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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction RBG-44355, Cycle 8 Startup Physics Test Summary1998-01-19019 January 1998 Cycle 8 Startup Physics Test Summary ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 1999-07-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20076K9161994-10-27027 October 1994 Updates to IST Pump & Valve Program Manual ML20059A8501993-12-23023 December 1993 Near-Term Performance Improvement Plan ML20128D9221993-01-29029 January 1993 Rev 6 to Pump & Valve Inservice Testing Plan for River Bend Station First 10-Yr Insp Interval ML20045E0311992-08-19019 August 1992 Change 92-01 to Rev 3 to RSP-0008, Odcm. ML20114D0711992-08-19019 August 1992 Rev 3 to Odcm ML20086G8411991-10-0202 October 1991 Rev 5 to Inservice Insp Plan for River Bend Station - Unit 1 ML20082M0061991-08-0909 August 1991 Rev 4 to RWS-0204, Radwaste Processing Control Program RBG-35-380, Rev 5B to River Bend Station Pump & Valve Inservice Testing Program Plan. Relief Requests Encl1991-07-26026 July 1991 Rev 5B to River Bend Station Pump & Valve Inservice Testing Program Plan. Relief Requests Encl ML20029B7841991-03-0606 March 1991 Station,Inservice Insp Plan,Summary Rept Refuel Outage RF-3 Second Period,First Interval, Vols 1 & 2 ML20070U7721991-02-26026 February 1991 Rev 4 to River Bend Station Inservice Insp Plan (First Interval) ML20245F0101989-04-24024 April 1989 Rev 2 to Offsite Dose Calculation Manual ML20114B7411989-03-0808 March 1989 Rev 5 to Procedure RWS-0304, Radwaste Handling & Control ML20245F0041989-02-14014 February 1989 Rev 3 to Offsite Dose Calculation Manual Procedure ML20154C9851988-08-16016 August 1988 Rev 3 to Inservice Insp-First Interval ML18053A7101988-03-22022 March 1988 Rev 5 to Pump & Valve Inservice Testing Plan,First 10 Yr Insp Interval. W/880422 Ltr ML20238C3651987-08-13013 August 1987 Rev 1 to Station Operating Procedure RSP-0008, Offsite Dose Calculation Manual Procedure RBG-26506, Rev 4 to Pump & Valve Inservice Testing Plan River Bend Station First 10-Yr Insp Interval. Fee Paid1987-07-29029 July 1987 Rev 4 to Pump & Valve Inservice Testing Plan River Bend Station First 10-Yr Insp Interval. Fee Paid ML20235Y0591987-07-16016 July 1987 Rev 2 to Radwaste Processing Control Program RBG-26044, Rev 2 to Inservice Insp Plan - First Interval1987-06-0202 June 1987 Rev 2 to Inservice Insp Plan - First Interval ML20114B7281987-05-14014 May 1987 Rev 3 to Procedure RWS-0307, Radwaste Segregation RBG-25841, Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual1987-04-30030 April 1987 Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual ML20114B7311987-03-16016 March 1987 Rev 2 to Procedure RWS-0207, Radwaste Shipping Criteria ML20209G3121987-01-0202 January 1987 Rev 3 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval ML20214T6231986-09-11011 September 1986 Revised Emergency Plan Implementing Procedures,Including Rev 5 to EIP-2-007, Protective Action Recommendation Guidelines & Rev 4 to EIP-2-024, Offsite Dose Calculations Manual Method ML20214N6811986-08-0606 August 1986 Rev 2 to Pump & Valve Inservice Testing Plan,First 10-Yr Insp Interval ML20207E8711986-07-0202 July 1986 Vol 1 to Rev 1 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval ML20206J1501986-06-20020 June 1986 Rev 4 to River Bend Station Unit 1,Preservice Insp Plan, Final Update ML20238C4141986-05-18018 May 1986 Rev to Nonradioactive Oil/Hazardous Matl Spill Prevention, Control & Countermeasure Plan ML20155G5391986-02-26026 February 1986 Station,Emergency Response Exercise Manual, Evaluated Exercise RBG-22-117, Rev 3 to Offsite Dose Calculation Manual1985-09-16016 September 1985 Rev 3 to Offsite Dose Calculation Manual ML20135A6331985-06-27027 June 1985 Revs to Nuclear Plant Engineering Preservice Insp/Pump & Valve Testing Plan, Replacing Pages 4 & 5 & App F RBG-21363, Rev 0 to Station Operating Procedure ADM-0053, Asiatic Clam Control Program1985-06-21021 June 1985 Rev 0 to Station Operating Procedure ADM-0053, Asiatic Clam Control Program ML20135A9211985-06-17017 June 1985 Rev 1 to OSP-0007, Preparation of Operations Sections Procedures ML20125D2751985-06-10010 June 1985 Updated Rev 1 to Nuclear Plant Engineering Preservice Insp/Pump & Valve Testing Plan ML20129E9531985-06-0606 June 1985 Rev 2 to Station Operating Procedure ADM-0022, Conduct of Operations ML20117P4831985-05-30030 May 1985 Rev 1 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval RBG-21545, Rev 2 to River Bend Station Offsite Dose Calculation Manual1985-05-27027 May 1985 Rev 2 to River Bend Station Offsite Dose Calculation Manual ML20128E8881985-05-17017 May 1985 Revised Program Plan for Tdi Standby Diesel Generators ML20117P1431985-05-13013 May 1985 Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage RBG-21-165, Rev 1 to, River Bend Station Offsite Dose Calculation Manual1985-04-24024 April 1985 Rev 1 to, River Bend Station Offsite Dose Calculation Manual ML20129E9591985-03-27027 March 1985 Rev 1 to Station Operating Procedure AOP-0001, Reactor Scram ML20112G4641985-01-0707 January 1985 Offsite Dose Calculation Manual ML20112G4491985-01-0707 January 1985 Rev 0 to Procedure RWS-0204, Process Control Program 1999-01-08
[Table view] |
Text
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. RIVER BEND STATION 4
APPROVAL SHEET
,, STATION OPERATING PROCEDURES l NO. RWS-0307 TITLE RADIOACTIVE WASTE SECREGATION
- 5. ITT RELATED
~
YES ] NO]
TECHNICAL REVIEW REQUIRED YES [ ' NO REV. PAGES INDEP. TEJ.
NO, ISSUED REVIEW REVIEW APPROVED BY EFFECT P'GRATURE/DATE SIGNATURE /DATE -SICRATURE/DATE DATE j 0 1 THRU 10 e b j.88 l
i 3/6/S S 8YW$Y Nf4(
l 1 Thru 8 j/ Y# 05-03-85 2 1 Thru 5 // 3.p .rt,, 10/22/86 3 I Thru 6 ,; . C - N A s/,zg,? r *' f/<v/r/ 05/14/87 FOR INFORM 5Tl0N ONLY issm i
j JUL0 1987 I i
I STATION DOCUMENT CONTROL f. ._
RECElvED ,
ppy 141987
! SDC 1
4 1
h I
920e320144 911223 PDR FOIA SHINKLE91-440 PDR
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i p,.,
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l RAEI0 ACTIVE LASTE SEGREGATION l
t I
l- TABLE OF CONTE \TS l l
1 i
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1 l SECTION PAGE'NO. l l
1 l 1.0 PURPOSE / SCOPE / APPLICABILITY 2 i l
I l
2.0 REFERENCES
2 l I
l 1 3.0 DEFINITIONS 2- l l
1 l l. 0 PEQUIRED EQUIP.'IENT 2 l I
l 5.0 PRECALTIONS l-3 l 1
I l 6.0 lit!ITATIONS 3- 1 I
l 7.0 I PREREQUISITES / INITIAL CONDITIONS 3 l l
1 8.0 l PROCEDURE / INSTRUCTIONS / REQUIRE.9ENTS 3 l 1
l l 8.1 Inplant Gross Segregation 3 l l 8.2 DAWSF Segregation a 8.3 l
} Non-Compactable Trash 5 S.4 l-l Contaminated Oily Waste 5 l l S.5 Harardous Waste .5 l l
- I l 90 RESTORATION 6 l l I
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i I I 11 -l i l i i 11 ( l l l l ll RWS-0307 l REV - 3 l PAGE 1-OF 6 l l I 11 l l I a-
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!. 1.0 PURPOSE / SCOPE / APPLICABILITY 1
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- 1.1 This procedure establishes recommended methods for the l segregation and sorting of radioactive waste, non-radioactive l waste, hazardous waste and mixed waste.
j
2.0 REFERENCES
i 2.1 RWS-0203, Personnel Qualifications for the Radwaste Section l
2.2 RWS-0304, Radioactive Wa.te Handling and Control l 2.3 RWS-0209, Conduct of Radwaste Vendor Services l
- 2.4 RWS-0310, Operation of the Nuclear Packaging Mode) WC-18000 Waste i Compactor
! 2.5 RSP-0200, Radiation Work Permits I
J 2.6 RSP-0213, Control and Handling of Radioactive Material l 2.7 RPP-0006, Radiological Surveys l
l 2.8 IE Information Notice No. 87-03, Segregation of Hazardous and
} Low-Level Radioactive Wastes 2.9 ADM-0038, Radioactive Waste Management Program '
! 2.10 ADM-0043, Radwaste Management Plan l
2.11 RBNP-020, Statement / Directive No. 9.
3.0 DEFINITIONS
{ 3.1 Hazardous Waste - As pertaining to River Bend Station and
- originating from the Radiologically Controlled Area-, Hazardous
- Wastes are defined as oils, synthetic lubricants, paints, sealers, strippers, cleaners, deconagents, lead or leaded j compounds.
, 3.2 Mixed Waste - Waste containing both ' radioactive'and hazardous
- properties.
4.0 REQUIRED EQUIPMENT j NOTE All or some of the following may be needed te perform this 4
procedure.
4.1 Absorbant Material /Dessicant 4.2 Yellow drums i
RWS-0307 REV - 3 PAGE 2 0F 6 4
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i f: 4.3 -Green drums i
j 4.4 iellow bags for contaminated waste
! 4.5 Red bags for potentially contaminated waste 1
f 4.6 Strong tight packages for non-compactables iP
{ 4.7 Radiation detection equipment having sensitivities compatable I with the release limits established in Reference 2.6. <
- 4 Hazardous Waste Labels for identification of Hazardous Materials.
I
! 5.0 PRECACTIONS T
5.1 Do not inadvertently release radioactive material. .
] 5.2 Containers for trash, contaminated clothing, et~.. should be
! labeled to indicate their contents.
$ 5.3 Wet Radwaste materials are to be dried or pcckaged with 4
i sufficient absorbant to absorb twice the volume oJ liquid in the material prior to permanent disposition, i
NOTE 4
i When in an RCA, wet material should not be placed in a-
{ contaminated waste container unluss it has been sealed in i seperate plastic bags to prevent water absorption by dry
{ materials. -
i
, 5.e Follow the access requirements of the appropriate RWP when-l ;erforming work in a Radiologically Contro led Area (RCA) to
- . maintain exposure ALARA. ,
i l 5.5 Tr<nsoort and handle radioactive material in-accordance with
- Refer nee 2.6.
?
6.0
~ .
LIMITATIONS i *
{ 6.1 All Radwas c segregat;.a should be done by personnel
- knowledgeabic in radwaste volume reduction. ~ Training j requirements are stated in Reference 2.9, 2.10 and-2.11.
e
- . 7.0 PREREQUISITES / INITIAL CONDITION j S/A i
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I RWS-0307 REV - 3 PAGE 3 0F 6
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4
, o.0 F ROCE!' t.E INFT'40CT!CNS. REQUIRD!ENTS 5.1 :2nt Gross Segregation 1 All personnel entering the RCA and generating waste shall be responsible for segregating trash ard placing in the appropriately color coded receptacle in secordance with I.eference 2.6. Training requirements are stated in References 2.9, 2.10 and 2.11.
8.1.2 The Radwaste Supervisor or designee should perform spot-checks throughout the RCA during peak periods.
Discrepancies should be documented in the Radvaste Volume Reduction Discrepancy Log. Contact responsible individuals for resolution.
8.1.3 Bags of trash should be inspected and initially segregated prior to removing them from the control point at a work area as follows:
- 1. Vet vaste should be segregated and throughly dried in the wet waste drying area. When completely dried, the waste shall be handled as DAV.
- 2. Inspect the bag (s) before_ taping shut for hara.f3us waste, non compactable objects and reusable items.
(i.e. oils, paint, lead, tools, respirators, PC's, etc.)
- a. If hazardous wastes, are found notify the Radwaste Specialist. I
- b. Place non compactable objects in designated
- containers. !
k
- c. If reusable item are found notify the Radwaste Specialist.
- 3. Transport radioactive material thru the RCA in accordance with Reference 2.6.
6.1.4 Fadwaste collected in red bags and yellow bags reading $2 e
r should be transferred to the segregation trailer for processing.
5.1.5 Radwaste collected in yellow bags reading >2 mr/hr but
$10 mr/hr should be pre screed to remove dose contributing material.
8.1.6 Radwaste collected in yellow bags reading >10 mr/hr should be transferred'to.the compaction area for packaging in accordance with Reference 2.4.
RVS-0307 REV - 3 PAGE 4 0F b i
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l$ S.2 & ;r n 2tien Facility i 1 21 The Segregation Facility is capable of separating clean l 1
waste from radioactive waste generated within the ,
l Radiologically Controlled Area. Vaste are presorted to !
- remove non-shredables, wet and hazt.rdous wastes prior to processing. Several sensitive radioactivity detection i
processes are utilized to prevent the release of i contaminated materials. In addition the clean waste is l shredded and packag:d for disposal. The facility may
- also be used to screen wastes originating from outside the RCA utilizing the bag monitor.
l 1 8.2.2 The facility may be operated by a vendor under an l i approved contract in accordance with Reference 2.3. -
l S.2.3 Strong tight containers will be staged for vastes entering and leaving the Segregation Facility. Clean wastes leaving the facility will be taken to normal refuse disposal.
8.3 Non-Cppactable Trash i
8.3.1 Non-compactable trash shall be surveyed for loose surface l and fixed contamination.
8.3.2 If loose surface and fixed contamination are within the
- release limits of Reference 2.6 the material shall be tagged for release as cican.
l 8.3.3 If loose surf ace and/or fixed contamination is above the release limits of Reference 2.6 the material shall be decontaminated by wiping, grit blasting, abrasive gr ding, or other acceptaM e methods, if practical, tay.ged and released as clean.
8.3.4 If unable to decontaminate or if decontamination is_
impractical, the material should be packaged with absorbent material, surveyed and stored in the DAWSF for shipment as radwaste.
S . J. "'ra.taminated Oily Vaste S.a.1 Contaminated rags, paper, etc. that are saturated with oil will-be placed in the oily trash staging area for special processing to remove as reuch oil as possible.
8.4.2 Contaminated wastes from this process shall then be packaged in sufficient oil absorbent to eliminate twice the volume of oil in the waste.
S.4.3 Packages should then be surveyed and stored in the DAWSF for shipment as Radwaste to an approved burial site.
RWS-0307 REV .3 PAGE 5 0F.6-
Free standing oil shall be processed using the latest most efficient technology and shipped to an approved burial site.
6.5 ;a:ardous Vastes 8.5.1 Hazardous Wastes, as defined in Section 3.0, originating from within the RCA will be separated from other waste types and analyzed for radioactivity content.
B.5.2 If approved for release from the RCA by the Radiation Protection department the material will be fowarded to the Hazardous Vaste yard for disposal by Environmental Services.
B.5.3 Hazardous wastes found to be contaminated will be fowarded to the Radwaste Department for identification and separation as mixed waste.
9.0 RESTORATION N/A "END" RVS-0307 .REV 3 PAGE 6 0F 6-
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