ML20125D279
| ML20125D279 | |
| Person / Time | |
|---|---|
| Issue date: | 04/21/1981 |
| From: | Jennifer Davis NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Santman L TRANSPORTATION, DEPT. OF |
| Shared Package | |
| ML20125D188 | List: |
| References | |
| FOIA-85-3 NUDOCS 8506120298 | |
| Download: ML20125D279 (1) | |
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AFR 211981 Mr. L. D. Santman, Director Materials Transportation Bureau Department of Transportation Washington, DC 20590
Dear Mr. Santman:
This refers to your letter of April 13, 1981 for support and assistance to the Department of Transportation and the International Atomic Energy Agency (IAEA) at the meeting of the IAEA Standing Advisory Group on the Safe Transport of Radioactive Materials to be held in Vienna, Austria,
during October 19-22, 1931.
Due to the limitation of foreign travel funds, we can send only one person to the meeting and that will be subject to the questionable availability of Fiscal Year 1982 funds. We will, of course, work closely with the U.S. delegation in order to prepare a unifom U.S.
position of the specific areas the I AEA has identified for consideration prior to the meeting.
Sincerely, Original Signed by Richard E. Cunningham s John G. Davis, Director Office of Nuclear Material Safety and Safeguards
'ti stri bution :
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' t 86ueleer Assurense Carperstlen 24 Eneastrve Peek West
/7 Auerne. Georgio 30329
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(404) 32H200 Teles: 549667. 542703 715 Honton Drive Grand Junctron. Coloredo atS01 (303)245 4320 TWX: 9109296334 Weinber0stresse 9 a001 Zuroch. sutronenet (01) 470844 Telen:57275 September 17, 1981 CRJ/81/105/ETS m _
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Uc -CMS Mr. John G. Davis Director
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Office of Nuclear Material Safety "dede.,@rr*/4e'efris7 7;,_,
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U. S. Nuclear Regulatory Comission Washington, D. C.
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Reference:
NRC Certificate of Compliance No. 6698 N "'">
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,~..'"M' Docket Number 71-6698
Dear Mr. Davis:
In response to the USNRC's Order to Show Cause dated July 22,1981, we have performed a series of tests and inspections of the NAC-1D spent
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fuel shipping cask.
The enclosed report, "NAC-ID Surface Contamination Evaluation," sumarizes the results of our evaluations to date. We believe the results of this work demonstrate that there is reasonable assurance that the cask will not experience excessive contamination levels in transport.
Our evaluation indicates that:
(1) The cause of excessive surface contamination is isotopes of Cesium imbedded in the cask surface that can be detected by measuring beta radiation emanating from the surfaces.
(2)
Effective and' practical decontamination procedures are available that are compatible with user waste treatment facilities.
(3)
Tests perfonned to date have verified items (1) and (2) above and that by modifying surface ~ con-tamination monitoring requirements, future cases of excessive contamination levels will not be experienced.
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Mr. John G. Davis Page 2 September 17, 1981 i
.e Plans for use of the cask include an initial move from its current I'
location with plastic sheeting covering the cask. After.a thorough survey for removable and imbedded contamination at its destination, the t
cask will be placed in service in its nomal transport mode moving spent fuel assemblies approximately 200 miles.
detailed surveys for removable and imbedded contamination will be made.t The cask will be removed from service if any survey indicates excessive
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surface contamination.
Should this occur, the cask will not be placed back in service without concurrence by the USNRC.
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On the basis of our investigations and evaluations and with the above stipulations for limited initial service, we request the Order to Sh'ow Cause be rescinded.
Sincerely, NUCLEAR ASSURANCE CORPO TION Charles R. Jo Vice President Engineering and Transportation Services CRJ:bam Enclosure cc: Mr. Charles E. MacDonald, Chief.
Transportation Certification Branch Division of Fuel Cycle and Material Safety
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6 CASK NAC-1D
. SURFACE CONTAMINATION EVALUATION September 1981 Prepared by C. C. Hoffman F. L. Danese C. R. Johnson f
NUCLEAR ASSURANCE CORPORATION l
24 Executive Park West e
j Atlanta, Georgia 30329 o,
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. TABLE OF CONTENTS Page
,1 1.
INTRODUCTION...................:::........................
- 1 2.
DISCUSSION...............................................
4 3.
CONCLUSION AND RECOMMENDATIONS...........................
13 Appendix A - Receiving Contamination Survey Data 1976 & 1977 15 GE Morris to San Onofre Appendix B - Receiving Contamination Survey De.ta - 1980 16 GE Morris to San Onofre Appendix C - Receiving Contamination Survey Data - 1981 17 Cask NAC-10 Appendix D - NAC-1 Cask Contamination Survey and Decontamination 18 Test Procedure
. Appendix E - Memo on D Cask Contamination Survey at Florida 19' Power & Light, Turkey Point REFERENCES.........................................;.........
24 t
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- i CASK NAC - ID SURFACE CONTAMINATION EVALUATION Introduction During the period from August 1980 to early September 1981 there were seven instances of excessive r'emovable radioactive surface contamination on the NAC-10 cask on arrival at its destination.
In four of the seven cases, the cask had been used to transport spent nuclear fuel.
In the other three cases the cask was transported empty.
Survey data from these shipments are charted and listed in Figure 1.
U. 5. Federal regulation 4g CFR 173 places a limit on remov'able surface contamination of 22 '000. disintegrations per minute per 100 ' square 2
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centimeters (dpm/100cm).
It is normal practice to decontaminate the outside surfaces of the cask before release from the shipping site to 10% or less of the removable contamination limit.
If the measured activity per square centimeter does not exceed 10 percent of the level 2
described 'above (or 2200 dpm/100 cm ), it may be assumed that those levels have not been exceeded.
The margin is desired to compensate for
' variations in counting methods and equipment and to allow for some release of fixed or semifixed contamination during transport.
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As a result of the recent history of violations of surface contam-7A
.4 ination limits and in particular the contamination levels reached during the Midwest Storage Facility (MSF) to Lacrosse Boiling Water Reactor R)P yf (LAC BWR) shipping campaign, the NRC Office of Nuclear Material Safety h<
and Safeguards issued an. order prohibiting the use of Cask NAC-1D outside 7,.tt-the confines of a licensed facility.
The suspension is to remain in m
}.k; effect until the USNRC finds there is reasoriable assurance'that surfac VD l. ),.
contamination levels will not exceed the requirements of 49 CFR 173
,m p.f.,'
during future shipments.
9
..V dj In an effort to reach ain understanding of the cause of the contam-ination problems.,a review has been made of spent fuel shipments, kfh decontamination agents used, and decontamination results'over the past year as well as survey results and experien'ce on earlier s' hipping programs.
Discussions were. held with supervisory and safety personnel
.y at the facilities involved with the cask contamination difficulties -s to their procedures, experience, and observations on decontamination and shipment of the NAC-10 cask.
Copies of the licensee contamination survey reports were obtained, the average contamination levels were calculated, and the distribution or location for the highest surface contamination spots were' reviewed.
Subsequent to the receipt of the "Show Cause" order, the NAC-10 cask has been utilized on-site at the Turkey point Nuclear Station for movement of fuel ' assemblies between the Unit 3 and Unit 4 spent fuel pools.
A program for survey measurements on the cask was perfonned e
2
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using a number of decontamination agents to determine their effective
- I The results showed a negligible increase *or change of the removable 4.
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contamination or surface equivalent radiation dose rates with time and f
usage during.,the fuel transfer operations at the Turkey Point Nuclear x
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Station.
Howefer, there were significant differences noted in the
..}'t effectiveness of the various decontamination agents.in reducing the t.
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surface equivalent beta radiation dose rates.
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1 This study analyzes the results of the reviews and the more con-trolled survey at Turkey Point and presents recomendations for action to provide assurance that surface contamination limits will not be exceeded during future shipping programs.
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MAXIMUM AND AYERAGE RDCVA8LE $URFACE CONTAMimTION ON CASK MC-1-0 AFTER TRANSPCRT dpV100 ou2 Date
_ Trip
_ Man imun
- Averno, b
(1) 8/12/80 San Onofre to GE MSF 35,000 10'000 (2) 8/25/80 San Onofre to BE MSF 39;000 8;000 3-(3) 2/02/81 B&W LRC to Oyster Creek 80,000 18;000 (4) 4/30/81 Battelle Columbus to Calvert Clif f s 50,000 20;400 (5) 5/30/81 GE M5F to Dalryland 380,000 80;000 (6) 5/31/81 Dalryland to GE MSF 283;000 61;000
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(7) 6/02/81 GE MSF to Dalryland 2,200,000 811;000 1000-.
400 9-6-
b 6-5-
4-3-
b 100-
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Discussion The NAC-ID spent fuel shipping cask is one of five casks of the same design that have been used by the Nuclear Assurance Corporation (NAC).
These casks have smooth stainless steel surfaces and are designed to be imersed in fuel pools for loading and unloading the radioactive spent fuel.
Comonly, spent fuel pools will contain various levels of fission I
products and rcdioactive corrosion products.
During removal of the cask from the pool, the cask is nomally rinsed with deionized water and decontaminated by manually wiping with a decontaminating agent.
Decontamination usually generates some liquid and solid low level i
radioactive waste.
Because of handling and disposal problems, utilities and others who decontaminate casks have a high incentive to minimize these wastes.
Consequently, we have observed a general trend to use cleaning agents and procedures that preclude liquid wastes.
We have also observed that casks occasionally arrive at their destinations with removable contamination exceeding the regulatory limits.
The f'requency of these violations with cask NAC-10 increased considerably in late 1980 and early 1981, particularly after the" cask had been imersed in pools with relatively high levels of fission product contamination.
Available contamination survey data covering shipments in NAC-1 casks during the years.1976 and 1977 have been compiled and are listed '
in Appendix A.
Appendix 8 is a record of surface contamination data on shipments arriving in 1980'at the M5F from San Onofre. As noted in the Appendices, there were occasional incidents of excessive contamination on arriving casks.
During May and June 1980 when San Onofre was not shipping, cask NAC-10 was used for two shipments of fuel from Connecticut Yankee to Battelle Columbus Laboratories (BCL).
These shipments were made with no reporte'd incidents of excessi e contamination.
NonSan Onofre resumed shipments in August, however, the first two shipments arrived at MSF with reportable contamination.
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Appendix C is a tabulation of the contamination survey results on all cask shipments made during the current 1981 calendar year.
Included in the total are the remaining five incidents reported in the NRC "Show Cause" order for NAC-10.
Some shipments were sade during this period 2
without exceeding the D0T limit of 22,000 dpm/100 cm ; however, excessive contamination was detected with increasing frequency up through the shipments to LAC BWR.
After the third shipment to LAC BWR, and in response to an Imediate Action letter from NRC Region III to LAC BWR, a temporary amendment to the cask certificate of compliance was obtained authorizing the cask to be covered with plastic during shipment of the low-heat-rate fuel. All subsequent-(through August 1981) cask movements were made, after decontamination of the cask surface to less than the DOT limit, with a cover of polyethelene plastic over the entire cask, surface.
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e Detailed discussions were held with licensee personnel at LAC BWR, Copies of the contamination survey sheets on all shipments were reviewed and discussed.
On the original shipment, for decontamination LAC BWR used "LOOK", a commercially available glass cleaner, and " ENVY", a foaming cleanser.
Following receipt of the first contaminated shipment, they included the additional decontamination agents acetone and a solution of ammonia.
In spite of these efforts, the* removable contamination
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exceeded DOT limits upon the return of the cask to MSF. After arrival of the next shipment at LAC BWR on June 2,1981, with extremely high contamination levels, detailed measurements and analyses were made.
A high level beta surface dose equivalent rate in the range of 400 to 500 mR/hr was detected.
Isotopic analyses were perfonned and showed that the contamination was primarily Cesium-134 and Cesium-137 with a trace of Cobalt-6D.
A further test was made to determine the effectiveness of the decontamination agents being used in removing surface contamination.
The following results were obtained during receipt, unloading, and decontamination of the cask during the time period of June 2 through June 5,1981, at LAC BWR:
a.
_ Loaded Cask NAC-1D Arrived at' LAC BWR from MSF.
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Measurements of removable surface contamination were taken.
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prj The average of all readings was approximately C00,000 dpm/
pf M.
2 100 cm with a high reading over 2,000,000.
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Contact dose rate measurement of the cask surface upon receipt i
were 6 mR/hr average Gasma reading and 264 mR/hr average Seta
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reading.
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b.
Cask was Unloaded and Removed from LAC IWR Pool.
The average Beta surface dose equivalent rate was measured as l
i 480 mR/hr. '
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c.
Cask was Decontaminated Usina "LOOK" and " ENVY",
j 2
Smearable contamination less than 2200 dpm/100 cm,
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I surface dose equivalent rate approximately 480 mR/hr.
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Cask Decontaminated Usine TURC0 4502 and TURC0 4521 1
Followed by a Domineralized Water Rinse.
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Smearable contamination less than 2200 dpm/100 cm.
Beta.
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surface dose equivalent rate approximately 120 mR/hr.
m.
The decontamination with the TURC0 agents was repeated.
Seta I
surface dose equivalent rate reduced to 60 mR/hr.
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These results provide e'vidence that the mild decontamination agents "LOOK", and " ENVY" which quickly reduced smearable contamination i
to acceptable levels, were ineffective in removing the semi-fixed beta' contamination. The stronger TURC0 products proved effective in reducing l
i both types of contamination.
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8eneral Electric personnel at MSF agree with NAC that the beta dose rate findings are important. A survey of the GE !F-300 cask on hand also showed the presence of measurable and significant' beta dose rates. An analys'is by General Electric confirmed the results obtained
... gC i.
l at LAC BWR showing an isotopic content of primarily Cesium-137 and 1
Cesium-134 in the contamination. Although M5F did not have an explan-t
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ation for the cause of recent contamination difficulties with NAC-10. it was felt that the existence of the beta contamination might furnish a k
The MSF storage pool maintains good quality pool water with an activity level of 1 x 10~4 uti/ml. The LAC BWR pool water had activity
' level of 2 x 10-2 9C1/m1.
l L
Both CAC BWR and General Electric provided copies of cask survey documents and discussed possible implications and findings.
Unfortunately there was no historical data on beta dose rates since'such records have not been routinely obtained and documented.
General Electric at M5F was
,using trisodium phosphate as their decontamination agent.
This agent was effective in removing smearable contamination. At that time, however, they had no data regarding its capability to reduce the Beta contamination.
i.
When the LAC BWR shipments were completed, Cask NAC-10 was placed in service at the Turkey Point Nuclear Station for use in shuffling fuel, between the spent fudl pools of Units 3 and 4.
The operation is perfomed by loading the cask in one pool and movement of the loaded cask by crane.
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to the second pool for unloading and return. This operation continued for the transfer of over 1g0 fuel assemblies.
No cask decontamination.
I other than rinsadown with domineralized water, was perfomed during I
these operations.
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The fuel shuffling continued at Turkey Point for approximately six weeks of multi-shif t operation.
It afforde'd an opportunity to study the.
cask surface contamination, to determine if there was a buildup of the surface contamination with time and use, and to explore the effectiveness of various decontamination agents used previously at other sites in cleaning the cask. 4 program was" established and carried out limited somewhat by the time constraints imposed to minimize interference with the Turkey Point operations.-
Accordingly, survey measurements were made on' July 25 and again on I
August 10, 1981.
These surveys were perfomed in accordance with the procedural steps presented in Appendix D; the results are attached as Appendix E.
It was demonstrated that several of the comon decontam-ination agents currently being used at nuclear installations (Tide, Alcohol, consolve, Trisodium Phosphate, Fantastic, Easy-Off) will reduce the smearable contamination b acceptable release limits without affecting the beta dose equivalent readings.
The TURCO agents 4502 and 4521 were effective not only in removing the smearable contamination but also in reducing beta surface equivalent dose rate levels.
Analyses of the spent TURC0 agents indicated the major contaminants removed were isotopes of Cesium.
9 10
Those results were corroborated during the August 10 tests.
On that date, however, it was shown that the use of a bristle brush, in lieu of a sponge or cloth wipes, when using Tide as a cleaning agent, did result in some reduction of the beta dose rate. The observations at Turkey point also indicated that there was no significant continuing buildup of cask surface contamination with time as the fuel transfer.
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operations proceeded. The smear counts after two weeks of operation were generally in the range of 10,'000 to 60,000 dpm/100 cm when no decontamination of the cask surface, other than a water rinse, had been performed.
The beta surface dose rate equivalent continued in the range of 10 to 30 mR/hr. After four weeks of operation,'these ranges of readings were almost identical.
Stainless steel depends on an oxide film to preserve its corrosion resistance. This thin film (several molecules thick) is readily formed in air at room temperature.l. Review of available literature (Ref.1, 2 and 3) indicates several mechanisms for radioactive isotopes to become semi-fixed contaminants on stainless steel surfaces.
These include adsorption, absorption, diffusion and chemical reaction.
In cases where the contaminant is adsorbed or absorbed, removal can be accomplished by wetting the contaminant and mechanically removing it.
I6. cases where
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the contaminant has become imbedded in the oxide film by diffusion or has reacted with the oxide, removal requires some action to reverse the process.
This might require dissolution of the oxide film or reaction f
with another material to render the' contaminant soluble.
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s
Experience gained at LAC BWR and at Turkey Point indicate that mild decontamination agents such as window cleaners are effective for removing loose surface contamination. However, these cleaners are ineffective in removing the source of beta radiation which is the precursor to future I
removable surface contamination. More aggressive cleaning agents such.
as the potassium permanganate and ammonium citrate.of the TURCO products, or more vigorous cleining methods such as Ihe use of stiff bristled brushes or steam, are needed to remove smearable contamination as well as imbedded contaminants.
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The final decontamination at Turkey Point employed steam and a mild TURCO detergent.
The average removable contamination after this treat-2 ment was 4000 dpm/100 cm.
The cask was allowed to weather on the decontamination pad and later wrapped in plastic with fourteen access
" windows" on the trailer from August 26, 1981, to September 2,1981, when a final removable contamination survey was made.
The average removable contamination was 4,900 dpm/100 cm with beta surface dose equivalent rates ranging from 2.5 to 5 mR/hr.
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e Conclusions and Recommendations Based on the experience during shipment of fuel from MSF to LAC BWR and the experiments and observations during the campaign at Turkey Point, it can be concluded that the precursor of excessive removable contamination after a shipment is residual imbedded contamination that was inadequately removed during pre-shipmen't decontamination of the cask..The mechanisms responsible. for release of this imbedded contam-ination include thermal cycling, vibration, atmospheric changes, scrubbing action of winds and wetting and drying cycles during weathering.
Ev.idence of inadequate removal of imbedded contamination is a high dose rate of beta radiation at the surface of the cask.
From experiments with decontaminating agents and nethods, reduction of surface beta' radiation fields to less than 15 mR/hr are practicable.
Once the beta field has been reduced to a low level, it can be maintained by prudent use of protective devices such as strippable paint or plastic sheaths when the cask is to be innersed in pools with significant contamination levels.
In lieu of preventative methods, more aggressive cleaning agents must be used.
To provide assurance that future shipments of the NAC-1D cask and other spent fuel shipping packages meet ~ acceptable contamination level requirements it is reconinended that:
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1.
Shippers be required to perform a-beta radiation survey in addition to the removable contamination survey currently perfomed to assure compliance with 49 CFR 173.397.
2.
Quantification of pemissible levels of beta radiation be established by experience with actual shipping campaigns.
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Initially, Beta fields for casks prepared for shipment be limited to a maximum of 15 mR/hr at contact.,
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Appendix' A - Receiving Cor.-
1976 & 1977 GE :
2 Date Cas m/100 cm
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3-17-76 1C 700 3-19-76 1D
-00 3-21-76 1B 100 3-25-76 IC f00
.3-27-76 1D 100 1
3-28-76 1B
'00 3-31-76 1C
- 00 4-02-76 1A 100 4-03-76 1D 130 05-76 IB "30 4-07-76 1C
.30 4-09-76 1A 30 4-10-76 1D 30 4-12-76 1B 30 4-14-76 1C 30 4-16-76 1A
.30 4-19-76 1D
.30 4-22-76 1C-
.JO 4-23-76 1A
- 0 4-27-76 IB
- ;0
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4-29-76 1C
- 0 5-03-76 1A
'00 5-04-76 1D 30 5-06-76 1C
~30 5-09-76 IB
.30 5-11-76 1A
.30 5-15-76 1D 30*
5-15-76 IB TO 5-17-76 1C
- 0 5-20-76 1A 30 5-21-76 ID-
- .0 5-24-76 1C
- .0 5-26-76 IB
- .0*
5-27-76 1A
- 0' 5-28-76 1D
- 3*
6-01-76 1C
.O 6-02-76 IB
- D 6-03-76 ID 20 6-05-76 1A 0
6-10-76 1C
- D 6-11-76 IB
- D 6-12-76 1D
'O 6-16-76 1A
'O 6-19-76 1C 3
3-29-77 1C
'3 4-13-77 IB
'3*'
4-25-77 IC 3
5-02-77 IB 3
5-03-77 ID 3'
5-05-77 1C 3
5-11-77 IB 3*
5-16-77 1C 5-15-77 1D
- Reported _
Appendix B - Receiving Contamination Survey Data - 1980 GE Morris to San Onofre Date Cask Highest dpm/100 cm 1-21
-- ~ "1D 19,000 1-22 IE
.< 2,200 1-29 ID 8,000 2-16 IE
< 2,200 3,400 2-18 1D
< 2,200 2-27 1E 2-27 1D 4,200 3-6 1E
< 2,200 3-8 1D 3,100 1E 3,000 3-15
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1D
< 2,200 3-16 3-22 1E 7,000 3-24 10.
5,500 8-12 1D 35,000 8-23 1D 39,000 9-7 ID 21,000 O
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Appendix C - Receiving Contamination Survey Data - 1981 Cask NAC-1D Date Trip Highest dpm/100 cm 2-2 B&W to Oyster Creek 80,000 2-20 Oyster Creek to BCL 1,400 4-30 BCL to Calvert Cliff 50,000 5-5 Calvert Cliff.to BCL 17,500 5-15 BCL to GE MSF 9,000 5-27 MSF to LAC BWR
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5-28 LAC BWR to MSF 8,300 10,600 5-30 MSF to LAC BWR
'380,000 5-31 LAC BWR to MSF 283,000 6-2
'MSF to LAC BWR 2,200,000 6-5 LAC BWR to MSF 2,200*
1,700*
7-2 BCL to Turkey Point 100,000**
Plastic wrapped Plastic wrapped - high reading unconfirmed J
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APPENDIX D NAC-1 CASK CONTAMINATION SURVEY A::D DECONTAMINATIO" TEST PROCEDURE 1.0 PURPOSE This procedure provides for the collection of fix~ed and smearable contam--
ination data from the outside surface of the NAC-1 cask.
This procedure also provides for the application and evaluation of the effectiveness of commonly used decontamination. agents.
2.0 EQUIPMENT The equipment required for this procedure is:
2.1 A radiation survey instrument capable of measuring contact beta-gamma and gamma radiation.
2.2 A box of pre-cut smears.
2.3 A smear counting ins'trument (in dpm).
2.4 Various de. contamination agents.
3.0 PROCEDURE
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3.1 A contact radiation survey is made over the length of the cask.
The
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l survey is made in two'. passes at one-fodt intervals on the centerline of each of the four quadrants of the cask.
During the first pass in each quadrant, the contact gamma radiation is measured (beta shield closed).
During the second pass, the contact beta-gamma radiation is measured.
These data are recorded on the attached forms.
2 3.2 A smear (dpm/100 cm ) is taken at each point that a radiation field is measured.
The results of the smear are recorded opposite the radiation. readings on the reporting form.
3.3 Following the completion of the radiation and smear surveys, 'two one-foot square test areas on each face '(at about the four-foot and six-foot elevation levels) will be decontaminated using the available 4
decontamination agents.
3.4 After decontamination, a new smear of the test area (s) will be made and the results will be recorded.
The contact beta-gamma and gamma will be measured to assess the effectiveness of each agent in removing fixed surface contamination.
3.5 The results of all radiation surveys' will be documented and'indepen-dently verified.
The record of results will be dated and signed by the individuals performing and verifying the measurements.
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APPENDIX E MEMO TO:
C. C. Hoffma FLD/81/56/ETS g
FROM:
F. L. Dane e, R. C. Bonnett
SUBJECT:
D Cask Contamination Survey at Florida Power & Light, Turkey Point DATE:
July 30, 1981 We arrived at Turkey Point Nuclear Station,-Homestead, Florida approximately 9:00 a.m. July 26, 1981.
Entry for Danese was delayed due to lost badge, so the process for obtaining a picture badge had to be gone through again.
At about 10:30 a.m., Danese received his badge and joined Bonnett and Mr. Bill Wymer in his office.
We discussed our plan with Mr. Wymer to perform a beta-
. gamma and smearable survey on each quadrant of the NAC-10 cask.
Mr. Wymer informed us that the cask was in the pool and it was very near crew change so we would have to wait until the next crew was at work. At approximately 12:30 p.m., the cask arrived at the ' cask wash-down area and was turned over to us and a Health Physics Technician from FP&L (Chris Caldwell).
Using a tape, we marked lines off at 12" intervals, beginning at the base of the cask on each of the four faces.
We then did a beta-gamma and smearable survey at each line and Chris Caldwell (FP&L) recorded the results.
Following his complete survey, eight areas (about '8" X 8"), were narked on the cask and cach of these areas was decontaminated with 'a different agent.
A smear survey was made to verify that the surface was below DOT limits (2,200 dpm).
When the smear results were below DOT ~ limits, a beta-gamma radiation was again measured and recorded.
All of the. data collected is shown on the attached survey sheets.
All tests were concluded at about 4:30 p.m.
FLD/RCB:bam Attachments cc:
Danese Johnson Danese file Corporate e
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References (1)
Decontamination of Surfaces Contaminated with Radioisotopes:
Decontamination agents, cisanability of surfaces of different kinds with the contamination with Strontium-90, Cobalt-60',
Cesium-137, Iridium-192, and Thallium-204.
F. Golder, T. Predmersky and O. Roka.
Isotope Ins.titute, Budapest.
197e.
(2)
Thi Radioactive Contamination of Metal Surfaces. Graham Oldham.
Nuclear Science Laboratories, University of Technology, Lough-borough.
1979.
(3)
On the Interaction of Cesium with Oxides of Stainless Steel.
Anthony G. Warner and Robert L. Woolley, Berkeley Nuclear Laboratories, England.
1978.
e b
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