ML20212A668
| ML20212A668 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/29/1997 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20212A666 | List: |
| References | |
| PROC-970929, NUDOCS 9710240130 | |
| Download: ML20212A668 (80) | |
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i l i ( ' 1 UNRESTRICTED RELEASE CONFIRMATORY SURVEY i PROGRAM i i HADDAM NECK PLANT i j CONNECTICUT YANKEE ATOMIC ' l POWER COMPANY l l l FINAL REPORT l l September 29,1997 ( l l i 1 / i i 9710240130 971017 DR ADOCK 0500 3 l
- b SUT,VEY PROGR AD FINAL REPORT b PAGE 2 "
LIST OF TABLES TABLE 1:
SUMMARY
FROM OUTSIDE THE PROTECTED AREA..15 TABLE 2:
SUMMARY
FROM WITHIN THE PROTECTED AREA..... 21 TABLE 3: TOTAL DATA
SUMMARY
................................................. 21 LIST OF ATTACHMENTS ATTACHMENT 1: Action Plan Unrestricted Release Confirmatory Measurments Program ATTACHMENT 2: Vendor Survey for Confirmatory Monitoring Program ATTACHMENT 3: Summary of Outside Area Activity ATTACHMENT 4: Summary of Ins:Je Area Activity ATTACHMENT 5: Project Pictures ATTACHMENT 6: Site Map
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TABLE OF CONTENTS
SUMMARY
.................................................................................................................3 PROG RA M D ES C RI PTl O N S U M M A RY ............. ..................................................... 3 1 E VE NT D ES CR I P TI 0 N .................................................................................................. 6 l I N I TI A L A S S ES S M E NT ......................................... ...................................................... 8 P L AN D E VE L O PM E NT .................................................. ............................................. 8 TRAI NING A N D Q UA L1 FI CATI ON .. ....... .................. ........................................... 8 O FF SITE VENDO R INTERVI EW RESULTS........................................ .................. 9 o EMPLOYEE COMMUNICATION AND 11OT LINE SETUP ................................... 9 PLAN IMPLEMENTATION OUTSIDE TIIE PROTECTED AREA......................10 PLAN IMPLEMENTATION INSIDE Tile PROTECTED AREA..........................10 PERSONNEL TlM E COMMITM ENT TO PROJECT .............................................11 C i l A L L E N G E S . . . .. ..... ... ..... ..... ..... . . ...... ... .... ... ... . ...... .. ........ ... .. ... ......... .................. ..... . 1 1 E Q U I P M E NT N E E D S ............................................... .................................................... 12 RESULTS OF SURVEYS OUTSIDE Tile PROTECTED AREA ...........................13 RESULTS OF SURVEYS INSIDE TIIE PROTECTED AREA ...............................16 TO TA L D ATA S U M M A R Y .......................................................................................... 21 AN A LYS I S O F 1 D E NTI FI E D ACTIVITY .................................................................. 2 2 1 NI TI A L EVA L U ATI ON CO M PA RI SO N .... ............................................................ 2 2 CONCLUSION..................-...........................................................................................24
S i SURVEY PROGRAM FINAL REPORT PAGE 3
SUMMARY
Data from this project indicates that there is a low protability for significant contaminated material to have been inappropriately released from the Haddam Neck Plant (HNP). For the most part, the items found to be contaminated would have been i extremely difficult to identify without the use of the Small Article Monitor (SAM) and low background radiation areas in which this project was conducted. The majority of these items were found due to the lower background and enhanced monitoring equipment. The contamination levels found on tools and equipment would not present any health and safety impacts to the workers or members of the general public. However, improvements in equipment and process initiated for release of matarial from the Radiologically Controlled Area (RCA) coupled with the extensive survey of material previously released, should prevent radioactive material from inappropriately being released from the Haddam Neck Plant in the future. PROGRAM DESCRIPTION
SUMMARY
As a result of radiologically contaminated equipment being inappropriately released to a non licensed vendor, an independent review of past unrestricted release practices at Haddam Neck Station has been completed. This review included extensive confirmatory measurements of material, on the Haddam Neck site, which may have been previously released from the radiologically controlled area, In addition, interviews were conducted with vendors which may have had material released from the Haddam Neck site in order to ascertain if identification and survey of this material was feasible. The confirmatory survey was performed in two phases, outside of the Protected Area and the area referred to as "inside the protected area" for purposes of the report. This second area consists of the space between the RCA and the Protected Area fence. Attachment 6 contains a site map for generallayout of site structures discussed within this report.
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*NINA["rYr"c*nS PAGE 4 Outside of the protected area there were a total of 11764 items surveyed.
Of these items surveyed,49 had indications of probable contamination,23 of the 49 had levels greater than or equal to 100 cepm (corrected counts ' per minute, equal to count rate minus background) using standard frisking techniques, and an estimated total detectable activity of about .05 microcuries. The contamination identified was nearly always localized to very small spots. No item outside the protected area had detectable removable contamination identified. 1 Twenty of the twenty three items w;th greater than or equal to 100 cepm were refurbished Containment Air Recirculation (CAR) fan filters which had previously been installed in the plant, removed from service and sent off site for charcoal replacement. All CAR fan filters were verified to currently be in the possession of the licensee. The remaining three items ' ' were a pair of side cutters, a welding lead, and a portable weld rod oven. Attachment 3 of the report provides a list of items with detectable levels of contamination by direct frisk. All 49 items with indications of contamination were returned to the RCA for final disposition with the decommissioning. There were approximately 175,000 items surveyed inside the protected area. Of these items surveyed,386 had indications of probable contamination,105 had levels greater than or equal to 100 cepm using standard frisking techniques, and an estimated activity of .21 microcuries detected. Of the items inside the protected area, three small piping pieces had detectable removable contamination identified on inside surfaces. All of the contaminated items were either retumed to the RCA for final disposition with decommissioning or disposed of as radioactive waste. The use of the small article monitors (SAM) greatly facilitated the identification of the contaminated items, in most cases the SAM alarms prompted very extensive surveys of the items in order to identify the fixed contamination location. Without the aid of the SAM, probably fewer than 100 contaminated items would have been identified. As a result of interviews with vendor personnel, it was determined that in most cases the ability does not exist to identify material which had been previously released from the Haddam Neck RCA. Further, as a result of confirmatory surveys performed at Haddam Neck. the disruption of vendor activities during an attempt to survey all materials at off site facilities was determined to not be justified or necessary.
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in order to put health risks in perspective, the intomal dose which could be received by one individual orally ingesting all of the identified activity (with - compensation for hard to measure isotopes potentially in the mix) was estimated at less than 25 mrom CEDE. This number is considerably less than the threshold for intomal monitoring for radiation workers and is also less than the annual limit for members of the public. Additionally, the extemal dose from this amount of material is very low. The highest measured contact count rate was 4500 cepm (approximately equal to 2 mrad /hr) on the cutting edge of a pipe cutter in the weld shop. l As a result of the survey work performed and improved controls for i release of material from the RCA, surveys of items leaving the Protected Area are considered no longer necessary. The surveys will continue until ! concurrence to stop this interim measure is received from the NRC. However, there are two identified areas on site _ outside of the RCA where release controls will cont lnue to be implemented. The first is for items stored on the peninsula area south of the plant. Some of the equipment - stored here has potential for contamination from prior use in the RCA. This equipment will be survey 0d as a part of decommissioning this area. The second area is sea vans stoisd within the protected area containing tube lock scaffolding poles. As a resdt of contamination identified by hand frisking techniques of a small sampl;ng of scaffolding poles, it has been decided to control this material until such time as improved survey methods and equipment are available for survey and release.
SURVEY PZCOAC
- FINAL REPORT PAGE 6 EVENT DESCRIPTION On February 26,1997, technicians at C&G Video facility detected radioactive contamination on video equipment which had been unconditionally released at Haddam Neck Plant (HNP). A representative of C&G Video informed Connecticut Yankee Atomic Power Company (CYAPCO) personnel of the discovery via a telephone call the same day.
On February 27,1997 representatives from CYAPCO traveled to C&G Video and segregated the contaminated items returned to C&G Video from those items with no measurable radioactive contamination. The contaminated items were packaged and returned to the Haddam Neck Plant as an " exempt quantity" shipment. The items found not to be contaminated were also transported back to the Haddam Neck Plant. The returned items were transported back to the HNP on February 28th. On March 4,1997, the Nuclear Regulatory Commission (NRC) issued a
" Confirmatory Action Letter" to CYAPCO. An initial response to the confirmatory action letter was submitted on March 7,1997. As a result of discussions with the NRC staff concerning the March 7th response, a supplemental response to the confirmatory action letter was submitted on March 20,1997.
l ' The supplemental response committed to development of an action plan to determine the extent to which radioactive material may have been inappropriately released from the radiologically controlled area (RCA). The action plan is to contain the following elements:
- 1. Identify survey locations
- 2. Identify items to be surveyed
- 3. Establish procedures to govern performance of the surveys
- 4. Determine resources required to complete the action plan S. Communicate the action plan issues and status to site management
- 6. Plan implementation i
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Su2VEY PR3cRAC r FINAL REPORT PAGE 7
- 7. Identify programmatic deficiencies l
- 8. Establish milestones and estimated completion dates
- 9. Analysis of data and conclusions.
Further, to ensure the action plan surveys are performed appropriately, the following actions are to be taken.
- 1. The Survey Plan Manager will communicate the standards and expectations regarding the performance of surveys to the health physics technicians. (To be included as part of training and qualification)
- 2. Health physics technicians performing the surveys will review and sign their acknowledgment of all procedures goveming the release of material from the RCA. (To be included as part of training and qualifica,' ion)
- 3. CYAPCO will ensure that the surveys are properly conducted through periodic assessments and management oversight. (To be included as part of Quality Assurance)
- 4. CYAPCO supervision will review all survey documentation for accuracy and completeness. (To be included as part of Quality Assurance) r f
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SunVEY PRecRAD f FINAL REPORT PAGE 8 INITIAL ASSESSMENT in order to determine appropriate confirmatory measurement schedule and scope, an initial evaluation for potential amounts of contaminated i equipment and probable maximum contamination levels expected was assessed. Based on s review of past pla'1t practices and procedures the survey plan was designed using the following assumptions: 1) the incidence of contaminated equipment being identified outside the Radiologically Controlled Area (RCA) will be low,2) the incidence level outside of the Protected Area will be lower than inside of the Protected Area, and 3) contamination levela encountered are expected to present no significant ' risk to workers or the general public. The Information reviewed which led to the above assumptions is documented in Attachment 1,
- Action Plan Unrestricted Release Confirmatory Measurements Program'.
PLAN DEVELOPMENT Approximately one month was utilized to develop the action plan for execution of the confirmatory measurements, identify personnel resources to conduct the surveys, ensure adequate instrumentation capabilities to complete the project, and train and qualify health physics technicians to perform these surveys. During this development phase, walkdowns of the site areas were conducted in an effort to estimate resource requireme7ts and time schedules for completion of the project. The priorities for completion of the confirmatory surveys were established with the greatest weight being placed on the survey of material which was already released from the Protected Area (due to lesser controls over potential release to the general public). Initiation of surveys inside the Protected Area were relegated to the time after completion of the outside Protected Area. TRAINING AND QUALIFICATION The technicians assigned to this project were qualified senior technicians in accordance with ANSI 18.1 1971. Specific training for this project was through a combination of classroom instruction and on-the-job qualification. The classroom portion of tha training included such items as; the event background / description; expectations for questioning attitude, i documentation, communication, procedural adherence, and teamwork (common goals); work observation of work by supervision and peers; and specific knowledge information about regulatory requirements, information conceming specific instrumentation to be used, and procedural instruction.
SURVEY PROTAO 1 FINAL REPORT PAGE 10 PLAN IMPLEMENTATION OUTSIDE THE PROTECTED AREA Completion of surveys for areas outside of the protected area were accomplished very nearly on the original schedule. Identification of contaminated CAR fan filter assemblies during the final week of the three week survey period resulted in an approximately one week extension to the scheduled time in these outside areas. Although initial estimates of time requirements were based upon a larger sampling of equipment in the warehouse, through comprehensive walkdown of the warehouse in concert with warehouse personnel, those itoms with virtually no probability for having entered the protected area were excluded from survey. As originally envisioned, essentially 100% of items stored in the recycle building were surveyed, while other peripheral areas utilized detailed walkduwns to identify items with highest potential. PLAN IMPLEMENTATION INSIDE THE PROTECTED AREA The initial estimate to survey areas inside the protected area was approximately 6 weeks. This estimate was exceeded by approximately 10 weeks due to a combination of factors. Primarily the added time was due to increased scope. The amount of materialin the shops was underestimated, sampling surveys in sea van containers and office spaces resulted in full scale (100%) surveys being required, and additional storage areas in the turbine building were identified. l Also affecting the time required to complete the inside areas was the material transfer aspects of the work, in most cases the location of the small article monitors made it necessary to transport large quantities of material to centralized counting equipment locations. l When the inside area was approximately 50% complete, operational concems resulted in the transfer of several technicians from the survey program to support plant needs. These technicians were subsequently replaced with additional contracted personnel, but not before approximately one person month of production on the survey program was lost. At the start of the project through interviews with various work groups on site, paperwork was identified which may have been in the RCA and not been surveyed through a small article monitor when personnel exited. These specific paperwork items identified in the plan for survey were completed with the exception of some operations working logs. In the course of the project, it was identified that these working papers had been discarded through the clean trash during an office move in February 1997.
SURVEY PRocRAC FINAL REPORT PAGE 9 OFF SITE VENDOR INTERVIEW RESULTS Contractors utilized during refueling outages 18 and 19 were interviewed . to determine the feasibility and need for performing surveys of material previously released to offsite vendors. For the most part either equipment l was transferred to a licensed facility or as in the case of turbine work, extensive decontamination was performed in the work area to preclude contamination of vendor equipment. In severalinstances material was free released but there was a lack of traceability for the equipment once released from Haddam Neck. In most cases this material was used later at other nuclear facilities. For detal!s of the results from the off site vendor interviews, see Attachment 2. EMPLOYEE COMMUNICATION AND HOT LINE SETUP in addition to the vendor interviews, health physics personnel were queried if any material had been brought back to site by any employees due to concerns for potential contamination. With the exception of contaminated material from a 55 gallon drum identified in 1980, no instances of personnel bringing items back to site were identified through these discussions with the health physics personnel. A special"HP Hotline" was established for any site personnel to report contaminated equipment / material concerns. This information was conveyed to site personnel through a "CY Today" site-wide distribution news article. To date, no responses have been received concerning contamination concerns on the hotline. It should be noted these efforts have been with site personnel. The effort to contact local residents concerning bulk mater % removed from the site during past construction activities is outside the scope of this report. y ._
t ' NA EPbR PAGE 11 PERSONNEL TIME COMMITMENT TO PROJECT The time expended by professional personnelin support of this project was approximately one half of a person year. Health phys!cs technician personnel time for performance of the actual surveys and documentation of survey results was about 2.5 person years. CHALLENGES Although the use of the small article, gamma sensitive, monitors greatly aided in the identification of potentially contaminated material, the false positive alarm rate was significant. See Attachment 5, picture AS 5 for the a small article monitor in use. Considerable time was required to evaluate alarms due to natural activity in solvents, grinding wheels, sand paper, and other items containing minimal amounts of potassium or thorium. Time was required to review compositions, get comparable new items, and cross compare count rates for new items to potentially contaminated items to evaluate the nature of the SAM alarms. The SAM was also being used for screening of any items which would physically fit inside the monitor. As a result of the significantly greater than 100 cm' surface area on the larger items, a fairly high number of alarms were received where no activity could be identified through later frisking techniques. Unless the alarm could be attributed to natural activity, these items were considered contaminated and returned to the FICA for disposal as radioactive waste or later disposition during decommissioning. Movement and setup of the SAMs created other challenges. Locations had to be found where there was sufficient space, background radiation constraints were met, and the location was convenient for the material to be processed. The movement of a SAM with the associated shielding often required the use of forklift trucks and in some cases overhead cranes. Many of the areas where material needed to be surveyed were under strict control for QC requirements or M&TE calibration considerations. As a result considerable site personnel support was often required in order to gain access to the material for survey.
SURVEY PROCRAD t FINAL REPCRT
, PAGE 12 The sequence for performance of surveys within the Protected Area had to be altered significently, due to the constraints for the movement of the small article monitors and the support needed to perform surveys in given i areas. The first areas done were the Fabrication Shop, clean side of the Butler Building, Generation Construction Facility (added from original scope), and scaffolding sea van containers where there was little support needed from the other site groups. This order was opposite of that originally planned, but based on experience gained in the surveys outside
, of the Protected Area, were appropriate for the overall goals of the project. EQUIPMENT NEEDS When the project began, two of three SAMc on site (one of which had 1 been borrowed from Millstone) were allocated to the survey project. This I left only one monitor to support the routine release of tools and equipment ) from the RCA, More monitors were ordered and about midway through the project, three additional monitors were received and calibrated for use. At this time the borrowed monitor from Millstone was returned and two i monitors could still be dedicated to completion of the survey project, J 4
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l INA R POR PAGE 13 RESULTS OF SURVEYS OUTSIDE THE PROTECTED AREA See Attachment 3 for a complete listing of the items with contamination levels which were detectable through direct frisking techniques. I Warehouse The main warehouse is located adjacent to the northeast corner of the Protected Area (Warehouse #1 & #2 on site map). A comprehensive l walkdown of materials stored in this area was completed with the ) assistance of the warehouse personne! The warehouse personnel were able to point out the material which at one time or another had been l transported into the plant and later returned to storage. Surveys were performed on 100% of the items identified by the warehouse personnel, p!us any u!her materials which appeared to have been used previously. See Attachment 5, picture AS 1 for a view inside of the warehouse. The total number of items surveyed within the warehouse was 87/16 with Indicated contamination on 32 items. Of the 32 items,23 items had
- detectable contamination by direct frisk. There were 21 items with l contamination levels greater than or equal to 100 cepm. One portable weld rod oven was identified with greater than 100 ccpm. The remaining 20 items with levels greater than or equal to 100 cepm were refurbished f CAR fan filters which had been recently returned from the vendor. The contamination identified *uas localized to very small spots, although several spots were identified on most of these filters. The maximum level identified was 800 cepm Verification was performed, through a review of chipping records, that all filters had been returned from the vendor. Based on no removable contamination being present on the filters and the low fixed contamination levels associated with the CAR fan filters, no surveys of the vendor facility were initiated. All of the 32 items with Indicated potential contamination were returned to the RCA. See Attachment 5 AS 2
& A5-3 for pictures of work progressing inside the warehouse, in addition, during tha comprehensive walkdown of the warehouse facility, three radiation detectors with installed Sr 90 sources were identified in storage in the warehouse. These detectors were transferred to radioactive source storage locations within the RCA,
suRyaY PRc00Ad f FIN AL. CE PORT l ( PAQs 14 ' Recycle Building { The recycle building (warehouse toward southeast she of parking lot on ! site map) primarily contains equipment used for general upkeep of i facilities Stored within the building are such things as paint, a snow plow, ' road sweeper, sand spreader, and miscellaneous janitorial / maintenance ; tools. See Attachment 5, picture A54 for an extemal view of the recycle ; building. A total of 1667 individualitems were surveyed within the recycle ! building, which represented nearly 100% of the small tool and requipment ! inventory, Larger items and general surface areas of the structure were also surveyed due to a satellite RCA cage being located within this structure. Although 12 separate items had indications of potential l contamination as indicated by SAM alarm, only one of the items was ! greater than 100 copm by direct frisk. The items retumed to the RCA ' included tin snips, hammer, drill, hard hat liner, safety belt, etc. The item ; greater than 100 copm was a pair of side cutters with a direct frisk rate on the cutting edge of 200 ccpm. There were also alarms received from , nearly all of the paint cans surveyed through the SAM Through _
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comparison to new paint can SAM count rates, the activity was evaluated , to be frem naturally occurring radioactivity, probably within the paint dyes. Mlacallaneous Outalda Areas included in this area are a steam generator mockup building, several sea van containers, chemical storage area, and a patellite warehouse storage area. A total of 1381 items were surveyed from these locations with ! indicated contamination on 5 items. One of the 5 items, a welding lead I found in a sea van container did measure 100 ccpm by direct frisk. The other items were two pieces off of a hydrolaser, an extension cord, and a _ gas hose, all of which alarmed the SAM, but had no detectable activity by . direct frisk. All of the items with indications were transferred to the RCA. ; 4 t
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SURVEY P7.002AU
# FINAL REPOPT PAGE 16 Below is a summary of information for surveys performed outside of the protected area:
TABLE 1
SUMMARY
FROM OUTSIDE THE PROTECTED AREA. 4 TOTAL ITEMS INDICATION t100 1100 ACTIVITY AREA SURVEYED INDICATIONS RATE cepm RATE (microcuries) Recycle 1667 12 0.72 % 1 0.06 % 1.26E-03 Building Warehouse 8716 32 0.37 % 21 0.24 % 5.16E-02 Misc. 1381 5 0.36 % 1 0.07% 4.50E 04 Outside l TOTA 1. 11764 49 0.42% 23 0.20 % 5.33E-02 f
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- f. SU3VEY PRDcRAC
, FINAL REPORT i PAGE 16 i
i RESULTS OF SURVEYS INSIDE THE PROTECTED AREA Note: The order of discussion la approximately the order each area was I
- corr.pleted within the survey project. !
See Attschment 4 for a complete listing of the items with contamination ! leyc36 which wore detectable through direct frisking techniques. l t :
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i Estricrtbn sbaa 1 F The Fabrication Shop was used primarily for the fabrication of sheet metal and insulation for site use. it consists of a shop area within a
- Butler" type .
I metal structure with a break area on e second floor above the shop area. ;
- There were 777 items surveyed in the shop and break area of the 2
F.'brication Shop. Eleven items were identified for potential contamination cod 10 of the 11 items did have detectable contamination by direct frisk. j Only 4 of the 10 items had levels greater than or equal to 100 ccpm with l the maximum count rate being 1500 ccpm found on both a cloth chair and i a pair of channel locks. The other items identified were small tools and
; " scrub" clothing. All items were retumed to the RCA for final disposition.
Betlar Building . C6n Elda (Insulation Shop on site map) 1 ; l The
- Butler" Building, as the name implies is a metal shell structure
{ primarily utilized to store contaminated equipment within the RCA. The - 1 i structure is located on the southeastern comer of the protected area. On ! the southern end of the structure is a small area separated from the RCA
- by a fence. This southem and was used to store insulation, various large pieces of equipment for sheet metal work, and miscellaneous small tools and equipment.
3 A total of 48g item were surveyed on the clean side of the Butler Building. Three of the items had detectable contamination by direct frisk. The maximum cuntamination level observed was 60 ccpm. All of the contaminated items wera returned to the RCA, l
s INA E OR PAGE 17 Generation Construction Facility The Generation Construction Facility (ISI & Contractor Services on site trap) is a modular two story office structure located adjacent to the western side of the Butler Building. This office area had been occupied by the generation construction torce during plant operation. The stnicture is being considered for use as office space in support of decontamination and decommissioning activities. To prepare for this potential use, large quantitles of paperwork, office equipment, and miscellaneous materials stored in desks and file cabinets were to be discarded. See Attachment 5, picture A6-6 for an external view of the facility. l The materials to be discarded, along with chairs, file cabinets, etc., to be maintained within the building were surveyed. A total of 6330 items were surveyed with 21 items having indicated contamination. All 21 items were 1 detectable through direct frisk and 11 of the 21 were greater than or equal to 100 cepm. The maximum contamination level detected was 600 cepm on a cloth chair. Allitems were either disposed of as contaminated waste or relocated to the RCA for ultimate disposition. Maintenance Shoo The maintenance shop is located in ',he service building, a metal structure attached to the southeastern side of the tur! :ne building. Within the shop are storage areas for both consumable small items and reusable small tools and equipment. Although some limited survey of the materialin the maintenance shop had been performed in February of 1996 as a test for newly acquired SAMs, the entire inventory of tools and equipment had not been previously surveyed. Over 68,000 items were surveyed in the maintenance shop area, Indications of contamination were found on 76 items. Of these 76 items, 58 had detectable contamination by direct frisk (23 with levels greater than or equal to 100 cepm). The maximum count rate by direct frisk was 2000 ccpm on a reaming tool head. All 76 items were returned to the RCA for final disposition with decommissioning.
SURVEY PRSCRAd l
- FINAL REPORT PAGE 18 l
Records from Vault i i A survey of records stilllocated at Haddam Neck was performed as a result of previously identified contaminated paperwork. A total of 34 file l'
. boxes of records were transported to the maintenance shop where a small '
- artick, monitor was used to survey 100% of the records in approximately j 1" increments. No contaminated paperwork was identified in the 34 boxes ;
of paperwork.1 l Wald Shop The weld shop consists of a curtained area in the southwestem comer of : the maintenance shop plus a break / storage area (Maint. Office on site , map) immediately south of the maintenance shop. A total of approximately 8500 items were surveyed in the weld shop area. Of the ; items surveyed,62 had indications of contamination and 27 had : detectable contamination by direct frisk. Nine of the items had
- contamination levels greater than or equal to 100 ccpm by direct frisk, with the maximum being 4500 on a pipe cutter part. The next most !
contaminated item was a chair with 300 copm by direct frisk. The items ; with potential contamination were either disposed of as radioactive waste or retumed to the RCA.- Electrical Shop The electrical shop is located in the middle floor of a three floor *B" , switchgear building. The building is located towed the north side of the protected area, approximately in the middle between the east and west fences. A sea van used for electrical maintenance material storage
' located immediately to the west of the "B" switchgear building, adjacent to -
the diesel generator building, was also surveyed in conjunction with the electrical shop. A total of approximately 15,250 items were surveyed with 15 items - i indicating contamination. Of the 15 identified items 10 had detectable l contamination by direct frisk, with 3 of the items having levels greater than i or equal to 100 ccpm. The maximum level observed by direct frisk was 400 ccpm on a wrench All 15 items were retumed to the RCA. h
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PAO: 19 Turbina niilldina us. n-n.nii. Stornam Ar=== ' Throughout the turbine building are various cages constructed for storage of tools and equipment. These storage areas contain items such as operations toob and equipment (e.g., LLRT equipment), slings and chain hoists, turbine tools and equipment, and ultrasonic test equipment. 1 Surveys were conducted on a total of more than 23,000 individual tools and pleoes of equipment stored in these cages. Of this total,65 items had l ! Indication of contamination and 34 of the 65 had detectable contamination by direct frisk. Detectable contamination levels greater than or equal to 100 ccpm were found on 15 of the items. Three items with removable contamination were found in the operations i tool cage. The removable contamination levels were 1) on the inside of a small pipe reducer bushing - 2600 dpm beta and 180 dpm alpha, 2) inside 1 a 1/2"_ pipe elbow -_200 dpm beta and 30 dpm alpha, and 3) Inside a -1/4" pipe to ferruled adapter - 50 dpm bots with no alpha. During the course of the project, no other removable contamination was identified on the items surveyed. The maximum contamination levels observed by direct frisk were 1000 ccpm found on the reducer bushing mentioned above, a pipe nipple, and a sling, Allitems with indications alcontamination were retumed to the RCA for final disposition with decommissioning. Control Room A drawer of assorted pliers, wrenches, tape measures, hammers, etc. is located in the control room for use by operations personnel. A total of 75 Items were surveyed from this area. Two pairs of dikes were identified with contamination, 300 and 60 cepm by direct frisk. The items were relocated to proper storage within the RCA. San Van Containers There are 26 sea van containers used for storage of material and equipment located within the protected area. Two were located adjacent to the east side of the Butler Building, eight on the southeastern corner of the turbine building, two to the south end of the turbine building, and the remainder on the area known as the "balifield" between the Generation Construction Building and the diesel fuel storage tank.
l suRveyPRe RAu
, PINAL REPGRT PAes 20 A total of nearly 24,000 items were surveyed from within these containers. i Of the items sueyed, 94 had positive indication by olther SAM or for i larger items, by direct frisk. Contamination was detectable by direct frisk on 58 of the these 94 items. Grcator than or equal to 100 copm was detectable on 30 iterns. The maximum level observed by direct frisk was l
1500 copm on a pressure gauge found in the " valve trailer", one of the two , storage locations at the immediate south end of the turbine building. All i items with positive indication were retumed to the RCA. One sea van container which contains scaffokling poles was begun as a !
- spot check" for contamination by direct frisk. However, contamination was identified on one of the poles being checked. As a result, the decision was made to defer surveys of the remaining scaffolding poles until better survey instrumentation is avaliable. This material is being administrativ61y controlled to prevent inadvertent release from site or use in a clean area .
prior to radiological survey and release. i Instrument and Control Shan " i The instrument and control shop is located in the ground floor of a : modular building attached to the north end of the turbine building, in _ ! addition to the shop itself, several equipment storage areas associated i with the l&C shop were also surveyed. A total of more than 2g,000 items were surveyed in the I AC area, of which 55 items indicated contamination. ! Of the 55 items,16 had contamination levels which were detectable with standard frisking techniques (g of the 16 were equal to or greater than 100 cepm). The maximum contamination level identified in this area was 1500 ccpm on a parker fitting. No items in the l&C Shop area were found 3 to have removable contamination. i p- --me= , ,i s s-e- a-sw-- - -wr, - 7 g<-w-w,ey.,vrw'--w'y - w ev v y ewweo--*=-+-ie=-v'- '1-*+N '- we-- -r-ee - o wyr e-=mv->-w -we> r -ww +
t
- SURVEY PRoORAD
, FINAL REPORT PAGE 21 Below is a summary of information for the surveys performed within the protected area.
TABLE 2
SUMMARY
FROM WITHIN THE PROTECTED AREA. TOTAL ITEMS INDICATION t100 1100 ACTIVITY AREA SURVEYED INDICATIONS RATE cepm RATE (microcuries) Sea Van 23822 94 0.39% 30 0.13 % 4.86E-02 Containers Fabrication Shop 777 11 1.42% 4 0.51 % 1.72E 02 Maintenance Shop 68051 58 0.09% 23 0.03 % 4.85E 02 Electrical Shop 15270 15 0.10% 3 0.02 % 4.95E-03 3 Butler Bldg Clean 469 3 0.64 % 0 0.00 % 7.21E 04 Side Control Room 75 2 2.67 % 1 1.33 % 1.62E 03 Turbine Bldg Areas 23126 65 0.28 % 15 0.06 % 3.32E-02 Gen Constr Bldg 6330 21 0.33 % 11 0.17 % 1.49E-02 Weld Shop 8548 62 0.73 % 9 0.11 % 2.94 E-02 l&C Shop 29137 55 0.19% 9 0.03 % 1.53E 02 Records Vault 34 0 0.00 % 0 0.00 % 0 TOTAL 175639 386 0.22 % 105 0.06 % 2.14E-01 4 TOTAL DATA
SUMMARY
The following table depicts the summation of the information from the survey for both outside end inside the protected area. l TABLE 3 TOTAL DATA
SUMMARY
TOTAL ITEMS INDICATION r. )0 1100 ACTIVITY AREA SURVEYED INDICATIONS RATE cepm RATE (microcuries) Outside 11764 49 0.42% 23 0.20% 5.33E-02 Inside 175639 386 0.22 % 105 0.06 % 2.14 E-01 TOTAL 181817 435 0.24 % 128 0.07 % 2.67E-01 1 r, .- .- , --- ---.n-- --
, 7 -. - , , - -
INA RE OR PAGE 22 ANALYSIS OF IDENTIFIED ACTIVITY The beta activity for the contaminated items was estimated assuming a nominal efficiency for the frisker of 10%. For the predominant remaining beta emitters of Cs 137 and Co-60 and noting that the contamination identified was nearly always localized to very small spots, the result should be a conservative estimate of the total beta emitting activity present. This amount of activity spread over more than 400 items is considered a negligible extemal dose consideration. In order to consider the internal dose consideration for this activity some very conservative assumptions can be applied. First, aesume all of the activity is ingested by one individual. The estimated dose due to oral ingestion assuming all the activity is the most limiting Cs-137 results in a dose of 10.8 mrem CEDE. Applying a typical beta to alpha ratio of 100:1 would result in approximately .0025 microcuries of alpha emitters also being present. The estimated dose due to oralingestion for this amount of alpha activity assuming all the activity is the most limiting Am-241 results in a dose of 13 mrem CEDE. Therefore, the worst case internal dose consequences from this amount of activity, based on simple ratios to the stochastic annual limits for ingestion (All), would be approximately 25 I mrem CEDE. INITIAL EVALUATION COMPARISON The data from this survey project supports the initial evaluation assumptions developed at the start of the project. Those assumptions and project data are as follows (see Attachment i under Initial Evaluation for details of assumptions):
- 1. Millstone Data (similar survey project completed in 1989)
The resuits from the survey project at Haddam Neck Plant yielded data very similar to that from Millstone. When the 2100 ccpm data is compared (this was the only data available from Millstone because there were no SAMs), the rates were 0.07% overall incident rate for Haddam Neck compared to 0.132% at Millstone. This lower rate was exhibited at Haddam Neck despite of the use of the small article monitors to help pinpoint potentially contaminated material.
*"fw*A["nsS"o'ni PAGE 23
- 2. Low Transport Outs!de of the Protected Area With the exception of the CAR fan filters identified in the warehouse, only 3 items were identified outside of the protected area wNh greater than 100 ocpm by direct frisk. When the CAR fan filter contaminated items are backed out of the data for outside of the protected area, the resultant incident rates are similar to those inside the protected area. This is despite the fact that the sampling outside the protected area was a biased
- l. survey of those items expected to be potentially contaminated.
t
- 3. No Significant Loss of Contamination control I
' For the most part, the items found to be contaminated would have been extremely difficult to identify without the use of the SAM and low -- background radiation areas in which this project was conducted. The R majority of these items were found due to the lower background and ,
- enhanced monitoring equipment, which is now in use for release of equipment from the RCA.
- 4. Maintenance and l&C Shop Data i
As a test of new SAMs obtained in February of 1996, some limited surveys were performed in these areas. Although the exact number of tools surveyed by use of the SAMs in February 1996 is not known, comparison of the time spent on this project versus 1996 leads to the conclusion that a very small fraction of the inventory was done previously. For that reason and the fact the incident rate for both shops is considerably less than comparable areas in the Millstone data, the initial assumptions appear to be supported.
- 5. Amount of Equipment Unconditionally Released Was Low The interviews with vendo.: 'or the past two refueling outages supported that the quantity of tools and quipment which entered the RCA and was subsequently unconditionally olessed was low (see Attachment 2 for details ofinterviews).
- 6. Past incident Rate Not Significantly Above Average for Plants of this Vintage This is a judgment based upon Adverse Condition Report data prior to the start of this project. The incident rate found by this project, despite the use of enhanced technology, seems to support the assumption.
. "" "[AE"na$"o'nS ie PAGE 24 CONCLUSION Overall, the data from this project indicates that there is a low probability for contaminated material to have been inappropriately released from Haddam Neck Plant. There is an even lower probability that any *significant" amounts of contamination were released from HNP, Approximately 75% of the items found to be contaminated would not have been found in a typical background radiation field at RCA release points ;
l without the use of the gamma sensitive small article monitors. ' The C & G Video equipment which was inappropriately released from the site may have been an isolated occurrence, in the instance of release of the C a G Video equipment, a single technician may have released the material from the contaminated area. Later, the same technician may have released the material from the RCA, and based upon the technician's prior knowledge of the equipment, may not have properly resurveyed in the lower background area prior to unconditional release. However, during outage close-out, there is a more structured process for release by different personnel at the _two points of survey. Thus, there would be a lower probability of reliance on previous survey work for final RCA release. The contamination levels found on tools and equipment would not present any health and safety impacts to the workers or members of the general public. However, improvements in equipment and process initiated for release of material from the RCA, coupled with the extensive survey of material prei busly released, should prevent radioactive material from inappropriately being released from the Haddam Neck Plant in the future.
4 1 Docket No. 50-213 CY-97 094 ATTACHMENT 1 Action Plan Unrestricted Release Confirmatory Measurements Program 1 4 September 1997
I survey Report Attachment i Page Al.1
- Attachment 1 ACTION PLAN UNRESTRICTED RELEASE CONFIRMATORY MEASUREMENTS PROGRAM Summary:
As a result of radiologically contaminated equipment being inappropriateiy released to a non-licensed vendor, an independent review of past unrestricted release practices at Haddam Neck Station has been commissioned. This document will detail tlw plans for assessment of past rekase practices, plans to perform confirmatory measurements of unconditionally released material, training and qualification plans for personnel performing confirmatory measurements, procedural guidelines to be employed during confirmatory measurements, and timeline for completion of the project. Event Descrintiom On February 26,1997, technicians at C&G Video facility detected radioactive contamination on video equipment which had been unconditionally released at Haddam Neck station. A representative of C&G Video informed Connecticut Yankee Atomic Power Company (CYAPCO) personnel of the discovery via a telephone call the same day. On February 27,1997 representatives from CYAPCC traveled to C&G Video and segregated the contaminated items retumed to C&G Video from those items with no measurable radioactive contamination. The contaminated items were packaged and returned to Haddam Neck Station as an " exempt quantity" shipment. The items found , not to be contaminated were also transported back to the Haddam Neck Station. The returned items were transported back to HNS on February 28th. On March 4,1997, the Nuclear Regulatory Commission (NRC) issued a " Confirmatory Action Letter" to CYAPCO. An initial response to the confirmatory action letter was submitted on March 7,1997. As a result of discussions with the NRC staff concerning the March 7th response, a supplemental response to the confirmatory action letter was submitted on March 20,1997. Additionally, on March 10,1997 while surveying boxed paperwork from the nuclear records office, three work orders packages were found to be contaminated. As a result, surveys were performed on 82 boxes of records from HNS at Millstone. The Millstone surveys found no additional contaminated papenvork. Interviews were conducted with site organizations to identify other items which may have been inappropriately released from the RCA. From these interviews three more potential items consisting of used tags, log books, and engineering drawings were identified for further investigation,
_- .. . - . _ _ = - -- ... _ - . - .. - ~ ,~. -.....~ . . . -,._. .--, . .- .,-- . . . ~ ..- I
- ( ,
survey Report Attachment 1 - , } Page A12 Action Plan ~ ' 1
?
The supplemental response committed to development of an action plan to determie s the extent to which radioactive material may have been inappropriately released from the radiologically controlled area (RCA). The action plan is to contain the following i [ elements: - -- 4
- 1. Identify surveylocations i
- 2. Identifyitems to be surveyed i.
- 3. Establish procedures to govern performance of the surveys
- 4. . Determine resources required to compbte the action plan 4
5.- Communicate the action plan issues ar.d status to site management - , ; 6. Planimplementation
- 7. Identify programmatic deficiencies
- 8. Establish milestones and estimated completion dates
- 9. Analysis ofdata and conclusions.
- - Further, to ensure the action plan surveys are performed appropriately, the following
- actions are to be taken.
, 1. The Survey Plan Manager will e- n.unicate the standards and expectations regarding -
- the performance of surveys to 11 ' ealth physics technicians. (To be included as part of training and qualification);
- 2. Health physics technicians performing the surveys will review and sign their i acknowledgment of all procedures governing the release of material from the RCA.
(To be included as part of training and qualification) f
- 3. CYAPCO will ensure that the surveys are properly conducted through periodic j - assessments and management oversight. (To be included as part of Quality Assurance) 1: 4.' CYAPCO supervision will review all survey documentation for accuracy and
;~ . completeness. (To be included as part of Quality Assurance) i' 4
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i-4 %i survey Report Attachment i Page Al.3 This action plan has been generated to satisfy commitments made in the March 20th # c = ! supplemental response to the NRC confirmatory action letter. <
; Initial Evaluation *
- In order to determine appropriate confirmatory measurement schedule and scope, an initial evaluation for potential amounts of contaminated equipment and probable maximum contamination levels expected has been assessed. Based on a review ofpast plant practices -
l - and procedures th6 survey plan was designed using the following assumptions: 1) the - incidence of contaminated equipment being identified outside the Radiologically Controlled Area (RCA) will be low,2) the incidence level outside of the Protected Area will be lower - i than inside of the P:otected Area, and 3) contamination levels encountered are expected to i present no significant risk to workers or the general public. I: The above assumptions are based upon the following conclusions from information reviewed: 1.
- 1. The data from a similar event at Millstone in 1989 indicated a contaminated incident rate
[ of 0.132% for nearly 500,000 individual items surveyed. Maximum count rate instrument response identified was less than 10,000 conected counts per minute for a standard thin
- . . window G M instrument (frisker). The vast majority of the contaminated items were tools
- stored either on-site or at the NUSCO Great Neck Warehouse.
I L Survey and release practices f'or Millstone prior to the 1989 event were similar to the 4 practices at Haddam Neck Station. Due to additions of more sensitive survey equipment in . i- early 1996 at Haddam Neck, qualitatively one would expect the practices at Haddam Neck i -- to be better than pre-1989 at Millstone. Further, the transfer of tools outside of the protected area at Haddam Neck appears to be considerably less than was the practice at pre-L 1989 Millstone, i I [ 2. A walkdown of the storage areas at Haddam Neck identified little transfer of tools and 4 equipment from inside the RCA to storage outside of the protected area. [ ' 3. Review of training and qualification material, station procedures,10CFR61 isotopic mix data, skin and clothing contamination reports, and discrete particle data indicates that 1) ' past practices appear to have been acceptable by industry standards,2) equipment used was - appropriate for identification ofisotopic mix, and 3) there does not appear to have been a j significant loss of contamination control at the station.
- 4. The results of tool and equipment surveys performed in the maintenance and instrument
- - & calibration areas using new SAM-9 instrumentation in February of 19% were similar to
.[ incident rates found during surveys in comparable areas at Millstone in 1989. E
- . - . . - . . - . - .. .-.-.....w.---,_ .- ~ ~ - . - - ~. n.-- - . - - . - ~ . - . .-~
e swvey Report Attachment 1 : Page A14 !
~
- 5. The total amount of equipment unconditionally released to vendors or to other NUSCO -
- facilities has been small.
? , [ 6.' Although there have been contaminated items found both within the protected area and l- the owner controlled area, the incidence of documented events does not appear to be significantly above the average for nuclear power plants of a similar type and age.
. hrvev I mtinne Plam 3 - The survey program is planned to begin in the Haddam Neck Warehouse and other -
l storage areas outside of the protected area. In addition to the main warehouse facility, there are storage areas in several outside buildings along the eastarn edge of the parking - . ) lot. Also there are several sea-van containers and a steam gento er mockup building which will need to have material surveyed. The equipment and material stored in the outside buildings does not seem to lend itself well to SAM 9 monitoring. For this reason it is expected that one survey team can begin in the outside buildings using primarily thin window G-M frisker instrumentation, while two other teams begin to process material in the main wr.rchouse. L
- Following completion of the areas outside of the protected area, the three teams will next j=
move to the tool storage areas associated with the maintenance shop and I&C labs. These F are the areas next fanhest from the RCA. They are also adjacent to areas where personnel + may have offices and/or eat and drink. The f' mal areas to be surveyed will be the storage areas around the fringe of the RCA such .
- as_the butler building, the numerous sea van containers stored within the Protected Area
~
and some various paperwork storage areas. Depending upon the outcome of the material ._ surveys to this point, these areas could complete the survey program. However, if
- substantial amounts or higher than expected levels of activity are four.d, other off site !
L areas may have to be added into the program, not necessarily in the order stated above. 1 Potential off-site areas could be vendors identified with high potential for equipment ! which was used in contaminated areas and was subsequently unconditionally released or ! material released to the Millstone Warehouse. Additionally, some areas of storage within
' the RCA may also be added based upon findings of survey program.
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I e, Survey Report Attachment 1 Page Al.5 4 heme to be Surveyed! In order to concentrate on the items with potential for contamination, equipment sealed in ; original packaging is considered to have no reasonable potential for contact with licensed - material. Dcpending upon individual storage area conditions, external surfaces of sealed equipment may still need to be surveyed due to potential cross contamination. Anticipated survey sample sizes are as follows: Main Warehouse - approximately 10% ofindividual items with reasonable potential for contact with licensed material in storage due to what appears to be a low probability for significant quantities ofitems returning to this facility after being in the RCA. -Items to be exdaded from survey will be those item obviously still scaled in original receipt condition. Of the remaining 10% surveyed, the material chosen will be biased toward items which appear to have been potentially returned to stock. P Outside the protected area storage - approximately 100% ofindividual items with reasonable potential for contact with licensed material in storage since there is a higher probability ofitems from on site being moved into these sto age facilities, not to mention a fairly high incidence of finding contaminated items here in the past. Paperwork in various locations including removed tagging from the plant being - stored by Operations, previcusly used log books from the RCA being stored outside, and a selected spot check of engineering drawings identified to have been inside the RCA. Tool rooms by shops - approaching 100% of tools and cquipment in storage areas
. due to the nature of equipment, not to mention it will serve as a benchmark of how well material has been controlled since February 1996 (when these facilities were done by SAM-9 surveys).
Butler Building (non-RCA side) storage - approximately 100% due to probability of contact with licensed material and higher incidence of past problems identified in this area. Additionally, the proximity of this area to RCA storage increases the risk of cross Icontamination. In protected area sea-van containers - approximately a 10% sample for clean side scaffolding, approaching 100% for other tools and equipment with reasonable potential for contact with licensed material.
l
.e survey Report Attachment i Page Al.6 Since other areas would be added due to unexpected results from the above mentioned arear, it is anticipated that the additional areas would then be expanded to the nearly 100% survey sample classification.
Survey Performance Practices-
- a. Intemal contamination evaluation: The survey proces: will begin with an evaluation for
' the potential for intemal contamination of the item to be surveyed. This evaluation will focus on 1) the probability of prior use in a contaminated area,2) the probability of prior use in an airbome area, 3) gauges, hoses, tubing, etc. with higher probability of having been connected to contaminated systems, and 4) the probability ofintemal contamination due to intemal cooling air flows. Any items evaluated to have a high probability ofintemal contamination will be physically measured through disassembly, intemal swab type smears or gamma spectroscopy.
- b. Removable surface contamination evaluation: The second phase of the contamination survey will be through an evaluation of remowh!e contamination on extemal surfaces of the item ofinterest. If the item has a large surface area with low probability for localized contamination on threads, connectors, crevices, etc., the survey may be accomplished through the use oflarge area smears. More thorough evaluation would be required for any large area smears which resulted in greater than 100 cepm reading for a standard thin window G-M frisker.
For items with smaller surface area or high probability for localized contamination identified as above, standard 100 square centimeter (or entire surface area, whichever is smaller) will be utilized to measure for removable surface contamination. Analysis of the small area smears will be performed thrcugh use ofinstrumentation capable ofidentifying levels less than 100 cepm.
- c. Total activity on extemal surfaces evaluation: The evaluation for total actisity on surface areas is to begin with a spot check using a thin window G M frisker for locations with a high probability for surface contamination. Such areas would be porous or uneven surfaces, threads, connectors, etc. For individual smaller items (but greater than 100 square centimeters of surface area) a single survey through use of the SAM 9 will be considered sufficient for total activity evaluation.
For significant amounts oflarge surface area items, additional survey equipment may be e evaluated for use. Such equipment may be use of a laundry monitor for large flat items or special equipment designed for the survey of tube lock scaffolding. The use of other equipment will be detennined by quantities and types of materials to be surveyed as the program progresses.
I Survey Report Attachment i Page Al.7 For items which have not had the entire surface area monitored through one of the above methods, the entire surface area will be surveyed by use of the thin window G-M frisker. Programmatic Deficiencies: The above procedures to be used, in conjunction with identified training and qualification plan for the senior health physics technicians, should address programmatic deficiencies which initially led to the inappropriate elease of radioactive material. Upon completion of root cauw analysis and associated recommended corrective actions associated with this event, details of this action plan will be reviewed to confirm no further action is required during the course of this project. Documentation of Survev Resultat Detailed survey results will be recorded for any items found to be contaminated. Included in the documentation should be the disposition ofitem, initial contamination levels, location of contamination on the item, discrete particle information if applicable, and any associated analysis ofisotopic constituents for the radioactive material present. Surveys of the items with no de.ectable radioactivity identified will be documented by log entries which as a minimum shall describe :
- 1. The location description for the item (or group ofitems for similar items like a given bin ofmaterialin the warehouse),
- 2. A general description of the item or group ofitems,
- 3. The percentage ofitems surveyed for a group ofitems,
- 4. The total number ofitems surveyed from a particular group ofitems,
- 5. A record of the survey method (s) utilized, and
- 6. Other additional notes or information as is appropriate.
[ swvey Report Attachment 1 Page Al.8 Trainino and Ounlification: The Survey Plan Manager is a Certified Health Physicist with more than twenty years experience in Power Reactor Health Physics. The manager's prior experience includes health physics program management, regulatory inspection, and management of quality assurance activities. All technicians assigned to this project will be qualified senior technicians in accordance - with ANSI 18.1 1971. The documentation of experience to comply with the ~ ANSI standard will be through established procedures of the utility. 1 Specific training for this project will be through a combination of classroom instruction and on-the job qualification. De classroom portion of the training will include such items as; the event background / description; expectations for questioning attitude, documentation, communication, procedural adherence, and teamwork (common goals); work observation of work by supervision and peers; and specific knowledge information about regulatory requirements, information concerning specific instrumentation to be used, and procedural instruction. The final phase of the training and qualification process will be the on-the-job training and evaluation. De documentation for the OJT process (as well as classroom instruction) will be in accordance with the utilities established approved training program. Ouality Ascurance for the Pronramt Instrumentation utilized for the survey program shall be calibrated in accordance with established utility procedures. Source and background checks of portable survey instruments shall be performed at least daily and documented in accordance with procedural guidance established for this project. A part of the quality assurance of this project will be documented observations to be performed by both supervision and assigned senior technicians. The observation sheets will include minimum performance standards to insure consistent performance by technicians throughout the course of the project, in addition, independent verification of survey results will be performed by personnel identified by the Survey Project Manager. The frequency of the independent verification will also be determined by the Survey Project Manager based upon revicit of technician observation and survey results. Copies of survey documentation will be forwarded to CYAPCO supervision daily to allow for review for accuracy and completeness.
, . . - .. . ~. - - - . . . . - . ._ .- -. .- - . . - . ~_- .. !- l survey Report Attachment i Page Al.9 l Resources Anticinated to Comnlete Action Plan?
[ ! Initial plans are for three teams of two technicians per team to be utilized for the survey program. The necessary survey equipment to support this number of teams working has [' been identified as currently available at Haddam Neck Station. Should expansion of the scope become necessary, additional personnel and equipment may be added to complete . the project within the committed time schedule. t . Milectnnen and Estimated Comnletioni
. Haddam Neck Warehouse and other storage areas outside of the protected area should have surveys begin the week of April 14th following technician training and -
. qualification. The estimated completion of surveys in these areas is approximately the week of May 5th.
[ - The tool storage areas associated with the maintenance shop and I&C labs will be 2 performed immediately following the outside areas, These areas should complete in approximately one week (week of May 12th). The final phase of surveys of storage areas around the fringe of the RCA are expected to [ be completed by June 2nd or 9th. The amount of time necessary to complete these areas is harder to estimate due to the unknown content of the many sea-van containers, L Obviously, as the project progresses, changes to the timeline may become necessary as any new areas to be surveyed are identified or the amount of contaminated equipment required to be dispositioned is greater than expected. Communication ofIssues and Status: Biweekly reports to the Health Physics Manager and the Unit Director are planned to communicate action plan progress, a summary of results from surveys, required changes
- to resources or schedule, and any concerns for incorporation into line organization j performance which may be identified. }'
s 4-
survey Report Attachment i Page Al.10 Finni Renort and Documentation Disnosition! A final summary report of the findings of the survey program will be prepared. Information to be included in the report will be such information as; actual resources utilized, number ofitems surveyed, number ofitems found to be contaminated, total activity found by area, difficulties encountered, and any recommendations and lessons
- learned that the utility may find beneficial during the decommissioning work ahead.
All original documentation generated as a result of this project will be tumed over to the utility for inclusion in the nuclear record files as appropriate.
Docket No. 50 213 CY 97-094 1 i i 4 ATTACHMENT 2 i Vendor Survey for Confirmatory Monitoring Program i i 4 1 i i 1- 't 4
}
i e September 1997 ] 1
Vendor Servey for Confirasatory Monitoring Progrant 9/25/97 8;19 AM j l Purchase Job Centracter Company and CY # or RFU 19 RFU 18 Comments N _ _ : _ __ Order Descripties Representative Centact People Assessment Assessment Number Name/Nember 509344 Replacement Westinghouse Electnc Corp. R. SeeIIP - Lhd not start - Same Contractor - Pnor to work No follow up Control Valve 100 Great Meadow Road Beganski Purchase thisjob used for same commencing on the surveys are Suite 702 245-5421 Rec. - Work would scope of work turbine a required due to Wethersfield, CT 06109 [MP-0542] #513856 have occurred contammation work being (203)258-2660 on theIIP survey was performed on the Turbine - -:--- 'Any secondary side, Subcontractedto1 esdyne, -contractor used positive indication and the fact the Pittsburgh, PA their own tools ofcontam. nation equipment is used resulted in black at other facilities. beauty used to drcon equipment and a" clean" dCtermmaison prior to work commencing. Exciter Jim Bothwell Consulting R. I person to -no individual -lhis contractor No follow-up Leveling 309 SW Ridge Lane Beganski watch was brought on- was not used for actions required. Stuart FL 34994-71267 245-5421 exciter site who RFO 18 (516)287-9940 in Flonda [MP-0542] performed physical work (770) 493-8850 in Atlanta 509332 IIP 1 urbine Mannings P 4-6 people - contractor -vendor was not -see discussion No additional Casing 53 Abbett Avenue Beganski brought their used for work on above for work follow-up is - Bolting P.O. Box 1365 245-5421 own equipment . RFO 18 condixted on IIP required for this Imsening Morristown, NJ 07962- [MP-0542] -some work had turbine contractor due to and 13655 started decontamination Tightening Robert Lake (201) 984-5522 -tools released to process used for Fax:(201) 984-5833 vendor turbme. 1 I _.
Vender Servey for Confirmatory Monitoring Progrant 9/25/97 8:19 AM l 1 rurchase Job Centractor Company and CY # or RFO 19 RFO18 Comments ri,_ ^ _ _ Order 16. ., ^ _ ; Representative Csetect Peepit Assessment Assessment Number Name/Nomber , 509348 Retaining Westinghouse Electric Corp. R. Max 3 -UT inspection -used in same - Pnor to work No fwther follow- I Ring 100 Great Meadow Road Beganski Most likely work scope as commencing on the up is required due inspection Suite 702 245-5421 2 people RFO 19 turbme a to decontammahon Wethersfield, CT 06109 [MP-0542] will work contammation process ofIIP Bill Kruger(860) 258-2660 24 hours a survey was turbme prior to Betsy Feldman- Nuclear day conducted. Any work m. . Kir4 Security (407) 281-5885 positive indicahon Joe Lupin ofcontamination Suku .cwdu to Wesdyne, resulted in black Pittsburgh, Penn. beauty used to Ronda Bowen decon equipment (412) 733 6010 and a
- clean
- David Williams determination prior .
(412) 733-6000 to work l I Andy Kaminski . -_- - --- - ;,g. (407)249-7504 513856 1G Project Westinghouse Electric Corp. st Project - Work tqan on - same work scope - see above - see atme Manager and 100 Great Meadow Road Beganski Manager - this project. as RFO 19 disposition for Project Suite 702 245-5421 John imel - -Vendor brought work on Retaining Engineer Wethersfield, CT 06109 [MP-0542] and 2 in their own Ring inspection. Bill Kruger(203) 250-2660 project equipment. HP Turbine Betsy Feldman -Nuclear Engineers Work - Security (407) 281-5885 welding, machining i 2
.. .. i Vender Survey for Confirmatcry Monhoring Programa 9/25/97 s: DAM l
t Purebase Job Centractor Company and CY # er RFO 19 RFO18 Comaments Despeesties i Order Description Representative Costeet People Assessment Assessment ; Namber Name/ Number 95713R Sandblasting Tota!!y Blasted R. 3-5 people - Turbmc work - used to perform -Equipment for No follow-up . P.O. Box 484 Beganski and additional Cavity cicaning RFO I8 surveyed at surveys requ::M .
, Portland, CT. 06480 245-5421 work on-site under time and found for work
[MP4542] Maintenance (Jim contaminated. performed on - Barry Baker (860)267-6999 DuPre) Equipment was turbme. RFO IS Jan Baker -used own purchased and issue is closed due I18 Greenwood Avenue equipment. resides at CY. to equipment Ilyannis, Mass 02601 purchase. 513659 Ofwirac Crane W.F. Myctic Contracting R. 2-3 peopic - performed work - performed - Turbme is on the No follow up Corp. Beganski on the Turbine similar ww..d y side of actions are P.O. Box 505 245-542I crane during the maintenance of the plant. required due to Brook, CT. 06016 [MP4542) first two weeks crane for RFO 18. location of the ' ofoutage. work on the
-replaced parts secondary side of on crane. the plant.
-Old parts surveyed for release.
517645 Remove liigh ARACOM R. 2 people -No work was -job scope would - Prior to work No additions! Spots from 555 Chase Road Begerski performed and no have been as wm..x go,g on the follow-up surveys IIP turbine & Lunenburg, Ma. OI462 245-542I equipment described turbine a required for this gland seal (508)342-0575 [MP-0542] brought on-site. - would have contamination vendor due to horizontal brought their own survey was process used to joints. Surface tools and conducted. Any decontaminate IIP will be blued equipment positive indication turbmc prior to
& checked for - used at other ofcontamination w.m.ag work.
contact plants for similar resulted in black work. beauty used to decon equipment and a" clean' determination prior to work m .. x.xuig. 3
Vendor Servey for Confirnestory Monitoring Programa 9/25/97 8:D AM ! Perchase Jeb Centreeter Comepony med CY # er People RFO 19 RFU 18 Cosoments P_:, _b Order Description Representative Centact Assessment Assessment Number Nasse/Nomber Provide Munters Moisture Co.amt R. 2 people -equipment used -Vendor not used Confirmatory Drsposition ! dehumidifiers Services Beganski -brought in in RFO 18. survey group to finalized on ; 2389 Main Street 245-5421 Bring in as dehumidifiers for survey both inside 7/24/97, Glastonbury. CT. 06033 [MP-0542) visitors-one LP exhaust hood. and out because unconditional Derrick Watson will be sales -equipment could they were used. release granted. ; 633-2665 or 659-1625 rep, one will still be in turbine Need survey to be service hall finalize dispositiort man to set up 519944 Provide Air l Atlas Copco Rental R. I person to -air m. 3-- > - vendor was used '
-C,- . .e - > No follow up Compressor Rt. 20 - RD #I Beganski explain were brought in to support similar located on survey required due Box 272 245-5421 setup. to support aux. functions fer RFO Secondary side of to location of i Altamont, NY 12009 [MP-0542) feed work and 18 the plant. equipment.
(518)356 5359 Bring in as sand blasting of -No potential for Mike Smith visitor turbine. internal 5 (518)356-5359 contammation. Labor SUN Tech R. 15-20 people -persormel only -vendor not used No additional Beganski (Under PO brought in for RFO 18 follow-up required 245-5421 016514) -compan~ tools as no tools released [MP-0542] provided to vendor. Labor CMF R. 45 people -interplant -provided labor Additsonal follow-Jean Bonaronte, Madison Beganski Rotating maintenance for outage. up serveys not , 245-5327 245-542I through out force used to -used own possible due to [MP-0542) outage support outages eq sipment and transient work
- bring their own also used force and equipment and company tools equipment.
also use for work. Release of material correpany tools. from another facility would have indicated potentsal for follos-up survey it adequacy ofrelease was of . issue. 4
Vender Survey for Confirmentory Monitoring Prograue 9/25/97 s:17 AM t Purchase Order Job Descriptsee Centracter Comepony and Represcata*ive C) Contact
# or People RFU19 Assessaneet RFU18 Assenament Ceasements W Number Name/Nomber 016514 Mechanical Sun Technical Services, Inc. J. Tyler 120 people - Personnel only -Samejob - No ad;ational Support 27285 Las Ramblas, Suite - 267-3668 - Company functen as RFO follow-up is Manpower 280 [MP-0656] equipment 19 requued.
Mission Viejo, CA 92691 supplied Kathleen Jackson Project Manager Tel:(602) 849-3033 or (714)582-1223 Fax:(714) 582-2554 Tami Brennan Site Representat;ve Tel:(714)582 *223 CY Site- 3096 954184 Refueling Westmghouse 1*stnc J.lyler - perfor.ned work - similarjob scope VenJor is bcensed No addet. anal Contract Corporation 267-3668 for RFO 19 for for RFO 19 to receive follow-up is kFO 18/ P.O. Box 158 [MP-0656] refueling radioactive required because RFO 19 Madison, PA 15663 -$rought their matenal they are alicensed c/o Mark Stickel- Mail Bin own tools which facility and 851 were both free perform work at Peter Defilippi relcamiand various difTerent (412) 722-5721 shipped sites around the Phylis Mashes radioactive. country. I (412) 722-5770 - perform work at ; Janet Rohack . vanous reactors (412) 722-5713 across the country. t 1 i 5 l 1
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Vender Servey for Confirmentory Monitoring Progrs= 9/25/97 s:2e AM Purebase Job Coetractor Company and CY Coetect # er RFO 19 RPO IS Coenaments r_ , _ ^ _ Order Description Represcatative People Assesseneet Assessament Number Nanse/Nomber 016335 Turbine ABB Combustion C. Peterson 30-40 - used courpany - similarjob scope - paperwork is ABB was NDE- E..s... u u.g [MP-3207] people equipmert that is for RFO I8 avahble at contactedon 3aly Stationary & traceable traough Millstone for 3,1997 forexact
. Misc. Denise Lucas the AWO to the tracability. . location of this C m. g .cs (860) 688-2400 ext.34 instrument serial - majonty of specialimi number. equipment is equipment. No'
- one specialim! .._.J.- a4 at additional follow-MT machine was Millstone- up is requwed.
brought in by the vendor: KRH 3D
#56%5EL*077 RCP Seal (2) Master-Lee Energy Service J. Tyler Sue - personnel only - not used for - mdevadual No addstenal Overtiaul 1639 Clearview Drive 267-3668 Matthews - no tools work in RFO 18 assigned as followasp required Tech Support Latrebe. PA 15650 [MP-0656] procedure uviter as tools were not for mamtenance involved for scope Mr. Chuck Cormers and operanons ofwork.
Mikellamby (412)$39-7597 ext.224 RCP Seal (2) Westmghouse Electric Corp. J. Tyler II people - no physical -performed RCP -company tools - No addstsonal Overhaul P.O. Box 158 267-3668 work performed overhaul using ma'mtamed at follow-up required Tech Support Madison, PA 15663 [MP-0656] for RFO 19. NU company Millstone for use as tools were not c/o James Borsh supplied tools by the interplant released to the maintenance force. vendor. 6
. . _ _ _ _ _ _ __ _ _ _ _ = _ _ _ -
Veeder Survey for Confirematory Monitoring Progrant 9/25s7 s: DAM Purchase Jeb Centracter Compney ace CY # er respie RFO 19 - RFOIS Censmeets r_,_^ Order Descripties Representative Canteet Assessment Assessment Nember Nasse/Nomber 017121 Valve Repair Newport News Industna' B. 23 people - some work - performed valve - mdsvuhsal relayed No addstnonal
& Manpower (NNI) Thomas initiated for repair and addstsonal follow-sp surveys .l 7007himble Shoals Blvd. 267-3144 RFO 19 provided information on is reqami of this i Suite 108 [Seabrook -used company manpower other recent vendor as no j Newport News, VA 2360(- x-7423) tools to perform -used company occurrences that equipment was 2544 work. tools forjob might warrarit returned to the scope. additional vendor 14:Trent (757) 380-7594 investigation ( see Mike Kurck (757) 380-7088 belowl q Valve Repair Atlantic Valve B. 'follw-up -Vendor used Thomas vendor throughout years to 267-3144 based on support valve
[ Scal: rook interview repair of secondary x-7423] side and fced reg. valves. Valve Seabrook Station B.
- follow-ep - Equipment was Scabrook notafmi.
Equipment Thomas facility both free released follew up surveys Transfer 267-3144 based on and sent LSA performed.No [Seabrook interview shipment to detectable x-7423) Seabrook. activities.
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Vender Survey for Confirmentory Monitoring Prograsu 9/25/97 8:19 AM 1 l 1 Purchase Jsb Centracter Company and CY Coetset # er RFO19 RFU 18 Comenents 1Mapsesteen Order Deserspeien Representati-e People Assessmeet Assessament Neinber Nanse/Neesber 016335 Erosion / Af. Y;ombustion B. Dietz Corrosion Er.gineering [MP-2028) 016335 SW ABil Combustson B. D etz Radiographic Engineering [MP -2028} y [ ' 016335 ISInipe AbB Combustsen B. Dietz 30-40 - Some work 'SI impection - Personnel only ( No follow-up inspection Engirr:ermg [MP-2028) people started to support under direction of - Used company survey repired John Sikorski RFO19 Jerry Fan supplied tools because no 688-2400 ext. 72 equipment was released to vendor 522028 Reactor Framatome Technologies R. Fuller 15 people - No work started - No similar work No follow ssp Vessel UT, 155 Mill ridge Road 267-3901 was performed for survey requhed VT and Pzr. Lynchburg, Virginia 24502- [MP-2276] RFO 18 for thisjob scope. Nozzle Innes 4341 See followmg Radius UT dispositsons R f Bryce Stallings additional l 1804)832-3351 infor,atson. I Michael D. Street Tel:(804) 832-3758 Fax:(804) 832-0622 8
.< so Vendor Survey for Confirmiatory Monitoring Prograns 9/25/97 s:D AM Purchase i Job Contracter Company and CY # er People RFO 19 RFO18 Ceemsee's r_ , _ ^ -
Order Descripties Representative Contact Assessment Assessmeet Number Name/Nomber 89107 Provide SG I ramatome Technologies R.. 160 people - No work - brought in own - vendor h:ts own rio follow-up : , Services 155 Mill ridge Road Pritchard performed. equipmeM license to receive survey required
~
Lynchburg, Virginia 24502- 267-3648 -equipment was radioactive mesenal boca.:se vendor l 434I both free release - vendor performs has licerse to ; and shipped similar work at receive radiocctin j Don Williams radioactive LSA. other facilities matenal and .l (Tmg/ALARA) -way side around the country tracability of l sludge lancmg contammation Mike Street -used Atlas Copco from CY is not (Project Manager) Rental possible because compressors equipment couH i I have been used at other facilities. Platform Spec 30 people - No work - subcontractor for No folkrw-up Workers (sub contractor of performed. Framatome servey required as Framatemej supp!-ing pe.'.sonnel subcontracted by only above vendor Ihsposatson is covered by above. 016335 Provide BOP ABB Combustion R. - No work -See additsonal No follow-up Eddy Current Engineering Pritchard performed or vendor survey required Testing 267-3648 equipment informa son below because no (ECT) brought in. equipment was Services brought in. Provide BOP South Shore Iesting R.
- Addstional -Performed no - Performed eddy -Brought in oute No follow-up Eddy Current Pritchard Vender work for RFO 19 current testing on equipment survey required Testing M7-3648 Identified secondary side of - No contamination because equipment (ECT) during plant areas Le. secondary used on secondary Services in::rviews side side of plant.
9
.* se Vender Survey for Confirmistory Monitoring Program 9/25/97 s:D AM Purchase Job Centracter Compsey and CY -f er People RFO 19 - RFOIS Comments P4 _
Order Dmription Representative Costaet Assessment Assessment Nember Name/ Number 519944 Provide Atlas Copco Rental R. - Diesel powered - Diesel powered - Co.w.uvi > No follow-up compressor RL 20- RD 8I Pritchard m..,, cswi s m. - =-.s rented located in RCA yard survey required and Box 272 267-3648 rented to support to support Turbine / -No potential for due to use of Associated Altamont, NY 12009 planned Steam Steam Generator mternal u...,,_.: and lack Equipment (518)356-5359 Generator work. work contammauon, high of potential for Andy Squitterri probability of internal (508)568J440 survey of external contaminauon. surfaces performed i prior to release. ~l 525048 SW Piping C1S Power Services R. Kasuga - perfenned - Not used for - Equipment used at No follow-up Cleaning 267-3637 minimal worit RFO 18 see vendor various stations so survey required for RFO 19 telow for work tracability to CY not due to work scope possible. controls
- Work scope had established rM instrumentauon lack of tracability sleeved prior to to CY.
insertion into pipe
-piping was only one year old SW Prping Virginia Corporation J. Fan
- Foalow - Not used for - Automated prpe - Equipment used at No follow-up i Cleaning up vendor RFO 19 walker various stations so survey required identified - UT scope and tracability to CY not due to work .
during cables possible. controls interviews - Work scope had established and ristrumentation lack of tracability sleeved prior to to CY. insertson into pipe
- piping was only one year old.
338907 Support fo' ABB Cor.rsustion S. Cames: I person - Some work Vendor has - used company No follow-sp IRPI Engineering 267-3120 initiated for RFO supported other supplied tools for survey required Installation Bring in as I? job scopes during work scope because no tools Testing visitor RFO 18. were released to Vendor. i e 10 ) t
. _ - - - c
W: --- - - - - Vender Survey for Confirmatory Monitoring Progrant 9/25m s;l) AM Perebsw Job Centracter Compsey and CY # or People RFO 19 RFD 18 Comments C_^ Order Descripties Representative Costeet Assessmeet Assessment Number Name/Nember 015326 IIP Support & Hardett Nuclear W. Gates 92 people - Personnel Only -Personnel Only No follow-up I Manpowa P.O. Box 1800 267-3533 total survey required l Plymoutig MA 02362 because no equipment Judy Tingley involved. 1-800-2.25-0385 x290 Gerry liiatt I-800-225-0385 x286 065 % 5 Audio and C & G Video W. Gates 4 people -brought in vulco - provided same -Inadvertent release Equipment was Video 223 West 6th Street 267-3533 and audio service as RFO 19 of material to retrieved from Services Oswego, NY 13126 surveillance unlicensed vendor C&G video and equipment - February 26,1997 retumed to CY for Chuck Bissesi CY was notireed of resurvey and (315)343-1519 event possible
- ACR initiated decontaminanon.
- Root cause items that were j initiated -NRC unsbie to be 1 issued CAL on released were l March 4,1997 purchased. I
- This event is the reason that CY is conducting confirmatory survey and personnel were interviewed for vendors brought en site for RFO I8 and RFO 19 who may have been sent contaminated material inadvertently.
11 L_ _
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Vendor Survey for Confirmentory Monitoring Progreat 9/25/97 8:19 AM Purchase Job Centracter Company and CY # er People RFO 19 RFU 18 A - t Comments O' ; : ^- __ Order Descriptome Representative Centact/ Assessment Number Name/Neseber 016537 QC Spec /NR1 TechnicalInc. J. -Personnel -Personnel primanly. Personnel visit No follow-up Inspection Methocen, NJ. Beauchamp primarily. A few other plants to survey required. Support [MP-2113] personal gauges perform similiar Du-: . *A-brought in such as work. Traceability traceability. mist scale, to CY not possible. welder fillet, and Cambmige gauges, etc. Cavity Decon ROV Technologies R. liaight I person - Robot came in -See information - Equipment No follow-up . . 267-3537 from Millstone to associated with returned to survey required. clean cavity Totally Blasted for Millstone Equipment was RFO 18 for - Equipment transferred to a description of work shipped as known licensee. and disposition. radioactive Car Fans Otto York Company D. Carnes 1 person - No equipment - Not used for RFO See additional No follow-up 42 Intervale Road 267-3135 broughtin. A 18. Work performed vendor information survey required. P.O. Box 3100 walkdown was by CY personncL below. Job scope did not Parsippany, NJ 07054-3100 performed. involve transfer of equipment. Car Fans Thomas Young D. Carnesi
- Additional - Not used for RFO -Performed Car Fan - Own equipment No follow-up 276-3135 vendor 19 Ilow tests for RFO 17. brought in. survey possible identified -Vendor used 4 due to length of J. Fan during years ago. time since vendor 267-3558 interview - Vendor supports was last used and process. multiple facilities the difficulty in during outr2e tracability of any times. contamination to CY. _
RWST PCI (Energy Services) J. Stabach 15 people - Startmg setting up - No similarjob was - brought in their No folk,w-up i Energy Drive 267-3129 to perform work for performed for RFO 18 own m.3a .,and survey required. P.O. Box 3000 bottom repair desks. Lake Bluff IL 60044 - Staging was erected and (847) 6R0-3100 insulation removed. Ron Seagraves exte 133 - Administrative Scott Achtor ext.: 146 support was setup otsside RCA. 12
i Vender Survey for Confirmiatory Monitoring Prograna 9/25m s:19 AM rurchase J.b centractor c.mpany and cv n er re. pie aro I, aroIs c.mments r;_- Order Descripits Representative Centact Assessement Assessment I Number Nasse/Nomber Iluned Proto Power Corp. R. Kasuga lI people -Personnel only - Personnel only No follow up Service Water 591 Poquonnock Road 267-3637 total survey required rehabilitation Groton, CT C6340 because there was 6 Miller no transfer of . Ed Bradshaw - CY 267-3930 Pipe equipment. \ Groton:(860) 448-6288 , Groton:(860) 446-9725 5 Proto work through Tim Larose Power ext. 35%
- Subcontractor-Miller Pipeline Inc.
8850 Crawfordsville Road P.O. Box 34141 Indiar=apolis,IN 46234 Ralph Miller (317)293-0278 1 800-428-3742 Jerry Briner (317) 293-0278 ext.159 Upender Nuclear Energy Services J. Stabsch to people - Diving - Vanous - Divmg suits / masks No follow-up repairs 44 Shelter Roci Road 267-3129 evolution in SFP functional support surveyed using survey necessary including Danbury, CT 06810-7095 in support of for RFO I8 and frisker diving transfer cart beyond. -Remainder of Lee G. Penny repairs and equipment supplied (203) 796-5338 maintenance by CY
- Diving suits Ted Kettler-Project Lead brought in by
, (Control setup individual) subcontractor- Computer was RUST released at IIcalth
-One specialized Physics Control computet brought Point.
in to setup electronic controls for opender 13
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.. ,c Vender Servey for Confirmiatory Menitoring Prograsm 9/25/97 s:19 AM Perchase Job Coetracter Company and CY # er RFU19 atFO 18 Conseemts 4^_ .
Order Descripties Representative Centact People Assessment Assessment Nember Nasse/Neseber ' Laborers / Stone & Webster R. - Personnel and - Personnel and - Laborers that Welders Grebesch both company both company and operate as part of George Carpenter ard own own equipment the IMF force for equipment Millstone /CY and other power facilities
-Maiority of equipment may reside at MP ' -
Laixwcrs AMF All Depts. - Personnel and - Personnel and - Lahorers that No follow up Mi.' stone /Seabrook both company both company and operate as part of surveys required and own own equipment the IMF force for as eqmpment equipment Millstone /CY and would have been caher power used at etter facilities facilities and tracability to CY is not possible. Laborers / NuCost Retirees -Personnel only - Personnel only No follow up Administrativa 154 IIempstead Street survey required as Assisstance Mew London,CT 06320 there was no transfer of Walter 1.Varney equipment. (860)437 7812 Fax:(860) 437 -7874 Fan Testng Altran Corp. M. Denny 2 people - No physical - no similar wort No followisp and Services 200 liigh Street 267-3556 work performed. pu fv. ..J survey required as Boston, Mass 02110 [L Fan -Personnel there was no Attn. Paul McDonough CY-3558] assistance only. transfer of (617)330-1130 equ W _ fax-(617) 333-1055 Scott Blodgett 14
.- ,a Vender Servey for Confiranatory Monitoring Progrant 9/25,97 8:ID AM l
I Perchase Job Coetractor Coaspesy med CY # or RFO 19 RFO IS Comments E'; Order Description Representative Centset/ People Assessment Assessment i Neusber Name/Neaeber i
!tadiography Rust J. Fan -Radiography of -Similarjob scope No follow-up 267-3558 various pipes on to that of RFO 19. survey required both hot and due to the method secondary side. that weeld have 'I been used to release the radiography source.
Diving Rust J. Tyler -Diving -Divmg - ET & is used No follow-up 267-3668 Evolution in the Evolutsons into the at n uitiple facilities survey required [MP-0656] Spent Fuel Pool Cavity, to support both hot due to 'ack of for m6denn.ce Screenwell, and and ~4 , side ~ tracability to CY. to transfer cart. Spent Fuel Pool. systems. Environmental Services I person - Personnel only No follow up survey required. IIPSI Pump Ingersoll-Dresse- Pump B. Forestt 4 people -Began work on -Were not used for -Used own and No follow up Vibration Company [Scabrook total IIPSI system RFO I8. company supplied survey possNe 50 School Street 474-952t] tools. Vendor due to lack of Wa!Fole, MA 02081 2 Mcch performs work at tracability to CY. Tel:'M 668-1000 JeffBibby 2 Super mukiple facilities. Fax:(508) 668-7618 267-3909 Gary Boudreau Tel:(908) 859-7282 fax:(908) 859-7282 Raytheon B. Forestt I person -Personnel only No follow up [Seabrook survey required. 474-9521] 15
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I . - o~ L Vender Survey for Confirmatory Monitorsag Progrann 9/25/97 s;tD AM Purebase Job Csatreeter Company and l CY # er People RFO 19 RFO18 Comments O's, _ ^ Order Descripties Representative Contact Assessment Assessment Number Name/ Number Contract Solutens B. Forestt -Personnel only -Personnel only No foi!ow up Two Keewaydin Drive [3eabrook surveys required Salem.N1103079-4875 474-952I] because there was 1-800-998-2741 no transfer of i 603-893-6776 equipment. Fax: 603-893-4208 Frank A.McKinnon 603-964-1117 Fax: 603-964-6741 URSA -Personnel only -Personnes only No follow up surveys required 1 Fan because there was 860-267-3558 no transfer of equipment. i f 16 i
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- Docket No. 50 213 i CY 97 094 .
.- i 4 l 4 i 1 a d > i ATTACHMENT 3 Summary of Outside Area Activity 2 S 4 i .i t t a 'I f i
. September 1997
$wvey Repet Attachment 3 r.,e u .i Attachment 3 Sumimary of Outside Area Activity WAREHOUSE
~
Activity ITEM Total cepm' (microcuries) ltems Surveyed Portable weld rod oven 600 2.70E 03 8716 CAR Filter #3930 1020 4.59E 03 CAR Filter #3931 1020 4.59E-03 Contaminated items CAR Filter #3932 1060 4.77E-03 32 CAR Filter #3934 300 1.35E-03 CAR Filter #3936 140 6 31E 04 Not Detectable by Frisker CAR Filter #3937 150 6.76E 04 9 CAR Filter #3938 380 1.71E-03 CAR Finer #3939 580 2.61E 03 2100 cepm l CAR Filter #3941 800 3.60E-03 21 I CAR Filter #3942 260 1.17E 03 CAR Filter #3943 400 1.80E 03 Contamination Rate CAR Filter #3944 280 1.26E-03 0.37 % CAR Filter #3946 690 3.11E 03 CAR Filter #3947 850 3.83E-03 CAR Filter #3949 350 1.58E-03 ' CAR Filter #3951 330 1.49E 03 CAR Filter #3952 1200 5.41E 03 CAR Filter #3953 340 1.53E 03 CAR Filter #3954 500 2.25E-03 CAR Filter # Unknown 140 6.31E 04 Control Air Filter 60 2.70E-04 l Total Activity 5.16E 02 l
' Total activity for CAR Filtern may be spread over multiple spots
(' Suney Report Amuhnwnt ) Page A3 2 ?* RECYCLE BUILDING i Maximum Activi,y ITEM ccpm - (microet ries) - ltems Surveyed 86de cutters 200 9.01E M . 1667 Drill 80 3.60E-04 l Total Activity - 1.26E 03 l Contaminated items 12 Not Detectable by Frisker 10 1100 ocpm 1 Contamination Rate 0,72 %
. MISC OUTSIDE PROTECTED AREA Maximum Activity l'EM cepm (microcuries) Items Surveyed Welding Lead 100 4.60E 04 1381 l Total Activity 4.60E-04 l Contaminated items 5
Not Detectable by Friskor 4 1100 cepm 1 Contamination Rate 0.36 %
i 8 Docket No. 60 213 CY 97 094 ATTACHMENT 4 t Summary ofinside Area Activity . September 1997
( 6wvey Repwt Amachnent 4 Page A41 8 Attachment 4 Susanary ofInside Area Activity MAINTENANCE l l Maximum Activity l ITEM- cepm (microcuries) items Surveyed A6r hose 9tting 120 5.41E-04 68051 Hydraulic cutters 500 2.25E 03 Tubing wrench 50 2.25E 04 Contaminated items Tubing wrench 300 1.35E 03 76 Nippers 300 1.35E 03 Nippers 60 - 2.70E 04 Not Detectable by Friskor Screwdriver 200 9.01E 04 18 Crossent wrench 1000 4.50E 03 Crosseniwrench 80 3.60E 04 a100cepm Pipe die - 100 4.50E 04 23 1" valve -50 2.25E 04 - Chain wrench 80 3.60E-04 Contamination Rate Ball poen hammer 200 9.01E 04 0.09 % Tin snips 60 2.70E-04 Tin snips 60 2.70E 04 , Socket 80 3.60E 04 2' level 40 1.80E 04 > 2' level 40 1.80E 04 2' evel 60 2.70E 04 2" level 300 1.35E 03 Torpedo level '300 1.35E 03 Level ruler 40 1.80E 04 Halogen leak detector - 50 - . 2.25E-04 Hitti gun chuck 200 9.01E 04 - Hittichipper 200 9.01E 04 Rope lanyard -400 1.80E-03 Clamp 40 1.80E-04 Clamp 40 1.80E-04 Safety belt 300 1.35E 03 Heater 60 2.70E 04 Water hose 60 2.70E 04 Breaker bar 160 7.21E 04 Tatchet 150 6.76E 04 Heat gun : 100 4.50E-04 Drill- 100 4.50E-04 Spanner wrench 200 9.01E 04 Socket 100 4.50E 04 Socket 60 2.70E 04 - Ratchet - 80 3.60E-04 Extension cord 40 1.80E-04 Extension cord 40 1.80E-04
$wvey Report Attachenent 4 Page A4 2 Maint Shop (cont.)
Extension cord 40 1.80E 04 Extension cord 40 1.80E 04 Extension oord 60 2.70E 04 Extension oord 80 3.60E 04 Banding equipment 40 1.80E44 Banding equipment 80 3.60E44 Hand saw 40 1.80E44
- Drop light 40 1.80E 04 Droplight 80 3.60E 04 Drop light 80 3.60E 04 Drop light 60 2.70E 04 Tube light 60 2.70E44 Tube light 80 3.60E 04 '
Utility knife 600 2.25E 03 ' Reamer 2000 9.01E 03 Hydraulic cylinder 80 3.60E 04 Air blower ; 1000 4.60E 03 l Total Activity 4.86E 02 l l ELECTRICAL SHOP Max 6 mum Activity ITEM ocpm (microcuries) items Surveyed Onli 80 3.60E 04 15270 Drill 40 1.80E 04 Grinder 40-- 1.80E44 Contaminated items Band saw 40 1.80E-04 15 Wrench 200 9.01E-04 Wrench 400 1.80E 03 Not Detectable by Friskor Safety belt - 200 0.01E 04 6 Toolpouch 40 1.80E 04 Carpenter rule 40 1.80E 04 1100 ccpm Can of sealer 20 9.01E-05 3 l Total Activity 4.95E 03 l Contamination Rate 0.10%
E, sunty Report Attachment 4 Page A4 3 SEA VAN CONTAINERS Maximum ActMty ITEM ccpm (microcuries) Items Surveyed Pee elbow 60 2.70E-04 23822 Scaffold knuckle 100 4.50E 04 Scaffold knuckle 60 2.70E 04 Contaminated items Scaffold knuckle 120 5.41E 04 94 Scaffold knuckle 120 5.41E 04 Scaffold knuckle 100 4.50E-04 Not Detectable by Frisker Scaffold knuckle 60 2.70E 04 36 Scaffold knuckle 60 2.70E 04 Scaffold knuckle 60 2.70E 04 1100 cepm Channellocks 180 8.11E-04 30 Scaffold tube lock 100 4.50E-04 Scaffold knuckle 60 2.70E 04 Contamination Rate Scaffold knuckle - 80 3.60E-04 . 0.39 % Scaffold knuckle 60 2.70E-04 Scaffold knuckle 60 2.70E 04 Scaffold knuckle 80 3.60E-04 Scaffold knuckle 80 3.60E 04 Scaffold knuckle 600 2.70E 03 Hose 60 2.70E-04 Flashlight 100 4.50E 04 Allen wrench set 200 9.01E-04 Packing puller 60 2.70E 04 Diameter calibrator 300 1.35E-03 Drill 100 4.50E 04 Wrench 500- 2.25E 03 Crows foot wrench 300 1.35E-03 T Allen wrench 600 2.70E-03 T Allen wrench 100 4.50E 04 Retractable wire cutter 100 4.50E 04 Flange 120 5.41 E-04 Small rubber gasket 800 3.60E 03 Weight 200 9.01E 04 Weight 60 2.70E-04 Weight 120 5.41E-04 Weight 80 3.60E 04 Weight 240 1.08E-03 Weight 140 6.31E-04 Wolght 200 9.01E-04 Wolght 40 1.8GE 04 Weight 40 1.80E-04 Box 40 1.80E-04 Wooden divider 800 3.60E 03 CYlC-GTE 100 60 2.70E 04
(
$wvey Repwt Auuhment 4 Page A4 4 Sea Van (cont.)
Box lid 60 2.70E-04 Box lid 40 1.80E-04 Pressure gauge 1500 6.76E-03 Globe valve 100 4.50E-04 Test box 40 1.80E 04 LLRT dew cell 40 1.60E-04 , Cloth chair - 300 1.35E 03 Air blower 100 4.50E 04 Air blower 200 9.01E 04 Extension oord 80 3.60E 04 DehumidWier 20 9.01E-05 D ring 40 1.80E-04 Extension cord 20 9.01E 05 Bottle cart 60 2.70E 04 i Crossent wrench 800 3.60E 03 l Total Actwity 4.86E 02 l l CONTROL ROOM Maximum Actwrty ITEM ccpm (microcuries) llems Surveyed Dykes 60 2.70E-04 75 Dykes 300 1.35E 03 l l Total Actwity 1.62E 03 l Contaminated items 2 Not Detectable by Friskor 0~ t 100 ccpm 1 Contamination Rate 2.67 % a
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$urtry Regvt Attachment 4 3, Pa** A4 $
TURetNE BUILDING AREAS Maximum Activity ITEM cepm (microcuries) ltems Surveyed Sling 200 9.01E 04 23126 Sling 120 5.41E 04 Shackel 800 3.60E 03 Contaminated items Sling 1000 4.50E-03 65 Sling 60 2.70E 04 U bolt 200 9.01E 04 Not Detectable by Friskor Pliers 200 9.01E-04 31 Safety spanner 120 5.41E 04 Needle nose pliers 140 6.31E-04 1100 cepm Pipe nipple 1000 4.50E 03 15 Shackel 80 3.60E 04 Extension cord 40 1.80E 04 Contamination Rate Drop light 40 1.80E 04 0.28% Bushing 1000 4.50E 03 Groung fault 500 2.25E 03 Pipe elbow 600 2.70E 03 Pipe plug 40 1.80E-04 Pipe plug 40 1.80E 04 Pipe plug 40 1.80E 04 Brass fitting 60 2.70E 04 Flashlight 120 5.41E 04 Drop light 40 1.80E-04 Vice grips 200 9.01E-04 Glove - 40 1.80E-04 UT standard 60 2.70E 04 UT standard 60 2.70E 04 UT standard 40 1.80E 04 UT standard 80 3.60E-04 Polarold Camera 20 9.01E 05 Leather instr. case 80 3.60E 04 CRT monitor & case 60 2.70E 04 Recorder box 60 2.70E 04 Pipe 40 1.80E 04 Fire extinguisher 200 9,01E 04 l Total Activity 3.32E 02 l
Suney Report Attadunent 4
- g Page A44 WELD SHOP ITEM Maximum Activity items Surveyed cepm (microcuries)
Clampwrench 40 1.80E-04 8548 Steam Trap 40 1.80E-04 Drill 60 2.70E 04 - Contaminated items Glove 60 2.70E 04 62 Glove 80 3.60E-04 Drill 60 2.70E 04 Not Detectable by Frisker Power box and cord 200 9.01E 04 35 Extension cord 40 1.80E 04 Extension cord 40 1.80E 04 a 100 cepm Extension cord 100 4.50E 04 9 screwdriver 100 4.50E 04
- Scrub top 40 1.80E 04 Contamin 'Jon Rate Pipe cutter part 4500 2.03E-02 0.73 %
Pipe cutter part 150 6.70E 04 Pipe cutterpart 100 4.50E 04 Pipe cutter part 80 3.60E 04 Socket 50 2.25E-04 Scrub top 40 1.80E 04 Scrub top 40 1,80E 04 Welding Jacket 40 1.80E-04 Slag hammer 100 4.50E-04 Gas hose 40 1.80E 04 Cloth chair 300 1.35E 03 Cloth chair 100 4.50E 04 Home 40 1.80E 04 Hose 40 1.80E 04 Hose 40 1.80E 04 [ Total Activrty 2.94E-02 l
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$wvCy Report Atomhment 4 Page A4 7 BUTLER ButLDING. CLEAN SIDE-Max 6 mum Activity ITEM ocpm (microcaries) Items Surveyed Pair of gloves 60 2.70E 04 469 insulation pad 40 1.80E 04 insulation pad 60 2.70E 04 Contaminated items l Total Activity 7.21E44 l 3 Not Detectable by Frisker 0
1100 copm 0 Contamination Rate 0.64 % i & C SHOP Maximum Activity ITEM ocpm (microcuries) ltems Surveyed Stainless Atting- 160 7.21E 04 29137 Parker Atting 1600 6.76E 03 Parker Atting 100 4.60E 04 Contaminated items Transducer 60 2.70E-04 66 Pipe cutter 160 6.76E44 Needle nose plier 600 2.26E 03 Not Detectable by Friskor Vice grips 100 4.60E 04 39 Pair of gloves 40 1.80E 04 Dykes._ 40 - 1.80E 04 1100 ccpm Twist pliers 200 9.01E44 9 Cover torque adaptor 200 9.01E 04 Foxboro special cover 60 2.70E44 Contamination Rate Go-no-go gauge 40 1.80E44 0.19% Fluke CYlC 161-063 40 1.80E 04 Micrometer 120 6.41E 04 Regulator / filter 80 3.60E44 l Total Activity 1.63E 02 l
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$un ey Retett Attachnwnt 4 Page A4 8 8
GENERATlON CONSTRUCTION BUILDING Maximum Activity ITEM cepm (microcuries) Items Surveyed
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Sheet of paper 40 1.80E 04 6330 Chair pad 500 2.25E 03 Scrub shirt 100 4.50E 04 Contaminated items Scrub shirt 100 4.50E 04 21 Scrub pamts 40 1.80E 04 inspection mirror 40 1.60E-04 Not Detectable by Frisker Polarold picture 400 1.80E-03 0 Polarold picture 200 9.01E 04 I Chair 600 2.70E-03 2100 cepm Headset pigtall 50 2.25E 04 11 l Computer cable plug 400 1.80E 03 I Soldering iron 60 2.70E-04 Contamination Rate Sling 80 3.60E-04 0.33 % Scrub pants 100 4.50E 04 AC test connector 100 4.50E-04 Pipe coupon 60 2.70E-04 Pipe coupon 100 4.50E-04 Pipe coupon 80 3.60E-04 Pipe coupon 120 5.41E-04 Pipe coupon 60 2.70E-04 Hack saw - 80 3.60E-04 l Total ActMty 1.49E 02 l FABRICATION SHOP Maximum ActMty ITEM cepm (microcuries) Items Surveyed Vice grips 300 1.35E 03 777 Channellocks 1500 6.76E-03 Staple gun 80 3.60E 04 Contaminated items Weld slag hammer 50 2.25E 04 11 Chair 1500 6.76E-03 Scrub shirt 60 2.70E-04 Not Detectable by Frisker Scrub shirt 80 3.60E 04 1 Scrub pants 80 3.60E 04 Scrub shirt 100- 4.50E-04 1100 cepm Hard hat- 60 2.70E 04 4 l Tots! ActMty 1.72E-02 l Contamination Rate 1.42 %
t Docket No. 50 213 CY 97494 ATTACHMENT 5 Project Pictures September 1997
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INSIDE WAREHOUSE .I i i The following picture (AS-1) illustrates the larger items stored in the warehouse at Haddam Neck Plant. 'Ihrough , walkdowns with warehouse personnel and physical appearance of these items, potentially previously used items were identified and surveyed for contamination. Smaller items were monitored by use of a gamma sensitive small article monitor. Larger items were monitored by standard " frisking" techmques. I a 4 I i l I
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LARGE ITEM SURVEY The following picture (AS-3) demonstrates the survey technique for larEe items which could not be monitored by use of the small article monitors. Standard end-window G-M friskers were used for total contamination surveys. Loose contaraination on large items such as the one in this picture um normally pfm. 44 by the use oflarge arm smears.
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I i i 1' RECYCLE BUILDING I k i t The following picture (AS-4) shows the recycle building in the foreground. At the far, northern end of the parking l lot can be seen the warehouse facility containing the hazardous material storage and controlled environment bays for easy access for resin and large equipment storage. I i
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P t-GENERATION CONSTRUCTION FACILITY . The following picture (A5-6) showr the generation construction facility. Sea van containers can be observed stored to the right and behind the basketball net. The " Butler" building can be obsen ed just behind the lett side of the generation construction facility. 'Ihe opposite end from that visible in the picture contains the non-RCA portion of the building. _..m. - ___ __.__m__._._
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e. Docket No. 50 213 CY 97-094 l A TTACHMENT 6 Site Map M September 1997
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