IR 05000309/1985004
| ML20135F910 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/06/1985 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Randazza J Maine Yankee |
| References | |
| NUDOCS 8509180014 | |
| Download: ML20135F910 (2) | |
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SEP 0 61985
Docket No. 50-309 License No. DPR-36 Maine Yankee Atomic Power Company ATTN: Mr. J. B. Randazza Vice President Nuclear Operations 83 Edison Drive Augusta, Maine 04336 Gentlemen: Subject: Inspection Report No. 50-309/85-04 This refers to your letters, dated April 30, 1985, June 3, 1985, and August 22, 1985, in response to our letter dated March 26, 198 Thank you for informing us of the corrective and preventive actions documented in your letters. These actions will be examined during a future inspection of your licensed progra With regard to Item B concerning the review and approval of procedures by station management, your letter dated June 3,1985, indicated that the vendor procedures in question had been incorporated by reference into station proce-dures that had been appropriately reviewed and approved. This citation is withdrawn and our records will be amende No reply to this letter is required. Your cooperation with us is appreciate
Sincerely, Original sisced BY 8 3CrrKL d. b d% l Thomas T. Martin, Director Division of Radiation Safety and Safeguards cc: C. E. Monty, President C. D. Frizzle, Assistant Vice President / Manager of Operations J. H. Garrity, Plant Manager P. L. Anderson, Project Manager G.' O. Whittier, Licensing Section Head J. A. Ritsher, Attorney (Ropes and Gray) Public Document Room (PDR) local Public Document Room (LPDR) Nuclear Safety Information Center (NSIC) NRC Resident Inspector State of Maine N OFFICIAL RECORD COPY RL MY 85-04 - 0001. /29/85 I I 8509180014 850906 PDR ADOCK 05000309 G PDR , ', L-
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April 30, 1985 MN-85-82 GDW-85-128 aegion i United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator References: (a) License No. DPR-36 (Docket No. 50-309)
(b) USMC Letter to MYAPCo. dated May ll, 1983 (c) USM C Letter to MYAPCo. dated March 26, 1985 - Inspection Report 85-04 Subject: Inspection 85-04 - Radioactive Materials Transport Program Gentlemen:
This letter transmits Maine Yankee Atomic Power Company's response to inspection 85-0 This response addresses the specific violations identified, and provides Maine Yankee's respons Notice of Violation A c-10 CFR 20.311(d)(3), " Transfer for disposal and manifests" requires a licensee who transfers radioactive waste to a land disposal facility to conduct a quality control program to assure compliance with 10 CFR 61.55 and 10 CFR 61.5 Contrary to the above, on July 19, 1984 and August 17, 1984, the licensee transferred two shipments of radioactive dewatered resin to the Chem-Nuclear, Inc. land disposal facility at Barnwell, South Carolina and the licensee did not conduct a quality control program to assure that the packages did not contain free standing liquid greater ttpa 1% of the waste r ' volume, that the waste was properly classified, and that the waste was structurally stabl J , This is a Severity Level IV violation (Supplement V).
l ' Maine Yankee Response
In response to the WC's guidance regarding implementation of 10CFR61, l Reference (b), Maine Yankee submitted a description of our program for l 10CFR61 implementation. This' program description-is attached for your,
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, MAINE YANKEE ATOMIC POWER COMPANY . i United States Nuclear Regulatory Commission Page Two Attention: Dr. Thomas E. Murley, Regional Adninistrator MN-85-82 We believe that we meet the requirements of 10 CFR 20.311 through
- administrative controls such as the 0QAD QA Program, implementing procedures, radioactive waste shipping procedures and department policies. We do not maintain a single document labeled the Radiological Controls QC Program, however due to the confusion this may have led to, we plan to explore the development of such a documen Maine Yankee maintains the following administrative controls which we believe meet the spirit and intent of the 20.311 requirement for quality
! control of the radioactive waste transport activitie ~ Radioactive waste shipping activities at Maine Yankee are governed by procedures. The following procedures were used for the shipment referenced in the inspection report:
o Operations Procedure 1-18-4, Spent Resin Storage and Processing - This procedure is used, in part, to ensure the waste shipment is dewatered to less than 1% (10 CFR 61.56).
The procedure requires Operational Quality Assurance Department
: (0QAD) personnel check waste container liners for free standing -
water prior to covering the liner. Procedure 1-18-4 also requires y the dewatering pump be run for one hour after continuous flow is y A i lost. This step was verified by Maine Yankee's Radiological Waste Coordinato o Radiological Controls Procedure 9.1.15, Shipment of Radioactive Material - This procedure covers packaging of radioactive materials and all preparations for shipment of these materials including Radiological Controls Department and OQAD signoffs.
, j At the time of the shipments cited in the inspection report, this , procedure required 0QAD personnel inspect all solidified or ' dewatered containers to ensure that there is no detectable free standing liquid (10 CFR 61.56). The procedure has recently been ~
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revised and it now requires 0QAD verification of the following: $.
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oo Liquid content of the waste is less than 1% of the volume of the waste if the container is designed to ensure stability (10 l CFR 61.56). j
oo Liquid content of the waste is less than 0.5% of the volume of the waste if the waste is processed to a stable form (10 CFR 61.56).
. o Chemistry Procedure 7-05-1, Operation of Canberra Series 80 l Multichannel Analyzer - This procedure is used to determine i isotopic content of gamma emmitters in radioactive waste.
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, MAINE YANKEE ATOMIC POWER COMPANY
, .- United States Nuclear Regulatory Commission Page Three i i Attention: Dr. Thomas E. Murley, Regional Adninistrator M-85-82 '
* Chemistry Procedure 7-05-6, Operation of the Packard Model 4430 Liquid Scintallation Counter - This procedure is used to determine
, the tritium content in the radioactive waste.
, Chemistry Procedure 7-05-1 and 7-05-6 are used to determine the i l isotopic content of the waste being shipped. This information, in '
- conjunction with the scaling factors determind by SA1, ensure ,
{ proper classification of radioactive waste (10 CFR 61.55).
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Chemistry Procedure 7.102, Process Control for In-Container : ' Solidification of Evaporator Bottoms - This procedure is used to , i determine the correct amount of cement and additives necessary to > ensure a structurally stable waste form and requires independent 7 ) verification of product stability (10 CFR 61.56)'.~~ - l Maine Yankee Radiological' Controls and Chemistry administrative ] practices ensure radiological waste is properly classified.
f -b* Annually, Maine Yankee sends samples to Science Applications, Inc.
! (SA1) to determine the approprite scaling factors to predict the " { isotopic content, (10 CFR 61.55). The scaling factors are ;
incorporated into Procedure 9.1.15 and any updates are immediately reflected in the procedur , j- * Internal Radioactive Waste Program quality assurance audits are i done on an annual basis.- One portion of this audit is to verify l that the waste classification method is proper (10 CFR 61.55).
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{ 10 CFR 61.56.b.1 states, in part, "(s)tructural stability can be ' provided by ... placing the waste in a disposal container or- ;
- - structure that provides stability after disposal." Maine Yankee
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packaged and shipped the radioactive waste mentioned in the report in HIC shipping containers. The HIC container is commonly used throughout the industry, and the container's stability has been evaluated and is considered acceptable (Barwell License #097,
- Amendment 41, Condition 398 and !@C Branch Technical Position f 5-11-83).
i l For the reasons mentioned above, Maine Yankee believes we meet the intent
- of 10 CFR 20.311.d.3 and request reconsideration and either vacating or l downgrading the severity of this violation.
Notice of Violation B' i i ' Technical Specification 5.8.1 " Procedures", requires that procedures be established, implemented and maintained covering the applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,197 Regulatory Guide 1.33 requires procedures for spent resin handlin Technical Specification 5.8.2 states "Each procedure of 5.8.1 above, and j changes thereto, shall be reviewed by the PORC and. approved by the Plant i Manager prior to implementation..."
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United States Nuclear Regulatory Commission Page Four Attention: Dr. Thomas E. Murley, Regional Adninistrator MN-85-82 Contrary to the above, the licensee used a vendor procedure (Westinghouse ResininHittmanRADLOKgMHittman 100 or Nuclear Inc. Pro edure
- 200 Containers with STD-P-02-010, Single Layer Transfer and De Underdrain Assembly to Less Than 1% Drainable Liquid), in preparing the two shipments of dewatered resin that were made on July 19, 1984 and August 17, 1964, and the procedure was not reviewed by the PORC and neither was it approved by the Plant Manager prior to its implementation.,
This is a Severity Level IV violation (Supplement V).
Maine Yankee Response B As stated (in the notice.of violation,1 Maine: Yankee used portions of a
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Vendor procedure in preparing the two shipments of dewatered resin.' ' The portions of Hittman Nuclear Inc. Procedure No. STD-P-03-010 used for the shipments were incorporated in Maine Yankee Operations Department Procedure 1-18-4 by Procedure Change Report Numbers 84-520 through 84-52 . e The procedure change report (PCR) is used for temporary changes to procedures to direct activities or provide guidance in an unusual - situation not covered in normal procedures. The PCR permits a procedure change without prior review by the Plant Operations Review Committee (PORC) and prior approval by the Plant Manager provided the intent of the original procedure is not altered, the change is approved by two members of plant management (at least one must hold a Senior Reactor Operator's License), and the change is reviewed by PORC and approved by the Plant Manager within fourteen days of implementation. This assessment was accomplished for PCRs 84-520 through 84-524 on July 12, 1984, PORC reviewed the procedure changes and the Plant Manager approved the changes on July 19, 1984. The PCRs were incorporated as a permanent changes to Procedure 1-18-4 on August 10, 198 Maine Yankee has made recent policy changes to limit the use of procedure change reports. Although we do not consider this citation to be a violation of Technical Specifications, we believe our current PCR policy should prevent this item from recurrin Very truly yours, MAltE YAtKEE ATOMIC POWER C0WANY t bW G. D. Whittier, Manager Nuclear Engineering & Licensing GDW/bjp cc: Mr. James R. Miller Mr. Cornelius F. Holden i ,
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MAIRE ~ HARHEE M0ml0POWERComPARHe AUGUSTA, MAINE 04336 i
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June 3, 1985 O MN-85-105 GDW-85-159
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Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Tnomas E. Harley, Regional Administrator Referer.ces: (a) License No. DPR-36 (Docket No. 50-309)
(b) MYAPCo Letter to USf6C dated April 30, 1985 (MN-85-82)
Subject: Inspection 85-05 - Radioactive Materials Transport Program Gentlemen: ' ihis letter provides additional information regarding our response to the subject inspection report as requested by Mr. P. Clemons of your staff.
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- Attachment A provides a copy of our letter to USNRC describing A Maine copy of this Yankee's program for implementation of 10 CFR 61 requirement letter was iriadvertently omitted from our earlier response, Reference (b).
A copy of PCR's 84-520 through 84-524 and a copy of Procedure 1-18-4 are also attached as Attachments B and C respectively, at the request of Mr. Clemon ' These documents were referenced in Reference (b) in our response to Notice of Violation B. These documents should be considered as additional
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information since they apparently were not brought to Mr. Clemens' attention during the inspectio Please feel free to contact me if you should have any additional question in this matte Very truly yours, MAINE YANKEE ATOMIC POWER COWANY t h G. D. Whittier, Manager Nuclear Engineering & Licensing GDW/bjp Attachment: 1, r rf {n l $)& 2 - - cc: Mr. James R. Miller O"r -
"<fT Mr. Cornelius F. Holden p,
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- 4 December 22, 1983 MN-83-268 GDW-83-149 p ;u yus2
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.- MO NSIBILITY Directcr of Nuclear Reactor Regulation United 5tates Nuclear Regulatcry Commission NE F.ESPOND BY _
Washington, D. C. 20555
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Attention: Mr. James R. Miller, Chief NRC DUE DATE
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Operating Reactors Branch No. 3 Division of Licensing References: (a) License No. DPR-36 (Docket No. 50-309) Subject: Request for Review of 10 CFR 61 Implementation Program - Gentlemen: Maine Yankee Atomic Power Company has developed a program for implementation of the 10 CFR 61 requirements on waste form and waste classification, effective December 27, 1983. This program is being submitted
{' for your review and concurrence as an adequate means of implementing these requirement It is anticipated that most process wastes to be shipped from our facility will not exceed the concentration limits listed in 10 CFR 61.55 for Class A wastes. It is our position that wastes solidified in accordance with our program, er placed within a certified high integrity container, are '
sufficiently stable such that they will not affect overall dispesal site stability, and need not be segregated upon disposal, irrespective of / j classificatio All operations described in this program will be conducted in accordance with fully approved plant procedures. The waste solidification system, supplied by Hittman Nuclear, will be operated in full conformance with their process co. trol progra Very truly yours, MAINE YANEE ATOMIC POWER COWANY J3 b- tw3.% G. D. Whittier Licensing Section Head GDW/bjp Enclosure: i ,
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cc: Dr. Thomas E. Marley e -m D ! Mr. Corneluis F. Holden hY) , _ , , l 2190t-rwsg( , gj j o . -
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MA1NE YANG E
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10 CFR 61 IPLEMENTAT20N PROGRAM k WASTE' STREAMS ,
. Evaporator Concentrates Exhausted Resins Cartridge Filters . Compactible and Non-Compactible Dry Active Wastes (OAWs) WASTE FORMS F . - Stable Wastes -
In order to preclude trench subsidance after disposal, wastes must have structural stabilit Such waste must generally maintain its physical dimensions under expected disposal conditions. Stability can be assured by either the waste form itself or the waste containe ' Two options are available to assure stability: Currently, a Hittman Nuclear portable cement system is utilized to solidify evaporator bottoms in accordance with approved
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procedures and Process Control Program (PCD).
' Exhausted resins can either be processed by the above cement
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system or loaded into approved High Integrity Containers (HICs).
' Cartridge filters are stabilized in concrete in either drums or liners or placed in HIC . Other Wastes ,
; --ADAW is low in activity and generally will be classified as " Class A Wkk
waste" requiring segregation upon disposal. These wastes will be V packaged within " strong, tight containers". (49 CFR 173.24)
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Compactible wastes will be processed with a hydraulic box compacto to reduce volume and increase density to the maximum extent j practicable. All waste processing and packaging will be in ! compliance with approved plant procedures.
i WASTE CLASSIFICATION ,
. As a minimum, all radionuclides required by 10 CFR 20.311 and 10 CFR 61.55 will be reported.
! A sample of each processed waste batch (concentrates, resin, filter) will be analyzed for gamma emitters. Tiie quantity of all major
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, 1 - contributors will be reported for each container. The isotopic , ,
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distribution contained in DAW will be based on the evaporator l concentrate . Gamma emitters not detected in (2) above, but required to be
. reported, will be reported as "below the lower limit of detection" (LLD). LLO values for radionuclides will be reported as required.
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10 CFR 61 IHoLEMINTATTON PROGRAM (, ,
(continueo) .. Non-gamma emitters required to be reported will be reported using scaling factors, where applicable. These scaling factors are currently. based upon a data base developed under a cooperative , program with the NRC and SAI and modified as the data base expand . Radioisotopes requiring reporting, which are not easily measured or ,
correlatable, will be reported based upon the methods described in the AIF ESP Report, " Methodologies for Classification of LLW From ' Nuclear Power Plants", November 198 . One sample, typical of each waste stream, will be fully analyzed annually until it is demonstrated to be unnecessary, to ensure the
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validity of the factors being utilize . Gross changes in waste stream radionuclide concentrations or ratios will require a reevaluation of the classification methods and will be
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addressed as the situation arise .
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l . A copy of this cac t shall te attachec to the af fe:te ' ;;c:ecure enc the ) criginsi shall be settittet to the Eccretary of FCR* Dy t'.e ce ar cent wnien i initiatec the change. C ce ent changes will not r,e s?*a:ne: to *n- aoplicacic ( prints, but sna11 te :t.:,t.itt<sc t the Se:retary cf rCA rc:t no. C-Ofs-2-3 ! ,
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A copy of this :e;crt shall be atta*hed to the affe-tec ; c:ccu:e and the original shall te sutrittec c the Eccreta:y cf CRC by t*te :ecarteent wnicn initiatec *.e enange. C=v ca.t changes will not .w c-*c:ne: to -e acclicaole
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COMPLETED: Dept. Head h , Proc. No. 1-18-4
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Plt. Mgr. ru Clas A DATE/ TIME PORC W Rev. No. 12 Mgr. of Ops r X S Issue Date 5-10-84 CJ P.S.S. REVIEW Review Date 5/86 1-18-4 SPENT RESIN STORAGE AND PROCESSING 8)fj MFORIAATIOff N i s .. DISCUSSION ,_ ..e.,,_ - . _ - - . This procedure provides the operator with specific steps required to store,' condition and solidify Spent Resin R 4.0 Spent Resin Conditioning in the Waste Resin Storage Tank TK 85 & Resin teldup Tk-109 4.1 Spent Resin Concitioning in TK-85 and Water Transfer to TK-109 4.2 Resin & Water Transfer from TK-85 to TK-109 4.3 Dewatering Resin Holdup TK-109 4.4 Resin Transfer from TK-85 to Liner 4.5 Transfer' of Resin from TK-109 to Liner , F - 1.0 CSICTIVE To store, condition and prepare Spent Resins for processin To pr'ocess Spent Resins to achieve a free standing solid in a suitable shipping containe .0 FRECAUTIONS 2.1 Always coserve the radiation reading in mr/hr on the panel prior to entrance to the Waste }tioup Tank Cubicle. Personnel should have a radiation survey meter when entering this cubicl .2 Be aware of high radiation levels in waste resin storage area, RCA, and waste holcup tank during these ope * ration .3 Ensure there is room in the ADT's to receive water when cewatering TK-109 to the ADT's.
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Proc. No.1-18-4 Rev. No. 12 Page 2 of 15 s . 2.4 When operating the dewatering pump, ensure oiler in air supply is ful .0 INITIAL CONDITIONS INITIALS 3.1 Ensure that the RCA Storage Building Ventilation System is in operatio .2 Proper plastic, paper or canvas has ceen applied to the RCA Building floor or Decon Pad to assure that the truck trailer or container is not contaminate .3 A Radiation Work Permit has oeen octaineo for all phases of solidification / Resin Transfe .4 Spent Resin has been sluiced to the Waste Resin Storage Tank for storage and deca . 3.5' Fill out batch report attached and return to H Ensure PEQAG nas checked liner for free standing water prior to covering up line .6 Ensure all outside doors to the RCA are closed when waste is bein processed.
, 3.7 Feve the Chemistry Dept. sample the waste holdup tank Dottom ~ NOTE: Chemistry must have activity levels for cask shipping recorc .8 To prevent rupturing FL-90 when starting the oewatering pump, (P-145) ensure it has a discharge path, and air regulator is set at 15 psi or les . 3.9 Obtain or manufacture a rig for determining water content in cask via
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cewatering pump (P-123) discharge.
! 3.10 vendors procedure available for us ' 3.11 Flexible hose is connected to WSS-91 and WSS-72 for resin fill and dewaterin * NOTE: Douole hose clamps snall De used to connect flexible hose to system.
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Proc. No.1-18 4 *
* Rev. No. 12 Page 3 of 15 INITIALS 3.12 Assure that the Waste Solidification System Flush Tank, TK-80, level "
within the operating bano as incicated oy the Level Gage Glas Keep water level in the REO ZON .13 Assure that the Waste Solidification System Flush Tank TK-80 is pressurized to 85-100 psig and is open to the Service Air Syste .13.1 If makeup to TK-80 is necessary, open PW-17 to admit primary water and maintain TK-80 pressure at 100 psig by throttling the mufflec vent, SA-20 , 3.14 Assure that the main Flush Water Isolation Valve, WSS-65 is ope NOTE: This valve should De left ope . 3.15 Assure that the main Instrument Air Isolation Valve, IA-201, is ope NOTE: This valve is locateo behind the RCA Storage Building Condensate Return Uni R 3.16 Ensure P-108 suction aligned to TK-8 '
- NOTE: RS-14 is located in a High Radiation, Airborne Acitivity Area and oces not have a reach rod. This valve is visible from above and should be checked in this manne .
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Proc. No. 1-18-4 Rev. N ! - Page 4 of 15 4.0 SPENT RESIN CONDITIONING IN THE WASTE RESIN STORAGE TANK / RESIN HOLOUP TAtK , DISCUSSION
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ibis section gives two methoos of transferring and processing resin. The old
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method of transfer to the radwaste holoup tank (TK-85) allows no means of returning the decant back to the ADT's. The new method allows transfer of water and resin to the resin holdup tank (TK-109) from TK-85. The resin may then be transferred to TK-95 for solidification or directly to a line The water MET be pumpea to the ADT's or TK-85.
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- The maxiasn capacity of TK-85 is 100 ft3 of resin or three charges. This
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assures that the resin level is below the 3 inch s]uice line. Normally.
processing of resin should be considered when two charges have been stored in TK-85 for at least 90 days and longer if possibl The maximum capacity of TK-109 is 704 ft3 of resin or 22 charges. 01 arts at 1 rear of this proceadre ano at TK-109 correlate tank level witn number of charges and gallons of water to tank leve NOTE: Prior to transferring spent resin to the Spent Resin Storage Tank (TK-85), the water level in the Spent Resin Storage Tank
; must be reouced to achieve a pumpable slurry. This will_be accomplishea by recircing the spent resin bed for 30 minutes with j ("
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the SCREEN PLUG CLOSED. After this operation, the excess water will oe pumpeo to TK-109. After this operation has been
1 accorro11shed, the spent resin is ready _for transfer to .the
- Waste Solidification System.
! INITIALS
4.1 Spent Resin Conditioning in TK-85 and Water Transfer to TK-109.
i ' 4. Assure that the Resin Storage Tank SCREEN PLUG IS CLOSE . Place the MODE SELECTOR SWITCH in ' RESIN <
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Rev. N Page 5 of 15
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INITIALS 4. Place the. PHASE SELECTOR on FILL HOPPE . Close the RESIN INLET VALVE, WSS-A-2 . Open tne Resin Transfer pump Recire. Valve, RS-1 R 4. Cneck snut RS-27 Hope Connectio .
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R 4. Close WSS-89 Resin Transfer to TK 95 manual stop and , WSS-92 P-144 Resin Transfer to TK 85/TK 9 .
NOTE: With WSS-89 closed, we will be filling TK-109, not the hoppe . 4. Hook up the air hose, to the air supply connection to TK-8' Fully open the air valve at the tank and then crack open 1/2 turn the air supply root valve to allow air to oe injected into ' the tank for agitation of resi CAUTION: The root valve at the air supply line should just i be cracked to prevent blcwing resin out of the tank.
6 CAUTION: If level in TK-85 reaches 100%, secure air to TK-8 " Restore minimal air flow after TK-85 level has decreased and stabilize I 4. Start the Resin Transfer Ptrnp, P-10 .1.10 Run in tnis mode for 30 minutes, or until radia. tion levels staciliz NOTE: The resin bed above the screen will purify the recir stream and capture any resin beads below the scree .1.11 Open WSS-90, TK-109 inle ,! > 4.1.12 Transfer excess water to TK-109 by opening tne RESINS INLET 'j VALVE, WSS-A-28 and closing recire. valve RS-1 .1.13 Continue decant transfer until waste Resin Storage Tank level decreases to 35%. CAUTION: At levels less than 354, resin clogging of P-108 ' may occu . . b '
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Proc. No. 1-18-4
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Rev. N Page 6 of 15 INITIALS 4.1.14 Stop resin transfer pump P-10 R 4.1.15 Close WSS-A-28 TK-85 Resin Inle .1.16 Open recire, valve RS-1 .1.17 Close WSS-90 TK 109 Inle . R 4.1.18 Open WSS-89 Resin Transfert et TK 95 manual sto .
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4.1.19 Place the Phase Selector on Recir .1.20 Refer to Section 5.3 to return oecant to ADT' AUX. OPERATOR DATE/ TIME 4.2 Resin and Water Transfer from TK-85 to TK-109 ,- C
- ~ 4. Check open the resin transfer pump (P-108) suction valve, RS-1 . Open recire. valve RS-1 . Hook up the air hose to the air supply connection to TK-8 Fully open the air valve at the tank and then crack open 1/2 turn the air supply root valve to allow air to be injected for agitatio t CAUTION: The root valve should just be cracked to prevent 010 wing resin out of the tan CAUTION: If TK-85 level reaches 1004, secure air to TK-85. *
Restore minimal air flow after TK-85 level has decreaseo and staoilize . Start the resin transfer pump, P-10 ' 4. After 15 minute recire. stop P-108 and close RS-1 i 4. Open the spent resin storage tank screen plug.
j R 4. Close WSS-89 Resin Transfer to TK 95 man stop and close WSS-92 '
, P-144 Resin Transfer to TK 85/TK 95.
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Proc. No.1-18-4 Rev No. 12 t Page 7 of 15 C .
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INITI ALS 4. Place the MODE SELECTOR ON RESIN . Place tne SELECTOR ON FILL HOPPE NOTE: Witn WSS-89 closed we will be filling TK-109, not the hoppe .2.'10 Open WSS-90, inlet to TK-10 .2.11 Open WSS-A-2 . 4.2.12 Start transfer of spent resin to TK-109 by starting the waste resin transfer pump, P-10 .2.13 Centinue resin transfer until the hign level alarm is reacheo in TK-10 .2.14 Stop P-10 .2.15 Dewater TK-109 as 'per S'..e; NOTE: .If all resin has been transferred to TK-109, do not dewater as tnis wate. will act as shieldin .2.16 Transfer remaining resin and water to TK-109 by. starting P-10 .2.17 If hign level is not reached before all resin is transferred fill TK-109 witn primary water by closing WSS-102 and WSS-98 and opening WSS-lO2 If shielding is needed. Reference TK-109, Volume Curve attache NOTE: Do not use more water than needed for shielding.
r NOTE: There is no automatic protection against overfilling with wate , l 4.2.18 Stop P-108 and close WSS-A-28 when transfer is complet .2.19 Close RS-15 and WSS-90.
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; 4.2.20 Place phase selector in recir AUX. OPERATOR C
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Proc. No. 1-18-4 Rev. N * Page 8 of 15 INITIALS R 4.3 Dewatering Resin Fb1 dup Tank, TK-109 to ADT or WHT 4. Ensure there is room in ADT's to accept decan R 4. Close WSS-98 P-145 Bypas , R 4. Open WSS-97 FL-89 Inle , R 4. Open WSS-99 P-145 Outlet
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R 4. Open WSS-100 FL-90 IQtle , R 4. Open WSS-101 FL-90 Outle R 4. To seno decant to WHT open RS-2 RS-20 Open To seno decant to ADT cpen RS-2 . RS-21 Open (Circle One) 4. C1cse vent WSS-103 (in pipe just above WSS-101).
R 4. C1cse WSS 102 nose connectio .3.10 Using 15 osi or less start dewatering pump P-14 CAUTION: Do not use greater than 15 psi or FL-90 could rupture - adjust as necessary after star CAUTION: When cperating P-145, ensure air line oiler is ful .3.11 When dewatering is complete stop P-14 , 4.3.12 C1cse WSS-97, 99, 100, and 10 .3.13 Close RS-21 and 20 as opened abov d AUX. OPERATCR DATE/ TIME 4.4 RESIN TRANSFER FROM TK-85 TO LINER DISCUSSION
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During this evolution, the discharge of the dewatering pump is directed back to TK-85. A level increase in TK-85 should be noted soon after cask I dewatering is started. Resin transfer should be considered complete when (Qf1 radiation levels on the liner fill line drop significantly...
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Proc. No. 1-18-4
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Rev. No. 12 Page 9 of 15
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INITIALS 4.4.1 Perform the following valve line up .4.1.1 TK-85 cubicl NOTE: RS-14 is located in a Hign Raoiation, Air 00rne Activity Area and does not have a reach ro This valve is visible from above and should be checked in this manne a) RS-14', P-108 suction Check open b) RS-15, TK-108 recirc Open c) TK-85, screen plug valve Open d)' TK-85 air sparger supply valve Open e) WSS-67 P-123 air supply Open f) WSS-68 P-123 air supply Open g) WSS-34 P-123 suction Closed . R 4.4.1.2 Waste Solidification Panel a) WSS-A-28 Resin Inlet to TK 8 Closeo o) WSS-A-35 TK-85 suction of P 12 Closed 4.4.1.3 TK-109 Cubicle
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a) WSS-93, R-109 recire Closed b) WSS-94, o-144 discharge Closed c) WSS-91, liner fill stop Closed d) WSS-92, P-108 discharge Open e) WSS-95, TK-109 Closed 4. mokup flexible hose from WSS-91 to connection at Liner IAW , vendor instruction .4.3 Hook up dewatering hose IAW Venoor instruction . Check Service Air supply to TK-85 sparger closed, then hook up air hose to service air supply valv , 4. Start P-108 to recirc TK-85 for at least 15 minute . Crack open the Service Air supply valve to agitate resin, open no more tnan 1/2 turn to prevent blowing resin out of tan CAUTION: If level in TK-85 reaches 100%, secure air to TK-8 Restore minimal air flow after TK-85 level ,
, has decreased and stabilize '
NOTE: If P-108 should clog with resin, secure P-108, shut RS-14, connect hose from flush water upstream of RS-27,
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and flusn system thru P-108 to liner by opening RS-2 g C., .
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, Proc. No. 1-18-4 Rev. No. 12
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Page 10 of 15 INITIALS 4. When recirc is complete, open WSS-91 and close RS-15 to transfer resin to line CAUTION: Radiation levels at the top of the cask may reach as hign as 25 rem /hr. Use a temporary mirror at the top of the cask to visually determine leve . Open liner dewatering hose isolation WSS-7 . Sta5tthedewateringpump(P-123)whenlinerlevelreaches2.5" from fill heaa. Adjust pump speec to maintain a slowly
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cecreasing level. Ensure WSS-A-44 opens. tote level increase in TK-8 NOTE: When operating P-123 ensure air line oiler is ful .4.10 When resin transfer is ccmplete, perform the following: 4.4.10.1 Stop P-10 .4.1 Snut WSS-9 '.4.10.3 Shut the Service Air supply valve to TK-8 .4.11 Cbntinue oewatering Liner IAW Vendor instIuction NOTE: To measure the amount of water in cask, hook up a temporary leak rig to discharge of P-123 and run P-123 in accordance with vendors proceedur .4.12 Stop cewatering pump when liner is dewatered and disconnect s hose IAW Vendors instruction . 4.4.13 Drain hose into line .4.14 Place hose in yellow poly bag and return to its storage are .4.15 Perform the following valve line ups: -
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4.4.1 TK-85 cubicl a) RS-15, TK-85 recire Closed b) TK-85 screen plug valve Closed c) TK-85 air sparger supply valve Closed
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4.4.15.2 Waste Solidification Pane ' a) WSS-A-28 Auto b) WSS-A-35 Auto l I .5 l ! V * ! [ _ _ _
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Proc. No. 1-18-4 k . Rev. N Page 11 of 15 PCR No. 84-520, 84-521 84-522
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INITIALS 4. 4. 15. 3 On wall near WSS-9 a) WSS-92 Ciccec 4.4.16 Fill out attacned data sheet and forward to C'.amistry/M AUX. OPERATOR DATE/ TIM Transfer of Resin from TK-109 to Liner CAUTION: Ensure there is enough room in TK-85 to receive decant from liner prior to co=encing the following step " 4. Hock flexible hose from WSS-91 to connection at liner.
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PCR #84-520
. 4. 5. 2 Install two stand pipes and level electrodes - Hittman liner as ? per Westinghouse - HiHnan Procedure ST0 '.03-010 Rev. 5, Section 5, equipment set t ) 4. Connect air hose to WSS-102 for resin agitatio PCR #84-521 4. Open WSS-96 P-144 suction from TK-109 and eneck closed WSS-90 and WSS-9 R 4. Open WSS-94 P-144 discharg '
R 4'. Open WSS-93 P-144 discharge'to TK 10 * R 4.5.7- Close WSS-91 flexible hose connectio . . Start P-144 from solidification control panel and open WSS-102
[ snd air supply to reirc. and agitate resin for 15 minute PCR #84-522 When recire. is conplete open WSS-91 and close WSS-93 to '
4. ..
.g transfer resin to liner, following Hittman Procedure STD-P-03-010 g Rev. 5, Section 6.0, transfer and dewaterin ) CAUTION: Radiation. levels at top of the cask may raach as high j as 25 rem /hr. Use a terrporary mirror at the top of -
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the cask to visually determine leve '
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4.5.10 Place the control switch for WSS-A-35 in the closed positio '
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Proc. No. 1-18-4
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Rev. No. 12 Page 12 or 13
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INITIALS 4.5.11 Open liner dewatering hose isol. valve WSS-7 ~'
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4.5.12 Verify that the dewatering pump air supply isol. valves, WSS-67 ; and WSS-68 are ope " __ PCR #84-523 4.5.13 Start the dewatering pump (P-123) and follow Hittman Procedure STD-P-C3-010 Rev. 5, Section 6.0, transfer and dewaterin NOTE: When operating P-123 ensure air line oiler is ful .5.14 When resin transfer is complete perform the following: 4.5.1 Stop P-144 - 4.5.14.2 Close WSS-9 .5.14.3 Connect primary water hose to WSS-95, then open WSS-95 ano start P-14 .5.14.4' After clear flush wa'ter issues from hose ooen WSS-93, (, j .close WSS-91 and flush recire, line for 1 minute ' 4.5.14.5 Stop P-144 , f 4.5.14.6 Close WSS-9 .5.14.7 Close WSS-9 + 4.5.14.8 Close WSS-9 >
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4.5.14.9 Close WSS-94.-
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4.5.14.10 Shut WSS-lO2 and air supply to secure agitatio PCR #84-524 4.5.15 Stop dewatering pump following Hittman Procedure STD-P-03-010, Section 6, transfer and dewaterin ' NOTE: Well point will be left in the liner to be shipoed off . , site with the resin. ; NOTE: To measure the amount of water in cask, book uo , temporary rig to discharge of P-123 and run P-123 in
- accordance with vendors procedur ,
I 4.5.16 Drain hoses into liner.
l.j .5.17 . Place yellow poly bag around hose and return to its storage
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Proc. No.1-18-4
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INITIALS 4.5.18 Ensure res'.n liner is dewatered prior to cappin _ 4.5.19 Fill out, cttached data sneet and forward to Chem /H'.
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Rev. No. 12 Page 14 of 15
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Proc. No.1-18-4 -
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Rev. No. 12
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i 1-18-4 WASTE SOLIDIFICATION OATA SHEET , NOTE: This form will be completed and submittea to the Hazardous Waste Doroinator DATE:
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1 (HP) CONTAINER SERIAL #
(OPS) WASTE TYPE: EV-1, EV-2, Resin Decant, Resin, Primary Water, Other (Circle One)
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, (CHEM) WASTE pH (OPS) WASTE TRANSFER START TLT (OPS) WASTE TRANSFER C0!PLETION TIME i
(OPS) TOTAL WASTE TRANSFERRED
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(FP) TOTAL CEMENT ADDED
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(HP) CONTAIER SURFACE DOSE RATE
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[ Rao waste Co-orcinator Signature
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. Operator Signature NOTE: Route this Batch Report to the Hazardous Waste Coordinator l
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' EDISON DRIVE MAME HARHEE ATOMICPOWERCOMPARUe nuousrx. uaine casas - (207) 623-3521 e
August 22, 1985 MN-85-152 GDW-85-225 Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator References: (a) License No. OPR-36 (Docket No. 50-309)
(b) USNRC Letter to MYAPCo dated March 26, 1985 -
Inspection Report 85-04 ,
(c) MYAPCo Letter to USNRC dated April 30, 1985 -
Inspection Report 85-04 - Radioactive Materials Transport Program (MN-85-82)
(d) MYAPCo Letter to USNRC dated June 3, 1985 - ,
Inspection Report 85-04 - Radioactive Materials Transport Program (MN-85-105) Subject: Inspection Report 85-04 Gentlemen: In Reference (c), Maine Yankee requested reconsideration of both , Violation (A) and Violation (B) noted in Inspection Report 85-04, Reference (b). Based upon recent telephone conversations with members of your
, staff, Dr. M. Shanbacky and Mr. P. Clemons, we understand that Violation B will be vacate During a recent visit to the Maine Yankee site by Mr. Clemons, our representatives D. Sturniolo and F. Setchell had an opportunity to continue the discussion of this Inspection. We now have a better understanding of the specific matter of concern set forth in Violation A and wish to withdraw our request for reconsideration of this violation at this tim We have taken corrective action to assure that appropriate quality control is exercised over the preparation of radioactive waste for shipment. Enclosed is a copy of a revised version of Procedure 9.1.15 " Shipment of Radioactive i Material". You will note that we have provided for specific OQAD sign-off on
! various aspects of cask and shipment preparation. We believe that this l l addresses the concern of the inspecto ! l
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M r1 /70 9 1_ w g vs'[ L"vv w g , ( ___ 6304L-FWS
--- - , MAINE YANKEE ATCMIC POWER CCMPANY ..
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United States Nuclear Regulatory Commission Page Two Attention: Dr. Thomas E. Murley, Regional Adninistrator M4-85-225
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If you have any questions regarding this matter please feel free to contact u Very truly yours, MAItE YAIKEE ATOMIC POWER COWANY J .oDLH G. D. Whittier, Manager
[a Nuclear Engineering & Licensing
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GDW/bjp
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Enclosure:
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cc: Mr. Edward J. Butcher, Jr.
. Mr. Cornelius F. Holden
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} ,q Dept. He d Proc. No. 9.1.15 PORC'N , M Clas l
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p g g, Rev. No. 16 A Issue Date 5-16-85 g,rk'
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Review Date 5/87 9.1.15 SHIPMENT OF RADI0 ACTIVE MATERIAL
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1.0 DISCUSSION
Radioactive material shipments by any of the normal modes of transportation are subject to controls listed in varicus sections of the Ccde of Federal Regulations. Maine Yankee is responsible for the safe packaging and labeling of l all radioactive material leaving the plant site. Before a shipment of radioactive material is made, a Radiological Controls supervisor will be notified. Should the shipment consist of any special nuclear materials the Reactor Engineering and Radiological Control Supervisors will also be notifie To insure safe radiation levels, a Radiological Controls representative will perform a radiation and contamination survey of the material to be shipped. A
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Radiological Controls Supervisor will calculate the activity of the shipment and l assure that DOT and NRC requirements are complied with. Authorization to ship j any radioactive material from the plant site will be made by a Radiological
! Controls Supervisor. Due to rapidly changing burial site criteria and State and 00T regulations, it may become necessary to deviate frcm this proced.;re in order to meet current requirement .
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2.0 OBJECTIVE .
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; Establish a procedure for shipping radioactive material from Maine Yankee' .
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3.0 REFERENCES ,
.. CFR, Parts 170-18 ; __ __ ..
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1 CFR, Parts 20, 30, 40, 61, 70, 7 ~ ' Waste Disposal Site criteria (latest edition). ~ ~ _
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l H.P. Procedure 9.1.17 Healtfi Physics Requirements For Radioactive Waste j Processing And Shippin _ _
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! AIF tESP Methodologies for Classification of LLW from Nuclear Power Plants, j November 198 I Latest scaling factors from Science Applications, In '
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? 4.0 PRECAUTIONS t .. .-
.. All of the general packaging requirements of 49 CFR 173.411 or 10 CFR 71.43, unless otherwise specified, must be me .
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Proc. No. 9.1.15 l
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i Rev. N j Page 2 of 52 I l i 1 If the shipment is overweight notify 1.he shipment contractor to obtain an
* " overweight permit" for the vehicl .3 Transportation of radioactive material on the Maine Turnpike is allowed only during daylight hours (sunrise to sunset). Do not allow any vehicle carrying radioactive waste material that requires placarding of the vehicle i
to leave the Maine Yankee site property without sufficient time to comply with the daylight travel only regulations of the Maine Turnpike Authorit ,!
) Assure that radiation levels do not exceed the specified limit ~
O Assure that the radiation levels on items loaded into shipping casks do not
{ exceed the limits in Attachment I Assure that liquid wastes are adequately mixed prior to sampling to insure
} that a representative isotopic analysis is performed before determining the
! disposal method. This is especially critical with oil and water mixture [I.E. notice 83-33]
l j If the shipment contains transuranic elements, the radioactive shipping contractor and the burial site must be notified before the shipment leaves
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I Maine Yankee.
'l Shipments requiring labels or placards must have the appropriate label or .
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placard attached before leaving the plant site. Special precautions must be - taken when applying labels or placards during inclement weather conditions
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to prevent them from falling off during transi .0 PREREQUISITES Unless exempt by 173.421 (limited Quantitles of Rcdioactive Materials and Radioactive Devices) or 173.425 (Low Specific Activity), only approved '
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containers will be used for shipment of radioactive materia .'2 Before Radioactive material is transferred to another licensee, verification of their license to receive, the type, forrr and quantity of radioactive
. material must be enecked by Maine Yankee. A copy of their license should be on file at Maine Yan}<e .3 All placarded shipments of radioactive material through the State of ;
Massachusetts require notification of the Massachusetts Department of Public Health. Notification is to be made by telephone. Form No. 9-1-15-HP-3
'l Masachusetts Department of Health Notification Form, lists the data required and the notification procedure. This form must be filled in for each such notification.
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.. :; Proc. No. 9.1.15 Rev. N : Page 3 of 52 .
s i 5.4 Shipments of fissile nuclear materials, both entering and leaving the state of Maine, require written notification of the following Maine State Agencies:
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1) Maine Turnpike Authority (must be informed three days in advance of shipment).
2) Maine Bureau of Civil Emergency Preparednes ) Paine Department of Environmental Protection, Bureau of 011 & Hazardcus ? Materia ) Maine State Polic ' l 5.5 All shipments of radioactive material that require placarding of the i vehicle, will require notification of the following Maine State Agencies by i telephone prior to leaving the sit ) Maine Turnpike Authorit . 2) Maine Department of Environmental Protection, Bureau of 011 & Hazardous g Materia ) Maine State Police. (Also requires not less than 24 hour advance p notification of any LLW shipment Form No. 9-1-15-HP-8).
>
Date, time and person contacted for such notification, made pursuant to this
[ paragraph, must be recorded on Maine Yankee State Agency Notification For Form No. 9-1-15-FP- j 5.6 Shipments of spent reactor fuel leaving the Maine Yankee site must be escorted by one individual from the Health Physics Department until the shipment leaves the State of Maine. Additional requirements, see Section 6. .7 Low Specific Activity (L.S.A.) shipments that contain greater than Type A quantities of radioactive material must be packaged in a container that meets the requirements of 10 CFR 71.52, 5.8 Prior to each shipment of fissile radioactive material, Type 8 or highway route controlled quantity of radioactive materials (see 6.1.5 + 6.5.3) the consignee must be notified of the shipping dates and expected time of I arrival. The consignee must also be notified of any special I loading / unloading instruction ,
I i 5.9 Shipments of radioactive material that require placarding through the State
. of Conneticut, New Jersey and Rhode Island require a permit unless the material is exempted by the individual state. The carrier is responsible '
for obtaining the above permit (
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5. Normally a Radiological Controls Supervisor will have the Connecticut application for a Radioactive Permit telecopied to Connecticut as soon f as the driver signs i The permit should come back to Maine Yankee and . be part of the driver's paperwor h 5. Massachusetts Department of Public Health is to be notified of all y shipments of radioactive material requiring placarding entering the j State (Form No. 9-1-15-HP-3).
5.10 The Radioactive Quality Assurance Record (Form No. 9-1-15-HP-1) must be completed for all shipments of radioactive materia ' 5.11 Prior to the first use of a package for which a license or certificate of compliance is required the Director of Nuclear Material Safety and Safeguards must be notified in writing of Maine Yankee's intent to use the packag .12 A broker must be obtained for shipments to Nevada or Washington if a third
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party is involve l 5.13 A determination of the type, form, classification, and whether any exemption j to the transportation regulations apply has been made for each packag l 4 i 5.14 A determination of whether each radioactive waste container is Class A, 8 or j C has been made (see Section 6.6 and 6.8.4). - -
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_ j 5.15 On a case by case basis as specified in 10 CFR.20.302 very low level -
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i radioactive waste may be disposed of in a manner not otherwise authorized in j tne regulations. [IE Notice 83-05] -
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l 6.0 PROCEDURE . . . _ _
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.. . .. Preshipment Requirements - -- - # - ~
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1 6. Arrange with carrier for type of vehicle or cask require ! '
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j Chem Nuclear: 1-803-259-1781_- - _ r ,T., J
; Hittman: 1-301-964-5047 _ . _ ._
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6. Chem Nuclear at Barnwell, South Carolin .
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- .) 6.1.2.1 Call Chem Nuclear by at least the fifth of the month to schedule a' -
shipment (s) for that mont . . NOTE: Maine Yankee has been alotted 506 '
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cubic feet per mont _
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6.1.2.2 Send prior notification form (DHEC 802) to South Carolina so that it is received no less than 3 days or nor more than 30 days prior to arrival.
Bureau of Radiolcgical Health Radioactive Waste Management Section i S.C. Dept. of Health and Environmental Control 2600 Bull Street 'I1 Columbia, South Carolina 29201 Telecopier: 1-803-799-6726
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Change or add information to PNP form: 1-803-758-7806, 6.1.2.3 Send copy of PtP form to Chem Nuclear at the same tim Chem Nuclear Systems, In J
. P.O. Box 726
[ Barnwell, South Carolina 29812 Attention: Scheduling Change or add information to PNP form: 1-803-259-1781 6. U.S. Ecology, Inc. at Richland, Washingto .1.3.1 After arranging for carrier, notify U.S. Ecology of the intended . .. -Iy shipment and approximate arrival dat ~
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Phone: 1-509-377-2411 NOTE: Carrier has to notify Washington State a .
'l minimum of four (4) hours prior to entering Stat .
6. Chief of Maine State Polic ] - _, 2- .
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6.1.4.1 At least 24 hour advance notification of any shipment of low-level
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waste is required.* Fill out Form No. 9-1-15-HP-8 and call in available infomation.-
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;l 6. If a " HIGHWAY ROUTE CONTROLLED QUANTITY" (49 CFR 173.403(1) is to be shipped, there are special requirements that must be adhered to. See ]t Section 6. . ! 6.1.5.1 Definition: A quantity within a single package which exceeds:
I
) (1) 3000 times the Al value ~ ~ ~ - ~~~ ~ . (2) 3000 times'the A2 value (3) 30,000 Curies, whichever is least - '( '
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Page 6 of 52 l 6.1.5.2 10CFR71.97(3) also has special requirements if a shipment contains:
. (1) Greater than 20 curies of other than special form for which A2 is less than or equal to 4 curie d,'
S (2) Greater than 200 curies of other than special form for which A2 is greater than 4 curie .2 Initial Survey of Emoty Transport Vehicle (Exclusive Use)
., 6. Upon arrival, the transport vehicle will be detained outside the plant " protected area by Security personnel until authorized to enter the plant y by a Radiological Controls Superviso t -
m 1 6. Radiological Controls personnel will survey the transport vehicle for
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contamination and radiation. They will complete Survey Form MY-HP-102-7 ' U Preparation for Shloment 6. All radioactive material shipping containers must have: _l
- a contact and three foot radiation reading
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- the contamination level on the outside of the container
- a determination of isotopic content of the material _-
- a determination of total curie content of container i
, - labels as per Section .. . _ - .;i
- markings as per Section 6.7 or 6.5.4.1 or 6.5. ~.g ( .
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gl Scecific Details
0 6. Debris J
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)d 1 6.4.1. Isotopic content can be determined from evaporator bottoms --
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isotopic analysis which should be representative of T C q contaminatio . 6.4.1. Curie content estimated using the following formula: . _
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/ Millicuries = MR/HR at 3' x 4 l
6.4.1. Normally shipped on exclusive use vehicle as RADIOACTIVE LSA, see Section 6.5.4.2, 6.9.1 and 6.1 ' _ i NOTE: Gross weight limit of DOT 17H drums j - - is'840 lbs. and DOT 63 is 560 7bs'.~-~
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6.4.1.2 L.S.A. Boxes 6.4.1. Isotopic content determined as in 6.4.1. .4.1. Curie content estimated using the following formula: Y Y Millicuries = m /m at 3' x 6.85.
V NOTE: Ensure that box lids are banded (for waste containers)..
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I 6.4.1. Normally shipped on exclusive use vehicle as RADI0 ACTIVE -< LSA, see section 6.5.4.2, 6.9.1 and 6.1 . 6. Laundry 6.4.2.1 Normally shipped in LSA boxes, see Section 6.4. j 6. Disposable Waste Liner _ss
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6.4. . Isotopic content determined from an isotopic analysis of the material put into the line il
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Curies = curies /gm or ml X volume in gms or mis
[ - . NOTE: If the material cannot tie sampled, a Chemistry or Radiological Controls Supervisor will calculate the T' . . - -
activity of the-materia .
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NOTE: Spent Resin
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l Barnwell, S.C. - shipped either solidified in cement or dewatered _ in a High Integrity Container (HIC). A qualitative and
- - .e quantitative (isotopic) analysis of all nuclides contained in i the resin expressed in uci/cc is required. A summation of the activity of nuclide with half-lives' greater than five years is i
_ . . . require " ~ _J C e Richland, Washington - The;same analysis information is require , If the summation of nuclide activities with half-lives greater L than five years is less than 1.0 uci/cc, the resin can be shipped dewatered. ~If this sum is greater than 1.0 uci/ce, the
- resin must be solidified in cemen i
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i ' l *. Proc. No. 9.1.15 g l Rev. No. 16 Page 8 of 52 6.4.3.2 Quality Control personnel must inspect all dewatered or solidified containers to insure that there is not detectable free standing liquid.
Barnwell, S.C. - Less than 0.5% by waste volume in a steel i containe Barnwell, S.C. - Less than 1.0% by waste volume in a High Integrity
! Container (HIC)
Richland, W.A. - Less than 0.5% or one gallon per container, which-ever is les .4.3.3 Normally shipped on exclusive use vehicle as RADI0 ACTIVE LSA, see Section 6.5.4.2 an 6.9.1 and 6.10.2 [ EL 6.4. See Section 6.5 for package requirements.
3' 6. Spent Liquid Filtration Filters 6.4. Isotopic content determined by isotopically analyzing a sample of the material deposited on the filt,er .4.4.2 Curie content is determined by estimating the total amount of c material deposited on the filters and using the followi_ng formula: Curies = curies /gm X weight of material in gms -
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NOTE: If the material cannot be sampled, a Chemistry or Radiological Controls Supervisor will
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calculate the activity of the materia .4.4.3 Analysis requirements are the same as in Section 6.4.3.1 for spent resin.
.t . 6.4. Free standing water requirements as in 6.4.3.2.
l - 6.4.4.5 Normally shipped on exclusive use vehicle as RADI0 ACTIVE LSA, see Section 6.5.4.2, 6.9.1 and 6.1 . 6. Samples for Analysis l 6.4.5.1 Liould
6.4.5. Isotopic content determined from isotopic analysis of each sample to be shippe '
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?g . , Proc. No. 9.1.15 y Rev. N i Page 9 of 52 f 6.4.5. Curie content of the package is determined using the following formula: Curies = curies /ml X volume in mis % 6.4.5. Mixed cargo is normally shipped as LIMITED QUANTITY, see ) Section 6.5.4.1 and 6.10.1.
) 1 NOTE: Shipping container must contain enough
[ absorbent material to absorb at least , twice the volume of the liquid being
- shippe (49CFR173.412(n)(2) and (3) l 6.4.5. See Section 6.5.4.1 for package requirement .4.5.2 Solids
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6.4.5. Isotopic content determined by isotopically analyzing a y representative smear (s) from item (s) being shippe l 6.4.5. Curie content estimated by calculating the surface area of j the item (s) and using the following formula: 3 Curies = area in em2 X curies /cm2 6.4.5. Mixed cargo is normally shipped as LIMITED CUANTITY, see Section 6.5.4.1 and 6.10.1.
- 4 6.4.5. See Section 6.5.4.1 for package requirement . Eoulpment
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j 6.4. Proceed as in Section 6.4.5.2 (Solid Samples). Detertnination of Type Package
~ , _ 6. Determine the total curie content of the material by Al or A2 values as listed in 49CFR173.435 or 49CFf1173.433 if not listed. See Attachment C for Al and A2 value .5.1'.1 Al values are for special form material like scaled sources. See 49CFR173.403Z, 469 and 47 LOT _E: Documentation of special form material must be obtained if shipcents are made in this categor (IE notice 83-47]
6.5.1.2 A2 values are for normal form material. Normally shipments are in thJs categor (
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Proc. No. 9.1.15
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Rev. tb. 16 j Page 10 of 52 >l
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6. Determine if values obtained are greater than or less than the Al or f A2 values listed as appropriate.
L 6.5.2.1 Type A packages are required if the contents do not exceed the A1
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or A2 values (49CFR173.415).
. } 6.5.2. A Demonstration of Compliance is required when a TYPE A package is required (49CFR173.461) [IE notice 83-47).
$ j NOTE: See Section 6.5.4 for exemption .
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6.5.2.2 Type 8 packages are required if the contents exceed the Al or A2 values (49CFR173.416).
[ : 6.5.2.3 If a TYPE 8 package is used, be sure that the Certificate of Compliance (C of C) is onsite and that all of its requirements are h . fulfilled.
I NOTE: No changes can be made to the package as described h in the C of C [IE notice 83-10). - t l 6.5. If a TYPE 8 package is required assure that the heat generated by the material will not exceed the shipping Cask thermal watt limitation as specified by the Certificate of Complibnc3ToTT).
- C of C's are located in the Casks Books in the Radwaste Offic Calculation is as follows for each isotope
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, WATTS = (e) (C1) (5.93 E-3) e = total energy per disintegration (beta energy to be 1/3 max energy + total energy of all gammas)
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, C1 = total curies of isotope
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6. If it is determined that a " highway route controlled quantity" is to be shipped, special requirements and pre-notifications are required: ,
, -(49CFR177.825b)
t f 6.5.3.1 Prenotification as described'in 10CFR71.97 for waste and 10CFR73.37 [ for spent fuel.
L 6.5.3.2 Special placards (49CFR172.527).
( 6.5.3.3 Special reporting requirements (49CFR173.22).
6.5.3.4 Always requires a RADI0 ACTIVE YELLOW III label (49CFR172.403c).
6.5.3.5 Each shipping paper related to the shipment must bear the package identification marking indicated in the USNRC apprnval (497R173.471c) i I r i
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[ TABLE 7 ACTIVITY LIMITS FOR LIMITED QUANTITIES, INSTRLNENTS, Am ARTICLES I Nature of Instruments & Devices I Materisis I i ! Contents IInstrument & Article Liniitsl l Package Limits l Package Limits i I I Solids: l I I Special form i Other form 10-2 Al l Al l 10-3 A1 l 10-2 A2 A2 10-3 A2 .
I i . I Liquids: I l l Tritiated water: l l l 1ess than l l 1 Ci/ liter i l l- 1000 Curies i I I 0.1 Ci to 1.0 C1/11 1 100 Curies l I greater than 1.0 l I i Ci/ liter i l l 1 Curie I i I Other liquids i 10-3 A2 c- 10-1 A2 10-4 A2 I
I I I cases: I i l Tritium 2 l 20 Curies l 200 Curies Special Fcrm l 20 Curies l 10-3 Al l 10-2 Al l 10-3 A1 Other Forms l 103 A2
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10-2 A2 10-3 A2 l I
. For mixture of radionuclides see.$173.433 (b).
2 These values also apply to tritium in activated luminous palat and tritium absorbed on solid carrier i Mixtures of Radionuclides Ratial + Ratio 2 + .... Ration (must not be greater than unity to qualify as limited quantity.)
Ratio a Total Activity of Isotope in Shipment
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Al r 2 Value from Table in Attachment C ( , Multiplied tSmes package limit or compared to value in Table 7 as appropriat .
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6.5.3.6 Special routing requirements (49CFR177.825c).
- f1 6. Exemptions 6.5.4.1 Limited Quantity.(49CFR173.421)
( 6.5.4. Package contact dose rate cannot exceed 0.3 mrem /hr.
R l 6.5.4. Isotopic content of material must be within the limits as
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listed in table 7.
f 6.5.4. Package only required to be a STRONG TIGHT container.^*
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6.5.4. Asealisnotrequired{onthepackag ld 3 6.5.4. The outside of the inner package must be marked RADIOACTIVE.
? 6.5.4. Certification statement (Form No. 9-1-15-HP-9) must
. accompany the shipmen (49CFR173.421-1(a)) ..
6.5.4.2 RADI0 ACTIVE LSA (49CFR173.425) -
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6.5.4. Material in which the radi~oactivity TS ess'entfRIly un1Tormly y distributed and in which the estimated average concentration __. .- of contents-does not exceed: (49CFR173.403n) ; . - 3 ; i ~. y -
.
-x- -
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. - .; , __ .0001'millicurie the A 'quentity~is not permore gramthan of rhdionuclides 0.05 curie. ~?for whiche_- ,I -
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2 . -v 1, _ _ J" .005 millicurie per gram of radionuclides for which the ; - A2 quantity is more ~than 0.05 curie, but not more than- 2.- 1 curie; or .; . - . _ _ . _ - _ .- -
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1 . . _ . r-_ q .3 millicurie per gram of radionuclide for which the .. M'. _ J A2 quantity is more than 1 curi e.-
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POTE:. This includes,-but is not limited to,'. ~ a'
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_ . , - J: materials 'such as residues or solutions ._, . . l. . from chemical' processing, waste such as'- -- O.- 5 building rubble, metal, wood and fabric, . . . - m #- J glassware, paper and cardboard; solid or 2 -
.'. -
liquidplantwastes,sludgesandashes.~} - ~{. , 6.5.4. Packages only required to be a STRONG TIGHT container up - through A2 quantity if shipped in exclusive use vehicl _ _ CAUTION: Shipments that contain greater than ...... l .-
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an A2 quantity must be packaged in - - T ~; ~# s'00T specification containe (10CFR71.52). -
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k _ ' * s .' Proc. No. 9.1.19 j;
. "
Rev. No. 16 Page 13 of 52 l
.t 6.5.4. There must always be two (2) markings of RADI0 ACTIVE LSA on each package 180* apart.
p NOTE: Markings must be at least 1/2" high.
t 6.5.4. A seal is not required on the packag .6 ' Determination of Waste Burial Class A, 8 or C; (10CFR61.55) 1 6. Determine the amount of activity, if any, of the isotopes listed in j Table 1 or 2, found in Attachment D, are contained in the wast i NOTE: Use Form No. 9-1-15-if-10 as a workshee _
,
6.6.1.1 Non-gamma emitters required to be reported will be reported using 1 scaling factors, where applicable. These scaling factors will be 0 based upon a data base developed under a cooperative program with
] the MtC and SAI and modified as the data base expands. These a
scaling factors are given in Attachment NOTE: One sample, typical of each waste ctream, will be fully 3 analyzed annually until it is demonstrated to be
'
unnecessary., to-ensure _the-validity-of.-the factors-being utilized.' _ , , j
~
NOTE: Gross changes in waste stream radionuclide concentrations or
~
t -
- .- ratios will. require a reevaluation of the classification .
methods and will be addressed as the situation arise . . ] . j 6.6.1.2 Radioisotopes requiring reporting, not easily measured or i correlatable, will be reported based upon the methods described in the AIF NESP Report, " Methodologies for Classification of LLW from 7,
-
_ Nuclear Power Plants", November 1983. (Report maintained in
, .
Radwaste Office.)
. l ; NOTE: . A 'nuclide is considered to be "significant for purposes
- . _ . _ - .-- ~
of classification".if its' concentration is greater than-m
- -
_ 0.01 times the concentration listed-in Table 1, Column 1 or 0.01 times the smallest concentration listed in Table '
-
This does not include isotopes identified in Table 2 as
, having half-lives less than 5 years. An isotope (other ,
than On-242) having a half-life less than 5 years is considered significant if it is contained in the waste in j concentrations greater than 7 uci/cc (0.01 times the
Table 2, Column i value).
- ,) 6. Determination of Waste Class from Table 1 l 6.6. If the concentration of the nuclide does not exceed the value in j ( Column 2, the waste is Class A.
.!
t- m .: l TC$** WDY.%% O*,...- h177M"_EMMs~ MY 7- !Y . ;jg d*UUD
'
*
,l }- Proc. No. 9.1.15 }'. Rev. No. 16
]
*
Page 14 of 52
:
i
6.6. If the concentration of the nuclide does exceed the value in Column
'
2, but does not exceed the value listed in Column 1, the waste is Class .6. If the concentration of the nuclide exceeds the value in Column 1,
.
the waste is not generally acceptable for near surface disposa a j 6.6.2.3.1 Proposals for disposal of waste in this category may be submitted to the tRC for approval under 10CFR61.5 .6. For wastes containing a mixture of nuclides listed in Table 1, the class is determined by the sum of the fractions rule as follows:
..
CAUTION: All values must be taken from the same column
- j in the same tabl ! Nuclide 1 Nuclide 2 Nuclide n uci/cc uci/cc uci/cc
_
-------- + -------- . + .... --------- = less than 1 Value in Value in Value in Column Column ,
Column J, j NOTE: If the answer is less than 1, the class of waste is determined by the column used.
c) 6. Determination of Waste Class from Table 2 -
- .
1 6.6. If the concentration of the nuclide does not exceed the value in - 1 Column 1, the waste is Class ~ l j 6.6. If the concentration of the nuclide exceeds the value in Column 1, j but does not exceed the value in Colunn 2, the waste is Class B.
- - - 6.6. If the concentration of the nuclide exceeds the value in Column 2, '
~ but does not exceed the value in Column 3, the waste is Class C.
Il * [. 3: 6.6.3.4 If the concentration of the nuclide exceeds the value listed in Column 3, the waste is not generally acceptable for near
-
g surface disposal. See Section 6.6.2.3.1.
- $
j t 6.6.3.5 For wastes containing a mixture of nuclides listed in Table 2 Q proceed as in 6.6.2.4.
.? 6. If the waste does not contain any nuclides listed in Table 1 or 2, the '
waste is Class i Marking (49CFR172.300)
}
6. Each package weighing more than 110 pounds must have its gross weight ( plainly and durably marked on the outside of the packag . .i - J g.
s un a . hy.g ,- y . + . 7. w~ . m.-
.
,
. . .-= 7
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- ~ .. - ,-- ,.
.---.y. -. .7 t- 7- .j , . n ,.. - ,m.,. m .,- .
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.
n ,7.. O.-,- m
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.,
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Proc. No. 9.1.15
,, Rsv. No. 16 Page 15 or 52 c
,
.
6. Each package which conforms to the requirements for Type A or Type B packaging (see section 6.5) must be plainly and durably marked on the outside cf the package in letters at least 1/2" high with the wording
" USA 00T 7A TYPE A and Radioactive Material (49 CFR 178.330-3) or the package identification marking indicated in the USt@C approval (49 CFR '173.471b) respectively".
6. Any markings must be at least 1/2" high.
- Labeling (49CFR172.403)
6. Radioactive White I 6.8.1.1 Package content dose rate cannot exceed 0.5 mrem /h ~~
.
6.8.1.2 Package cannot contain FISSILE CLASS I or II materia .8.1. Fissile material is (49CFR173.403j): Plutonium - 238, 239 or 241
' , Uranium - 233 or 235 6.8.1.3 Package cannot contain a " HIGHWAY ROUTE CONTROLLED QUANTITY" of matefill. de rsTctTon 6. . Radioactive Yellow II -
_ 6.8.2.1 Packag's e with contact dose rates exceeding 0.5 mrem /hr, but not _
-
greater than 50 mrem /hr and not exceeding 1.0 mrem /hr at one meter _c_ ,
(3.3 feet).
^ 6.8.2.2 Must use on FISSILE CLASS II package having a Transport Index (TI) of 1.0 or les =.
*
6.8.2. TI is the max'imum dose rate in mrem /hr at one meter from the
^
packag . Radioactive Yellow III -
( 6.8.3.1' Package contact dose rates e'ceeding x 50 mrem /hr or greater than mrom/hr at one mete {; CAUTION: See section 6.10 for maximum package contact dose rate .8.3.2 Must.use on FISSILE CLASS III packag .8.3.3 Must use on a package containing a " HIGHWAY ROUTE CONTROLLED QUANTITY" of material. See section 6.1.5 and 6. ~
~
6. Each package of radioactive waste must be labeled as Class A, B or C as per Section 6.6. (10CFR61.57) l
.
e
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'* ' Proc. No. 9.1.15 Rev. No. 16 l
.
,
Page 16 of 52
, " 6. The contents asked for on Radioactive Yellow II and III labels are the major isotopes contained in the materia . There must always be two (2) labels on each package 1800 apar . All packages shipped under a label must be at least TYPE . All packages shipped under a label must incorporate a feature such as as seal on the outside of the package, which is not readily breakable and which, while intact will be evidence that the package has not been illicitly opene (49CFR173.412b) Placarding (49CFR172.500) 6. All RADI0 ACTIVE LSA shipments sent by exclusive use vehicle must be placarde I 6. Any vehicle which contains a package bearing a RADI0 ACTIVE YELLOW III label must be placarde _ l 6. Placards must be on each side and each end of the vehicl .9.3.1 If shipping on a tractor trailer, the placards are put on each end and-each-side of-the-trailer-c& load. --- 6.10 Method of Shipment . 6.10.1 * Motor Freight (Mixed Cargo)(49CFR173.441a) 6.10.1.1 Packages with contact dose rates up to 200 mrem /hr and a Transport Index of 10 or les .10.2 Motor Freight (Exclusive Use Vehicle) (49CFR173.441b)
.
6.10.2.1 Packages with dose rates that exceed those in Section 6.10.1.1 can be shipped on an exlcusive use vehicl . 6.10.2.1.1 Up to 1000 mrem /hr on the external accessible surface of the package (closed transport vehicle only).
NOTE: Vehicle must be equipped with an attached exterior enclosure, which during normal transport, restricts the access of unauthor-ized persons to the cargo space containing the radioactive material.. (49CFR173.403c)
.
MGS:n& M mM WWwwmmmm&wMW
l
: - .j' .
4 Proc. No. 9.1.15 d Rev. No. 16 Page 17 of 52 f
(N 6.10.2.1.2 Up to 200 mrem /hr at any point on the external surface of the car or vehicle (closed transport vehicles only).
i 6.10.2.1. Open vehicle limited to 200 mrem /hr on
,} contact with the package (s),
e
*
6.10.2.1.3 Up to 10 mrem /hr at any point 2 meters (6.6 feet) from
, '
the vertical planes projected by the outer lateral surfaces of the car or vehicle, a 6.10.2.1.4 Up to 2 mrem /hr in any normally occupied position in the l car or vehicle except that this provision does not apply ( to private motor carrier J 6.10.2.2 Specific instructions for maintenance of the exclusive use (so'le i use) shipment controls must be provided by the shipper to the d carrie .10.2.3 Shipment must be loaded by consignor and unloaded by the consignee from the transport vehicle in which originally loade .11 Loadino of the Transcort Vehicle
, 6.1 Radioactive Shipment Quality Assurance Record (Fern No. 9-1-15-HP-1).
[ 6.11. Radiological Controls personnel will complete Sections J .
]a 6.11. Radiological Controls and Quality Control personnel will complete Section II, III, IV and Section II to be completed ;i prior to loading any material, j 6.11.2 Opening, loading and closure of casks used to transport radioactive y material will normally be done in accordance with Equipment Handling Procedures supplied by the radioactive material shipping vendor, ;p Hittman,= Chem-Nt; clear, etc.).
t: I - 6.11.3 Radiological Controls personnel will conduct a final survey on all radioactive material being loaded for highest *ontact and one meter radiation level .11.4 Radiological Controls personnel will monitor the external radiation levels of the package for compliance with external radiation criteria N [200 MR/HR contact, 10 MR/HR at two (2) meters and no greater than 2 1 MR/m inside the tractor cab, 173.441(a)(b)] as the truck is being loade .11.5 Assure that proper labels are placed on containers, see Section 6.8 or 6.5.4.2, and are properly adhered to prevent removal during inclement weathe l b s kawwwmx m - :: m v ~ = = . r .?~ m
* '
Proc. No. 9.1.15
,, Rev. tb. 16 c <
Page 18 of 52
$
i 6.11.6 Assure that proper markings are placed on containers, see Section 6.7, and are properly adhered to prevent removal during inclement weathe j 6.11.7 Assure that all packages have been adequately blocked or braced to
~
h prevent load shifting during transportatio .12 Closure of the Transport Vehicle - a g 6.12.1 Radiological Controls perscnnel will verify compliance with external radiation level criteria (sce 6.11.4) before final closure of the transport vehicl f
4 6.13 Final Vehicle Survey 6.13.1 Radiological Controls will survey snd record the highest contact, and 2-~ - meter radiation level of the shipping package as per H.P. Procedure- - 9.1.1 i H 6.13.2 Radiological Controls will survey the dose rate of the cab at the l closest point et the load external of the cab if possible and record the
; result k NOTE: If the cab reading is greater than 1.5 mrem /hr, the load should ) be repackage _
+--- . . .
._
6.13.3 Radiological Controls will check and record the external surface of the package, transporter and vehicle tires for contamination. Contamination . N shall be less than 100dpm/100cm2 gross activity or less than 1000 ~ l dpm/100 cm2 beta-ga. Trna and less than 100 dpm/100 cm2 alpha. (49 CFR ~l - l 173.443) - . ~W~ i-
.
6.13.4 The Final Shipment Radiation Surveys of each package (s) and transport - l vehicle will be performed by two different individuals using different .. s survey meters. The second complete survey will be performed by-a . . . Radiological Controls Superviso T-
]f _ l 6.14 Placarding 6.14.1 Assure that the proper placards are placed on the transport vehicle, see l Section 6.9 and 6.5.3, and are properly adhered to prevent removal
,
_ l during inclement weathe ~~ 6.15 Shipping Manifest: (49CFR172.200) , RADIOACTIVE WASTE (Also 10CFR20.311) . I i- 6.15.1 Radioactive waste is normally manifested on forms provided by the burial i ~ sit I 6.15.1.1 All required information is requested on these form ,
.
..ie j ..-
-
- .
"
,.:.; ' VR.A(ir /@..@. Q. j[@. .@.. @-]..Q.s.Q. . . ".'G. ..P.,{. ,IW.W7. -{!I@ f.gjl;[.rh .
.
~ ~ . .
. .
.
, *
,
*- Proc. No. 9.1.15 j ., Rev. No. 16 Page 19 of 52
_ l 6.15.1.2 The total quantity of the radionuclides H-3, C-14, Tc-99 and i I-129 must be shown.
i 6.15.1.2.1 If any of these nuclides are known not to be present, i the quantity should be recorded as "not present".
6.15.1.2.2 If any of these nuclides is known or suspected to be present but in quantities less than the lower limit of detection (LLD), the quantity should be recorded as less than minimum detectable, with the LLD value liste .15.1.3 Other nuclides listed in Table 1 and 2, if significant for i purposes of classification, should be listed. See Section 6.6. _ 6.15.1.4 Other nuclides not listad in Table 1 or 2 should be reported if l l they are contained in significant quantities (l m a greater of total activity in container).
! 6.15.1.5 The total quantity of source or special nuclear material should
{
.
be reported, if the waste contains such materia ! 6.15.1.6 Distribute copies of the manifest as indicated on the form } (10CFR20.311d (5, 6, 7)) l
* 6.15.1.6.1 Mail copy to burial site at time of shipmen !
i 6.15.1.6.2 Include one ccpy with the shipping paper ~
._ m .;_,
l, '
-
-
-
: -. '
6.15.1.6.3 Rctain one copy on-sit l 6.15.1.7 If Maine Yankee has not received a signed copy of the manifest or equivalent documentation, indicating receipt of the shipment from the burial site within 20 days after the shipping date, ana
-
-
_- investigation must be started to locate the shipment.- - - - i (10CFR20.311h(1)) - J . . 6.15.1.7.1 The investigation shall' include tracing the shipment and -
-
l filing a' written report with the nearest NRC office
; ,
within 2 weeks of the completion of the investigatio t (10CFR20.311h(2))
.:
k RADI0 ACTIVE NON-WASTE
! '
6.15.2 Radioactive material that is not waste is normally manifested on Maine
'
Yankee's Radioactive Shipment Record (RSR). (MY-HP-23-72)
{
6.15.2.1 All required information is requested on these forn . 6.15.2.2 Radionuclides that attribute 1 3 or greater to the total activity
,( contained in the shipment should be listed on the RSR form."
l _. _ .. . _ ..
,
#geneW-g .,
' y,p.s. . .y. c g.:.g;:.? g g*,-. gyp, ...: v s . .. g% l. ..
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.
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!. j Proc. No. 9.1.15 i- Rev. No. 16 Page 20 of 52
'
3 _ e
~
6.16 Records The transportation of radioactive material requires various records and forms to be properly completed before the shipment leaves the plant sit A checklist of required forms and records will be maintained and new forms or records will be added to the list as required (Form No. 9-1-15-HP-5). A Health Physics Supervisor will verify that each item on the list is completed before the shipment leaves the plant sit .0 FINAL CONDITONS } Radioactive material is properly packaged and ready for shipment.
j-
1 l
:
:
.
.
* wme.+
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1 - _
-
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' . .
f ' ., Proc. No. 9.1.15 t Rev. No. 16 ; i Page 21 of 52 a
,
y ATTACmENT A _ RADWASTE DOSE RATE LIMITS BY PK l h CASK TYPE 00SE PAYLOAO VOLUME INER SUPPLIER L .MODEL RATE (MAX) ft3 /# PKG. SPE ' N (R/$) LIER /0 RUMS ll I CNS 8-120 li B 200 R 20,000 124 / 8 SEC. CONTAIER CNSI pCNS14-195-H Ii c II .A 15 R 17,700 195 / 14 SEC. CONTAIER CNSI f !l [ CNS 21-300 l ll' A 1R 27,250 300 / 21 SEC. CONTAIER CNSI ' II CNS 6-80-2 II A 500 R 7,500 80 / 4 SEC. CONTAIER CNSI II CNS 14-190- 1I B 5R 10,000 195 / 14 SEC. CONTAIER CNSI
<! II I CNS 4-45 ll B 10,000 R 10,000 45 / 4 SEC. CONTAINER CNSI ! Ii 8 CNS6-75 ll A 150 R 10,300 85 / 6 00T TYPE A CNSI . . _ .
ll t 4-85 ll '8 50 R 5,700 88 / 4 SEC. CONTAINER ll J - 00T TYPE A CNSI - - 1I m -LOO Ser 1 ll 4 A~. R 14,500 170 / 14 SEC. CONTAIER HPOC-Il ~ "-- - i HN-lCO Ser 2 ll A 5R 14,500 170 / 14 SEC. CONTAINER HNDC
-
ll - f. HN-100 Ser 3 _ll A 5R 17,800 170 / 14 SEC. CONTAIER Hf0C L _ ll .
~ HN-100 Ser 3 Il ' -
cith shield ll -- -
, insert ll R 10,400 125/ 14 SEC. CONTAINER HrOC J -- ,1 1 = ~;.
q HN-1005 ~ r ll Ar 1R 17,000 170./ 14 SEC. CONTAINER HNOC
'
m-200 l B~ 600 R 10,675 80 / 3 SEC. CONTAIER Il 00T SPEC. 17-H HNOC
..
ll - h W-300 ll A 1R 8,000 - / 12 .00T TYPE A j
'
l 00T SPEC. 17-H HNOC i I W-400 ll A 1R 12,000 - / 18 00T TYPE A 11 DOT SPEC.17-H HrOC
~ 11 l m-600 l' A 50 R 13,000 87 / 7 SEC. CONTAINER HNOC . I i .0E0 11 VANS ll N/A 0.5 R 27,000 - 160 N/A VARIOUS II
! , l 3 . - . . wwean e :e nwm-~~n em.-,, m-= mm- =~ ~m
. . . . . . . . . . . .
('* ..' .
'
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;. .,
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'
Proc. No. 9.1.15 Rev. No. 16 N Page 22 of 52
- , ATTAONENT 8
,
GUIDELINES FOR PROPER SIZE WIRE SLINGS & SHACKLES l TAa:.s 1. SArt Woas.oro IAADS oM YAA:oCS TTFES or S'.tscs .
.
*
" l Totalload on two-leg slings
,
(For three-les sling mulupty by 11
; For four leg siing c:citiply by 2) g.jgg
- Nom per it g ,g g cal . , l
-
ye.teleme of see, o ; I boon. tne,
.
.
y '* f % phe),th h Single Choker Basket s de . 30mie aling,Ib sling,Ib U M Ih sling, Ib bn6e)b ; bridle bridle.gIb 3 6 X 19 knproved plow 1 1.350 1,010 1700 2.360 1 330 1.910 1.110 003 steel rope 6 1.S40 1,380 3,680 3.220 3.180 2.600 1,540 0.31 e
*(Fece s! spec.RR-R-571) + 2.420 1,815 4,840 4.240 4,130 3.420 2.400 0.40
e Tsc.cr of ::.fety - 8 n 1900 3,500
% I75 2.550 5,500 7,600 5,050 6.650 5.000 4.110 5,@
2.900 0.51
., 1 6.570 3.500 0.63
)L g 5060 3.M0 10,520 9 C0 9,100 7,430 50$0 i 0.90 i Sp!:s e'!L.e .cy - 50', 7,000 5450 10000 11250 111CO 9.900 7.;oo 1.23 4 1, 9,000 6.750 18.000 15,750 i 15. ,000 1.60
,
Rope diameter ---+- 1 11.200 8,400 21400 19,600 i 19 400 15.900 11.?JO - 2.03 jl, 1 11500 10,350 27,000 l 26000 , ; 23,900 19,550 , 13.500 2.50
,
I ! Ifen m t:echsin 6; 1.710 1410 ' 3,420 3,000 l 2.9*0 l 2.420
'
1.*10 IM d -
'
' 1545 2.130 3,690 4,G50 , 4.040 4.030 1845 2.75 .
4 (ASTil spec. A 56-39) 4.350 3,250 5.750 7.650 ' 7,600 8.200 4,350 4.30
- , 6,415 4,820 12.830 9.100 6.415 6.15 Tactor of intery 5 8,s50 6.630 17,700 11200 15.500 l 11.150 15,150
> , 12.650 1.MO s.20
-- 11,750 8,500 23 W) -
V O
20.600 l .20.400 16.650 . 11.775 10.45 . Stock diameter - . - 16 15.350 11.500 20,700 26.900 26.650 21.7n0 't tram g;10 It , 19250 14,400 l 3.9,500 33,700 33.500 27,250 IU. fA
.. . . . . . . . . . . . . . .
TAata IV. Sars I. ores on SsAcuss' ] . , . . - Shank, i Safe load, Pia, j Inside iridth,'Ineide length, . Ibt i I l in, f
.) 2,330 -
L
{{ 1 <
s _~~ f, - .
*g 3,530 < '
y 14 1 T~ < 4,420 < 19, 2
,
6460 3,650 y It 2p , n 1 1 2u 1 11,310 tc 1 3e le 13,360 1< - 1 , 3 . 16,500 1-- 19,960 10 2 3d Id 19 ,2e &j 23,740 " 14 !< .
1 *,900 1<g . 2,. IJ 3%*40 2 ! * S}
-
2" 42420 2) l 3f l 6f
* c.1. Ie.,r, a.e..e at h,s t sater swer o . - - ( - ' <
NOTE: Tables taken from " Handbook of Rigging" by Rossnagel, Third Edition.
- I t
. .
-
- ._ - -. .
~ , _
,9 : w ,- w a - ,.,.e,e..e>,w -.-r, n .~~ ,.
, , , .. ,,' -
Proc. No. 9.1.15 1 Rev. N j Page 23 of 52
j ATTACFNENT C
TABLE OF Al and A2 VALUES FOR RADIONUCLIDES I ELEMENT & ATOMIC NUMBER RADIONUCLIDE3 A1(C1) A2(C1)
(Special Form) (Normal Form) :
- I ACTINILM (89) Ac-227 1000 0.003 Ac-228 10 4 ] )* AMERICIUM (95) Am-2415 8 0.008_ ._ , Am-243 . _ 8 0.008 -
-
, _
ANTIMONY (51) Sb-122 - 30 30 , Sb-124 5 5 Sb-125 40 25
'
ARGON (18) Ar-37 1000 1000 - Ar-418 1 1 Ar-41(uncompressed) 2 20 20 l ARSENIC (33) As-73 1000 400 1 As-74 20 20 . - -
! As-76 -
1 . 10 _ '. ~ C - As-77
~
J 300
- -
-
.2___,
_
--._
20 ,i_ , _,._]_;:--..
.
_, -
,
-
At-211
-~
ASTATINE (85) 200 7 ;f
--
~
-
BARIUM (56) Ba-131 40 4 0 _.' ~ ---
- -
Ba-133 40 10
~
~
-
Ba-140 20 J
; 20_ f __ __ m ; _
y-BERKELIW (97) 8k-249 1000 17 _
-
_ _ BERYLLIUM (4) Be-7 -- 300 300 $ -i
..
' ,
- -
. ._ : .. . ,
- .
l BISMUTH (83) 81-206 5 5 - - ' .- - - 81-207 " ' ~ "- 10 10 --'. -. i Bi-210 100 4 1 -
'2 rf-
~
81-212 6 6 .?. t
- .
?
'
BROMItE (35) Br-82 6 6 i Br-77 70 25 -- b - - t . .
*
CADMIW (48) Cd-109 1000 70 j Cd-ll5m 30 30 ~. _
~~ .
Cd-ll5 80 20 .n ~~ l(
! CALCIUM (20) Ca-45 1000
._
Ca-47 20 20 . ~ . , . ...
.: - ' .. T.'
.. *
" u, . [ .f * -
_ y: 4 - " -
* '
.- .
'? ' ~~- =
.
-
. * !. '.
..
~
*-
Proc. No. 9.1.15
*
Rev. No. 16 Page 24 of 52 ATTACHMENT C l t
,
TABLE OF Al a'd A2 VALUES FOR RADIONUCLIOES (Cont'd) ~ L ELEMENT & ATOMIC NUMBER RADIONUCLIDE3
# A1(C1) A2(C1)
(Special Form) (Normal Form)
,
CALIFORNIUM (98) Cf-249 2 0.002 Cf-250 7 0.007
) Cf-25 2 0.009
?
; CARBON (6) C-Il 20 20 t C-14
-
._
-
1000 60
. . - - . .
CERIUM (58) Ce-139 100 100 1 Ce-141 300 25 d Ce-143 60 20 Ce-144 10 7
., .L CESIUM (55) Cs-129 40 40 ! Cs-131 1000 1000 Cs-134m 1D00 10 "
Cs-134 10 10 Cs-135 1000 25 l} Cs-136 7 7
-) - - --
Cs-137 30 10
-
_
-
~~
.'
j__ ~ lCl l~ 36
~
7 ~ CHLORINE (17) _ 300 ~ 10 'E Cl-38 _ 10~~'
- - - ! 10 ) ._, CN10MIlN (24) Cr-51 .
600 600
. . - -. _ -
c_ _ COBALT (27) .Co-56 _ -~-5 5 _.._--n_-
--
_- ~. Co-57 - _
~ ~
90 ~ 90 ' q _
-
Co-58m - 1000 1000
?q ;- . - .._- 1
__-~ . - Co-58 . j 20 20 -
-
. := 7._- :. __
- _ =~ - Co-60 : .---
~7_
.
-
.--
.
^ - -
; . :_-
.
- -
-- .
j -- COPPER (29) _ _ Cu-64 _- - -. 80 25
.
c. - - Cu-67 -- 200 - 25 (
~
CLRItN (96) Cm-242: '
-
200
'
Cm-243~ 9 0.009 Cm-244 0.01
-
-
r
' ~
On-245 6 0.006 _- - Cm-346_ - 6 0.006 'l .._ _ _ DYSPROSIUM-(66)- . Dy-165 - --- '
- - - -
100 - -
- 20 - -~ ' -
__ Dy-166 -- - 1000 - 200 ( ERSIUM (68) ~ Er-169 1000 25 Er-171 50 20 ^
---
- : n- . _
_
.
-
..~_
--. , _-
g
.:=;-, . ,
_
-
^
. - - -- ~_ i~M' -. _ , . .
.
~'
. . .
_ ' W?ii'?.M.-Dif.E9E= Talin %2_4iW~=yn]]+iW%%e&2f:AbMcMM-b +L>;2M.%D ~ %?%7P!Wah % an
'
i'. ' j '* . . j ,, Proc. No. 9.1.15 l , Rev No. 16 Page 25 of 52
' ~,l '
ATTACENENT C
'l TABLE OF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd)
ELEENT & ATOMIC NUMBER RADIONUCLIDE3 Al(C1) A2(C1)
(Special Form) (Normal Form) , EUROPIlN (63) Eu-152m 30 30 Eu-152 20 10 Eu-154 10 5 ;. Eu-155 400 60 q
i_ FLUORIE (9) - F-18 20 20
~
GADOLNIUM (64) Gd-153 300 100 Gd-159 300 20
{ GALLIUM (31) Ga-67 100 100 1 Ga-68 20 20 Ga-72 7 7 r)
GERMANIUM (32) Ge-68 20 10
-
Ge-71 1000 1000
.,.1 _ .= . GOLD (79)T Au-193 -
200 200 -
-
-
._- -
Au-196 30 30 J _ _ .. = Au-198 40 20
~1:-r
-
._ . ~ - - Au-199 200 25 y
y; HAFNIU4 (72)_ Hf-181 30 25 l{- }_ HOLMIUM (67) Ho-166 30 30
'
HYDROGEN (1) H-3 (See Tritium)
- , - ' Q _ _ ILOIlN-(49) _ In-lll 30 25 - -
_
. __
In-113m 60 60
<
C _' - , _ __ In-114m
*
30 20
~ -; -
_ In-ll5m 100 20 n IODIE (53) I-123 50 50
# _ .--
'
--
I-125 1000 70
-
I-126 40 10 I-129 1000 2 h-l. u;-
- -
I-131 I-132
7
7
.. .
_ . . _ _ __ _ - ~ I-133 30 10
--
_
-
I-134 8 8
.
I-135 10 10
. -gm .m u y-u -. - .;.
g *
,,!,et N 8 *' '
.
.
-
..
.
.
h~
-
Proc. No. 9.1.15 Rev. No. 16 'I Page 26 of 52 I - -
-
ATTAO+ENT C
'
_ _ TABLE OF Al and A2 VALLES FOR RADIONUCLIDES (Cont'd) ELEENT & ATOMIC NUMBER RADIONUCLIDE3 A1(C1) A2(C1)
(Special Form) (Normal Form)
[t IRIDILN (77) Ir-190 10 10 Ir-192 20 10 Ir-194 10 10
{
-
_ IRON (26) Fe-52 5 5
[ :
~
---- .
Fe-55 1000 1000 - l
- -
Jl . -
-
-
Fe-59 10 10 I
'
YPTON (36) Kr-85m8 3 3 Kr-85m (uncompressed)2 100 100 l' Kr-858 5 5 Kr-85 (uncompressed)2 1000 1000 Kr-878 .6 Kr-87 __
- -_: 2 _ .- ..---
__ _(uncompressed)2 _ . r. --- _ 20 _
.
.
--
::_
-
- -
- La-140 30 -
-
-
-
-
_ LA.THANUM-(57) -
-_-J
-
% ;. .
:--: - -
- . --y - . -
N r - ~3 _;- -f ~ :
- . .
_
-
3 _ LEAD.(82T .J ~, Pb-20ln 20- - == 20 - n -?
.;
~
Pb-210 100~ ~
-
~Pb-212 -
~
- -5
_-- - ~'_ . . ._ _ _ _ _ _ _ , _, _ .- ._ -
-
LUTECILN (71). _. -Lu-177 300 - 25 . -
--
-. _ - - = .
'
._ _- .- __. _ .-
_ x -
- '~ ^~
# ~
Mg-28 6 6
--
MAGNESIlN'(15)
=.
-
-- , .
~
t _ = M .SE (25) r___.Mn952 7__ _ . _ _ 5_ . - _~ m _~~~_~~ - -- 20 -~ _ __
".
_ __
. - . _ _
.. -- Mn-54 _~-~~1 _] -
20 ;-
. :_.. ::_ .
~
. _- ... ..._Mn-56 ._ ,._y . 5 . _-
-
-
, _-
-- -
-_ _ _
_
- .I ERCLRY (80) . -Hg-197m 200 200 i i _ -
1~ ,' . - - ; 7.- - Hg-197 _
~. - 200 -
_ ; 200 .
. _ 'l - '
~
- Hg-20 _
:~
.
.- - - .
.
___
-
-
MIXED FISSION PRODUCT .MF-P_ _ 10 ~
. _ _ MOLYBDENUM _.(.42) . _ _ Mo-99___..____ _ __ _- - - _ 20 --- _
-
,
NE00YMIlN (60) ~ Nd-147 100 20
! ! Nd-149 30 20
-
_ :.: - 3:. .
~ '
-
, . .
- , .-
-
-
, .
__
._ _ . .,
~ ~
_ . .
-:
_ . _ .
-
.
, . _- . ,. __
. , -
' _- jr * .~~l{ '
.. -j -' .-
..
' * f *. ~'~.y : Q - .
- "., .- 3 u
..- g -...--:.-
_ _ \] . .. _ - = _ . n-- - _ : - ,-- ,. . .- ,wgg.g. - - - _~~~ ~. .. ; L - .: . -
I
. . ,* l
Proc. No. 9.1.15 )
.. '
Rev. No. 16
, l Page 27 of 52 ) ATTACMENT C j TABLE OF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd)
ELEMENT & ATOMIC NLNBER RADIONUCLIDE3 AI(C1) A2(C1)
} (Special Form) (Normal Form)
NEPTUNILM (93) Np-237 5 0.005
.
Np-239 200 25 NICKEL (28) Ni-59 1000 900 Ni-63 1000 100
. . N1-65 10 10
_
~
NIOBILN (41) Nb-93m 1000 200 , 2-95 20 20 Nb-97 20 20 NITROGEN (7) N-13 20 10
3 OSMIlN (76) Os-185 20 20 j Os-191m 200 200 Os-191 600 200
. . . . .
Os-193 100 20
. _ -w - . - _ . -
-
Pd-103 ~ 1000_ 7' s
' -- .-~ ~
PALLADIlN (.46) 700 . S~~ -
- -
Pd-lO9 100
-
-g -__ _
- _
,
, . _ . .. . ' . -
_
- :;- - n _
-
_
'
'
3[7 '"
~
PK)SPHORUS (15)~ P-32' -~ 30 ~ 30-q'='~ _ PLATINLN (78) Pt-191 100~ 100 4_.7-
-
j- __
- . . _ _ _ _ . . - - Pt-193m -
200 200 n- - _ :2 - -
--
Pt-197m 300 - 20 =z__, Pt-197
-
300 20
-
. - - - _
,
.- . . -
_ b{~'-- ( .g .- _~' PLUT0NItN (94) Pu-2384,5-
-r -., 32 0,003
. _ ~ '.-- '
._ Pu-2394,5 _____ . 0.002 _
Pu-2405 0.002
-
i 3 .2. --- _ _ _
-
.
-- -
,
Q ~ - -- -,
.. ._ _
Pu-2414,5 _ 1000 0,1 .'j c _ t
.
_ _ Pu-2425 3 0,003
,t ,--
Po-210- ~ d, :?-:=-- _~[ E 200
. POLONIlN (84)
-
- -
: -
{ -[[-2 ~
~
POTASSILH (19) K-42 10 10
*
, K-43 20 10 __ .. _ . .] _,n PRASE00YMIlN (59) Pr-142 10 10
- i_- . .; - _ . . Pr-143 300 20 -
y (_ .
-
. _
_.
- : ;._a-- -
-
-
,
-
I ___' _; _
-
-
. . :". . t -
- ~~
- -
-
. . - ;,. .
_
~
g_ w eg;*-
'
,% . __
-
.
-
4 _ % i*E'=s~ ~ '* T[ .1._, _ __
- . :d __ ,_ __
-
$K.ifsTeNPid6Ef4As46%5E$sandNIMs36Oh AN4f6EME?EFQTO5EN#*i NEie< E
' .
i '* . I i Proc. No. 9.1.15
[ ,,- Rev. No. 16 t
*
Page 28 of 52 ATTACH 4ENT C
'
.
' '
TABLE OF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd) ELEMENT & ATOMIC NUMBER RADIONUCLIDE3 Al(C1) A2(C1)
(Special Form) (Normal Form) . '
PROMETHILN (61) Pm-147 1000 25
,
Pm-149 100 20
~
PROTACTINIUM (91) Pa-230 20 ; Pa-231 2 0.002 -:
'
Pa-233 100 100 , _ RADIUM (88): Ra-223 50 Ra-224 6 Ra-226 10 0.05 Ra-228 10 0.05 RADON (86) Rn-222 10 2 RHENILN (75) Re-186 100 20
, Re-187 Unlimited Unlimited i, Re-188 10 10 Unlimited Unlimite .
Re-natural
. -
_ _
,
__
. ,. - . . - . _ ~
RH00ItN (45) . _ 1000 1000 _- +fl_ i
-
i : e - - -
-
-
E Rh-103m
-; _ . ..
Rh-105 200~ 25 - . _ _ _ ~ - ~. 2 -
)__ 9
. .
.-
_
- RUBIOILN (37) Rb-81 30 25
],__ -
. . _ Rb-86 30 30 __
a
- ~~ ~~
Rb-87 Unlimited Unlimited ~ j i~t .
~
__
,._ t Rb-natural Unlimited Unlimited -
RUTENItN (44)_ Ru-97 80 80 . A g[ - -. __ . - ~~-- -
-
.Ru-103 30 25 ..
V -
.r _ rr r- Ru-105 2 20 20 -
l'- _
~
"
~_--
-
- Ru-lO6 .
-
10 7
-- .. . ;. . -
SAMARILN (62) Sm-147 Unlimited Unlimited
.f . , ._ Sm-151 1000 90 ,
300 20 _
- '
'
Sm-153
. i l' SCAf0IlN (21) Sc-46 8 8 i Sc-47 200 20
-
Sc-48 5 5
.j
~
[,, SELENItN (34) Se-75- 40 40 (- SILICON (14) Si-31 100 20
-
. ~ _ m
. . _ - 1
-
i
. ;i - --
.. .-. _
.
.
-&;
*
[.- _ l ; .- __ ~~ [[
g.ex ag:=wQg.a.u . m ., , q m =ns m:;rsy s.;.= 7 s== 5 m m = m y m m r:n w . 3 7
.. . 1- .. .i 'l - Proc. No. 9.1.15 1 ' Rev. No. 16 1 Page 29 of 52 ATTAC W JT C
-
TABLE GF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd) ELEMENT & ATOMIC NLNBER RADIONUCLIDE3 A (C1) A2(C1) f (Spec al Form) (Normal Form) .- SILVER (47) Ag-105 40 40 Ag-llCm 7 7 Ag-111 100 20 SODIUM (11) Na-22 8 . Na-24 -- _ 5: _ _ _ 5 __
-
-
3 _ _ STRONTIUM (38) Sr-85m 80 __ 80 - +j Sr-85 30 30 Sr-87m 50 50
> Sr-89 100 10 Sr-90 10 ? Sr-91 10 10 Sr-92 10 . 10 l SULPHUR (16) S-35 1000 60
.) _
--
. .
'27 ~i
~
1 TANTALIUM (73) Ta-182 T 20 ' - - - ' 7-:_20 4 _ ._-- _
-_ - _ \
TECHNETW (43) Tc-96m ~ Tc-96~ _
~~
-
1000 6_
:
_
[M00 _ -g
..- ~
-
[
l
~
Tc-97m 1000 ~ 200 - j Tc-97 1000 -
-
400. ~ ._
;- - - ~~
1 Tc-99m - 100 - _ 100 -- -f f ,
] y Tc-99 - -.-
1000"_:- . _ _ _251._. _- . _ x-
:. __
, - .. . a 1000 _ -
- . .
',
_ _ TELLURILN (52) Te-125m 100 - _ j Te-127m 300 _~_ ~1__._20? J _ _ - T i Te-127 _-- - 300 __ -_20 - ~
-_ r- -_ ~
~
T- ' 1 Te-129m 30 .
~ 10 , - 1 -
j Te-129 100 .- :- 20 : _ .= . =,- I Te-131m 10 --
~:10 - ~ -r } Te-132 7 M 7-~~~'-~
1.!
-
=is - ;-.! _
J TERBIUM (65) Tb-160 20 . ~i10; - _ - p_
.
- _
} TPALLIW (81) T1-200 20 20 i T1-201 200 -
200 - - - il T1-202 40 -
~~
40 -
- ! T1-204 ' - -
300 - - ' ' !10 2 -
~
~j- -
. _- .. .
.1 . _ . .
-
. _ .
'
r -- -
.
_ ._ i) . - =_...-=._r=-g.
>; -
.- .
-
_
..._:_.._~ ' ~
_
.
-- - .__.:
.. :
.g-- w . --
m:L: ,u
.- _:: , :p& -t ql
.
-. .
;-l--?--l- 1,2,?' S . ;_ ^& .
_ _ _
. *
d:* e, ] ,, Proc. No. 9.1.15 il -
-
Rev. No. 16
.
Page 30 of 52
. ._
ATTACFNENT C l
: . ) -
TABLE OF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd)
~ ! _-
ELEMENT & ATOMIC NUMBER RADIONUCLIDE3 Al(C1) A2(C1)
.,{.
-
-
_
(Special Form)
_
(Normal Form) ,
A THORIt.N (90) Th-227 200 d 0.008 Th-228 6 4 Th-230 3 0.003 W Th-231 1000 25 l Th-232 Unlimited Unlimited 3 . Th-23 n .:_ 1 ? Th-natural- - Unlimited _
? -
--
. Unlimited
-
_, : Th-(irradiated)6 __r ___ i. '
,
. - _ :.
~
-
THJLLIt.N (69)~ Tm-170 300 10
{ Tm-171 1000 10
,
TIN (50) Sn-ll3 ~ 60 60 i Sn-119m 100 100
- Sn-125 . _ 10 10 ., -
j TRITIUM (1) H-3 (uncompressed)2 ~
~
t 1000
-
_ H 32(compresses)J. ? 1000l=: 1000 H-3.(activated 1'-Z.R - g
~
"
^?
! -
-e __
- - . - m- filuminous paint);1000 9 1000
'. . .
-
H-3.(absorbed on s511d -~~
- -- carrier)
'
'M' " r 1000
~
1000
-
H-3 (tritiated water)l000 1000
-
H-3 .(other forms)_=g_ g.20.- ,. ._
S TUNGSTEN (74) - W-181 - h_=; --20h- 100 W-185 - --
-
"--~1000- 25 .
i W-187- _~ _ - & %40, 20 _ . _c _ ._-- _ - - -. .-
- .
T 1.: t-~100t _ y _ URANIUM (92)
-
'U-230 ;c.flC;3 ~
y U-232 0.03 U-2334 . _ _--__ _ 7 10 . -- U-234 . ~~ m ._ r '-100 ~ 0.1 ' 4 .-
~ : U-235 _ ,.;- . 10 .2
_v
~
j - U-236 -~ : r 200 i U-238~ ~~.C. Unlimited Unlimited U-natural Unlimited Unlimited (See 173.434)
, ' '
U-enriched 4-less than' ~20% ; Unlimited Unlimited (See 173.434) U-enriched 4:a ._ . . . _ _ _ =
--
greater than_204- 100-~ Unlimited (See 173.434)
-
U-depleted -
: Unlimited Unlimited (See 173.434) 'k .
U-irradiated
~
_---- ---- !
~'
- - . . - _ ' - -
.'- --
_
--;..__.-
j
,
, , . ,
. . . .
- - -
-_
_-;;
-g_-
_
,
'j j ,[M; . a - - [ C, L-h J- > ' E Gi ; 'iit:i~5.T 5 M EC- 3 . R..'t. .p:- W Y@ ht?s W * w M ~ Y . ;~'". ="% _ _ . .
' W " 3*M ** ~ '- "#
.' . . . "
Proc. No. 9.1.15
: Rev. No. 16 Page 31 of 52 ATTACHENT C TABLE OF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd)
ELEMENT & ATOMIC NUMBER RADIONUCLIOE3 Al(C1) A2(C1)
(Special Form) (Normal Form)
VANADIlN (23) V-48 6 6 XENON (54) - Xe-1278 5 5 Xe-127 (uncompressed)2 70 70 Xe-131m8 10 10
-
Xe-131m (uncompressed)2 100 100 Xe-1338 5 5 Xe-133 (uncompressed)2 1000 1000 Xe-1358 2 2 Xe-135 (uncompressed)2 10 70 ,
( YTTERBIlN (70) Yb-169 80 80 1 Yb-175 400 25
_ _ , [ YTTERIlN (39). Y-87 20 20 &
~ ~ --_ ~ ~ ' i-- - ~~"-
Y-90 10 10
'
5 . Y-91m 30 30 Y-91 30 30
=. _ Y-92 10 10 --- .- Y-93 10 10 -
ZINC (30). ^ Zn-65 30 30 ' T~ Zn-69m 40 20 2n-69
'
i -- _ __ . 300 20
~ ~ ZIRCONIlN 940) Zr-93 . 1000 200 -
_- ' Zr-95 20 20 Zr-97 20 20
.. .
lAtomic number shown in parenthese Uncompressed means at a pressure not exceeding 14.7 psi (absolute).
- - - 3 Atomic weight shown after the radionuclide symbo (' 4Fissile radioactive materia '
--
_
== $' g -
e2 #
.
**.-,
~ ~
- -
-
- . -- - ...
. .
O .
-
-
Proc. No. 9.1.15 Rev. No. 16 Page 32 of 52
.
ATTACHMENT C
> .
r _ TABLE OF Al and A2 VALUES FOR RADIONUCLIDES (Cont'd)
-
a f( . SFor shipments solely within the United States, the Al value is 20 curies americium and plutonium contained in Am-Be or Pu-Be neutron sources or in nuclear powered pacemaker _ 6The values of Al and A2 must be calculated in accordance with the procedure .
.specified in 173.433 of this subchapter,.taking into account the activity of the -. ,I fission products and of the uranium-233 in addition to that of the thoriu . _ .
_
.
._ . .
.3-- . _
7The values of Al and A2 must be calculated in accordance with the procedure -- specified in 173.433 or this~ subchapter, taking into account the activity of the fission products and plutonium isotopes in addition to that of the uraniu < 8Compressed (greater than 14.7 psi (absolute)).
:
_ . .
-
. :. ^
. _ . .
~
--' <
.: , . - .:- . ~ _-~ ; [-
_
,.
_
- _ . - ~ . , _.. -- -~ _
- . . _ - - -
'
' ~ ' --*
. _ .-- e- -[
_
.,.,y - . . ,-
; . - _ _ .. . .
~ *-
. . . . . . .
-,
***
~
~ -
.
-- _
-~
-'- . . - - - . , . - - _ .- '
::= -
.- - -
-
:.
_
~
.l- ^ ri . _ . -
- . ..
_ _._. . . .
*
-
M.- ei e
.. . . . .-
'_..,_.- f
-
* *
me. - - - - * *-~
'
^ ' * * . * _
-
'
_ _ . 3 - , _
-
_7 -
-
_ l ,
;
-
-
o . .- _ : .
.
"'
- .$, _
..
'
~-
f.m. .';. :.* _
.
-
. . _
~
~
.
-
.
.
. ,
y - _- _w..: e1 . _
~ ~ * - ~ "
_ __
.._,.. - -
no..+* . A
- * - ~ . ~- . '*
*,+.
-. . _- ,,,
(
-
'
'h
-- - ' "
.+,. ~mM -
- .., &9 %" _ .-
:% . .
:; .
....:..,-
--
j- Y* ^~
.
--~.f_j
.
n . ;. :3; w a 1, x - . -= _ s
-
.- _ . . .
'
+ ..
! l
'
l ., Proc. No. 9.1.15
'
e Rev. N Page 33 of 52 f_ b ATTAC W NT D (lOCFR61.55) Table 1 l l l CONCENTRATION (uci/CC) l L l RADIONUCLIDE l Column 1 l Column 2 l l l Class C Limit l Class A Limit l
'
g l C-14 I 8 1 l
} l C-14 in activated metal l 80 l 8 l l Ni-59 in activated metal l 220 l 22 l g i Nb-94 in activated metal l .02 l [, l Tc-99 l 3 1 l -
1 I-129 l 0.08 1 0.008 l l Alpha emitting transuranic nuclides l l l l with half-lives greater than 5 yrs l +100 +10 ( l l I l .Pu-241 1 *3,500 l +350 l I cm-242 1 420,000 1 *2,000 I i * Units are in Nanocuries per gram
-
s Table 2 _
.
i T. _
'
i l CONCENTRATION (uci/CC) l _ ' ~ h l RADIONUCLIDE l Column 1 l Column 2 l Column 3 l
;i l l Class A l Class B l Class C l l l Limit l Limit l Limit l l Total of all nuclides with half- l l l l __
l lives less than 5' years l 700 l No Limit l No Limit l
'
l H3 1 40 i No Limit l No Limit l
- -
l Co-60
-
l 700 l No Limit l No Limit I
-
l Ni-63
'
y l 3.5 l 70 l 700 l j l Ni-63 in activated metal I 35 I 700 l 7000 l 1 l Sr-90 1 0.04 l 150 l 7000 l l Cs-137 l 1 1 44 1 4600 l
-,
d NO LIMIT - Although no limit is specified, practical consideration such as effectis ij of external radiation and internal heat generation on transportation, j handling and disposal will limit the concentrations for these waste ._ t These wastes will be Class 8 unless the concentrations of other nuclides ,l in Table 2 determine the waste to be Class C independent of these
- (
f3 nuclide ) . _ .
-
i . El - T - .a~
- :-.-,. ~ * * * * * * " * * ' ' l,,
.
l
.< '
. ~* * '
Prc. tb. O.l.15 .
'
r ATICDKHT E Rev. Des. ~l4 8 (
#
* j Page 34 MI I * - I SCAL.IIC FN'IGts f tTI HAltE YM4GE l- (Ellio4ite o DY SAI orte Mmti 1964
]
- b i St allna Fartors
'
t ,
'l '
a l l l All I l '.' ~ I j, 4 l Scaltry l All l Kalne il $sples th! s fiatcli *
.
t
.st Nic!!de l f%r Ymikee l Reactor l Iter Evaguaretor [ . l ,. . 's .g paclide l I
Sarmies 5: soles All Sisyles l' Coolmit l
' Saustge nott<ue Sacar l-
.
.
i .- ., 3n . . ... ... ,
( .'
h ,
. *! *
1*C * * "* "" ( 5.70E-6) (4. %E-M (l . DE-H ( 7.o1E-4) , , i? ~5 ye % (4.ogo.,3,io-1 ( l . i .o.6),1@ <l.l.o.6),io-o (l.7.o.2),io-1 (l.1.o.2)=100 ( I . I .o. 5) = i ou ( 2.4.o. 8 ):100 jl ~
' ~59nt % (1.2.o.5) 10-3 (2.4.o.9) 10-7 (2.5.l.7)=10-2 (2.9.I.3)=lo-3 L(2.2.o.2)=to-2 (6.a.2.3) lo-3 (( 7.o.o.7)=io-2 ;
i .
*
M1 ajco ~(3.i.o.3),lo-1 (,.s.5.2)=to-1 (8.0p.e)=10-1 (2.3.o.2)=10-1{(2.s.o.2)lo o (9.313.2).10-1 ( 6. 5.o.s ).100 1 !. 90st 137cs (4.0 1.5)n10-2 (3.e.l.8)nIO-3 ((I.I+0.7)=I0-3 - (3.7 2.2)s10-1 l(2.0 10.2)n10-3 (6.4g.4)sto-4 (e.7p.6)sto-4
-- *
j % .. .. . ..
[ ;
I N ic 337Cs (2.9 2.7) 10-3 [ : TBI 7 37cs '(1.4$o.6)=to-3 l ! e
.
i ~743 N __144ce (4.0.o.6)m10-1 (1.510.6) 10u (1.9 1.5)nlW {(1.10.9)=10
3 (2.1.o.4)=101 (1.7 0.5).!# (1.9.o.e)mitP 74km 344ce (2.2 0.4)mlo-2 (( g,110,4),10-2 (3.5 5.o)mlo-3 l (1. l e_o.8)n t o-1 (1.1.o.3) 10-2 (8.411.3)mlo-3 ( 3.4 1. 3)m 10-3 . 5 litJ 5 yr 144Ce (3.t 11.1)m10-2 (3,9 4.6) 10-2 7,9 2.2)nlo-A '
(1.4.o.5) 10-3 ( 5.o.a. 5)s to-1 (5.1.o.4)mlo-7 (6.1 1.2)nlo-2 i . ! .,' 238,239, , , 240 m ] *
24 Ige; 243,244Cm
'
l - Mbo 14te (1.5 0.7)m100 (3.4 1.2):102 (g,3 o,9)n103 (2.8 1.6)n1o 3 f(6.51.olalol (1.4 0.7)n1o3 (7.6 2.7)alo2
'
.
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Ce-144 l Co-do l l l l(3.57E-4) l(1.54E-4) l(7.14E-4) l(1.32E-3)
?, NOIE Uuts as C-14 tactors aie"UEi/ge, Ma tiilt on UUer # m' tors , ' Scaling not applicabl l "Scallrg rur!!de ruit curmitly identified. Use Mt. values for estlantion guarpose ' ' "' *
l .".Use
*
i
'
-; usereactor coolant cmcmtration concentratim values from analyses and estimate of like maste of water samplesin west for estisetton purposes, j f .Ratlos were develq>ed fran run-selghted evers}es of ruclide concentration ,
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n .' Form No. 9-1-15-HP-10I-DATE: _ Rev. No. 16 R.C. SU Date Revised: WORKSHEET FOR DETERMINATI m 0F WASTE CLASSIFICATION (10CFR61.55) Page 35 of 52 l l l l l l l Class A l Class B I Class C l l Table 1 l Scaling l Scaling l Scaling l Isotopic l MY l l cl l cl l cl l Isotopes l Factor l Isotope l Isotope l Conc. l LLO l imit l Ratio l Limit l Ratio l Limit l Ratio l l
'
l l l uci/cc l ucl/cc lucl/ccl(uci/ccl l uci/cc l l uci/cc l l l 1 I I I I I> I I I////////l I l l C-14' l l l l l l 8E-01 l l d I////////l 8E00 l l l l l l l l 1 I I 1////////l l l l Tc-99 l l l l l l 3E-01 l l ..d l////////l 3E00 l l l l l l l l l l l I////////l l l l I-129 l l l l l' I 8E-03 l l d I////////l 8E-02 l l l . . I i I, a I i i I l l l !- 1////////l l l ll TRU l l l l l - l 10 l l 'd l////////l 100 l l , l - aI I l . I li , i l l l I////////l . l l i l Pu-241 l l 'l oi l l l 350 l l d I////////l 3500-l l li a1 I l- l l' I I I I////////l I l ' l Cm-242 l l l l l l 2000 l l d' l////////l 20000 l l I RnTIOS I////////l I////////\////////l////////\ l ' l Table 2 I .
'j l t
l' Isotopes l l l : I I I I I I I I . I I I I
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l H-3 l l l l ;
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I l 1E00 l l 4.4E+0ll I 4.6E+031 l I i , I l l , I I l l l l l p'i .j 1i (l-l .less With thanII/ ! l' , l'i . l lt l l l l l l l 7 l 5 year l l
-
I 'i- l l l 7E+02 l l b l l b l l 0 .I I RATIOS i I////////l I////////l I////////l l
:
i j c. Units are nanocuries/ gram , It is not necessary to list on manifest any nuclide whose ratio is less than
,'f,V .
b.(Nolimi ,
.
.ql 0.01 except C-14, Tc-99, I-129, H3 f,1j i l' ..p , p.~
'
, If Class A limit is exceeded tne waste is Class . ,. .
h .% , NOTE: For resin assune 50% of Volume"is liquid and 'use reactor coolant H-3 value to determine the amount of H-3 in shipmen . i h. I i -l l
i 6' ..' $' M. i '. ' I 4
'
, e
'
.' .
* . ,, Fom. No. 9-1-15-HP-1 l Rev. No. 16 ) *-
Date Revised: 5/9/85 j Fage 36 of 52
'
RADIOACTIVE MATERIAL PACKAGING AND SHIPPING QUALITY ASSURANCE RECORD
SECTION SHIPPING INFORMATION (Radiological Controls) Shipment Number J l ICarrier I i Tractor License No. i l lDate of Arrival l Trailer License No. l ' l l l Time of Arrival ' l Cask Type 1, I l Driver (s) Name l l Cask Serial N l l j l - l l Shipoing Contracter i l l j SECTION II. DOCUMENT VERIFICATION l _ DATE
- -
l RC l 00AD l' q l ITEM IINITSITIMElINITSITIME l
) l (Exclusive i i l l l } l Initial Radiological Survey Taken use Veh!cle) l l l l -l l ~l l l l l l 2. An updated copy of the consignee license to l l l l l < l recieve radioactive material is on site l l l l l ll '
R l l l l l l l 3. Inspect the transport vehicle (exclusive use l l l l l t i only) attach Form No. 9-1-15-HP-1 l l l l l 1~ l ._
-- 1 I i i l
{
l 4. Handling equipment to be used to~ load the
~
l l l l l _ l radioactive material has been inspected, checked l l l l
-
l l and designed to handle the intended load weight. l l l l l Attachment B is a guide to insure proper slings l
-~
l l l l l
: I and shackles are use I I I l l
' I i i i i i
~
: l ~ Certificate of Corrpliance for the shipping l l l l l
{. l cask-is on site -
-
l I l l l
-
4 l - - 1 I i l l i l 6. Inspect the cask and tie-down system (chains, l l l l l
: l cables,_ binder, etc.) to assure that it has not l l l l l*
l l- _ sustained any damac l l _l- l : - 3 1 - _2 -
- -.
1 I l l l
} l 7. Cask has been r'ecelot inspected per Proc. 0-03- l l l l _
i l -- I l i l l
>
l 8. _. Cask is marked with same ID No. as on C of C and l l l l l j l H.Y. is identified as a registered user l l l l l ( 10CFR71.85c).
- 1 1 l l l l l
! I i i ! l l l 9. Personnel opening and loading the cask have a l l l l l , I working ccpy of the cask handling procedur l l l l ,
l _ i i i I
, 11 Inspect the cask interior for defects,- l l l l l '
l obstructions to loadino, et l l l - l l J
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Form No. 9-1-15-HP-1
.
Rev. No.16 s *. Date Revised: 5/9/85 '
;
Page 37 of 52 RADIOACTIVE MATERIAL PACKAGING & SHIPPING QUALITY ASSURANCE RECORD (Cont,'d)
'
SECTION III. ' SHIPMENTS WITH ACTIVITV LESS THAN Al or A2 VALUES (49CFR173.475$ I DATE
,
I I RC l OQAD l l ITEM IINITSITIMElINITSITIE l t i I I i i l I i 1. The container (s) is proper for the contents to l l l l l l be shipped, l l l l l l i l i l I i l
l 2. The container (s) is in unimpaired physical l l l l l } l condition except for superficial mark I l l l l j .I I I i l l l l 3. For fissile material, each moderator and neutron l l l l l l absorber, if required, is present and in l l l l l j(2 l proper conditio I I l l l l l 1 1 I l
, ! 4. Each special instruction for filling, closing, l l I l l -
q' l and preparation of the container (s) for shipment i ! l l 1 I has been followe I I I I I J l I i I i ! i 1 Each closure, valve, or other opening of the l l l l l containment system through which the radioactive
' ! I l l l l ; I content might escape, is properly closed -
l l l l 1 , I and seale l l l l 1 1 I I I I } l 6. Each closure device of the container (s) including l l l l l _
! I any required gasket, is properly installed, I l l l l _ . . . ,
I secured, and free of defect l l l __~
~ The internal pressure of the containment system l I l l -l
l will not exceed the design pressure during l l l l l
! l transportatio l l l
-
.1 l 1 l ,
I I j i 8. The case is proper for the contents to be i I I I l _ 1 i shipped (see C of C). l l l l ,'- i l i a i I ' -
! l 9. Inspect the container (s) or cask tiedown system l l l* l l t I (chains, cables, binders, etc.). 1 I I i -
~ ~
3 - 1 I I I l
! 110. Each cask closure device including any required l l l l l l l gasket, is properly installed and secured and l l l l l 1 l free of defect I j .
i 111. The cask has been loaded and closed in-i l l l l l
.
l l
] I accordance with written M.Y. approved procedures l l l l l l and the user check-off sheet has been comoleted. 1 I I I R 1 l l 1 l l 112. All user required conditions listed on the C of Cl 1 l l l
!{j . l _ for the cask have been complied with and l l l l l -
'l I documented and referenced documents are on sit l l l -
i l - i t ,
! 113. Package (s) and vehicle radiation and l l l* <
{ l contamination levels are within the allowable l l l d I limits specified (see Section 6.11.4 and l l l l l l 6.13.3 and H.P. Procedure 9.1.17). l l l l l
}
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!. .. Form No. 9-1-15-HP-1 : Rev. No. 16 l Date Revised: 2/11/85 i Page 38 of 52 ,
- RADIOACTIVE MATERIAL PACKAGING & SHIPPING QUALITY ASSLRANCE RECORD (Cont'd) SECTION II (Con't.)
- l @ l OATE (IOCFR61.55 & .56
? I I RC l OQAD l i l ITEM INITSITIElINITSITIME I I l i I I I i 1. Waste material in container (s) has been l l l l l
,, I classified (see Section 6.6). l l l
'
I I I I i l
,
1 Waste container and/or form meets the stability I I l l l
.] 1 reauirements of 10CFR61.5 l l l l l ;j l l I I I l l 3. Liquid content of the waste is less than 1% ~
V l l l l l of the volume of the waste if the container " I l l l l 1
- I is designed to ensure stabilit l l l l l
? -
1 I I I I l
- ! 4. Liquid content of the waste is less than 0.5% l l l l .l -
l of the volume of the waste if the waste is l I I I i
l processed to a stable for l l l l l 1 1 I I I l l I I I I I I l l I l _ _l ._
., ,. -1 t I I I I I I J I -
1 I I I I 2 - 1 I I I I I - 1- -
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. Form No. 9-1-15-HP-1 !' '- Rev. No. 16 ., -
Date Revised: 5/9/85 Page 39 of 52
<
RADI0 ACTIVE MATERIAL PACKAGING & SHIPPING QUALITY ASSURANCE RECORD (Cont'd) SECTION IV SHIPfENTS WITH ACTIVMTY GREATER THAN Al or A2 VALUES (10CFR71.87) NOTE: Section III, Items pertain;.ng to the container (s) must also be complete l
. I mm l l RC '
OQAD l l ITEM IINITSITIE IINITSITIME l l - 1 1 I l [V l 1. The cask is proper for the contents to be l l l l l shippe (See C of C) I l ! l l d l l l l 1 1 ' I 2. The cask is in unimpaired physical condition l l l l l i 1 except for superficial defects such as marks l l l l l J l or dent I I I I l l 1 I I I I-l 3.~ For'~ fissile material, any moderator or neutron l l l l l
-
3 absorber, if required, is present and in proper l l l l 1
- 1 conditio I i l
'
l-l i I i . l
]' 1 Each closure device of the cask, including l l l l l I any required gasket, is properly installed, I l l l' l ,
I secured, and free of defect l l l l l 4 l t i I i 1
#
1 Any system for containing liquid is adequately l l l l l 1 I sealed and has adequate space or other l l l l l 1 1 span.ified provisierrfor expansion ofte-liquid. i i --l - I h I i l I , I o
*
1 Any-pressure relief device is operable and set l l l l l , I in accordance with written procedure l l l l l y -l _ c.4 _ _ i i i l 1 0 .l 7. _Any~ structural part of the cask which could l l l l l
l be used to lift or tiedown the cask during i l l l l l transport is rendered inoperable for that l l l l l 1 l- purpose unless it satisfies the design require- l l l l l
$~ l -ments of $71.4 l l l l l
:l . . - - 1 I I i l T( l.8.. Accessible cask surface temperatures will not l l l l l
'
t l exceed the limits specified (122*F for. mixed i i l l l l caroo, 180*F for exclusive use vehicle). l l l l l
]
l' l ;- - ---- 1 I I I l _ l 9. Inspect the cask tiedown system (chains, I l l l l
, -
l cables, binders, et l l l l
~
I I I l l l1 The cask has been loaded and closed in i l l l l accordance with written M.Y. approved procedures l
- . l l l l l '
I and the user check-off sheet has been complete l l l R l
-
1 I I 111. All user required conditions listed on the C of Cl l l l l l for the cask have been complied with and l l -l l l documented and referenced documents on sit " l l l l l l l - 1 I I I
'
l12. Package (s) and vehicle radiation and l l l l l
'
I contamination levels are within the allowable l l 1.- l l 1 limits specifie (See Section 6.11.4 and l l 'I g l 6.13.3 and H.P. Procedure 9.1.17). l l l
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Form No. 9-1-15-HP-1
. Rev. No. 16 -
Date Revised: 2/11/85 Page 40 of 52 RADI0 ACTIVE MATERIAL PACKAGING & SHIPPING QUALITY ASSURANCE RECORD (Cont'd)
-
* __ .-
[ SECTION V Final Shipment Verification - . I DATE I
- -
l RC I 00AD l } l ITEM lINITSITIElINITSITIE l 1 1 I I I I l ' l 1. Material to be shipped has a contact and three, I l l l l l foot radiation survey take l l l l l l 1 i l 1 l l j i 2. The outside of each container or cask must have l l l l l - s I a seal that is-not easily breakable that will l I l l l r demonstrate that the package has not been l l l l_ l - 8: illicitly opene (Not applicable for LSA or l I l 1l 1 7, I exempt shipments).- - - l l I~- I l
'
I ~ l I i i _ .l -
-
, l 3. Final health physics survey of the package and/ori i l l l transporter is completed as per H.P. Procedure
~
'
I l l l l l l 9.1.1 I I l l l
- - : I -
1 I I I l l 4. Final vehicle survey results have been verififed l l l l l
-
i l (exclusive use vehicle). l l l l l _c l i i i i l r -- L~ l The consignee has been notified if the shipment T l l _l ! .. -_f - - - a l contains fissile material. Type B or a l l l .. - l . _d; ;- J l Highway Route Controlled Quantit I I' I
~
~ l -
_
-
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-- l .-C.>R~.i T .r - .
I I 6. The State of New ~ Jersey has been notified if. the I l
l l
~
shipment contains greater than 20 curies and willl~ pass throuch the State of New Jerse I
- l l
l l_ I l
'l:Cl-EQ9-l-
":-- l: f TY l . -E
'
j l ._ i l 1 l- I 1# [- 1 l 7. The routine determination required by 10CFR71.87 l l l- l~ ~ l ' 5: 7-- - I and/or 49CFR173.475 have been performed and are l
=
l l " l~" l _-s ~- p I acceptabl l~ l - l L l I 8. Connecticut Radioactive Permit obtained_ for I i .
.. I [J __ nT i l i _ Im
__ll, .~ - ;-- -l._h_;2 _
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I carrie ~ l- l -l
, '
I 9. Copy of RSR mailed to Hittman and called prior
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_l 1 -- -1 5 _lc_Mo -g_ . J. - l l . lc= .li_, 5- W r
-
I to shipment leavin l " l : r"" _.~.r . l l , .
.
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110. Reactor Engineering and Health Physics notified I l' l ~ Gl_ -; . :l 9_. .9 J l if spent fuel & X Core detectors being shippe l l l l ~l d l._ , y ( l I I l_ l ' " U_ -
.
11. Appropriate markings and labels have been adequately applied to container (s) and cask if l I l l -l l 1'~ l'- l -(
~ ;. ,
applicable (see Section 6.7 & 6.8). l l l l~ ~1-
.
j l
. . . _
112. Appropriate placards have been adequately _ . _ .l _ .l _. . l 1 - l ll~=l1l-- NN ;H, _ l- _ l applie (See Section 6.9). l ~~ ~ 'l i Z-?F ,
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. . * ., Form No. 9-1-15-HP-1 l J Rev. No. 16 l I *'
Date Revised: i
; Page 41 of 52 RADI0 ACTIVE MATERIAL PACKAGING & SHIPPING QUALITY ASSURANCE RECORD (Cont'd)
fi I DATE l l RC l OQAD l [ l ITEM lINITSITI411NITSITIE I E . 1 I I I I l
. 113. Driver satisfied with arrangement of load i l I l l i 1
'
(driver's initials). l l l l l
;
'
3 I I I I I l F 114. Shipping capers have been completed.(10CFR20.311)l l l l l l k l i i i l I 115. Radiological Control Supervisor final vehicle l l l l l ];q l inspection complete I l l 4 l , 1 I l 116. Required notifications either by telephone or i l l l l _ i i letter have been mad I l l I l 3 l l l l l l
.l '
l Maine Turnpike l l l l l d I i i l l I j _ l State Police l l l l l
:j .
i i I i l i g i Department of ~ I l l l l
,. 1 Environmental Protection l l l l l 1 1 l l l l l 1( l Mass. Dept. of Public Health - l l l l l '
1 l _- -
-
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g l Burial Site Representative l l l l
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d- - I . .- _~ i l I- I
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l So. Carolina Dept. of- . 1 I _ -l __ l s: _I h} '- l Health if Applicable l l ' l l l '.l 1 - 1 I i 1 l j l Maine Bureau of Civil - -- 1 I i 1 -l 1 l Emergency Preparedness l l l l
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Form No. 9-1-15-HP-10 ij Rev. No. 16 1 Date Revised: 1 Page 42 of 52
CUIDELINE FOR EXCLUSIVE USE VEHICLE INSPECTION _ j Vehicle Identification: _ Shipment N . f Tractor Date
'
Trailer 00AD Inspector
'd g 1 -
l l l~
'
l Items to Inspect _ _ _ l SAT l UNSAT l _ ._
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~
l - l l l _ l I l 7
: l Tires: ~
l
-
l 1. Tread and general conditio . l l 2. Rims and lugs intac I l' I l Bra <e Tuoina ano Hose: l l 1_ -
, "
l Long cno flexible enough to accommodate, without damage, all l l l normal motio l l t l Suitably secured against chafing, kinking, or other mechanical l l l-
! damace'. --
l l l-(!i I C.- Heaalignts anc Reflectors: - l l l - l Heaolamps, turnsignals, clearance lanps, land reflectors intact l l l1-l and functiona .
- - - -
l l l '; l
-
l Mirrors r . _ _
~~
._ l l l-z2 l Two rear vision mirrors one on each silile F l l
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lY l E. Couclino Device: l 1 lA l 1. No cracking, warping or deformation of the fram l l l c l 2. Installation includes a device-for positive prevention of I l l __ a l shiftin l l [_
{ l Fire Extinguishers: _- - -
l l l' I Properly filled and located so that it is readily accessibl l l l" I Brakes:
-
.1 l l -l-l 1. All brakes operativ _ _
; l l _- g-l 2. Low air pressure warning device _present. r l l 71 2 1 1 3. Pressure gauce indicating pressure available'. I i l=..
J l Winoshielo Wipers: ~ 1 I [? l l Equippeo with two automatically operating windshield wiper l l - !O
! l blade l l l _ l '
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Form No.9-1-15-P-2 Rev. No.16 l Date Revised: 4/17/84 Page 43 of 52 l ORIVER INSTRUCTION RECORD ! 1.0 SHIDMENT INFORMATION Shipment Number Type of radioactive material Vehicle radiation levels 1 - contact mr/hr Transport index 2 - one meter mr/hr 3 - two meters mr/hr j 4 - inside cab mr/hr 2.0 EXCLUSIVE USE (SOLE USE) VEHICLE INSTRUCTION (if applicable)
-
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l This shipment of radioactive material is being transported in an exlcusive u_se vehicl . The material is to be loaded by the shipper and unloaded at its final I destination only.
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] Repositioning or movement of any loaded material without the written
}; permission of the consignor is prohibited. - _.
4_, Changing of ~Oie tractor is prohibited without the express consent of Maine j _
- Yanke _
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.:. Frequently check to ensure that the four (4) placards are still presen ; _ ~ - - -
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3.0_ EMERGENCY II6TRUCTIONS _
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;1.- ~In case of an accident, keep all unnecessary personnel clear and call Maine
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~~ YankeelAtomic Power Company, phone 207-882-6321. Give details of acciden .
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t_DAj5[-RadwasteCoordinator
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Y NIGHTS - Plant Shift Superintendent i- - -- 2.3 Notify State Police in state of accident. Give details of acciden y a_ .~. '_ y -- b_ q _,. __ Notify the U.S. Department of Transportation, phone 202-426-183 r Y_; 4.0.- TRAVEC INSTRUCTIONS IN TIE STATE' 0F MAINE -
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- Routinoi Depart Maine Yankee via Route 144 to U.S. Route 1 to Interstate 95
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and enter the Maine Turnpike at Entrance 9. Remain on the Maine Turnpike
. -- - throughout'until leaving the State of Maine. DO NOT DEVIATE from this rout r ._ _
5 - _ Hours of Travel: Transportation of radioactive material on the Maine Turnpike is allowed only during daylight hours (sunrise to sunset).
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I have read and understand the abov Driver's Signature: u - Company: Date: kl.W, - _ . _- _ _
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.T } Date Revised:
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Page 44 of 52
. -
MASSACHUSETTS DEPARTMENT OF PUBLIC HEALTH NOTIFICATION FORM
R j.] The Massachusetts Department of Public Health must be notified of all shipments of radioactive material entering the stat If possible, 24 hour notification is to be i give i, Shipment Number Curie Content oT Snipment
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Date Called Type of Material ':- =
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1. Radioactive waste N Time of Call 2. Radioactive lhundry 1 3. Spent fuel
*[l . Person Making the call 4. New reactor fuel e Other-k .] Person contacted in Department of y Public Health 9 .
Tima and.Date of Shipment
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_ Route through Massachusetts -- - 3f _ _ _ . .
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_1 ' During normal work hours the phone numbers for:the following are:
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1. R. Hallisey (617) 723-6214
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2. G. Swibble .(617) 727-6248
.
3. Emergency (617) 729-9710 j During off hours, weekends or holidays contact one of the following: 1. R. Hallisey (617) 729-5728 ' 2. G. Swibble (617) 387_7768 _ _ _ _ _ . __ ._ , _ _ .
. . _ . .
In the event contact cannot be made in the above manner, call Massachusetts State Police Headquarters (617) 566-4500, Extension 237 or 238. Ask for Communication Room and ( - explain circumstances.
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, Rev. No. 16 _ ; Date Revised: 12/28/83 1 Page 45 of 52 i
MAINE STATE AGENCY NOTIFICATION FORM Shipment Number
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1.0 SHIPMENTS OF FISSILE NUCLEAR MATERIALS AND/OR RADI0 ACTIVE WASTE: ]i 4 For all shipments of Fissile Nuclear Materials and/or Radioactive Waste leaving j tne plant site, the following State of Maine Agencies must be notified by - i telephone before the shipment leaves the plant site. Time and content of - 1 notification is to be recorded belo _ . _q-
-
a) Maine Turnpike Authorit Person Notified -# j Fare Collection:
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j Phone: 871-7724 Date/ Time /Notifico By: i b) Dept. of Environmental Protection Person Notified
{ Bureau of 011 & Hazardous Material j Phone: 289-2651 - Date/ Time / Notified By: _
l ~ c) Maine State Police Person Notified ~ ~ ~ ~
.) State Officer of the Day j ~ Phone: J 289-2155 _
Oate/ Time / Notified By:_
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l ~ Fissile Nuclear Material Only- - -
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Emergency Preparedness Pnone: 622-6201 5-
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The-following in'ormation has been conveyed to-the above named agency as applicable to 7 -- the s'11pment cor.cerne * -- y _ _
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This shipment contains_ Fissile Nuclear Material requiring prior written - * '~
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ir paragraph The written notification has been mailed -. 2.0 b'elow). on-(the date s 'j =
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Form No. 9-1-15-HP-4 Rev. No. 16 Date Revised: 12/28/83
.l Page 46 of 52
.
.
MAIFE STATE AGENCY NOTIFICATION FORM (CONT.)
L 2.0 SHIPENTS OF FISSILE NUCLEAR MATERIALS ONLY: _
/l For all shipments of Fissile Nuclear Materials entering or leaving the State, the '
agencies listed below must be notified in writino no later than three days prior to the expected shipping or receiving cat a) Maine Turnpike Authority c) Maine State Police - Mr. David H. Stevens _ , 36 Hospital Street ' _ . , 17 Bishop Street -- -
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Augusta, Me 04330 - . .i .. Portland, Me 04103 --
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b) Dept. of Environmental Protection d) Director
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Bureau of 011 and Hazzardous Material Maine Bureau of Civil Statehouse Station #7 Emergency Preparedness Augusta, Me 04330 State House
) Augusta, Me 04330
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The written notification required under this paragraph have been mailed -- by: on: . . A
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, Date Revised: 12/28/83 Page 47 of 52
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' MAItE YANKEE ATOMIC POWER COMPANY t
i RADI0 ACTIVE MATERIAL RELEASE FORM
E Date:
.) Shipment Number Time: ,1 *
NOTE: This form must be completed by a Radwaste Supervisor before plant security will allow any. radioactive material to leave the plant site. Plant security will note the date and time of departure and return this form to Radwast ,.
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.. R;V. Ib.16 . - Date Revised: _
Page 48 of 52 - t
,, RADWASTE SHIPMENT ROUTE-l . . .
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i1 According to the dispatcher at the truck routing from Maine Yankee Nuclear Power Station to -- q is as follows:
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'* , 'o Form No. 9-1-15-HP-8 . R v. No. 16 , .
Date Revised: Page 49 of 52 g CHIEF OF MAINE STATE POLICE RADI0 ACTIVE WASTE SHIPMENT PRENOTIFICATION+ _ TITLE 25, Section 2109
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8l 4, SHIPMENT NUMBER: SHIPMENT DATE:
. DATE CALLED:
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_ _ _ CONTACTED: at 289-2155 _.- ._ y CONTACTED BY: j *A minimum of 24 hour advance notification is require SHIPMENT INFORMATION
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l ROUTE THRU HAINE: Route 144 to US Route 1 to Interstate 95 and enter the Maine'._ . Turnpike at Entrance 9' Remain on Maine Turnpike u~ntil leaving _ ~ the State of Maine at Kitter .-- . _ _ _ __ ,- . __ .. -
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Page 50 of 52 LIMITED QUANTITY CERTIFICATION 49CFR173.421-1(a) i
- SHIPMENT N DATE:
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,1 Maine Yankee Atomic Power Company certifies that: .
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~ I l 49CFR173.421 for excepted radiosctive material, limited qusntity, n.o.s.,
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Rev. No.16 Date Revised: 9/17/84 i Page 51 of 52 i I RADIOACTIVE MATERIAL SHIPMENT CECKLIST i Shipment Number A. The following forms have been cogleted if applicable: I r l ITEM l INITIALS l
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[ l 1. Form No. 9-1-15-HP-1 (Radioactive Shipment Quality l Assurance Record) l I l I l i I _ ' l 2. Form No. 9-1-15-HP-2 (Drivers Instruction Record) l I I l Original to carrier, retain copy l l , I I I r! l 3. Form No. 9-1-15-HP-3 (Mass. Dept. of Public Health l l l Notificaticn Form) 1 i
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l 4. Form No. 9-1-15-P-4 (Maine State Agency Notification Form) l I l i I ({ l S. Form No. 9-1-15-HP-5 (Radioactive Material Shipment Checklist)l l k 1
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l 8. Form No. 9-1-15-HP-8 (Chief of the Maine State Police - l .-- l Radioactive Waste Shipment Prenotification) l l
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l 9. Form No. 9-1-15-W-9 (Limited Quantity Certification) l l . l Must accompany a limited Quantity shipmen l l C e 'l i I ,- d l10. MY-HP-23-72 (Maine Yankee Radioactive Sh! ment Record) l l l Completed if consignee does not have one l
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l11. DEC 802 (South Carolina's Prior Noti'fication and Manifest l l l Form) l l
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L 112. DEC 803 (South Carolina's Certification Form) l l l Original to carrier, retain copy l l
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l I l l l13. DSHS RW-318 (Washington State Certification Form) < l
, 1 Original to carrier, retain copy l
" ' I . I I l14. US Ecology (Rad. Waste Shipment & Disposal Form) Retain l l ! indicated copy, mail copy to US Ecology, other 2 to carrie ( l l15. Chem Nuclear (Rad. Shipment Record Form) Retain indicated I
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i% Form No. 9-1-15-+P-5 j Rev. No. 16 i Date Revised: 12/28/83 i Page 52 of 52
i RADI0 ACTIVE MATERIAL SHIPMENT CFECKLIST - CONT'D 0 -
1 i l } , 116. Maine Yankee straight bill of lading l } l Last cooy retained, others to carrier l , ) i i 1
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