ML23011A338
| ML23011A338 | |
| Person / Time | |
|---|---|
| Site: | 07201026 |
| Issue date: | 09/30/2022 |
| From: | Westinghouse, Westinghouse |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| LTR-NRC-22-38 | |
| Download: ML23011A338 (1) | |
Text
{{#Wiki_filter:Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Enclosure 1 Supplemental Response to NRC RAI A-RCS1 (Non-Proprietary) September 2022 (122 pages including this cover page) Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, PA 16066
© 2022 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 2 of 122 FuelSolutions Certificate of Compliance (CoC) No. 1026 Renewal Application Supplemental Response to NRC RAI ARCS1 Justify the use of the 5year Technical Specification radiation survey frequency.
Background:
On August 15, 2022, the NRC staff and Westinghouse held a discussion regarding the initial Westinghouse response to the first FuelSolutions CoC 1026 Renewal Application NRC Request for Additional Information. With respect to the Westinghouse response to Request for Additional Information RAI ARCS1, the NRC staff asked Westinghouse to provide supplemental information regarding the proposed use of a fiveyear frequency for performing cask concrete radiation surveys on exposed (unencased) cask concrete areas as described in FuelSolutions Technical Specification 5.3.5, Cask Surface Dose Rate Evaluation Program. The Technical Specification 5.3.5 cask concrete gamma and neutron radiation surveys were initially intended to be a onetime only survey of each newly loaded FuelSolutions cask to verify that the cask was properly loaded and had surface concrete gamma and neutron dose rates within the acceptance criteria established in accordance with FuelSolutions Technical Specifications 5.3.5.1, 5.3.5.2 and 5.3.5.3. Attachment A to this supplemental response is the Big Rock Point (BRP) Technical Specification 5.3.5 Procedure No. DFSISFSl2 Perform Final Dose Rate Survey which documents BRP cask concrete gamma and neutron radiation dose rate compliance with the Technical Specification 5.3.5 Acceptance Criteria for each of the eight currently loaded FuelSolutions Storage Casks, Serial Nos. 210, 310, 410, 510, 610, 710, 810, and 110. (Cask 110 only contains Greater Than Class C [GTCC] Waste and has no neutron source material). The Technical Specification 5.3.5 Acceptance Criteria for each loaded cask can be found on Page 13 of 13 of each loaded cask data set which are contained in Procedure No. DFSISFSl2. FuelSolutions Storage Cask Concrete Radiation Surveys Conducted During the Past Twenty Years In addition to the Technical Specification 5.3.5 cask concrete radiation surveys conducted on each newly loaded cask in 2002 and 2003, annual cask concrete gamma radiation surveys have been conducted for each year following cask loading, including the most recent survey in 2022. These annual cask concrete radiation surveys are conducted as part of an overall annual BRP ISFSI area radiation survey. The results of the most recent four years of BRP ISFSI radiation surveys are included in Attachment B to this supplemental response. The overall ISFSI survey results are briefly described on Page 1 of 14 of each annual ISFSI radiation survey report, and the oncontact cask concrete gamma radiation survey measurements of the cask sidewall and lower vent areas are contained on Page 4 of 14 of each annual ISFSI radiation survey report. The annual oncontact cask concrete gamma radiation survey results are consistent with the original Technical Specification 5.3.5 cask concrete gamma radiation survey results at the same cask sidewall and lower vent locations. There are some minor year to year measurement variations mostly due to different radiation instruments and calibrations sources being used during the twenty years. There are 1 of 3
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 3 of 122 no discernable trends in the measurement results. The measured cask sidewall and lower vent gamma radiation dose rates are small (well less than 10 percent) compared to the original acceptance criteria established for these locations in FuelSolutions Technical Specifications 5.3.5.1, 5.3.5.2 and 5.3.5.3 as found on Page 13 of 13 of each loaded cask data set in Attachment A. In addition to the annual concrete cask and ISFSI area gamma radiation surveys, there have been occasional neutron radiation surveys. As shown in the Attachment A neutron radiation survey measurement results for each newly loaded cask, the cask concrete sidewall neutron radiation levels are smaller than the measured gamma radiation levels at each sidewall location. Therefore, the occasional neutron radiation surveys have focused on the cask vent areas. Attachment C to this supplemental response shows the results of a typical cask vent neutron radiation survey. NRC Cask Radiation Survey Guidance The original NRC RAI ARCS1 referenced Study of the ACI 349.3R02 Tier 2 Criteria Impacts on Dose Rates for Several Spent Nuclear Fuel Dry Storage System Designs (ML19072A031). RAI ARCS1 asked whether or not the ACI 349.3R Tier 2 visual acceptance criteria are sufficient to ensure the FuelSolutions cask concrete shielding effectiveness function is adequately maintained based on the radiation decay calculations considered in the case study. If the dose rates after 20 years of storage with the degradation allowed by the ACI 349.3R Tier 2 criteria (as evaluated in study analysis) do not exceed the design basis dose rates (which would be the dose rates at the time of loading), then the evaluation of compliance with 10 CFR 72.104 in the FSAR remains valid and bounds the system's performance during the period extended storage with the AMPs only relying on the ACI 349.3R Tier 2 criteria as acceptance criteria. Answering that question assumes that the design basis dose rates are derived from the analysis in which the technical specification dose rate limits were derived. The analysis would also support the evaluation of compliance with 10 CFR 72.104, in accordance with the requirement in 10 CFR 72.236(d). Westinghouse decided that the case study analysis did not support the use of the ACI 349.3R02 Tier 2 Criteria for the FuelSolutions cask shielding effectiveness adequacy determination. Instead, Westinghouse proposed going back to the acceptance criteria established in FuelSolutions Technical Specifications 5.3.5.1, 5.3.5.2 and 5.3.5.3 which is based on Sargent and Lundy Calculation Package, Number R1088101, Dose Rates in the Vicinity of the Big Rock Point ISFSI as cited in Attachment A. Technical Specification Radiation Survey Frequency The key question then is how frequently to perform the cask concrete radiation surveys on exposed (un encased) cask concrete areas as described in the FuelSolutions Technical Specification 5.3.5, Cask Surface Dose Rate Evaluation Program. Based on the twenty years of annual cask concrete radiation surveys which have been conducted as part of the overall annual BRP ISFSI area radiation survey, the cask concrete shielding effectiveness has not degraded in anyway during the past twenty years. By reintroducing the use of the FuelSolutions Technical Specification 5.3.5, Cask Surface Dose Rate Evaluation Program, with a frequency of every five years starting within one year after renewal of the FuelSolutions CoC 1026, the more thorough un 2 of 3
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 4 of 122 encased concrete radiation surveys, both gamma and neutron, would be implemented to enhance the ongoing annual cask concrete radiation surveys. The Technical Specification 5.3.5 surveys include eight cask side wall survey locations which are averaged to compare to the Technical Specification 5.3.5 Acceptance Criteria. (The annual BRP cask radiation survey includes only four side wall survey points.) Both gamma and neutron surveys would be performed at the fiveyear frequency. No reductions in the scope or frequency of the annual BRP ISFSI area radiation surveys are proposed or planned. This approach and frequency would assure that the baseline cask concrete shielding effectiveness back to the Technical Specification 5.3.5 Acceptance Criteria is maintained during the period of extended cask storage. Based on twenty years of BRP cask concrete shielding effectiveness surveys, there is no indication of FuelSolutions cask concrete deterioration at a rate that would require a more frequent application of the Technical Specification 5.3.5 surveys. The proposed FuelSolutions cask concrete shielding effectiveness AMP requirements and frequency have been previously drafted and submitted in accordance with these considerations. Attachment A: Big Rock Point Technical Specification 5.3.5 Procedure No. DFSISFSl2, Revision 0, Perform Final Dose Rate Survey. Attachment B: Big Rock Point Cask Concrete Radiation Survey Data 2022, 2021, 2020 and 2019. Attachment C: Big Rock Point Cask Vent Neutron Radiation Survey 2010. 3 of 3
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 5 of 122 Attachment A to Supplemental Response to NRC RAI ARCS1 Big Rock Point Technical Specification 5.3.5 Procedure No. DFSISFSl2, Revision 0 Perform Final Dose Rate Survey (65 pages including this coversheet)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 6 of 122 BIG ROCK POINT NUCLEAR POWER PLANT PROCEDURE APPROVAL AND AUTHORIZATION Procedure No. Rev No. 0
-DFS-ISFSl-2 Procedure
Title:
PERFORM FINAL DOSE RATE SURVEY TECHNICAL SPECIFICATION 5.3.5 CURRENT REVISION STATUS Author WEEllman Date 07/18/02 Quality Review Form No. 218-02 APPLICABILITY ISSUE HISTORY Revision No. _ _ _ _ _ _ _ Date _ _ _ Quality Review Form No. _ _ __ Approved for use Procedure Sponsor/Designate':::::; Sb' z *~"""--::.,.---, Authorized Period of Use _J~u=-ly~18:::....,.,-=2c..;;:.0....:..0=2_ _ _--'t-'--'-hr'"""o-"'"u"""gh'-'--J.c._;u=-ly~18=,-=2=0=0....:..4_ _ __ BEFORE USING THIS PROCEDURE FOR WORK ACTIVITIES, VERIFY WITH THE RESPECTIVE PROCEDURE CONTROLLING DEPARTMENT THERE ARE NO OUTSTANDING TEMPORARY CHANGES When applicable: PROCEDURE IMPLEMENTATION HISTORY Reviewed for System or Component Operability Performed by C Method of Verification Title D Functional Test
\ ~ \ \ \..(_'i:> L \ ~~ o PJll/Sical Inspection Date Time ~dministrative Review AMMS WORK ORDER NO. (if applicable) _ _ _ _ _ _ _ _ _ _ _ _ __
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Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 7 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 1 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date 1.0 PURPOSE AND SCOPE 1.1 PURPOSE The purpose for evaluating the Storage Cask surface dose rates is to assure that the Independent Fuel Storage Installation (ISFSI) does not violate the requirements of 10CFR72 and 10CFR20 regarding radiation doses and dose rates. The dose rate limits are used to identify Casks which could cause the regulatory limits to be exceeded. 1.2 SCOPE This procedure is conducted for each Storage Cask following its placement on the ISFSI pad. Based on Big Rock Point (BRP) Plant Manual Volume 31, Dry Fuel Storage Technical Specifications, Section 5.3.5.4, these measurements need to be completed within 12 hours following placement of the Storage Cask on the pad.
2.0 REFERENCES
AND ATTACHMENTS
2.1 REFERENCES
- a. BNFL FuelSolutions' Storage System Final Safety Analysis and Review (SAR) WSNF-220
- b. Big Rock Point Plant Manual, Volume 31, Dry Fuel Storage Technical Specifications, Section 5.3.5, Cask Surface Dose Rate Evaluation Program
- c. RP-29, Radiological Surveys
- d. Sargent and Lundy Calculation Package, Number R-10881-01, Dose Rates in the Vicinity of the Big Rock Point ISFSI r i r 1 c1 ci !'~ *f 1 * ::-: fJ ;:.i !: ; :::; r:i DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 8 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 2 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date
- e. Westinghouse Design Analysis Report (DAR)
Number CMPC.1503.003
- f. BNFL FuelSolutions' Calculation Package, CMPC.1503.004, Storage Operations Occupational Exposure Estimate
- g. DFS-STAG-13, W150 Storage Cask Preparations for Canister Loading 2.2 ATTACHMENTS
- a. Attachment 1, W150 Storage Cask Dose Rate Survey Sheet
- b. Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria 3.0 RESPONSIBILITIES Personnel performing a task in this procedure are qualified per DFS-PROJ-1, Cask Loading Sequence/Project Requirements.
The following personnel are required in this procedure:
- a. Radiation Protection (RP) Technician
- b. Radiation Safety Supervisor (RSS)
- c. Dry Fuel Storage (DFS) Manager
- d. DFS Field Supervisor 4.0 PREREQUISITES
- a. A ladder, scaffolding, or other means is available at the ISFSI to reach Storage Cask top and Outlet Vent screens to perform the dose rate survey. j/
(RP)~ /)/)~()J-( i 1:1 ( ! ( i DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 9 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 3 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date
- b. Calibrated survey instruments (gamma and neutron).
(RP)-dl~y c. d. A calculator is available for averaging and adding dose rates. The DFS Manager has determined that this procedure is (RP) ~ w-ready to be performed per DFS-PROJ-1, Cask Loading I Sequence/Project Requirements and has given permission to proceed with the procedure. (DFS Manager)~ f1*\l. .. oL-5.0 PRECAUTIONS AND LIMITATIONS
- a. Survey is to be performed within 12 hours of placement at the ISFSI.
- b. Radiation doses at the Outlet Vents could exceed 80mrem/hr (Administrative HRA); use ALARA principles and caution while working in these areas.
- c. When working aloft, the BRP Accident Prevention Manual requirements shall be followed.
6.0 PROCEDURE
- a. Record on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet, Part a, the Storage Cask serial number and the date/time the Cask was placed in its storage location on the ISFSI pad.
---zfl iltlfV
,4 (RP)
DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 10 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 4 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date
- b. Obtain eight neutron and eight gamma contact dose rate measurements from eight equally spaced locations around the circumference of the Storage Cask, approximately six feet from the bottom, and record them on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet, Part b. These points should have been previously identified on the Cask during completion of DFS-STAG-13, W150 Storage Cask Preparations for Canister Loading.
(RP)#-- /!
- c. Calculate the average Cask vertical surface neutron and gamma dose rates by summing the eight dose rate values and dividing by eight. Record the average values on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet. Compare the average values against the criteria in Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
Less than Acceptance Criteria? YES V/ NO If Yes, continue with Step 6.0.d; if No, stop and notify the RSS and DFS Manager. (RP) --iJf!2 /Ut-o
- d. Determine the total average Cask vertical surface dose
_ rate by adding the average neutron and gamma dose rates and record on Attachment 1 , W150 Storage Cask Dose Rate Survey Sheet. Compare against the total maximum acceptance criteria in Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria. Less than Acceptance Criteria? YES NO If Yes, continue with Step 6.0.e; if No, stop and notify the RSS and DFS Manager. DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 11 of 122 DFS-ISFSl-2 Revision O PERFORM FINAL DOSE RATE SURVEY Page 5 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date
- e. Obtain neutron and gamma dose rate measurements from each of the four Inlet and four Outlet Vent screen surfaces and record them on Attachment 1, W150Storage Cask Dose Rate Survey Sheet, Part c.
-4 (RP)~ /lll
- f. Calculate the average Outlet and Inlet Vent screen dose rates for gamma and neutron by summing the four dose rate values corresponding to Inlet or Outlet and dividing by four. Record the average values on Attachment 1, W150 Storage Cask Dose Rate Survey sheet. Compare these average values for neutron and gamma against the acceptance criteria in Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
Less than Acceptance Criteria? YES V NO If Yes, continue with Step 6.0.g; if No, stop and notify the RSS and DFS Manager. (RP) -1,L _/l_*OZ-
- g. Determine the average total dose rate for the four Inlet and the four Outlet Vent screens by adding the average neutron and average gamma dose rates and record on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet. Compare against the total maximum acceptance criteria in Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
Less than Acceptance Criteria? YES NO If Yes, continue with Step 6.0.h; if No, stop and notify the RSS and DFS Manager. DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 12 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 6 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date
- h. Obtain five neutron and five gamma measurements from the surface of the Storage Cask top lid and record them on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet, Part d. One measurement is from the center and the other four taken at equal spacing 30 inches from the center. These points should have been previously identified on the cover during completion of procedure DFS-STAG-13, W150 Storage Cask Preparations for Canister Loading.
Vi (RP)#-
- i. Calculate the average neutron and gamma dose rates by summing the five dose rate values and dividing by five and record them on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet. Compare against the maximum acceptance criteria in Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
Less than Acceptance Criteria? YES v NO If Yes, continue with Step 6.0.j; if No, stop and notify the RSS and DFS Manager. (RP)_,_ _ _
- j. Determine the total average Cask Lid surface dose rate by adding the average neutron and gamma dose rates and record on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet. Compare against the total maximum acceptance criteria in Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
Less than Acceptance Criteria? YES NO If Yes, proceed to Step 6.0.k; if No, notify the RSS and DFS Manager. f ! CI (! ( ! ( *1** ::-; ( t ::- 1
~:, ::-~
1 DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 13 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 7 of 13 TECHNICAL SPECIFICATION 5.3.5 lnit Date
- k. Ensure meter serial numbers and calibration due dates have been recorded on Attachment 1, W150 Storage Cask Dose Rate Survey Sheet, Section e.
/'/
(RP)-#-- 7.0 RECORDS AND REVIEWS List any corrective action documents [Work Requests (WRs), Condition Reports (CRs), etc.] issued as a result of this procedure: None 1 (RS Supervisorrdi_/#'1 Administrative Reviews: (DFS Field Supervisor) ..f.ei.) \<--\\1.\o (DFS Manager) ¥-fl** l)
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Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 14 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 8 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 1 W150 STORAGE CASK DOSE RATE SURVEY SHEET NOTE: All surveys to be performed in accordance with RP-29, Radiological Surveys. Acceptance Criteria: See Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
- a. Storage Cask Identification Storage Cask Serial Number W150- J/t) - NMC-Date!Time placed on ISFSI Date /L *IL-ol..---Time /c13o
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage Cask at approximately six feet above the base. Neutron and gamma-ray dose rates are measured and averaged separately (all values in mRem/hr).
Location #1 Location #2 Location #3 Location #4 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma
.L. . /
- z__ --<. I <,/ ,L--
J Location #5 Location #6 Location #7 Location #8 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma
-<. I ., ""-,/
Average Neutron Dose Rate _;:._,_1__ mRem/hr I) ( < 1.1 per Acceptance Criteria) Average Gamma Dose Rate __ , _z-._,_ mRem/hr y ( <48.9 per Acceptance Criteria)
*'7 Total Cask Surface Dose Rate _._._.5_ _ mRem/hr (average neutron+
average gamma) (<50 per Acceptance Criteria) i: I Cl 1: I ( I 1'! *,,* :;: i: I ;:.- !: I *:~! :i DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 15 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 9 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 1 W150 STORAGE CASK DOSE RATE SURVEY SHEET
- c. Inlet and Outlet Screen surface dose rate. Neutron and gamma measured separately.
NOTE: Values for all four Inlet and four Outlet screens should be recorded. Outlet Screen Surface Neutron Gamma North
/
"'::> 3 ,) -* mRem/hr East e 1/7 ~ mRem/hr South ; 3 mRem/hr West ,/ mRem/hr Average Neutron , (i mRem/hr rJ (<17.5 per Acceptance Criteria)
Average Gamma .5. I mRem/hr y (<289 per Acceptance Criteria) Total outlet dose rate J, S'B mRem/hr (<307 per Acceptance Criteria) (Average neutron+ average gamma) ( ! 1: I (I t: ! ,*! *,,* :; : ( ! ;::, !: , *::: ;::, DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 16 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 10 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 1 W150 STORAGE CASK DOSE RATE SURVEY SHEET Inlet Screen Surface Neutron Gamma North I --- mRem/hr East # mRem/hr South
). z- , Z- mRem/hr West J f , mRem/hr Average Neutron _ _ mRem/hr I') (<5.3 per Acceptance Criteria)
Average Gamma_,_mRem/hr y (<14.0 per Acceptance Criteria) Total inlet dose rate , &-'~ mRem/hr (<19.3 per Acceptance Criteria) (Average neutron + average gamma) /. 0 i: I Cl i: I i: I ,*I *,,* l: : i: I ;:-* !: I ':;! :::, DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 17 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 11 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 1 W150 STORAGE CASK DOSE RATE SURVEY SHEET
- d. Five measurements taken on the top lid, with one reading from the center and the other four taken at equal spacing 30 inches from the center. Neutron and gamma measured separately (all values in mRem/hr).
Center Location #1 Location #2 Neutron Gamma Neutron Gamma Neutron Gamma Location # 3 Location #4 Neutron Gamma Neutron Gamma
;3
,./-#'
Average Neutron Dose Rate -*~::>- mRem/hr rJ (<3.2 per Acceptance Criteria) Average Gamma Dose Rate mRem/hr y (<11.5 per Acceptance Criteria) Total Cask Top Dose Rate mRem/hr (average neutron+ average gamma) (<14.7 per Acceptance Criteria) 1: I 1: I ( I ( I ,'.! *,,* ::: 0 ;::,I:,'::! 1') DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 18 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 12 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 1 W150 STORAGE CASK DOSE RATE SURVEY SHEET
- e. Date/Time survey completed: Date ;Z !Z rJ L Time /~ o (Note: This time must be within 12 hours of time/date under Section a of Attachment 1.)
Gamma dose rate meter/serial# /;z_ #(ZS/ Cal. due date 6- ,03 Neutron dose rate meter/serial#" ::j;/:,z r:J/53c: Cal. due date /L-Z7-oZ-
,/
(RP) ~~~::::::=-Date /Z -It:, ,<J 2-- (RS Supervisor) - - - - - - - Date/ :;/1/~ (DFS Manager) ---+-<---_.....,=- Date i 2- - \ t -0 L-DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 19 of 122 DFS-ISFSl-2 Revision 0 PERFORM FINAL DOSE RATE SURVEY Page 13 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 2 W150 STORAGE CASK SURFACE DOSE RATE ACCEPTANCE CRITERIA Big Rock Point Plant Manual Volume 31, Dry Fuel Storage Technical Specifications, Section 5.3.5.1, requires an analysis to confirm that the limits of 10CFR20 and 10CFR72.104 will be satisfied under the actual site conditions and configurations considering the planned number of Casks to be used and the planned fuel loading conditions. This analysis (Reference 2.1.d) was performed by Sargent and Lundy (S&L) to predict the Storage Cask dose rates and dose rates at the ISFSI pad for the planned Cask loadings at Big Rock Point. Although there are only going to be seven Casks containing fuel, the analysis assumes the potential placement of one Cask containing "Greater Than Class C" waste at the ISFSI, which would affect dose rates. Based upon the assumptions and calculations in this analysis, the following W150 Storage Cask surface dose rates were determined and are used as the acceptance criteria in this procedure: Location Gamma Neutron Total Storage Cask Top Cover 11.5 mRem/hr 3.2 mRem/hr 14.7 mRem/hr Cask Vertical Surface @ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50 mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRem/hr Outlet Vent Surface 289 mRem/hr 17.5 mRem/hr 307 mRem/hr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOTE: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit is 50.0 mRem/hr. The gamma and neutron guideline limits for this survey location were established based on percentages from Table 6-3 of the S&L Analysis to meet the 50 mRem/hr cumulative limit.
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Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 20 of 122 CERTIFICATE OF AUTHENTICITY This is to certify that the microphotographic images appearing on this roll of microfilm are accurate reproductions of the records of: Consumers Energy Co., Big Rock Point Plant and were microfilmed in the regular course of business pursuant to established routine company policy for systems utilization and/or for the maintenance and preservation of such records through the storage of such microfilms in protected locations. It is further certified that the photographic processes used for microfilming of the above records were accomplished in a manner and on microfilm which meets the recommended requirements of the Records Management Department for permanent microphotographic reproductions. ~1,:i:00,3 Date~rofilmed Bi2 Rock Point Location
~~J:Jiv A1ltrized Signature
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 21 of 122 DP!te Completed I *.J...I'--<,.) SUBJECT INDEX NUMBEF1S Area and a Systems and/or Administrative Number MUST be Coded Area Svsterns Administrative Equipment Equipment Administrative Area Unit System Number (AREA) (UNIT) (SYSCODE) Classification Number (EQUIPCL) (EQUIPNO) (ADMIN) 71...Jo o~~ J..a ~37~1 .1)
- 39 * /0
- RETENTION J__
(RETEN) _ _ _ _ {Life of the Plant (L), Life of the Company (LC) or Number of Years To Be Retained) Check Appropriate Record Classification: D Safeguards Information D 10CFR2.790(d) Information D Confidential ~ Other - - - - - - - - - - Following Descriptors To Be Indexed Where Applicable - - - - - - - - - Project Name _(3 ___R_P__*~----~r--'-fj_v.._e.._\_S. .fo_~_' . J_(.._____________ (PROJNAM) ArchitecVEngineer Number _ _ _ _ _ _ _ _ _ __ Personal File Number (BECHNO) (PERFIL) Document Name ___,;j)'---F_5_-__,_?_~_0_:fa....-_~_(_____ Sequence Number _ _ _ _ _ _ _ _ _ __ (DOCNAM) (SEQNO) Reference _ _ F_C_-_'7_0_]___________ (REF) Department _ _ J)_ ~ _ _ _ _ _ _ _ _ __
* (DEPT)
Subject c_le._..:..I_ _J+-'_ _...r;;;L~o;;......;..:.R-".-D--.;;;..C-4-y__ _..;:..C'_,:1:J.....:.n-"t~...___,;:'--__.,~_l_ _,___.....c,C_;..tl....S'-t_-_.._17_____ (FRETEXT) (\)~l?p~,~~-* 7 :J ~-*-' Date(s; 02 / ~ (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Organization (FAOMORG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 22 of 122 DfS..ISFSl-2 , *. PERFORM FINAL DQll,,.ll 8U1Y1JY TECHNICAL SPECIF1CA11:JN*a.s~,
...... ~13 ATTACIMNT1 W1§0 §IQMGE CAll(QQIE RATE SURVEY SHEET N~: All Survey8 to be perfonned in accordance with RP-29, Radiological Surveys.
Acceptance Crtlaria: See ~tactwnent 2, W150 Storage Cuk Surface DOie Rate Acolptanoe Crtlerla.
- a. Storage Catk Identification Storage Cask Serial Number W150- 7 / O - ,.JMC Date/Time placed on ISFSI Date 11/ro/o?-
1 I Time /'(/"/
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage Cask at approximately six feet above the base. Neutron and gamma-ray dose rates are measured and averaged separately (all values In mRemlhr).
~ttQn #1 Location #2 Location #3 Location #4 Neutron Gamma Neiisltron Gamma Neutron Gamma Neutron Gamma
- p. o 'L __ . . tJ, o_. . ;,. .I ._i o.o ,;
LOC!11lQ!l. #5 Location #6 Location #7 Location #8 ~eutron ,__Gamma Neutron Gemma Neutron Gamma Neutron Gamma _,2.0 __ . ,;. q.o . ;i. 0,0 ,;J. o.. o ,i Average Neutron Dose Rate *o I mRem/hr I) (<1.1 per Acceptance Criteria) Average Gamma Dose Rate , .?- S mRem/hr r (<48.9 per Acceptance Criteria) Total Cask Surface Dose Rate , a6 mRem/hr (average neutron+ average gamma) (<50 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 23 of 122 c.
,,........,..,,...llfv.
Inlet and OU011*$WJ1ft . . . _ . . . natl. Neutron and gamma NOTE: v.,.. for al four Inlet and four Outlet ICINn a should be reoc:.,rdtld. QvUll §cDen SUrface Neutron Gamma North ,5 y.J. mRem/hr East ,5 1* o mRern/hr South ,5 s.o mRem/hr West _d_ ,_ I* t7 mRem/hr Average Neutror. , 5 mRem/hr 11 (<17.5 per Acceptance Criteria) Average Gamma ,,J. ~ mRem/hr y (<289 per Acceptance Criteria) Total outlet dose rate S. 3 mRem/hr (<307 per Acceptance Criteri a) (Average neutron + average gamma) Ofs-lS FSl-2 .doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 24 of 122 lntlt$nlnk(ace Nlutmr! <;ar;wa North /.0 0, J. mRemlhr East 0,5 02 mRemlhr
/,0 South {),'-/ mRem/hr West O.) o,'-1 mRem/hr Average Neutron . t ~ mRem/hr I) (<5.3 per Acceptance Criteria)
Average Gamma , 3i' mRem/hr y (<14.0 per Acceptance Criteria) Total inlet dose rate /,o, mRem/hr (<19.3 per Acceptance Criteria) (Average neutron + average gamma) DF8-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 25 of 122 d. CIDtlt WIIIWJf1 l#ftltJ
~qamma ~ Gamma NeYffllfJ** .lflnml
,4/ 01' I y O* ,g /.) 5 /, 0 kgcation#3 LgcallonM NfUtrPn Gamma Neutron. (iamma
, '-I /. o ,'-/ O* '8 AveragE, Neutron Dose Rate *5 7 mRemlhr I) (<3.2 per Acceptance Criteria)
Average Gamma Dose Rate
- 1a../ mRem/hry (<11.5 per
~
Criteria) Total Cask Top Dose Rate I,'-/ I mRem/hr (average neutron + average gamma) (<14.7 per Acoeptanoe Criteria) DF8-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 26 of 122
- e. ~f::.!~J!",!(~.,;:i:!:.,
of Attachment 1.) Seclkln
- Gamma doM rate meter/9erial f ...te-2: )6"1' cal. due dale ~rtb 2 Neutron dole rate meter/serial# ¢sl'-l "".us JI/ Cal. due date 1
~,
-1/2,J, (RP) :> Date PV'!'
(RS Supervisor) (DFS Manager) DF8-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 27 of 122
.......,.0 P... 1Sd1S W1 Big Rock Point Plant,..,.,... Volume 31. Dry Fu,I Stora-.;e Technical Speciflcationa.
Seotion 5.3.5.1, ~ an ..,... _, eot'lllrll1 ,that the HmNa of 10CPR20 and 10CFR72.104 Wilbe - - *
- under & . .'.. oonditioM and oont1gurationa considering the plar.,eciflUIJk of c.kt,to ...... and the planned fuel loading conditions. Thia IN'Hil_.(R.,_,_ 2.1.d)-. performed by Sa....-,t and Lundy (S&L) to predict the ~ Cask dole ratell*Md dole rates at the 18FSI pad for the planned Cask loadinsi- mIlg Rock Point Allhough there are only going to be seven Casks containing fuel, the analyail MSumes the potential placement of one Cask containing *Greater Than Class c* waste at the ISFSI, which would affect dose rates.
Based upon the assumptions and calculations in this analysis, the following W150 Storage Cask surface dose rates were detennlned and are used as the acceptance criteria in this procedure: Location Gamma Neutron Total Storage Cask Top Cover 11.5 mRem/hr 3.2 mRem/hr 14.7 mRem/hr Cask Vertical Surface @ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRem/hr Outlet Vent Surface 289 mRem/hr 17.5 mRem/hr 307 mRemlhr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOTE: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit la 50.0 mRem/hr. The gamma and neutron guideline limits for this survey locatic)n were established baaed on percentages from Table 8-3 of the S&L Analysis to meet the 50 mRem/hr cumulative limit.
(: DFS-ISFSl-2.doc ¥>,
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 28 of 122 Date Completed I -#f-<J .3 SUBJECT INDEX NUMBERS Area and a Systems and/or ,"rfministrative Number MUST be Coded Area Svstems Administrative Administrative Area (AREA) Unit (UNIT) System (SYSCODE) uquipmant lassiflcation Equipment Number I Number EQUIPCL) (EQUIPNO) (ADMIN)
,LIO D ;J , ~ J. \-.i3 7 ~ l ;}_' *)9
- J/J
- RETENTION /
(RETEN) --'-J,,- _ _ (life of the Plant (L), Life of the Company (LC) or Number of Years To Be Retained) Check Appropriate Record Classification: 0 Safeguards Information O 10CFR2.790(d) Information 0 Confidential ~ Other
- - - - - - - - - - Followinn Descriptors To Be Indexed Where Applicable - - - - - - - - -
Project Name 8 RP _____,,D. . . . ._~':::\_..~6_,,_v.~e~I---'S__h_~____,,_>::(...___ _ _ _ _ _ _ _ _ _ __
.S r (PROJNAM)
Architect/Engineer Number _ _ _ _ _ _ _ _ _ _ __ Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) (PERFIL) D r.s
- Document Name ---'--_r________
o..,. - I
*1.::::>1? ~ - - - - - - - - - - - Sequence Number _ _ _ _ _ _ _ _ _ __
(DOCNAM) (SEQNO) Reference _ _ f. .:. _C_-_'7_0_3--=---------- (REF) j\J-Department _ _-LI;;;..;,..... s (DEPT) Subject 1 OAO C Y C_L-'-'/E;;._-"'2~__C,.__._f9.u..O..a..l=SM~_ffe_.-=2-;~-~C_.;::-/J=.fk:=*-J:l:_3=------ (FRETEXT) J (:)ueRp~clc ~ 3 To He Co111pldl'd-By Docunwnt C'.,.011l1 ol <ll E11g111cer111c1 HPcord Cr>11te1 Date(s) 0:C,,J 2.. (DATE) Addressee(s} _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Originator(s) Organization (FROMNAM) (FROMORG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 29 of 122 Completed By _..._._...,.____ _ _ _ _ _ _ _ _ location ___,_____ _ _ Date Completed ,},-4/*0j SUBJECT INblX NUMBERS Area and a Syatems and/or Administrative Number MUST be Coded r *- Area Area Unit System Equlpmont ClaSllflcdon Svstems Equipment Number
- Administrative Admlnlatrative Number (AREA) (UNIT) (SYSCOOE)
(AOMIN) (EQUIPCL) (EQUIPNO)
'?40 D~" a~ ;?37 ~ \ ;21 . 3'?
/0
- RETENTION (RETEN) ____
l
.___ (Life of the Plant (L), Life of the Company (LC) or Number of Years To Be Retained)
Check Appropriate Record Classification: D Safeguards Information D 10CFR2.790(d) Information 0 Confidential Jl1 Other
- - - - - - - - - - Following Oeac:r!pter: To Be !ndexed Where Applicable - - - - - - - - -
Project Name _ ...E = - - - - - - - - - - - - - - - __,..8c._:.R_P._____.D..._,,_1:.x.,._..;...Fc_.;(.(;..;;;.e...:..(_S....;1/4;__~;;_"'--il¥,- (PROJNAM) Architect/Engineer Number_ Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) (PERFIL) Document Name _D~1-;_s_-_ _P_tr_o_;r_-_.,_____ Sequence Number _ _ _ _ _ _ _ _ _ __ (DOCNAM) (SEQNO) Reference _____F ___c.*. ___,__.]_o. . . . 3. .__________ (REF) Department _ _ _ _ _ _ _ _ _ _ _ __ (DEPT) Subject J,.Qc.d _Cycle. 3) 0&,,dce Ji: 3 Cork# 8 (FRETEXT) 1,, H,* l .,1nplr t,*<J U, U,,,, ,, *,! ( 1 11(,1,, f '"Jill( l"*'J i,,., ord C1*nt1*1. 0ate(s) 0'301 (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Originator(s) Organize/lion (FROMNAM) (FROMOAG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 30 of 122 NOTE: Rate
- a. Storageeatk*~
Storage C.-,C Serial Number W1SO- [/ d - ~ DatefTime placed on ISFSI Ont / * ~ :,..- ol Time IJ10
- b. E i g h t ~ taken at equal apacing around the outside vertical...,,,.. .of the ~ c.ec. at approximately
- feet above the base. Neutron a n d ~ doae-..... are measured and averaged separately (al va1uea*1n mRem/hr).
r Location #1 Location #2 Location t3 #4 rf Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma LocatioQ i <, I ,2 <'.,I ,,._ ~. I <. A <, I <, 1 Location #5 Location #6 Location #7 Location #8 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma S, I ,A <. I lb <. l ,'2, :<, I ,~ Average Neutron Dose Rate -<, I mRem/hr rJ (<1.1 per Acceptance Criteria) Average Gamma Dose Rate D, / !i' mRem/hr y (<48.9 per Acceptance Criteria) Total Cask Surface Dose Rate fJ.15 mRem/hr (average neutron + average gamma) (<50 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 31 of 122 c. NOTE: V.._ for aR fOur Inlet and four Outlet screens should be
~ -.
~-§<gen . . . .
Neitmo ~ North o, 'I 1, ').. mRem/hr East 1,£ l.,~ mRem/hr South O,~ 3,2' mRem/hr West _LJ__ J,O mRem/hr Average Neutron ,jtS: mRemnir I) (<17.5 per Acceptance Criteria) Average Gamma 6.1 mRem/hr y (<289 per Acceptance Criteria) Total outlet dose rate .3,il.f mRem/hr (<307 per Acceptance Criteria) (Average neutron + average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 32 of 122 lali§nlDf. . . North Ntitor1
,f
-***=~
,l.. mRemlhr East l,l,. I~ mRemlhr South ,.;.,, <.2. mRem/hr West l,i I l.. mRem/hr Average Neutron l 1~ mRem/hr ri (<5.3 per Acceptance Criteria)
Average Gamma ,l1S: mRemlhr y (<14.0 per Acceptance Criteria) Total inlet dose rate J.'17f mRem/hr (<19.3 per Acceptance Criteria) (Average neutron + average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 33 of 122
- d. ..........
..-...,._.,_._Id ___,__ Ill . . . th
...,.,..*tom*
l,.gcatlpn 12 Neutron Gtmma
<.1. ,l.. ., <.~
Location t 3 L9C1Jkm H Neutron Gamma NeutronGamma I 1/ '1 .1 Average Neutron Dose Rate ,¥~f mRem/hr I) (<3.2 per Acceptance Criteria) Average Gamma Dose Rate ./5' mRem/hry (<11.5 per Acoeptance Criteria) Total Cask Top Dose Rate ,S-7 t;" mRem/hr (average neutron+ average gamma) (<14.7 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 34 of 122
- e. ~~ COfflPlltidt ._ I* 2,1 *I 3 Time. IS'.1£ .
(Note: lNl time~ bewJlhtn 12 hours o f ~ under Section a of Au.chment 1.) Gamma d* rate meter/aerial t R91/2.u S: ea*. due date 1-2-11 Neutron do,e rate meter/aerial t Asr-1l,v11
- Cal. due date ,./1/-11 (RP) zu.wt....,lllllll!ll.4S::-Date 1-;q-11 (RS Supervisor) * ...::::;..~~------ Date (Jd *OS (DFS Manager) Date J*l. i ,d_>
DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 35 of 122 DF8-ISFSl-2 n.rtllDflO PERFORM FINAL D08E 1ATE .SURVEY ,,...1Stl1S TECHNICAL SPECIFICATION 5.8.5 ATTACHMENT 2 W150 STORAGE CASK IIJBFACE DOSE RATE ACCEPIANQE.CR1TERIA Big Rock Point Plant Manual Volume 31, Dry Fuel S t ~ Technical Specfflcationa, Section 5.3.5.1, requinte an enalysia to contlrm that the llmltl of 10CFR20 and 10CFR72.104 wtU be ~ under the ~ site condltlona and conflgurationa considering the planned number of C8ekl to be used and the planned fuel loading conditions. Thia ana,Y.il (Reference 2.1.d) wu performed by Sargent and Lundy (S&L) to predict the Storage cask dose rates and dose rates at the ISFSI pad for the planned Cask loadings at Big Rock Point. Although there are only going to be seven Casks containing fuel, the analysis assumes the potential placement of one Cask containing "Greater Than Class C" waste at the ISFSI, which would affect dose rates. Based upon the assumptions and calculations in this analysis, the following W150 Storage Cask surface dose rates were determined and are used as the acceptance criteria in this procedure: Location ____ G=*m=m=-*-------Ne ___ut o__ __r__ n _ _ _ _ _T.:...:ota=I-Storage Cask Top Cover 11.5 mRem/hr 3.2 mRem/hr 14.7 mRemlhr Cask Vertical Surface @ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRern/hr Outlet Vent Surface 289 mRem/hr 17.5 mRem/hr 307 mRem/hr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOTE: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit Is 50.0 mRem/hr. The gamma and neutron guideline limits for this survey location were established based on percentages from Table 6-3 of the S&L Analysis to meet the 50 mRem/hr cumulative limit.
DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 36 of 122 SUBJECT INDEX NUMBERS Area and a Systems and/or Administrative Number MUST be Coded Area Svstems Administrative Equipment Equipment Admlnlatratlv* Area Unit* System Number Number (SYSCODE) Clasaification (AREA) (UNITI (EQUIPCL) (EQUIPNO) (ADMIN) 0 :JI,;; ~. 'J.)7'd../ ~) *) 7
- ID*
RETENTION (RETEN) _ _ _ _ (Life of the Plant (L), Life of the Company (LC) or Number of Years To Be Retained) Check Appropriate Record Classification: D Safeguards Information D 10CFR2.790{d) Information 0 Confidential
- - - - - - - - - - Following Detcrlptora To Be Indexed Where Applicable - - - - - - - - -
Project Name {J f P -i)/2 7 F~ S b'Y?;E( (PROJNAM) Architect/Engineer Number _ _ _ _ _ _ _ _ _ __ Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) (PEAFIL) Document Name ____D.___.t:._
.....---'1_-_*....,ar_:-:._e_,_}T..._--__1____ Sequence Number _ _ _ _ _ _ _ _ _ __
(DOCNAM) (SEONO) Reference _ ____._F__..C..._*-_7 u_3 (REF) Department _ _ _ _ _..__ j) ps (DEPT) Subject L DA cl C1c le__ (FRETEXT) 0 fJt1,rh-c Y s Oate(s) t!) !So L (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Orlginator(s) Organization (FROM NAM) (FROMORG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 37 of 122 tlM111onO Pagejof13 W1 NOTE: Ail surveys to t,,e ~ in ~ with RP-29, Radiological Surveys. Acceptance C--: Sle Attact,ment 2, W150 Storage Calk Surface Dose Rate Acceptance Criteria.
- a. Storage Cask Identification Storage Cask Serial NumberW150- S:10 -llnc,,
Datemrne placed on ISFSI Date , -~ 9 - o J Time /0:10
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage cask at approximately six feet above the base. Neutron and gamma-ray dose rates are measured and averaged separately (all values in mRern/hr).
Location #1 Location #2 Location #3 Location #4 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma 0.1 O,'f 0.0 O.'f o., Q,'f (),.J. O.o/: Location #5 Location tl6 Location #7 Location #8 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma O.D Q,'f o.o 0.'f 0,/ o. 'f 0,0 0. 't Average Neutron Dose Rate 0. 06 mRem/hr I') (<1.1 per Acceptance Criteria) Average Gamma Dose Rate O.'t mRem/hry (<48.9 per Acceptance Criteria) Total Cask Surface Dose Rate 0. '-' (i,_ mRem/hr (average neutmn + average gamma) (<50 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 38 of 122 'OF~2 PeRFQIM~,........ TECHftlCAL SPIC W1
- c. Inlet and Outlet Screen surface dose rate. Neutron and gamma measured separately.
NOTE: Values for all four Inlet and four Outlet screens should be recc,rded. Outlet Screen §u!f!ge Neutron Gamma North 0,5 3.'1 mRem/hr East O,'f 3,Q mRem/hr South 0.1:, 3.,2 mRem/hr West /,0 ~, 'f mRem/hr Average Neutron Q,,3 mRem/hr rJ (<17.5 per Acceptance Criteria) Average Gamma 3.05 mRem/hr y (<289 per Acceptance Criteria) Total outlet dose rate J. loS mRem/hr (<307 per Acceptance Criteria) (Average neutron+ average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 39 of 122
..,~.
,.-, ~~ ,,,-..
,,-,- 1-,_c~;< ;3:*'£,.;r/,~,.-,0;...+,-
**:*:: t;:i?!f*
Pl!~"FINAI,.. *. TECHNICAL SP*. ..
,at.,,..V**
loffYj~J:t
':C' ,
.. Att~..-rr 1 W150 s:rQfWIJ* - : - BATE SURVEY SHEET tntot Scrnn* Suff!2!
Neytron Galm-:~ North 1.0 o.s mRem/hr East o,, - 0,(p mRem/hr South 1.0 0.{p mRem/hr West l1:J tJ.!; mRem/hr Average Neutron O, 9S mRem/hr I) (<5.3 per Acceptance Criteria) Average Gamma O.SS mRem/hr y (<14.0 per Acceptance Criteria) Total inlet dose rate [.S mRem/hr (<19.3 per Acceptance Criteria) (Average neutron+ average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 40 of 122 1UiiAA11f 0iI:.Sff' . **
;-,_ fi!S---'!---l *; ;_, __ ~*.;-+,.+,;-r,/"ii, ',J,;,/f,, _._. ~ _,_:_-cic"_-*--£:,,-./1_,_ / /
...:~i;ir .,
- d. FIYe ~ - - ( J l *
- t o p Hd, with one.....,.
cen1et and1he otherfout._......... IP'ICil9 30 inches from the from the c:ienter. Neutron and gamn,afl)NSUr,xt aeparatety (all values in mRemlhr). Center ~ Logmon #1 Neutron Gamma Neutron Qlmma Neutron Gamma 0.3 O,'t D,S Q.3 Location t 3 Location #4 Neutron Gamma Neutron Gamma Q,4 fl<<'-1 '2,3 O,'t o.141 Average Neutron Dose Rate.~ mRem/hr I') (<3.2 per Acceptance Criteria) Average Gamma Dose Rate 0,'1'f mRem/hr y (<11.5 per Acceptance Criteria) Total Cask Top Dose Rate (2. 7j mRem/hr (average neutron+ average gamma) (<14.7 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 41 of 122 8. Gamma do,e rate m**~* A1JJ/ ,,, s Cal. due date 4, ... .2...p_J Neutron dole rate m * ~
- Asf-y'lY'tQ Cal. due date ~-l"l*OJ (RP) .Jd~C~~~ate /- ct* OJ (RS Supervisor) I-JJ-o9
{DFS Manager) __;.___..~--..Date ( "15 '03 DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 42 of 122 DFs-.lSFat,.2 . . *. *.. * .h * . PERFdttM FINAL ooe&ftl\1-IURVEV TECHNICAL SPECIFICA"i1QH '&.3.5 RATE Big Rock Point Plant Manual Volume 31, OryF-1 Storage Technical Speoificdons, Section 5.3.5.1, requiret an analylia to confffmhd the limits of 10CFR20 and 10CFR72.104 will b e ~ under the ICtlMl1i* conditions and con'ftgurations considering the planned number of Cub to*e. uted and the planned fuel toading conditions. Thia analysit ~ 2.1,d) -,*performed by S.,vent,-,,d*Lundy (S&L) to predict the ~ Cask dole rate. and dose rates at the *1sFSt pad for the planned Cask loadings at Big Rock Point. Although there are only going to be seven Casks containing fuel, the analysis assumes the potential placement of one Cask containing "Greater Than Class c* waste at the ISFSI, which would affect dose rates. Based upon the assumptions and calculations in this analysis, the following W150 Storage Cask surface dose rates were determined and are used as the acceptance criteria in this procedure: Location _G_a-m_m-a_ _ _ _ _N_e~u~tr_o_n_ _ _ _ _ To~t-al__ Storage Cask Top Cover 11.5 mRem/hr 3.2 mRem/hr 14. 7 mRem/hr Cask Vertical Surface@ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50 mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRem/hr Outlet Vent Surface 289 mRem/hr 17 .5 mRem/hr 307 mRem/hr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOT~: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit is 50.0 mRern/hr. The gamma and neutron guideline limits for this survey location were established based on percentages from Table 6-3 of the S&L Analysis to meet the 50 mRern/hr cumulative limit.
DFS-ISFSl-2.doc t L...M~ .. ~--~~. . ~~~ililill~II
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 43 of 122
- - - - - - - - - - - - - Location &P DateComplet SUBJECT INDEX NUMBERS Area and a Systems and/or Administrative Number MUST be Coded Area Svstems Administrative Area (AREA)
Unit (UNln System (SYSCODE) I Equipment Classification (EQUIPCL) Equipment Number (EQUIPNO) Administrative Number (ADMIN) 1\/0 t>:i, ~~ ~7d.\ ~'
- d7* /0 RETENTION (RETEN) _ _ _ _ (Life of the Plant (L), life of the Company (LC) or Number of Years To Be Retained)
Check Appropriate Record Classification: D Safeguards Information D 10CFR2.790(d) Information D Confidential 11(Other
- - - - - - - - - - Following Descriptors To Be Indexed Where Applicable - - - - - - - - -
Project Name _if~R._?_""""'D~~-i-1--(;~'-'=c. . . .l._~S={o~&-%r-ai'.__ _ _ _ _ _ _ _ _ _ _ _ _ __ (PROJNAM) Architect/Engineer Number _ _ _ _ _ _ _ _ _ _ __ Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) (PERFIL) Document Name D4='S - PR I.) r- ( Sequence Number _ _ _ _ _ _ _ _ _ __ (DOCNAM) (SEQNO) Reference _ _F ___C'_-_7_0_'3__________ (REF) Department __ J)_f::'_5 (DEPT) Subject _.....;l=-d_4__~..__=0-'J'l-"~--'-l=s;--~--~------------------*----- (FRETEXT)
~a ('.q lf.-/oe.
/l s--
Date(s) _ _ __ (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG} Originator(s) Organization (FROMNAM) (FROMOAG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 44 of 122 NOTE: AH surveyatq . . ~ m~ w t l h RP..29, Radiological Surveys. Aoceptaft0I ~ : $te ~ 2 . W150 Storage Caek StJtface Dose Rate Acceptance CrltiNia.
- a. Storage ~ ldentificatkm Storage Ceak Serial Number W150-(e IO Datemme placed on ISFSI Date 2-/ 11 / 03 .'~:ff?_
Time~
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage Cask at approximately six feet above the base. Neutron and gamma-ray dose rates are measured and averaged separately (all values in mRem/hr).
Location #1 Location #2 Location #3 Location #4 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma
. 35 <?- .oi: .2. ~.0/ .g ~.Of _.J____
Location #5 Location #6 Location #7 Location #8 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma
~ .OI ~.2. . .3 . 2- ,.01 .3 ~-~' . z.
Average Neutron Dose Rate
- oS mRem/hr I) ( <1.1 per Acceptance Criteria)
Average Gamma Dose Rate . :2 3 mRem/hr y (<48.9 per Acceptance Criteria) Total Cask Surface Dose Rate . 31 mRem/hr (average neutron + average gamma) (<50 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 45 of 122
..*. ;i;c*" t'(i:'i ti~1r1t~\11tr*>':;
- 1 Ptljl'tit 18.
W1
- c. Inlet *nd OUtlat Screen surface dole rate. Neutron and gamma meuured ......ly.
NOTE: Valuea for all four Inlet and four Outlet screens should be recorditd. Outftt Screen ~yrface Neutron Gamma North -~ z_ mRem/hr East .5 ,.1 mRem/hr South 1- mRem/hr West .5 2.2 mRem/hr Average Neutron ~mRem/hr I) (<17.5 per Acceptance Criteria) Average Gamma .:J. mRem/hr y (<289 per Acceptance Criteria) Total outlet dose rate ,;J.IIS' mRem/hr (<307 per Acceptance Criteria) (Average neutron + average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 46 of 122 ftj#iorl~ North * :lo *3 mRern/hr East
- S: ~.z mRemlhr South
- as-
- 2- mRern/hr West . C'/
--- . c/ mRern/hr Average Neutron .l.,f mRemhlr I') (<5.3 per Acceptance Criteria)
Average Gamma . ;i.3 mRemlhr y (<14.0 per Acceptance Criteria) Total inlet dose rate , 8~ mRem/hr (<19.3 per Acceptance Criteria) (Average neutron+ average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 47 of 122 d. cenw:*-**--..*
- F ~ . ~ - l f t f i . . top Rd. wltn one fMdinO from the oetHt. tt.utron antfQllmffli~red mRtitMV).
equat...,. ao .... from the HP1111teiy ( - ~ I n Clfllr lQQltioo #1 LQQltion f2 Neutron *Gamma NtutrQn
- Gamma Neutron Gamma
.o& ,2
- I Z. * .3 Location # 3 Location #4 Neutron Gamma Neutron Gamma
.2. . t, Average Neutron Dose Rate . o7 mRem/hr 'l (<3.2 per Acceptance Criteria)
Average Gamma Dose Rate ' , 34/ mRem/hry (<11.5 per Acceptance Criteria) Total Cask Top Dose Rate
- S- mRem/hr (average neutron+
average gamma) (<14.7 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 48 of 122 OF&-ISFSl-2 Page 12of 13 PERFORM FINAL D0e RATr $UIWEY TECHNICAL SPECIFIOA1ION 5.3.5 ATTACHMENT 1 W150 STQBAf,iE CASK ctbB RATE §URYEY SHEET
- e. Date/T'me turV8Y completed: Date z:/1t/01 Time /COi (Note: Thil time must be within 12 hours of time/date under Section a of Attachment 1.)
Gamma dolo rate meter/aerial # f1.o: z. 1t,t,, t Cal. due date 4/r/4J Neutron dose rate meter/aerial #fill J9c/Q Cal. due date ~~ (RP) C Date~~ (RS Supervisor) --1,-1,,.~""--- Date -r/t}"' 1 (DFS Manager) -,t-.:.::~._~ Date i.,. W Cf> DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 49 of 122 DFS-ISFSS.-2 ,.....,.0 PERFORM FINAL DOSE Rt TE SURVEY Pa;e1Sof13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 2 w1so sTQMQE .CAIJS IIBlAC~ pose RAD; ACCEPTANCE CRITERIA Big Rock Point Plant Manual Volume 31, Dry Fuel Storage Technical Speoificatk>na, Section 5.3.5.1, requtn. an analyais to confirm that the limita of 10CFR20 and 10CFR72.104 will be aatilOed under the actual. lite oonditionl and cnnftGtntiona considering the planned number of CMks to be UMd and the planned fuel loading conditions. This analysil (Reference 2.1.d) WM performed by Sa,gent and Lundy (S&L) to predict the Storage Cask dose rates and dole rates at the ISFSI pad for the planned Cask loadings at Big Rock Point. Atthough there are only going to be seven Casks containing fuel, the analysis anumes the potential placement of one Cask containing *Greater Than Claas c* waste at the ISFSI, which would affect dose rates. Based upon the assumptions and calculations in this analysis, the following W150 Storage Cask surface dose rates were determined and are used as the acceptance criteria in this procedure: Location _G=am ____a.___._________Ne........_utron ___m ..........___________To....ta.....1 _ Storage Cask Top Cover 11.5 mRem/hr 3.2 mRem/hr 14.7 mRem/hr Cask Vertical Surface @ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50 mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRem/hr Outlet Vent Surface 289 mRem/hr 17.5 mRem/hr 307 mRem/hr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOTE: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit la 50.0 mRem/hr. The gamma and neutron guideline limits for this survey location were established based on percentages from Table 6-3 of the S&L Analysis to meet the 50 mRem/hr cumulative limit.
DFS-ISFSl-2.~
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 50 of 122 SUBJECT INDEX NUMBERS Area and a Systems and/or Administrative Number MUST be Codad Area - $VAteffls Administrative Equipment Equipment Administrative Area Unit System (AREA) (UNIT) (SYSCOOEi Clalsfflca1lon Number Number (EQUIPCL) (EQUIPNO) (ADMIN)
. 39 1L/O OJ~a;l.. ~17a l ;;i} * )0
- RETENTION t-{__
(RETEN) _ . & ;_ _ _ _ _ _ _ (life of the Plant (L), Life of the Company (LC) or Number of Years To Be Retained) Check Appropriate Record Classification: 0 Safeguards Information O 10CFR2.790(d) Information D Confidential Xother
- - - - - - - - - - Following !1>escriptors To Be Indexed Where Applicable - - - - - - - - -
Project Name _ __.B........_R_....P..___j)'-'-R"-f'----.....f--=~K~l-..,,.S,....fa....::.=12A-~7_.,:f______________ (PROJNAM) Architect/Engineer Number _ _ _ _ _ _ _ _ _ __ Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) (PERFIL) Document Name --J..D. . . .f--=S::;_'
. _-___,_P___;R;._;;o;_J=--__.I.____ __ Sequence Number _ _ _ _ _ _ _ _ _ __
(DOCNAM) (SEQNO) Reference _ _ F_C_-_,_a_3___________ (REF) Department DFS (DEPT) Subject Lo,q if C<t c le l, (FRETEXT) L o,q.cl Crc le l CIM'4iee --------- (i:> ()\JcR p1c t; '-/ 1u H,* C(1i11plel1'd E.ly Document Cont, ol ot Engrne<'r ,nu RPc 01 d Ct>nler Date(s) D3o"'3 (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Originator(s) Organization (FROMNAM) (FAOMORG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 51 of 122 DFS-ISFSl-..2 PERFORM FINAL DOl&,RATE SURVEY
...,..0 P..-8of13 TECHNICAL SPEoaPICAl tuN 6.3.~
A'rl"AO~ 1 W1§0 §IOBAGE CAK'-*MIE SURVEY SHEET NOTE: Aq surveys toblJelfOm'led*lo ~ with RP*29, Radiological SUrveya. Acceptance Orillltta: See Attachment 2, W150 Storage Caal< Surface Dole Rate Acceptance Criteria.
- a. Storage Ci!lk ldentfflclltion Storage Cask Serial Number W150- tf \0 - tJft.,C-.
Datemme p1acec1 on ISfSI 0ate 3(slo., Time ll 3b
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage Cask at approximately six feet above the base. Neutron and ganvna-ray dose rates are measured and averaged separately (an values in mRem/hr}.
Location #1 Location #2 Location #3 Location #4 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma Q,'1 0,1 tJ, I o,3 a.o~ o,3 a.o; o.'f Location #5 Location #6 Location ~z Location #8 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma t) ; 0 t- 0: ;J_ 0
- l),l O If I 0,()3, 0, 'f J2~~ o. k *.
Average Neutron Dose Rate 0.0 'lj mRem/hr I) (<1.1 per Acceptance Criteria) Average Gamma Dose Rate O, ':f JJ mRam/hr y (<48.9 per Acceptance Criteria) Total Cask Surface Dose Rate 0.'1,1 mRem/hr (average neutron+ average gamma) (<50 per Acceptance Criteria)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 52 of 122 OFs.&SFSl-2 PEAFOAM FINAL oaaEPTI IUIM!Y TECHNICAL SP!CIFiCA'TtON*S.3.ij
,.\-rt,*,
- c. Inlet ~. Outlet Screen surface doN rate. N&utron and ganvna measUNKJ ..... ately.
NOTE: Values for all four Inlet and four Outlet lfCfNn8 should be recorned. OuJ!ot §green §yrface Neutron Gamma North 0,3 4 mRem/hr East 0, 'J 3 mRem/hr South 0,7 a.. mRemlhr I West 0eI J mRemlhr Average Neutron C).3)£ mRem/hr rJ (<17.5 per Acceptance Criteria) Average Gamma 3,0 mRem/hr r (<289 per Acceptance Criteria) Total outlet dose rate 3,3':S mRem/hr (<307 per Acceptance Criteria) (Average neutron + average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 53 of 122 DF8-18Fll-2 fllMlioflO PERFORM Pt.W. tKtl&Ft~TE 8URWY P... 10ot 1s TECHNICAL SP&Cff1GATIQN 5.3.S AffACHt.tllNT 1 W11Q §TQRAGE CASK bQIG:flATE SURVEY SHEET lDllt §green §MrfNt Neutron Gamma North a., o. 't
- mRem/hr East o., o.tt mRern/hr South l,4 0 ,41 mRem/hr West o, fl o.~ mRern/hr Average Neutron 0.'6 mRem/hr I) (<5.3 per Acceptance Criteria)
Average Gamma o ,'t mRem/hr y (<14.0 per Acceptance Criteria) Totai inlet dose rate i.~ mRem,'hi (<19.3 per Acceptance Criteria) (Average neutron + average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 54 of 122 OF8-t8Fil-i . *.. . PERF~ fttNM. ooae:fg~:IUIMiY TECHN1CAL SPECfFICA'AON 6.8~
. ATT, ,
- d. F i v e ~ ~ontt. i,p Ud, with one reading from the cenW . * ,h.CJlherbi'~*---epac1ng*so*N11esfromthe cenler. Neutron and pMmi *MN1UNK1 aeparalely (all values In mRemlhr).
Ctmtr LQQIU9D f1 LOQIUon #2 Neutron G,mma N§utrgn i,lmma Neutron Gamma o,o, '1, I o.tU Q.3 Location # 3 LOQIUon f4 Neutron Gamma ~ Gamma
- 0. S O,t-;
Average Neutron Dose Rate O.cf't mRemlhr r> (.c:3.2 per Acceptance Criteria) Average Gamma Dose Rate 4), ff mRem/hr y (<11.5 per Acceptance Criteria) Total Cask Top Dose Rate Q.5,'I mRam/hr (average neutron+ average gamma) (<14.7 per Acceptance Criteria) DFS-ISFSl-2 .doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 55 of 122 OfS-.ISFSt-2 PERFOAM F I N A L ~ . *.. . . TECHNICAL ..,~a.a,
- e. ~ 1UMY ~~ **oa. 3 ... s," 3 Time 1':tte (Note: 'Thtltlme *fflUlit bt Within* 12.hours of time/data under Section a of Attachment 1.)
Ganvna dcse rate meterllerial # a<<<<-LDS7'Z. , Cal. due date j*,M-oJ Neutron dose rate meter/serial# dSf-1./ Xf'fO Cal. due date ,-l'(:41 (RP) (RS Supervisor) (DFS Manager) 1i j 11
.1 1
ll 1 OFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 56 of 122 DFS-ISFSl-2 ~o PERFORM FINAL DOSE RATE SURVEY Page 13 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMENT 2 W15Q §TO~ii-MfSE RATE Big Rock Point Plant Manual Volume 31, Ory Fuel Storage Teohnlcal 8peclfloationa, Section 5.3.5.1, requm an analyetl to oonllrm that the lin~lta of 10CPR20 and 10CFR72.104 will be aatitfted µnder the ..... site condtlloM end oonflguratlon1 considering the planned numl:l'er of Cd<e to be uNd and the planned fuel loading conditions. Thia anatysia (Reference 2.1.d) wu performed by Sergent and Lundy (S&L) to predict the Storage Caak dole rates and dole ratee at the 18F8t pad for the planned Cask loadings at Big Rook Point Although there are only going to be NYen Casks containing fuel, the analysis aesumea the potential placement of one CUk containing "Greater Than Class c* waste at the ISFSI, which would affect dole rates. Based upon the assumptions and calculations in this analyaia, the following W150 Storage Cask surface dose rates were determined and are used ** the acceptance criteria in this procedure: Location Gamma Neutron Total Storage Cask Top Cover 11.5 mRem/hr 3.2 mRem/hr 14.7 mRem/hr Cask Vertical Surface @ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50 mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRem/hr Outlet Vent Surface 28SmRem/hr 17,5 mRem/hr 307 mRem/hr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOTE: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit is 50.0 mRemlhr. The gamma and neutron guideline limits for this survey location were established based on percentages from Table 8-3 of the S&L Analysis to meet the 50 mRem/hr cumulative limit.
DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 57 of 122
- - - ~ - - . . . - - - - - - - - Location _ __,,8_1??'-"'-'------ Date Completed _ _ __
SUBJECT INDEX NUMBERS Area and a Systems and/or Administrative Number MUST be Coded Area Svatems Administrative ArN Unit System Equipment Equipment - Admlnlltralive Clmltk:atlon Number Number (AREA) {UNIT) (SYSCOOE) (EQUIPCL) (EQUIPNO) (ADMIN)
'l ~o ():lit, l.~_ ~)7:2_\ .:2 l
- 39 * )0
- RETENTION 1 "'
(RETEN) ---._ (Life of the Plant {L), Life of the Company (LC) or Number or Years To Be Retained) Check Appropriate Record Classification: D Safeguards Information D 10CFR2.790(d) Information D Confidential ~Other
- - - - - - - - - - Following Descriptors To Be Indexed Where Applice1>ie - - - - - - - - -
Project Name _,_;.0_R_P__D'-'-R....,f,...._-'6'---'--"lt-""S,........, _=&:.i..f9-=-=-~~7-':C,..______________ {PROJNAM) Architect/Engineer Number Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) {PERFIL) Document Name _ _.D~~'--'.S'--*_P_~_o_r.;:._-_...._____ Sequence Number _ _ _ _ _ _ _ _ _ __ (DOCNAM) (SEQNO) Reference _ _ ...:.F__,.C~-_']_._0~3________ (REF) Department {DEPT)
- -~*D_ _ f----r__- - - -
_ ~-- Subject _ _ _ L.._o__e.._d_____~_y,_.c......,....le__')...____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (FRETEXT) LOA cl C\1 ~ If ~ J J 1o !3,* Compl,*tprJ n) Docu111Pnt Control 01 Eng111eerrng RPcord Centc, , Date(s) D.,30Z., (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Originator{s) Organization _ _ _ _ _ _ _ _ _ _ __ (FROM NAM) (FROMORG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 58 of 122 DF~l8F$1-I ~o PIRF<"'Rt.f.~.~-1'~1':IURVEV P*lof 18 TECHNICAL SPECIFIOA110N S.3.5 ATTAQWIHT1 W1§0 §TQMGE CASK DOR BAIE §UR\lEY SHEU NOTE: Ali surveys to be performed in accordenoe with RP-l9, Radiological Surveys. Acceptance Criteria: See Attachment 2, W150 Storage Cask Surface Dole Rate Acceptance Criteria.
- a. Storage Cask Identification Storage Cask Serial Number W150- j /0 -...t!!::1 G Datemme placed on ISFSI Date ;J.at,/43 Time 091(
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage Cask at approximately six feet above the base. Neutron and gamma-ray dose rates are measured and averaged separately (all values in mRem/hr).
Location #1 Location #2 Location #3 Location #4 Neutron Gamma Neutron. Gamma Neutron Gamma Neutron Gamma o.O ,5 o.o ,5 (),o I 'I (2.0 _.3__ Location #5 Location #6 Location #7 Location #8 Neutron Gamma Neutron Gamma Neutron Gamma Neutron Gamma 0, 0 I '( Q,O Ii o. o . '/ o, o ~i./ Average Neutron Dose Rate o. 0 mRem/hr I) (<1.1 per Acceptance Criteria) Average Gamma Dose Rate o.f mRem/hr r (<48.9 per Acceptance Criteria) Total Cask Surface Dose Rate o. '{ mRem/hr (average neutron + average gamma) (<50 per Acceptance Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 59 of 122 C. Inlet a.ad Qutlet Screen aurflloe doee rate. Neutron and gamma meaaured separately. NOTE: Values for all four Inlet and four Outlet screens should be recorded. Outlet Screen Sump Neutron Gamma t f North O,i q.o mRem/hr v
~.
East o.'/ c/.o mRem/hr
~
i_ lI South a,3 3,0 mRem/hr o,~ 3 ,'-/ mRem/hr r* West Average Neutron , ':L mRem/hr I) (<17.5 per Acceptance Criteria) Average Gamma J. ,* mRem/hr y (<289 per Acceptance Criteria) Total outlet dose rate '{. O mRem/hr (<307 per Acceptance Criteria) (Average neutron + average gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 60 of 122 OFS..ISFSt-2 R.vlllonO PERFORM FINAL ~tfr.,$MM!Y P... 10of13 TECHNICAL SPECIFICATION S.3.5 ATTAOHMINT 1 W150 STQRAGE CASK pose BATE SURVEY SHEET Inlet Screen Syrface Neytron Gamma North c?, ~ o~"I mRem/hr East o.../ p.t../ mRem/hr South o.$ O, 4f mRem/hr West o. (. 0," mRem/hr Average Neutron tJ* 5 mRem/hr I) {<5.3 per Acceptance Criteria) Average Gamma o,'-/ mRem/hry (<14.0 per Acceptance Criteria) Total inlet dose rate 0, 9 mRem/hr {<19.3 per Acceptance Criteria) (Average neutron + average gamma) DFS-iSFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 61 of 122
- d. Five~ -..,on the top lid, with one INding from the center and the other four__, at equal spacing 30 inchel from the center. Neutron and gamma measured ! ~aratety (all values In mRemlhr).
Center Location #1 Location #2 Neutron @amma Neutron Gamma Neutron Gamma 17, I Location # 3 Location #4 Neutron Gamma Neutron Gamma
- o. 'i o. cf Average Nel1tron Dose Rate p. 'I mRem/hr I) (<3.2 per Acceptance Criteria)
Average Gamma Dose Rate O, 1 mRem/hr y (<11.5 per Acceptance Criteria) Total Cask Top Dose Rate O. g mRem/hr (average neutron + average gamma) (<14.7 per Acceptance Criteria) DFS-iSFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 62 of 122 DFS-ISFSl-2 ~o PERFORM F1NAL DOSE AA1~ SURVEY Page 12 of 13 TECHNICAL SPECIFICI.TION* 5.3.5 ATTACHMINT 1 W150 STORAGI; CASK POSE RATE SURVEY SHEl;T
- e. Date/Time survey completed: Date ,/H/42 Time / 30 r>
(Note: This time must be within 12 horirs of time/date under Section a of Attachment 1.) Gamma dose rate meter/serial# ~ 0 /* ,:1,t/ Cal. due date,-;-"} Neutron dose rate meter/serial #Af~, / 3 'J'/'O Cal. due date (-1'{-fl3 (RP) ~ A-c=e: Date ,)<A, (RS Supervisor) __.,._J./;__ Date ] £/4 *
~l (DFS Manager) Date 9l 1.... ~
DFS-iSFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 63 of 122 OFS-ISFSl-2 RevilionO PERFORM FINAL DOSE AA,.: SURVEY Page 13 of 13 TECHNICAL SPECIFICATION 5.3.5 ATTACHMEN1' 2 W150 STORAGE CA§K SUBfACE DOSE RATE ACCEPTANCE CBf[ERlA Big Rock Point Plant Manual Volume 31, Ory Fuel Storage Te:-:hnical Specifications, Section 5.3.5.1, requires an analysis to confirm that the limits of 10CFR20 and 10CFR72.104 will be satisfied under the actual site conditions and oor,ftgurationa considering the planned number of Casks to be used and the planned fuel loading conditions. This analysis (Reference 2.1.d) was performed by Sargent and Lundy (S&L) to predict the Storage Cask dose rates and dose rates at the ISFSI pad for the planned Cask loadings at Big Rock Point. Although there are only going to be seven Casks containing fuel, the analysis assumes the potential placement of one Cask containing "Greater Than Class c* waste at the ISFSI, which would affect dose rates. Based upon the assumptions and calculations in this analysis, the following W150 Storage Cask surface dose rates were determined and are used ~s the acceptance criteria in this procedure: Location Gamma Neutron Total Storage Cask Top Cover 11.5 tJ1Remt'hr 3.2 mRsm/hr 14.7 mRem/hr Cask Vertical Surface @ 6 feet 48.9 mRem/hr 1.1 mRem/hr 50 mRem/hr* Inlet Vent Surface 14.0 mRem/hr 5.3 mRem/hr 19.3 mRem/hr Outlet Vent Surface 289 mRem/hr 17.5 mRem/hr 307 mRem/hr NOTE: These values were obtained from Tables 6-1, 6-2, and 6-3 of the S&L Analysis. If the averaged limits, for gamma, neutron, or total are equaled or exceeded, refer to Volume 31, DFS Technical Specifications, Section 5.3.5.5, for further actions.
*NOTE: Per Volume 31, DFS Technical Specifications, Section 5.3.5.3, this limit is 50.0 mRem/hr. The gamma and neutron guideline limits for this survey location were established based on percentages from Table 6-3 of the S&L Analysis to meet the 50 mRem/hr cumulative limit.
DFS-ISFSl-2.doc L.
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 64 of 122 SUIIJeCT INDEX NUMBERS Area and a Systems and/or Administrative Number MUST be Coded Area Svatema Administrative Aru Unit Syatem Equipment Equipment - Admlnlltratlve (AREA) (UNIT) CIMllllcaton Number Number (SYSCODE) {EQUIPCL) (EQUIPNO) (ADMIN) 740 D ~18 ;;l. .:t. ;13,;t l ;21
- 39
- JO
- RETENTION (RETEN) L<!- (Life of the Plant (L), Life of the Company (LC) or Number of Years To Be Retained)
Check Appropriate Record Classification: D Sateguards information O iOCFR2.790(dj ir,l0111,&iion VUIIIIUOIIUQ
- - - - - - - - - - Following Descriptors To Be Indexed Where Applicable - - - - - - - - -
Project Name _...,8....,f-"-P,____D_12_1-+--h-~ ___S-=...;...i-1'~ri.,,.~t-""1:-------------
,,0cn IN.6.U\,
ArchitecVEngineer Number _ _ _ _ _ _ _ _ _ __ Personal File Number _ _ _ _ _ _ _ _ __ (BECHNO) (PERFIL) Document Name .D ~s * - p RO ! - / Sequence Number _ _ _ _ _ _ _ _ _ __ (DOCNAM) (SEQNO) Reference ___ F_c,_~-~-_'1....._c_3__________ (REF) D t-.S Department - - - ' " - - - - - - - - - - - (DEPT) Subject ___ i.. . o.....A......c_-'__C_y_c_le__g______ ._;6;;:;_7i_,_C'""-""C_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (FRETEXT) L0-4 d C-, d~ 1 I > :., 6 TC C Cttrk To BP Compl!'kcl By Docu11wnt Co11trol or Engineering Record Center ' Date(s) Q8o6 (DATE) Addressee(s) _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Organization (TONAM) (TOORG) Originator(&} Organization (FROMNAM) (FROMORG)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 65 of 122 0Fs..t8F81-2 FtMlonO PERFORM FINAL 008E RATE SURVEY Page8of13 TECHNICAL SPECIPICArlON 5.3.& ATTACHMINT 1 W150 STQMGEPASK DO$i RATE SURVEY SHEET NOTE: All surveys to be performed in aooordanoe with RP-29, Radiological Surveys. Acceptance Criteria: See Attachment 2, W150 Storage Cask Surface Dose Rate Acceptance Criteria.
- a. Storage Cask Identification Storage Cask Serial Number W150- /If> - ~v Date/Time placed on ISFSI Date ¢/o3 Time tJfi~O
- b. Eight measurements taken at equal spacing around the outside vertical surface of the Storage cask at approximately six feet above the base. NeutroR aREt gamma FaV aeae rates ar:e measuFeEt aRa a~mgeet separately (all values in mRem/hr).
Location #1 Location #2 Location #3 Location #4 NoutFOR ~1/ma NeutreR G~fma NeutFOn Gamma
,2 NeMtreR ~'j1ma Location #5 Location #6 Location #7 Location #8 Neutron Gamma NeutreR Gamma Neutron Gamma Neutron Gamma
,J <<2 .y ====== . ;2.
J\.¥erage Neutron Dose Rate mRemJhr I) (<1.1 per Aeeeptanee Criteria) Average Gamma Dose Rate _,_3__ mRem/hr y (<&48-:9 per Acceptance Criteria) Total Cask S1:1rfaoe Dose Rate _ _ _ mRemJhr (a¥erage neutron ..... a*,erage gamma) (<60 per A888ptanGe Criteria) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 66 of 122
- c. Inlet and~ ScNJen .,,._ gamma dose rate. Newtr-eA *Ad gamma meNWAtd **11*~t.
NOTE: ValUM for all four Inlet and four Outlet screens should be recorded. QJ.dllt Screeo §yrface Newtr-OR Gamma North .3 mRem/hr East ; 'i mRem/hr South , ). mRem/hr West ,3 mRem/hr AtJeFage NeutFon mRemJlu ~ (<17.6 peF AcseptaRee GFiteria) Average Gamma . 3 mRem/hr 'Y (<aQL~ per Acceptance Criteria) Total outlet dose rate mRemJhr (<307 i:>er Acseptanee GFiteFia) (A¥erage neutron
- a1.-eFage gamma)
DFS..ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 67 of 122 OF8-IIF81-2 RMillon 0 PEAFORM*FtNAL DOSI. . IIATE.SUflYEY Paoe* 10 of 13 TECHNICAL SPEOIPIOAtlOH 5.3:S .
. ATTACHMENT 1 W15Q STORAGE OAS Pda BAIE SURVEY SHEET Inlet Screen §vrfaa Nt\ltf9A o,mma North - - -
- mRem/hr
, ').
East mRem/hr South .3 mRem/hr West
- - mRem/hr
.A.tJeFage NeutFaA mRem/.hF F) (<5.3 peF .'\888ptaRee CFiteFia)
Average Gamma ~ 1 mRem/hr y ( < ~44.0 per Acceptance Criteria) Total inlet dese Fate mRemlhF (<18.3 peF .A.ooeptaAee CriteFia) (Average neutron + ayerage gamma) DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 68 of 122 DFS-ISFSl-2 Revilk>nO PERFORM FINAL DOSE RATE SURVEY Page 11 of 13 TECHNICAL SPECl~ICATSON 5.3.5 ATTACHMENT 1 W150 STORAGE CASK PQR RATE SURVEY SHEET
- d. Five measurements taken on the top lid, with one reading from the center and the other four taken at equal spacing 30 inches from the center. NeutreR aRd gamma meas1:1red t.eparately (all values in mRem/hr).
Center Location #1 Location #2 Ne1:1troR Gamma Ne1:1tr-oR Gamma Ne1:1troR Gamma Location # 3 Location #4 NeutreR Gamma Ne1:1treR Gamma ft.i.ierage NeutroA Dose Rate ___ mRemthr F) (<3.2 per Jlc,oseptaAse Criteria) Average Gamma Dose Rate -<-'. ;, mRem/hr y (<lii-14:i per Acceptance Criteria) Total Cask Top Dose Rate ___ mRem,(hr (a~<erage Ae1:1troA
- average gamma)
(<14.7 per ft.ooeptaRse Criteria) Gamma dose rate meter/serial# .,<:_t>_-_~___5_c,_3_/ Cal. due date ',&~/43 NeYtroR dose rate meterhlerial # Cal. d1;1e date (RP) (RS Supervisor) ::Jg le\=(~ Date ,.:,.,*0$ Date s- wJ-./8 I (DFS Manager) Date_ S*SO t DFS-ISFSl-2.doc
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 69 of 122 Section.*** 10CFR72: 835.1 .-..*.*~ be. ......
*.:.**** . v=
Big Rock Point Pta.,t ~ual Vofurne31, .OW Fuel ~ Technical Specifications, 104 .ae :*i . .:. *. ~ tti4t conaiclerlng t h e ~ : ~ of ~'Jitbe UMCI Ind the plann<~,:~/;,;~--;;~1,-/:;.~~i,~~-~~kJ~~~s:kW>.riii.;,;{;;;.,:.i*t)i~:~ji*!~1:jLii~~t . ,'.)"
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 70 of 122 Attachment B to Supplemental Response to NRC RAI ARCS1 Big Rock Point Cask Concrete Radiation Survey Data 2022, 2021, 2020 and 2019 (51 pages including this coversheet)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 71 of 122 RP Log Entry for 07-19-2022 Page I of 14 Completed the BRP ISFSI 2021 Annual and 2nd Quarter Radio logical Survey m accordance with RPG-28 on 06-29-2022. All radiation surveys were completed using RO-20 #1301 5 with a calibration due date of 09-30-2022. All smear s were counted on frisker PRM-6 #938 with a calibration due date of 09-30-2022. The operational check of the RO-20 on the 5 mrem /hr scale was perfon ned on the IO µCi Cs-13 7 sealed check source. RO-20 # 13015 response to the sealed source was 1.3 mrem/hr on 06-29-2022. The readings are consistent with the expected dose rate from the check source. The radiological posting signs at the ISFSI are clear, clean and concise. The postings are not faded, and they are securely fastened to the fencing. Line of site verification of no temporary residences was compl eted from the ISFSI location. There is no radioactive material stored on-site other than the sealed source, spent fuel and the Greater Than Class C waste in the storage casks.
- Late Log Entry due to inability to document surveys due to Holtec Transition.
JP J K Potter 07-19-2022 I 048
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 72 of 122 RADIOLOGICAL SURVEY ANO STA Page _1_ of J 4 TUS SHEET 06-29:2022 / l0J() UFI #24* 11-0 1 Techn,cian .JKfotter loca1,on JSFSI General Dose Rate* 0.1 mRem lhr(Y) N/ A mRem/hr(P) Area Posting* X RMA Conta m,nat 1on Area (CA; General Contaminat,on. _ _ _ NIA _ _ _ _ _dpml I 00cm ' X RCA O1her specify)
'.J Rad,at,on Area (RA)
Special lnstrucl1ons* , Nolify Rad Pro PRIOR to any *work Entry* Survey Meler Requir ed 1n HRAs 7 Air Samphng Requi red for Entry X O1her (Speci fy) FRISKJSG EXE:-.IPT dpm/100cm' 7 dpm/1 00cm' 13 dpm/100cm' dpmlt0 0cm' 19 dpm/l0 0cm' 25 8 dpm/l0 0cm' 14 dpm/100cm' 20 3 4 dpm/100cm'
. dpm/100cm*
9 15 N *-d ml dpml100cm' 27 dpml1 00cm' 10 dpmll 00cm' dpml100cm' 22 dpm/100cm' 5 _dpml100cm* ____dpm/1 00cai' _dpm/ 100cm' 17 A dpm/100cm' 23 dpmi100cm' 28 29 dpmll 00cm' 12 . dpm/100cm' 18 _dprrf1 00cmt dpm/100cm' 24 dpml10 0cm> 30 dpml1 00cm' Commenls All dose rates are General Area Dose rates in mrem/hr. Map Ket # =General Area Dose Rate CiGA = Contact and General Area Dose Rate
--X** X* = Radiological Boundary 0 = Smear Location LOWA = Low Dose wa,t,ng Area
* = Hot Spot D. = A,r Sample Location Abbreviations/Units* NOA- No Detectable Ac1iv11y (<1000 DPM) CCPM - Direct Frisk Reading Result 0PMJ100cm'
- Smear Reading Result ot rrR n:,;n 1,~1~ H~n 1----------------~------
1 ------------------------
< 0.1 ------------------------
< 0.1 <0 I ---------~----- -----i
< 0.1 oI OI , O; .__ 0 I ll I OI I
,< 0.1
<01 <01 < 0.1 <0 I 01 <0.1 <OJ
- ,, 0 I < ul CASK J - SKID
< 01
<01
< 0.1
< 0.1 I
- < 0 I
<0.J
'G 610 0.1 0.1 O.l 0,1 GO! 0I 0 I 01
< 0 I 0.1 0.1 01 OJ 0.1
).{~) 0 G 0 0 0 I
- < OI tl.l 0.1
<01 0.1 0 I 01 01
< 0.1 '
, < 0.1 <0 I < 0.1
'*-****-*-*~*-****
< 0. I <0 I , OJ
*************---** <0 I < 0 I < 0.1
< 0.1 :
I -*MW l--~---**-******-
*-*-***~******-**
I
--------****-* t RO2 0/#l 30l5 09-30-2022
_ Cow,t ,rg !ml ISt:t.. NIA
~!!1 ~~/h : _!!5__~ot__l:.._r_;t_____-~? 6-2 9-2 022 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 73 of 122 RADIOLOGICAL SURVEY AND STATUS SHEE T Page _J_ of .H.. . 06-29-2022 I IO 15 UFI #24-11-01 Oate/Time Location ISFSI General Dose Rate: NI A ____ mRemlhr(Y) Ni A ____ mRem/h<iJ3l Area Posting X RMA Contaminat,on A1ea ICA 1 X RCA Other spec,fy L*.. General Con!am,nauon. NDA ...._dpm11 00r;m' Radiation Area (RA) Special lns!ructions* Notify Rad Pro PRIOR to any *wo1k Entry Survey Mete, Required in HRAs Air Sampling Required for Entry X Other (Specify; FRISKl\'.G EXEM PT --
~--*- *---~
NOA dpml100cm' 7 NQA _dpml100cm' 13 ..... <IPm/100:m' 19 ~._d pm/l OOc m' 2 NOA dpml100 cm' 25 _@A .*- ... dpm/100 cm' 8 NOA dpm'100 cm' 14 .. N'JA.~ .-*dpm/ tOOcm ' 20 ._dpm/lOOcm' 26 _liQA.. 3 NOA dpml100cm 1 9 NOA dpml100cm' dpm1100ccc* 15 pml100cm' 21 NOA_ _ 4 !:jQA dpm/100 cm' dpmltOOcm' 27 . NDA_ _______ dpmi100 cm' 10 NOA dpmilOOcm* 16 NOA dpm1100cm* 22 NOA dpm/100 cm' 5 NOA dpml100cm* 11 28 --1:!Q, L dpm/lOOcm' NOA dpr1/ 100cm' 17 NDA dpm,100 cm' 23 .JtQ!1_ _____dpm/tOOcm' 29 _;Y.A. _ _ _ dpm,100 cm' 6 NQA dpm/100 cm' 12 NQA dpml100 cm' 18 .. NOA -***--dp m/lOO cm* 24 ~ ___ dpmllOOcm' 30 ..l:!!..L.___ dpmi100 cm' commenIs. Smears 23 - 27 taken on the horizontal surface of the electrical boxes. Smear 28 taken on vertic surface of A/C unit vent. All other smears samp al les taken on concrete surface Map Key =General Area Dose Rate C/GA = Contact and General Area Dose Rate
= Smear Location
-*X**X * = RadioI091cal Boundary LOWA = Low Dose Waiting Area " = Hot $pol Ll = Air Sample Location Abbrevia!ions/Uni!s: NOA - No Oe1ec1able Ac!iv ty ( < 1000 DPM) CCPM Oirec1 Fnsk Reading Resul! OPM/100cm' - Smear Reading Resull Ol TFR H-"-CI'
~-**------------------------¥~------------------------*--------
1
-----~-------~-*---------------------
I t1 J
- SKID
@ G i'f~ f:::\ ~ G( j)r ::\ (,:\ © V&V V@ 510 V @ (:;
North ----+ JK Potter .%-- BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 74 of 122 Page _4_o f 14 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24*11-01 joatefT ime 06-29-2022/ 1040 Technic,an JK Potter l General Dose Rate NJ A .. mRemfN iYl NIA mRem1n1{!3) Area Post,cg RMA Location* CASKS Contam ination Area (CA) I General Contarninat,on NDA dpml100 cm'
- RCA _;I{ Other spec,fy L !'Lo.TIL I Radiation Area (RA)
Special instructions Notfy Rad Pro PRIOR to any Work E1try SuNey Meler Requred ,n HRAs A,r Sampling Required for En!ry X Other (Speofy j None dpm11COcm 1 dpmllCO cm' 8 dpmJ100cm 1 13 dpmf100 cm 1 I 19 dpm/100cm 1 25 dpml100 cm' 14 120 do _dpm/100cm 1 dpml1C0cm' 9 dpml100 cm' 15 ! _dpm/100cm' 27
, _dpml100cm' dpml1COcm' dpmllCG cm'
'0 dpml100c dpmll00 cm' 11 II 22 23 dpm/100 cm'
_dpml100cm' 28 29 dpml100 cm* pml100c m' 12 dpin/100cm' 18 ! 24 dpml100 cm' 30 dpmi100 cm' dpc,1100 cm' I Commenis: All dose rates meas ureme nts are on conta ct with the vent/cask. All dose rates are in mrem/hr. Map Key # = General Area Dose Rate = Co<'!ac1 and General Area Dose Rale CiGA 0 = Smear location
--X--X - = Rad,o!og,cal Boundary LOWA = low D,se Waiting Area * = Hot Spot 6. = Aor Sample Location Abbrev*ahons/lJ.,,ls, NOA - No Deleclable Ac1,v1ty ( < 1000 OPM) CCPM Direct Frisk Reading Result DPM/10 0cm' - Smear Read ng Result 110 0.1 0.2 NDA 0.1 I
1 I 0.1 NDA 0.1 0.1 i NDA 0.1 0.1 NDA i 210 0.2 0.3 I NDA 0.3 l 0.2 NDA : 0.2 0.2 j NDA 0.2 0.3 NDA II 310 0.3 0.2 : NDA 0.3 II 0.3 NDA 0.3 0.3 i NDA 0.3 0.3 NDA i 410 0.2 0.2 *: NDA 0.2 I 0.2 NDA 0.2 0.3 [ NDA 0.3
;---- ----+-----------,--.***----
+----1----+----+----'---- 0.3 NDA
! 510 t
----+--------i 0.3 0.2 I NDA 0.3 0.3 NDA 0.3 i
0.3 i NDA 0.3 0.3 NDA I 610 0.2 0.2 \ NDA 0.2 0.2 NDA j 0.2 0.2 '. NDA 0.2 0.2 NDA i 710 0.3 0.3 \ NDA _ 0.3 0.3 NDA 0.3 0.3 1 NDA 0.3 l 0.3 NDA j 810 0.2 0.3 NDA 0.3 0.3 NDA 0.3 0.3 : NDA 0.3 l 0.3 NDA RO20/# 13015 09-30-2022 Dose Rate Meteri N NIA NiA al Due: PRM-6/#938 Ct<,1/Jtlr,g '"t\/51'( _ _ _ _ _ _ ,;;ii .R\<L_09-30 __
-2022
~r~rn ~... JK Potter_ 1f.- -~Y _6-2 9-!0 22 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 75 of 122 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11 06-29-2022/ 1120 JK Potter Technic,an: Location TRAN$f]::'.RCASK General Dose RaIe. < 0.1 mRem/hr(Y ) NIA mRemlhr(p ) Area Posting RMA _ Contamma tion Area (CA) NDA RCA X Other specify) No~ .. General Contam1nalion: dpml100cm ' Rad1alton Area (RA, Special lnslruclions Notify Rad Pro PRIOR to ar1y Work Entry* Survey Meter Required ,n HRAs Atr Sampling Required for Entry K Other (Specify)_ ** None NQA dpml100cm' 7 NOA dpm/100cm* 13 NOA dpml100cm* 19 .lliM. dpm/100cm* 25 NOA _dpm/100 cm' 2 NOA dpm/100cm' 6 NQA dpm/100cm' 14. NQA dpml100cm' 20 ~ . dpmi\OOcm' 26 ..tl!Qa. _dpm/100cm* 3 NOA dpml100cm* 9 NOA dpm/l00cm* 15 NOA dpml100cm* 21 NOA _dpm/100cm* 27 ~ . dpm1100cm' 4 NOA dpm/100cm' 10 NOA dpml100cm* 16 NQA dpm/100cm' 22 l'ID,A. . dpm/100cm' 28 1:lQt,_ _dpm/l00cm*
- 5. NOA dpmll00cm ' 11 NOA dpmll00cm* 17 NOA dpml100cm' 23 -~ dpm/100cm' 29 1:!l/A.... dpm/100cm*
6 NOA dpmll00cm ' 12 ~-dpm/ 1-(Jl)cm
- 18 NOA dpmll00cm ' 24 m_~ dpm/100cm' 30 ~ dpml100cm '
31 .!:!.QA dpm/100cm ' Comments: All dose rates are in mrem/hr on contact and at 1 foot. Smear 1, 2, 22 and 23 on end bell mating joint. The Transfer Cask is labeled as "EMPTY". The Transfer Cask is labeled as "RADIOACTIVE MATERIAL". Map Key*. # =General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X ** X * = Radiological Boundary LOWA= Low Dose Waiting Area *=Hot Spot 6 = Air Sample Location Abbreviations/Units NDA- No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Result OPM/100cm '
- Smear Reading Result
<0.1 North Q):
i
< 0.1
;@ : <0.1 <0.1
< 0. l <0.1 G)j @ < 0.1 0.1
- @\ ~@*
" .* - *.* * *r *. -
< 0.1 < 0. l
@*@ \
,\********: *-*** 0.1 < 0.1
*:*--*-***{ -***----
<0.1 C'E:-..TERLINE BOTTO~!
JK Potter 9# BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 76 of 122 Page _()_ of _!_i_ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Date/T,me* 06-29-2022/ 1130 Techn.c,an: JK Potter ' "'----- , Locat,on TRAN SFJ:R CASK SKID General Dose Rate. NIA _mRem1hr(Y) mRem/hr{j3) Area Posting RMA Contam nation Area (CA)
** RCA Non_£____
General Contami nation NDA . __ dpml100 cm' Cl( Other specify)_ Radial on Area (RA} Special lnstructIOns Notify Rad Pro PRIOR to any *work En1ry* Survey Meter Required in HRAs Air Sampling Requ,red for Entry X Other (Specily)_ _~N~o_n~e___ ___ NQA dpm/100cm' NOA dpm/100cm' 13 NOA dpml100cm 1 19 2 NOA dpml100cm' 8 NOA dpml100cm' 14 NIA dpml100cm' 20 3 NOA dpm/100cm' 9 NQA dpm/l00 cm' 15 NIA dpml100cm' 21 4 NOA dpml100cm' 10 NOA dpmll00 cm' 16 NIA dpmllO0cm' 22 5 ~-dp m110 0cm' 11 NQA dpml100cm' 17 NIA dpml100cm' 23 G ~--dp ml10 0cm' 12 NOA dpm/100cm' 18 NIA dpmll00 cm' 24 Comments None Map Key # =General Area Dose Rate C/GA = Contact and Gee.era! Area Dose Rate 0 = Smear Location
--X--X * = Radiological Boundary LOWA = Low Dose Wa,t,ng Area *=Hot Spot £1 = Air Sample Location Abbrevrations/Units NOA - No Detectable Activity {<1000 DPM) CCPM - Direct Frisk Reading Resull OPM/100cm'
- Smear Reading Result North I
0 I 0 q *0
©*
©
*1
[ Oo,e R,a1, M,t1,r1st,1 NIA N:A I Co~"!IOO 1mt.1fil:!.;___...PRM-6/#938 09-30-2022 JK Potter BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 77 of 122 Page 7 of 14 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Daleffime 06-29-2 022/ 11 l 5 Technician* JK Potter Location -~J=---~S~K~l=D=-------- General Dose Rate: < 0.1 mRem/hf1Y) N'A mRem/hr(j)) Area Posting
- RMA Contamination Area (CA)
General Contamination. _ _N_D_A
-- RCA - Other specify) None
___ dpm/100cm' RadiatiOn Area (RA) i Special Instructions* Nolify Rad Pro PRIOR to any 'Wort< Entry' Survey Meter Required in HRAs A,r Sampling Required for Entry OtMr(Spe cify)_ None NOA dpm/100cm' NOA _dpl'l'i100cm' 13 dpm/100cm* 19 2 NOA dpm/100cm 1 8 NOA dpm/100cm' 14 dpm/100cm' 20 3 NOA dpm/100cm 1 9 t:!QA dpm/100cm' 15 dpm/100cm* 21
- 4. NOA dpm/100cm' 10 NOA dpm/100cm' 16 dpm/100cm 1 5 _.t:!Q6 ._ dpm/100cm' .dpm/100cm' 11 NIA dpm/100cm*
. dpm/100cm' 29 dpmllOOcm' 6 ~--dpm /100cm ' 12 NIA dpm/100cm* dpm/100cm* 24 .dpm/100cm' 30 dpml100cm '
comments All dose rates are General Area Dose Rates in mrem/hr. Map Key # = General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X-*X* = Radiological Boundary = Low Dose Wailing Area LOWA ,. : Hot Spot Cl = Air Sample Location Abbreviations/Units: NOA - No Delectable Activity ( <1000 OPM) CCPM - Direcl Fr*sk Reading Result DPM/100c m'
- Smear Reading Result North
<0.1
< 0.1
<0.1 @
Dose Rate Meter/SN RO20/# 13015 09-30-2 022 NIA 10 e PRM~6/#938 c2wotm IMUSN: . - - - - . ---~" 'Q... a.LQ.11:L JK Potter BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 78 of 122 Page_ 8_ o f ~ RADIOLOGICAL SURVEY AND STATUS SHEET UFI #24-11-01 Date/rime 06-29-2022/ 1145 JK Potter ISFSI FENCE LINE Localion Gel'eral Dose Ra1e < 0.1 mRemihr(YJ mRemlhr('3) Area Posling - RMA Contam1nat1on Area (CA) RCA X Other specfyl None General Contamination __N_D_A ____dpmltOOcm' _ Rad1a11on Area {RA) Special lnstruc1ions Notify Rad Pro PRIOR to any Work Entry Survey Meter Required ,n HRAs Air Sampling Required for En!ry ~ Other '.Specify) None NQA dpm/100cm* NOA dpm/100cm' 13 NOA dpml100cm* 19 _dpm/lOOcm' 2 NOA dpm/100cm' 8 NQA dpm/100cm' 14 NOA dpml100cm' 20 3 NOA dpm/100cm' 9 NQA dpml100cm' 15 NOA dpml100cm' 21 4 NOA dpm/100cm' 10 NOA dpm1100cm' 16 NQA dpml100cm* 22 dpml100cm' 5 NOA dpml100cm' 11 !:(QA dpm/100cm' 17 NOA dpm/100cm* 29 dpmllOOcm' 6 NQA dpml100cm' 12 NOA dpm/100cm* 18 ....l!Q6.__dp mll00cm' 30 _dpm/100cm 1 comments All smears taken on horizontal surfaces of light poles or concrete surface except smears 1 and 14 taken in the interior of the buildings. All dose rates are General Area Dose Rates in rnrem/hr. Map Key: # ::: Genera' Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smea, Loca!ion
**X**X* = Radiological Boundary LOWA= Low Dose Wa,t1ng Acea * =Hot Spot t,,. = Air Samp e Location 1
Abbreviations/Units NOA- No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Resull DPMi100cm'
- Smea, Reading Result t <O@
@<O.I ©<0.1
< 0.1
@<0.1 @<0.1 North-- +
LP C Light Pl'!~ PJ Po11.i John
<0.1@
0 RO20/# 13015 iCal Due. 09-30-2022 NIA NIA Air Sam ler CalD e
~Jm_:r.$US Jt_____ PRM-61#93 8
____ "'"""'!J)w: -~-*3_0_-20==------":"""i~i:t ~ - - ... J Date 'f-/ (2-I_~ 2-p~rij;f~h JK Pottcr . .f . Date 06-29-2022
-.,,a, Cm,w,., ""'/Jf '7 Mo., zlziln BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 79 of 122 Page~ of 14 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 DaIefTime 06-29-2022/ 0940 JK Potter Technician Locat,on ISFSI POLE BARN General Dose RaIe < 0.1 mRem/hr( Y) NIA mRemlhr(P) Area Posting: RMA Contam1nahon Area (CA) RCA ~ Other specify) No~ General Contamination __N_D_A___dpmll00cm
- Radiation Area (RA)
Special InsIrucIions Nolify Rad Pro PRIOR 10 any 'Work Enlr 1 Survey Meter Reqwed ,n HRAs Air Sampl ng Required for Entry ~ Other (Specify) None NOA dpmllO0cr n' 7 NOA __ dpmll00cm ' 13 NOA dpm/100cm' 19 NOA dprn/l00cm ' NOA 25 NOA dpml100cm* dpm/l00cm ' 8 NOA dpm/100cm* 14 ~ - - d p m / l 0/xm' 20 NOA dpmll00cm ' 26 3 NOA dpm/100cm ' ~ . dpm/ 100cm' 9 NQA dpml100cm ' 15 NOA dpm1100cm' 21 _NOA _dpml10 0cm' 27 ~- dpml100cm ' 4 NOA dpml100cm ' 10 NOA dpml100cm ' 16 NOA dpml100cm ' 22 NQA dpmt100cm ' 28 NOA t>JQI\. dpm/100cm ' 5 dpm/lO0cm ' 11 ___l:illt,_ dpm/100cm ' 17 NOA dpml100cm ' 23 NQA dpm/100cm ' 29 ~- . dpmll00cm ' 6 NOA dpm/l00cm
- 12 NDti. .dpm/100cm ' 18 "!DI\ _dpmll00cm' 24 NOA dpm/100cm* 30 _ NOA _____ dpm/l00cm '
comments All dose rates are General Area Dose Rates in mrem/hr. Map Key # = General Area Dose Rate C/GA ::: Contact and General Area Dose Rate 0 = Smear Location
*-X**X* ::: Radiological Boundary LOWA = Low Dose Waiting Area * ::: Hal Spo1 6 ::: A*r Sample Location Abbrev,at,ons/Units. NOA No DetecIable Activity ( < 1000 DPM) CCPM - Direct Frisk Reading Result DPM/100c m'
- Smear Reading Result
< 0.1 @
@@ @ 0. I
<0.1 0 @
< 0.1
© (0< i) <o.d@ )
<0.1
<0.1 < 0.1 @
G) @
@<O .\ @ < 0.1 01
@ <0.1
< 0.1
("10(
< 0.1 0 @
+-- North < 0.1
< 0.1 Cat Due: 09-30-2022 Air NIA NIA al Due:
PRM-6/#938 09-30-2022
** C.ll1;n1,n9 ~!.Stt * * - - _________ _ ~ig Roe~ /)___ -:,. ( I 'f / 2- 2...
JK Potter
- ,. ,, afuJ~~--i-+"--~.-. Y~* =----j ,__1Qiffi-* ,J..+ll:c h-i BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 80 of 122 Page RADIOLOGICAL SURVEY AND STATUS SHEET of UFI # 24-11-01 DaterTlme 06-29-2 022/ 0845 Technician . JK Potter Locat,on ISFSI Road Central Gener al Dose Rate < 0.1 mRem/hn Y) NIA mRem/hr(I )) Area Posting -* RMA Con1amin alion Area (CA) General Contamina tion NOA - RCA X Other specify) None ___ dpm/100c m'
- Radiation Area (RA)
Special Instructions: Notify Rad Pro PRIOR to any -work Entry* Survey Meler Required .n HRAs Alf Sampling Required tor Entry X Other (Specify) None NQA dpm/100cm ' 7 NQA dpm/100cm ' 13 _dpm/100cm' 19 dpm/100cm' 2 ~ dpm/100cm' 8 NOA dpm/100cm ' 14 dpm/lOOcm' 20 dpm/10Ccm' 3 NOA dpm/100cm ' 9 NOA dpm/lOOcm' 15 dpm/100cm' 21 d 4 NOA dpm/100cm ' 10 NOA dpm/100cm ' 16 28 dpmi100c m' 5 NOA dpm/100cm ' 11 NOA dpm/100cm ' 29 ,dpm/100c rn' 6 NOA dpm/100cm' 12 NOA dpm/100cm ' _dpm/100cm' 24 dpm1100cm' 30 dpml100c m' Comments. All dose rates are General Area Dose Rates in mrem/hr. Map Key* # = General Area Dose Rate CiGA = Coniact and General Area Dose Rate 0 = Smear LocaI1cn
**X**X* : Radiological Boundary = Low Dose WaH,ng Area LOWA *=Hot Spot .6 = Ar Sample Loca1ion AbbrevialionslUn1ls. NOA - No Detectable Activity ( < 1000 OPM) CCPM - Direct Frisk Reading Resull DPM/100c m'
- Smear Reading Result
~~
<0.1
<0.1 @
SFJ Pok Barn Area
<0.1 Ci) l North
_QQ~Ra!eMe!ef!SN RO20/ #l3015 , LJI.Q11! 09-30-2022 Coi.vling in,tJSN PRM-6/~938, lal Du</- 09-30-2 022 f'iWQffi'.eg e~ JK Potter I(! oats 06-29-2 022 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 81 of 122 Page _ 1_1_of 14 OatefTime: 06-29-2022/ 0825 Genera' Dose Rate: General Contamination NOA _ _ _ _ _ _ _apm11oocm' RADIOLOGICAL SURVEY AND STATUS SHEET Technician: NIA JK Potter mRemlhr(j3) Area Posting: Location
- J RMA c RCA ISFSI ROAD NORTH UFI #24*11- 01
- J Contamina tion Area (CA)
X Other specify) None
-l
- Radiation Area (RA)
Special Instructions: Notify Rad Pro PRIOR to any *work Entry ;... Survey Meter Required ,n HRAs Air Sampling Required for Entry X Other (Specify)_ _ _N_o_n_e____ __ NOA dpm/100cm' 7 NQA dpm/100cm 1 13 NDA dpml100cm ' 19 2 _l!QA_d pm/100c m' 8 NOA dpml100cm* 14 __ .t!Qt__dpr nl100cm' 20 3 ~--dpm /100cm ' 9 ~_dpm/ 100cm' 15 NQA dpml100cm ' dpm/100cm ' 4 ~ _..dpm/100cm' 10 NOA dpm/100cm' 16 NIA dpmll00cm ' dpm/t00cm ' NOA 5 6 !::jOA dpm/100cm' dpml100cm' 11 _@A_~d pml100c m' 12~ _dpml100cm' 17 18
-NIA~ dpml100cm '
_dpm/100cm' dpm/100cm* 30 dpm/100cm ' Comments All dose rates are General Area Dose Rates in mrem/hr. Map Key #=Genera l Area Dose Rate CIGA = Contact ar,d General Alea Dose Rate 0 = Smear Locat,on
--X--X * = Rad,olog,cal Boundary LOWA = Low Dose Wailmg Area "= Hal Spot L\ = Air Sample loca!<On Abbr1WiaIions/Un~s NOA - No Detectable Activity (<1000 OPM) CCPM - 0:recl Fnsk Reading Result DPM/100cr n'. Smear Read,ng Result
~
< 0.1
@)
@ <0.1
<0.1© 0.1 0.1([)
0.1 01 0.1© 0.1@ l Banit'r,;
< 0.1 North Entergy Cvnsum.:r.; Energy P1opet1y Linc
< 0.1 CD D seR R020/# l 3015 lcar Due 09-30-2022 NIA NIA AirSam Ir: Cal 0 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 82 of 122 Pag e~o f~ RADIOLOGICAL SURVEY AND STATUS SHEET
-*-- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- UFI # 24-11-01 Dateffime; 06-29-2 022/ 0740 ______ Techruc,an JK Potter -=- ---- ~
Locauon ___,I=S=F~Sc:..1-=-R~O~A-=D_,S-e...'O"'-U=-"T.:..H"-_ General Dose Rate _ _ <_O_._l___ mRemlhr(Y) NIA mRemihr(Jl) Area Posling _ RMA ** Contamina tion Area (CA) General Contam,nation NDA
- RCA X Other specify) ..None
_ _ _ _ _dpml100c m'
- Radiation Area (RA)
Special Instructions -* Notify Rad Pro PRIOR to any *work Entry Survey Meter ReQUired :n HRAs
*- A,r Samp'ing Reqwred for Entry
- X Other (Specily)_ _N-1~o~n~ c~---- -
NOA dpml100cm ' 7 NOA dpm/lOOcm' 13 NOA dpm11 COcc-' 19 ___ NDA. _ _ dpm/100cm ' 2 NQA dpm/100cm ' 8 ___NOA **-** dpmllOOcm' 14 NOA .._ dpm11 CO cm' 20 -~dpm /100cm ' 3 NOA dpm/lOOcm ' 9 --*- NOA __ dpmllOOcm ' 15 NOA dpm!100cm 1 4 NOA dpm/100cm ' I 21 NIA dpml100cm ' 10 NDA _dpmllOOcm' 16 _ NOA ..._.dpm/lOC cm* , 22 ~jiA dpm/100cm
- 5 NOA dpm/lOOcm ' .... NOA _dpm!10 0cm' 6 NOA 11 17 ______1:/_QA _ _ dpm! t 00cm' I 23 NIA .dpml100cm
- dpm/lOOcm ' 12 _---1:!QA _._dpmllO Ocm' '
18 NOA dpr:11 100cm' 124 ____.NIA ___.dpm/100c m' comments All dose rates are General Area Dose Rates in mrem/hr. Road smear survey locatio ns align with utility poles. Map Key # = General Area Dose Rate CIGA = Contact ancl General Area Dose Rate 0 = Smear Location
--X--X- = Ract,ological Boundary LDWA = Low Dose Wa*ttng Area ,. : Hot SPot b. = Air Sample location Abbrev,aUons/Unils NOA~ No Detectable Achvity (<1000 DPM) CCPM Direct Fnsk Reading Result DPM/l00c m' . Smear Reading Resull Dose Rat M IPr/SN: R020/# l 3015 09-30-2 022 NIA AirSam ler Cal Q.l'=e;~_N_I_A___----1 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 83 of 122 RADIOLOGICAL SURVEY AND STAT US SHEE Pa ge~ of~ T UFI # 24-11-01 Date/Time- _ _ 0_6_-2_9_-_2_0_2_2_/_0_6_4_0___ __ Technician: JK Potter
< 0.1 location - LOWER ADMIN. BLDG, Genera l Dose Rate: _ _ _ _ _ _mRem/h r(Y) NIA mRemlhr(Jl) Area Posting C: RMA ::J Con1aminalion Area (CA) 1 ::.J RCA X Other specify) None Genera l Con1am,nation* _ _ N__D_A __ _ dpm/10 0cm' c., RadiatiQn Area (RA)
Special lnstrucll ons: :J Notify Rad Pro PRIOR to any *work Entry*
- Survey Meter Requ1ted in HRAs
- Air Samplin g Require d for Entry X Other (Specify ) _ _N~o ~n~e ~----
1 NOA dpml100cm' NOA dpm/100cm' 13 NOA dpm1100cm' 19 _<lpm/100cm' 2 NDA dpm/100cm 7 8 25
!!Q6._ dpm/1 00cm' 14 NDA _dpml100cm' 3 _l!M . _ _dpm/100cm' 20 9 _____l!QA. _ _dPmil00 cm' 15 -~_d pm11 00cm '
4 NOA dpm/l00 cm' 10 NOA dpm/100cm' 16 -~-d pm/l 00cm
- 5 [::!DA dpm/100cm' 11 NOA dpml10Dcm' <lpm/100cm' 17 NIA dpm/100cm 1 6 ~ _ _ dpml100 cm' dpm/100 cm' 12 NOA dpm/100cm' 18 _ ______WA.. dpm/100cm*
30 dpml100cm* Comments All dose rates are General Area Dose Rates in mrem/hr Map Key: # = General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X**X - = Radiological Boundary LOWA =Low Oose Waiting Area *=Ho t Spot l'i = A,r Sample Locatio n Abbreviat,ons/Uni!s* NOA - No Detecta ble Activity ( < 1000 DPM)
CCPM - Direct Frisk Reading Resul1 DPM/10 0cm'
- Smear Reading Resull
< 0.1 Stairwell (j) < 0.1 <0.1
<O.l CD G) <0.1
< 0.1 0 0.2 North
©
< 0.1 Q)
< 0.1
< 0.1 0
< 0.1
<0.l DoseRa M ter/ N* RO20/#13015 Cal Due: 09-30-2022 NIA NIA AirSam ler.
I Due: PRM- 6/#93 8 BRP151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 84 of 122 RADIOLOGICAL SURVEY AND STATUS Pa ge~ of~ -- SHEET I Oatem me 06-29-2022/ 0700 Techn,cian: _ _ _ JK __P_o_l_te_r__ __ __ __ _ UFI # 24-11-01 I General Dose Rate. Locaoon* UPPER ADMIN. BLDG.
< 0. I mRem /hr(Y) NIA mRemfhr{P) Area Post,n g C RMA C Contam ination Area (CA)
NDA ::::; RCA X General Contam1na1ion: _ _ _ _ _ _ _dpm/1 00cm' Other spec,fy) None Radiation Area (RA) Special Instructions* Ci Notify Rad Pro PRIOR to any Work Entry* _ Survey Meter Requ,r ed in HRAs Air Sampli ng Reqwe d for Entry X Other (Spec,fy)_~N_,_Q=n=e__ __ __ NOA dpm/100cm' NQA dpm/100cm' 13 .......@6.._ _dpm/100Cm 1 19 dpm/!OOcm* NOA dpml100cm 1 8 _lli1: L,_dp m/10 0cm' 25 14 NOA dpm/100cm' 3 NOA 20 dpm/100cm' 9 NOA _ _dpml100cm' 15 ~--d pm/ 100 cm 1 21 4 NOA dpm/100cm 1 10 NOA dpm/100cm* 16 NIA dpm/100cm' 5 NOA dpm/100cm 1 22 11 NOA dpm/100cm* .,,..,,i\ ,-----d pm/10 0cm'
- 17. !:!/A_ dpm/100cm' 6 NOA dpm/100cm 1 12 NOA dpml100cm 1 dpmll0 0cm' 18 N/A dpm/100cm*
30 dpm/10Ccm' Comments All dose rates are General Area Dose Rate s in mrem/hr. Map Key: # = Genera l Area Dose Rate CIGA = Contac t and Genera l Area Dose Rate 0 :: Smear Locatio n
-*X**X * = Radiological Boundary LOWA = Low Dose Waiting Area
* = Hot Spot ,1 = Air Sample location Abbreviations/Units* NOA - No Detect able Activit y(< 1000 DPM)
CCPM D11ecl Frisk Readin g Result OPMl1 00cm'
- Smear Readin g Result North
< 0.1
- 0) @ ..,._.. 'itairw dl Down
~- < 0.1 0 <0.1 I
< 0.1
< 0.1
< 0. l @ @
/
\
3)<011 ) <01
< 0.1
< 0.1 0 < 0.1 (0
~/
CT) (j) BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 85 of 122 RP Log Entry for h-22-2021 Page I of 14 Completed the BRP ISFSI 2021 Annu<1! and C)uarkr Radiological Survey in accord,mcc with RPG-28 on 6-22-202 ! . All radiation smvcy s were completed using RO20 # l t
/XS, \\'Ith a ca!1br<1tion duc date of l 0-31-2021. All smcc1rs were counted on frisker PR\1-C 1 i 1 9(lJ, with a calibrati(1n due date nf!2-3 1-202 1.
The operational check of the RO20 on the 5 mrcrn ihr scale was performed on the IO pCi ( *s-137 scaled check source RO20 # I l 785 response to the scaled source was
- l. I mrcm thr on 6-22-2020. The readings me consis tent with the expected dose rate from the check source.
The rncliological posting signs at the ISFSI arc dear. cbm and concise. The ptistings arc nut fndcd, and they arc secure! y fastened to the fcnci 11g
.inc* r0 1' site \*cnfication ,li'no temporary residences 1,*:a, co:11plctul from the ISl-'Sl iucatio11 There i~ 110 radioactive material stored on site other th;111 the scaled source. spent fuel nnd the C,rcatcr Than Class C waste in the storage casks.
r~/.-* LI r KFPallagi C,-22-2021 17:20
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 86 of 122 F~ADIOL.OGIC!\L SUR VEY AND STA Page '> of 14 TUS SHEET 6 22-2021 iJ 3:()l) UFl# 24-1 1-01 K.Ll 'alla gi () ISFSl X RMA on NA X f,CA HilAs X f'RhK l:-:<i t.\i*\1 1'1 dyrrflO O,:n 1 dym! 100cm ' 20 dprt'i10 0crn 1 JJµ1n/ "- 10 22 17 A 23
*Jp1, 11 10\Jcm '
2*1
- Jpm'H '!Oun:
cocnnie,*!5 All dose rates are General Area Dos e rates in rnrern/hr.
; ;\ f I f ! \i I nl !l I !li il I oI 01 OI 11.I ll I 111 01 ll I IJ I 01 11 I '
11 I r *SKID t ] Ii I p ! I tl I (. -,
' <III ,; I
,,_1~)*1 I ,11 !JI 111 ll I 01 I! I f/l c~,~ DOI II I 01 01 01 01 0~~0 11.I
(~~ 01 _/ oI
< ll. I
*<O I <01 01 UI < fj 0 I <01
- ii I '!JI North ***
10-31-2021 KEP allag 1 NIA 6-22-2021 f::::"'b;;\ ,_ _ __"__________ Date*- ------- --~-~- --
.b. .M ~ .£:.d~-~D=a!e~v.,_.../2-2/z~ ,
~.£/l~
BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 87 of 122 RADIOLOGICAL SURVEY AND STAT US SHEET Page 3 of 14 li-22-:1021 .' l 2 55 UFI ff 24-1 1-01 K.L, Pallagi N,-!\ lSFSI X RI.IA NDA X p,*,_ 25 NDA 1 .1 t!Q~~ n !illA 3 tlOA i5 ~{Qi~:
,l tlQA_ drm! !DCcn1 1 dpT-flOO:,inr 16 dp<Fl1 00crn' NpA dpr:,Jt:J(\:rr/ dµn ttOC::m !
dr,n1! 1GOr.m' 17 till£~ (;prn/10Gcm 1 18 @A_ L'J t)I-:\
?.I t!'+/-\
con@e n1s Smears 23 - 27 taken on the horizonta l surface of the electrical boxes. Smear 28 taken on vertical surface of A/C unit vent. All other sme ars samples taken on concrete surface 0 = Smear tocct!:on G l~1
@ G i\'ort h Do,e Rate Me~S N ___________ _
N;A Pertormed By __ -K_:~:_11allagi / BRP 151 01/1512019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 88 of 122 Page 4 of 14 UFI # --- 24 --- -~ --- 01 6-22-2021: 12:46 - -- K.E.Pallagi Locaton _CASKS _ Con'.a,n,r'a\:c.1 .<Vea (CA.; ND!\ X 0,1 ,,. spec,\; i'lonc dpmt!CCc 01 1 I dp:r!lCC,:,rn'
'3 dpm'!O\}:-n: j 1) dr:r:i,*H'!J cm*
1-1 dprn/lt;o :m' "' dr,rJ1C:C un 1 _ dprr!lCC un' 9
'}
Vi N _dpw/10-\~*, ;
/ 20 d1rw dpnvtGOcm 1 2?
dprp!lOO:rn 1 22 dprnll00r m' A
*~
17 All dose rates meas ureme nts are on contact with tile venl/cask. All dose rates are in mrem/hr. t,,tJp r<ey # :: Ger er JI Ar2i1 Dose Rt1te C-'G,\:::: CJ<t3c! Jnd G1~ner,1 1!\11::1 Oase Fate
-~X--X- :,::
0 ::: SireJ; Lc<::tt nn U:nJ '.:.'.G')'Cc!l B<}'Jf :J,ir, LOWA ::.: ~ ,-,/, Ce;:~ \Vad'n;J t\reJ
' ::: 11,-t Sr,c! 1\ ::.: /'*:i ~,;w1r; 1e l c: 'J;-,,n
/\G'Yr--,<-it c,n::;: UPi::, NGA i',l' O::'.t;( !.Jh 11* A,:t, ,I'* f i,,: L':: 0 f)i~t. 1 } c{::*u (}r,-1:! Ft $!-, P~;d f: ) Ht'":;t H Uf-l~.t* 1Cr S*1;e,H R ~w1,1-.,J F~~ .. *r 0
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> (/) ,_J (/) .3 > 2: ::; 2; > ~ C, ?.::
I 10 U) (/) -l (/) 7. > 7. :1 7. ....J
<0 I < 0.1 NDA 0.1 , 0.1 NDA 0.l < 0.1 NDA 0.1 < 0.1 ND/\
210 0.2 0.1 NDA () 2 0.1 ND/\ 0.1 0.1 NIM 0.1 0I NDA
- 10 0.2 () 2 NDA (U 0.2 ND/\ il.2 0.1 NDA 0.2 0.2 NDA 410 0.2 (). I NDA O.l 02 NDA 0.2 0.1 NDA 0.2 o. I NDA
'110 0.2 O. I NDA 0.2 o. I NDA 0.2 O. l NDA ! 0.2 610 0.2 0.1 NDA () 2 O. l NDA 0.2 0.1 NDA
~::[.
0.2 l I 710 810 0.2 0.2 0.2 Cl. I NDA NDA 0.3 0.l 0.3 0.1 NDA 0.2 [ 0.2 NDA 0.3 0.2 0.2 0.1 NDA 0.2 I O.l NOA J _ Dose H?!e ~1etenSN _
. Co,ni;rg_1ns1 iSN __ _
RO20 /#l l 785 PRM-61#969 C:al Due
.I Ca! Dt.e NI A ~---~-
-- - --~----- ---~
K.E.Pallagf.,.... _Q;1 le d 2..J, /
------ -----~ 2- J 6-22-2021
. *---------*- Dale Qate ~Lzl)~t.>_?l BRP 151 01/15/ 2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 89 of 122 RADIOLOGICAL.~_UR\(EY /\ND STATUS SHE:_ or 14 l::I 6-2'.1-2021:'l 3:22 ---UFI tt 24-11
---- -01 Ger--2-rJ: Do:::e Ra:e oI TR ANS FER Ci\S K
/uez, {CAJ Nl)A Rc.A X Other None St.:r:ey Mel,;~, R,-; -:;;,ited :r; HHA s X Nt)l1C
\J 14 tL~~>-- _dpr, 1 t10Qcrr/
3 NOA (iJ::rnIHJOcrn' 20 *,l)A 9 !:l?A t{J_~ d1J Pfto0rm '
~.Q!~ fJ;rnf1COcrn 1 tLQt dp11,!10{)c,t;'. 1U N._1/~\
21 ~ill-~\__ ___ 2? dprn!H)O,,m' IG HQ/~ dp.v!l 00:::rn' 11 NC)~~ n NOA dpql 1OOc,r/ I" dp r/100::rn ; LJ
!? f~Q!\ d;w1i10!}_:rr. 1 29 ~~[)~
le 2-1 nf~!\ dP'ni100 C*ll 1 31 NDA dpn°'100crn> Ccmments All dose rates are in mrem/hr on contac t and at 1 fooL Smear 1, 2, 22 and 23 on end bell labeled as "EMPTY*. Tr,msfer Cask is latieled as FU1DIOACTIVE MATE mill*ng joint The Trarisfer Cask is RIAL" 0 North
- 01 0.1 @ @
i
< 0.1 G) 0.1 I). I 0: 0 @ 0.1 < 0.1
@)
0.1 (l I G) @
.. ~ . 0.1 O.l
@ 0.1 cF:-:rrnu:-;;:
BOT IO.\I
. Dose Rate_Me!eNSN 2 11785 R0 0,'_fl____ ___ .___ ., ____+"=-""'" I 0-3 l-2021 NiA I PRivt-6/#969
___C::ounlin_g 1,wlSN ------ *------
- l2-3!-2021 Air S..i!D.1Jl,er 819 Reck
... Re*,!!)wegJl_y ....
.. Cal N1A Ow, _______ __________
K.E.Pallagil Lv-' 6-22-2 021 Date b_/zs /202( BRP 151 01/15 i2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 90 of 122 BA12JQL9GICAL SURVE Y /\ND STATU ;,J?li!;_ U Page (1 or 14 6-22-20 2!/!3 27 --UFI
- # 24-11-0
--- 1 K Ef'aliag i TRANS FER C'ASK SKID N'A Ni.'\
RC,,\ X O!hPt '",r~:of1) N_~~-P~ P'aj1Jt1*y; Arf:a (qJq I, dpn.:10G.:rnt I~ 9 opm! 1CO:~*r' d;:,n1/10Dcni 1 df,.11'~ ,:;o._,n' _U;.,rr!\)T:1, \ 1 19 20 Vi di::m:1CO;_:n1: 21 dptP!Eli':r;1n i dfr"'i10Gc1r' durn!1.J0_:::in' 22 di,rr~/ i ,JCcn1 1 11 ~1~'*ni 100:.:m' 6 13 NUA CtnA ::: Contar:I ano Ger*er:1! Area Dcse Hale 0 :::: Sn1ear Lccat:on Nurth CD
@ r G)
Q) G) l 0
~*.
--0--
6-22-2021 BRP 151 01115/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 91 of 122 Page of 14 RAD IOLO GICA L SUR VEY AND STAT US SHEE T 6 22-2021/13.31 UFI # 24-11 -01 K E.Pallagi J - SKIJ) Ccr,un w1J!J( n Are:3 {CA.} NDA svocify ) None t,.ieter R*Jq,,'re'.:l Hf~/\s t\onc c,omme,.,, All dose rates are General Area Dose Rates in rnrem/hr. North
© (j) 0.1
- 0.1
-----(2)-
-*-*** -*---- --.--- -*-*** ***-*- ~
<0, 10! )
Dose Role Me.lerlSN .. RO 201/i ! l 785---f-"-"--"'""*--*-*-l_0__-._3__! -.2___0_2_..l. -- PRM -6!#969 f__S:1t;r1J1n~ l~s1 IS_N_*. __ l 2-3 ! -2021 Performe_d ft:;_ __ KEP allag il / ,,....,- BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 92 of 122 RADIO LOGIC AL SURV EY AND STATUS SHEET of UFI#2----
------- 4 01 K.LP;dl:1gi 1S FS I FENCE LINF O.l NA n,Re*,*,wr;p) I ND/\
N::-!,f1 Ra,J PD P/',UOR to an; V/v'r-. (ntiy f...;r 3,1n1r) ., sJ f{t,:;t, re:1 (( r [p'i y IJ
-~dpa*,;JC Ctm' 8 11 3
9 15 dpwllGO un; dt;;-J1UC<01 1 \1 dp,r/1GC rr;1' 17 dp1)1!l:JO un 1 dp,11 1'\0Ccm' rJ;m"i1Cl :cn/ dµ,n/lG1k 1r! (!p:r!1':::0C !:l; ccnvncn1s All smears taken on vertica l surfac es of light poles or concrete surfac e except smear s 1 and interior of the buildings Al' dose rates are General 14 take:i in the Area Dose f~ates in mrern/hr. lkpKr,, 0 ::: Sn12ar lOC3li0'1
~ ~ I k'. Si;,y /\ :::: /.. r S:F11pl~ t*:,::Ji:01*
() 1
@0.1 @*0.1 0.1 0 O.l I I' l.1rln I',+:
Pi p._11t:1 J1ilm Q
<Ol
<01 cf!L0< O.l
""" """ ""-"" " R020/il 11"185 t"Ca~D::""" I 0-31-2021 Ccun11r~!ns!)SN PR-;[-6if;96l) .
- 12-31-2021
(_Y Pe1f0m1e_tL8y . . K.E.Pall~!s_l(t~---. oa.:~ 6-22-2021
~:,:,ewe qj3y t4U, I~ tf!: ~ .. Date 1.,/~:r/2oz1 c4- ,7- /l-- --- -
BRP 151 01/15i 2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 93 of 122 Page tJ of 14 81\[)IQLOGICAL SUHV [Y AN[) STATUS SHEFT UFI #24-11 -01 K .E.l'al lag1 Lccat,cr ISFSJ POLE BARN N:A RCA :X :::i:he, ;p,:,-,,111 None Rt1,hH :_;;- /ue;1 {fUq IJ 25 dpr;~Jt('1Jcm* 11 15 Ui;:n!iCOc m 1
*1 t,J df,inftC!J: m 1 5 d;.Fr' 100cm' 28 17 G 23 13 dpm/10Gs ni 1
?4 ccrnme,;1s All dose rates are General Area Dose Rates in mrem/hr.
0= Smear Lcc:1t LOWA:::: Low Dose
" ::::: H:-:: Sf;-)t 0 I 0
0 I
@-0 1 01 O.l 11.!
© @
@ .0 I
@ UI 0.1
@ @ < 01 Nunh @ < (l.l
_Dos<1Rate MeteriSN* R0 20 1# 11785 _Cal_Oue_ N!A
.. Coun~_l nst lfil{
K. Fl>a! lagi I 1,
....c=D"='e~bL~_!___ _
Performe1J By 6-22-2021 Date 4'/2-S/ZOZI BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 94 of 122 Page 10 of 14 6-22-2021 Ii I :25 1-01
-- .. *-~**~*--*
K.1 PaHagi
<01 ISFSI Road Central N1A Area RCA X o,,,f"f srer:fyl None
!:' ~{f{,\s N, nc dp1n/100u11' 5 dn1-,'l0Ccn 1' 11 NQA 12 NQ>\ dp,n/10Dcm r co,111nen1s All dose rates are General Area Dose Rates in mrem/hr.
1\
<01 01(3)
,,i1@
01 (3)
<0.1 CD l North I 0-31-202 l NIA Co~ntiq lLlU.Sl:LI>RM-6/#969 .. 12-31-2021
/1;1:,IL I
""'"'" "' P 4 t "'"
. _P~tc (,
Performe*:J_Elv: ___ K.E.Pallagi v.</
~
6-22-2021
~/2,~/zo2-,
BRP 151 01/15/2 019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 95 of 122 f:V1_DIOLOGICAl. Page 11 of SURVEY.l'l:JD ~Tf\T US Sflff T l
! Oat~rf,n1,~ *- UFI # 24-1I K E.f'.dlagi lSFSI ROAD NOR l'l I C!Jrila;**,n3!1cn /uea (CA)
X Oih1* sce: 1y) Nlll1C 13 1\ dfi:*1!IGOr:,;1! dr;rnfi00 cm 1 dprrfiCC cn' I' fi 18 ccnffen :s All dose rates are General Area Dose Rates in rnrem/hr. 0 010 010 010
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- 0.1 0
<0.1 o.1Q 0 l North
. Dose Rate Meler/S t/
BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 96 of 122 Page 12 of 14 UFI # 24-11-01 6-22-2021/ 10 57 K.E.Pal\agi
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ISFSI ROAD soun 1 ND;\ X Area (fii\) En!ry HRAs G'Dn~ dp~1:1JCO:T: 11 3 dp,nl1COcrr:: Vi ,1 16 72 - 3:.H0_ __dpm:;coc,1'i 1 17 2J ___ Ji.!}<,__ dpm'iCOt:in 1 12 Id All dose rates are General Area Dose Rates in mrem/hr. Road smear survey locations align with utility poles. l.'1p BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 97 of 122 Page 13 of 14 Bi\fJIQLQ (il~\L$lJB VEY ANDS l~TUS SHEET 6-22-2{C l /IO i 8 1-01 KEPaliag i
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lvea {CAI NDA X None R Fn 1 !Cd 1*1 HfV\::; for Nom* c!prr!li)1)cd, 1 NDA dpHii1QOc~1i' 10 Upq,1iGOc:n 1 ,. d1w*/lOOr::n1l 1? cornrnen1s All dose rates are General Area Dose Rates in mrern/hr Mao Ke1 ft= Area Dcse R1:e 0 ::: Srrear Locc11
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- 0 I Cal Due 10-31-2021 NIA NIA PRM-6/#9 69 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 98 of 122 Page 14 of 14 RJ\DIO_L._Q_GJC:AL SUfN EY ANQSTAilJ§_i3tfi= El 6 202 It I 1P(i UFI
----~----#---24 - -- 11-01 K.1:.Pallngi -
UPP ERA OMI N, BLD c; 0, 25 I.J;>i-1 ~ df!11,/lO:Jc1n' d;:rnf10 0u1;i 21
,l dp1nflCOc:rn 1 dprr'li.:Gc,J\ 1 'il 5 f(J,\ _1h;:r,J 100c,n' dprnf1 GLetn 1 1; C, 11()/l_ 21 ----- rlr:i:: tC');,ir. 1 dprl'f18 Ccrd 15 2i..---- d;vn'iCO-:-n' Cco,n, enh All dose rates are General Area Dose Rate s in mrem/hr North -
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Cal Due K.E.Pallagi 6-22-2021 BRP 151 01/\512019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 99 of 122 RP Log Entry for 6-24-2020 Page 1 of 14 Completed the BRP ISFSI 2020 Annual and 2nd Quai1er radiological survey in accordance with RPG-28 on 6-22-2020 and 6-24-2020. All radiation surveys were completed using RO20 #11782. with a calibration due date of 7-31-2020. All smears were counted on frisker PRM-6 #965. with a calibration due date of 9-30-2020. The operational check of the RO20 on the 5 mrem/hr scale was performed on the 10 µCi Cs-13 7 scaled check source. RO20 # 11782 response to the sealed source was 1.1 mrem/hr on 6-22-2020. RO20 # 11782 response to the scaled source was 1.1 mrem/hr on 6-24-2020. The readings are consistent with the expected dose rate from the check source. The radiological posting signs at the ISFSI are clear. clean and concise. The postings arc not faded, and they are securely fastened to the fencing. Linc of site verification of no temporary residences was completed from the ISFSI location. There is no radioactive material stored on-site other than the sealed source. spent fuel and the Greater Than Class C waste in the storage casks. rij;:?G~ ~ KEPallagi 6-24-2020 16:45
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 100 of 122 Page _2_of J..:L RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Daterr,me _ _ _ . .c6_-"'2""2--'-2cc..0.c.-=2..c.0. c.l. .cl. .c0-'-:4-'--'-8___ Technician: _ _ --'-'K=*=E=.P'-'a=l=la="'-'-i 0 _ _ _ _ _ __ Location. _~l~S~F_ S~l~------ General Dose Rate: _ _ _ 0_.3___ mRem/hr(Y) _ _ _N_/_A___mRem1hr(f3) Area Posting X RMA Contamination Area (CA) X RCA Other specify) _ _ _ __ General Contamination: ___N_'I_A____dpm/100cm' Rad1at1on Area (RA) Special Instructions* G Notify Rad Pro PRIOR to any *work Entry* C Survey Meter Required in HRAs
= Air Sampling Required for Entry X Other (Specify) FRISKl:--:G EXE~Wf 1 dpm/100cm' 7. dpm/100cm' 13. dpm/100cm' 19. dpmi100cm' 25 2 dpm/100cm' 8 dpml100cm' 14 dpmi100cm' 20. d ,<.V dpml100cm' 3 dpm/100cm' 9 dpm/100cm' 15. N dom/ *- ' ' dpm/100cm' 27 dpm/100cm' 4
5 dpm/100cm' dpm/100cm' .10 dpm/10'11-m' dpm/100cm' 17. ~ dpm/100cm' dpm/100cm' 22. 23. dpm/100cm' dpm/100cm' 28. 29 dpm/100cm' dpm/100cm' " dpmi100cm' 12 dpml100cm' 18 dpm/100cm' 24 dpm/100cm' 30 dpm/100cm' comments. All dose rates are General Area Dose rates in mrem/hr. Map Key #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Locat,on
--X--X- = Rad1olog1cal Boundary LDWA = Low Dose Waiting Area *=Hot Spot 6 = Air Sample Location Abbreviat,ons/Un,ts* NDA- No Detectable Activity (<1000 DPM) CCPM- Direct Frisk Reading Result DPM/100cm'
- Smear Reading Result Ol 'fl:R I L:-.n
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~---------------------------------------------------------------------------------------------------1 I No11h RO201# I I 782 7-31-2020 Dose R~t" M"t"r/SN: Cal Due: Air Sarnoler. NIA Cal Due* NIA Counting lnst./SN NIA
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1~ Date: hI i.q / 2 v K.E.Pallagi ' c 6-22-2020 Performed B : Da BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 101 of 122 Page ___l_ of _11_ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Daterrime . ___ 6_-_2_2_-_2_0_2_0_/_I_0_:_3_3____ Technician _ _ . . :K~.E==-*:. :.P. c.a:.:.l:.:.la; ; ;g"'i_______ Locallon:_--"-I=S=F--"S"-'I,____ _ _ _ __ General Dose Rate _ _ _N_/ A I ___ mRemthr{Y) _ _ _N_/_A___mRemthr{i3) Area Poshng X RMA Contamination Area {CA) X RCA Other specify) _ _ _ __ General Contamination ___N_D_A ___dpm/100cm' Rad1atIon Area (RA) Special lnstruclions* Notify Rad Pro PRIOR to any *work Entry** Survey Meter Reqwed in HRAs Air Sampling Reqwed for Entry X Other {Specify) f'RISKl'-:G EXE:-VIPT 1 NOA dpmi100cm' 7. NOA dpm/lO0cm' 13 NOA dpm/100cm' 19 NOA dpm/100cm' 25 NOA dpm/100cm'
- 2. NOA dpm/100cm' 8 NOA dpm/100cm' 14 NOA dpmt100cm' 20. NOA dpmi100cm' 26. NOA dpm/100cm'
- 3. NQA dpm/100cm' 9 NOA dpmi100cm' 15. NOA pm/100cm' 21 NOA dpm/100cm' 27 NOb dpml100cm' 4 NOA dpm/100cm' 10 NOA dpmi100cm' 16 NOA dpm/100cm* 22. NOA dpm/100cm* 28 NOA dpm/100cm' 5 NOA dpm/100cm' 11 NOA dpm/100cm' 17 NOb dpm/100cm' 23 NOA dpm/100cm' 29. NIA dpm/100cm' 6 NOA dpm/100cm' 12. NOA dpm/100cm' 18 NOA dpmi100cm' 24 NOA dpmi100cm' 30. NIA dpm/100cm' comments Smear 27 taken on the horizontal surface of the electrical box. Smear 28 taken on vertical surface of A/C unit vent. All other smears samples taken on concrete surface Map Key #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Locahon
--X--X- = Rad1olog1cal Boundary LOWA = Low Dose Wa,t,ng Area *=Hot Spot b. = Air Sample Locat,on AbbrevIat,ons/Urnts NOA- No Detectable Activity {<1000 DPM) CCPM- Direct Frisk Reading Result DPM/100cm'. Smear Reading Result r
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NIA NIA NIA NIA Dose Rate Meter/SN: Cal Due* Air<::amnler Cal Due: QQunting In~! /~N: PRM-61#965 Qal Due: 9-30-2020 B,g Rock Reviewed B~: _J t--- D,!te: r.,lv1l2.o K.E.Pallag1
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- D te: 6-22-2020 Review dB : L4ttk'e'6~
BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 102 of 122 Page _4_of _!_+/-_ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 oatefTlme: _ _ 6_-2_2_-_2_0_2_0_1_1_1_:_0_9____ Technician: _ _ _K_._E_:._P_a_ll_a-=g'-i_____ __ Location CASKS General Dose Rate NI A mRem/hr(Y) _ _ N_I_A___ mRemlhr(~) [_~Ar-ea Posting - RMA =i Contamination Area (CA)
- . RCA X Other specify) None General Conlam1nal!on: _ _ N_TO_A___dpm/100cm' Radiation Area (RA)
" --- -----~---~------- - --
Special Instructions. ,, Notify Rad Pro PRIOR to any *work Entry- -- Survey Meter Required in HRAs
- Air Sampling Required for Entry ~ Other (Specify) None
- 1. dpm/100cm' 7 dpmil00cm' 13. dpm/100cm' 19 dpm/100cm' 25.
2 dpml100cm' 8 dpmll00cm' 14. dpm1100cm' 20 d _,. *- ,v dpm/100cm'
- 3. dpml100cm' 9. dpmll00cm' 15 N dpm/1""""-- 2 - . dpmt100cm' 27. dpml100cm'
- 4. dpml100cm' 10. dpm/10Qcm' " dpm/100cm' 22 dpml100cm' 28 dpm/100cm'
- 5. dpml100cm' i dpm1100cm' 17. A dpm/100cm' 23 dpml100cm' 29. dpml100cm'
" dpm/100cm' 12. dpm/100cm' 18. dpm/100cm' 24 dpm/100cm' 30. dpm1100cm' Comments: All dose rates measurements are on contact with the vent/cask. All dose rates are in mrem/hr. Map Key #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA = Low Dose Waiting Area *=Hot Spot /1 = Air Sample Locat,on Abbreviations/Units NOA- No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Result DPMl100cm'
- Smear Reading Result
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~
u 110 0.2 0.2 NOA 0.2 0.2 NOA 0.2 0.2 NOA < 0.2 < 0.2 NOA 210 0.3 < 0.3 NOA < 0.3 0.3 NOA < 0.3 < 0.3 NOA < 0.3 < 0.3 NOA 1-----+----t----jc------t----+-----+--*---t-----t----
-t----+----+-----t-----i 310 0.3 0.3 NOA 0.4 0.3 NOA 0.4 0.3 NOA 0.4 0.3 NOA 410 0.3 < 0.3 NOA 0.3 0.3 NOA < 0.3 < 0.3 NOA 0.3 0.3 NOA 510 0.3 < 0.3 NOA 0.3 0.3 NOA 0.3 0.3 NOA 0.3 0.3 NOA 610 0.2 < 0.3 NOA 0.2 0.2 NOA 0.2 0.2 NOA 0.2 0.2 NOA 710 0.3 0.3 NOA 0.3 0.3 NOA 0.3 0.3 NOA 0.3 0.3 NOA 810 0.4 0.3 NOA 0.4 0.3 NOA 0.3 0.3 NOA 0.3 0.3 NOA RO201# 11782 7-31-2020 NIA Dose Rate Meter/SN: Cal Due* Air Samnler: Cal Due:
NIA Counting Inst/SN* PRM-61#965 Cal Du!l* 9-30-2020 Big Rock Review!:d By: tJ___ Di!!!l b / 2. q I Z..t.> Performed By K.E.Pallagi fv 6-22-2020 Date: BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 103 of 122 Page _2_of 14 RADIOLOGICAL SURVEY AND STATUS SHEET ______________________________ --------------------------------=U:..:...F..:..I.:.:. #---=2c..:.4. . :-1c..:.1---=-0c..:.1~ 6_-2_4_-_2_0_2_0_/_0_9_:5_0_____ I Datemme: _ _ Techrncian:. _ _ K_.E_'._P_a_ll_a..:::g_i____ ____ Locatton:_T=-=--.:RA==--=:.N....:c:S=-=F:....=E=R~C=A....= e.S=K"'--"'-_ General Dose Rate. _ _ <_O_._l___ mRem1hr(Y) _ _ _N_/_A___ mRem/hr(J3) Area Posting ~ RMA ::J Contamination Area (CA)
- RCA :X Other specify) None General Contamination: _ _N_D_A ___dpm/100cm' Radiation Area (RA)
Special Instructions _, Notify Rad Pro PRIOR to any *work Entry* Survey Meter Required in H RAs
,~ Air Sampling Required for Entry X Other (Specify) None
- 1. NOA dpm/100cm' 7 NOA dpm/lOOcm' 13 NOA dpm1100cm' 19. NOA dpm1100cm' 25. NOA dpm/100cm'
- 2. NOA dpml100cm' 8. NOA dpml100cm' 14 NOA dpm/lOOcm' 20 NOA dpmllOOcm' 26. NOA dpmI100cm'
- 3. NOA dpm/100cm' 9. NQA dpm1100cm' 15 NOA dpm1100cm* 21. NOA dpm/100cm* 27. NOA dpm/100cm' 4_ NOA dpml100cm' 10. NOA dpm1100cm' 16 NOA dpm/100cm' 22 NOA dpml100cm' 28. NOA dpmI100cm' 5 NOA dpml100cm' 11. NOA dpm/100cm' 17 NOA dpm/100cm' 23 NOA dpm/100cm' 29. NOA dpm/100cm'
- 6. NOA dpml100cm' 12 N08 dpm/100cm* 18 NOA dpm/100cm* 24 NOA dpml100cm' 30. NOA dpm/100cm'
- - - - - - - - - 31. NOA dpm/100cm' comments All dose rates are in mrem/hr on contact and at 1 foot. Smear 1, 2, 22 and 23 on end bell mating joint. The Transfer Cask is labeled as "EMPTY". The Transfer Cask is labeled as "RADIOACTIVE MATERIAL".
Map Key_ #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA = Low Dose Waiting Area *=Hot Spot 6. = Air Sample Location Abbrev1at1ons/Units NOA - No Detectable Activity (<1000 DPM) CCPM - Direct Fnsk Reading Result DPM/100cm' - Smear Reading Result 1
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RO20/#11782 7-31-2020 NIA NIA Dose Rate M"ter/SN: Cal Due: AirSamnler Cal Due PRM-6/#965 I 2. D Counting Inst /SN* Cal Du~: 9-30-2020 Big Rock Reviewed By: J-11-_ Date* bf-iq K.E.Pallagi [V 6-24-2020 P rf rmed B : Date BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 104 of 122 Page _6__ of --1.:L RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Datefflme _ _6_-_2_4_-_2_0_2_0_/0_9_:_5_5_____ Technician _ _K_._E_._P_a_ll_a""'o-_i_ _ _ _ _ _ __ Location: TRANSFER CASK SKID General Dose Rate _ _ N_I_A___mRemlhr(Y) _ _ _N_I_A___mRemihr{f3) Area Posting RMA = Contamination Area {CA) RCA X Other specify) None NDA General Contamination _ _ _ _ _ _ _dpml100cm' Radiation Area {RA) Special Instructions. r** Notify Rad Pro PRIOR to any *work Entry* ::..: Survey Meter Required in HRAs Air Sampling Required for Entry X Other {Specify) _ _~N~o~1~1e~----- i I 1. -~N=D-'-'A_ _ dpm/100cm' 7 NDA dprnl100cm' 13. --'-'N=DA'-'--__dpml100cm' 19 _ _ _ _ _d.pml100cm' 25 II 2 NOA dpm/100cm' 8 NOA dprnl100cm' 14. NIA dpm/100cm' 20 26 , 3. NOA dpm/100cm' 9. NDA dpmi100cm' 15 NIA dpm/100cm' 21. _ _ _ __ 27 4 -~N=OA'-'--__dpm/100cm' 10 NDA dpml100cm' 16. NIA dpm/100cm' 22 _ _ _ _ _dpml100cm' 5 -~N=DA~__dpm/100cm' 11 -~N=DA~__dpml100cm' 17. NIA dpm/100cm' 23 _ _ _ _ _dpmll0Ocm'
- 6. -~N=DA~__dpml100cm' 12 -~N=D~A_ _ dpmi100cm' 18. NIA dpm1100cm' 24 """"":.....__ _ _, _ _ _ _ _dpmll00cm' Comments* None.
Map Key #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear location
--X--X- = Rad1olog1cal Boundary LOWA= Low Dose Waiting Area *=Hot Spot 6. = Air Sample Location Abbrev1at,onslUnits NOA- No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Result DPM1100cm'. Smear Reading Result North
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Dose Rate Meter/SN: NIA Cal Due NIA Air Samoler NIA Cal Due* NIA Counting Inst/SN* PRM-6/#965 Cal Due: 9-30-2020 Big Rock Review§Q B~* j__,J_.__ Date: 4/z.8 l2..o Performed B: K.E.Pallagi &v4--- Date* 6-24-2020 Reviewed B
- BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 105 of 122 Pane 7 of 14 b --- --- RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 DatefTime: _ _ 6_-_2_4_-_2_0_2_0_/_I0_:_0_0_____ Technician. _ _ K_.E_'._P_a_ll_a~g_i________ Location. _ _ J~-~S~K=J =O~------ General Dose Rate __ <_0_._l___mRem/hr(Y) _ _ _N_/_A___ mRemihr((l) Area Posting* = RMA ,_; Contamination Area (CA)
- RCA Other specify) None General Contamination. _ _ N_1_D_A____.dpm/100cm' Radiation Area (RA)
Special Instructions Notify Rad Pro PRIOR to any -work Entry* Survey Meter Required m HRAs Air Sampling Required for Entry - w Other (Specify) None
- 1. NDA dpm/100cm* 7. NDA dpml100cm' 13 dpm/100cm' 19
- 2. NOA dpm/100cm' 8. NOA dpm/100cm* 14 dpml100cm' 20.
- 3. NDA dpm/100cm' 9. NOA dpm/100cm' 15 dpml100cm'
- 4. NOA dpm/100cm' 10 NOA dpml100cm* 16
- 5. NOA dpml100cm' 11. NIA dpm/100cm' dpm/100cm* 29 dpml100cm'
- 6. NDA dpm/100cm' 12 NIA dpml100cm* dpmllOOcm' 24. dpm/100cm' 30 dpml100cm' comments. All dose rates are General Area Dose Rates in mrem/hr.
Map Key # = General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area *=Hot Spot 6 = Air Sample Location Abbreviations/Units NDA- No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Result DPMl10Dcm'
- Smear Reading Result North
< 0.1
< 0.1 Dos<> Rate Meter/SN: RO20/#l 1782 Cal Due 7-31-2020 Air i::~mnler. N/A NIA Cal Due:
Counting ln~t/~N PRM-6/#965 Cal Due 9-30-2020 Big Rock R!lviewed B:{ _J_w,___ Date: 1,/2-9l1-u Performed B: K.E.Pallagi ~ Date: 6-24-2020 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 106 of 122 Page_8_of ~ RADIOLOGICA L SURVEY AND STATUS SHEET UFI # 24-11-01 Date/Time: _ _ 6_-2_4_-_2_0_2_0_/_I0_:4_5_____ Technic,an: _ _K_.E_-._P_a_ll_a-"g'-i________ Locat,on. _ _IS_F_S_I_F_E_N_C_E_L_I_N_E_ __ General Dose Rate _ _ <_0_._l___ mRemlhr(Y) _ _ _N_/A___,mRemthr([3) Area Posting* - RMA -- Contamination Area (CA) RCA X Other specify) None General Contaminat,off _ _N_D_A ____dpm/100cm' Radiat,on Area (RA) Special Instructions -- Notify Rad Pro PRIOR to any Work Entry* - Survey Meter Required in HRAs Air Sampling Required for Entry ~ Other (Specify) _ _N~1 wa~n~"---- -- 1 NOA dpm/100cm* 7 NOA dpm/100cm* 13 NOA dpml100cm' 19 _ _ _ _ _dpm/100cm*
- 2. NOA dpml100cm' 8. NOA dpm/100cm' 14. NOA dpm/100cm' 20. _ _ _ __
- 3. NOA dpm/100cm' 9 NOA dpm/100cm' 15 NOA dpm/100cm* 21. _ _ _ __
4 NOA dpm/100cm' 10 NOA dpm/100cm' 16 NOA dpm/100cm' 22 - - - - - ' ~----dpm/100 cm' 5 NOA dpm/100cm' 11 NOA dpm/100cm* 17. NOA dpm/100cm' 29 _ _ _ _ _d.pm/100cm' 6 NOA dpm/100cm' 12 NOA dpm/100cm' 18. NOA dpm/100cm* 30 _ _ _ _ _dpm/100cm' comments All smears taken on vertical surfaces of light poles or concrete surface except smears 1 and 14 taken in the interior of the buildings. All dose rates are general area dose rates in mrem/hr. Map Key* # = General Area Dose Rate CIGA = Contact and General Area Dose Rate 0 = Smear Locat,on
--X--X- = Rad1olog1cal Boundary LOWA = Low Dose Waiting Area *=Hot Spot 6. = Air Sample local!on Abbrev,at,ons/Units NOA- No Detectable Activity (<1000 OPM) CCPM - 0Jrect Frisk Reading Result OPM1100cm'. Smear Reading Result
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<0.1 < 0.1 Dose R;,te Meter/SN: RO20/#1 I 782 7-31-2020 NIA N/A Cal Du"* AirSamnler. Cal OuP Counting lnst.lSN*
PRM-6/#965 Cal Due 9-30-2020 Big Rock _j_rJ.____ 6l zRlio K.E.Pallagi v- 6-24-2020 Reviewed By: Date,;__ --. --~*-***--- P rtormed B: Date BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 107 of 122 RP Log Entry for 6-27-2019 Page I of 14 Complet ed the BRP ISFSI 201 Annual and 2 nd quarter radiological survey in accordan ce with RPG-28 on 6-27-2019. All radiation surveys were completed using RO2 #3031, with a calibration due date of 4-30-2020. All smears were counted on frisker PRM-6 #1006, with a calibration due date ofl0-31 -2019. The operatio nal check of the RO2 on the 5 mrem/hr scale was perfonne d on a recently procured l 0 µCi Cs-13 7 sealed check source. The expected response from the sealed source is 1.5 to 2 mrem/hr. RO2 #3031 response to the sealed source was 2 mrem/hr. In addition, as a check, RO2 #539 with a calibration due date of 4-30-202 0 was also source checked with a response of 1.8 mrem/hr; RO20 # 11782 with a calibration due date of 6-30-201 9 was also source checked with a response of 1.6 mrem/hr. The sealed source and the containe r for the source are labeled as required by 10 CFR 20.1904. The room in which it is used and stored is exempt from the IO CFR 20.1902 posting requirem ent as the activity of the source does not exceed 10 times the 10 CFR 20 Appendi x C quantity requirement. The sealed source is stored such that it meets the requirem ent of IO CFR 20.180 I, Security and Control of Licensed Material. The radiological posting signs at the ISFSI are c.:lear, clean and concise. The postings are not faded and they are securely fastened to the fencing. Line of site verification of no tempora ry residences was completed from the ISFSI location. There is no radioactive material stored on-site other than the sealed source, spent fuel and the Greater Than Class C waste in the storage casks. j/~ //L -~ KEPallagi 6-28-2018 11 :00
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 108 of 122 Page _2_of li_ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 DatefTime: _ _ _6.c_.c-2c...7_-~2_0~!_9_/_1~0_:4~1___ Technician: _ _ _K~.E~*=P~a=ll=a'-"'g=i___ ____ Location: __ JSFSI- - - - - - - - - - General Dose Rate: ___<_0_._l__mRemlhr(Y) _ _ _N_I_A___ mRemlhr(fl) Area Posting: X RMA :J Contamination Area (CA) X RCA _ Other specify) _ _ _ _ __ General Contamination: ___N_IA ____dpm/100cm' '.J Radiation Area (RA) Special Instructions: -' Notify Rad Pro PRIOR to any "'Work Entry* " Survey Meter Required in HRAs Air Sampling Required for Entry X Other(Specify) FRISKl:-.:G EXEMPT
---- - -. ---~ -*
1 dpm/100cm ' 7 dpm/100cm ' 13. 2 _dpm/100cm' 8. dpm/100cm ' dpm/100cm ' 19. _dpm/100cm' 25 **--
- 14. dpm/100cm ' 20 d*-'1"'~
~
<O dpm/100cm '
3 dpm/100cm ' 9 dpm/100cm ' 15 dpmI1nn
- 4. _dpm/100cm'
' -- _dpm/100cm' 27. dpm/100cm '
- 10 dpm/10Qcm' dpm/100cm ' 22 dpm/100cm '
- 5. dpmt100cm* . dpm/100cm ' 17. A 28 dpm/100cm '
dpm/100cm ' 23. -- dpm/100cm ' 29 C dpm/100cm '
-- - __ dpm/100cm ' 12. dpm/100cm ' 18. dpm/100cm ' 24 dpm/100cm ' 30 dpm/100cm '
comments All dose rates are General Area Dose rates in mrem/hr. Map Key #= General Area Dose Rate CIGA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Wailing Area * = Hot Spot D. = Air Sample Location Abbreviations/Units: NOA - No Delectable Activity (<1000 OPM) CCPM - Direct Frisk Reading Resull DPMl100cm' - Smear Reading Result
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North RO21#3031 4-30-2020 Dose Rate Meler/SN: Cal Due: Air Samoler: NIA C:al Due: NIA Countina Inst/SN: NIA K.E.Pallagi \Iv/" Cal Due: NIA Sig Rock Reviewed Bv: j)A._ _ Date: 1-/ d I, Performed B : 6-27-2019 Date: Date: r Z It'\ BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 109 of 122 Page _3_ of _Jj_ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 6_-_2_7_-_2_0_I_9_l_l_0_:_2_3____ K_.E_._P_a_l_la..,_g'--i_____ Date/Time:. _ _ Technician: _ _ _ Location: ISFSJ General Dose Rate: _ _ _ N_I_A___ mRem/hr(Y) _ _ _N_I_A ___ mRem/hr(fl) Area Posting: X RMA Contamination Area (CA) X RCA :J Other specify),_ _ _ __ General Contamination: _ _ _ ND __A ___ dpml100cm' '.J Radiation Area (RA) Special Instructions: Notify Rad Pro PRIOR to any *work Entry" = Survey Meter Required in HRAs _ Air Sampling Required for Entry !X Other(Specify) FRISKl:--G EXEMPT 1 _ .l!Q&___dpml100cm' 7. NOA dpm/lOOcm' 13 NOA dpm/100cm' 19. --1iQt,____ _dpm/100cm 2 25 __,_=~-....:dpm/10 NOA 0cm'
- 2. NOA dpmllOOcm' 8 ~ ___ dpm/100cm' 14 NOA dpm/100cm' 20 NOA dpml100cm' 26 __,_=,____
NOA __ dpm/100cm' 3 ~ _ _ dpml100cm' 9. NOA dpm/100cm' 15 NOA pml100cm' 21 NOA __ dpm/100cm' 27. __,_=,__ NOA __ dpm/100cm'
- 4. ~ _ _dpm/100cm' 10 NOA ___dpm/100cm' 16 NOA dpm/100cm' 22 NOA dpm/100cm' 28. NOA _ _ dpm/100cm'
__,_,=c..__ 5 NOA dpm/100cm' 11 ~ __dpm/100cm' 17. NOA dpm/100cm' 23. NOA _dpm/100cm' NIA 29 ---'-"'-'--- __ dpm/100cm' 6 NOA dpmllOOcm' 12 NOA dpm/100cm' 18 NOA dpmllOOcm' 24. NDA dpm/100cm' 30. --'--"-"'----dpm/10 NIA 0cm'
--~-
comments Smears 23 through 26 and smear 27 taken on the horizontal surface of the electrical boxes. Smear 28 taken on vertical surface of A/C unit vent. All other smears samples taken on concrete surface. Map Key* #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Wailing Area * = Hot Spot !:'!. = Air Sample Location Abbreviations/Units: NOA No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Result DPM/100cm' - Smear Reading Result Ol"TrR fE:-:CE r
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North --+ NIA NIA NIA NIA Dose Rate Meter/SN: Cal Due: Air Samnler: Cal Due: Countin lnst./SN: PRM-6/#1006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: J_4._ Date: 1- 1I II 1 Performed B: K.E.Pallagi jlV- Date: 6-27-2019 Date: '?1 Z /'1 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 110 of 122 Page of - 14-RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Dateffime _ _ 6-2?:_?_9l9/l l :09 _____ Technician: _ _ _ K_.E_.P_a_l_l_a=g_i_______ Location: CASKS General Dose Rate: _ _ N_I_A___ mRem/hr(Y) _ _N_I_A___ mRem/hr(Jl) Area Posting: :J RMA C Contamination Area (CA)
- J RCA X Other specify) None General Contamination: _ _ N_O_A___dpm/100cm' :J Radiation Area (RA)
Special Instructions: C Notify Rad Pro PRIOR lo any *work Entry'" =:l Survey Meter Required in HRAs
'.:"' Air Sampling Required for Entry :;{ Other(Specify) None dpm/100cm' 7 dpm/100cm' 13 dpm/100cm' 19 dpm/100cm' 25 2 _dpm/100cm' 8 dpm/100cm' 14 dpm/100cm' 20 d dpm/100cm' 3 dpm/100cm' 9 dpm/100cm' 15 N dpm/10n
' dpm/100cm' LU.
- 27. dpm/100cm'
____ dpm/100cm' 10 dpm/100cm' dpm/100cm' 22 dpm/100cm' 28 dpm/100cm' dpm/100cm' ,. dpm/100cm' 17 A dpm/100cm' 23 _dpm/100cm' 29 dpm/100cm' __ dpm/100cm' 12. dpm/100cm' 18 dpm/100cm' 24 _dpm/100cm' 30 dpm/100cm' Comments: All dose rates measurements are on contact with the vent/cask. All dose rates are in mrem/hr. Map Key: #= General Area Dose Rate C/GA = Conlacl and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Wailing Area * = Hot Spot 6. = Air Sample local1on Abbreviations/Units: NDA - No Detectable Aclivity ( < 1000 DPM) CCPM - Direct Frisk Reading Result DPM/100cm' - Smear Reading Result
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(/) w ty' C) u z.....: Cl) > C/l Z> 110 < 0.1 0.1 NOA < 0.1 0. l NOA < 0.1 O. l NOA < O.l 0.l NOA 210 0.1 0.2 NOA 0.l 0.2 NOA 0.1 0.2 NOA 0.1 0.2 NOA 310 0.2 0.1 NOA 0.2 0.2 NOA 0.2 0.1 NOA 0.2 0.2 NOA 410 0.1 0.2 NOA 0.1 0.2 NOA 0.1 0.2 NOA 0.2 0.2 NOA 510 0.2 0.1 NOA 0.2 0.2 NOA 0.2 0.2 NOA 0.2 0.2 NOA 610 0.2 0.2 NOA 0.1 0.2 NOA 0.2 0.2 NOA 0.2 0.2 NOA 710 0.2 0.1 NOA 0.2 0. l NOA 0.2 0.2 NOA 0.2 0.2 NOA 810 0.2 0.2 NOA 0.2 0.2 NOA 0.2 0.2 NOA 0.2 0.2 NOA RO2/#3031 4-30-2020 NIA NIA Dose Rate Meter/SN: Cal Due: Air Samnler: Cal Due: PRM-61#1006 10-31-2019 Big Rock Countina lnst./SN: Cal Due: Reviewed Bv: Date:
. i,-'
Performed Bv: K.E.Pallagi f Date: 6-27-2019 Reviewed Bv: LA/iJ!..e £~ &~ Date: r/z/2'( BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 111 of 122 Page_5_of ~ RADIOLOGI CAL SURVEY AND STATUS SHEET UFI # 24-11-01 Date/Time: _ _ 6_-2_7_-_2_0_1_9_1_1_1_:2_3_____ Technician: _ _ K_._E_._P_a_ll_a_g_i_____ ___ Location: TRANSFER CASK General Dose Rate: _ _ <_0_._l___ mRemlhr(Y) _ _ _N_IA ____ mRemlhr(ll) Area Posting: :J RMA C Contamination Area (CA)
- J RCA X Other specify) None NDA General Contamination: _ _ _ _ _ _ _ dpm/100cm'
- J Radiation Area (RA)
Special Instructions: Notify Rad Pro PRIOR to any *work Entry* u Survey Meter Required in HRAs Air Sampling Required for Entry
~ Other (Specify) None NDA dpm/100cm' 7. NOA dpm/100cm' 13 NOA dpm/100cm' 19 NOA dpmllOOcm' 25 NOA __.dpm/100cm'
- 2. NDA ___ dpm/100cm' 8 - ~ ___.dpm/100cm' 14 NOA dpm/100cm' 20 NOA dpmllOOcm' 26. NOA dpml100cm' 3 NOA dpm/100cm' 9 NOA dpml100cm' 15. - ~ - .dpm/100cm' 21. NOA .._.dpm/100cm' 27 NOA __ .dpml100cm'
- 4. _ - ~ __dpm/100cm' 10 NOA dpm/100cm' 16 ___ -1'!Q6.__dpm/10 0cm' 22 NOA dpmllOOcm' 28. NDA dpm/100cm' 5 --*- NDA __ dpmllOOcm' 11 NDA dpml100cm' 17. NOA dpm/100cm' 23. NOA dpmllOOcm' 29 NDA dpm/100cm' 6 NOA dpm/100cm' 12 __..!'!Qll___dpm/100cm' 18 NOA dpml100cm' 24 NOA dpm/100cm' 30 NDA dpm/100cm'
"-----~-- 31. NOA _dpm/100cm' Commen1s: All dose rates are in mrem/hr on contact and at 1 foot. Smear 1, 2, 19 and 23 on end bell mating joint. The Transfer Cask is labeled as "EMPTY". The Transfer Cask is labeled as "RADIOACTIVE MATERIAL".
Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area * = Hot Spot /"i = Air Sample Location Abbreviations/Units* NOA - No Detectable Activity ( < 1000 DPM) CCPM - Direct Frisk Reading Result DPMl100cm'
- Smear Reading Result
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Countina lnst./SN: PRM -6/# I 006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: 1~lJ- Date: :i-ldt'l K.E.Pallagi (vY 6-27-2019 Performed B : Date: Reviewed B : Date: T: Z '11 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 112 of 122 Page_§ __ of _11_ RADIOL OGICAL SURVE Y AND STATUS SHEET UFI # 24-11-01 Oatemme: _ _ 6_-2_7_-_2_0_1_9_/_l_l_:_2_8____ _ Technician: _ _ K_.E_.P_a_l_la_,!:,"--'i____ ____ Location: TRANS FER CASK SKID General Dose Rate: __N_/A ____ mRem/hr(Y) _ _ _N_/_A___mRem/hr(fl) Area Posting: :J RMA = Contamination Area (CA) NOA RCA X Other specify) None General Contamination: _ _ _ _ _ _ _ dpm/100cm '
- J Radiation Area (RA)
Special Instructions: Notify Rad Pro PRIOR to any Work Entry ::::; Survey Meter Required in HRAs Air Sampling Required for Entry :X Other (Specify)_ _ ~N~o=n=e____ __ NOA dpm/100cm' 7 NOA dpm/100cm' 13 NOA dpm/100cm' 19 dpml100cm' 25. 2 NOA dpml100cm' 8 .__ NOA .. . dpml 100cm' 14 NIA dpm/100crn' 20 ____.._dprnl100 crn' 3 NOA dpml100crn' 9 NOA _dprn/100cm' 15 NIA dprnl100cm' 21. dpm/100N '
- 4. NOA dprnl100cm' 10. NOA __ __ dprn/100crn' 16. NIA __dpml100cm' 22. _ _____dpml100 dprn/100cm' 5 _JiQ6...__ _dpm/100 cm' 11 _ NOA __.__dpm/100crn' 17. NIA dprn/100crn' 23. ._.dprn/100cm' 6 NOA dpm/100cm' 12 NOA --* .dpm/100crn' 18 NIA dprn/100cm' 24 30 dpm/100cm' Comments: None.
Map Key: # = General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA = Low Dose Waiting Area * = Hot Spot l\ =Air Sample Location Abbreviations/Units: NDA - No Detectable Activity ( < 1000 DPM) CCPM - Direct Frisk Reading Result DPM/100c m' - Smear Reading Result North 7 1-------~
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Dose Rate Meter/SN: NIA NIA NIA Cal Due: Air Samnler: C:al Due: NIA Countina lnst./SN: PRM-6/#1006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: j_~ Date: -=1-/1 l,'t Performed 8 : K.E.Pallagi lµ/' Date: 6-27-2019 Reviewed B: l,1ftlt'G fF- Date: BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 113 of 122 Page --- 7 of 14 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Datemme: _ _ 6_-_2_7_-2_0_19_/_l_l_:3_3_____ K_._E_._P_a_ll_ag'-i_____ __ Technician: _ _ Location: J - SKID
<0 I General Dose Rate: _ _ _. _ _ _mRemlhr(Y) _ _ _NIA _ _ _ _ mRem/hr(i3) Area Posting: RMA :.J Contamination Area (CA)
RCA *' Other specify) None General Contamination: _ _N_D_A ____dpm/100cm' Radiation Area (RA) Special Instructions: Notify Rad Pro PRIOR to any *work Entry Survey Meter Required in HRAs Air Sampling Required for Entry __, Other (Specify)_ _ _ N_o_1_1_e______ 1 ~ ___ dpm/100cm' NOA dpm/100cm' 13. _ _ _ _ _ dpm/100cm' 19 2 _NOA .* dpm/100cm' 8 NOA dpm/100cm' 14 _ _ _ _ _ dpm/100cm' 20 3 --~_dpm/10 0cm' 9 NOA dpm/100cm' 15. _ _ _ _ _ dpm/100cm' 21 4 __ .NOA .. .dpm/100cm' 10 NOA dpm/100cm' 16 22. 28 5 NOA dpm/100cm' 11 NOA dpm/100cm' 23. _______ .. _dpm/100cm' 29 ______ dpm/100cm' 6 NOA ... _dpm/100cm' 12 NOA dpml100cm' 24. _ _ _ _ _ _dpm/100cm' 30 _ _ _ _ _dpm/100cm' comments: All dose rates are General Area Dose Rates in mrem/hr. Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area * = Hot Spot /j. = Air Sample Location Abbreviations/Units: NOA - No Detectable Activity (<1000 DPM) CCPM - Direct Frisk Reading Result OPM/100cm'
- Smear Reading Result No11h G) <0.1@
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<0.1© Dose Rate Meter/SN: RO21#3031 Cal Due: 4-30-2020 NIA NIA I,/~
Air Samnler: Cal Due: Countina lnst./SN: PRM-6/#1006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: j_~ Date: 1-I Performed B : K.E.Pallagi ~v- 6-27-2019 Date: Reviewed B : Date: 7' 2 11 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 114 of 122 Page of -14 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Dateffime: _ _ 6_-2_7_-_2_0_1_9_/_1_1:_4_7_____ Technician: _ _ K_.E_._P_a_ll_a_g_i________ Localion: _ _ IS_F_S_I_F_E_N_C_E_L_I_N_E_ _ General Dose Rate: __<_0_.l___ mRem/hr(Y) _ _ _N_/_A ___ mRem/hr(fl) Area Posting: ::::J RMA ::J Contamination Area (CA)
~ RCA X Other specify) None General Contamination: __N_D_A____dpm/100cm' Radiation Area (RA)
Special Instructions: Notify Rad Pro PRIOR lo any *Work Entry ::J Survey Meter Required in HRAs
._, Air Sampling Required for Entry ~ Other (Specify)_ _~N~a~o~e_______
NDA dpm/100cm' 7 ~ ___ dpm/100cm' 13 NDA dpm/100cm' 19 _ _ _ _ _dpm/100cm'
- 2. NDA dpm/100cm 2 8 NDA ___ dpm/100cm' 14. _ NDA dpm/100cm' 20 dpm/100cm' 3 NDA dpm/100cm' 9 NDA dpm/100cm' 15 NOA dpm/100cm' 21. - - - - -
4 NDA dpm/100cm' 10 ~ _.. ___dpm/100cm' 16 NDA ___dpm/100cm' 22 _ _ _ _ dpm/100cm' 5 NDA __ dpm/100cm' 11 NDA dpm/100cm' 17 NDA dpm/100cm' ______ dpm/100cm'
- 6. NDA dpm/100cm' 12 _ NDA_ ____dpm/100cm' 18 ___ NDA _____ dpm/100cm' 30 _ _ _ _ _dpm/100cm' comments: All smears taken on vertical surfaces of light poles or concrete surface except smears 1 and 14 taken in the interior of the buildings. All dose rates are general area dose rates in mrem/hr.
Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LDWA = Low Dose Waiting Area *=Hot Spot I:,. = Air Sample Location Abbreviations/Units* NDA- No Detectable Activ,ty(<1000 DPM) CCPM- Direct Frisk Reading Result DPM/100cm' - Smear Reading Result LP ~ Light Pok PJ - Po11a John
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Countina lnst./SN: PRM-6/# 1006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: _JL_ Date: 1-!,!,'l Performed B : K.E.Pallagi \1-- Date: 6-27-2019 Reviewed B : Date: z/rl BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 115 of 122 Page _9_ o f ~ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Date/Time: _ _ 6_-_2_7_-_2_0_!_9_/_1_2_:_l5_____ Technician: _ _K_.E_._P_a_ll_a=gc-i________ Location: ISFSI POLE BARN General Dose Rate: _ _<_O_._l___ mRem/hr(Y) _ _ _ N_/_A___ mRemlhr(P) Area Posting* ::J RMA :::; Contamination Area (CA)
- J RCA :X Other specify) None General Contamination: _ _N_D_A___dpm/100cm'
- J Radiation Area (RA)
Special Instructions Notify Rad Pro PRIOR to any Work Entry* ::::; Survey Meter Required in HRAs Air Sampling Required for Entry ~ Other (Specify)_ _ None NDA dpml100cm' 7 NDA dpm/100cm' 13 NOA dpmll00cm' 19 NOA dpml100cm' 25 NDA dpm/100cm' 2 NOA dpm/100cm' 8 NDA. __ dpml100cm' 14 NOA dpm/100cm' 20 NDA dpm/100cm' 26 NDA dpm/100cm' 3 ~ __ dpm/100cm' 9 ~ __ dpml100cm' 15 NDA dpml100cm' 21. NDA dpml100cm' 27. _@tL. _dpm/100cm' 4 ~ . _dpm/100cm' 10. NDA _______ dpm/100cm' 16 ~ ___dpm/100cm' 22. ~ _ _ dpm/100cm' 28 NDA dpm/100cm' 5 NDA dpm/100cm' 11 NDA dpm/100cm' 17 NOA dpm/100cm' 23 NDA dpm/100cm' _ NOi\_ 29 __ dpm/100cm' 6 ~ ____ dpm/100cm' 12 __l'!M... ____ dpm/100cm' 18 NOA _dpm/100cm' 24 NOA dpml100cm' 30 ~ ___dpm/100cm' comments All dose rates are General Area Dose Rates in mrem/hr. Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LDWA = Low Dose Waiting Area *=Hot Spot 6. = Air Sample Localion Abbreviations/Units: NDA- No Detectable Activity(<1000 DPM) CCPM - Direct Frisk Reading Result DPM/100cm'
- Smear Reading Result
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<0.1 CD North < 0.1 < 0.1 Dose Rate Meter/SN: R0 2/# 303 I Cal Due:
4-30-2020 Air Samoler: NIA Cal Due: NIA Countino lnst./SN: PRM-6/#1006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: j14- Date: '}/i/ I'f K.E.Pallagi i!,v"" 6-27-2019 Performed B: Date: Reviewed B : Date: q BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 116 of 122 Page~ of~ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Date/Time: _ _6_-_2_7_-_2_0_1_9_/_12_:_4_0_____ Technician: K.E.Pallagi Location: ISFSI Road Central General Dose Rate: __ <_0_._l___ mRem/hr(Y) _ _ _ N_/_A___ mRem/hr(P) Area Posting: S RMA = Contamination Area (CA) NOA General Contamination: _ _ _ _ _ _ _ dpm/100cm'
= RCA iX Other specify) None u Radiation Area (RA)
Spec,al Instructions: Notify Rad Pro PRIOR to any "Work Entry' := Survey Meter Required in HRAs
.. " Air Sampling Required for Entry X Other (Specify)_ ___,_N.,.o=-'n""e_ _ _ _ __
1 _ __!filL_dpm/1 00cm' 7 NOA dpm/100cm' 13 _dpm/100cm' 19.
-~-- dpm/100cm 2 25 2 NOA dpm/100cm' 8 NOA dpm/100cm' 14. dpm/100cm' 20.
3 NOA dpm/100cm 2 9 __ NOA __ dpm/100cm' 15. ..---* ____ dpm/100cm' 21. 4 NDA dpm/t00cm' 10 NDA dpm/100cm' 16 22. 28. dpm/100cm' 5 NDA dpm/100cm' 11. - ... NDA . dpm/100cm' 23 29 dpm/l00cm' 6 NDA dpm/100cm' 12 NOA dpm/100cm' 24 _ _ . _ _ _ dpm/100cm' 30 dpm/100cm' Comments: All dose rates are General Area Dose Rates in mrem/hr. Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area * = Hot Spot 6. = Air Sample Location Abbreviations/Units NOA No Detectable Activity ( < 1000 DPM) CCPM - Direct Frisk Reading Result DPM/100cm'
- Smear Reading Result
- ..... - - - - .. - .. ___ ..... ____ .................- ...*----- .. ------ ---~-- .... ---.... - - -...- .. --.-- -..
Gate
~--~ \'.).'<l_i
< 0.1
<0.1(3) 0 Ci) < 0.1
© < 0.1 ISFI Pok Barn Arca
<0.10 l North Dose Rate Meter/SN: R0 2/# 303 l Cal Due:
4-30-2020 Air Samnler: NIA Cal Due: NIA Countino lnst./SN: PRM- 6/#l00 6 Cal Due: 10-31-2019 Big Rock Reviewed Bv:
.J_!,L_._ 1-ld,q Date.
Performed B : K.E.Pallagi V Date: 6-27-2019 Reviewed B : Date: r, 2' 'l'l BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 117 of 122 Page 11 of 14 RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 DatefTime: _ _ 6_-_2_7_-_2_0_1_9_/1_2_:_2_5_____ Technician:_ K.E.Pallagi _ _ _ _ _ __ Location:_IS_F_S _I_R_O_A_D_N_ O_R_T_H _ __ General Dose Rate: __<_0_._l___mRem/hr(Y) _ _ _N_I_A __ mRem/hr{Jl) Area Posting: RMA ::J Contamination Area {CA) NDA '..J RCA X Olher specify) None General Contamination: _ _ _ _ _ _ _ dpm/100cm' Radiation Area {RA) Special Instructions: ~ Notify Rad Pro PRIOR to any Work Entry* ::J Survey Meter Required in HRAs
~ Air Sampling Required for Entry '.R Other (Specify)_ _ _ None NOA dpm/100cm' 7 ___li!M_ _______dpm/100cm' 13 __ NOA __ dpm/100cm' 19. ______ dpm/100cm' 25 2 NOA dpm/100cm' 8 NOA dpmllOOcm' 14 NOA dpm/100cm' 20. _ _ _ _ _ dpm/100
- 3. NOA dpm/100cm' 9. _NOA ____ dpm/100cm' 15 NOA dpm/100cm' 21 dp 4 NOA dpm/100cm' 10. NOA dpm/100cm' 16 NOA dpml100cm' 22. dpm/100cm' 5 _NOA. __ dpm/100cm' 11 - NOA ___ dpml100cm' 17. NIA dpm/100cm' dpm/100cm' 6 NOA dpm/100cm' 12 _.lliM.._ __ dpm/100cm' 18 NIA dpm/100cm' 30 dpm/100cm' Commenls: All dose rates are General Area Dose Rates in mrem/hr.
Map Key: #= General Area Dose Rale C/GA = Contact and General Area Dose Rale 0 = Smear location
--X--X- = Radiological Boundary LOWA= Low Dose Wailing Area * = Hot Spot f.. = Air Sample Location Abbrev,alions/Units: NOA- No Deleclable Aclivily {<1000 DPM) CCPM - Direct Frisk Reading Result DPM/lOOcm'
- Smear Reading Result 0.1G) 0.1G o.iC~)
0.1G) 0.1G) Barriers
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Dose Rate Meter/SN: RO-2/#3031 Cal Due: 4-30-2020 NIA NIA Air Samoler: Cal Due: Counting lnst.lSN: PRM-6/# I 006 Cal Due: 10-31-2019 Big Rock Reviewed B~: _J_~ Date: 1-l, 11-='t Performed B: K.E.Pallagi ~VV' 6-27-2019 Date: Review dB: Dale: 'r BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 118 of 122 Page~o f~ RADIOLOGICAL SURVEY AND STATUS SHEET UFl#24-11-01 Oate/Time: _ _ 6_-2_7_-_2_0_19_/_1_3_:2_7_ __ Technician: K.E.Pallagi location ISFSI ROAD SOUTH General Dose Rate: _ _ <_0_,_l___ mRem/hr(Y) ____N_/_A ___ mRem/hr(fl) Area Posting: RMA :J Contamination Area (CA)
- RCA :X Other specify) None NDA General Contamination: _ _ _ _ _ _ _ dpm/100cm' _ Radiation Area (RA)
Special Instructions: - Notify Rad Pro PRIOR to any "Work Entry
= Survey Meter Required in HRAs
-* Air Sampling Required for Entry ~ Other (Specify) None 1 NOA dpm/100cm' 7. __ NOA dpm/100cm' 13 NOA dpm/100cm' 19 NOA _dpm/100cm'
- 2. NOA dpm/100cm' 8 NOA dpm/100cm' 14 NOA dpm/100cm' 20 ~ __ dpm/100cm' 3 NOA __dpm/100cm' 9 _NOA _dpm/100cm' 15 NOA dpm/100cm' 21 N/A dpm/100cm' 4 NOA dpm/100cm' 10 NOA dpm/100cm' 16. NOA dpm/100cm' 22 N/A dpm/100cm' 5 NOA ___ dpm/100cm' 11. __ NOA__ ____dpm/100cm' 17 NOA dpm/100cm' 23 N/A dpm/100cm' 6 NOA dpm/100cm' 12 NOA dpm/100cm' 18 NOA dpm/100cm' 24 N/A dpm/100cm' comments: All dose rates are General Area Dose Rates in mrem/hr. Road smear survey locations align with utility poles.
Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area * = Hot Spot 6. = Air Sample location Abbreviations/Units: NOA - No Detectable Activity ( < 1000 DPM) CCPM Direct Frisk Reading Result DPM/100cm' - Smear Reading Result Dose Rate Meter/SN:
RO2/#3031 Cal Due: 4-30-2020 AirSam ler: NIA NIA Cal Due: Countm lnst./SN: PRM-6/# 1006 10-31-2019 Big Rock Cal Due: Reviewed B : Date: K.E.Pallagi 6-27-2019 Performed B : Date: Reviewed B : Date T. 'Z 'l'i' BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 119 of 122 Page~ of~ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 DatefTime: _ _ 6_-_2_7_-2_0_1_9_10_9_:_5_0_ _ _ _ Technician: _ _K_._E_.P_a_ll_a=g_i_ _ _ _ _ _ _ Location: LOWER ADMIN. BLDG. General Dose Rate: < 0.1_ _ _ _ mRem/hr(Y) _ _ _NIA _ _ _ _ mRem/hr(P) Area Posting* RMA c:; Contamination Area (CA) RCA X Olher specify) None General Contamination: _ _N_D_A ____dpm/100cm' ~ Radiation Area (RA) Special Instructions: Notify Rad Pro PRIOR to any* Work Entry __, Survey Meter Required in HRAs Air Sampling Required for Entry X Other (Specify)_ _ _ N_o~n~e'- ------- NOA dpml100cm' 7. ~ __ dpm/l00cm' 13 NOA dpm/100cm' 19. _ _ _ _ _dpm/100cm' 2 NOA dpml100cm' 8 NOA dpml100cm' 14. NOA ___dpm/100cm' 20 3 NOA dpm/100cm' 9 NOA dpml100cm' 15 NOA dpm/100cm' 21. _ _ _ __ 4 NOA dpml100cm' 10. NOA _dpm/100cm' 16. NIA dpm/100cm' 22 _ _ _ _ _dpm/100cm' 5 -~_dpm/10 0cm' 11 NOA dpml100cm' 17 _ __,N_,,1'--'A_ _ dpm/100cm' _________ dpm/100cm' 6 -~_dpml10 0cm' 12 NOA ___ dpm/100cm' 18. __~,._,,J/"-'A'--_dpm/100cm' 30 _ _ _ _ _ dpml100cm' comments: All dose rates are General Area Dose Rates in mrem/hr Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area * = Hot Spot 6. = Air Sample Location Abbreviations/Units: NOA- No Detectable Activity (<1000 DPM) CCPM - Direct Fnsk Reading Result DPM/100cm' - Smear Reading Result
< 0.1 Stairwell 0 < 0.1 < 0.1
< 0.1 CD G) <0.1
< 0.1
< 0.1 @) 0.2 North CD
@ < 0.1 Q)
~0.1
< 0.1 GD
< 0.1 CD < 0.1 Dose Rate Meter/SN: RO21#3031 4-30-2020 NIA NIA Cal Due: Air Samnler: Cal Due:
Counting lnst./SN: PRM-61#1006 Cal Due: 10-31-2019 Big Rock Reviewed B¥: _j lL__ Date: '"}/,_II~ Performed B : K.E.Pallagil t,--" Date: 6-27-2019 Reviewed B : Date: 7', Z, /q BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 120 of 122 Page~of~ RADIOLOGICAL SURVEY AND STATUS SHEET UFI # 24-11-01 Datefrime: _ _ 6_-2_7_-_2_0_1_9_/_0_9_:3_7______ Technician: _ _ _K_._E_._P_a_ll_ac...g_i_______ Location: UPPER ADMIN. BLDG. General Dose Rate: __ <_0_._l___ mRem/hr(Y) _ _ _N_/_A___.mRem/hr(~) Area Posting: - RMA :::: Contamination Area (CA) NDA :J RCA X Other specify) None General Conlaminal1on: _ _ _ _ _ _ _ dpm/100cm' :J Radiation Area (RA) Special Instructions: w Notify Rad Pro PRIOR to any -work Entry Survey Meter Required in HRAs Air Sampling Required for Entry X Other (Specify) None NOA dpm/100cm' 7 NOA dpm/100cm' 13 NOA dpm/100cm' 19 _dpm/100cm' 25 2 _-1'!QA_ _ dpm/100cm' 8 --~-dpm/100cm' 14 NOA dpm/100cm' 20 3 NOA dpm/100cm' g_ NOA __dpm/100cm' 15 __ NOA _ dpm/100cm' 21 4 _tlQA_ _ _dpm/100cm' 10 NOA dpm/100cm' 16 NIA dpm/100cm' -A---___dpm/100cm' 5_ NOA dpm/100cm' 11 NOA dpm/100cm' 17_ NIA __ __ dpm/100cm' 29 _ _ _ _ _ dprn/100cm'
- 6. _ll,QA_ _ _dpm/100cm' 12 ______liQ{\_ ___ dpm/100cm' 18 N/A dpm/100cm' 30 _ _ _ _ _ dprn/100cm'
--~-----
comments All dose rates are General Area Dose Rates in mrem/hr. Map Key: #= General Area Dose Rate C/GA = Contact and General Area Dose Rate 0 = Smear Location
--X--X- = Radiological Boundary LOWA= Low Dose Waiting Area * = Hot Spot 6. = Air Sample Location Abbreviations/Units: NOA- No Detectable Aclivily (<1000 DPM) CCPM - Direct Frisk Reading Result DPM/100cm' - Smear Reading Result North
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RO2/#3031 4-30-2020 NIA NIA Dose Rate Meter/SN: Cal Due: Air Samoler: Cal Due: Countino lnst./SN: PR.i\1-6/# I 006 Cal Due: 10-31-2019 Big Rock Reviewed Bv: Jb---. Date:
-,..J, !,,
K.E.Pallagi l 6-27-2019 Performed B : Dale: Reviewed B : Date: r, 'Z 1 BRP 151 01/15/2019
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 121 of 122 Attachment C to Supplemental Response to NRC RAI ARCS1 Big Rock Point Cask Vent Neutron Radiation Survey 2010 (2 pages including this coversheet)
Westinghouse Non-Proprietary Class 3 LTR-NRC-22-38 Enclosure 1 Page 122 of 122 l og Number I RADIOLOGICAL SURVEY SHEET 2010-864 Room ID XXX RWP # I Area/Room Description 2010-0050 Big Rock Point Dry Fuel Storage Reactor Power: N/A DatefTlme 7/21/10 09:48 0 Smear I 0 Gamma Status Sheet/RWP Meter Type/Serial No./Cal Due Date !Meter Type/SeriaNIN/Ao.lCal Due Date I Meter Type/SNeri/aAINoJCal Due Date 0 0 Beta ASP-1#2574 1/30/10 0 Massllnn Frisk NA NA Updated NO Neutron Surveyed/Recorded by/Badge Number LDDine 246-3 I Reviewed by/Badge Number Date Smears Note: All Dose Rates are in mRem/hr unless otherwise noted dom/100cm 2 Comments: Performed a neutron survey at Big Rock Point Dry Fuel Storage casks. r1 N/A Upper number designates top vent neutron dose rate and lower number designates bottom \<lr~~m-__;..:.,..._:__---1 neuJron dose rate. ~ X __ - X-- _ _ _ -X-2
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lI 0 l X t Massllnn Wipe ccpm/LAS I NIA I I l Alpha Smear dpm/100 cm 2 0 N/A 0 0 I 0 I 0 I I ---x 0
- X - - -x -x- - ~ 0 RMA Frisking Exempt Area}}