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16
b. Flow Biased Simulated 1 3 (b) F SR 3.3.1.1.1 <0.66 W Thermal Power - High SR 3.3.1.1.2 + 71% RTP SR 3.3.1.1.7 and <_120%

SR 3.3.1.1.13 RTP(c)

SR 3.3.1.1.16

c. Neutron Flux - High 1 3 (b) F SR 3.3.1.1.1

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) Each APRM channel provides inputs to both trip systems.

(c) [0.66 W + 71% - 0.66 A W] RTP when reset for single loop operation per LCO 3.4.1, 'Recirculation Loops Operating."

BFN-UNIT 1 3.3-6 Amendment No.-2-6;, 262

,RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

2. Average Power Range Monitors (continued)
d. Inop 1,2 3 (b) G SR 3.3.1.1.16 NA I
e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.14 SR 3.3.1.1.16
3. Reactor Vessel Steam Dome 1,2 2 G SR 3.3.1.1.1 < 1055 psig Pressure - High(d) SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14
4. Reactor Vessel Water Level - 1,2 2 G SR 3.3.1.1.1 >528inches Low, Level 3 (d) SR 3.3.1.1.8 above vessel SR 3.3.1.1.13 zero SR 3.3.1.1.14
5. Main Steam Isolation Valve - 1 8 F SR 3.3.1.1.8 _ 10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14
6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.8 !52.5 psig SR 3.3.1.1.13 SR 3.3.1.1.14
7. Scram Discharge Volume Water Level - High
a. Resistance Temperature 1,2 2 G SR 3.3.1.1.8 < 50 gallons Detector SR 3.3.1 1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 !550 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) Each APRM channel provides inputs to both trip systems.

(d) During instrument calibrations. if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-7 Amendment No. 234, 257, 258, 262

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

------------- NOTES--------- --------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.
2. When an RBM 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 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.2 -.--------.------- NOTE-- -

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at _<10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ------ NOTE------------------.....

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is*< 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 ----------- NOTE -----------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months (continued)

BFN-UNIT 1 3.3-18 Amendment No.-2-34, 262

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.5 Verify the RWM is not bypassed when 18 months THERMAL POWER is*< 10% RTP.

SR 3.3.2.1.6 -NOTE Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.2.1.7 Verify control rod sequences input to the Prior to declaring RWM are in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SR 3.3.2.1.8 --------- NOTE----

Neutron detectors are excluded.

Verify the RBM: 18 months

a. Low Power Range - Upscale Function is not bypassed when THERMAL POWER is > 27% and _ 62% RTP.
b. Intermediate Power Range - Upscale Function is not bypassed when THERMAL POWER is > 62% and *_82%

RTP.

c. High Power Range - Upscale Function is not bypassed when THERMAL POWER is > 82% RTP.

BFN-UNIT 1 3.3-19 Amendment No.-24-, 262

Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR FUNCTION OTHER REQUIRED SURVEILLANCE ALLOWABLE SPECIFIED CHANNELS REQUIREMENTS VALUE CONDITIONS

1. Rod Block Monitor
a. Low Power Range - Upscale (a) 2 SR 3.3.2.1.1 (e)

SR 3.3.2.1.4 SR 3.3.2.1.8 b Intermediate Power Range - Upscale (b) 2 SR 3.3.2.1.1 (e)

SR 3.3.2.1.4 SR 3.3.2.1.8

c. High Power Range - Upscale (f),(g) 2 SR 3.3.2.1.1 (e)

SR 3.3.2.1.4 SR 3.3.2.1.8

d. Inop (g).(h) 2 SR 3.3.2.1.1 NA
e. Downscale (g).th) 2 SR 3.3.2.1.1 (i)

SR 3.3.2.1.4

2. Rod Worth Minimizer 1 (c)02 (c) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.7
3. Reactor Mode Switch - Shutdown Position (d) 2 SR 3.3.2.1.6 NA (a) THERMAL POWER > 27%.and < 62% RTP and MCPR less than the value specified in the COLR.

(b) THERMAL POWER > 62% and < 82% RTP and MCPR less than the value specified in the COLR.

(c) With THERMAL POWER _ 10% RTP.

(d) Reactor mode switch in the shutdown position.

(e) Less than or equal to the Allowable Value specified in the COLR.

(n THERMAL POWER > 82% and < 90% RTP and MCPR less than the value specified in the COLR.

(g) THERMAL POWER _ 90% RTP and MCPR less than the value specified in the COLR.

(h) THERMAL POWER _ 27% and < 90% RTP and MCPR less than the value specified in the COLR.

(i) Greater than or equal to the Allowable Value specified in the COLR.

BFN-UNIT 1 3.3-20 Amendment No.-2-34-, 262

SDM Test - Refueling

  • 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:
a. LCO 3.3.1.1, "Reactor Protection System Instrumentation,"

MODE 2 requirements for Functions 2.a, 2.d, and 2.e of I Table 3.3.1.1-1;

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence (BPWS) requirements of SR 3.3.2.1.7 changed to require the control rod sequence to conform to the SDM test sequence, OR
2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;
c. Each withdrawn control rod shall be coupled to the associated CRD;
d. All control rod withdrawals during out of BPWS control rod moves shall be made in notch out mode;
e. No other CORE ALTERATIONS are in progress; and
f. CRD charging water header pressure _>940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

BFN-UNIT 1 3.10-22 Amendment No.-24, 262

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to the LCO 3.3.1.1, Functions 2.a, 2.d, and 2.e of applicable SRs I Table 3.3.1.1-1.

SR 3.10.8.2 ---.....------.-.------ NOTE -........-------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to the LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1. applicable SRs SR 3.10.8.3 --------- NOTE--- --------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> progress.

(continued)

BFN-UNIT 1 3.10-24 Amendment No.-234, 262

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