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MONTHYEARML0212600082002-05-0101 May 2002 Tech Spec Pages for Amendment Nos. 152 and 152 Alternate Criteria for Axial Primary Water Stress Corrosion Cracking at Dented Intersections Project stage: Other ML0212302712002-05-0101 May 2002 Amendment Nos 152 & 152 Alternate Repair Criteria for Axial Primary Water Stress Corrosion Cracking at Dented Inspections in Steam Generators Tubing Project stage: Other 2002-05-01
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Category:Technical Specifications
MONTHYEARML23012A2172023-02-0909 February 2023 Issuance of Amendment Nos. 244 and 245 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition ML21242A2162022-12-21021 December 2022 Issuance of Amendment Nos. 243 and 244 Technical Specifications and Revised License Conditions for the Permanently Defueled Condition (EPID: L-2020-LLA-0261 DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2022-07-26026 July 2022 License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML21188A3452021-07-0808 July 2021 Issuance of Amendment No. 238 Revision to TS 3.7.8, Auxiliary Saltwater (Asw) System (Emergency Circumstances) ML21188A0372021-07-0707 July 2021 Attachment 1 TS_3_7_8 (Marked Up Pages) ML21188A0352021-07-0707 July 2021 Attachment 2 TS_3_7_8 (Retype Pages) ML21188A0342021-07-0707 July 2021 Attachment 3-TS Bases Section 3_7_8 (Marked-up Pages) DCL-19-094, License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report2019-12-0505 December 2019 License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology2018-12-26026 December 2018 License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology ML16330A6722017-01-0505 January 2017 Issuance of Amendment Nos. 228 and 230, Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML16139A0082016-12-21021 December 2016 Issuance of Amendment Nos. 227 and 229, Digital Replacement of the Process Protection System Portion of the Reactor Protection System and Engineered Safety Features Actuation System ML16035A4412016-04-14014 April 2016 Issuance of Amendment Nos. 225 and 227, Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML16083A5642016-03-23023 March 2016 License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12., Low Temperature Overpressure Protection (Ltop) System. DCL-16-028, Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information2016-03-23023 March 2016 Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information ML16055A3592016-03-0909 March 2016 Issuance of Amendment Nos. 224 and 226, Revise Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and TS 5.6.5 (COLR) Paragon and Nexus Methodologies ML16032A0062016-02-19019 February 2016 Redacted, Issuance of Amendment Nos. 223 and 225, Revise UFSAR Section 15.4.2.2 to Incorporate Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident Into Licensing Basis ML15245A5422015-09-30030 September 2015 Issuance of Amendment Nos. 220 and 222, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone H Full Implementation Date ML15204A2222015-08-27027 August 2015 Issuance of Amendment Nos. 219 and 221, Adopt Technical Specifications Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) ML15162A8822015-07-0101 July 2015 Issuance of Amendment Nos. 218 and 220, Revise Surveillance Requirements in TS 3.8.1, AC Sources, Related to Diesel Generator Testing DCL-15-052, Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2015-04-29029 April 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. ML14042A1932014-02-27027 February 2014 Issuance of Amendment Nos. 217 and 219, Editorial and Clarifying Changes to Technical Specification (TS) 3.7.10, Control Room Ventilation System (CRVS) and TS 5.6.5, Core Operating Limits Report (COLR) (TAC MF1959-MF1960) ML13130A2252013-05-10010 May 2013 Technical Specification 3.5.2 Safety Injection Pump 2-1 Issue Information ML13267A1352013-01-31031 January 2013 Attachment 6 to DCL-13-016, LTR-RAM-1-13-002 NP-Attachment, Revision 0, Justification for the Application of Technical Specifications Changes in WCAP-14333 and WCAP-15376 to the Tricon/Als Process Protection System at the Diablo Canyon Powe DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac.....2012-11-0101 November 2012 Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac..... DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 12012-05-31031 May 2012 Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 DCL-11-097, License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake2011-10-20020 October 2011 License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake DCL-11-059, Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Sys2011-06-0101 June 2011 Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Syste DCL-11-055, Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs).2011-04-21021 April 2011 Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs). DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)2011-02-17017 February 2011 License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) DCL-10-028, Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-028, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-018, License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-02-24024 February 2010 License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-09-062, Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15.2009-09-0303 September 2009 Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15. ML0919601772009-07-0303 July 2009 License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for RCS Leakage Detection Instrumentation DCL-09-009, License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function2009-02-24024 February 2009 License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function DCL-08-100, Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS)2008-11-25025 November 2008 Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS) ML0824102622008-10-30030 October 2008 Issuance of Amendment Nos. 200 and 201, Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk-Informed Initiative 5b) DCL-07-097, License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b)2007-10-15015 October 2007 License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b) DCL-07-075, Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information2007-08-0909 August 2007 Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information ML0713707332007-06-26026 June 2007 Tech Spec Pages for Amendment Nos. 197 and 198 TS 5.5.16, Containment Leakage Rate Testing Program, for Consistency with 10 CFR 50.55a(g)(4) ML0709900742007-06-25025 June 2007 Units, 1 and 2, Tech Spec Page for Amendments 196 and 197 Administrative Changes to the Technical Specification 5.5.8, Inservice Testing Program. ML0703500522007-04-17017 April 2007 Tech Spec Pages for Amendment Nos. 195 and 196 TS 3.4.1 Reactor Coolant System Pressure, Temperature, & Flow Departure from Nucleate Boiling Limits & TS 5.6.5 Core Operating Limits Report. ML0704404942007-03-21021 March 2007 Tech Spec Pages for Amendments 194 and 195 Regarding Steam Generator Tube Integrity Technical Specifications ML0701902142007-01-19019 January 2007 Units, 1 and 2 - Tech Spec Pages for Amendments 192 and 193 Technical Specification 1.1 Definitions and Technical Specification 3.4.16 Reactor Coolant System Specific Activity DCL-06-143, License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program2006-12-29029 December 2006 License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program DCL-06-136, License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating....2006-12-29029 December 2006 License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating.... DCL-06-142, License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343)2006-12-29029 December 2006 License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343) ML0635500312006-12-20020 December 2006 Tech Spec Pages for Amendment 192 Regarding TS 5.6.5, Core Operating Limits Report. DCL-06-129, Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage2006-11-17017 November 2006 Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage ML0631905402006-11-15015 November 2006 Technical Specifications, Issuance of Exigent Amendment No. 190 Revision to TS Section 3.8.4, DC Sources - Operating to Extend the Completion Time to Restore an Inoperable Station Battery 2023-02-09
[Table view] |
Text
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Pro-gram (continued)
- 3. The tubes selected as the second and third samples (if required by Table 5.5.9-2) during each inservice inspection may be subjected to a partial tube inspection provided:
a) The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and b) The inspections include those portions of the tubes where imperfections were previously found.
- 4. Implementation of the steam generator tube/tube support plate repair criteria requires a 100% bobbin coil inspection for hot-leg and cold-leg support plate intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold-leg tube support plate intersection having ODSCC indications shall be based on the performance of at least a 20%
random sampling of tubes inspected over their full length.
- 5. Inspection of dented tube support plate intersections will be performed in accordance with WCAP-15573, Revision 1, to implement axial primary water stress corrosion cracking (PWSCC) depth-based repair criteria. The extent of required inspection is:
a) 100 percent bobbin coil inspection of all tube support plate (TSP) intersections.
b) Plus Point coil inspection of all bobbin coil indications at dented TSP intersections.
c) Plus Point coil inspection of all prior PWSCC indications left in service.
d) If bobbin coil is relied upon for detection of axial PWSCC in less than or equal to 2 volt dents, then on a SG basis perform Plus Point coil inspection of all TSP intersections having greater than 2 volt dents up to the highest TSP for which PWSCC has been detected in the prior two inspections or current inspection and 20% of greater than 2 volt dents at the next higher TSP. If a circumferential indication is detected in a dent of "x" volts in the prior two inspections or current inspection, Plus Point inspections will be conducted on 100% of dents greater than "x - 0.3" volts up to the affected TSP elevation in the affected SG, plus 20% of dents greater than "x - 0.3" volts at the next higher TSP. "x" is defined as the lowest dent voltage where a circumferential crack was detected.
(continued)
DIABLO CANYON - UNITS 1 & 2 5.0-11 Unit 1 -Amendment No. 4-35, 152 TAB 5.0 - RXXX 11 Unit 2 - Amendment No. 4-35, 152
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Pro-qram (continued) e) If bobbin coil is not relied upon for detection of axial PWSCC in less than or equal to 2 volt dents, then on a SG basis perform Plus Point coil inspection of all dented TSP intersections (no lower dent voltage threshold) up to the highest TSP for which PWSCC has been detected in the prior two inspections or current inspection and 20% of all dents at the next higher TSP.
f) For any 20% dent sample, a minimum of 50 dents at the TSP elevation shall be inspected. If the population of dents is less than 50 at the TSP elevation, then 100% of the dents at the TSP elevation shall be inspected.
The results of each sample inspection shall be classified into one of the following three categories:
Cate-qory Inspection Results Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
- c. Inspection Frequencies - The above required inservice inspections of SG tubes shall be performed at the following frequencies:
- 1. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; (continued)
DIABLO CANYON - UNITS 1 & 2 5.0-1 Ia Unit 1 - Amendment No. 4.35, 152 TAB 5.0 - RXXX 12 Unit 2 - Amendment No. -45, 152
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Program (continued)
- 2) This definition does not apply to the portion of the tube within the tubesheet below the W* length. Acceptable tube wall degradation within the W* length shall be defined as in 5.5.9.d.1.k. *
- 3) This definition does not apply to axial PWSCC indications, or portions thereof, which are located within the thickness of dented tube support plates which exhibit a maximum depth greater than or equal to 40 percent of the initial tube wall thickness. WCAP 15573, Revision 1, provides repair limits applicable to these intersections.
- 4) A tube which contains a tube support plate intersection with both an axial ODSCC indication and an axial PWSCC indication will be removed from service.
g) Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of a Double Design Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 5.5.9.c.3, above; h) Tube Inspection means an inspection of the SG tube from the tube end (hot leg side) completely around the U-bend to the top support of the cold leg; i) Preservice Inspection means an inspection of the full length of each tube in each SG performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial Power Operation using the equipment and techniques expected to be used during subsequent inservice inspections; j) Tube Support Plate Plugg-qing Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the plugging limit is based on maintaining steam generator tube serviceability as described below:
(i) Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to the lower voltage repair limit (NOTE 1), will be allowed to remain in service.
(ii) Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the lower voltage repair limit (NOTE 1), will be repaired or plugged, except as noted in 5.5.9.d.1.j (iii) below.
(continued)
- Applicable for Units 1 and 2, Cycles 10, 11, 12, and 13 only.
5.0-13 Unit 1 -Amendment No. 4-35, 1-54, DIABLO CANYON - UNITS 1 & 2 152 TAB 5.0 - RXXX 14 Unit 2 - Amendment No. 1-35, 1-54, 152
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Pro-gram (continued)
(iii) Steam generator tubes, with indication of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the lower voltage repair limit (NOTE 1) but less than or equal to the upper voltage repair limit (NOTE 2), may remain in service if a rotating pancake coil inspection does not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater than the upper voltage repair limit (NOTE 2) will be plugged or repaired.
(continued)
DIABLO CANYON - UNITS 1 & 2 5.0-13a Unit 1 - Amendment No. !-35, 152 TAB 5.0 - RXXX 15 Unit 2 - Amendment No. 35, 152
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.10 Steam Generator (SG) Tube Inspection Report
- e. (*) The results of the inspection of W* tubes shall be reported to the Commission pursuant to 10 CFR 50.4 within 90 days following return to service of the steam generators. This report shall include:
- 1) Identification of W* tubes.
- 2) W* inspection distance measured with respect to the BWT or the top of the tubesheet, whichever is lower.
- 3) Elevation and length of axial indications within the flexible W* distance and the angle of inclination of clearly skewed axial cracks (if applicable).
- 4) The total steam line break leakage for the limiting steam generator per WCAP-14797.
- f. (*) The aggregate calculated steam line break leakage from application of all alternate repair criteria shall be reported to the Commission pursuant to 10 CFR 50.4 within 90 days following return to service of the steam generators.
- g. For implementation of the repair criteria for axial PWSCC at dented TSPs, the NRC shall be notified prior to startup, pursuant to 10CFR50.72, of the following conditions that indicate a failure of performance criteria:
- 1) The calculated SG probability of burst for condition monitoring exceeds 1 X102.
- 2) The calculated SG leakage for condition monitoring from all sources (all alternate repair criteria and non-alternate repair criteria indications) exceeds the leakage limit determined from the licensing basis steam line break dose calculation.
- h. For implementation of the repair criteria for axial PWSCC at dented TSPs, the results of the condition monitoring and operational assessments will be reported to the NRC within 120 days following completion of the inspection. The report will include:
- 1) Tabulations of indications found in the inspection, tubes repaired, and tubes left in service under the ARC.
- 2) Growth rate distributions for indications found in the inspection and growth rate distributions used to establish the tube repair limits.
- 3) Plus Point confirmation rates for bobbin detected indications when bobbin is relied upon for detection of axial PWSCC in less than or equal to 2 volt dents.
- 4) For condition monitoring, an evaluation of any indications that satisfy burst margin requirements based on the Westinghouse burst pressure model, but do not satisfy burst margin requirements based on the combined ANL ligament tearing and throughwall burst pressure model.
(continued)
Applicable for Units 1 and 2, Cycles 10, 11, 12, and 13 only.
5.0-30 Unit 1 - Amendment No. 4-35, 51-,
DIABLO CANYON - UNITS 1 & 2 152 TAB 5.0 - RXXX 33 Unit 2 - Amendment No. 4-3.5, 1-5-1-,
152
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.10 Steam Generator (SG) Tube Inspection Report
- 5) Performance evaluation of the operational assessment methodology for prediction flaw distributions as a function of flaw size.
- 6) Evaluation results of number and size of previously reported versus new PWSCC indications found in the inspection, and the potential need to account for new indications in the operational assessment burst evaluation.
- 7) Identification of mixed mode (axial PWSCC and circumferential) indications found in the inspection and an evaluation of the mixed mode indications for potential impact on the axial indication burst pressures or leakage.
- 8) Any corrective actions found necessary in the event that condition monitoring requirements are not met.
- Applicable for Units 1 and 2, Cycles 10, 11, 12, and 13 only.
5.0-30a Unit 1 - Amendment No. 4-5, 4-54, DIABLO CANYON - UNITS 1 & 2 152 TAB 5.0 - RXXX 34 Unit 2 - Amendment No. 4-35, 4-54, 152