ML100500982

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Spent Fuel Pool Criticality Presentation for Feb 17 Public Meeting
ML100500982
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/17/2010
From: Sanders C
Plant Licensing Branch 1
To:
Dominion Nuclear Connecticut
Sandeers, Carleen, NRR/DORL, 415-1603
References
FOIA/PA-2011-0115
Download: ML100500982 (10)


Text

MP3 RAI 26-30 Response Plan

  • RAJ 26
  • Issue: Margin needed to cover power history effects
  • NUREG/CR-666S estimated history effect magnitude -0.002 LiI<
  • Soluble boron used for simulated fuel depletion was cited as a source of margin in RAI 5 response, boron margin information requested
  • Response plan - Power history effect margin
  • Deplete at constant power and add margin for history effects
  • ORNL/TM-12973 says to apply margin as "uncertainty in k-n"
  • Conservatively apply as a constant 0.002 LiI< bias in burnup requirement curves using burnup relationship discussed in RAI 2 7( b) response
  • No bias needed for fresh fuel with no burnup history
  • Penalty will be applied as part of RAI 30 response

MP3 RAI 26-30 Response Plan

  • RAJ 26
  • Response plan - Provide soluble boron margin
  • Analysis used constant 1000 ppm for simulated depletions
  • Provide cycle average boron for all completed cycles and current cycle
  • Expect 50-100 ppm margin for SPU cycles based on recent cycles and currently operating SPU cycle
  • Response plan - Clarify RAJ 5 soluble boron margin response
  • 1000 ppm is projected to bound SPU cycles
  • Cycle 6 (pre-SPU) had greater than 1000 ppm cycle average boron
  • Outlier 21 month cycle
  • All Cycle 6 fuel was depleted in at least one other cycle
  • Maximum 2 cycle average boron is 1008 ppm
  • Very small reactivity impact
  • Multiple sources of compensating margin are available (credit as operated moderator temperature)

MP3 RAI 26-30 Response Plan

  • RAJ 27(a)
  • Issue: Provide code validation or justify not performing a criticality code validation for calculating RAI 21 penalties
  • PARAGON / SCALE 5.1 used to develop RAI 21 burnup penalties
  • PHOENIX / SCALE 4.4 used for original WCAP 16721 burnup calculations
  • Response plan - SCALE 5.1
  • Provide code validation information for SCALE 5.1
  • Provide a comparison of SCALE 5.1 and SCALE 4.4 uncertainty and bias
  • Bias difference between SCALE 5.1 and SCALE 4.4 cancels out for reactivity difference calculations
  • Response plan - PARAGON
  • PARAGON and PHOENIX are used to calculate isotopic content of depleted fuel determined at reactor operating conditions, not for K-eff in the SFP
  • PARAGON SER permits use for the same purposes as PHOENIX
  • Bias between PARAGON and PHOENIX cancels out for reactivity difference calculations

MP3 RAI 26-30 Response Plan

  • RAJ 27(b)
  • Issue: Explain the basis for Table 21-6 (~I( / ~Bu ratios)
  • Response plan
  • Values in Table 21-6 are superseded by RAJ 30 response
  • Basis for the ratios is (K2-KI)/(Bu2-BuI) using values from WCAP Tables 4-9 and 4-10 over a burnup change of io GWD/MTU
  • RAJ 27(C)
  • Issue: Provide depletion parameters used in RAI 21 response
  • Response plan
  • Provide a list of depletion parameters used
  • Moderator temperature
  • Core power
  • Fuel characteristics
  • RAI 21 parameters are bounded by RAI 30 (higher moderator temperature)

MP3 RAI 26-30 Response Plan

  • RAI27(d)
  • Issue: Response to RAI 21 for No Blanket fuel takes credit for margin that earlier responses already took credit for as conservatisms
  • Explain impact on earlier responses
  • Explain how bias and uncertainty are affected by use of as-built fuel characteristics ana depletion conditions
  • Response plan
  • RAJ 21 response crediting as-built conditions was only for Region 2 for already depleted No Blanket fuel .
  • Dominion will store all No Blanket fuel in Region 1 or Region 3
  • Restriction footnote will be added to TS Figure 3.9-3 (Region 2)
  • Region 1 justification:
  • RAI 21 issue was justification of axial burnup shapes
  • Region 1 burnup requirements are very low
  • Uniform axial shape is conservative for low burnup
  • Region 3 justification
  • All No Blanket fuel was used in pre-uprate cycles
  • Existing TS Figure 3.9-4 is basis for this fuel

MP3 RAI 26-30 Response Plan

  • RAJ 27(e)
  • Issue: Provide RAJ 21 title change to TS Figure 3.9-4
  • Response plan
  • RAJ 21 response was referring to changes made to TS Figure 3.9 4 that were already provided in the original submittal
  • No change needed to TS Figure 3.9-4 as submitted in Dominion letter Serial Number 07-0450

MP3 RAI 26-30 Response Plan

  • Issue: Conflicting DNC and NUREG/CR-6760 conclusions about the effect of IFBA must be resolved
  • DNC submittal indicates it is conservative to ignore IFBA
  • Response plan
  • Recalculate IFBA effect
  • Use maximum previous or proposed IFBA loading, 120 inch IFBA
  • Use RAI 21 shapes and models, RAI 30 temperatures
  • Determine burnup penalty versus assembly burnup
  • Include in burnup penalty described in RAI 30
  • Add burnup penalty to TS curves for Region 2 and Region 3
  • Burnup requirement is too low for a penalty in Region 1

MP3 RAI 26-30 Response Plan

  • RAJ 29
  • Issue: Has MP3 used any flux suppression devices?
  • RAJ 5 response stated that MP3 fuel management does not use fixed burnable absorbers
  • Response plan - flux suppression devices
  • MP3 has not used any flux suppression devices in any cycle
  • Response plan - Clarify RAI 5 fixed burnable absorber response
  • MP3 fuel management has no current or planned use of fixed burnable absorbers
  • Batches B, C, and D (pre-SPU Cycles 1 and 2) had fixed absorbers in No Blanket fuel
  • Clarification - Region 1:
  • Existing TS Figure 3.9-1 bounds SPU analysis and is basis for pre-SPU fuel
  • Burnup requirement is very low in Region 1
  • Absorber history is not significant at very low burnup
  • Clarification - Region 2:
  • RAJ 27(d) response does not permit storage of No Blanket fuel in Region 2
  • Clarification - Region T
  • Existing TS Figure 3.9-4 is basis for pre-SPU fuel

MP3 RAI 26-30 Response Plan

  • RAI30
  • Issue: Provide the core average moderator exit temperature (nominal flow) and maximum assembly moderator exit temperature (minimum flow)
  • It appears that a nominal rather than a conservative value was used
  • Response plan
  • Provide nominal core average moderator exit temperature (620 .4 F vs 628 F analyzed)
  • Provide bounding maximum assembly moderator exit temperature versus burnup based on recent cycle fuel management and minimum TS flow
  • Calculate moderator exit temperature penalty using RAI 21 models and burnup profiles
  • Sum all relevant penalties
  • Bounding exit moderator temperature penalty
  • RAI 21 axial node and burnup shape penalty
  • RAI 28 IFBA history penalty
  • RAI 26 power history penalty
  • Increase administrative margin from 0.1% ~K to 0.5% ~K
  • Convert penalty to burnup using best estimate ~K/ ~Bu (WCAP Tables 4-9 and 4-10)
  • Summarize RAI analysis conservatisms