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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999
Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis
ML17300B3521999-09-29029 September 1999
Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7
ML17300B3321999-09-14014 September 1999
Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes
ML17313B0601999-08-31031 August 1999
Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999
ML17313B0081999-07-14014 July 1999
Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1.
ML17313A9571999-05-26026 May 1999
Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection
ML17313A7511998-12-16016 December 1998
Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3
ML17313A4181998-06-0909 June 1998
Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown
ML17313A1141997-11-0707 November 1997
Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1
ML17312B6411997-08-28028 August 1997
Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic
ML20217Q6801997-08-22022 August 1997
Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure
ML20141H7831997-07-18018 July 1997
Proposed Improved Tech Specs Section 3.8, Electrical Power Sys
ML20141H7461997-07-18018 July 1997
Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs
ML17312B0311996-11-0606 November 1996
Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating
ML17300B2651996-06-17017 June 1996
Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131
ML17312A9451996-05-14014 May 1996
Rev 3 to Significant Condition Investigation.
ML17312A6491996-04-0101 April 1996
Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07
ML17312A6401996-03-26026 March 1996
Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06
ML17312A6321996-03-26026 March 1996
Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants.
ML17312A6371996-03-23023 March 1996
Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage
ML17312A5691996-03-0505 March 1996
Revised Pages to ISI Program Summary Manual
ML17312A5011996-01-17017 January 1996
Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies
ML17311B3221995-12-20020 December 1995
Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure
ML17311B3181995-12-20020 December 1995
Revised Pages to ISI Program Summary Manual
ML17311B0301995-07-0303 July 1995
Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage
ML17311A9771995-06-21021 June 1995
Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation
ML17311A8651995-05-0202 May 1995
Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures
ML17311A8231995-04-18018 April 1995
Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair
ML17312A9381995-02-0303 February 1995
Corrective Action Program.
ML17311A5631994-12-28028 December 1994
Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine
ML17311A5021994-12-0707 December 1994
Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators
ML17311A4341994-11-30030 November 1994
Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2
ML17311A3851994-10-31031 October 1994
Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine.
ML17311A3341994-10-0909 October 1994
Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage
ML17311A2171994-08-18018 August 1994
Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss.
ML17310B4511994-07-12012 July 1994
Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8
ML17310B4151994-07-0101 July 1994
Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6
ML17310B4331994-06-20020 June 1994
Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13
ML17310B4091994-06-17017 June 1994
Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08
ML17310B1661994-03-28028 March 1994
Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level
ML17310B0911994-03-0202 March 1994
SG Tube Insp Plan.
ML17310B0771994-02-24024 February 1994
PVNGS Unit 1 Cycle 5 Startup Rept.
ML17310B0611994-02-18018 February 1994
Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities
ML17310B0251994-01-27027 January 1994
Unit 2 Steam Generator Tube Insp Plan Addendum.
ML17310B0001994-01-19019 January 1994
Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension
ML17310A8361993-11-16016 November 1993
Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan
ML17310A7421993-10-27027 October 1993
Revised Unit 1 SG Tube Insp Plan.
ML17310A7351993-10-26026 October 1993
Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core
ML17310A6501993-09-17017 September 1993
Unit 1 SG Tube Insp Plan.
ML17310A6161993-09-0808 September 1993
Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits
1999-09-29
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17313B0081999-07-14014 July 1999
Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1.
ML17313A7511998-12-16016 December 1998
Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3
ML17312A9451996-05-14014 May 1996
Rev 3 to Significant Condition Investigation.
ML17312A5691996-03-0505 March 1996
Revised Pages to ISI Program Summary Manual
ML17311B3181995-12-20020 December 1995
Revised Pages to ISI Program Summary Manual
ML17312A9381995-02-0303 February 1995
Corrective Action Program.
ML17310B0911994-03-0202 March 1994
SG Tube Insp Plan.
ML17310B0251994-01-27027 January 1994
Unit 2 Steam Generator Tube Insp Plan Addendum.
ML17310A7421993-10-27027 October 1993
Revised Unit 1 SG Tube Insp Plan.
ML17310A6501993-09-17017 September 1993
Unit 1 SG Tube Insp Plan.
ML20056D3951993-08-0909 August 1993
Rev 04.01 to Procedure 41AO-1ZZ08, SG Tube Leak
ML20056D3961993-06-16016 June 1993
Rev 00.07 to Procedure 41EP-1R004, Excess Steam Demand, Consisting of CRS Actions & Details on Emergency Notification & Support
ML20056G0111993-03-21021 March 1993
Rev 7 to Odcm
ML17306A9831992-09-0303 September 1992
Window 2B08B, Rc LO Temp Over Press of Rev 5 to Procedure 40AL-9RK2B
ML17306A9841992-09-0303 September 1992
Window 2B08B, SDC Ln Isol VLV Not Fully Closed of Rev 5 to Procedure 40AL-9RK2B
ML17306A9851992-09-0303 September 1992
Window 2B09A, SDC Ln Isol Vlvs UV-653/654 Inverter Trbl of Procedure 40AL-9RK2B
ML17306A9871992-09-0303 September 1992
Window ES2A01B, LO Press Safety Inj of Rev 2 to Procedure 41AL-1ES2A
ML17306A4741991-10-30030 October 1991
Rev 2 to Nuclear Administrative & Technical Manual 76PR-9RW01, Solid Radwaste Process Control Program.
ML20085L3671991-10-28028 October 1991
Emergency Response Data Sys (ERDS) Implementation Program Plan for Palo Verde Nuclear Generating Station
ML17305B5521991-01-31031 January 1991
Rev 6 to Salt Deposition & Impact Monitoring Plan for Palo Verde Nuclear Generation Stations,Units 1,2 & 3.
ML17305B2731990-07-31031 July 1990
PVNGS 1991 Business Plan.
ML17306A5181989-10-22022 October 1989
Rev 0 to Nuclear Administrative & Technical Manual 01PR-0QQ02, Employee Concerns Program Policy.
ML17306A5161989-09-28028 September 1989
DOL000483, Employee Concerns Program.
ML20127J4161989-03-0808 March 1989
Procedure 2-3-89-001, Safety Equipment Status Sys
ML20082D9681989-01-18018 January 1989
Rev 1 to Nuclear Administrative & Technical Manual 81AC-OCC07, Cable & Raceway Control & Tracking Sys
ML20082D9721988-08-19019 August 1988
Rev 0 to Administrative Change Notice 03 to ES03.03, Cable & Raceway Control & Tracking Sys
ML20082E6001988-07-11011 July 1988
Rev 0 to Administrative Change Notice 02 to ES03.03, Cable & Raceway Control & Tracking Sys
ML20082D9801988-06-21021 June 1988
Rev 2 to QA02.02, QC Insps
ML20082D9871988-06-0202 June 1988
Rev 0 to ES10.00, Sys Engineer Program
ML20082D9901988-05-26026 May 1988
Rev 7 to 73AC-OZZ29, Engineering Evaluation Request
ML20082E6221988-05-19019 May 1988
Rev 0 to Administrative Change Notice 01 to ES03.03, Cable & Raceway Control & Tracking Sys
ML17304A1651988-05-10010 May 1988
Loose Part Monitoring Sys Loose Part Detection Program Rept. W/Eleven Oversize Drawings
ML20082E6291987-09-0202 September 1987
Rev 0 to ES03.03A, Cable & Raceway Control & Tracking Sys
ML20237H5571987-08-0303 August 1987
Public Version of Revs to Emergency Plan Implementing Procedures,Including Temporary Procedure Change Notice (Tpc) 3 to Rev 5 to EPIP-02, Emergency Classification & Tpc Notice 2 to Rev 11 to EPIP-03.W/870820 Release Memo
ML20235X0961987-07-0202 July 1987
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 3 to EPIP-56, UHS Emergency Water Supply, Rev 4 to EPIP-33, Offsite Assistance & Rev 5 to EPIP-27, Post-Accident Sampling Analysis
ML17300A7801987-04-16016 April 1987
Procedure Change Notice 1 to Rev 0 to Procedure 41AO-1ZZ54, Monitoring Reactor Vessel Inventory W/Reactor Vessel Level Monitoring Sys Inoperable. W/870416 Ltr
ML17303A3611987-03-20020 March 1987
Test/Retest Recovery Program Diesel Generator B & Associated Support Equipment.
ML17333A1801987-03-13013 March 1987
Diesel Generator B Test Insps.
ML20206N4501987-03-0606 March 1987
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure Change Notice 02 to Rev 5 to EPIP-02, Emergency Classification, Closing Out Open Item Noted by NRC
ML20212M8121987-01-28028 January 1987
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 11 to EPIP-04 Re Alert,Site Area & General Emergency Implementing Action,Consisting of Temporary Change Notice 02T
ML20214U1761986-09-11011 September 1986
Public Version of Procedure Change Notice 3 to Rev 10 to Emergency Plan Implementing Procedure EPIP-3, Notification of Unusual Event Implementing Actions. W/860925 Release Memo
ML20205E5391986-07-29029 July 1986
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 4 to EPIP-23, Fire Fighting, Rev 5 to EPIP-02, Emergency Classification & Rev 11 to EPIP-04, Alert,Site Area..
ML20211Q5951986-07-10010 July 1986
Public Version of Rev 10 to EPIP-03, Notification of Unusual Event Implementing Actions & Rev 4 to EPIP-15, Protective Action Guidelines. W/Procedure Change Notices 1 & 2 to EPIP-03
ML20212N2671986-07-0303 July 1986
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 5 to EPIP-02, Emergency Classification & Rev 10 to EPIP-03, Notification of Unusual Event Implementing Actions
ML17300A3731986-06-25025 June 1986
Rev 0 to Pump & Valve Inservice Testing Program, for Units 1,2 & 3
ML17300A2611986-05-29029 May 1986
Rev 0 to Inservice Insp Program Summary Manual.
ML20155K1011986-04-17017 April 1986
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 10 to EPIP-03 Re Notification of Unusual Event Implementing Actions & Rev 9 to EPIP-04 Re Alert Implementing Actions.W/Grimsley 860521 Release Memo
ML20206E5991986-04-0808 April 1986
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Index,Cancellation of Rev 2 to EPIP-28, Personnel Monitoring & Decontamination & Cancellation of Rev 2 to EPIP-29
ML17299B1791986-03-11011 March 1986
Public Version of Revised Emergency Plan Implememting Procedures EPIP 11,EPIP 19 & EPIP 20 & Revs 1 to Administrative Procedures 7N409.08.00 & 7N409.09.00, respectively.W/860409 Release Memo
ML17299B0501986-02-21021 February 1986
Rev 2 to Operations Procedure 42AO-2ZZ50, Venting Charging Pumps.
1999-07-14
[Table view] |
Text
SOLID RADWASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION 8408i$ 0277 840807
'DR ADOCK 05000528 PDR A,
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TABLE OR CONTENTS Section Title ~Pa e 1.0 PURPOSE 2.0 DEFINITIONS AND ABBREVIATIONS 3.0 PROGRAM DESCRIPTIONS 3.1 Waste Types 3.2 Process Parameters 3.3 Waste Classification 3.4 Waste Preconditioning 3.5 Verification of Solidification 3.6 Stability Requirements 3.7 Data Sheets 3.8 Record Retention 3.9 Radiological Precautions
4.0 REFERENCES
APPENDICES Appendix A Schematic Plow Diagram Appendix B Radwaste Cement Solidification System
1.0 PURPOSE The purpose of the Process Control Program (PCP) for Palo Verde, Units 1, 2 and 3 is to establish a set of process parameters which will provide reasonable assurance of complete solidification of various liquid radio-active "wet wastes" including resin slurries, evaporator bottoms, filter sludges and chemical drains in accordance with the requirements of appli-cable portions of the Palo Verde Quality Assurance Program, Department of Transportation (DOT) regulations, Nuclear Regulatory Commission (NRC) regulations, licensed burial facilities acceptance criteria, and 10 CFR 61 for solidification, packaging and shipment to an approved off-site burial site. There are no Arizona State Regulations applicable to PVNGS.
Toward this purpose the PCP ensures that the solidified substance is a monolith having no free standing liquid and is within the limits as set forth in the above mentioned regulations and acceptance criteria. This PCP will also ensure solidification will be performed to maintain any potential radiation exposure to plant personnel to "as low as is reason-able achievable" ALARA levels.
2.0 DEFINITIONS AND ABBREVIATIONS
- a. ~SA As low as is reasonably achievable.
- b. Batch A quantity of water type(s) prepared in the waste feed tank for solidification.
- c. Bench Laboratory testing of the solidification process on a Test reduced scale with representative mixing ratios and similar operational techniques.
- d. Wet waste types are liquid radioactive wastes, sludges and 'ion exchanger resins.
- e. Monolith A free standing, solid object.
3.0 PROGRAM DESCRIPTION
- a. Appendix "A" "Schematic Flow Diagram" illustrates the different waste types to be processed by the solidification system. They are listed as follows:
- 1) Chemical regenerative and decontamination waste (evapor-ator concentrates) from a forced recirculation evaporator.
- 2) Boric Acid waste from the Boric Acid Concentrator.
- 3) Bead resin waste as a slurry from the Spent Resin Tanks.
- 4) Chemical Drain Tank waste.
- 5) Spent filter cartridges.
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- b. Typical and atypical wet waste types shall be identified by the "Solidification Process Control" procedure, which provides a record of waste formulations.
c~ When the radiation level of a waste batch is determined to be excessive by ALARA standards, a waste substitute shall be pre-pared in accordance with the "Solidification Process Control" procedure.
3.2 Process Parameters
- a. An acceptable waste product for transfer and disposal in accor-dance with 10 CFR 20.311 for Class A, B and C waste shall be provided by compliance with the "Solidification Process Control" procedure and the "Solidified Radioactive Waste Classification" procedure.
- b. The process parameters for various class-A wastes shall be based on the "Hittman Radwaste Solidification System (cement) topical report, HN R1109 NP, Rev. 4 and the "Solidification Process Con-trol" procedure. These documents establish boundary conditions to provide reasonable assurance that solidification will be com-plete.
C~ For class-A waste types containing concentrations of chemicals that do not fall within the bound of chemical concentrations for which pre-operational solidification tests have been performed by Hittman Nuclear and Development Corporation, acceptable base data for test solidifications shall be developed in accordance with the "Solidification Process Control" procedure.
'd ~ In the event the inplant system is inoperative due to mainten-ance, repairs or modifications, a portable solidification system will be used to process class A, B and C waste types in accor-dance with the vendor's operating procedures and qualified 10 CFR Part 61 Topical Report.
- e. For class-B and class-C waste types a 10 CFR Part 61 qualified solidification process will be used on the installed solid radwaste system in accordance with the "Solidification Process Control" procedure, or a portable solidification system will be used in accordance with the vendor's operating procedures and qualified 10 CFR Part 61 Topical Report.
Process mixing ratios for class-A, B, and C waste types shall be determined for each waste batch in accordance with the "Solidi-fication Process Control" procedure.
3.3 Waste Classification
- a. The "Solidified Radioactive Waste Classification" procedure shall provide PWR scaling factors for identifying specific radionuclides as required by 10 CFR 61.55 "Waste Classification".
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- b. Scaling factors shall be verified or updated annually by waste stream analysis to ensure acceptable standards are maintained for waste classification.
- c. During incident conditions where the use of the existing scaling factors is questionable, the waste shall be classified by corre-lation factors or actual sample analysis in accordance with the "Solidified Radioactive Waste Classification" procedure.
3.4 Waste Preconditionin
- a. The "Operation of Solidification System" procedure shall desig-nate the required mixing/recirculation times and system opera-tions to ensure a representative sample is obtained after chemi-cal addition and prior to process initiation.
- b. Adjustment of the waste solution pH shall be in accordance with the "Operation of Solidification System" procedure.
- c. The "Operation of Solidification System" procedure shall desig-nate when heat tracing is required to ensure chemical suspension.
3.S Verification of Solidification
- a. Solid Radwaste S stem
- 1) The solidification bench tests per Hittman Topical Report Radwaste Solidification (cement) System, HN-R1109-NP, Rev.
4, provides the solidification bench testing base data for the "Solidification Process Control" procedure and class-A waste type.
- 2) 'The solidification bench tests per a 10 CPR Part 61 quali-fied vendor's Topical Report will provide the bench test-ing base data for the "Solidification Process Control" procedure and class-B and C waste type.
- 3) During solidification system operations, additions to the waste feed tank, waste feed pump operations and process mixing ratio adjustment shall be in accordance with the "Operation of Solidification System" procedure.
- i. No additions will be made to the waste feed tank while the tank is being recirculated for sampling or pro-cessing.
ii. The waste feed pump will not be stopped during samp-ling.
- 4) A periodic solidification bench test shall be performed as specified by and in accordance with the "Solidification Process Control" procedure for verification of an accept-able solidification process.
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- 5) If any solidification bench test is found not to be accep-table, subsequent operations and testing shall be in accordance with the "Solidification Process Control" procedure.
- 6) The solidification bench test Acceptance Criteria shall be in accordance with the "Solidification Process Control" procedure.
- 7) Solidification product quality is assured by the performance of the "Operation of Solidification System" procedures.
- b. Portable Solidification S stem The portable solidification vendor will verify proper solidifi-cation of the waste product in accordance with the vendor's operating procedures and Topical Report.
- c. Handling of unacceptable solidified waste containers shall be in accordance with the "Operation of Solidification System" pro-cedure.
3.6 Stabilit Re uirements The "Solidification Process Control" procedure shall identify the stability specifications as set forth in 10 CFR 61.56 "Waste Char-acteristics", and Branch Technical Position ETSB 11-3, Rev. 2, July 1981, "Design Guidance for Solid Radioactive Waste Installed in Light Water Cooled Nuclear Power Plants".
Management'ystems 3.7 Data Sheets
- a. For each solidification bench test actually used for waste pro-cessing, a test data record shall be maintained in accordance with the "Solidification Process Control" procedure.
- b. For each batch solidification process a feed rate determination shall be completed in accordance with the "Solidification Process Control" procedure.
- c. For each batch solidification process, record shall be used for recording the unique batch information in accordance with the "Solidification Process Control" procedure.
- d. For each batch solidification process, a waste classification record shall be completed in accordance with the "Solidified Radioactive Waste Classification" procedure.
3.8 Record Retention i
For each batch solidification proc'ess, all records generated shall be maintained 'in accordance with the "Document and Record Turnover procedure.
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3.9 Radiolo ical Precautions The radiological precautions necessary for implementing the Process Control Program shall be followed and are covered in the "Radiation Protection Program" procedure.
4.0 REFERENCES
- a. NUREG-0472, Radiological Technical Specifications for PWR.
- b. 10 CFR 20, Standards for Protection Against Radiation.
- c. 10 CFR 71, Packaging of Radioactive Material for Transport.
- d. PVNGS Unit One Interim Technical Specifications, Oct. 28, 1983.
- e. 49 CFR Subchapter C, "Department of Transportation Hazardous Mat-erials Regulations".
- f. Palo Verde Nuclear Generating Station Final Safety Analysis Report, Section 11.4, 12.1 and 12.3 (Amendment 12).
- g. "AIBA Program" procedure.
- h. "Operational equality Assurance Program" procedure, Rev. l.
Standard Review Plan 11.4, Rev. 2, July 1981. "Solid Waste Manage-ment Systems" procedure.
"Solidification Process Control" procedure.
- k. "Operation of Solidification System" procedure.
- 1. "Solidified Radioactive Waste Classification" procedure.
- m. "Document and Record Turnover" procedure.
- n. Hittman Radwaste Solidification (Cement) Topical Report HN-R1109-NP, Rev. 4, Apr. 1977,Section VII, "Cement Solidification Process Chem-istry".
- o. Branch Technical Position ESTB 11-3, Rev. 2, July 1981, "Design Guidance for Solid Radioactive Waste Management Systems Installed in Light Water Cooled Nuclear Power Plants".
- p. 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste".
- q. "Radiation Protection Program" procedure.
APPENDIX A EVAPORATOR CONC NT ATE MONITOR TANKS WASTE FEED TANK CHEMICAL DRAIN TANKS CEMENT AND ADDIT VE WASTE/CEMENT PROCESSOR SPENT DRUM OR RESIN LINER TANKS SPENT FILTER CARTRIDGES SCHEMATIC FLOW DIAGRAM
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APPENDIX B CEMENT TANK ADDITIVE ROTARY VALVF ADDITIVE FEED CONVEYOR CEMENT ROTARY VALVE INPUTS AND CONVEYOR MIXER WASTE FEED TANK WASTE l CEMENT PROCESSOR DRUM OR LINER RADWASTE CEMENT SOLIDIFICATION SYSTEM
a A
