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Category:Annual Operating Report
MONTHYEARML22118A5822022-04-28028 April 2022 Annual Radioactive Effluent Release Report for 2021 ML21120A0872021-04-30030 April 2021 Submittal of Annual Radioactive Effluent Release Report for 2020 ML21120A1052021-04-30030 April 2021 Submittal of Annual Radioactive Environmental Operating Report for 2020 RA-18-055, 10 CFR 50.46 Annual Report2018-05-23023 May 2018 10 CFR 50.46 Annual Report RA-18-046, Oyster Creek, Unit 1, Annual Radiological Environmental Operating Report for 20172018-04-30030 April 2018 Oyster Creek, Unit 1, Annual Radiological Environmental Operating Report for 2017 ML18123A3532018-04-30030 April 2018 Annual Radiological Environmental Operating Report for 2017 RA-18-046, Annual Radiological Groundwater Protection Program Report for 20172018-04-30030 April 2018 Annual Radiological Groundwater Protection Program Report for 2017 RA-17-034, Transmittal of 10 CFR 50.46 Annual Report2017-05-23023 May 2017 Transmittal of 10 CFR 50.46 Annual Report RA-16-109, Independent Spent Fuel Storage Installation - Annual Report2016-12-28028 December 2016 Independent Spent Fuel Storage Installation - Annual Report RA-16-048, Transmittal of 10 CFR 50.46 Annual Report2016-05-26026 May 2016 Transmittal of 10 CFR 50.46 Annual Report RA-16-039, Independent Spent Fuel Storage Facility, Submittal of Annual Radioactive Effluent Release Report for 20152016-04-29029 April 2016 Independent Spent Fuel Storage Facility, Submittal of Annual Radioactive Effluent Release Report for 2015 RA-15-101, Independent Spent Fuel Storage Installation (ISFSI) - Transmittal of Annual Report2015-12-0303 December 2015 Independent Spent Fuel Storage Installation (ISFSI) - Transmittal of Annual Report RA-15-040, Submittal of 10 CFR 50.46 Annual Report2015-05-19019 May 2015 Submittal of 10 CFR 50.46 Annual Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report RA-14-110, Independent Spent Fuel Storage Installation, Annual Report for 20142015-01-23023 January 2015 Independent Spent Fuel Storage Installation, Annual Report for 2014 RA-14-064, Independent Spent Fuel Storage Installation Annual Report for 20132014-07-25025 July 2014 Independent Spent Fuel Storage Installation Annual Report for 2013 RA-14-047, CFR 50.46 Annual Report2014-05-20020 May 2014 CFR 50.46 Annual Report RA-14-042, Annual Radiological Groundwater Protection Program Report for 20132014-05-0101 May 2014 Annual Radiological Groundwater Protection Program Report for 2013 RA-14-042, Oyster Creek Nuclear Generating Station - Submittal of Annual Radiological Environmental Operating Report for 20132014-05-0101 May 2014 Oyster Creek Nuclear Generating Station - Submittal of Annual Radiological Environmental Operating Report for 2013 RA-14-042, Oyster Creek Nuclear Generating Station, Unit 1 - Annual Radiological Environmental Operating Report for 20132014-05-0101 May 2014 Oyster Creek Nuclear Generating Station, Unit 1 - Annual Radiological Environmental Operating Report for 2013 ML14126A7832014-05-0101 May 2014 Annual Radiological Environmental Operating Report for 2013 ML14126A7822014-05-0101 May 2014 Submittal of Annual Radiological Environmental Operating Report for 2013 RA-13-056, CFR 50.46 Annual Report2013-05-31031 May 2013 CFR 50.46 Annual Report RA-13-048, Annual Radiological Environmental Operating Report, from January 1 Through December 31, 20122013-04-30030 April 2013 Annual Radiological Environmental Operating Report, from January 1 Through December 31, 2012 RS-13-004, Independent Spent Fuel Storage Installation Annual Report2013-01-10010 January 2013 Independent Spent Fuel Storage Installation Annual Report ML12354A4182012-12-0505 December 2012 Revised Annual Radioactive Effluent Release Report for 2006 ML12354A4192012-12-0505 December 2012 Revised Annual Radioactive Effluent Release Report for 2007 RA-12-004, Revised Annual Radioactive Effluent Release Report for 20082012-12-0505 December 2012 Revised Annual Radioactive Effluent Release Report for 2008 RA-12-004, Oyster Creek, Revised Annual Radioactive Effluent Release Report for 20072012-12-0505 December 2012 Oyster Creek, Revised Annual Radioactive Effluent Release Report for 2007 RA-12-004, Oyster Creek - Revised Annual Radioactive Effluent Release Report for 20062012-12-0505 December 2012 Oyster Creek - Revised Annual Radioactive Effluent Release Report for 2006 RA-12-060, CFR 50.46 Annual Report2012-06-0101 June 2012 CFR 50.46 Annual Report RA-12-055, Independent Spent Fuel Storage Facility - Annual Radioactive Effluent Release Report for 20112012-04-27027 April 2012 Independent Spent Fuel Storage Facility - Annual Radioactive Effluent Release Report for 2011 RA-12-056, Submittal of Annual Radiological Environmental Operating Report for 20112012-04-27027 April 2012 Submittal of Annual Radiological Environmental Operating Report for 2011 RA-11-097, Annual Sea Turtle Incidental Take Report - 20112011-12-21021 December 2011 Annual Sea Turtle Incidental Take Report - 2011 RA-11-003, Annual Radiological Environmental Operating Report, 1 January Through 31 December 20102011-04-30030 April 2011 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2010 ML11130A0662011-04-30030 April 2011 Oyster Creek Nuclear Generating Station - Annual Radiological Environmental Operating Report - 2010 RA-11-003, Oyster Creek Nuclear Generating Station - Annual Radiological Environmental Operating Report - 20102011-04-30030 April 2011 Oyster Creek Nuclear Generating Station - Annual Radiological Environmental Operating Report - 2010 RA-10-083, Independent Spent Fuel Storage Installation - Annual Report2010-11-0101 November 2010 Independent Spent Fuel Storage Installation - Annual Report RA-10-040, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 20092010-09-24024 September 2010 Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 NEI 07-07, Oyster Creek, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 20092010-09-24024 September 2010 Oyster Creek, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 RA-10-002, Oyster Creek, Annual Radioactive Effluent Release Report for 20092010-04-30030 April 2010 Oyster Creek, Annual Radioactive Effluent Release Report for 2009 ML1012411392010-04-30030 April 2010 Oyster Creek, Annual Radioactive Effluent Release Report for 2009 RA-09-081, Independent Spent Fuel Storage Installation Annual Report for November 2008 Through October 20092009-11-19019 November 2009 Independent Spent Fuel Storage Installation Annual Report for November 2008 Through October 2009 RA-09-047, CFR 50.46 Annual Report2009-06-0505 June 2009 CFR 50.46 Annual Report RA-09-038, Annual Radiological Environmental Operating Report, January 1 - December 31, 20082009-04-30030 April 2009 Annual Radiological Environmental Operating Report, January 1 - December 31, 2008 RA-10-002, Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report2008-12-31031 December 2008 Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report ML1012411412008-12-31031 December 2008 Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report RA-08-099, Independent Spent Fuel Storage Installation - Annual Report2008-10-22022 October 2008 Independent Spent Fuel Storage Installation - Annual Report RA-08-050, 10 CFR 50.46 Annual Report2008-06-0606 June 2008 10 CFR 50.46 Annual Report ML0715806512007-06-0707 June 2007 10 CFR 50.46 Annual Report 2022-04-28
[Table view] Category:Letter type:RA
MONTHYEARRA-19-091, Commitment Change Summary Report - 20192019-12-27027 December 2019 Commitment Change Summary Report - 2019 RA-19-080, Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report2019-10-18018 October 2019 Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report RA-19-076, Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC2019-09-12012 September 2019 Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC RA-19-065, Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-162019-08-28028 August 2019 Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-16 RA-19-052, Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18)2019-06-11011 June 2019 Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18) RA-19-023, Annual Radioactive Effluent Release Report for 20182019-04-30030 April 2019 Annual Radioactive Effluent Release Report for 2018 RA-19-019, Submittal of Changes to Technical Specifications Bases2019-04-12012 April 2019 Submittal of Changes to Technical Specifications Bases RA-19-012, Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-03-0707 March 2019 Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements RA-19-007, Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation)2019-02-13013 February 2019 Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation) RA-19-003, Amendment No. 17 to Indemnity Agreement No. 8-372019-01-0808 January 2019 Amendment No. 17 to Indemnity Agreement No. 8-37 RA-18-103, Annual Sea Turtle Incidental Take Report - 20182018-12-13013 December 2018 Annual Sea Turtle Incidental Take Report - 2018 RA-18-080, License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements2018-11-12012 November 2018 License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements RA-18-098, License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-11-0606 November 2018 License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-097, Exelon Nuclear Radiological Emergency Plan and Addendum Revisions2018-10-24024 October 2018 Exelon Nuclear Radiological Emergency Plan and Addendum Revisions RA-18-092, License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-10-22022 October 2018 License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-093, Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement2018-10-16016 October 2018 Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement RA-18-091, Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses2018-10-0101 October 2018 Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses RA-18-090, Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements2018-10-0101 October 2018 Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements RA-18-083, Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station2018-09-25025 September 2018 Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station RA-18-088, Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek.2018-09-25025 September 2018 Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek. RA-18-087, Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report2018-09-24024 September 2018 Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018 Secondary Containment Capability Test RA-18-078, Submittal of Sea Turtle Incidental Take Report 2018-0042018-08-15015 August 2018 Submittal of Sea Turtle Incidental Take Report 2018-004 RA-18-077, Sea Turtle Incidental Take Report 2018-0032018-08-14014 August 2018 Sea Turtle Incidental Take Report 2018-003 RA-18-072, Pressure and Temperature Limit Report Revision 12018-06-29029 June 2018 Pressure and Temperature Limit Report Revision 1 RA-18-066, Response to Questions Pertaining to Licensed Operator2018-06-18018 June 2018 Response to Questions Pertaining to Licensed Operator RA-18-070, Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 20182018-06-0808 June 2018 Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 2018 RA-18-068, Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station2018-06-0606 June 2018 Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station RA-18-065, Registration of Use of Cask to Store Spent Fuel2018-05-31031 May 2018 Registration of Use of Cask to Store Spent Fuel RA-18-059, Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-05-30030 May 2018 Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events RA-18-055, 10 CFR 50.46 Annual Report2018-05-23023 May 2018 10 CFR 50.46 Annual Report RA-18-053, Update to Spent Fuel Management Plan2018-05-21021 May 2018 Update to Spent Fuel Management Plan RA-18-052, Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ...2018-05-0808 May 2018 Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ... RA-18-049, Registration of Use of Cask to Store Spent Fuel2018-05-0707 May 2018 Registration of Use of Cask to Store Spent Fuel RA-18-046, Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 20172018-04-30030 April 2018 Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 2017 RA-18-047, Annual Radioactive Effluent Release Report for 20172018-04-30030 April 2018 Annual Radioactive Effluent Release Report for 2017 RA-18-018, Submittal of Changes to Technical Specifications Bases2018-04-13013 April 2018 Submittal of Changes to Technical Specifications Bases RA-18-021, Request for Exemption from Record Retention Requirements2018-04-12012 April 2018 Request for Exemption from Record Retention Requirements RA-18-028, Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2018-04-12012 April 2018 Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) RA-18-027, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2018-04-12012 April 2018 Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-18-036, Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ...2018-03-29029 March 2018 Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ... RA-18-019, Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance2018-03-29029 March 2018 Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance RA-18-020, Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance2018-03-29029 March 2018 Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance RA-18-032, Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2018-03-27027 March 2018 Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues RA-18-034, Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv)2018-03-22022 March 2018 Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) RA-18-015, Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations2018-02-15015 February 2018 Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations RA-18-014, Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-02-13013 February 2018 Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-102018-02-0808 February 2018 Summary of Changes to Quality Assurance Topical Report, NO-AA-10 RA-18-010, Supplement to Relief Request for Extension of Torus Examinations2018-01-24024 January 2018 Supplement to Relief Request for Extension of Torus Examinations RA-17-086, Commitment Change Summary Report - 20172017-12-21021 December 2017 Commitment Change Summary Report - 2017 2019-09-12
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Text
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Oyster Creek Generating Station wVWMV.exeIUI '-UI p.I.-TJI I IN UL.LI Cd.I Route 9 South PO Box 388 Forked River, NJ 08731 November 19, 2009 RA-09-081 The Honorable John C. Parker Mayor, Lacey Township 818 West Lacey Road Forked River, NJ 08731
Subject:
Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Annual Report
Reference:
Building Permit; Appeal 93-40 (after remand)
The above referenced Building Permit requires the Oyster Creek Generating Station to submit routine monitoring reports to Lacey Township on an annual basis. Enclosed is the Temperature Monitoring and Radiation Survey data as required by Condition 10 of the Building Permit, and the number of spent fuel assemblies in dry storage as required by Condition 11 of the Building Permit.
The status of Federal Government's plans to site a permanent spent fuel repository is also provided, as required by Condition 17 of the Building Permit. This fulfills the reporting requirements for the year 2009 (November 2008 through October 2009).
If any further information or assistance is needed, please contact Richard Milos at 609-971-4973.
Sincerely, Michael J. Massaro Vice President, Oyster Creek Nuclear Generating Station Enclosure cc: USNRC Document Control Desk; Docket 72-15 Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 09006
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Enclosure Independent Spent Fuel Storage Installation (ISFSI) Building Permit Condition Ten:
"The applicant shall provide to the township on a yearly basis, written records revealing all temperature and radiation measurements. The applicant shall further advise of any and all repairs made to the concrete modules."
Oyster Creek Generating Station Reply to Condition Ten:
The temperatures of the loaded, concrete, Horizontal Storage Modules (HSMs) are monitored daily and are part of the station's surveillance records. The temperatures of the loaded HSMs can be up to 30 degrees higher than the unloaded HSMs depending on the heat load of the spent fuel loaded.
During the summer months, the highest concrete HSM temperatures were less than 120 degrees.
This is well within the design limits of the HSMs and represents an actual heat loading of about 7.5 KW.
The attached temperature graphs represent average monthly temperature data for the period from October 2008 through September 2009, for the HSMs we loaded in 2002 (# 1-4), the HSMs we loaded in 2003 (# 5-8), the HSMs we loaded in 2004 (# 9-11), and the HSMs we loaded in 2005 (#
12-16). HSMs #17-20 remain empty and are at ambient temperatures.
The highest radiation measurements on the vertical face of the HSMs were 0.8 mr/hr gamma and
<0.1 mr/hr neutron. The highest gamma dose rate at the opening between the HSMs (bird screens) was 3.6 mrem/hr. These readings are well within the design limits of the HSMs. The roof of the HSMs is a posted radiation area and is not readily accessible. The highest radiation levels at the ISFSI security fence facing Route 9 was <0.2 mr/hr gamma and <0.1 mr/hr neutron.
Radiation survey data sheets are included following the temperature graphs.
Two HSMs (#19-20), were installed in October 2008. We plan to load the remaining four spent fuel canisters into HSMs #17-20 during 2010. This will complete the existing Independent Spent Fuel Storage Installation reviewed under the Building Permit, Appeal 93-40 (after remand).
There were no repairs to the concrete modules since the last report.
Independent Spent Fuel Storage Installation Buildinq Permit Condition Eleven:
"The applicant shall provide to the township on a yearly basis, the specific number of spent fuel rod assemblies which have been moved into the dry storage facility."
- Oyster Creek Generating Station Reply to Condition Eleven:
There were no fuel assemblies loaded into the ISFSI prior to 2002. During 2002, 244 fuel assemblies were transferred to the ISFSI. During 2003, 244 additional fuel assemblies were transferred to the ISFSI. During 2004, 183 additional fuel assemblies were transferred to the ISFSI. During 2005, 305 additional assemblies were transferred to the ISFSI. No fuel assemblies have been loaded into the ISFSI since 2005. The Oyster Creek ISFSI currently contains 976 fuel assemblies.
Independent Spent Fuel Storage Installation Building Permit Condition Seventeen:
"The applicant shall submit a report to the Township of Lacey no less than annually as to the status of the efforts of the Federal Government to site a permanent spent fuel repository."
Oyster Creek Generating Station Reply to Condition Seventeen:
The Yucca Mountain Repository project funding has been reduced to those costs necessary to answer licensing inquiries from the Nuclear Regulatory Commission. The current Administration is considering a new strategy toward spent nuclear fuel storage.
4-
HORIZONTAL STORAGE MODULE TEMPERATURE TRENDS 120 100-.---HSM #1
-- HSM #2
-EHSM #4
-*--e-HSM #5 80 -- HSM #5
HSM #8 I-40 . .HSM
. *HSM #10#12 HSM #13 HSM #14 HSM #15 20 HS#1 0
A 0)
'1~
I 3Ct S Radioloaical Survev IND. Vjt*s 6 fs% - 6. 1/0 IDate /[0)- //OYITIme // Location INDEPENDENT SPENT FUEL STORAGE FACILITY RWP e8-8 0 //S.* Reason 744-57-In J& 4/Z Rx. Power - 0%7 D9 j
)3x LOCATION SMEARABLE CONTAMINATION y 0 CCPM [ DPM I INSTRUMENTATION DATA RADIATION SURVEY A R DPM AREA
_____ ____ ____ ____ ____ ____ _____ _____ I_ _ _ __ _ __ _ __
4O.O~'.
7.0 0, "p 2 N COD 2_.Z-BCF0 5F f,)
0.0 lý'ov 3 INST 'r
~; oK'<
4 S/N
/) -7;9 BCF f1_4~ 5 ____________ _____CDD Ism 5
CDD_ CONTAMINATION SURVEY 7 INS fAkIA' O.A 9 _CDD 8 S/N 10%
10 ___EFF BKG", CPM
[J7 3'
- .cApes~ r - 11 __________ ___INST 12 _______________ S/N CJ_0TL~vA? 1j3 ____________DD I"I~' I"'1411m I*!* I*'! 14 15 CF BKG AIR SAMPLE DATA CPM I
I I
161 17 18 _________
FC LL_________
Larg Ar
=________
T NC = Not Countea_
ma u
-7 19. N.A - Not Ilicable 201 NT = Not Taken syor:lPrlnt Name) /o 41
- "o # = Gamma G.A. = Smear P k DV
~, ii
.~1v Date # B = Beta OF - Direct Frisk
£V~oF I~~YkV f '1~4 1/i 1 /(.Y ;411~-k /j IO; 11(C*' T
, # N = Neutron X-X or - - = Rad Bound Signature .*-
- Date #/# = Contact 3/cm 3 #_ Beta / yContai Hd = Head, =ChestK =Knee, w= aiSt #BI#=P/y #1# Beta / y 30cm All dose rates in mrem/hr unless otherwise noted I 0 No Beta Detected Unless Otherwise Noted X--No Beta Readings Taken EAL Threshold Values: HSM Dose Rate Tech Spec Limits: A/outiine Surveys:
- 1. Natural phenomena affecting a loaded cask CONFINEMENT BOUNDARY <400 muernhr at 3 feet from the HSM yand 'it dose rate surveys on conttact as indicaled by on contact radiation reading a 10 times normal. OR surface and lfl from the loaded HSMs.
General area and fence line as
- 2. Accident conditions affecting a loaded cask CONFINEMENT BOUNDARY < 100 mren/hr HBM door on center line necessary to verily postings. Gross as indicated by on contact radiation reading , 10 times normal. OR of DSC wipe contaminalion survey.
- 3. Any condition in the opinion of the Emergency Director that indicates loss < 20 mrem/hr end shseld wall extenot of loaded fuel storage cask CONFINEMENT BOUNDARY.
oI'.o-!-o"._
DCGS Radiological Survey
= l
&V OR--)iG =
I* I* Date a til ITime /),'L?
iT Location INDEPENDENT SPENT FUEL STORAGE FACILITY
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iii~~eason j 'v, C.~6 000SMEARABLE
-O *'" ~~~~~Rx. Power- /0j/O % I*Ha~
CONTAMINATION ____INSTRUMENTATION DATA
-OC- 703OCCPM 9 ,'(/**** DPM RADIATION SURVEY LCTO 0MRAD/HR io*SM /, IBC ov/:
a~ P C (03 1 LOCATION AREA
- el /IJV / / O R~S 2.- <9 2.(o 2 ~j 1COD loio/.,'/9
- 3. .- *,4 . _INST /Z.2 4 1.ti, S/N 0 733,4 BCF 9(0 4 .7 6 - (, . I S CONTAMINATION SURVEY 7 k,-j Lf _ -____-- INST l- 0 L) 8 F Cr,
.- Cf 1 ( SIN a0 -7 1 .1 1 -
, Z.Z .3~ 2-( 9 u-*.. k COD /-1-t,
?
r9) 10: . ______-______ EFF 10% BKG It_, CPM
/- -4 r7L5J'14"I.' a13*1I11 11 12 131
__________SIN 1I__S-'_-_,__,
COD 14 CF BKG CPM-.
15 __ ýP-"-AIRSA14PLE DATA 4.1. its .'a 16 FC NT 171 L= Large Area Smear I
18_ INC Not Counted 191 NA = Not Applicable 201 1 NT - Not Taken Surneyor:(Print plame) ,
/# L4 _ I#Gamma G.A. @ = Smear I
- N = Neutron X-X or - - = Rad Bound z SI.0 # I # = Contact 1 30 cm /# _ Beta/ y Conta, Z. G 0pp 0 -.00 d, CCh=hest, Kn = Knee, W'= Wiai# #BI#=P1# Beta / y 30cm 1
All dose rates In mremthr unless otherwise noted 2 ý -3 '1 - I-all r.A . . . .
4LL COMA4T*- JTaoP'. EAL Threshold Values:
_______________ 11NoseBOW 12f ... nI~a%
ý sf r.erwasnn*.n~
l Ew nom aReaingsin SKen HSM Dose Rate Tech Spec Limits: Routine Surveys:
- 1. Natural phenomena affecting a loaded cask CONFINEMENT BOUNDARY _
400 mrernhr at 3 feet Irom the HSM 7 and 'n. dose rate surveys on contact as indicated by on contact radiatiornreading > 10 times normal. OR surface andill from the loaded HSMs.
General area and fence line as CH.. '- L._&.
.4* e-.' A C ý
- 2. E Accidlent conditions affecting a loaded cask CONFINEMENT BOUNDARY s 100 mremrohr HSM door on center line necessary to verily postings. Gross as incdicated by on contact radiation reading > 10 times normal. OR ot DSC nape contamination survey.
A-o " ,~ ~
jI-4 (~~Dot , 10 Q.A*"{-j I' 3. Any condition of loaded in storage fuel the opinion ofthe cask Emergency Director CONFINEMENT that indicates loss BOUNDARY. < 20 mrem/hr end shield wall exterior
)CGS Radioloqical Su rvey i~o'IF- q -5'S-9 !S Date O(0 09 I1~Time I( 3e"3 Location INDEPENDENT SPENT FUEL STORAGE FACILIT IQIQ~'Q 0Q I NWI I/ "Z3 Reason e4-NjA.-TQrt-2Li\J . -- enlJ-17 "9 ERx-Power - 50 t-rF ~ ~ U 7 -~
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LOCATION I
SMEARABLE CONTAMINATION I
0 0y0 CCPM MRAD/HR IW DPM I A)
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I il VILU .IJ ILJr v m *II*r 'l GO I 17 z.sý II /2 f2 (.2.
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- <.2. 2___ CDO 65* 0-+ 1 3 ______ __ INST Ak~ -
4,S/N !L BCF-55 CDD (C 04>
I 61 CONTAMINATION SURVE Q.2. 0~.1 7 u~l. ___ ___ _ INST 9t\ 114 Azaý.s I *V- VA 9_
10 TA__A_._.
4*A,*I4 CoD EFF 10%
0(o G BKG (Co 10 CPM 4.Z J7 13 Jill 1.
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= e zl"AAAC.
'rAIIAAAC.____
INST SI COD K_
K.I I 14 .. .X4J I BKG CPM
'
- 15 T . I ___- AIR SAMPLE DATA 16 oDrt__ IFC NT cd Z. 01 -7.G. z ý6e' I 17 4 C *1 ~~ L . Large Area Smear 18 NC = Not Counted 129 NA Not Applicable 20 NT = Not Taken Surveyor:(Prlnt Name)
JI,,- ., # :=Gamma G.A. (@= Smear t*% 1tC-0:* 1 # B = Beta DF - Direct Frisk AlN= Neutron X-X or- - = Rad Bout
/-L, #1#=Contactl30cm ## _Betay Con Hd =ý ý, Oh Chest, Kn Knee, W = Waist #B/#t PBy ## Beta / y 30cr All dose rates In mrem/hr unless otherwise noted
<.2. 2 .4.,- 2, L ,24z. .X No BetaO letected Unless Otherwise Noted rNo Beta Readings Taken I L-- ,resholdValues: HSM Dose Rate Tech Soec Limits: Routine Surveys:
~ tre 4 N~Tc:r LLCOPTAC.... 0d'*e -9AAT)4 l Natural phenomena affecting a leaded cask CONFINEA tENT BOUNDARY tKz o400 merrn/hrat 3 feet from the HSM y7and in, dose rate surveys on contact normal. OR surface and I ft from the loaded HSMs.
as indicated by on contact radiation reading > 10 times General area and fence line as tENT BOUNDARY <100 mremhr HSM door an center line necessary to venty postings. Gross normal. OR of DSC wipe contamination suiey.
IJ 3 Any condition in the opirnon of the Emergency Director t[hati ndicAtes loss <20 mrenmhr end shield -Nall extericr of loaded fuel storage cask CONFINEMENT BO UNDARY.