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MONTHYEARML21077A1362021-03-18018 March 2021
Temporary Instruction 2515/194 Inspection Documentation Request
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Enclosures 1 to 3 - EAL Scheme Revisions Enclosure Summary, Discussion of Change and Mps EAL Scheme Revisions-Supporting Documents
ML16266A5462016-12-21021 December 2016
Summary of Results of Flooding Hazard Reevaluation Report for Millstone Power Station Units 2 and 3
ML15231A3642015-05-27027 May 2015
FOIA/PA-2014-0204 - Resp 1 - Final, Group a
ML15065A2382015-02-0606 February 2015
Acord Certificate of Liability Insurance
ML14358A3182014-12-22022 December 2014
FOIA/PA-2014-0508 - Resp 1 - Partial. Group a (Records Being Released in Their Entirety)
ML14128A0412014-04-30030 April 2014
Attachment 2 - 2013 Radioactive Effluent Release Report - Volume 2
ML14041A1782014-02-0606 February 2014
Attachment 1 - Response to Request for Additional Information for Alternative Request IR-3-17, for ASME Section XI for Repair/Replacement of Class 3 Service Water System Valves
ML14041A1792014-02-0606 February 2014
Attachment 3 - Examination of Millstone Unit 3 Service Water Valves for Dealloying
ML13364A2832013-12-30030 December 2013
Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013
ML12093A0832012-04-0202 April 2012
Notice of Public Meeting - April 19, 2012
ML12056A0522012-03-12012 March 2012
Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
ML12032A2252012-01-25025 January 2012
Attachments 4-6 to 11-687, Regarding License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3
ML1123405052011-08-21021 August 2011
Verbal Authorization, Relief Request RR-04-12, of Millstone 2 Temporary Non-Code Compliant Condition of Emergency Diesel Generator Supply Piping in the Service Water System
ML1123404642011-08-20020 August 2011
MPS2 RR RAI Response
ML1117502192011-06-22022 June 2011
NRC Inspection Findings Related to Closed Cooling Water Systems (1/1/2004 to 6/22/2011)
ML1034706502010-12-13013 December 2010
Millstone 3 Draft Response to GL2004-02 RAI No. 6
ML1015305562010-06-0202 June 2010
Mps GL-04-002 Draft RAI Responses/Public Telecon Handouts
ML1011904172010-04-22022 April 2010
Westinghouse Electric Co., LLC, LTR-SGMP-10-50 NP-Attachment Assessment of the Effect of the Location of the Bottom of the Expansion Transition on H.
ML1009804152010-04-0808 April 2010
Draft Millstone GL2004-02 Supplemental Responses to Support Public Teleconference on 4/08
ML1019304602010-03-25025 March 2010
List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants
ML0933507512010-01-14014 January 2010
Temporary Instruction 2515/180, Managing Fatigue
ML0813006902008-04-17017 April 2008
Meeting with Neac to Discuss Millstone, Attendance List
ML0813006872008-04-17017 April 2008
Annual Assessment Meeting Attendance List
ML0732400242007-10-25025 October 2007
Examples of Max Thermal Power License Conditions
ML0729502402007-10-10010 October 2007
Siren Milestones
ML0730400302007-10-0101 October 2007
Sign-In Roster for Public Meeting with Dominion Nuclear
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
ML0713102392007-04-12012 April 2007
Enclosure 6: List of Proposed Generic Level 1 Milestones
ML0634705992006-12-14014 December 2006
Plant Service List
ML0701805992006-07-26026 July 2006
Report of Investigation, Case 1-2006-004, Millstone Nuclear Power Plant, Units 2 and 3: Discrimination Against a Senior ECP Investigator for Having Engaged in Protected Activities
ML0610704982006-04-17017 April 2006
PI&R Team Inspection Required Documents
ML0622700642006-03-29029 March 2006
Statement of Attorney General Richard Blumenthal of Connecticut Regarding the NRC Annual Safety Assessment Public Meeting at Millstone Nuclear Power Station March 29, 2006
ML0614301522006-03-29029 March 2006
Sign-in Sheet for Public Meeting Between NRC and Connecticut Nuclear Energy Advisory Council (Neac) to Discuss Millstone Station'S Annual Assessment for CY2005
ML0527000442005-09-21021 September 2005
Attachment 10, FAQ Log 9/21/05
ML0514602372005-05-20020 May 2005
Event Response Roster
ML0514505132005-05-20020 May 2005
Branch 6, Management Directive 8.3 Check Sheet for 3/6/04 Millstone Unit 2 Turbine Trip
ML0514505172005-05-20020 May 2005
Branch 6, Management Directive 8.3 Check Sheet for 3/15/04 Millstone Unit 2 Turbine Trip
ML0514602232005-05-20020 May 2005
Region I Event Chronology
ML0514602362005-05-20020 May 2005
Region I Event Chronology
ML0514602602005-05-20020 May 2005
Handwritten Notes - 7
ML0516000592005-05-18018 May 2005
Attendance Sign in Sheet for Public Meeting Between NRC and Nuclear Energy Advisory Council (Neac) Ref: April 17, 2005 Event
ML0513005592005-05-0505 May 2005
Enclosure 5, Response to Requests for Additional Information Replacement Discussion of Changes
ML0513005562005-05-0505 May 2005
Enclosure 4, Response to Requests for Additional Information Marked Up Discussion of Changes
ML0513005442005-05-0505 May 2005
Attachment 2, Response to Requests for Additional Information Re Proposed Technical Specifications Changes Associated with Nuclear Facility Quality Assurance Program Description
ML0513005392005-05-0505 May 2005
Attachment 1, Response to Requests for Additional Information on Nuclear Facility Quality Assurance Program Description
ML0514602222005-04-19019 April 2005
Forced Outage Schedule, Cold Shutdown
ML0514602682005-04-17017 April 2005
Notes from 04/17/2005 Millstone 3 Alert
ML0514602742005-04-17017 April 2005
Unit 3 Control Room OPS
2021-03-18
[Table view] |
Text
February 7, 2003 Analyses of Spent Fuel Pool Accident Consequences Using MELCOR-Predicted Source Term Introduction The first preliminary integral analysis of a severe spent fuel pool event has recently been completed and is documented in "Evaluation of Spent Fuel Pool Accident Response to a Complete Loss of Coolant Inventory," January 2003.V-'
hi. ."
.he first consequence analysis was a comparison of the consequences from the generic spent fuel pool source term used in the NUREG-1 738, "Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants," February 2001 with the consequences from the MELCOR predicted source term."
NUREG-1738 Consequence Assessment As part of the effort to develop generic, risk-informed requirements for decommissioning, RES completed an analysis of offsite radiological consequences of beyond-design-basis spent fuel pool accidents (NUREG-1738). In this analysis, RES evaluated the consequences using fission product inventories at 30 and 90 days and one, two, five, and ten years after final reactor shutdown to provide insight into the effect of reductions in nuclide inventories available for release. Some of the main assumptions in the NUREG-1738 analysis are shown below.
Inventories: The spent fuel pool nuclide inventories used were those for a small BWR (Millstone 1) given in Appendix A of NUREG/CR-4982, adjusted to represent a large BWR (3441 MWt) during decommissioning. Two adjustments were made to the NUREG/CR-4982 inventories. The first adjustment was to multiply .the inventories by a factor of 1.7, because the thermal power of the large BWR is 1.7 times higher than that of Millstone 1. The second adjustment was made because NUREG/CR-4982 was for an operating reactor and the NUREG-1738 analysis was for a decommissioning reactor. In this adjustment, the inventories of the entire final core offload were added to the spent fuel pool.
Fission Product Release Fractions: Two set of release fractions were used in the NUREG-1738 analysis. These two sets were a) the release fractions of NUREG-1465 and b) the release fractions of NUREG-1465 modified to assume the ruthenium release fraction is that for a volatile fission product and the fuel fines release fraction is that from the Chernobyl accident. These two sets are shown in Table 1.
Inforiv ~tion .inthis record was deleted Pa dl7YTo) ri~ -\Lc d Ex in accordance with the Fpedom of 1~fomation y6 Act, ex .emptiOfls FOIA-.
Source Term Release Fractions Xe I Cs Te Sr Ba Ru La Ce NUREG-1465 1 .75 .75 .31 .12 .12 .005 .0052 .0055 NUREG-1465 (modified) 1 .75 .75 .31 .12 .12 .75 .035 .035 Table 1. NUREG-1738 release fractions to the environment Fission Product Release Timing: The release timing was that for a large, early release from the Surry NUREG-1 150 consequence assessment. In this case, the release occurred over the period of approximately 1 to 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the start of the accident.
Plume Heat Content: The plume heat content of 3.7 MW was that for a large, early release from the NURE(G-1150 consequence assessment.
Evacuation Timing and Fraction: The evacuation timing was that from the Surry NUREG-1150 consequence assessment. The evacuation begins at 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The fraction of people evacuating is .95.
MELCOR Fission Product Release Fractions and Timing 5I Fission Product Release Fractions: The NUREG-1738 consequence assessment assumed that all of the assemblies in the spent fuel pool heated up and released their fission products.
As discussed above, two sets of release fractions were used in NUREG-1738. The first set was from the NUREG-1465 source term. The second set was the NUREG-1465 source term modified to account for uncertainty in release fractions of ruthenium and fuel fines. This second set of release fractions is shown in the first row of Table 2.
2
Source Term Release Fractions Xe I Cs Te Sr Ba Ru La Ce NUREG-1465 (modified) 1 1*~.751 .5 .31 1.12 1i. 21.75 1.035 1.035
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Table 2. MELCOR-predicted release fractions to the environment
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The NUREG-1738 release fractions were thef'actions of the total inventory in the spent fuel pool that were released to the environment.
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