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MONTHYEARML23137A0782023-02-0101 February 2023 Public -Byron and Braidwood Commitment 10 Audit Call Questions RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020 Proposed Changes to Decommissioning Trust Agreements ML19228A1562019-08-21021 August 2019 NRC-2017-000292 - Resp 1 - Interim (Formerly FOIA/PA-2017-0292), Agency Records Subject to the Request Are Enclosed (Released Set Interim Response 1 - NRC-2017-000292) ML19046A2222019-02-0808 February 2019 NRC-2019-000158 - Resp 1 - Final. Agency Records Subject to the Request Are Enclosed ML18291B3162018-10-17017 October 2018 E-Mailed NRC Information Request for Braidwood Station - IP71152 Documents and Support Requested for Onsite Review Sent 10/17/18 (DRS-M.Holmberg) ML17319A0762017-10-30030 October 2017 FOIA-2017-0677 - Resp 1 - Final. Agency Records Subject to Request Enclosed ML17117A6552017-04-13013 April 2017 E-Mailed Request for Information Dated 04/13/17 for Braidwood Station, Unit 2, Inservice Inspection (Msh) ML17034A3542017-02-0202 February 2017 Samuel Miranda Statement ML17018A4302017-01-0606 January 2017 Supplemental Request for Information - Braidwood Station MOD/50.59 Inspection ML15230A2362015-09-0303 September 2015 Tables 1 and 2 ML15106A7362015-04-23023 April 2015 Conference Call Submittals ML15071A1192015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML14191B1482014-07-17017 July 2014 Updated Talking Points for July 17th Meeting with Exelon Regarding Braidwood and Byron AFW Cross-tie Amendment ML14188A2482014-07-0707 July 2014 AFW Cross-tie Amendment - Talking Points for Public Teleconference RS-14-138, Enclosuresponses to Requests for Additional Information Re Environmental RAI AQ-11 to AQ-15 (as Amended by Exelon Generation Letter RS-14-283)2014-04-30030 April 2014 Enclosuresponses to Requests for Additional Information Re Environmental RAI AQ-11 to AQ-15 (as Amended by Exelon Generation Letter RS-14-283) ML14007A0902013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 7 of 15 ML14007A0942013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 10 of 15 ML14007A0892013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 14 of 15 ML14007A0882013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 13 of 15 ML14007A0832013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 2 of 15 ML14007A0842013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicants Environmental Report. Part 3 of 15 ML14007A0852013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicants Environmental Report. Part 5 of 15 ML14007A0922013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 9 of 15 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1024506922010-09-0101 September 2010 EC 361017, Revision a, Evaluation of the Interim Remedial Action Pumping System ML1024506892010-09-0101 September 2010 EC 360234 Evaluation, Braidwood Station ML1024506882010-09-0101 September 2010 EC 360234, Eval - Mech, Braidwood Station ML1019702832010-06-16016 June 2010 EC 361965, Rev. 00 - Remediation of Tritium Contaminated Groundwater in the Vicinity of Vacuum Breaker #1 ML1019702802010-06-16016 June 2010 Attachment 2, Complex Troubleshooting, MA-AA-716-004, Revision 9 ML1017301232010-06-0909 June 2010 Green Ticket Tritium Releases ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0924506942009-09-0101 September 2009 Supplemental Document Request to Support Baseline ISI Inspection Procedure 71111.08 ML0808000362008-03-13013 March 2008 List of Attendees, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors RS-08-010, Additional Information Supporting Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program2008-01-31031 January 2008 Additional Information Supporting Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0634705992006-12-14014 December 2006 Plant Service List ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0618403682006-06-27027 June 2006 Special Format for Chairman'S Back Q&A'S ML0617003992006-06-13013 June 2006 S.A.F.E Tracking Board - Portions Outside the Scope of the Request ML0617003832006-06-13013 June 2006 Inadvertent Liquid Releases - Portions Outside the Scope of the Request ML0617003852006-06-13013 June 2006 within Last Year - Portions Outside the Scope of the Request ML0617003872006-06-13013 June 2006 Tritium Sample Results ML0617004032006-06-13013 June 2006 Groundwater Contamination ML0617003792006-06-13013 June 2006 Tritium Questions - Portions Outside the Scop of the Request ML0617003762006-06-13013 June 2006 Contracts Made Braidwood ML0617004022006-06-13013 June 2006 Portion Outside the Scope of the Request ML0617004052006-06-13013 June 2006 Ground Water Contamination 2023-02-01
[Table view] |
Text
A File: 50.75g @% LF L!
CW0557/59 Vacuum Breaker Vault Leaak On 11-20-00 water was observed leaking from the CW057/58 Vacuum Breaker Vault. It was estimated the leak had been occurring for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Tritium samples were taken from three locations: the vault, center of the south end of the 345' switchyard fence, and from the southwest end of the 345' switchyard fence. A gamma isotopic was
- pVriomned on the water from the vault.
No radioactive releases were performed during the period of the lealing vacuum breaker.
Gamma istopotic analysis indicated no quantifiable peaks. All tritium analyses were below the lower limit of detection (1.87E-06 uCi/mil).
No further sampling warranted. -f Kim Aleshire, HP Q
8wCP 220-2T1 Revision 0 Information Use TRITIUM SAMPLE DATA SHEET Liquid Scintillation Analyzer Model 2500TR ,Dlate: 11? -k- 00O Serial Number# _ oooo I Analyst_ ______
11-'
(3) t Sample Name . l BLANK I 7 yrc5S
- 2. Date/Time Sample Obtained N/A i- Aoo0. ,
- 3. Sample Number 1 J . _ .
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- 4. Count Duration (min)
IL3o0 1I
- 5. Blank CPMA 9V I
N/A /A j/A G. DPM1 N/A I ! l
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-11
- 7. Sample Amount (g) ,-q 'P. (2 I __
- 8. Tritium Activity (pCi/g) N/A a(57 9
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_ I _- _,~ t G _ " 1 _7 _ _, __- __5.r
___ - - -1
- For Water Sample Calculations Activity (pCi/g) = DPM 1 (2.22EG' (grams of sample)
- For Silica Gel Calculations - See BwCP 220-2 Remarks:
./
APPROVED Reviewed by: /f.
4,
.APR !4Z3 (Final)
(5/22/96) BRAIDWOOD I
'ON SITE REVIEW#
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Protocol t4: a UNCONDITIONAL R!ELEA4S User: LSC 400001 Time: 11.00 Data Mode: DPI1 Muclide: BRAID H3 Quench Set: BRAID H3 Background Subtract: 1st Vial 1L1, UL LC 1. B KG Regi on A: 0.5 - 8.0 0 . .0 3 J1 II b, i oln 13:
0 tO 0.0 - 18. ; 01 6 .9 Region C: 0.0 - 0.0 0.0 0.n00
-uerich Ind icator: tSIE T:xt Std Terminator: Count.
%ATER SAMPLES COUNTED) TO EIIV1-RONllMBE1TT.,L L LD
'oinc idencer TinE ( Ys)): 18
)elay Before 8uklst(rns): Normal TI IIF. CY1IAh DPH1 ,I S tcSIF, pLAGfInst ;s
-1 . 00 3. 9J 2 4 . ;1364 563.71 B 400001 11 . CIO 1 . 00 2. 10 S. 938 560. 55 400001.
I 1 00 1.i 0. 5 5 1.15 16,050 562.60 4100001 11 . 00r 1 rJ9C- 2.2C! 25.54c5 t8.2 56!9 400001I
Post-NID 'Peal; Search Report Page : 2
-Sample ID : Acquisition date : 20-NOV-2000 14:23:22 It Energy Area Bkgnd FWHM Channel Left Pw %Err Fit Nuclides 0 351 .98 20 28 2.10 703.97 700 8 51.0 PB-214 0 610.01 27 26 0.97 1220.03 1214 9 40.5 BI -214 0 1166.99 10 2 1.37 2333.96 2328 9 40.0 0 1764 .17 24 0 2.10 3528.29 3523 11 20.4 BI-214 1I Ci)JF-' 'i
Unidentified Energy Lines Page 3
,Sample ID : Acquisition date : 20-NOV-2000 14:23:22 It Energy Area Bkgnd FWHM Channel Left Pw Cts/Sec %Err %Eff Flags 0 1166.99 10 2 1.37 2333.96 2328 9 2.87E-03 40.0 1.98E+00 Flags: 'T"= Tentatively associated :r FLU At k y'.. \<g1j i - ' ;
Rejected Report Sample ID : Page : 5 Acquisition date : 20-NOV-2000 14:23:22 Half -Life Activity I-Sigma Nuclide Half-life Ratio Energy %Abund RU-103 (UCI/1600) %Error Rejected by 39.26D 0. 0 0 497.08* 91.00 --- Not Found ---
Abun.
610.33 5.76 7.015E-08 41.36
% Abundances Found = 5.95 Flag: "*" = Keyline i- . r t. .. . ..
. ... . I . . :
,t,.; %\, Is i, Ii
Miinimum Detecztable Activity Report Page : 6 Sample ID: Acquisition date: 20-NOV-2000 14:23:22 Bckgnd Energy MDA Nucl ide Sum (keV) (UCI /1600)
BE-7 21. 477.61 3.0094E-08 KA-24 9. 1368.63 4.7186E-09
-L-38 4. 1642 .42 4.9947E-08 K-40 64. 1460.81 1.0286E-07 kR-41 2. 1293 .64 3.6514E-09 SC-46 18. 889.28 4.3132E-09 R-51 24. 320.08 2.8117E-08 VIN-54 15. 834.84 3.8527E-09 TIN -56 11. 846.76 4.9602E-09
- 0-57 47. 122.06 4.4426E-09 0-58 17. 810.77 3.9984E-09 FE-59 11. 1099.25 7.2968E-09
_O-60 15. 1332.50 5.3195E-09 YU-64 4. 1345.88 7.2647E-07 4II-65 1. 1481 .84 1.3255E-08
'lq - 65 13. 1115.55 8.7557E-09 JN-69M 19. 438.63 3.2776E-09
- E-75 39. 264 .66 5.3890E-09
.S-76 23. 559.08 8.3157E-09
- R-82 18. 776.52 4.7907E-09
- R-85 28. 514 . 01 8.5314E-07 R- 85M
- R-87 44.
20.
151.19 402.58 5.3204E-09 1.1917E-08 (fTZ\' , .;
R-88 33. 196.32 1.4971E-08 I I ,! ,: I 1 B -88 3. 1836.00 3.1694E-07 13-89 8. 1031.88 1.9527E-07 R- 91 12. 1024.30 1.3657E-08 R-92 8. 1383.94 6.7647E-09
--92 9. 934.46 3.1281E-08 B-95 8. 765.79 2.7939E-09 R-95 12. 756. 72 5.8885E-09 97 15. 657 . 92 7.3532E-09
-97 16. 743.36 4.1354E-09
>99 35. 140.51 3.3695E-09
- - 99M 35. 140.51 3.4312E-09
>101 29. 306.81 1.4026E1-07 J-103 15. 497.08 3.0193E-09 J- 105 19. 724 .50 9.7826E-09
- - 110M 16. 657 .76 3.5585E-09
- - 113 41. 255.12 1.7498E-07 3-122 10. 564 .24 3.6130E-09
.- 123M 51. 159.00 4.0412E-09
,-124 14. 602.73 3.0992E-09
-125 22. 427.89 1.0346E-08
- - 125M 39. 109.28 1.3920E-06
-126 22. 666 .33 3.9216E-09
.- 126M 29. 414 . 70 6.7783E-08 131 27. 364.48 3.8332E-09
-131M 36. 163 . 93 1.4742E-07 132 21. 667 .72 5.7896E-09
-132 34. 228.16 3.2918E-09
Yiinimum .etectable Activity Report (continued) Page : 7 Sample ID : Acquisition date : 20-1NTOV-2000 14:23:22 Bckgnd Energy MDA
ŽJuclide Sum (keV) (UCI/1600) 3A - 133 34. 356.02 5.4547E-09 r-133 13. 529. 87 3.2434E-09
%E-133 29. 81.00 1.7843E-08 (E- 133M 33. 233 .22 2.8245E-08
'S-134 19. 604 . 70 3.5208E-09
[ - 13 4 11. 847.03 1.0491E-08
[-135 6. 1260.41 1 .4236E-08 (E-135 30. 249.79 3.4297E-09 CE- 135M 19. 526.57 1.2878E-07 zS-136 11. 818.50 3.3379E-09 tS - 137 15. 661.66 3.8424E-09 2S- 138 6. 1435.86 2.8531E-08
.E - 138 35. 258.41 4.1297E-07 3A-139 31. 165. 85 2.2724E-08 IA- 140 11. 537.32 1.0355E- 08 jA- 140 3. 1596.18 3.4560E-09
.A-141 34. 190.22 1.1031E-07
'E-141 37. 145.44 6.2567E- 09 A-142 41. 255.12 2.2650E-06 E- 143 32. 293 .26 7.3280E-09 E-144 36. 133 .54 2.8054E-08 R-144 12. 696.51 5.1597E-06 61" F- 181 A-182 19.
19.
482.00 1121.30 3.5139E-09 1.5070E-08 W,
ft
-,> I [ - ... II
- 187 18. 685.74 1.4290E-08 L - 208 19. 583.14 4.0125E-09 I-212 18. 727.1 7 3.1569E-08
--228 7. 911.07 1.0795E-08
-I-234 34 . 92.38 1.8422E-07
?-239 33. 106.12 1.6862E-08 H- 51 1 85. 511.00 0. OOOOE+00 321_SUM 6. 1321 .00 O. OOOO÷F00
- 20_SUM 5. 1620.00 0. 000OE4-00 Reviewed by
.. Ji-t L i ./.
Date: i//i o,/ n)
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1/'t iswCP 220-2T1 Revision 0 Information Use TRITIUM SAtMPLE DATA SHEET r -/J' Liquid Scintillation Analyzer Model 2500TR f, Date: iV7-OOQ Serial NumberX L/QQQ0 I Analyst: ..t.'
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C.WC 3 5 7 (S 5 x nC S L -'feV yq7 >45 w- T
- 1. Sample Name BLANRK V.cc'. - ,.c\r
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- 2. Date/Time Sample Obtained N/A H- -o-(
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- 3. Sample Number 1
- 4. Count Duration (min) 5.~~ _ _ _ _ _ _ _ ~ I . '
- 5. Blank CPMAl Tv M/A N/A N /A I__.___
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- 6. DPM1 N/A le eI41
- 7. Sample Amount (g) PU __ I__0_.___
I
- a. Tritium Activity (ACi/g) N/A -IW76- & -'-I 3 -7 k
- --- - -1
- For Water Sample Calculations Activity (ACi/g) = DPM 1 (2.22E5)(grams of sample) e For Silica Gel Calculations - See BwCP 220-2 Remarkss: _
Reviewed by: v;,
T,,
(Final)
APP R4O (5/22/96) BRAIDVIOOD. I
'O VtO REVIEW