|
|
(2 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 01/26/2015 | | | issue date = 01/26/2015 |
| | title = E-mail Fr R. Mckinley to M. Lampert Re Pilgrim'S Cask Weight | | | title = E-mail Fr R. Mckinley to M. Lampert Re Pilgrim'S Cask Weight |
| | author name = McKinley R R | | | author name = Mckinley R |
| | author affiliation = NRC/RGN-I/DRP/PB5 | | | author affiliation = NRC/RGN-I/DRP/PB5 |
| | addressee name = Lampert M | | | addressee name = Lampert M |
Line 15: |
Line 15: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1Haverkamp, Trisha From:McKinley, Raymond Sent:Monday, January 26, 2015 12:07 PM To:Mary Lampert | | {{#Wiki_filter:Haverkamp, Trisha From: McKinley, Raymond Sent: Monday, January 26, 2015 12:07 PM To: Mary Lampert |
|
| |
|
| ==Subject:== | | ==Subject:== |
| RE: Pilgrim's cask- weight? | | RE: Pilgrim's cask- weight? |
| Attachments: | | Attachments: Lampert Pilgrim QA 1-9-2015.pdf |
| Lampert Pilgrim QA 1-9-2015.pdfMary, Please see the attached PDF for the answers to your questions. | | : Mary, Please see the attached PDF for the answers to your questions. |
| | Ray McKinley Chief, Division of Reactor Projects Branch 5 U.S. NRC Region I From: Mary Lampert [mailto:mary.lampert@comcast.net] |
| | Sent: Friday, January 09, 2015 10:00 AM To: McKinley, Raymond Cc: Pine DuBois |
|
| |
|
| Ray McKinley Chief, Division of Reactor Projects Branch 5 U.S. NRC Region I From: Mary Lampert [mailto:mary.lampert@comcast.net | | ==Subject:== |
| ] Sent: Friday, January 09, 2015 10:00 AM To: McKinley, Raymond Cc: Pine DuBois
| | Pilgrim's cask- weight? |
| | Hello Ray and Happy New Year! |
| | There is a dispute up here regarding the actual weight of Pilgrims dry cask. |
| | I think the widely varied numbers may refer to different steps in the process. Hope you can resolve it. |
| | Is my understanding correct that Pilgrim is using Holtec HI-Storm 100 S Version B MPC-68 dry cask storage system? The system is comprised of three components: MPC-68, HI-TRAC 100D, and HI-STORM 100 S Version B MPC-68. |
| | MPC-68 is a leak-tight metal canister that has a storage capacity of 68 BWR spent fuel assemblies. |
| | HI-TRAC 100D transfer cask is a metal transfer cask that provides a means to lift and handle the canister as well as provide radiological shielding of the spent fuel assemblies HI-STORM 100 S Version B storage overpack is steel-encased concrete storage cask that provides physical protection and radiological shielding for the metal canister when in storage. It is vented for natural convection cooling to dissipate the spent fuel decay heat. |
| | 1 |
| | : 1. How much does the cask itself weigh when placed into the pool to get loaded? |
| | : 2. How much does the fully loaded cask (68 assemblies) weigh while inside the pool? |
| | : 3. How much does the cask weigh when it is taken out of the pool, dewatered and then lowered to the building floor to get ready for transport? |
| | : 4. How much does it weigh when placed on the outdoor padtotal weight that includes assemblies, canister, outer pack? |
| | Thank you! |
| | 2 |
|
| |
|
| ==Subject:==
| | At Pilgrim Nuclear Power Station, Entergy is using the HOLTEC HI-STORM 100S Version B for the on-site dry storage of spent nuclear fuel. The system consists of three main components: |
| Pilgrim's cask- weight? HelloRayandHappyNewYear!ThereisadisputeuphereregardingtheactualweightofPilgrim'sdrycask.Ithinkthewidelyvariednumbersmayrefertodifferentstepsintheprocess.Hopeyoucanresolveit.IsmyunderstandingcorrectthatPilgrim is using Holtec HI-Storm 100 S Version B MPC-68 dry cask storage system? The system is comprised of three components: MPC-68, HI-TRAC 100D, and HI-STORM 100 S Version B MPC-68. MPC-68 is a leak-tight metal canister that has a storage capacity of 68 BWR spent fuel assemblies. HI-TRAC 100D transfer cask is a metal transf er cask that provides a means to lift and handle the canister as well as provide radiological shielding of the spent fuel assemblies HI-STORM 100 S Version B storage overpack is steel-encased concrete storage cask that provides physical protection and radiological shielding for the meta l canister when in storage. It is vented for natural convection c ooling to dissipate the spent fuel decay heat.
| | MPC-68, HI-TRAC 100D, and the HI-STORM 100S Version B. Entergy has constructed and began operations of an Independent Spent Fuel Storage Installation (ISFSI) under a general license. Details about the system and its operations can be found in Amendment 7 of the HOLTEC HI-STORM 100S Version B Certificate of Compliance (ADAMS Accession Number: |
| 2 1. Howmuchdoesthecaskitselfweighwhenplacedintothepooltogetloaded?2. Howmuchdoesthefullyloadedcask(68assemblies)weighwhileinsidethepool?3. Howmuchdoesthecaskweighwhenitistakenoutofthepool,dewateredandthenloweredtothebuildingfloortogetreadyfortransport?4. Howmuchdoesitweighwhenplacedontheoutdoorpadtotalweightthatincludesassemblies,canister,outerpack?Thankyou!
| | ML093620049) and HOLTECs Final Safety Analysis Report (revision 9) (ADAMS Accession Number: ML101400161). |
| At Pilgrim Nuclear Power Station, Entergy is using the HOLTEC HI-STORM 100S Version B for the on-site dry storage of spent nuclear fuel. The system consists of three main components: MPC-68, HI-TRAC 100D, and the HI-STORM 100S Version B. Entergy has constructed and began operations of an Independent Spent Fuel Storage Installation (ISFSI) under a general license. Details about the system and its operations can be found in Amendment 7 of the HOLTEC HI-STORM 100S Version B Certificate of Compliance (ADAMS Accession Number: | | In your January 9, 2015 email you asked several questions concerning the weight of components at various stages of the dry cask loading process. In the table below, two sets of values are provided. The first is the calculated weight using values in the FSAR. The second is an actual weight as recorded during Pilgrims initial loading campaign and verified during on-site inspections conducted by the NRC. |
| ML093620049) and HOLTEC's Final Safety Analysis Report (revision 9) (ADAMS Accession Number: ML101400161). | | Cask Configuration FSAR1 Value Actual Recorded (Ibs) Value (lbs)2 |
| In your January 9, 2015 email you asked several questions concerning the weight of components at various stages of the dry cask loading process. In the table below, two sets of values are provided. The first is the calculated weight using values in the FSAR. The second is an actual weight as recorded during Pilgrim's initial loading campaign and verified during on-site inspections conducted by the NRC. | | : 1. How much does the cask3 itself weigh when placed 121,306 NA4 into the pool to get loaded? |
| Cask Configuration FSAR 1 Value (Ibs) Actual Recorded Value (lbs) 2 1. How much does the cask 3 itself weigh when placed into the pool to get loaded? 121,306 NA 4 2. How much does the fully loaded cask (68 assemblies) weigh while inside the pool? 209,558 184,500 | | : 2. How much does the fully loaded cask (68 209,558 184,500 assemblies) weigh while inside the pool? |
| : 3. How much does the cask weigh when it is taken out of the pool, dewatered and then lowered to the building floor to get ready for transport? 193,679 174,235 4. How much does it weigh when placed on the outdoor pad-total weight that includes assemblies, canister, outer pack? 392,281 NA 4 1Actual component weights are dependent upon as-built dimensions. FSAR values are located in Table 8.1.3 & 8.1.4 and are estimates. | | : 3. How much does the cask weigh when it is taken out 193,679 174,235 of the pool, dewatered and then lowered to the building floor to get ready for transport? |
| 2Adjusted for Yoke weight (i.e., removed from actual measured value on crane).
| | : 4. How much does it weigh when placed on the outdoor 392,281 NA4 pad-total weight that includes assemblies, canister, outer pack? |
| 3Cask = MPC + Transfer Cask (HI-TRAC).
| | 1 Actual component weights are dependent upon as-built dimensions. FSAR values are located in Table 8.1.3 & 8.1.4 and are estimates. |
| 4No recorded value for cask in this configuration.}}
| | 2 Adjusted for Yoke weight (i.e., removed from actual measured value on crane). |
| | 3 Cask = MPC + Transfer Cask (HI-TRAC). |
| | 4 No recorded value for cask in this configuration.}} |
|
---|
Category:E-Mail
MONTHYEARML22335A2802022-11-0404 November 2022 11-4-2022 Email Transmitting Draft Questions Pertaining to Pilgrim ISFSI Exemption Request ML22270A0422022-09-26026 September 2022 Acknowledgement Email for Holtec'S Request for Reporting Exemption with Regards to the Pilgrim ISFSI Annual Radioactive Effluent Release Report (Docket No. 05000293) ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22007A2602021-12-0606 December 2021 E-mail from P. O'Brien, Holtec, to A. Snyder, NRC, on Pilgrim Effluent Discharge ML21287A6192021-10-14014 October 2021 E-mail from S. Phillips, MEMA, to A. Snyder, NRC, Pilgrim Nuclear Power Station, Commonwealth of Massachusetts Consultation Response to Amendment Review for Emergency Preparedness ML21266A2512021-09-23023 September 2021 Consultation with Commonwealth of Massachusetts Regarding Proposed Amendment Application for Emergency Plan and Emergency Action Levels ML21266A2772021-09-23023 September 2021 HDI Clarification of Exemption Requested from 10 CFR 20, Appendix G, Section Iii.E ML21267A0012021-09-23023 September 2021 E-mail from A. Snyder, NRC, to A. Sterdis, Holtec, - Pilgrim Nuclear Power Station - Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E Acceptance Review ML21257A3832021-09-15015 September 2021 E-mail from A. Snyder, NRC, to A. Sterdis, Holtec, - Pilgrim Nuclear Power Station - Follow-on Request Re Request for Additional Information 2 Pilgrim - License Amendment Request Independent Spent Fuel Storage Installation Only Emergency Pl ML21211A5912021-07-22022 July 2021 Consultation Response from Commonwealth of Massachusetts Regarding Proposed Pilgrim ISFSI Only Technical Specifications ML21211A5162021-07-22022 July 2021 Consultation Response from Commonwealth of Massachusetts Regarding Proposed Pilgrim ISFSI Only Physical Security Plan ML21200A2352021-07-13013 July 2021 Consultation Request to Commonwealth of Massachusetts Regarding Proposed Pilgrim ISFSI Only Technical Specifications ML21200A1522021-07-13013 July 2021 Consultation Request to Commonwealth of Massachusetts Regarding Proposed Pilgrim Isfi Only Physical Security Plan ML21176A1842021-06-25025 June 2021 Email from HDI Regarding Pilgrim Nuclear Power Station Training ML21180A0582021-06-17017 June 2021 Email from Region I Regarding Pilgrim Nuclear Power Station Inspection - EA-13-132 ML21097A0402021-04-0606 April 2021 E-Mail Consult with Commonwealth of Mass Re - Amendment Application - Physical Security Plan for the Pilgrim Nuclear Power Station L-20-092, Email Pilgrim Nuclear Power Station-Exemption from Annual Force-On-Force Exercise Requirements of 10 CFR Part 73, Appendix B,2020-12-10010 December 2020 Email Pilgrim Nuclear Power Station-Exemption from Annual Force-On-Force Exercise Requirements of 10 CFR Part 73, Appendix B, L-20-096, Supplemental Information to Support Physical Security Plan Revision and License Amendment Request to Incorporate Alternate Measures - Holtec Email Dated December 10, 20102020-12-10010 December 2020 Supplemental Information to Support Physical Security Plan Revision and License Amendment Request to Incorporate Alternate Measures - Holtec Email Dated December 10, 2010 ML20328A2982020-11-16016 November 2020 Response from Commonwealth of Massachusetts on No Significant Hazard for Pilgrim ISFSI Amendment to Address ISFSI II Dated November 16, 2020 ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20266G4032020-09-22022 September 2020 Acceptance Review Email - Request for Approval of HDI Fleet Decommissioning Quality Assurance Program, Revision 0 ML20163A6802020-06-11011 June 2020 Confirmation of the Scope of the Requested Regulatory Relief for Pilgrim Security Qualifications ML20280A1912020-04-17017 April 2020 Request for Additional Information- Clarifying Information for Pilgrim ISFSI Physical Security Amendment Application ML20269A3542020-03-0505 March 2020 CFR 26.717 Reports 2019 Transmittal Email ML19336A0302019-11-27027 November 2019 OEDO-15-00479 - Re 2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding ML19336A0332019-11-26026 November 2019 OEDO-15-00479 - E-mail to Petitioner - 2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding (CAC No. MF6460; EPID L-2015-CRS-0002)- Issuance of Final Director'S Decision ML19331A1952019-11-21021 November 2019 NRR E-mail Capture - (External_Sender) Pilgrim Nuclear Power Station - Commonwealth Consultation Response - Amendment Regarding Site Emergency Plan and Emergency Action Level Scheme ML19331A1732019-11-12012 November 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station -Consult with Commonwealth - Amendment Regarding Cyber Security Plan ML19331A1642019-11-0505 November 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station -Consult with Commonwealth - Amendment Regarding Site Emergency Plan and Emergency Action Level Scheme ML19331A1792019-11-0505 November 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - EA and Fonsi for Pilgrim Emergency Planning Exemption CY-19-007, LTR-19-0441 Henrietta Cosentino, E-mail SECY-19-0078 Request by Entergy Nuclear Operations Inc. for Exemptions from Certain Emergency Planning Requirements for the Pilgrim Nuclear Power Station2019-11-0404 November 2019 LTR-19-0441 Henrietta Cosentino, E-mail SECY-19-0078 Request by Entergy Nuclear Operations Inc. for Exemptions from Certain Emergency Planning Requirements for the Pilgrim Nuclear Power Station ML19275H1962019-09-24024 September 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Consult with Commonwealth - Amendment Regarding Permanently Defueled Technical Specifications (PDTS) ML19239A0372019-08-26026 August 2019 E-mail from Entergy Dated August 26, 2019, Notification of Pilgrim License Transfer ML19239A0262019-08-23023 August 2019 LTR-19-0330 Janet Azarovitz, E-mail a Plea for More Time and Reasonable Discussion Including the Citizens of the Commonwealth in the Sale of the Pilgrim Nuclear Power Station ML19234A2072019-08-20020 August 2019 LTR-19-0328 Lawrence Delafield, President, Six Ponds Improv Assoc., Plymouth, Ma, Ltr Requests NRC to Postpone Consideration of Transferring the Licenses for the Pilgrim Nuclear Power Until the NRC Has Answered Concerns by Pilgrim Watch, Se ML19232A4032019-08-20020 August 2019 LTR-19-0322 Diane Turco, Director, Cape Downwinders, Massachusetts, Letter/E-mail Requests Suspension of the Pilgrim License Transfer from Entergy to Holtec Until the Adjudicatory Hearing Is Held and Raised Contentions Are Resolved ML19308A9942019-08-19019 August 2019 Entergy Nuclear Operations, Inc. Confirmatory Order Rescission Supplemental Information ML19226A3912019-08-14014 August 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - EA and Fonsi for Pilgrim Decommissioning Trust Fund Exemption (Holtec) ML19226A3962019-08-14014 August 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station -Consult with Commonwealth - Conforming Amendment in Support of Pilgrim License Transfer Application ML19226A1212019-08-13013 August 2019 OEDO-15-00479-2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding - Status (CAC No. MF6460; EPID L-2015-CRS-0002) ML19227A1032019-08-0707 August 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Draft Wording for Potential Condition of License Transfer Order ML19207B3662019-07-26026 July 2019 NRR E-mail Capture - Pilgrim - RAI Direct and Indirect Transfer of Lic.; Conforming Lic. Amend.; Req. for Exemption 10 CFR 50.82(A)(8)(I)(A) for Holtec Decom. International, Llc ML19176A3452019-06-25025 June 2019 2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding - Information (OEDO-15-00479) (CAC No. MF6460; EPID L-2015-CRS-0002) ML19154A0652019-06-0303 June 2019 NRR E-mail Capture - Pilgrim - Permanent Cessation of Power Operations ML19154A5242019-06-0303 June 2019 NRR E-mail Capture - RAI - Pilgrim Post-Decommissioning Technical Specifications (PDTS) License Amendment Request (LAR) ML19161A2122019-05-20020 May 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Acceptance of License Amendment Request to Remove Cyber Security Plan Requirements ML19123A0332019-05-0101 May 2019 NRR E-mail Capture - Logbook Entry: 05/01/2019 Endangered Species Report Regarding a Confirmed Sighting of North Atlantic Right Whale(S) (Balaena Glacialis) ML19122A4912019-04-29029 April 2019 NRR E-mail Capture - Logbook Entry: 04/29/2019 Regarding the Confirmed Sighting of Ten North Atlantic Right Whales (Balaena Glacialis) ML19108A2372019-04-18018 April 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Acceptance of Requested Licensing Action, Proposed Exemptions from 10 CFR 50.54(w)(1) - On-Site Property Damage Insurance ML19108A2362019-04-18018 April 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Acceptance of Requested Licensing Action, Proposed Exemptions from 10 CFR 140.11(a)(4) - Primary and Secondary Liability Insurance 2022-09-26
[Table view] |
Text
Haverkamp, Trisha From: McKinley, Raymond Sent: Monday, January 26, 2015 12:07 PM To: Mary Lampert
Subject:
RE: Pilgrim's cask- weight?
Attachments: Lampert Pilgrim QA 1-9-2015.pdf
- Mary, Please see the attached PDF for the answers to your questions.
Ray McKinley Chief, Division of Reactor Projects Branch 5 U.S. NRC Region I From: Mary Lampert [1]
Sent: Friday, January 09, 2015 10:00 AM To: McKinley, Raymond Cc: Pine DuBois
Subject:
Pilgrim's cask- weight?
Hello Ray and Happy New Year!
There is a dispute up here regarding the actual weight of Pilgrims dry cask.
I think the widely varied numbers may refer to different steps in the process. Hope you can resolve it.
Is my understanding correct that Pilgrim is using Holtec HI-Storm 100 S Version B MPC-68 dry cask storage system? The system is comprised of three components: MPC-68, HI-TRAC 100D, and HI-STORM 100 S Version B MPC-68.
MPC-68 is a leak-tight metal canister that has a storage capacity of 68 BWR spent fuel assemblies.
HI-TRAC 100D transfer cask is a metal transfer cask that provides a means to lift and handle the canister as well as provide radiological shielding of the spent fuel assemblies HI-STORM 100 S Version B storage overpack is steel-encased concrete storage cask that provides physical protection and radiological shielding for the metal canister when in storage. It is vented for natural convection cooling to dissipate the spent fuel decay heat.
1
- 1. How much does the cask itself weigh when placed into the pool to get loaded?
- 2. How much does the fully loaded cask (68 assemblies) weigh while inside the pool?
- 3. How much does the cask weigh when it is taken out of the pool, dewatered and then lowered to the building floor to get ready for transport?
- 4. How much does it weigh when placed on the outdoor padtotal weight that includes assemblies, canister, outer pack?
Thank you!
2
At Pilgrim Nuclear Power Station, Entergy is using the HOLTEC HI-STORM 100S Version B for the on-site dry storage of spent nuclear fuel. The system consists of three main components:
MPC-68, HI-TRAC 100D, and the HI-STORM 100S Version B. Entergy has constructed and began operations of an Independent Spent Fuel Storage Installation (ISFSI) under a general license. Details about the system and its operations can be found in Amendment 7 of the HOLTEC HI-STORM 100S Version B Certificate of Compliance (ADAMS Accession Number:
ML093620049) and HOLTECs Final Safety Analysis Report (revision 9) (ADAMS Accession Number: ML101400161).
In your January 9, 2015 email you asked several questions concerning the weight of components at various stages of the dry cask loading process. In the table below, two sets of values are provided. The first is the calculated weight using values in the FSAR. The second is an actual weight as recorded during Pilgrims initial loading campaign and verified during on-site inspections conducted by the NRC.
Cask Configuration FSAR1 Value Actual Recorded (Ibs) Value (lbs)2
- 1. How much does the cask3 itself weigh when placed 121,306 NA4 into the pool to get loaded?
- 2. How much does the fully loaded cask (68 209,558 184,500 assemblies) weigh while inside the pool?
- 3. How much does the cask weigh when it is taken out 193,679 174,235 of the pool, dewatered and then lowered to the building floor to get ready for transport?
- 4. How much does it weigh when placed on the outdoor 392,281 NA4 pad-total weight that includes assemblies, canister, outer pack?
1 Actual component weights are dependent upon as-built dimensions. FSAR values are located in Table 8.1.3 & 8.1.4 and are estimates.
2 Adjusted for Yoke weight (i.e., removed from actual measured value on crane).
3 Cask = MPC + Transfer Cask (HI-TRAC).
4 No recorded value for cask in this configuration.