ML20091R284
| ML20091R284 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/06/1984 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8406150068 | |
| Download: ML20091R284 (66) | |
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' a GPU Nuclear Corporution i
ggg{ Post Office Box 388 Route 9 South Forked River,New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:
June 6, 1984 Mr. Richard W. Starostecki, Director Division of Project and Resident Programs U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Starostecki:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Radwaste Overboard Discharge Piping Maintenance The attachments to this letter provide our evaluation with supporting documentation of the incident referred to in your letter dated May 10, 1984.
As discussed therein, we conclude that there are no programmatic deficiences existent amongst the departments involved and that appropriate corrective actions were taken expeditiously.
If you should have any questions, pl' ease contact me or Mr. Drew Holland at (609)971-4643.
Very truly yours, 5^ -
j iedfe r Vice President and Director Oyster Creek PBF:PFC: dam Attachments cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue
- King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, EJ 08731 W :.:. l I sd 1: QQ riev ~ -- ,; .,
8406150068 840606 PDR ADOCK 05000219 P PDR GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation
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- BACKGROUND
?The possibility _ of a leak in the overboard discharge piping was first noted by radwaste operations personnel on Wednesday, March 14,1984.. A. cave-in had
. been found under the sidewalk.near the southwest cornerjof the Old Radwaste -
, Building. 'At first, it was thought that the cave-in was due to the extremely
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heavy rains- which had occurred on Tuesday,' March 13, and the early morning hours of = Wednesday, March 14. Further observations confirmed that water was t -in fact .b abbling up f rom underground. Since the 30 inch diameter service
- water discharge header and radwaste overboard discharge line to the service water header run' underground in the area of the cave-in, it was thought that J tida piping or connection could be the source of the leakage. As an overboard discharge was then in progress the discharge was promptly stopped. A water sample was sthen obtained by Chemistry personnel. . The analysis of the water sample indicated activity levels less than minimum detectable activity (MDA) of 1 x 10-7 uci/cc. .Excavacion in this area revealed no leakage.
On Thursday, March'15, further excavation was performed to uncover more of the t radwaste overboard discharge line outside the Old Radwaste Building. No leaks
,were :found in the portion of pipe which was exposed. - A sample of the water in
-the excavation was obtained. Analysis disclosed a small amount of Cesium 137 e
- activity, below the administrative -limit of 20 percent of 10 CFR 20. In an
. attempt to verify the source of the leakage, demineralized w 'sc was flushed through the overboard discharge line. As soon as the flush started, water was 1
observedLleaking into the excavation. The source.of the leakage was determined to be beneath the Old Radwaste Building, in the vicinity of the point where the pipe penetrates the floor of the building. The overboard discharge isolation valves were tagged out to prevent any further discharges
.until repairs were completed.
I Excavation resumed on Friday, March 16.- The intent was to expose the pipe all the1way back to the pipe penetration in the floor of the building. In order to do , this,11t was necessary to excavate beneath the foundation of ' the building. During thel course of the digging, seven (7) soil' samples were
! obtained at various locations. The sample analysis showed some activity, but
, .all were below applicable station limits. Also, dirt was directly surveyed during excavation with a HP210- probe and no contamination was detected. By the evening of Friday, March 16, excavation was complete and the pipe uncovered to the -leakage source.. A hole was found adjacent; to a 90 degree
_ - elbow. The hole was large enough that a person could reach inside. In an effort.to characterize the_ radiological. status of the pipe internals, a Radiological Controls technician wearing gloves took several smearable
- contamination wipes on the internal surfaces of the. pipe. - The results
-_ indicated smearable contamination to be 1ess than 1000 dpm/100 cm2 .
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In addition, a large area gross wipe was taken inside the pipe. The gross wipe
~ indicated -800 cpm above ba'c kground.
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o Dose rates taken on the external surface of the pipe were less than 2 mR/hr.,
with no detectable Beta present. However, the hole in the pipe was not large enough to place a dose rate meter inside the pipe. Up to this point in time, all work had been performed without a Radiation Work Permit (RWP), with the full knowledge of the Radiological Controls Department (Rad Con). None of the criteria which require the use of an approved RWP had yet been met. The work was within the Radiologically Controlled Area of the plant, and all workers were wearing proper dosimetry.
At this point late Friday af ternoon, March 16, discussions began concerning the methods to be used to repair the damaged pipe. The damaged section would obviously have to be replaced, but the details of how this was to be accomplished (i.e., location of cuts, method of cutting, type of replacement material, etc.) was turned over to the Plant Engineering Department for resolution. In anticipation of making the cuts upon receiving Engineering direction, the Maintenance and Construction Department (M&C) Area Supervisor submitted a Radiological Engineering Review Request to the Radiological Engineering group, for the purpose of receiving detailed radiological requirements which would be imposed for the work. No RWP waa submitted at that time. Rad Con personnel (both Field Operations and E34 Engineering) assumed that an RWP would be submitted before repair work commenced. It was obvious to them that an RWP was required because of the likelihood of fixed contamination inside the pipe. It was further assuced that, since no RWP was submitted Friday night, there were no plans to work the job on the weekend.
During the day on Saturday, March 17, Maintenance and Construction workers erected a temporary structure over the excavation to shelter the work area from rain. Also on Saturday, che M&C Area Supervisor said that he believed that the pipe was clean. This led him to believe that an RWP would not he required. He overlooked the possibility of fixed contamination on the pipe internals.
On Sunday, March 18, the M&C Area Supervisor, having received direction from Plant Engineering, turned the job of cutting the pipe over to a Job Supervisor and work crew telling them that an RWP was not necessary. The work crew spent most of the day gathering equipment for the job and did not notify Rad Con personnel of their intent to begin work because they believed this to be a non-RWP job. Upon arriving at the job site, the work crew did not encounter any special radiological postings around the excavated area, further reinforcing their belief that an RWP was not required. In order to facilitate any further preparatory work needed prior to making the cut, the Rad Con Department had withheld erection of any special postings. Conditions did not yet exist requiring such postings because the job site was already within a posted Radiation Area and Radiologically Controlled Area (RCA). No smearable contamination above limits had been detected, and the pipe itself, being a permane'ntly installed process system, was not labelled.
Late Sunday af ternoon, the work crew cut out the damaged section of pipe using a torch and grinding wheels. Since an RWP/RER had not been obtained, no radiological precautions were taken. However, standard hot work and burning precautions were used (i.c., welder's masks and gloves, coveralls) by the 2
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personnel actually performing the work. After cutting out the damaged section of pipe, the work crew removed it from the excavation and carried it to the RCA exit, intending to take it to the machine shop for measurements. Upon frisking themselves and the piece of pipe, it was discovered that the pipa was contaminated. Also, one worker's gloves and one shoe were contaminated, and another worker's gloves were contaminated. The workers immediately notified the on-duty Group Radiological Controls Supervisor (GRCS) of the situation.
The GRCS had been unaware that this work had been taking place. Surveys were started on the path of travel from the job site to the frisking area, and of the job site itself. The pipe section was surveyed and bagged. The GRCS notified the Rad Con Field Operations Manager, who directed that a hold be placed on any further work, and that Whole Body Counts (WBC) be arranged for all workers who were involved in the incident. The WBCs were performed Sunday night, March 18. Surveys of the removed pipe section and the exposed pipe ends at the job site showed no smearable contamination on the externals, some low level smearable contamination and higher levels of fixed contamination on the pipe internals. Since an earlier (prior to cutting) survey of the pipe internals had not shown any smearable contamination, it was thought that the flame cutting and grinding operations had loosened some of the fixed contanination. The exposed pipe ends at the job site were bagged and labelled.
On Monday morning, March 19, the M&C Area Supervisor was made aware of what <
had happened, and he subnitted an RWP in order to continue with the repair work. The Rad Engineering Review which he had requested earlier was completed on Monday. On Tuesday, March 20, the RWP/RER for the work was issued, the normal radiological controls for this type of work were established, and work proceeded from that point on without further incident.
On Tuesday, March 27, a formal critique was held with the entire work crew, the M&C Job Supervisor and Area Supervisor, and M&C and Rad Con Management.
This critique completed the Company's investigation of the incident, and was performed within the required time Ibnits.
SPECIFICS
- 1. How, when and by whom this event was identified and to whom it was reported.
This event (cutting pipe without an approved Radiation Work Permit) was first identified by the Maintenance and Construction work crew when they attempted to r emove the severed section of pipe from the Radiologically Controlled area of the plant at about 1745 hrs on Sunday, March 18. When they checked the section of pipe with a frisker, the frisker alarmed. Realizing the significance of this, they immediately notified the on-duty Group Radiological Controls Supervisor by telephone. Af ter determining what had occurred, the GRCS in turn notified the Rad Con Field Operations Manager at home by telephone.
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_2.. 1The date(s)fon which the event occurred.
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W - The actual' cutting of the pipe occurred late.in the af ternoon on1 Sunday, LMarch 18. Upor discovery of what - had occurred, a ' hold was -
- placed on any. further work. - On March 20, an approved RWP/RER was -
-issued for.the repair; work. No work was performed between Sunday
- evening and the issuance' of the RWP. on Tuesday. .Af ter the RWP/RER uns' issued on Tuesday,l March 20, work proceeded without further
- incident.-
y '3. The' potential for worker exposure to, contamination from and/or
. . internal deposition of radioactive material. '
. The' initial smear survey (#3873-84) taken inside the pipe on Friday, ,
. : March 16, indicated- that ' there was no smearable contamination present F above limits, although a gross wipe taken over a large area did indicate a small amount of smearable activity. There was a high
- ~" probability of fixed contamination on the _ internals of the pipe. The hole in the pipe was not large enough to ' allow direct measurements to
. be.taken on the pipe internals.-- The outside of the pipe was clean, jy soil and water samples taken in'the excavation were all below
. applicable limits, and dose rates in--the work area and on contact U <
, with the. pipe were less-than 2 mrem /hv. Also, it was noted by
- 'several individuals who inspected the damaged section of pipe that
- l. Lthere was an inward flow of air through the hole in the pipe. This was. thought to be due to a vortex aspiration effect from the large
-volume of gravity flow through the Service Water Discharge. Header.
The Radwaste Overboard. Discharge Line ties into the top of the p . Service Water Discharge Header. The flow through the Service Water line was creating a vacuum in the Overboard ' Discharge Line. This-
_ theory was borne out by the fact that even after'the torch cutting 4 and grinding operations, no _ smearable contasination was detected on
- the externals of the pipe, o'nly.on 'the internals.' The highest levels
- of smearable contamination found af ter cutting on the internals of-
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e either the removed section of pipe or the piping which remained in place were'12,000 d'pe/100f em2 (Survey Nos. 3955-84 and 3959-84).
_~ The.results of an air sample taken in the. work" area containment immediately after_the incident was discovered were 8.0 E-11 uCi/cc P gross beta-gamma.- The workers who-actually performed the cutting, r . while not wearing Anti-Contamination clothing'or respiratory
_ protection, were wearing welding masks, gloves and _ work coveralls.
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This ' gear.was all frisked and;found to be free of contamination. The two workers .who received clothing contamination (work gloves) were -
thought to have done 'so during the transfer of the pipe section from I the ' job site to the frisking" station at the RCA exit point. Whole ~
. body counts-performed on all cf the workers involved showed no activity above MDA.
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- In retrospect, although no conscious decision ~ was ma'de beforehand to
.-allow the job to -begin without. engineering controls and protective clothing,' it is felt that, because of conditions which existed at the time of.the cutting and results'of surveys and Whole Body-Counts
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performed after the fact, the. potential for worker exposure to contamination and/or internal deposition was' minimal.
14._ - The results of any surveys' performed before, during or af ter the work was performed.
-During preliminary excavation work to find the source of leakage and after the hole in the pipe had been uncovered, several water and soil samples were obtained and analyzed by the Chemistry Department. The results of these samples are summarized in _the attached memorandum to g C. Jg Halbfoster, Manager - Plant Chemistry, dated April 12, 1984.
The activity _ in all samples was below applicable station limits. >
. Dirt being removed from the excavation was randomly surveyed by direct frisk with an. HP210 probe.- No activity greater than 100 cpm above background was detected. After the hole in the pipe was made accessible, several smears were taken on' the pipe internals. .All these smears'showed loose contamination to be less than '1000 dpe/100 cm2, Since the Rad Con Department was not' aware that the pipe was- being cut on the afternoon of Harch 18, there was no Rad Con technician in attendance, and, therefore, no surveys were taken during the actual
- cutting evolution. Follow-up surveys that were taken on the evening of March 18, af ter cutting, indicated that some relatively low-level smearable contamination (12,000 dpe/100 cm2 highest) was generated during the cutting process; however, the smearable contamination was .
confined to the internals of the pipe, probably by the inward flow of t'
air'into the' pipe. These same surveys showed that there was no spread.of contamination either at the job site or along the path of
, travel from the job site to the friskers at the RCA exit. The-
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removed pipe section~and the two exposed pipe ends were immediately begged and appropriately labelled to further prevent any spread of -
contamination.
No work took place between the evening of March 18 and the issuance of the approved RWP/RER on March 20. Once work resumed following the
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issuance of the RWP/RER, numerous surveys were ' performed during the course of work. These surveys showed .that there was never any spread '
of. contamination, nor was any airborne radioactivity above applicable
. limits generated, even during hot work and grinding. Copies of the surveys are attached for reference. '
- 5. The radiological safety precautions taken prior to and during the time the work was being performed.
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'During preliminary excavation work to uncover the source of leakage, water.and soil-samplesLwere taken and analyzed, and found to'be below applicable limits. Random samples of dirt being removed from the excavation were frisked, and no contamination was detected. Since none of the requirements' for an RWP had yet been met, ru) RWP was required. - However, a Rad Con technician was in almost constant
-attendance to monitor for changing conditions which might dictate the use of an RWP. None were encountered. All the work being performed was already within a posted Radiation Area and RCA. It was the.
intent of!the_ Rad Con' Department, in order.to facilitate preparatory work to hold off on establishing special posting and RWP. requirements until such time'as either contamination was encountered or the pipe was ready to be cut, whichever came first. As soon as the hole in the pipe became accessible, omears were taken inside the pipe and no contamination above applicable limits was found. As of the_close of the workday on Friday, March.16, an RWP had not been required.
s Since the actual event-in question (initial cutting of the pipe on the evening of March 18) occurred without an RWP and was.not monitored by Rad Con, no special radiological precautions were taken
-during.the cutting. However, it is felt that.the conditions.which existed at the time (i.e., inward flow of air and welder's gear) did provide some measure of protection.- p Prior- to the resumption of work RWP #751-84 and ~ RER #155-84 were issued.for use on March 20. RER #163-84 was added onto the RWP on March 22, to address added scope'of work.--Basically, the RWP and
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RERs required the use of full protective clothing and respiratory protection (PAPRs), augmented by a portable HEPA-filtered exhaust ventilation system. The. temporary enclosure which had been erected ;
over the excavation was utilised asia contamination control barrier.
> Copies of RWP'#751-84 and the two RERs are attached for reference-as ,
'to specific requirements. All work performed after March 18 was controlled by these documents.
- 6. . The controlling radiological and maintenance work procedures involved with the job.
The two primary procedures which should have been. controlling in,this
' situation ,are Station Procedure 105 titled " Conduct of Maintenance," '
o -and Station Procedure 915.12, titled " Radiation Work Permit". The l stated purpose of Procedure 105 is "to provide standard administrative, management and radiological control practices for the planning and conduct of maintenanceist Oyster Creek." The stated purpose of Procedure 915.12 is to provide an administrative ,
. method of controlling personnel access to RWP areas for the purpose i of minimizing the total! dose equivalent as low as reasonably achievable (ALARA) and work'ing with maximum radiological safety."
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- 7. The adequacy'of the controlling procedures.
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Station Procedure 105, " Conduct of' Maintenance," contains clearly
' defined. responsibilities for all personnel involved in the planning and' execution of maintenance work,_ radiological and otherwise. There nare detailed instructions-for requesting, obtaining and using.a
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- Radiation WorkiPermit, when required. Station Procedure 915.12,
- " Radiation Work Permit", clearly defines the conditions which require the use of an RWP and contains detailed instructions for obtaining
.and'using an RWP. It is felt that these procedures, as currently written,~ are more than adequate. 'For-the period January 1, 1984 '
-through May 20, 1984, the Maintenance and Construction Department completed over 2100 maintenance _ job orders, some involving
- radiological ~ work and some not. In support of the effort, the
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iRadiological~ Controls Department has written and issued ll50'RWPs
'during the same time period. With the single exception of the incident in question, the proper determination was made in all cases concerning the; necessity for RWPs. The incident in question was an isolated occurrence that is not indicative of a' programmatic. problem
. caused by inadequate procedures.
'8. sThe corrective actions takenior planned ~to prevent' recurrence
-includingLehe dates of these actions.
Immediate corrective actions taken at the. time the incident was discovered were as follows::
-A. The job was stopped and Radiological Controls management notified.1 'An immediate hold was placed on any further work pending the issuance of's valid RWP/RER;
.B.- Surveys were taken to determine whether or not any spread of contamination had occurred. Contaminated items were' properly.
identified and controlled.
!C. Whole Body _ Counts were arranged for. all wx:kers involved.
TThese immediate actions were performed on the evening of March 18.
,. : On March 20,, an approved:RWP/RER was issued to allow work to continue with the proper radiological precautions. On March 27, a formal critique of the incident was held by manageneat with all involved personnel, including the individual making the allegation. At the critique, procedural requirements were reviewed and determined to be adequate as written. .All! attendees'were asked if there were any e remaining open ~ items, questions ~or-comments and there was no response. The critique would have been held earlier had'it not been
- for _the unavailability of key personnel. = 10n March 28, the M&C Area
, Supervisor was counseled by his management for. failure to submit'an
' WP R for the~ job, and'not following up on his initial request for-an RER. These actions concluded the Company's investigation into'the incident.
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L9.; - The ra'diologica1> health effects.on the workers involved in the job.
Externa 1'whole: body and extremity exposure received by the. workers as a' result of this incident were minimal. Dose rates on contact with
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the' pipe were less than 2' mrem /hr. General area dose rates in the work area were less than 2 mrem /hr. None of the workers involved f
' received any skin ~ contamination as a result of the incident. Results of the Whole Body Counts performed on all five workers indicated that there was.no detectable activity above MDA present, and, therefore, no significant. ingestion of. radioactive material by any of them.
" Based on the'above' facts, it can be' stated that there were no adverse
- radiological health effects on any of the workers.
- 10. Pc .pective as to the need-for en RWP, and the reasons why or why
'not, including potential interface difficulties between various GPUN Divisions.
g It is felt that'all the' preparatory work which led up to the. actual
- cutting of the pipe was properly performed without an RWP being
. required. As previously stated, none of the conditions which wc Id
< have dictated the use of an RWP had yet been met, and the preparatory work was being closely monitored by Rad Con personnel.
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- There was information available which could mislead a maintenance supervisor to believe an RWP was not required for removing the pipe.
Survey results did not indicate contamination above limits, either on the soil, in .the water coming 'out of the pipe, or on the externals
.and. internals of the pipe. Althought the Rad Con Department believed unknown radiological conditions existed;inside the pipe which
. required an RWP, this was not clearly communicated to the maintenance supervisor. The maintenance supervisor did-not specifically ask the
< . Rad Con Department if an RWP was required and did not clearly.
communicate when the work was .co be performed. The submittal of a Radiological Engineering Request-(RER) misled the Radiological I Controls Department to the conclusion that the maintenance supervisor realized unknown' radiological conditions existed on the pipe
> internals.- No intent by the maintenance supervisor, the workers or .
Radiological Controls to bypass procedural requirements or, '
Radiological Controls rules was demonstrated. In fact,'upon discovery of contamination, the workers reported promptly to 4 ' Radiological Controls.
Concerning -interface difficulties between CPUM divisions, it has
!already been pointed out that M&C routinely performs a very large
- volume of work and that Rad Con routinely issues and enforces a large number of RWPs in support'of that work. This is done in an orderly fashion, in ~accordance with prescribed procedures and with the ' proper
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determinations'made as to whether or not RWPs are required. The i . incident in question is considered to be an isolated instance of truman error, and is'not indicative'of a programmatic. interface j problem between the two divisions nor of control of' radiological work.
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SIDSIARY The incident in question (cutting the pipe without an RWP) occurred on
- March 18,1984. - As soon as the error'was discovered, timely and appropriate corrective actions were taken. No further work was allowed until an approved RWP/RRR was issued. A formal critique of the incident was convened on March 27, 1984, well within the time period specified in Station Procedure 915.10. The critique concluded the Company's investigation into the incident.
- Mr. Rayment stated in his letter that .he unsuccessfully sought resolution to his concerns before writing the letter. - The fact of the matter is that Mr.
Rayment personally attended the critique meeting, and when asked if he had any.
unanswered concerns or:open' issues, he responded that he did not. . Furthe r,
- between the critique' on hrch 27, 1984 and the date of his letter, May 1, 1984, he did not express any concerns to Supervision or knagement in his own
-Department, nor did he approach anyone in Supervision or knagement in th?
Radiological Controls Department.- Mr. Rayment has an open invitation from the Vice President / Director of Oyster Creek to discuss any concerns that he may have at.any time. He did not do this.- He did not express his concerns to anyone in Corporate k nagement,- including the GPUN Ombudsman.
Contrary to Mr. Rayment's statement, he did not' utilize any of these avenues to express' his concern for any _ issues he believed war'e not addressed.
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haior-Offico Memorandunk Date April 12, 1984 _
Subject Cl$emistry Sampling: Overboard Discharge Pipe nreak kh]= Nuclesr - -
To C. J. Halbfoster Location Oyster Creek On March 14th, water was discovered coming up from the south-west corner of the ORW Building. The overboard discharge line in in thin region and, nince an overboard relcane was in pro-gress, the overboard discharge was promptly stopped.
The first chemistry sample obtained was a water sample from the general area. Chemistry technicians were unable to collect a sample from the immediate vicinity of the water source. This liquid sample was within all requirements for a non-processed water release.
A liquid sample was obtained late March 15th during excavation.
Maintenance effect' repairs. was digging undershowed This sample the southwest Cesium-137corner (Csg{) ORW to activity below administrative limits of 20% of 10 CPR 20.
The results of the liquid samples are shown in Table 1. The results of the two (2) previous overboard releases are also in-cluded for compar.ison. The 20% of 10 CPR 20 limits for liquid releases are shown.
Maintenance personnel exposed the discharge piping, but observed no hole. Domineralized water was put through the line and the hole location was determined to be under the ORW Building.
Chemistry collected seven (7) soil sampics during excavation of the area arcound the discharge piping. Four (4) samples were approximately at the same elevation as the discharge piping.
The sample locations are mapped on Attachment 1.
Table 2 contai.ns the results of the radiological analyses Sample Number 4 shows greater activity levels for both Co50 and Csl37 The activity levels for these four (4) samples do not exceed 10 CFR 30 limits :.or the administrative limit for Cal 37 of 10 times 10 CFR 20 limits.
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- Chemistry collected three (3) additional samples approximately
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ono (1)- foot below the dischargo piping. These samples-(5-7) are mapped on Attachment 2.
Table 3 contains the results of the radiological analyses. The
- activity levels for those . throo - (3) samples do not exceed 10 CFR 30-limi' nor the administrative limit for Cs137 cf 10 times 10.CFR-20 limits.
The somewhat 'g reater activity lovels (greater than 10'l, of limits) for Sample Numbers 4 and.6 are. typical of soil in the Radwaste yard area. Table 4 illustrates activity; levels from several soil samples from the north side of JORW.
Based on-the above informaton, it .can be concluded that no environ-mental release. exceeding any imposed limits occurred as a result of I ho overboard dJ nchargo pipe break. Thone actionn have been reviewed by the Plant Review Group (PRG), Messrs. Cowgill, Nimitz
-andcBellamy of the NRC and have been approved.
If you have any questions or. comments, pleaso contact me on Extension 4606.
'q( k, w-radley Shumak r Chemistry -
BCS/CJII/mjw Attach.
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' TABLE; 1 LIQUID SAMPLES I
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Date:- Sample No Description. Activity gCi/ml-b- .f3-07 .522-84:
Overboard ( MDA 3-14 225
- 3 -07. 518-84 . overboard <,MDA' 3-14 1335 3-14 571-84 = Water 2.n Ditch (MDA Between ORW Control Room & R.R. Ai--Lock 137 2.64H-G 3-1f . 577-84 Water in Excavation -Cs of-Discharge Piping.
l37 20%'of 10 CPR 20 Cs 4.0E-G
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'E : SOIL SAMPLES- ,
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Activity pCi/gm 2
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ds 1 cs 137 s
1.11 3-16' 583-84 1.21E -
6.88E-6 z,
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384 8.44E-6 -
7.40E-6
_- !3 :3-16' 585-84' 2.5GE - 1.53E-G t-f4 L L3-16. 586 84 1.01E-4 4,07E-6 1.65E-4
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. SOIL SAMPLES
- , c .
4
-y
, ActivityJuC1/gm No., .Date . Sample-No.- Co 60 Cs 14 Cs 85 y i -
3-16~- 1.47E-S
~
15 ~
'590-84 -
7.86E-6 y ,
f w~.
591'-84
- 6' s -'3-16 4.45E-5 2.45E-6 8.70E-5
~
, y '7'- :3-16 592-84 t >1.68E-5 - 7.01E-6
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i.'f TABLE 4 NORT!! OF ORW. SOIL SAMPLES.
FOR' COMPARISON _
Activity NCi/gm JSampld-Number- - Co Cs Cs
[ .. L.2957-83 9.26E-5 3.15E-C 1.39E-4 ,
'2958-83 . 3.94E-6 -
8.91E-6 L
T2959-83. 9.01E-5 { 3.14E-6 1.87E-4 29607s-83 ^ -8.71E-6 l ' .5 8 P.- G G.GIR-5 N
'2960B-83 8.30E-6 1.80E-6 6.51E-5 a
- 2961-83 5.39E-6 - 1.40E-5
[2962-83 '3.88E-6 -
l.51E-5 V
2965 4.44P-6 -
1.44E-5 e
- A 2966-83 6.59E-6 -
1.56E-5
'2967-83; 3.llE-5. -
9.85E-5
2968-83 ,
8.83E-6 1.85E-6 1.04E-4 4
4 4
- - . - . - - _ . _ - . . . - - . _ . . - . --___._----_..~ ----_-_._---- -_- ___-___ _ _-- ___ - -- _ _n ---
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Limits r
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Isotope. 20% 10'CFR 20 (mci /ml)-
10'CFR 30 (pci/gm) jk; -
Co 60 .6,0E-6 5.0E ...;.
134
[ 'Cs 2.0E-6 9.0E-5 137- - *-
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'10 CFR 20.Llimit.
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- 08731 UNUSUAL _ INCIDENT CRITIQUE .
=
LOCATION DATE 3 / P /C+[ TIME ' ' I tt ' ,#97e *'
0F M " f I* I\' 0' I '1 N A INCIDEM Sv W e OCW /1H N/ IMd} UNUSUAL INCIDENT REPORT f l 3 f- R I INVESTIGATT0*i DATA; DATE J7 !b'! TIMg i f00 ,
ATTENDEES:
R fL NC tb MPA Or1Nce_ - [ tR 7 ~
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I
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TITLE NAlE DEPT.
."EC INCIDEM DATAy ,
SEE AITACHSD COPY OF UNUSUAL INCIDENT REPORT EUIR / 3[-8 I
.III. IS THIS INCIDENT REPORTABLE TO THE NUCLEAR REGULATORY COMMISSION IN ACCORDANCE UITH 10 CFR 19,10 CFR 20, OR TECHNICAL SPECIFICATIONSt YES NO NRC NUfIFIED BY: DATE TIME- -
EXPLAIH' 1
I I
INDIVIDUAL FROCESSING REPORT TO NRC ' .
. i'.,
y . - - .
,__. PERSONAL IEC.T'MMINATIO:i RESUITS 915.10 Rev. 1 6/3/80
't
!.', e A. FOR LOCATION OF C05TAMINATION SEE ATTACHED PERSONNEL COIC' AMINATION FORM.
B. INITIAL READINGS AFTER FINAL DECONTAMINATION ,
D?M <f DPM [
~
[
Ma/nR Ts 1" Ma/la TO 1" MRAD /Im 3' O 1" MRAD /lfR.B- @ 1" C. LIST IDENTIFIED IScr0 PES D. TYPE CONTAMINATICN: REMARKS-LIQUID I.
- \
DUST, SAND, DIRT
~
RESINS
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OTHER
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I BIO-ASSAY MEASUREMFXT A. TYPE ASSAY & TIME TAKEN.. . ... . . . . .. WHOLE BODY COUNT [
URINAI;YSIS...... /
/
[-
FECAL..........
UTHER( ). /
l _
B. RESULTS:
ISOTOPE @ nci %MPBB
. T0rAL,,[,._
C. ADDITIONAL ACTION TO BE TAKEN,GIVING TIME FRAMES
?.. ..
915.10 Fev. 1 6/3/80
. j ',A. PAR'J' 0F BODY EXPOSED: 1. ] imD 5 0 Anvs 9 O ' SKIN
- 2. EYES
, 6. C LEGS 3 TRUNK 7 ] HANDS i
- 4. O oon^os 8- rzer '
B. TYPE RADIATION g {f ] NEUrRON ALPHA C. ESTIIMTED EXPOSURE & METHOD OF DETEF21INATION D. REMARKS
'J W
'ZII .
ADDITIONAL INFORMATION
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[ *.'
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9 CRITIQUE REVIEW D
9 v
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ENuoleer oyster Creek Nuclear Generating Station '
RadiologicalConteof Survoy Record
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* ~
Page . 16. _____ _ __. ___ _ _ . _ ____ . __ ___ ____ ___.__ _ __ _ _ .________.__.m
- N m:HARMYKIRICHARD U- ID: 148-34-2423 Job: Fil: 1941. Tim: 18-MAR-84 '21;41-
-Investigational RWP: NONE Emp:JCPL Cn t: S. WYNN ACCUSCAN
- Ccm:POSSIBLE INTERNAL. CONTAMINATION '
3- ; Exp Tim: 3/18/84 1530 Exp typ: ..: t __ _ __ _ __ _ _ __._ _ ___
; Nuc K-40' . CD-60 TOTAL-
! Act 122.7 6. 3 129.0-
! Err 19.0 29.0 1 %BB O. O O. 5 .
O. ' S l Nam: HARNED KENNETH E ID: 138-38-4419 Job: '
~~~~ '
* * - ' '-M AR-84 09: 40 ,
, i New Hire 'Em p : CATALYTIC ' AN Com: NEW HIRE'. _ _,
/(
i l Nuc K-40 TOTAL Act 67.2 67.2-Err 34. 5 - 4
- XBB O. O O. O I Nam:HARNED KENNETH E ID: 138-38-4419 Job: .-MAR -84 10:38 i Termination Emp CATALYTIC :AN i Com: TERM COUNT i Nuc K-40 CO-60 TOTAL i Act 103.0 B. 3 111.3 i Err 26.9 37.0 i ZBB O. O O. 7 0. 7
_ _ _ _ _ _ _ _ _ _ _ - - _ _ = _ _ . . Nam: HARTLACE ANTHONY ID: 169-32-7961 Job: 2-MAR-84.12: 59 i New Hire Emp:PROTO POWER CAN I Com:NEW HIRE 1 i Nuc K-40 TOTAL
- Act 90.9 90,9
- Err 26.2
%BB O. O O. .O
~~ ~~ ~ ~~~~~
bamIHES FRANCIS 5
- New Hire
~~~iBI~555234-5545-Emp : JCPL 5bi----- Fiii iE527 TimT55-T4AR-04 IIT55~
- Com:NEW HIRE Cnt: FLEQHMAN FASTSCAN Nuc K-40 TOTAL i Act 85.9 83.9 1 : Err 29.9 i %BB O. O O. O
_ _ _ . . . _ - _ _ _ _ _ . _ _ - - _ = ._=-__ ___ ___. __ _ __ _ _ i 4
RGport: OYCOO4 ________________________________-_________________.____________________________,_,,,,__g________Pago:'.30 i Nam: STERLING ROBERT W ______p___q 0
- N;w Hire ID: 158-32-3555 Job: Fil: 1648.
! C m:NEW HIRE Emp: JCPL T im: 05-MAR-04 11:01 4
; Cnt: FLESHMAN FASTSCAN
- l ________________________________
Nuc K-40
! Act 74.1
- Err 35.0 TOTAt
! %BU 74. 1 O. O i
! Ncm: STONER LINDA G O- O NLw Hire ID: 309-66-6747 Job:
I; Com:NEW HIRE COUNT Emp: CATALYTIC R-84 13: 1/ l Nuc-_______________________________ K-40 _ ____ i Act 86. 5
- Err 27.8 e TOTAL I 7BD
- 86. 5 O. O
- N;m: STROLLO STEPHEN O. 0
- Routine Frq: ANNUAL ID: 146-40-5295 Job:
I; Com: Emp: CATALYTIC R-G4 10:24 l Nuc ________________________________ K-40
! Act .06. 8
! Err 27. 0 TOTAL
- ZBD O. O 106.0 ,
l Ncm:STROUP EDWARD W Y O. 0 ID: 138-48-0175
- Investigational RWP: NONE Emp:JCPL Job: Fil: 1943. Tim: 18-MAR-04 22: 04
! Com: Cn t: S. WYNN ACCUSCAN g
POSSIDLE INTERNAL CONTAMINATION _ _ _ _ _ - ,_ _ _ _ _ _ _ _ _ _ _ _ _ E x p T i m : 3 /18 / 84_ _ _ _ _ _ _ _ _ _ _ _ _ _p 1530 Cx typ: i Nuc K-40 _______________ i Act 154.4
- Err 13.9 TOTAL I ZDB O. O 154.4
)
_____________________________________________________ O i N:m: STRUDL" CHRIS N ID: 137-46-1866________________________________________________O F
! Routine Frg. ANNUAL Emp : JCPL Job: Fil: 1847. Tim: 14-MAR-04 09 41 !; Com: Cnt: NG WILLI FASTSCAN l ______.________________________
Nuc CD-60 K-40 ______________________ i Act 12.0 171.4 Err 15.7 TOTAL 19.4 103.4
! ZDD 1. 0 0. 0
________________________________________________________ ________=-
- 1. 0 i Nam: SWAN THOMAS S ID: 002-40-8702 --____________________________________.
i Routine Frq: ANNUAL Job: Fil: 1738. I Com: Emp : JCPL Tim: 07-MAR-84 15:20 Cnt: FLESHMAN FASTSCAN l Nuc K-40 _
; Act 115.4
- Err TOTAL 23.2 115.4 1 7BD O. O
__-_________________________________________________________________________________-__________--___-().O _ _ _ _ . 4em * *- e.*m- h ssp + Naur=4 *Me = e+ -e
.g-.
--_z se F- 4 '.' 6e # . A %
__-___------_--_-------------_-----__----_--_--_______--_______--_--_----__--__-_--_--__--____---- =;-. -a Report: OYCOO4 Dyster Creek Nuclear Power Station - ~ . . . . t
- -Nrm:
- _ _RUSSELL
_ - - - _GLENN _ - - -J- _ . . - - - _ _ _ _ _ _ ID:- _ _-_--------_--__-__ 154-48-0244
- - - - - _ - - P,vj
- - - - _ - - _ _ --_--__-----------..- - - _o -:. _TN_
I Routine Frq: ANNUAL Emp:JCPL Job: Fil: 1848. Tim: 14-MAR-04 D9L44
! Com: Cnt: NG WIL
- Nut i Act-
_ K-40
- - _ _ - _ _ _ _ _ - - - _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _LI FASTSCAN ___-__.__--
109.6 leTAL
- Err 26.8 I %DD O. O 109.6
! Num: RUSSO ; BRUCEU ES A O. O
- Investi' ational RWP: NONE ID: 109-40-5090 Job: -Fil: 1942.
Emp:JCPL Cn t: S. WYNN Tim: 18-MAR-04 21: 52
!1 Ccm: POS IDLE INTERNAL CONTAMINATION ACCUSCAN g
l -Nuc _ - - _ - - _ _ _ _ _ _ - _ _ _ _ _ _E x p Ti m: 3/18/84_ _ _ _ _ - -1630 _ _ - -K-40 _ _ _ _ _ _Ex _p typ: I
! Act 125.3 i Err 16. 8 e
TOTAL
; XDD O. 0 123.3
! Nam:RUTLAND EDWIN J 0. 0
- Termination ID: 178-30-5911 Jt ' - "* 'Aos
- Com: TERMINATION COUNT Emp: GENERAL ELEV CD Tim 06-MAR-84 13:11 FSCAN
! Nuc --__-________---_--__-_______
K-40 ___-__-- i Act 104.3 i Err 23.4 TOTAL
! %DD O. 0 104.3 i Nam: RYAN JAMES 0. 0
- Routine Frq: ANNUAL ID: 138-48-3326 J '
Com: Emp : CATALYTIC :12-MAR-84 13:56 TSCAN l Nuc -_-----__-____-___~___-______ K-40 ^ i Act 122.4 1 Err 22. 1 TOTAL
- ZDD O. O 122.4
_____~_____-__-_-____--__-______-----_-__--_----__--
- - _ - _ _ - - _ O. - _0_ _ ! Nam: SADAUSKAS GERALD ID: 104-34-1093 i Routine Frq: ANNUAL Emp:GPUN J
- OS-MAR-84 11:33
- Com
- iTSCAN I ____--___-___--__-__--_--_---
Nuc K-40 , ._ __ ___- Act 128.9 i Err 19.4 TOTAL 1 XDD O. 0 120.9 I Nam: SAFFER HENRY J i Termination ID: 138-12-7237 ----__--___-----_-______--_____-_______----__-0.0 Job: Fil: 1637. l Com: TERMINATION COUNT , Emp: CATALYTIC Cnt: FLESHMAN F T.m: 05-MAR-04 10:13 l Nuc i Act _ _ _ K-40 _ _ _ _ _ _ _ - _ _ - _ _ ~ _ _ _ _ _ - _ _ - - _ _ - - - _ _ ~ _ _ _ - _ - _ _ASTSCAN __ -___--_ 93.7 TOTAL
- Err 26.9 1 %DD O. 0 93.7
-___----___-__-__-___--_____---___---_-_-_-----__--__- ~
--_---__-_____-__----_-------__---__-----_---_0.0 _ _ - - - .
, eea gp spa .,.O en = .O h-=M * * ' "
r._ _ - .___ ..___ _- -. . ~. _ . ! 4 . ..
~
_________________________ ____________________________________________________________________________u___, L0gster Creek Nuclear Pouer Station - - At . . -~..
~
RGpcrt: -Page: 1: ________'OYCOO4. ___________________________________________________.__ ___________________________.________ a___. _________________________________________________________._________________________________________-___u.__, i N m:AACE THOMAS- ' ID: 138-32-3130: Job: Fil: 1858. Tim: 14-MAR-84 ~10: :43; Cn t: NG- WILLI FASTSCAN Tormination Emp: CATALYTIC
- . Ccm: TERM COUNT l Nuc K-40 '
-T UT AL .
- Act- 108.9 10H.9
- - Err 24.8 i %BB O. O -
- 0. 0
__________________________________'_ ________---____________________________________- _- ______________= 1 N m:' ADAMS ' JOHN 2 K nW - ID: 546-60-4799 ~ Job: Fil: 1939. Tim: 18-MAR-84 21: 16 l'Investiaational RWP: NONE Emp:JCPL ,
' Cnt: S. WYNN ACCUSCAN
- Cem:POSSIBLE INTERNAL CONTAMINATION i Exp Tim: 3/18/84 1530 Exp typ:
! Nuc K-40 TOTAL
- Act 117.6 117.6 i Err 18,4 ,
I XBB O. 0 0. 0 -
~~
! N m: AGUADO ~CLIFFORD ID: 151-50-4825 Job: Fil: 17
i Routine Frq: ANNUAL Emp:JCPL Cn t: FLE I Com: l'Nuc K-40
- Act ' 148.2
- Err 19.7
- %BB O. O Nam:ALESI' FRANK C - ID: 137-64-7030 Jo b : 01 Fil: l'
- Termination Emp : HYDRO-NUC Cnt: P.
I Com: TERM DODY COUNT , ____________a _ _ _ _ _ _ ____________________
! Nuc CD-60 K-40
- Act- 13.8 110.5 i Err 18.0 20.6
%BB 1. 1 0. 0 Note: Ex ternal contamination suspected due to recount' showing reduced activity.
I Results more representative of the true internal burden are available elt I N5m: ALESI FRANK ID: 137-64-7030 Job:01 Fil: 18-1 I nve s t i g a t i ona l - RWP : NONE Emp: HYDRO-NUC Cn t: P.
- Com: GREATER THAN 1% IN FASTSCAN
- Exp Tim: Exp typ:UNKNUWN g __________________________._._______________________ __
! Nuc K-40 TOTAL
- Act 138.0 130. 0 i Err 10.8
- %BB O. O '________________O.O _ _ _ _ _
________________________ __________________ ___====______________________________ eee+4 -e ,. eier mdemq m eyam.ne .q1.y 5 e = w e%er e- - a6. g..e.e.pq s- ,.-, e%m - 4' . ee emei a e .,e,p y si pd* yse a 4 ,,g.. ,.sgg.
is ame w win e r_a m wwwu s- .- - -
~q t
Dyster Creek! Nuclear-Power Station. ' " " ' '
"?'-
Ropert: OYCOO4 . 9 ________________________________________________.______________________________u_______-_________Pager __-__u__-
! Nem:DADDUNDO MARK ID: 135-66-6674 dob:01 Fil: 1902. Tim: 15-MAR-04 *13.: 50 Tormination a Emp : HYDRO-NUC Cn t: P. CANAL FASTSCAN i Ccm: TERM DODY COUNT 1 Nuc CD-60 K-40 TOTAL
, i-Act 14.9 98.5 113.4-1 Err 15.9 27.4-i %DD 1. 2 0. 0 g ______-___,_______-__._______________________-____1;R 1 Nate:Results Ex t ernal contamination suspected due to. recount showing reduced activitu. I more representative of.the true internal burden ar _____--__________________________________________________________,e_-______________________________________. available elsewhere in this report. I Nzm: DADDUNDO MARK ' ID: 135-66-6674 Job: Fil: 1906. Tim: 15-MAR-84 14:24 i Investiaational RWP: NONE Emp: HYDRO NUC Cn t: P. CANAL'ACCUSCAN
! Cem: RECOUNT GREATER THAN 1%MPPD I
g _________________________p
! Nuc K-40 Ex Tim:
Exp ty p : UNKNOWN
! Act 134.5
- Err 17.1
! %DD O. 0 Nam:DAUDERMAN JAMES V ID: 160 40 7245 Job:CN Fil: 1951.
1 Termination Emp:O'D CANNON Cnt: D FISHDI' i Com: TERM COUNT g __________________________________________ I Nuc CO-60 K-40 Act 17.1 116.5
! Err 15.9 24.2 i %DB 1. 4 0. 0 g _____.--__________________________________ ' No te: Ex ternal contamination suspected due to recount showing reduced activity.
- Results more representative of the true internal burden are available elsewher I Nam: DAUDERMAN JAMES V ID: 160-40-7245 Job:CN Fil: 1953.
I Termination Emp:0 D CANNON Cnt: D FISHDE
! Com: TO VERIFY FASTSCAN TERM COUNT OVER 1
! Nuc K-40 -
l Act 121.6' ' Err 24.2 i %DB O. 0 . i _____________________________________________________________________________________________________u... _____ Nam: DEACON ? THOMAS ? ID: 069-34-0489 dob: Fil: '1940. Tim: 18-MAR-84 21: 29
! ! Investigational RWP : NONE Emp : dCPL. Cnt: S. WYNN ACCUSCAN I Com: POGSIBLE INTERNAL CONTAMINATION
, ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Ex_p_Tim: _ _ 3/18/84
_ _ _ _1530 _ _ _ _ Ex _p typ: l Nuc K 4O TOTAL
, i Act 139.0 139.0 i Err 16.3 i %BD O. 0 0. 0 4
9
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g LCS (beta) SAC (Initial Alpha) '
. SAC (Decayed _ Alpha) j' SER START CROSS CROSS NET ACTIVIT1 SER START GROSS CROSS NET LCTIVIT1 8EI Id. Cross . Cr9ss NET Activity',
i # TIMR - _ COUNTS c8M c'M -4ct!ce ! ,fue ennu,e cPN _EF C defIcc 8 Y mam r a CPM . CPM uisi/cc J (7 2. /JT/ t' 4 "2 /7 7.Y 72.2, (,.2e 12. 3,L2_ 2 /53r or 7.9 F.% /.9E73 4M l_ msV B1/ 7?c 3 /Wo. G 14/0.7 2.le'9 W9 isMr 9/ 4.f 37 132 ! ,_1 .472- nry 4W,7 Y719 4W .dRtil m 2. nrr ze 2 1r 2-(.c c.ve /4 . i r~:qk iDn N9YY '/W%9 .tSIC 9= 24T.T.: 9.9E"'to . w e. /d I*c t. fa G.S O Cl0 $ tm M M: MD &% "" n =- " .;
- _3. in / 3ft 2 # '7 43.4 7. 2. 1r.4 s1 s- W z. No4 t- y 19 2.76 MMW .
}
} J -m /35 4 439 978 57 7 .$. %7"l/ NH 1Vo& P/ Y.t 1. 9C l 521h I 1 l J /7L / YoC /2/oE 141( :23f M ti7e lo e/64- N/7 //// / 4./ 13-?G 5.2r f 3 '
] ;
j My /40G 7to4 /' yy0.? I'f&d_ loN670 46v /4/7 N ~ T. M M .2dFl3FirU A ' y, !:l
~
Alpha Fraction .
' .g.- (Decayed)
, ' ,. i . . _(Cali) ' -(Cali) TOTAL ,;
i "I BEC GEL.I CAI .CNEM SATT MEAM man t. M. M . CPM RR kcton C TNNT R Ev[ - ' YES NO Fract$oh Act"VITY
- Tu-:AL .
PRAcTfnN TOTAL Ac?TUf,Y r. wmA8,fm FRACTION
.l l'i LCSi /77,- 36.2. ( 2 5- 5 HIN .y _ y,, .py
#1 FART E D 1 -
! LCSI C7 d PT.cf d. 5 MIN r r)4*y #1 CNAR 0 0
*- '"79 #
qi l' SACf 4'/, L- .I4 3 '/ 10 HIN t -2/-G-t/ #2 FART O O M .c -
l 1 .i SAC # Id de .V ^< 3 15 MIN '7-/f - h #2 CliAR O G . I .. ; , uca . p i SAC 4 - ' -
- 1 . '
',f _ .,*
! CONVERSION FACTORSI
- ' 28 ,,,
ll
' 2.83254 cc/cf AI.MA HPC DECAMD AM. 5 TECl( !
- 1000 cc/ liter I FRACTIN = .3 x 10~1 I
Initial Sample < l
- j Count Review CRCS f
~* ', $ pecayed Sample i E Count Review
- cat'st
. i .
..u . .-.:- ,.'..:. .
AIR SAMPLE LOC 7/28/83 FORH I 915. 3-l Rev. 2 [ DATE NI l PACE b Ur '- AIR _ TIiE _ TOTAL, FLOW RATE [' FILTER - SAMPLE LOCATION SAMPLER SAMPLER SAMPLE RWP T1HE VOLUME COLLECTED 8.* . 8/N CAL DUE i # ON OFF (HIN) Chi IPH (CC) BY { [ts'd to074 I . a y 'T;wr to l o L.-l4-h4 6915 8% 7V6 -Pd 1460 t'? ? o 1doO bo 9.fc 6'? ' t en j 2 ^'PI C AsT- ' @ " A crf* t&LL 6-') I ~) 'I (d'lL I -Ilo'b & b1620 \'27 0 12L0 (, 0 ~7.EG '? , 2 pm 4 3 'O t .M t- 6 6 9> - 7-T < (c.9-'l-) Ts6 ) L.2 0 t%5 r7 ~) T 60 ~).')6~)/ 3 Tp J St* 'h . 3 Llnd 'l- d l 69TI / S fes t r3D t3dM \ 9.T G6 l.t -) g r) 4 'pj[ ' g 77- lw t ?_'5 I,-79 l L,9% i $~t> n i M5 Gto )W t., o ' t n <;M J pi2 LI-19 L LY l 6LD I WIO ^ G'5 0 6 l ') * 'Th 3 (,"3 ) 19 0 Gn I . b l2t l _f M .'
! "7 N h e se b m'h v.tur=,e" '2369 9-? N L W ) 4 ' 75'I- 4 13Mf N20 : S 2.- ~2 _
ZH Ebb ] Tr ' 8; kr.w *A'dP NG#rR(2.- '2n~)9 9-l9 -8N fd23dLD3M 14of.1410 2.5 Q _7.bh% ,8 ,,P, fd, , _, LCS (beta) SAC Qnitial Alpha) SAC (Decayed _ Alpha) SER START CROSS CROSS HET ACTIVIT1 SER START GROSS CROSS HET (CTIVIT1 SER id.' Gross. Cr9ss NET Activity',
# TIHR Co[]jiTS CPM cpm McTfet' 8 I1ME-JOUNTS-- Celi- CC Ar'ffcc I Cnim r a CPM . CPM ubf/cc j t7 7 tt)?P. 4% 0 .~2- 54.'Z- 3.M F tlL 2. g 5bf 7tG 7.L L 7t M /?N t oc
_j ni4 Mo 9 o9 ft.).8 \4T.2s 1.l L E-I\ dLd i-r# A')V T' 7 9, T744 R.)4F-0 dra
.2 n> w. < m itRA L9.d _ 6 0L E-fz do rs6 61L' L1 L L,7M liF-l'L -
- 02 J ,,A w .- en u 7 . L_, w s. ) 4.z ;E-t '. tkA ms 2A 19 na 4Pm at J N KtT 'd 7El A '2 A .5 1.2'2 6-) D NL'2 M75 \9b 19.0 l9.M '2.M E'll. . -
O(2 i T40.N t- A .Ci '1."12E -f t Ad J >>.a iM '7')67- iT2T god g n,6 9 6LI J. psE-IA . n p_. J bi' 1O< 2W3 *2C.W 73 W $$IG-\\ $(.T \*SAO 'VC; 9-t%- C V.% !" 9 f-/.2 ' -' a, e - a f d _ts7f_ <h2- on.t! %. S 19sE-v dtd m4 0 /79 n.e /7 W me w diu 17s ib n.r A u.^W-6 ,
, y.
g. Alpha PTC Fraction ,
,, ',- . - (Decayed) _( Celi) (Celi) TOTAL BKC C RR CELI CAI.. CHECK SATT PARTICU', ATE CllARCnJ f. H.P.C.
COUNT CAL DUE CPM F CTna .TTHR tuTg . Frac,tjo g . pg( r FRACTION LCSI 177- . n , n.$ 5 HIN 1.%.84 #1 PART 0 0 1 - 2
Ms's-.-d '
?
32.M tl D 5 HIN 5-n 4) #1 CilAR O Q . 3 ' SACf h7 A2. 3 'I 10 HIN 9 -7 t.9M #2 PART O O r- .c SACS 4(d .& M 10 HIN '7 - ts.M #2 CilAR O d h . SACiw
- II ' ' .N LS\ wwsW r m .9 q ,
SAC 4 ' - i I
- CONVERSION FACTORS (8 ,,
,/
U E. @ ALPHA DECAYED ACT. 1 ' 2.832E4 cc/cf 1000 cc/ liter E
,3 x 10 TECil '
>r .
- {d('
FRACTION . * * * ' Initial Sample g Count Review CRCS . . 1 M ffr vt' ~ / Decayed Sample . Count Review CRCS WJ
.c ,.
- i. .
AIR BAMPLE LOC 7/28/83 FORH f 915. 3-l Rev. 2 [ DATE 3 ~ 3/-N l PAGE "7 Ur AIK TIHE TOTAL FLOW RATE FILTER *
! SAMPLE LCCATION SAMPLER 3 AMPLER SAMPLE RWP TIME, s. VOLUHE COLLECTED-l _
8/H CAL DUE # f ON OFF (HIN) CfM ' l'P (CC) BY l A t OA h> VMA ' DT5 ' 'AMJMCd "OO V" G-%- CL) A9Y? - W ~7 C / - N //2O 17 5.2 ~'92: ~ dW s'). ? f / 7 I WC- { 2 nlWE ) O M W* *
<2??6 9 -2 /-W 69 % \ 7W /780 / 7/ 8' /9' 3-7 /.91 & & _2 /~6 3 // 9 / 'Ak- cf ESP S9&* S' 2-9 tJ (A % \ S~CO /S*r D /f"VD / < '-S~O bO 9*. '7 K ~7 3 JL l n~cn '
4 l'"/' A X s1K &~P o=<s V 6 '/ -W / 9 << (- I / ?O /dn esD Go R'. 7 E'7 4 s c. g_$ . M m: >:M"us Rn */(<' 89b 7 /O - f +' /M7 l 70'-/ . /r> 'rc sceO -2 ST G*' / 53 c_ 7 _3 9M
', 6 i n? <' v i due1. 97L// 4f //,c>9 6 -Ju-NV (Rh ! . 56 4 I //W /_c%D e2 ST~ GO / -I'r
- <!*? _6 ~7~t-
/ cirW l ' 6b l /W4 /Go 1 C bA 1h h C/H/A) a fo/6, 6 .*>9*-5%-
75 60 ~+d S~ EG _] As 8 W PMa>FA V7' Al- 21*M/vwv /2-2 9-5'-Er'/ (cf90 $ SS.~Q, b /'l0S A"hS SO . & G' Q 6 Q_ . l'CS (beta) SAC _(Initial Alpha) SAC (Decayed _ Alpha) SER I START TTHE CROSS cnUNTA CROSS CPM NET CPM ACTIVIT1 SER 4c7 /" 1 START CROSS 21NL-COUNTS-JP}{_ CROSS NET CPM' Aff/f'c (CTIVIT1 SER I ik F Cross cnitn t a Crges CPM NET
. CPM Activity' util/cc l _.L / 7.2- 19/5 /9c/ W .374 . L 3'f Ma f.2 6-// -+4:& JHs /*H"O /*/~C' /y*/By //h-// LD~ & 'Yh- Y.3 - 3.64- 3 AM-6 j /*O. 2 c/64' /XYS /A O //, L W s/,0 a'-// 2Ht 8
~
i U/s G /"</** 7 sJ/ // $~~7 3, f, E-/c / .2- 1% c, .R O.2 d 2. t51 t~~6
/+W. $ 9, 2 5-12 YM /9/O 0?l
,_} /7h 19 0D V ~} Y / 7*i' b 23*l 2.297 4' <f f*-/3 MR j 2 nt ~ s'NO M ,2 Z' . 4 3*7. 9 2. 7 f-nu U6'S /9/D /40 4 /'d / b > L, v 2. rf-e me
,,,_} ' 7 .*L /'f/ C A s/C & <f _ -? ? / ?f-// dd*2- J'AM' V7 S *? 85 bOf-/A . -
Asor
, j ?? A /C//S r,7 9 'l- .
" '%', 9 2& % / Of -// A*d lN5 29 O0 l*k 2.7f-/3\
- m IL .
l 'J .i-72 /% ~~ / 5'k 37 dj rp (pf.// 442, 793 S 9 9 , 75' 33 d~-/3
- p t f- ,
y ? .1/ ~N /Q26 /'M '.9 C G b./ <2.4ff-// </$ tJ
/9.W f7 l* ~l .' .l>
Alpha
'/ b O S-/3 PLPG Fraction
.UO '
, y, g .. .
,. . . .- (Decayed) _Cali)
( (Celi) TOTAL BKC CELI CAL. CHECK SATT PARTIClr ATE CHARenJT. M.P.C. RR COUNT CAL BUE CPH CTna T T H p^ nATI -Fractjoh TUTAL . TOTAL r. FRACTION
; . . . YES NO --
AqTIVTTY 'RACTfnN A f'T Tit T TY gn A8PYnt LCSp g . .-G , /a. y 5 HIN 7_jo _vy #1 Pl.RT O 1 -
" *b S- -
2 - LCSl A w'd 3'2 ; 6' /3 O 5 HIN Cf/ _py #1 CHAR ] , SACg 4 6.2., , /2. 27 10 HIN 9 4/-gy #2 PART O p r- .. SACf +0 , 26 3. 3 lbHIN 7-/S~WE/ #2 CIlAR O .. , SACat '2N .$ ' +', / ! >nh 2 Sh- , 6
~ '
I SAC 4 - - I la DECAYED ACT. l 2 83 E ALPHA .-
%M HPC =
1000 cc/litar FRACTION 3 x 10~ , TECl{/ 5 ' .l .[ / [ () * ' . Initial Sample Count Review CRCS '
' + "M M '
//
?
l~ Decayed Sample
* @wma mcw&m * '
1 cRcs
a . { AIR SAMPLE LOC 7/28/83 FORH # 915. 3- f Rev. 2 [ DATE N-l - l PACE or , AIR .. _ TItig _ TOTAL FLOW RATE FILTER , SAMPLE LOCATION SAHPLER SAMPLER SAMPLE RWP TIME ., e,,, VOLUME COLLECTED d _ S/N CAL DUE i i ON OFF (HIH) CFM ' LPH (CC) BY l 4-1 os. e & u e . o n m. &au (' vuob 110 '~1- L -IN '7019 -M 'l as n . Ol 14el , $ 'L'l 103- 'Go G . i t, C L. I f,8
; 'vc ' e a %r :r, pe en f., - r il -
2 lon9 ~In t o - I n f Li - 09 n o r.co s 3*54 f. c, T t r r -s 2 PtL ~ 3 c .. 7, m al m- D. _ w ,,*,e ., L a,t- 4- e-- ,,e i - 77n n. e, ovn Sn 4 s c. v r, ~3 4 Ari 4,uktge nim S w. (mroh 007 R-P - Te 7_ - 7 fl - # 70r 1826 ~/ 5' - 60 4. ti F /' 4 // - . g._L tw nw.a <.. e I m.. e wr n13 t-,- R * 'I s 6 - l'id-i 1%< 'Llo o l> O I. ' G i '1 AT
' 9 n =f. - 5 6 -
c --mk- '
.6 mk. ?
J .. J 8 . . - -PA ~T.;.;:6&& J S_ . is - LCS (beta) SAC (Initial Alpha) - SAC (Decayed _ Alpha)
.SER START TIHR CROSS entturs CROSS epw NET cpu ACTIVITi SER START GROSS CROSS NET (CTIVIT1 SER id. Crosa . Crqaa NET Activity',
f 4cvfen i IINE-JOUNTS-JPli.- Ci dlEYffe E I"'in c . cpH . CPM t,b1/cc h,I t 17. huu- M S- 58.b, 26.5- 7.ur-it 4yt im6- '3t - '3. I' i. o2- 6.'l@ t6 '" - silR
,_2_ 1hs4 UAO W8 FRL .58.7 /.*ser-il th,d ecs 66 S, L. 5.'L P> B Hi-t3 J l ;)
,J _L 1.L , r e# 5 Ll % WT.'l 64. t 6. 'er- n 4 f,7 IStB 141 14.2. 24.11 7.?f-11 14/ 14 Y 1/. 4 R.8 G - 13 1 zhs4 19/ 7 L17 I 2 f.L %.1 f. M F- 10 tu,4 19.13 iHI i 8-l. t f 3.7K s.o rr-t2. Al /R
,_1 n? 7icA 3G"2- 72 .ti .M . 3 1.9 t-t I tlt? 2iin 51 5.;;L s./2 rea . .
4N4
-p s.4 st = , .
j.6.-n l t- 6 e - - p Q u.M 4+-
- y, Alpha MFC Fraction
'htO
- g. .
',- .- (Decayed) _Cali)
( (Celi) TOTAL , BKG CORR COUNT CAL DUE CELI CAL. CHECK SATT - PARTICtT ATE CHARC0Jf. M.P.C. CPM FACTOR TIMD^ f1ATR Fractjor TOTAL . TOTAL r. FRACTION l LCSi n?. 33.8 t '2 ..; 5 HIN q .go-g c/
. YES HO -- = -
AqI.LV.LTY.- 'RAcTinpt actftrrry FRA h l I e
#1 PART O O E 1 < m o.a .a lA -
3 wi> 2 . - [ -LCSi n e sd ' 3I 'l . t%.o 5 HIN s - n -6t( #1 CHAR O O , -
' P r- e c i -
s , i SACf *,7 o.cn 17 10 HIN 0-71 -e / #2 PART O G 3. - .,- -- s
'g -
I SACf %d' es .M Ab lb ElIN i- H;-84 f2CllAROf s ~
~
SAC; 2</s ' n ,, c, ' 'I . I 16Mid 2 t b 44-itV , 6 _ SAC 4 ' I a .
' CONVER3 ION FACTORSI -
k - ALPHA DECAYED ACT. - 2.832E4 cc/cf *
=
TECll Nl %N k /t [ HPC 1000 cc/ liter ,3 x 10
~
D' FRACTION ' ' Initial Sample / . Count Review CRCS ' v _ dA7 W Decayed Sample s
//
1 ' Coum Smh
- CRes .A
.,. _. _ s
. . . ~ . = .-
. . . . . .a .
AIR 8 AMPLE LOC 7/28/83 FORM i 915. 3-l Rev. 2 'I [ DATE l FACE \ Ur '. 8AMFLE 14 CATION AIR TIME - SANFLER SAMPLER TOTAL FLOW RATE
, SAMPLE RWF FILTER l
l '. ' S/N CAL DUE f
# ' T1HE 8 VOLUME l J fled # ON OFF (HIH) CfM COLLECTED j _2 d' seS f, 3 d 29 -8J lo A t -84 56 n - e+4 rgo LPH (CC) BY - ' #355 i4ts T 74-onti 7-.'d+ 1072 - 6 f,n - ' ifn A , (,7 ,= 7 1
(.w
. 3 e la '
1346 tw , d 'a in *
. i, en rn-r p w c~ n. on re 74 -
,-s-707s . *r ro o - (35o r3 Se 144ca ten bo A GA F 7 2 < ,
d T. r, . i P nu = . < - w w. ,te- L iom> iqid z s ,,
- 8. <-9 ;~7 3
_( m _ I 6 - T"c . .* - 1)"L 4 '29- ~702 6- W'A - so i. u, 4 n,4 ' p.' o 937. Won 533 Go
, 1 ~..l1.,. . n.,*ob l "2.4 Mo t, (3 '} o (,- O 4f, , o rM ' ed.fo ai? 4
,_ *> t @ ~1 J U s
2 8i m n :,,in r.2 7tnret y E W (i m t? t W
.e n-t1 -) 7o 2.1 v P, Lit. , gnT I4 to 6 t K-bo "A . 6 E 7 ,g h.
~ 4 n W TVP %4 Go
- 3. '5 E '1 l ~.1q2e? W
'96(b4 rnlov 1-r1 7 **'
.) .K '
LCS (beta) } Wh*~c" - la O * #9 2 rta j #w SAC (Initial Alpha)
*SER START CROSS SAC (Decayed _ Alpha)
CROSS HET ACTIVIT1
# TIME cntmTR _ EPH SER START CROSS L - !
CROSS PDW AIPT/Pe NET (CTIVIT1 SER : Cross gna #3 ni to M to1 l'13 9
,,J a g{gr
0UNTS CPM __ JPH ' _* Acffcc #
(%m e a Crgas NET Activity' , _l. ilt- t t M (- m -in CPM .CPH uhi/cc ' J rr.w in,
~l M IEG.4 fr .7 Itit sloV-t%
11-r 6. 5 2 e -it 4t,4 1 J 11]_ th /cv 1540 _ 9 tt *h4 ~1.08 L 35f-/3 dl(t 7.i t . G 11f, . 5 1 Ite F-il ,vk 462 #640 J n.W v5 4 6 SSI 'lo . "2. ~5r3 A 10 4 16. a/ "t6.ht 'i . 2 V-G J _rr ? #bre '42 3
- t. 6 t c-tt Wi.4 '651 iM isR iMg s .4ff-(2
,JfrL '
bN L le t . 5 f.06c-14 4t,1 II.b4 OI j new in V. 6.f f, . 0 L __ pfL d4 f 0 82 'TO. t, 3 kl6G-li 9.4$-11 4W/ _ita DS , a ot .i . . t 69i t e ,1 %i (. 2w-il %t iv4s 7aN t?7 7n.4 20,0$ l.0%~-17 s *
. 3fg e it .
3 j Q] i34'y "L{GD %% B .' LZ.hj"T.42E-16ql 4dj - id - 12.7 - i? . t,2 7. w m *
,J/c_
1 O l'& %b E 'Ir Ig,,[f-@ ~l ""'
*'1 '* e
- f. .
Alpha trG Fraction
" dM (Decayed) . ,
BKC RR _(Geli) (Cali) TOTAL CPM CTOR CELI CAL. CHECK SAT 7 i PARTICU, ATE '
. . T^ cHAncn11. H.P,C.
LCSg s7Z. 33.) Fractioh TUTAL 10TAL 12 6 5 HIN r-ao-gG TES NO -- - F_ AgIIVITY FRAPTTOM AetfUTTY i- FRACTION JBAf4 fru
.f$f _??rN (1 FART G O 1-3)M ta.O 5 HIN 5-i n-e[ 2 .
+
'Sdd[_%R o.0%
#1 CHAR O Q .
3 ~7 . SACf- 44 Nu 3 'S 10 HIN Q-2t-8 tl #2 FART O O 4 s,
~ '
lb IIN ~7- lS-BY
#2 CliAR O N, I
~
$4 Cat 2di _ o.% 4. )
SAC 4 -- io m.c ' Z ~?-k g,g , 6 '
\
C0 S
,)Q tl8 5msa usk .
i e ALPHA DECAYED A q.
- 1000 cc/ liter HPC =
TECl{ li wa ' FRACTION 3 x 10~1D - Initial Sample l}im _
/
. ~* Count Revisw CRCS _
'7tM 9 liecaped Sa3Bn -
- -- - . - . - . . . . . ~ . - _ - . _ . . . . . - . ,. ....~_._n.. ..,.? .
w..a g g n. .
. ..u '
- 1. *
.. . .i ' . ,/.: . ,..-...L.a. . . . , . ,.. -
- Jt J. , ,
AIR SANFLE LOC 7/28/83 _ FORM # 915. 3-l Rev. 2 [ DATEe LI ' 3 ' N '/ ^l Fact l '/ ~ or / '/ . ' SANFLE IACAT70N SANFLER SAMPLER. AIR SANFLE RWF
~ TIME : TOTAL
. TIME-FLOW RATE
, . , . s.
FILTER, VOLUME COLLECTED'
.' i
, L/N CAL DUE f # ON OFF -(HIN) CfM I'FM (CC) ~ BY
} l V e. c 4 6 . . t < M e ARW He m nRL ~) 2 / 8-rcy 7 5 /.-f 4 /850 2/9s /75 -
6G / .65- F7 - 1 Vv A'S .
; ht in'uwPim rN~A 2'"el,M LWimVY;iA Rn693 :C 9:F4 M M4;t4 ^75f-84 $435" YlW niantr M C.hr n 7nsf>w TN#$
3
/ '
J _ _ . - 4 t
/ 4 I!'
,s / .
5
' 6
[ 6
, 1 .e / .
,) '
8
. . - /_ _,
,.8____-. .
LCS (beta) SAC (Initial Alpha)
- SAC (Decayed _ Alpha)
SER START GROSS CROSS NET cw ACTIVIT1 SER START GROSS- CROSS NET LCTIV10 8ER Ib.' Y Grose. Cr9ss NET Activity', c
. # TIHe _.catigT3 cow Acvfec g-- , TIM * "a 'N'ES-- CEM-- CPM 'M Mcv/cc # can ra CPM . CPM uis1/cc
[J71 22 W 9W W.R Kf 2 fy/F-// 4Q 120f I/4 .l l. 4 //J1 M F-p f/P y %sq %qr ;qqm q c: 1 1,79: S;qq Fay 1914 74w x129c rn A1 nw knf.n c=c na em _ unw men wmm ' 2 - 1 '
,_3. V- . . . ,
s b s *
! J '
J. . l ___
- y. Alpha riru Fraction g.'
(Decayed) _(Cel_i) ' (Cali) TOTAL. '.; ' BEC CORR CELI CAL, CHECK SAT 7 PARTICtLATE cHAnnni s. M.P.C. COUNT DUE CPN FAcTna Tfum vm yEg 30 Fractjol TuTAL Ivy roActrnu TO Ac,TAL 1vrev ena/Lerm
- i. FRACTION U. S
, ~ ~ ~
LCSf /72 * /2.f 5 HIN 7-10 -3 y -
' #1 FART E O 1- - -
.s N# 24h 39;/ ' O.o 5 MIN ' I-N-T/> #1 CHAR O O /W
$AC# 4/h .OE 3.7 10 MIN f-2/ JV #2 FAR'r O E 3- 1 -; '
I
*=
4 ' g , I SACf l/P/ ,34 "J. 3 15 MIN '7-#-ff s ., . . #2 CIIAR O E. v Sec;, 2W- Y,/
/0/91[ 2 7-ff *
. -[ - 6 r.;
i < SAC 4 l7 1 CONVERSION FACTORS's
'8 * '
DECAYED ACT. .. Qf J fh g.]
, 2.83284 cc/cf , 9, ,
1000 cc/ liter MFC ~
= ~II'
FRACTION 3 x 10 - Initial Sample. Count Review CRCS . l .- ' ~, t -r / c Decayed Sample. I- '
@mTRJh@n_* _._caca v. _ _ _ _ _ _ _ _ _ _ _ _ _
.n w i i -
t 1 - U v x 9-v e qe r mt e t-au- 5
% m - o .
7 i y o h d IjZ 3 ce q $$ c- .'Q q u tt t y 4 ai b .
' )
u <= q q.@Ng g 'N h.X r. , . a;mg-rq 9at*! .% g . &. * ( p ' j . E 5
.e w wo d
e rQm ' C r N w m a
!! . - [
2 abwb N p 7 re M M b .. -
, C q c.
1
~.
*=8 O
- y g -
- . M e W
a sn
- D* CI N
. 4 4 08') < a (. ,
}
q' I'* { =='- 8 M C ,
"
- g' g 7 i e
0-be C=
-w h hM <> -k *
\.
M n Q [ as N e m s x. o ( C O q ::-)v
- E o COF 3m g [ l s I sc FC 9 4 o e V v
_.*a , 3 ef , a s i 9 v ec w 1 3 - e i o ai y < b 4
- N *of '-
m ( l- l 1 1 ll tra < ot i e o a
~
N Ue S {
~
=- m ok%k k b
^
NE= tc 4 e e, Q b b > . e c c yt o-x s - - -
~h c:at
- y bHw
~ e< d a- av
~ % F -
N a<>
- < Hw oc e.
pe = = e sQ t: 1 ccc 1
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7 /t t 3 af 2:S t* 41l F-2 -6 Y 72fo 32 Y c 33* sfoo Cfo f. o 'V /Yd 7 ] Gad 8 ALei t%.L.a _, &a 4 vv-EY 2 Lit \/ 82[,t/ 0Fh // w /Po a &v _ /, tre 7 6 h . LCS (beta) SAC (Initial Alpha) - SAC (Decayed Alpha) A SER START I TIMR_ CROSS COURIS CROSS PPM NET PPM ACTIVIT1 SER Mcfff'n .,_j- - START IINE CROSS CROSS JOUNTSJEM-.- CEH2 4c 7 /f'f' NET (CTIVITT SER I kY Cross Crgsa NET Activity',
'/ 77 "26,1 -'
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'I J V.L e / L. ( 5 M" '/-36 -87
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qtivity raAcTinM APTivfTY gg@!nn L #1 FART 5 O #1 - jg j;CSi M "0.214y~ e 2 +, 9 n.o 5 utu r-// W #1 CHAR O DA i2 b' ACI M lo J,7 10 MIN 7'JI 'd 7 #2 PAR'r O W 3- 1 ,,
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1
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r* M Nucicar - Oyster Creek YlololAl2lil21ol1lol Radioactivo Work Parmit gwp,gpg.,;gg,99[ Job Locatior, g g Ext ded RWP Start of Job Date~ OUETLRn@ n ~ DrsS@Gf Pl PE -4h'A $ ([/kr '
/b3moh1 I io it is p' afdn,Date F 'Phoffty Code Job Order 3 l*)l1 lC]2 l 1 l 2 l0l1 l0 l 11 Job Tktte RWPnlOI)l$1/181Y m /88/,2 _ g 23 ***' 2 7 81.(1-2t/sur/o.MfW/0) ' '
JM9lU[Q& f [ 6 Typ Work:[ l I Insert Appropriale Code
, E Reactor Operations & Survesiience Tile OO&fbAILD n /Sd4A4G E L /A76~ ~E a**"ad'-' ">'a"a-a
__.ojyj somat Piant Mainienance j (OIlb h6 b Ilj l MOM [ .M O N Refueling 0perations 3 Wsste Processing R lnservste inspection PROTECTIVE EQUIPMENT a D Hard Hat O Lab Coat RESPIRATORY DEVICES REQUIRED h[* [ gy, { "',"*",C'p, Cover)is REQUIRED t K Whole Body TLD o Entremety TLD gOther_IApb pt. Air-Purifying l h us D NeutJn TLD o Beta Gasses % Other it Sell Reader 10-2001 0 Goggles
! )O Self Reader 10-500) U a Full-face NP m . o Self Reader 10-10001 <
u Face Shield e ) Cotton Gove Liners g
- o o Plastic Goves h 0 Alarming Dosunete' O Othet z O Neoprene Goves Atmos-supply ,.
j
)( Rubber Goves - 2 7 f
- O Full-face CF f
yncicrr4 Shoe Covers-g 900'ne, g6 O Hood CF O r Boo s SCBA
, S eIM t equ. red [
f t- a interrruttent E UM Z
)C Contenuous g Y otherl$
- i I
t CONTAMINATION CONTROL REQUIREMENTS EXPOSURE CONTROL REQUIRE,MENTS Jir Rad Con to be Present for Equipmens Opening or Line Break O Gamma Alarm p' w O Air Particulate Monitor (CAM) , W Pteplanning Meeting LA[G S6f@fNerskeb5upu. l. T Dr_ _ pC M Jll Air Grab Sample EveryS.M pt Particulate o Charcoal
+ 8.k b(.%mA Sign in sedent on Special Supplemental Sheets 05 y Notify Rad Con Prior 10 Start of Work b
i O Establish High Contamination Isolation Area o Timekeeper Required I O General Decontamination before Start of Work O Mock-up Training See RWP # a . Temporary Shielding 36 Establish LocalVentilation -
- O Stay Time Hours -- Min '
JC Use h t wrd Collection Contain@er- Sor At'iof.oq MOS a V X Authorized Periodic Field Exposure Survey for ThisEreryducigIDE Job _MREMtoj.* Oc Y)$~*?$r"Ea*m'p7e'r"" Drop Cloth or YBlotter Paper- Huciartt. pe NeYe$. d $c $ $ 5*"E Stfa? $ek tA)R G _o d ota. SURVEY MEASUREMENTS SPECIAL PRECAUTIONS h5-+ S/S* 3969-8Y Location Hadiation Contamina, Ar re 00 D O_n nfd O in m A -+ c.orn
@ rem.or/hr.
tion DPM/100cm2 pCi/CC tal t th' 2.* 155.-gy. frit //, ;ry , g g ogf R69_# 16E-89 or G8CS IR 9'
' D2u) O w boar & ),9,0DO 8,0 G-H As 'tw /EK -ik %3-t4 " "
Disekare g ,Di.ce 8E t Requested by1 Mr -L d Date b b 19 Time Od Rad o gicalCo ro b _ e O 19 Time nob Operations dw - Eh 'Date 3-@O__i9M Time Joh% - Rrdiological Control Termination " Date_ L 19 Time -- h L AOOO1278
g ,y - 'i . . , - > . 915.12 R;v'. 6 .
"J Figuro RO'915.12-3_ ,
8/31/8*' '
@YSTER CREEK NUCLEAR GCNERATING STATION hq '"",' ~ g p g p.o.acx ass per<eo aivan . ysw ; sassy . u 2-Ed)v c
A MAR 1419M RADICI,0GICAI, ENG3EERUG REQUEST ALARA NO.
~ N @ 9D.* * . NI [ N
~
To: MANAGER, RADIGIDGICAL CorrrROLS *
Subject:
oun Renn n Disc %ws Pibe Cec:act: W kf 0 0 Req. Ccep. Oate DESCRI?"ICK OF REQUEST: Tk Arw- WA- - O. N . ~ & M ~l o \
&. amcak &a a .L. M A % r.x.aD20 .
PS.ASC::5/ DISCUSSION:
~
Abu ;
. I SIGa:u > fo A 1 & Y
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M MGE 3l/Y0kCWbdD c R.E.D. SUPV.
- IN SERVICE U NN 1 3 10'"* (AT::ACI EFE.ATICN CT P.IFAI:33G '4C?Z k ISTI:%TED
. CCFF.2TICN DATI) 3 0 JECT ANAL.
,. R.E.D. SUPV._ .
~
O2 7 CCNFLETED R'a7 y 4
, FF0 JECT ANAIIST R . E . D. SUP7.
v . d . Page 1 of 1 9 ' _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ - - - .m
N . a. . . ,*. ' . '. '. ' 915.12 R:v. 6
. Figur(RC 915'12-4 8/31/82-
~
- . ease 1 or 4 R.E.Rf/6 F/
! RWP/ ALAR A WORK SHEET .
4 Initiated by: CEM500t 0 2 mm)radiolog'ical engineering _dgpart ment ett 6980 t Radic1cgical Engineering Review Required D ATE:191984 I Special Procedure Required & Approved i I Mock Up & Training Pre *Jork Meeting with Superviscrs & *4crkers Required sup4 Post 'Jork Meeting Required g Other I nw I II MAN REM E. MON) 8l,$2reen f 0.6 efXJ02 F/4.
- M.3 Numhet of Vorkers on Job 2 ' .[ R. C. T ,, '4Aey s6 Estimated Man-Rea 4.,026* gg
. Actual Man-Rem Esti=atic'n Calculated By III AREA SEI UP & CLEAN UP) __
j f Decca Required in Area. Describe AL L E5fD Sort.:M rs '7V _M" < c*.rrM'1 Llytyy sp7 gam po: ejes.x. j)fr m iss n ettyss y, 1 ? Verification of Decon By /AD Cnn,9 furtury/6stC2 Rencre Radioactive Materials Contributicg To 3kg1 Levels, teserite dfjodh/7/#/#2P
. f,y J"Ad && fwt WV,b4 , fit - I13A"A f. e. #1 A. fih 9Y 1h iset A"V#a?s/Wourdy
/%'>f>*vL?! Ahotf /?sMN' Ar*fn9.
l Verification of Renoval By /s"n c'r./ W"rNF/' / @c' f l er . l C Ceteral Ecusekeeping Required. Leserite /// / g"~? f/~4*////' /#"/ner.rrfe /_
*ll
/4//' // ';'.T!/\*. /.*.AD t//s2 M *?p^tFCt' fsygt,Mmpe &.911//d! /.ef A*~no :r:>/s.) '
thf/>AW112 - Verification of Con:pletion By JM ,[s,A_ge2*psfast. i C Additions 1 Lighting Required. Describe [ojefpM s
.w/m ,/pgJv>#MA///#4/
lM?t/11/WA9ffA/* r
~
Verification of Installation By dads IufcTv//cdju/Artp?f. I
. t 0 Special Instructions __W4' 7) /3/ki/Jf' l'f)V7Cf/>f &Af?I!/l t$t./>!R/'M NA.
g j gf>gdL__f,.// & [ [ 8 & / / t).ff N * .
- i (2M 1 .
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. Ficure.RO 915.12 ,4, ' .-
915.12 Rw. 6
~'
8/31/82
~ , t-Page 2,of 4 l
l l h
._, IV D001. m I] )
[ TLE C Aler=i'ng Desi=eter 3 y
- 5eutron Set Point (
~ Extremity TLD c: e=
Rt. Hand @ Self Reading Desi=eter
~ I 200 =R Lt. Eand ~ 7 l~ Rt. Foot ~ 500 e3
, 1000 c:R !
' Lt. Foet
- L Neutron .
SPECIAL ISS1EDCTICES 77/E Aff621 Fest f,tTA62Y/7cecNs/&se/A//- / ssc AsofAtrys 4,4ts % JO,tR7 fimtetv9.rf CC 6/A AM/svc'f4Wxd . CAD .stS9tf">:'M AW
~
,c e ir i m w n a r,' -
V MONITGRING)
~
.. l
~
; j
> Meter Required 1
Continuous By Tech Q Time Keeper Required , l Intermittant By Tech Stay Time ! i-
@ C A R.M. To Be Set Up i l @
I Q Intervals or as Follcus: . Set Point j Cortse9W/ wsTN kwn/4/Cff/
/NJ~/tfVta*//M, I
SPECIAL 1551'RUCT105S $MM/fluotJJ prurs ras is//. S ei t / , 6 r :fs p . I Il g
.VI RADIhiCN EIPCSURE CCDTROL) ,
Het Sp_og Identified & Tagged Or Roped O.. , ( System or Equipeent To 3e Filled With Water System or Equi;=ent To Be Drained j Remete Eandlimg Tools Required & List _ i) C Shielded Dr.:=s Cr Casks Requirect For Re= oval Cf Ect Parts Cr Waste !/.//4 h U m e fO
-- ? _
9 -- Wm -
j . . . _ . ... -- -
. -- ?. . . . . . . 1. .a~. . . . . .
g.., ,
' _ , 1915.12 Rsv. 6
... Figure RC 915.12-4 8/31/82 Page 3 of 4 Shielding Required O -Per=====t O Te=rerarr I R.E.D. Engi:eering Request Fcr= Filled Out & Attached
- i. Yerification That Shielding'Is I:staned & Levels Acceptable .or Work In Are's S?ECIAL INSTRUCTIONS M7 A 6.%r>n# p.7J.
l
" VII CONTAMDIATION C'CT'ROL) t - ' '
I" Establish Hi-Contamination Area t L
& Floor Covering Required Drip Pan Required & Size T & T pe kWW SW /k'2*W e L
i
, Drsa Cr Bottle Required For Liqr.id Collection & Size ,
, Sleering Required & Size Glove Eag or 3cx Required 3 Certain=ent Structure Required M Bu/L7 -
[ Special Containment Required & h.E.D. hg reering Request Fors Filled Out I And Attached C Vacuu: Assisted IVR Tools Required
- Cc= tai-asts Checked Oct & Verified 37 '
Date a __
., L S??CIAL I535UCTIO55 f./Nf hb> d' w/11/ UBMts? rTffoA. -
y , d!r~f1r.siv) p 1 A.ls AAfD o*lfh%1 Arin3 6 MfA TVR . * !/l AOLL of. /N vfew /7.sc2pr Fod Inspo.rgt a VIII h.anLT.ATICK UNITS ) . 500 ct=/Eepa F'11ter
- p' 1000 efc/Hepa Filter (reinos sum)
Vacuum Cleaner / Absolute Filter . Tent 111ation Units, Filters & Set Up of Units checked Oct & verified .Br Date SPECIAL IESIRUCTICRS 901 t Sue Yiad % .fus/mt' *sorf< , . bl.nx s feut 6 ot/ nom
/MK e#5 St/ AHTE,Y % h/PCA 7 wc2 n)s JA. . .
l -
, II AIR SAMPLING)
_l ( . ~ 1: - Eefore Vork
- l D=$cg Vcrk
~ Arter Vark w .. At Fo11 cuing Specific Tir.es *C02/W hnm Mb'.s el MS7dise MM w
/
g C <'7 M .";i;ir i [ _ y" f
P 915.12 Rev. 6 c.',* ~,-' .
. 71 .RC' 915.12-4' *
'8/31-/82 -
Fage 4 cf 4 I
~
; Locatien & Type of Sa:pler Requi. red ,
[ Lov Volu=e [ Work Ares l , High Volume ,,,, Breathing Zen Laper Outside Work Ares { CAM $ CLher 8 cat /V.Y room fwf/fsKes Jt)3f,w 11eM, {
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. Attention: 3-NY .
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RADIOLOGICAL EI;GII!EERII;G DEPT.
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