ML100331825
| ML100331825 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/11/2010 |
| From: | Berg W Dairyland Power Cooperative |
| To: | Document Control Desk, NRC/FSME |
| References | |
| LAC-14093 | |
| Download: ML100331825 (16) | |
Text
WILLIAM L. BERG President and CEO DAIRYIAND POWER COOP E RAT IV E
January 11, 2010 In reply, please refer to LAC-14093 DOCKET NO. 50-409 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR)
Possession-Only License DPR-45 Annual Decommissioning Plan Revision
REFERENCES:
(1)
DPC Letter, Taylor to Document Control Desk, LAC-12460, dated December 21, 1987 (original submittal of LACBWR's Decommissioning Plan)
(2)
NRC Letter, Erickson to Berg, dated August 7, 1991, issuing Order to Authorize Decommissioning of LACBWR (3)
NRC Letter, Brown to Berg, dated September 15, 1994, modifying Decommissioning Order The annual update of the LACBWR Decommissioning Plan has been completed, and the pages with changes and their explanations are included with this letter. Each page with a change will have a bar in the right-hand margin to designate the location of the change. None of the changes were determined to require prior NRC approval, and they have been reviewed by both the plant Operations Review Committee and the independent Safety Review Committee.
The individual pages requiring revision are enclosed with this letter. Please substitute these revised pages in your copy(ies) of the LACBWR Decommissioning Plan. Reasons for the changes are listed on a separate enclosure.
If you have any questions concerning any of these changes, please contact Jeff Mc Rill of my staff at 608-689-4202.
Sincerely, DAIRYLAND POWER COOPERATIVE William L. Berg, President & CO WLB:JBM:two Enclosures cc:
Kris Banovac NRC Project Mgr.
A Touchstone Energy Cooperative 3200 East Ave. S..
PO Box 81 7 o La Crosse, WI 54602-081 7 o 608-787-1258 o 608-787-1469 fax o www.dairynet.com WILLIAM L. BERG President and CEO January 11,2010 DAIRYlAND POWER COOPERATIVE In reply, please refer to LAC-14093 DOCKET NO. 50-409 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
REFERENCES:
Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR)
Possession-Only License DPR-45 Annual Decommissioning Plan Revision (1)
DPC Letter, Taylor to Document Control Desk, LAC-12460, dated December 21, 1987 (original submittal ofLACBWR's Decommissioning Plan)
(2)
NRC Letter, Erickson to Berg, dated August 7, 1991, issuing Order to Authorize Decommissioning of LACBWR (3)
NRC Letter, Brown to Berg, dated September 15, 1994, modifying Decommissioning Order The annual update of the LACBWR Decommissioning Plan has been completed, and the pages with changes and their explanations are included with this letter. Each page with a change will have a bar in the right-hand margin to designate the location of the change. None of the changes were determined to require prior NRC approval, and they have been reviewed by both the plant Operations Review Committee and the independent Safety Review Committee.
The individual pages requiring revision are enclosed with this letter. Please substitute these revised pages in your copy(ies) of the LACBWR Decommissioning Plan. Reasons for the changes are listed on a separate enclosure.
. If you have any questions concerning any of these changes, please contact JeffMc Rill of my staffat 608-689-4202.
Sincerely, DAIRYLAND POWER COOPERATIVE
~~p~enr::r WLB:J8M:two Enclosures cc:
Kris Banovac NRC Project Mgr.
A Touchstone Energy Cooperative ~1'~
3200 East Ave. S. 0 PO Box 817 0 La Crosse, WI 54602-0817 0
608-787-1258 0 608-787-1469 fax 0
www.dairynet.~om
ATTACHMENT 1 10 CFR 50.59 SCREEN FORM Page 1 of 2 Document No.
N/A 50.59 Screen Rev. No.
0 Activity
Title:
Decommissioning Plan Activity
Description:
2009 annual review and update of the LACBWR Decommissioning Plan.
Document Listing:
LACBWR Decommissioning Plan, December 2008.
LACBWR Possession-Only License, Docket No. 50-409, Amendment No. 69, date of issuance April 11, 1997.
LACBWR Possession-Only License, Appendix A, Technical Specifications, Amendment No. 70, date of issuance April 3, 2006.
NRC to DPC, Confirmatory Order Modifying NRC Order Authorizing Decommissioning of Facility, dated September 15, 1994.
Design Functions:
The Decommissioning Plan functions as a Final Safety Analysis Report (FSAR) at LACBWR and submittal of revisions to this FSAR fulfill requirements found in 10 CFR 50.71 (e)(4). The Decommissioning Plan is also considered a Post-Shutdown Decommissioning Activities Report (PSDAR), NRC notification under 10 CFR 50.82(a)(7) is required if changes are inconsistent with or make significant schedule changes to those described in the PSDAR. None of the changes in this revision to the Decommissioning Plan describe activities that require prior notification.
ATTACHMENT 1 10 CFR 50.59 SCREEN FORM Page 1 of 2
\\
Document No.
N/A 50.59 Screen Rev. No.
0
~~----------------------
~----------
Activity
Title:
Decommissioning Plan Activity
Description:
2009 annual review and update of the LACBWR Decommissioning Plan.
Document Listing:
LACBWR Decommissioning Plan, December 2008.
LACBWR Possession-Only License, Docket No. 50-409, Amendment No. 69, date of issuance April 11, 1997.
LACBWR Possession-Only License, Appendix A, Technical Specifications, Amendment No. 70, date of issuance April 3, 2006.
NRC to DPC, Confirmatory Order Modifying NRC Order Authorizing Decommissioning of Facility, dated September 15, 1994.
Design Functions:
The Decommissioning Plan functions as a Final Safety Analysis Report (FSAR) at LACBWR and submittal of revisions to this FSAR fulfill requirements found in 10 CFR 50.71 (e)(4). The Decommissioning Plan is also considered a Post-Shutdown Decommissioning Activities Report (PSDAR). NRC notification under 10 CFR 50.82(a)(7) is required if changes are inconsistent with or make significant schedule changes to those described in the PSDAR. None of the changes in this revision to the Decommissioning Plan describe activities that require prior notification.
ATTACHMENT I 10 CFR 50.59 SCREEN FORM Page 2 of 2 10 CFR 50.59 Screening Questions Yes No
- 1. Does the proposed activity involve a change to a structure, system, or component (SSC) that adversely affects a design function described in the ED Decommissioning Plan?
- 2. Does the proposed activity involve a change to a procedure that adversely affects how SSC design functions, described in the Decommissioning Plan, ED are performed or controlled?
- 3.
Does the proposed activity revise or replace evaluation methodology described in the Decommissioning Plan that is used in the safety analyses, or D
which establishes the design bases?
- 4.
Does the proposed activity involve a test or experiment not described in the Decommissioning Plan, where a SSC is utilized or controlled in a manner that El N
is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the Decommissioning Plan?
- 5. Does the proposed activity require a change to LACBWR Possession-Only License, Appendix A, Technical Specifications?
- 6.
Will the proposed change result in a significant environmental impact not previously evaluated in NUREG-0586, Supp. 1, "Generic Environmental El N
Impact Statement on Decommissioning of Nuclear Facilities," dated November 2002?
Conclusion Any of questions 1, 2, 3, or 4 are answered YES; questions 5 and 6 are answered NO. 50.59 Evaluation shall be performed. This Screen form does not need to be retained.
Questions 5 or 6 are answered YES. NRC approval is required prior to implementation of the activity; proceed to license amendment process. This Screen form does not need to be retained.
All screening questions have been answered NO. 50.59 Evaluation or NRC approval is not required. Implement the activity per the applicable procedure for the type of activity. Attach this Screen form, as approved, to documentation for the activity. Provide justification that a 50.59 Evaluation is not required in the space below.
Justification:
Changes arise from annual review and update of D-Plan. Changes provide updated dose levels and activity concentrations, decay-corrected to current values. These D-Plan changes are administrative and have no adverse effect on any design bases nor create any significant environmental impact not previously evaluated.
Signatures 50.59 Screen Preparer (print name):
(Signature)
Date:
ORC Approval and Meeting No.
(Chairman Signature)
Date:
ATTACHMENT 1 10 CFR 50.59 SCREEN FORM Page 2 of 2 10 CFR 50.59 Screening Questions
- 1.
Does the proposed activity involve a change to a structure, system, or component (SSC) that adversely affects a design function described in the Decommissioning Plan?
- 2.
Does the proposed activity involve a change to a procedure that adversely affects how sse design functions, described in the Decommissioning Plan, are performed or controlled?
- 3.
Does the proposed activity revise or replace evaluation methodology described in the Decommissioning Plan that is used in the safety analyses, or which establishes the design bases?
- 4.
Does the proposed activity involve a test or experiment not described in the Decommissioning Plan, where a SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the Decommissioning Plan?
- 5.
Does the proposed activity require a change to LACBWR Possession-Only License, Appendix A, Technical Specifications?
- 6.
Will the proposed change result in a significant environmental impact not previously evaluated in NUREG-0586, Supp. 1, "Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," dated November 2002?
Conclusion Yes No D
[8J D
C8J D
C8J D
[8J D
[8J D
[8J 0
Any of questions 1, 2, 3, or 4 are answered YES; questions 5 and 6 are answered NO. 50.59 Evaluation shall be performed. This Screen form does not need to be retained.
0 Questions 5 or 6 are answered YES. NRC approval is required prior to implementation of the activity; proceed to license amendment process. This Screen form does not need to be retained.
All screening questions have been answered NO. 50.59 Evaluation or NRC approval is not
~
required. Implement the activity per the applicable procedure for the type of activity. Attach this Screen form, as approved, to documentation for the activity. Provide justification that a 50.59 Evaluation is not required in the space below..
Justification:
Changes arise from annual review and update of D-Plan. Changes provide updated dose levels and activity concentrations, decay-corrected to current values. These D-Plan changes are administrative and have no adverse effect on any design bases nor create any significant environmental impact not previously evaluated.
Signatures 50.59 Screen Preparer (print name):
(Sign"H /rIc-;UP Date:
- J£PF fVlvt<~( I (
t~f%1 ORC Approval and Meeting No.
(Chairman Signature)
Date:
o q" t-C I~_r;~~/'
7 Iif-)(o /D1
2009 LACBWR Decommissionine Plan Review Cover Page Update Decommissioning Plan revision date.
Page 9-2 Section 9.2, Spent Fuel Handling Accident: The curie content remaining as of And October 2008 and calculated values for Whole Body Dose and Skin Dose as of Page 9-3 October 2008 are updated to October 2009.
Page 9-4 Section 9.3, Shipping Cask or Heav Load Drop into FESW: The curie content remaining as of October 2008 and calculated values for Whole Body Dose and Skin Dose as of October 2008 are updated to October 2009.
INITIAL SITE CHARACTERIZATION SURVEY FOR SAFSTOR (LAC-TR-138):
Cover Page Update revision date.
Page 9 Table of Core Internal/RX Component Radionuclide Inventory as of January 1, 1988, has note at bottom of page revised to state that components were removed and disposed of in 2007.
Page 24 curie content values decay-corrected to October 2008 are updated to October 2009 values.
Pages 26, 27 Attachment 3 curie content values decay-corrected to October 2008 are updated And 28 to October 2009 values.
Page 1 of I 2009 LACBWR Decommissioning Plan Review Cover Page Update Decommissioning Plan revision date.
Page 9-2 And Page 9-3 Page 9-4
\\
Section 9.2, Spent Fuel Handling Accident: The curie content remaining as of October 2008 and calculated values for Whole Body Dose and Skin Dose as of October 2008 are updated to October 2009.
Section 9.3, Shipping Cask or Heavy Load Drop into FESW: The curie content remaining as of October 2008 and calculated values for Whole Body Dose and Skin Dose as of October 2008 are updated to October 2009.
INITIAL SITE CHARACTERIZATION SURVEY FOR SAFSTOR (LAC-TR-138):
Cover Page Update revision date.
Page 9 Table of Core IntemallRX Component Radionuc1ide Inventory as of January 1, 1988, has note at bottom of page revised to state that components were removed and disposed of in 2007.
Page 24 curie content values decay-corrected to October 2008 are updated to October 2009 values.
Pages 26, 27 Attachment 3 curie content values decay-corrected to October 2008 are updated And 28 to October 2009 values.
Page 1 of 1
LA CROSSE BOILING WATER REACTOR (LACBWR)
DECOMMISSIONING PLAN Revised December 2009 DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR) 4601 State Road 35 Genoa, WI 54632-8846 LA CROSSE BOILING WATER REACTOR (LACBWR)
DECOMMISSIONING
(
PLAN Revised December 2009 DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR) 4601 State Road 35 Genoa, WI 54632-8846*
- 9. SAFSTOR ACCIDENT ANALYSIS - (cont'd)
The assumptions used in evaluating this event during SAFSTOR were similar to those used in the FESW reracking analyses.1,2 The fuel inventory calculated for October 1987 was used. The only significant gaseous fission product available for release is Kr-85. The plenum or gap Kr-85 represents about 15% (215.7 Curies) of the total Kr-85 in the fuel assembly. However, for conservatism and commensurate with Reference 1, 30% of the total Kr-85 activity, or 431.4 Curies, is assumed to be released in this accident scenario. (Due to decay, as of October 2009 only 24.2% of the Kr-85 activity remains - 104.4 Curies.)
No credit was taken for decontamination in the FESW water or for containment integrity, so all the activity was assumed to be released into the environment. Meteorologically stable conditions at the Exclusion Area Boundary (1109 ft, 338m) were assumed, with a release duration of two (2) hours commensurate with 10 CFR 100 and Regulatory Guides 1.24 and 1.25.
A stack release would be the most probable, but a ground release is not impossible given certain conditions. Therefore, offsite doses were calculated for 3 cases. The first is at the worst receptor location for an elevated release, which is 500m E of the Reactor Building. The next case is the dose due to a ground level release at the Exclusion Area Boundary. The maximum dose at the Emergency Planning Zone boundary3 for a ground, level release is also calculated. Adverse meteorology is assumed for all cases.
Elevated Release Average Kr-85 Release Rate 431.4 Curies
= 6.00 E-2 Ci/sec 2 hrs. x 3600 sec/hr X
Worst Case Q for 0-2 hours at 500m E = 2.3 E-4 sec/m 3 Kr-85 average concentration at 500m E 6.00 E-2 Ci/sec x 2.3 E-4 sec/m 3 = 1.38 E-5 Ci/m 3 Immersion Dose Conversion at 500m E Kr-85 Gamma Whole Body Dose Factor (Regulatory Guide 1.109) 1.61 E+1 mRem/yr x 106 pCi x 1.142 E-4 yr = 1,839 mRemihr jtCi/m 3 Ci hr Ci/m 3 Whole Body Dose at 500m E 1839 mRem/hr x 1.38 E-5 Ci/m3 x 2 hr = 0.05 mRem (as of 10/09 0.01 mRem)
Ci/m 3 D-PLAN 9-2 December 2009
- 9. SAFSTOR ACCIDENT ANALYSIS - (cont'd)
The assumptions used in evaluating this event during SAFSTOR were similar to those used in the FESW reracking analyses. 1,2 The fuel inventory calculated for October 1987 was used. The only significant gaseous fission product available for release is Kr-85. The plenum or gap Kr-85 represents about 15% (215.7 Curies) ofthe total Kr-85 in the fuel assembly. However, for conservatism andcommensurate with Reference 1,30% of the total Kr-85 activity, or 431.4 Curies, is assumed to be released in this accident scenario. (Due to decay, as of October 2009 only 24.2% of the Kr-85 activity remains - 104.4 Curies.)
No credit was taken for decontamination in the FESW water or for containment integrity, so all the activity was assumed to be released into the environment. Meteorologically stable conditions at the Exclusion Area Boundary (1109 ft, 338m) were assumed, with a release duration of two (2) hours commensurate with 10 CFR 100 and Regulatory Guides 1.24 and 1.25.
A stack release would be the most probable, but a ground release is not impossible given certain conditions. Therefore, offsite doses were calculated for 3 cases. The first is at the worst receptor location for an elevated release, which is 500m E of the Reactor Building. The next case is the dose due to a ground level release at the Exclusion Area Boundary. The maximum dose at the Emergency Planning Zone boundary3 for a ground level release is also calculated. Adverse meteorology is assumed for all cases.
Elevated Release Average Kr-85 Release Rate 431.4 Curies
= 6.00 E-2 Ci/sec 2 hrs. x 3600 sec/hr X
Worst Case Q for 0-2 hours at 500m E = 2.3 E-4 sec/m3 Kr-85 average concentration at 500m E 6.00 E-2 Ci/sec x 2.3 E-4 sec/m3 = 1.38 E-5 Ci/m3 Immersion Dose Conversion at 500m E Kr-85 Gamma Whole Body Dose Factor (Regulatory Guide 1.109) 1.61 E+1 mRemlyr x 106 !lCi x 1.142 E-4 yr = 1,839 mRemlhr
~Ci/m3 Ci hr Ci/m3 Whole Body Dose at 500m E 1839 mRemlhr x 1.38 E-5 Ci/m3 x 2 hr = 0.05 mRem (as of 10/09 = 0.01 mRem)
Ci/m3 D-PLAN 9-2 December 2009
- 9. SAFSTOR ACCIDENT ANALYSIS - (cont'd)
Kr-85 Beta/Gamma Skin Dose Factor (Regulatory Guide 1.109) 1.34 E + 3 mRem/yr 106,Ci x 1 mRem/hr x.4 3C xl1.142E-4-- =1.53E53
/PCi/m 3 Ci hr Ci/m 3 Skin Dose at 500m E 1.53 E5 mRem/hr x 1.38E-5 Ci/m 3 x 2hr = 4.2 mRem (as of 10/09 =1.0 mRem)
Ci/m 3 Ground Level Release at EAB Worst Case X for 2 hrs at 338m NE or 338m SSE using Regulatory Guide 1.25 Q
2.2 E-3 sec m3 Whole Body Dose at 338m Skin Dose at 339m 10/87 = 40.4 mRem 10/09 = 9.8 mRem 10/87 = 0.49 mRem 10/09 = 0.12 mRem Ground Level Release at Emergency Planning Zone Boundary Worst Case-X for 2 hrs at 100m E Q
1.02 E-2 sec m3 Whole Body Dose at 100m E Skin Dose at 100m E 10/87 = 187 mRem 10/09 = 45.3 mRem 10/87 = 2.25 mRem 10/09 = 0.54 mRem As can be seen, the estimated maximum whole body dose is more than a factor of 30,000 below the 10 CFR 100 dose limit of 25 Rem (25,000 mRem) to the whole body within a 2-hour period.
D-PLAN 9-3 December 2009
- 9. SAFSTOR ACCIDENT ANALYSIS - (cont'd)
Kr-85 Beta/Gamma Skin Dose Factor (Regulatory Guide 1.109) 1.34 E + 3 mRemlyr x 10 6
,uCi x 1.142E _ 4 yr = 1.53E5 mRem/hr
,uCi/m 3 Ci hr*
Cilm 3 Skin Dose at 500m E mRem/hr 3
1.53E5 3
x1.38E-5Cl/m x2hr=4.2mRem(asofl0109=1.0mRem)
Cilm Ground Level Release at EAB Worst Case X for 2 hrs at 338m NE or 338m SSE using Regulatory Guide 1.25 Q
2.2 E-3 sec m3 Whole Body Dose at 338m 10/87 = 0.49 mRem 10109 = 0.12 mRem Skin Dose at 339m 10/87 = 40.4 mRem 10109 = 9.8 mRem Ground Level Release at Emergency Planning Zone Boundary X
Worst Case -
for 2 hrs at 100m E Q
1.02 E-2 sec m3 Whole Body Dose at 100m E 10/87 = 2.25 mRem 10/09 = 0.54 mRem Skin Dose at 100m E 10/87 = 187 mRem 10109 = 45.3 mRem As can be seen, the estimated maximum whole body dose is more than a factor 0£30,000 below the 10 CFR 100 dose limit of25 Rem (25,000 mRem) to the whole body within a 2-hour period.
D-PLAN 9-3 December 2009
- 9. SAFSTOR ACCIDENT ANALYSIS - (cont'd) 9.3 SHIPPING CASK OR HEAVY LOAD DROP INTO FESW This accident postulates a shipping cask or other heavy load falling into the Fuel Element Storage Well. Reference 1 stated that extensive local rack deformation and fuel damage would occur during a cask drop accident, but with an additional plate (installed during the reracking) in place, a dropped cask would not damage the pool liner or floor sufficiently to adversely affect the leak-tight integrity of the storage well (i.e., would not cause excessive water leakage from the FESW).
For this accident, it is postulated that all 333 spent fuel assemblies located in the FESW are damaged. The cladding of all the fuel pins ruptures. The same assumptions used in the Spent Fuel Handling Accident (Section 9.2) are used here. A total of 35,760 Curies of Kr-85 is released within the 2-hour period. The doses calculated are as follows. (Due to decay, as of Oct. 2009 only 24.2% of the Kr-85 activity remains - 8,654 Curies.)
Elevated Release Whole Body Dose at 500m E Skin Dose at 500m E 10/87 = 350 mRem 10/09 = 84.7 mRem 10/87 = 4.2 mRem 10/09 = 1.0 mRem Ground Level Release at EAB Whole Body Dose at 338m Skin Dose at 338m 10/87 = 3.34 Rem 10/09 = 0.8 Rem 10/87 = 40.2 mRem 10/09 = 9.7 mRem Ground Level Release at Emergency Planning Zone Boundary Whole Body Dose at 100m E Skin Dose at 1 00m E 10/87 = 15.6 Rem 10/09 = 3.8 Rem 10/87 = 186 mRem 10/09 = 45 mRem As can be seen, the estimated maximum whole body dose is more than a factor of 400 below the 10 CFR 100 dose limit of 25 Rem (25,000 mRem) to the whole body within a 2-hour period.
D-PLAN 9-4 December 2009
- 9. SAFSTOR ACCIDENT ANALYSIS - (cont'd) 9.3 SHIPPING CASK OR HEAVY LOAD DROP INTO FESW This accident postulates a shipping cask or other heavy load falling into the Fuel Element Storage Well. Reference 1 stated that extensive local rack deformation and fuel damage would occur during a cask drop accident, but with an additional plate (installed during the reracking) in place, a dropped cask would not damage the pool liner or floor sufficiently to adversely affect the leak-tight integrity of the storage well (i.e., would not cause excessive water leakage from the FESW).
For this accident, it is postulated that all 333 spent fuel assemblies located in the FESW are damaged. The cladding of all the fuel pins ruptures. The same assumptions used in the Spent Fuel Handling Accident (Section 9.2) are used here. A total of35,760 Curies ofKr-85 is released within the 2-hour period. The doses calculated are as follows. (Due to decay, as of Oct. 2009 only 24.2% of the Kr-85 activity remains - 8,654 Curies.)
Elevated Release Whole Body Dose at 500m E 10/87 = 4.2 mRem 10/09 = 1.0 mRem Ground Level Release at EAB Whole Body Dose at 338m 10/87 = 40.2 mRem 10/09 = 9.7 mRem Skin Dose at 500m E 10/87 = 350 mRem 10/09 = 84.7 mRem Skin Dose at 338m 10/87 = 3.34 Rem 10/09 = 0.8 Rem Ground Level Release at Emergency Planning Zone Boundary Whole Body Dose at 100m E 10/87 = 186 mRem 10/09 = 45 mRem Skin Dose at 100m E 10/87 = 15.6 Rem 10/09 = 3.8 Rem As can be seen, the estimated maximum whole body dose is more than a factor of 400 below the 10 CFR 100 dose limit of25 Rem (25,000 mRem) to the whole body within a 2-hour period.
D-PLAN 9-4 December 2009
LAC-TR-138 LACBWR INITIAL SITE CHARACTERIZATION SURVEY FOR SAFSTOR By:
Larry Nelson Health and Safety/Maintenance Supervisor October 1995 Revised: December 2009 Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54601 LACBWR INITIAL SITE CHARACTERIZATION SURVEY FORSAFSTOR By:
Larry Nelson Health and SafetylMaintenance Supervisor October 1995 Revised: December 2009 Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54601 LAC-TR-138
LAC-TR-138 PAGE 9 Core Intemal/RX Component Radionuclide Inventory - January 1, 1988 Estimated Curie Content Other Nuclides Components Co-60 Fe-55 Ni-63 TI/2< 5y T1/2> 5y Total 4
I-4 4
I-In Reactor Fuel Shrouds (72 Zr, 8 SS)
Control Rods (29)
Core Vertical Posts (52)
Core Lateral Support Structure Steam Separators (16)
Thermal Shield Pressure Vessel Core Support Structure Horizontal Grid Bars (7)
Incore Monitor Guide Tubes Total In FESW Fuel Shrouds (24 SS)
Fuel Shrouds (73 Zr)
Control Rods (10)
Start-up Sources (2)
Total 22,109 4,886 1,270 9,108 33,439 1,443 347 6,458 173 307 79,540 13,667 918 3,456 3,177 21,218 63,221 4,826 594 21,477 78,851 3,402 1,029 15,230 408 188 189,226 14,988 1,007 2,386 2,285 20,666 1,352 817 63 770 2,826 123 10 546 15 611 7,133 2,384 95 910 156 3,545 2,810 24 2,396 105 386 17 2
75 2
7 5,824
-0 27
-0 5
32 15 15 4
8 30 1
-0 6
-0 5
84 26 3
17 3
49 89,507 10,568 4,327 31,468 115,532 4,968 1,388 22,315 598 1,118 281,807 31,065 2,050 6,769 5,626 45,510 NOTE: Core Internals/RX Components were removed and disposed of in 2007.
Core IntemallRX Component Radionuclide Inventory - January 1, 1988 Estimated Curie Content LAC-TR-138 PAGE 9 Other Nuclides Components Co-60 Fe-55 Ni-63 T1/2 < 5y T1/2 > 5y Total In Reactor Fuel Shrouds (72 Zr, 8 SS) 22,109 63,221 1,352 2,810 15 89,507 Control Rods (29) 4,886 4,826 817 24 15 10,568 Core Vertical Posts (52) 1,270 594 63 2,396 4
4,327 Core Lateral Support Structure 9,108 21,477 770 105 8
31,468 Steam Separators (16) 33,439 78,851 2,826 386 30 115,532 Thermal Shield 1,443 3,402 123 17 1
4,968 Pressure Vessel 347 1,029 10 2
~O 1,388 Core Support Structure 6,458 15,230 546 75 6
22,315 Horizontal Grid Bars (7) 173 408 15 2
~O 598 Incore Monitor Guide Tubes 307 188
.ill.
7
-.2 1,118 Total 79,540 189,226 7,133 5,824 84 281,807 In FESW Fuel Shrouds (24 SS) 13,667 14,988 2,384
~O 26 31,065 Fuel Shrouds (73 Zr) 918 1,007 95 27 3
2,050 Control Rods (10) 3,456 2,386 910
~O 17 6,769 Start-up Sources (2) 3,177 2,285
~
-.2 2
5,626 Total 21,218 20,666 3,545 32 49 45,510 NOTE: Core Intemals/RX Components were removed and disposed of in 2007.
LAC-TR-138 PAGE 24 ATTACHMENT 1 SPENT FUEL RADIOACTIVITY INVENTORY Decay-Corrected to October 2009 Half Life Activity Half Life Radionuclide (Years)
(Curies)
Radionuclide (Years)
(Curies)
Ce-144 Cs-137 Ru-106 Cs-134 Kr-85 Co-60 Pm-147 Ni-63 Am-241 Pu-238 Pu-239 Pu-240 Eu-154 Cm-244 H-3 Eu-152 Am-242m 7.801 E-1 3.014 E+1 1.008 E+0 2.070 E+O 1.072 E+1 5.270 E+O 2.620 E+0 1.000 E+2 4.329 E+2 8.774 E+1 2.410 E+4 6.550 E+3 8.750 E+0 1.812 E+1 1.226 E+1 1.360 E+1 1.505 E+2 9.94 E-3 1.01 E+6 0.46 220 2.83E+4 3.62E+3 128 3.04E+4 1.42E+4 1.06 E+4 8.83E+3 7.15E+3 713 1.56E+3 160 168 443 Sr-90 Pu-241 Fe-55 Ni-59 Tc-99 Sb-125 Eu-155 U-234 Am-243 Cd-113m Nb-94 Cs-135 U-238 Pu-242 U-236 Sn-121m Np-237 U-235 Sm-151 Sn-126 Se-79 1-129 Zr-93 2.770 E + 1 1.429 E+I 2.700 E+0 8.000 E+4 2.120 E+5 2.760 E+0 4.960 E+0 2.440 E+5 7.380 E+3 1.359 E+1 2.000 E+4 3.000 E+6 4.470 E+9 3.760 E+5 2.340 E+7 7.600 E+I 2.140 E+6 7.040 E+8 9.316 E+1 1.000 E+5 6.500 E+4 1.570 E+7 1.500 E+6 6.65E+5 3.98E+5 1.94E+3 287 276 1.14 7.95 63.7 61 5.85 15.9 14.0 12.2 8.58 6.32 3.64 2.19 1.89 1.28 0.7 0.552 0.39 0.111 Total Activity = 2.18 E6 Curies LAC-TR-138 PAGE 24 ATTACHMENT 1 SPENT FUEL RADIOACTIVITY INVENTORY Decay-Corrected to October 2009 Half Life Half Life Radionuclide Radionuclide Ce-144 7.801 E-l 9.94 E-3 Sr-90 2.770E+ 1 6.65E+5 Cs-137 3.014E+l 1.01 E+6 Pu-241 1.429 E+ 1 3.98E+5 Ru-l06 /
1.008 E+O 0.46 Fe-55 2.700 E+O 1.94E+3 Cs-134 2.070 E+O 220 Ni-59 8.000 E+4 287 Kr-85 1.072 E+ 1 2.83E+4 Tc-99 2.120 E+5 276 Co-60 5.270 E+O 3.62E+3 Sb-125 2.760 E+O 1.14 Pm-147 2.620 E+O 128 Eu-155 4.960 E+O 7.95 Ni-63 1.000 E+2 3.04E+4 U-234 2.440 E+5 63.7 Am-241 4.329 E+2 1.42E+4 Am-243 7.380 E+3 61 Pu-238 8.774 E+l 1.06 E+4 Cd-113m 1.359E+ 1 5.85 Pu-239 2.410 E+4 8.83E+3 Nb-94 2.000 E+4 15.9 Pu-240 6.550 E+3 7.15E+3 Cs-135 3.000 E+6 14.0 Eu-154 8.750 E+O 713 U-238 4.470 E+9 12.2 Cm-244 1.812 E+ 1 1.56E+3 Pu-242 3.760 E+5 8.58 H-3 1.226 E+l 160 U-236 2.340 E+7 6.32 Eu-152 1.360 E+ 1 168 Sn-121m 7.600 E+l 3.64 Am-242m 1.505 E+2 443 Np-237 2.140 E+6 2.19 U-235 7.040 E+8 1.89 Sm-I51 9.316 E+l 1.28 Sn-126 1.000 E+5 0.7 Se-79 6.500 E+4 0.552 1-129 1.570 E+7 0.39 Zr-93 1.500 E+6 0.111 Total Activity = 2.18 E6 Curies
LAC-TR-138 PAGE 26 ATTACHMENT 3 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - OCTOBER 2009 Nuclide Activity, in 4Ci System Total
ýtCi Content Plant System Fe-55 Alpha Co-60 Cs-137 CB Ventilation Offgas -
upstream of filter Offgas -
downstream of filters TB drains CB drains TB Waste Water CB Waste Water Main Steam Turbine Primary Purification Emergency Core Spray Overhead Storage Tank Seal Inject 8
104 105 SYSTEM SYSTEM 82 182 17 1,008 1,249 4
427 SYSTEM 62 8
REMOVED REMOVED 40 3
7 79 290 2
12 REMOVED 34 4
1,103 2,466 234 13,625 16,869 60 5,775 843 104 3,097 1,487 74 1,425 124 483 34 217 4,322 4,138 332 16,137 18,408 190 6,214 1,422 150 Plant System CB Ventilation Offgas -
upstream of filter Offgas -
downstream of filters TB drains CB drains TB Waste Water CB Waste Water Main Steam Turbine Primary Purification Emergency Core Spray Overhead Storage Tank Seal Iniect LAC-TR-138 PAGE 26 ATTACHMENT 3 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - OCTOBER 2009 Nuclide Activity, in f,.tCi System Total Fe-55 Alpha Co-60 Cs-137
!-lCi Content 8
lO4 105 217 SYSTEM REMOVED SYSTEM REMOVED 82 40 1,103 3,097 4,322 182 3
2,466 1,487 4,138 17 7
234 74 332 1,008 79 13,625 1,425 16,137 1,249 290 16,869 18,408 4
2 60 124 190 427 12 5,775 6,214 SYSTEM REMOVED 62 34 843 483 1,422 8
4 lO4 34 150
LAC-TR-138 PAGE 27 ATTACHMENT 3 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - OCTOBER 2009
- (cont'd)
Plant System Nuclide Activity, in [tCi System Total LtCi Content r
+/-
Fe-55 Alpha Co-60 Decay Heat Boron Inject Reactor Coolant PASS Alternate Core Spray Shutdown Condenser Control Rod Drive Effluent Forced Circulation Reactor Vessel and Internals Condensate after beds & Feedwater Condensate to beds 480 SYSTEM SYSTEM 96 SYSTEM 720 7,203 SYSTEM SYSTEM SYSTEM 490 REMOVED REMOVED 94 REMOVED 720 7,000 REMOVED REMOVED REMOVED 6,488 1,298 9,732 97,323 7,458 1,488 11,172 111,526 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - OCTOBER 2009
- (cont'd)
NuClide Activity, in /-lCi System Total Plant System f.lCi Content Fe-55 Alpha Co-60 Decay Heat 480 490 6,488 7,458 Boron Inject SYSTEM REMOVED Reactor Coolant PASS SYSTEM REMOVED Alternate Core Spray 96 94 1,298 1,488 Shutdown Condenser SYSTEM REMOVED Control Rod Drive Effluent 720 720 9,732 11,172 Forced Circulation 7,203 7,000 97,323 111,526 Reactor Vessel and Internals SYSTEM REMOVED Condensate after beds & Feedwater SYSTEM REMOVED Condensate to beds SYSTEM REMOVED LAC-TR-138 PAGE 27 ATTACHMENT 3
LAC-TR-138 PAGE 28 ATTACHMENT 3 PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - OCTOBER 2009
- (cont'd)
Nuclide Activity, in jitCi Plant System Fe-55 Aloha Co-60 Cs-137 System Total
-[tCi Content t
-I-t I
-t Fuel Element Storage Well System Fuel Element Storage Well
- all but floor Fuel Element Storage Well floor Resin lines 4,082 6
124,859 624 52,825 390 5
7,600 100 8,500 55,150 84 1,686,940 8,435 713,705 2,854 25,398 59,622 2,949 1,844,797 9,159 775,030 Main Condenser PLANT SYSTEMS INTERNAL RADIONUCLIDE INVENTORY - OCTOBER 2009
- (cont'd)
Nuclide Activity; in /lCi Plant System Fe-55 Alpha Co-60 Cs-137 Fuel Element Storage 4,082 390 55,150 Well System Fuel Element Storage Well
- all but floor 6
5 84 2,854 Fuel Element Storage Well floor 124,859 7,600 1,686,940 25,398 Resin lines.
624 100 8,435 Main Condenser 52,825 8,500 713,705 System Total JlCi Content 59,622 2,949 1,844,797 9,159 775,030 LAC-TR-138 PAGE 28 ATTACHMENT 3
NRC Docket No. 50-409 "TRANSMITTAL/ NOTIFICATION/ ACKNOWLEDGMENT" Page 1 of 2 TO:
NRC Washington - Doc Control CONTROLLED DISTRIBUTION NO. 53 (TWO COPIES)
FROM:
LACBWR Plant Manager 1/25/2010
SUBJECT:
Changes to LACBWR Controlling Documents I.
The following documents have been revised or issued new.
DECOMMISSIONING PLAN, revised December 2008 Remove and replace the following pages:
Cover Page Pages 9-2 thru 9-4 SITE CHARACTERIZATION SURVEY Remove and replace the following pages:
Cover Page Page 9, 24, 26 thru 28 rxI I have received and properly filed the material(s) listed above. I have destroyed superseded material, if necessary.
El I have placed the material(s) listed above in the appropriate "controlled" procedures binder.
I]
I have reviewed the material(s) listed above, and if necessary I have notified my reporting personnel of the changes noted above. The signatures on the back of this form serve as acknowledgment of understanding and Read and Heed Training.
El I have updated the index or indices with pen and ink changes, if needed.
II.
The following procedure(s) has been CANCELLED. Please destroy all copies and update the index or indices with pen and ink changes.
/S/
DATE Please return this notification to the LACBWR Administrative Assistant within ten (10) working days.
NRC Docket No. 50-409 "TRANSMITTALI NOTIFICATIONI ACKNOWLEDGMENT" Page 1 of2 TO:
NRC Washington - Doc Control CONTROLLED DISTRIBUTION NO..2L (TWO COPIES)
FROM:
LACBWR Plant Manager 1125/2010
SUBJECT:
Changes to LACBWR Controlling Documents I.
The following documents have been revised or issued new.
DECOMMISSIONING PLAN, revised December 2008 Remove and replace the following pages:
Cover Page Pages 9-2 thru 9-4 SITE CHARACTERIZATION SURVEY Remove and replace the following pages:
Cover Page Page 9, 24, 26 thru 28
[R]
I have received and properly filed the material(s) listed above. I have destroyed superseded material, if necessary.
[R]
I have placed the material(s) listed above in the appropriate "controlled" procedures binder.
[R]
I have reviewed the material(s) listed above, and if necessary I have notified my reporting personnel of the changes noted above. The signatures on the back of this form serve as acknowledgment of understanding and Read and Heed Training.
[R]
I have updated the index or indices with pen and ink changes, if needed.
II.
The following procedure(s) has been CANCELLED. Please destroy all copies and update the index or indices with pen and ink changes.
IS/ ______________________________ __ DATE ________________ _
Please return this notification to the LACBWR Administrative Assistant within ten (10) working days.
ACP-07.1 Issue 76.1 "LACBWR Read and Heed" Page 2 of 2 77 LACBWR Read and HeedT Today's Date:
Type of Training:
L Read & Heed*
Procedure Number:
Revision:
Revision Date:
Procedure
Title:
Instructor:
Training Method:
El Reading Material By signing below, the signer acknowledges comprehension of the above named Read and Heed Training. This acknowledgment serves as proof of training and will be maintained on-file as a permanent record.
F-If this box is checked, instructor verification is required for Read & Heed Training.*
Intuto eifrto o tenac o ed& Heed~ f(fqqe fo l ed edT Instructor Name:
Instructor Date:
Signature:
Copy to Training Supervisor (Date):
Copy to Training Records (Date):
Today's Date:
"LACBWR Read and Heed" Page 2 of2 DRead & Heed*
Type of Training:
Procedure Number:
Revision:
Revision Date:
Procedure
Title:
Instructor:
Training Method:
o Reading Material ACP-07.1 Issue 76.1 By signing below, the signer acknowledges comprehension of the above named Read and Heed Training. This acknowledgment serves as proof of training and will be maintained on-file as a permanent record.
o If this box is checked, instructor verification is required for Read & Heed Training.
- Instructor Name:
Copy to Training SupeNisor (Date):
Instructor Signature:
Date:
Copy to Training Records (Date): _____ _