ML17194A327
ML17194A327 | |
Person / Time | |
---|---|
Site: | Zion File:ZionSolutions icon.png |
Issue date: | 03/22/2017 |
From: | Houff J ZionSolutions |
To: | John Hickman, Vaaler M Office of Nuclear Material Safety and Safeguards |
References | |
ZS-LT-100-001-001, Rev 1 | |
Download: ML17194A327 (13) | |
Text
Hickman, John From: Jerry X. Houff <jxhouff@energysolutions.com>
Sent: Wednesday, March 22, 2017 10:29 AM To: Hickman, John; Vaaler, Marlayna Cc: Nick Williams
Subject:
[External_Sender] NRC Submittal Documents Attachments: Continuing Char Plan.pdf John, Fourth and final submittal for 1300 meeting.
Jerry Houff ZionSolutions Licensing Manager
. jxhouff@enrgysolutions.com Work Phone (224)789-4090 Cell Phone (860)608-6408 1
Attachment 6 ZS-LT-100-001-001 Survey Unit Pre-Characterization Walk-Down Revision 1 Page 1 of2 Information Use Survey Area No.:
-03000
Survey Unit.No.:
-03201 Survey Unit Type: Open Land 0 Structural Interior l2SI Structural Exterior D .
Survey Unit Area: - - -723 mi Survey Unit
Description:
Spent Fuel Pool (SFP) I Transfer Canal Physical Configuration of. Survey Unit: The Spent .Fuel Pool/Transfer Canal is rectangle in shape and included, Spent Fuel Pit Heat Exchangers, Spent Fuel Pit Pump Rooms and Decon Pit The 617' elevation include the New Fuel Storage Area and 602 ft elevation Mezzanine, Spent Fuel Pool and Cross-town Area and SPING Gallery and after demolition, all that remains. are the basement floor and wall below the 588 grade. The surface area for this survey unit is approximately 7, 783 ft2 or 723 m2
- Performed [] Date:
Walk-Down was: - - - - - - By: (Name)
Not Performed D Reason Walk-Down was not Performed:
Observed or Potential Hazards:
D -Heat stress or stroke D -Confined Spaces D - Kinetic energy sources (moving equipment) o*-Cold work environment D -Hazardous atmospheres D -Stinging insects D -Load bearing stresses D - Vehicle traffic D -Hazardous plants and/or iXj - Lack of structural integrity LJ - Overhead piping or animal (structure, floor) components l2SI - Tripping hazards D - Exposed electrical circuitry D -Standing water > 1ft deep D -Release of stored energy l2SI - Sharp objects or surfaces sources (hydraulic, steam, etc.)
l2SI -Fall hazards D - Falling objects D -Work @ height > 6ft D -Buried utilities D - Other _ _ _ _ _ __
l2SI - Open excavations . D -Overhead power lines D- Other - - - - - - - -
(Each hazard identified must be evaluated to determine if the hazard can be eliminated, avoided, or minimized, as well as the need for additional support/expertise)
Hazard(s) Mitigation Measures:
Attachment 6 ZS-LT-100-001-001 Survey Unit Pre-Characterization Walk-Down Revision I Page 2 of2 Information Use Survey Unit Preparation for Characterization:
D -Mark reference grid D -Clear vegetation D - Set-up Man Lift D -GPS D -Confined space permit D - Extension poles D -Mark survey unit boundaries D -Set-up Temporary Ventilation IZl - Equipment Set-up D -Clear equipment and/or tools IZJ -Radiation Work Permit D- Other ~------~
D -Clear loose material and/or D -Erect Scaffolding debris Preparation Details:
Survey Unit Classification:
Initial Classification: Non-Impacted D Class 3 D Class 2 D Class 1 [?SI If the Survey Unit is a Class 2, Class 3 or Non-Impacted Survey Unit?
- a. Are there any posted Radiologicaily Controlled Areas in the survey unit? Yes [?SI No D Investigation:
- b. Is there any posted Radioactive Material Areas or lab<;:led, tagged or bagged m
radioactive material or potential radioactive material the survey unit? Yes [?SI No D Investigation:
- c. Is the survey unit in the path of a known transport route for unpackaged radioactive materials? Yes D No~
Investigation:
- d. Is there any observable evidence of any past remediation activities within this survey unit? Yes IZl No D Investigation:
The initial classification for this survey unit was Class 1
-- - - - . Based upon the visual observations of the walk-down, the initial classification of this survey unit is: ~ is justifiedO is not justified.
Submitted: Reviewed:
Name/Date Name/Date
Attachment 7 ZS-LT-101-001-001 Survey Package Cover Sheet Revision 1 Information Use GENERAL SECTION Sample Plan #: 1 IsurV"e""y-Area No.: 03000 ISurvey Ui-tit No~-;03201 --*-*
rSmvey I
u~it'N~~= SFP/T;~f~;c~~f'--**--*-**-*-*--------*--*----*----------***--*-*-------****--*----
rsnrvey Unit Type: . . --,***-..--.. . . . . . . . . .-
l--- -*--------------'---------'
0- Open Land ~- Structural Interior D- Structural Exterior D- System Initial.Classification: D - Non-Impacted D - Class 3 D - Class 2
- IZ! -Class 1 PREPARATION FOR CHARACTERIZATION ACTMTIES Reference Grid and/or Reference Coordinates have been established (if appropriate).
D (check box signifies affirmative response) IZI Not Applicable A walk-down has been performed of the Survey Unit and a completed Survey Unit Pre-Characterization Walk-Down is included with this survey package. D Not Applicable D (check box signifies af:firtnative response)
All survey preparation activities (clear vegetation, erect scaffolding, etc.) as identified by the Sun,ey Unit Pre-Characterization Walk-Down have been completed.
D (check box signifies affirmative response) D Not Applicable Area has been cleared of all non-essential materials and equipment.
D (check box signifies affirmative response) . D Not Applicable COMPLETE PRIOR TO COMMENCING SURVEY SURVEY PACKAGE APPROVAL Prepared: Patsy Giza Date: 3/:J.if 13-(Name) 1 . I Peer Review: f?_, F. yeit~-vjjI_
(Name)
- Date: 3/i1b1 Approved: tf?y~e/Z Date: . ~h'.//
Characterization/License Termination Manager
Attachment 8 ZS-LT-100-001-001 Characterization Data Quality Objectives and Survey Design Revision 1 Information Use Survey Unit No: ~0~3~2~0=-1_ _ _Sample Plan #~1_ _ __
Survey Unit Description Survey Area No.: - 03000
Description:
SFP/Transfer Canal Survey Unit No.: _0_3_2_0_1_ __
Description:
Concrete Surfaces below 588 ft elevation Survey Unit Type:
0-0penLand ~- Structural Interior D- Structural Exterior 0- System Survey Unit Area: 723 square meters Survey Unit Classification:
Initial Classification: D - Non-Impacted D - Class 3 0 - Class 2 ~ - Class 1 Description of Survey Unit Boundaries, Physical Conditions~ Orientation and Landmarks: The Spent Fuel Pool (SFP)/Transfer Canal is rectan'.gle in shape. The SFP/Transfer Canal, prior to decommissioning included the Trackway/Car Shed/Open Area, Spent Fuel Pit Heat Exchangers, Spent Fuel Pit Pump Rooms and Decon Pit on the 617' elevation which include the New Fuel Storage Area and 602 ft elevation Mezzanine, Spent Fuel Pool and Cross-town Area and SPING Gallery. The SFP/Transfer Canal concrete (below 588 foot elevation) is all that remains after the completion of open air demolition and removal *of the steel liner. The Basement floor and wall surface area for this survey unit is approximately 7, 783 ft2 or 723 m 2 Types of Surfaces: Composition of Surfaces: Types of Media:
~-Floor ~-Concrete D - SUrface Soil
~-Wall 0 - Steel
- D- Subsurface Soil 0 - Ceiling 0 - Cinder Block 0 - Sediment .
0-Roof 0-Brick 0 - Water D - Paved Road 0-Tile D *-Liquids (not water) 0 - Concrete Pad 0-Wood 0-0il 0-Gromid 0-Asphalt ~ - Volumetric Concrete 0 - Surface Water 0-Tar 0 - Volumetric Asphalt D- System 0-0ther - - - - - - - - 0-Metal 0 - Other _ _ _ _ _ __ 0 - 0ther - - - - - - - - 0-Paint.
0 - Other _ _ _ _ _ __ 0-0ther - - - - - - - - 0 - Other _ _ _ _ _ __
Survey Unit Historical Information Previous operational functions: Spent Fuel Pool is a 40 foot deep pool that contained the storage racks for the spent fuel assemblies. It is isolated from the Containment by a flange in the Transfer Canal, which was used to transfer spent nuclear fuel between Fuel Building and Containment. Stainless steel racks with borated poly(or similar material) were used to store each spent fuel assembly. The racks were approximately 16 feet high. A bridge crane was used for moving spent fuel into the storage racks 1 Page 1 of5
Attachment 8 ZS-RP-107-001-001 Characterization Data Quality Objectives and Survey Design Revision 0 Information Use Survey Unit No: _0~3_2~0_1-~-Sample Plan #--"-1_ _ __
- Basis for initial classification: The Zion Station Historical Site Assessment (RSA) - September 2006 classified the Fuel i-Iandlirig Building 617' Pool, New Fuel Storage Areas, 592' Decon Pit, Fuel pit Pump RM, Spent Fuel Pit Heat Exchangers, as Class 1.
Summary of processes and incidents from Historical Site Assessment: Fuel pool was originally built to hold 340 spent fuel assemblies. Later modifications upgraded the storage to 868 (in 1976), to 2112 (in 1981).
Two documented overflows of the pool occurred. The first on 4117/1991 and the second on 8/24/1994.
Interview information noted a fire in the transfer canal area in 1971 (pre-operational), .and potential leakage path via pool leakage "tell tales". Although the pool is lined, some po.tential exists for contaminants (particularly tritium) to have migrated to subsurface soil adjacent to the pool.
SURVEY DATA: 01/1999. -1 mR/hr Gen. Area, -3K dpm/100 cm2 Summary of Current Radiological Condition: Three (3) Concrete core samples were previously obtained in the Spent Fuel Pool, two on the wall and one on the floor. The analysis of these samples indicated a maximum Cs-137 of 4.84 pCi/g and a maximum Co-60 concentration of3.73 pCi/g.
- Data Quality Objectives:
- 1. State the Problem: Validate that the current Radionuclides of Concerns (ROC), radionuclide mixture and insignificant radionuclide dose contribution applicable to the SFP/Transfer Caria! is appropriate by perform continuing characterization surveys to quantify the contamination of structural concrete exposed by the removal of the steel liner. This survey plan pertains to the Spent Fuel Pool and Transfer Canal co:n,crete floor and walls inside the Fuel Handling Building 592 ft. el. that is below 3 feet grade and will be subjected to FSS.
- 2. Identify the Decision: Identify locations on the concrete floor where physical and radiological conditions are conducive to fixed and/or volumetric contamination of the concrete media. Take.concrete core samples at the locations identified
- 3.
- Identify Inputs:
- a. Can the objectives of the characterization survey be achieved with reasonable confidence based on existing data? (If "Yes, then document the basis for the Yes D No [ZI acceptability of the data.)
Basis: NIA
- b. Identify the Action Levels from Attachment 1 that will be used for the characterization of this survey unit.
~ Isotopic Volumetric D Gross Surface Activity D Detectable Activity> Background
/
Page2 of5
Attachment 8 ZS-RP-107-001-001 Characterization Data Quality Objectives and Survey Design Revision 0 Information Use Survey Unit No: _0"'"'3~2~0~1_ _ _Sample Plan #---=-1_ _ __
- c. Identify the types of measurements and/or sample to be taken for the characterization of the survey unit.
- D Surface Soil Sample(s) D Swipe Sample(s)
D Subsurface Soil Sample(s) D Direct beta-gamma measurement(s)
D Sediment Sample(s) D Direct alpha measurement(s)
~ Concrete Core Sample(s) . ~Surface Scans (structures)
D Volumetric Concrete Sample(s) D Surface Scans (soils)
D Volumetric Asphalt Sample(s) D Other ~----------'-----
D Water Sample(s) 0 Other - - - - - - - - - - - - -
- d. Designate the radiological instrumentation that will be used to acquire field measurements and denote the anticipated static and scan MDC for each.
NOTE: Static and Scan MDC for scanning structures and soil will* be determined in accordance with the guidance provided in Attachment 5.
Instrument Type: Detector Type: Static MDC: co Scan MDC:
Ludlum Model 2360 Ludlum 43-93 1, 114 dpm/l 00cm2 3,808 dpm/100cm2 c2i 2 Ludlum R0-2 NIA NIA NIA 3
(1) Based on t, = 1 min, th= 5 min, 81 = 0.235, 8s = 0.25 and Rb= 300 cpm (2) Based on i = 1.37, p = 0.5, d' = 1.38, 8; = 0.235, 8s = 0.25 and Rb= 300 cpm Are the static and scan MDCs for the instruments and detectors listed above less than the Action Levels selected? (If "No", then document the reason why the instrument will continue to be used for this survey and the impact on data.
quality.) Yes D No D Explanation: NiA
- e. Determine the type of analyses that will be performed on volumetric material sample(s). NIA Analyses D Gross Beta Gamma D Gross Alpha ~ Gamma Spectroscopy D Liquid Scintillation D Alpha Spectroscopy
- 1. Each Yz-inch concrete .core puck will be analyzed by the on-site RCA radiological laboratory by gamma-spectroscopy on each side for plant-derived gamma emitting radionuclides.
- 4. Define the Study Boundaries:
- a. Specify the number of judgmental measurements and/or samples that will be taken in this survey unit to adequately address the objectives of the survey (SeeAttachment2).
Surface Soil Sample(s)
--- Subsurface Soil Sample(s)
--- Water Sample(s)
Swipe Sample(s)
--- Sediment Sample(s) --- Direct
--- --- Direct beta-gamma measurement(s) 5
--- Concrete Core Sample(s)
Volumetric Concrete Sample(s)
--- Other alpha ineasurement(s)
--- --- 0ther ---~-~--~---
--- Volumetric Asphalt Sample(s)
Page 3 of5
Attachment 8 ZS-RP-107-001-001 Characterization Data Quality Objectives and Survey Design Revision 0 Information Use Survey Unit No: _0=3~2~0~1_ _ _ Sample Plan #--=-1_ _ __
- b. Designate the locations of the judgmental samples and the location coordinates on Attachment 11, "Sample/Measurement Identification and Coordinates" and on the survey map. NIA
- c. Explain the basis for the .determination of the judgmental measurement and/or sample population size and the selection of the measurement and/or sample locations.
- Basis: A scan survey will be performed on the floor and walls of the SFP/Transfer Canal. The floor surface that exhibits the highest fixed contamination level will be identified and marked. The identified location will represent radiological conditions that are conducive to fixed and/or volumetric contamination of the concrete media. A concrete core sample will be taken at this location
- 5. List Decision Rules to be used for this Survey Package:
"If' "Then" 1 Scan indicates th.e location of the maximwn Mark as a potential location for acquisition of observed scan measurement concrete core sample 2 Visual observation of floor surface indicates Mark as a potential location for acquisition of potential locations of surface contamination (such concrete core sample as discolorations, cracks, standing water) 3 Gamma Spectroscopy analysis of concrete core Establish distribution ratios for the quantified samples indicates the presence of plant-derived gamma-emitting radionuclides of concern.
radionuclides greaier than MDC 4 Gamma Spectroscopy analysis of concrete core Perform additional off site analysis to quantify samples indicates the presence of plant-derived concentrations of the Hard-to-Detect (HTD) beta radionuclides greater then MDA and alpha emitting radionuclides
- 6. Specify Limits on Decision Errors:.
This survey package is dedicated to the acquisition of surface scan measureinents on the floor and foundation walls of the Spent Fuel Pool and Transfer Canal. . Concrete Cores will be collected for gamma spectroscopy and analysis for HTD radionuclides
- 7. Optimize the Design for Obtaining Data:
- a. Designate the scan coverage requirements for this survey unit.----------------------------- See Basis Page4 of5
Attachment 8 ZS-RP-107-001-001 Characterization Data Quality Objectives and Survey Design Revision O Information Use Survey Unit No: _0~3_2_0_1_ _ _Sample Plan #~1_ _ __
- b. Is less than 100% scan coverage required? Yes D No 1:8:1
- (If "Yes", then designate the areas to be scanned using the reference coordinate system that equates to the required total area that is to be scanned and document below the basis of why that area was selected.)
Basis: Areas on the floor and foundation walls of the area that exhibit a high probability of surface contamination, based upon physical configuration (i.e. drainage pathway), visual observation (i.e. standing water on the floor) or radiological posting or markings will be scanned. The
- location exhibiting the highest surface contamination level on the floor and the foundation walls will be identified as a potential location for the acquisition of a concrete core sample.
The identified sample location will be marked accordingly. The floor and foundation walls
\
will be scanned with a Ludlum Model 2360 paired with a Model 43-93 detector or Ludlum
.R0-2
- c. Designate the locations of the scan areas and the location coordinates on Attachment 12, "Scan Area Identification and Coordinates" and on the survey map. NIA
- d. Establish a priori alarm set-points and/or action levels for scanning.
D Structures (beta-gamma) 570 cpm (assuming observed mean background of300 cpm plus 2cr) units 0 Open Land (gamma)
- 8. Additional Comments:
- 1. Adjust beta-gamma a priori alarm set-point (in cpm) using the mean observed background in
- ~:.~~:::~:::[(:~(:::.. *~:,,=* H Survey Design Review Prepared by: Patsy Giza (Print Name)
Peer Reviewed by: 12*f, 'Jetf *w BY' (Print Name)
Page 5 of5
Attachment 9 . ZS-LT-100-001-001 Survey Instructions Revision 1 Infonnatio:p Use Sample Plan No.: _1--~--
Survey Area No.:. _0_3_0_0_0_ __
Description:
SFP/Transfer Canal Survey Unit No.: _0_3_2_0_1_ __
Description:
Concrete Surfaces below 588 ft elevation Survey Unit Type:
. D - Open Land ~ - Structure Interior D - Structure Exterior D- System
. Survey Unit Classification:
Initial Classification: D . Non-Impacted D - Class 3
- 0- Class 2 ~ - Class 1 General Instructions:
- 1. Personnel will follow all relevant safety directives and procedures while performing this work. .
- 2. Survey and sampling will be perfonned by qualified technicians under the direction of Characterization/PSS Supervision.
- 3. Instrumentation used in the field will be used in accordance with applicable procedures.
4.* Detailed field notes and observations will be documented during survey and sampling.
- 5. Photographs should be taken as necessary to clarify survey and sampling activities or survey constraints.*
- 6. Samples will be controlled and documented in accordance with procedure Characterization Sample Media Collection
- 7. Documents generated during the performance of survey and sampling will be complete and legible.
Cmrections will be made using a single line-out followed by an initial and date.
- 8. Sample & measurement locations will be identified using coordinates consistent with the established reference coordinate system. Sample and measurement locations will be identified by marks or flags prior to and during survey implementation.
General Instructions Page 1 of 1*
Attachment 9 ZS-LT-100-001-001 Survey Instructions Revision 1 Information Use Sample Plan No.: 1
--~~--
Survey Area No.: -03000
Description:
SFP/Transfer Canal
.Survey Unit No.: 03201
Description:
Concrete Surfaces below 588 ft ele'vation Specific Instructions:
I. Proceed to the survey unit.
- 2. Initialize.and utilize a "Field Log" document.
- 3. Enter the Fuel Handling Building on' the 592 ft. elevation
- 4. Evaluate the.exposed concrete .surfaces of the Spent Fuel Pool and Transfer Canal for potential locations for core sample acquisition.
- 5. Using a Model 2360 data logger paired with a Model 43-93 detector, scan all floor surfaces and walls that
- are accessible from the bottom of the SFP or Transfer Canal, concentrating on any areas with visual cues (i.e. floor discoloration, cracks in the concrete, the presence ofstanding water, etc ... ), areas with markings or postings indicating possible fixed.contamination. Denote the scan results in the Field Log (Hand Written).
- 6. Select and mark any potential concrete core sample locations based upon the highest scan reading obsented in the area.
- 7. Mark the selected potential location surfaces using an indelible marker *or marking paint. Denote the observed scan results on the concrete surfaces next to each potential sample location.
- 8. Take a digital'photograph of each sample location after it is marked.
- 9. Generate a map of the area and document the location of each potential sample location marked and the observed scan reading at that location.
I 0. Set-up core drill at the selected locations. Acquire a 6 inch core sample from the selected location using a 3 inch core bit.
- a. If a core breaks either during coring or extraction, ensure that the core markings as specified in step
- 11 are accomplished as well as the marking of both sides of the break with the depth of the break (e.g.
1.25 in.).
- 11. Using an indelible ink marker, mark the top ofeach concrete core sample as "O in" and mark the bottom of each concrete core sample as "6 in". Mark the sample ID number on the side of the core. Place the concrete cores in individual plastic bags and seal and label the bags as necessary.
- 12. Transport the core samples to the area set-up for concrete core preparation.
- 13. Cut a %'-inch concrete puck from the top of each concrete core using a concrete saw. The top of each puck should already be labeled as "O, in". Mark the bottom of each 112-inch puck as '% in" ..
- 14. Dry the concrete puck. Using a Ludlum Model 2360 paired with a Model 43-93 detector, scan the bottom (marked "112 in") of the puck and the top (also marked "112 in") of the remaining core. If elevated activity in excess of the beta-gamma alann set-point based on the mean observed background (see calculation in section 8 of the survey design) is observed, then cut a second 112-inch concrete puck from the core. The bottom of the second core would be lab.eled as "l in". Repeat the process until no elevated activity is
.detected by the scan.
Specific Instructions Page 1 of 1
Attachment 9 ZS-LT-100-001-001 Survey Instructions Revision I Information Use
- 15. Place all the~-inch concrete core pucks in individual plastic bags and seal and label each of the bags accordingly. * *
- 16. Complete a chain-of-custody fonn for the remainder of each concrete core saniple in accordance with procedure ZS-WM-131, "Chain-Of-Custody" (Reference 6;7).
- 17. Transport the concrete core pucks to the on-site laboratory for analysis by gamma spectroscopy.
- a. Weigh each puck segment to the nearest 0.1 grams. If portions ofrebar are imbedded, they should also be included. * *
- b. Analyze the top and bottom of each concrete puck on the characterized gamma spectroscopy system taking in account the density and geometry of the segments by using the geometry composer software feature. Activity results should be provided as in pCi/g or µCi/g units and reported by the sample ID number follow~d by the depth that the puck face represents.
- 18. All concrete samples taken as a result of this survey package will be placed in a secured storage location for future additional analysis:
Specific Instructions Page 1 of 1
Attachment 10 ZS-LT-101-001~001 Field Log Revision 1 Information Use Sample Plan No.: - - - -
Survey Area No.: -03000
Description:
SFP/Transfer Canal Survey Unit No.: 03201
--~---
Description:
Concrete Surfaces below 588 ft elevation Field Log: Date:
Observation or Comment: Technician Field Log Page 1 of _ _