Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly: Difference between revisions

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{{#Wiki_filter:KY/UNITED STATES NUCLEAR REGULATORY
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                                  UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 July 5, 1996 NRC INFORMATION


NOTICE 96-39: ESTIMATES
WASHINGTON, D.C. 20555-0001 July 5, 1996 NRC INFORMATION NOTICE 96-39:   ESTIMATES OF DECAY HEAT USING ANS 5.1 DECAY


OF DECAY HEAT USING ANS 5.1 DECAY HEAT STANDARD MAY VARY SIGNIFICANTLY
HEAT STANDARD MAY VARY SIGNIFICANTLY


==Addressees==
==Addressees==
All holders of operating
All holders of operating licenses or construction permits for nuclear power


licenses or construction
reactors.
 
permits for nuclear power reactors.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information


Commission (NRC) is issuing this information
notice to alert addressees to the sensitivity of analytical results to input


notice to alert addressees
parameters used with American Nuclear Society standard 5.1 on decay heat


to the sensitivity
(Reference). It is expected that recipients will review the information for


of analytical
applicability to their facilities and consider actions, as appropriate, to


results to input parameters
avoid similar problems. However, suggestions contained in this information


used with American Nuclear Society standard 5.1 on decay heat (Reference).
notice are not NRC requirements; therefore, no specific action or written


It is expected that recipients
response is required.


will review the information
Background


for applicability
American Nuclear Society standard 5.1 (ANS 5.1 standard) for decay heat


to their facilities
generation in nuclear power plants provides a simplified means of estimating


and consider actions, as appropriate, to avoid similar problems.
nuclear fuel cooling requirements that can be readily programmed into computer


However, suggestions
codes used to predict plant performance. The ANS 5.1 standard models the


contained
energy release from the fission products of U-235, U-238, and Pu-239 using a


in this information
summation of exponential terms with empirical constants. Corrections are


notice are not NRC requirements;
provided to account for energy release from the decay of U-239 and Np-239, and
therefore, no specific action or written response is required.Background


American Nuclear Society standard 5.1 (ANS 5.1 standard)
for the neutron activation of stable fission products. Although the empirical
for decay heat generation


in nuclear power plants provides a simplified
constants are built into the standard, certain data inputs are left to the


means of estimating
discretion of the user. These options permit accounting for differences in


nuclear fuel cooling requirements
power history, initial fuel enrichment, and neutron flux level.


that can be readily programmed
==Description of Circumstances==
During a review of decay heat estimates calculated using various codes for the


into computer codes used to predict plant performance.
same plant, the staff found that the predicted decay heat varied considerably.


The ANS 5.1 standard models the energy release from the fission products of U-235, U-238, and Pu-239 using a summation
This was unexpected because the analyses were made using the 1979 ANS 5.1 standard and were to be used in best-estimate" thermal-hydraulic analyses.


of exponential
The staff compared calculations of decay heat using MELCOR, TRAC, RELAP, and


terms with empirical
a vendor code for a pressurized water reactor operating at 1933 megawatts


constants.
thermal (MWT). The staff made 3 calculations using RELAP but varied certain


Corrections
inputs. These calculations appear as RELAP,, RELAP2, and RELAP in the


are provided to account for energy release from the decay of U-239 and Np-239, and for the neutron activation
following tables. The decay heat estimates in MWT calculated ?or 2 hours


of stable fission products.
PD& IC            ';cs        95-o3q            9(.oqoS


Although the empirical constants
9606250199    1      A


are built into the standard, certain data inputs are left to the discretion
O


of the user. These options permit accounting
0o            161b'~'k          ussOAf


for differences
IN 96-39 July 5, 1996 after shutdown of the reactor using the various codes and allowable inputs


in power history, initial fuel enrichment, and neutron flux level.Description
were as follows:
                              MELCOR -      20.70 MWT


of Circumstances
Vendor code - 22.15 MWT


During a review of decay heat estimates
RELAP1 -      22.02 MWT


calculated
RELAP 2 -    26.13 MWT


using various codes for the same plant, the staff found that the predicted
RELAP3 -      20.82 MWT


decay heat varied considerably.
TRAC -        22.02 MWT


This was unexpected
ORIGEN -      20.90 MWT


because the analyses were made using the 1979 ANS 5.1 standard and were to be used in best-estimate" thermal-hydraulic
It should be noted that the differences in predicted decay heat resulted from


analyses.The staff compared calculations
the parameters selected for input and not from the codes themselves.


of decay heat using MELCOR, TRAC, RELAP, and a vendor code for a pressurized
The last entry in the table was not calculated by the ANS 5.1 standard but was


water reactor operating
calculated by the ORIGEN computer code. ORIGEN does not use empirical methods


at 1933 megawatts thermal (MWT). The staff made 3 calculations
to calculate decay heat but tracks the buildup and decay of the individual


using RELAP but varied certain inputs. These calculations
fission products within the reactor core during operation and shutdown.


appear as RELAP,, RELAP 2 , and RELAP in the following
ORIGEN also includes the effect of element transmutation from neutron capture, both in fissile isotopes and fission products. Because ORIGEN is a rigorous


tables. The decay heat estimates
calculation of all decay heat inputs, it was used in the calculations for


in MWT calculated
decay heat in attached Figure 1 and is contrasted with attached Figure 2 using


?or 2 hours PD& IC ';cs 95-o3q 9(.oqoS 9606250199
decay heat internally calculated by RELAP to the ANS 5.1 standard.
1 O A 0o 161b ussOAf '~'k


IN 96-39 July 5, 1996 after shutdown of the reactor using the various codes and allowable
Discussion


inputs were as follows: MELCOR -20.70 MWT Vendor code -22.15 MWT RELAP 1 -22.02 MWT RELAP 2 -26.13 MWT RELAP 3 -20.82 MWT TRAC -22.02 MWT ORIGEN -20.90 MWT It should be noted that the differences
The staff found that the different decay heat estimates occurred because the


in predicted
ANS 5.1 standard was not fully utilized in the selection of inputs. Attached


decay heat resulted from the parameters
Table 1 shows the various inputs to the codes to estimate decay heat.


selected for input and not from the codes themselves.
Attached Table 2 shows the effect of different assumptions on best estimate


The last entry in the table was not calculated
calculations of decay heat 2 hours after shutdown of the reactor.


by the ANS 5.1 standard but was calculated
The variation in peak cladding temperatures with various predictions of decay


by the ORIGEN computer code. ORIGEN does not use empirical
heat may be seen by comparing the attached Figures 1 and 2. These figures are


methods to calculate
plots of the peak cladding temperatures for a hypothetical beyond-design-basis


decay heat but tracks the buildup and decay of the individual
loss-of-feedwater event. For Figure 1, values of decay heat predicted by the


fission products within the reactor core during operation
ORIGEN code were input directly into RELAP. Figure 2 is the same event with


and shutdown.ORIGEN also includes the effect of element transmutation
the decay heat internally calculated by RELAP using the ANS 5.1 standard.


from neutron capture, both in fissile isotopes and fission products.
Input assumptions to the standard were those that produced the highest values


Because ORIGEN is a rigorous calculation
of decay heat denoted in Table 1 as RELAP2 . The difference in predicted peak


of all decay heat inputs, it was used in the calculations
core cladding temperatures (approximately 250° K [6300 F]) demonstrates the


for decay heat in attached Figure 1 and is contrasted
importance of carefully selecting required input parameters when using ANS 5.1 because analytical results may be significantly affected. Depending on the


with attached Figure 2 using decay heat internally
input parameters selected the results may be conservative or nonconservative.


calculated
IN 96-39 July 5, 1996 This information notice requires no specific action or written response. If


by RELAP to the ANS 5.1 standard.Discussion
you have any questions about the information in this notice, please contact


The staff found that the different
one of the technical contacts listed below or the appropriate Office of


decay heat estimates
Nuclear Reactor Regulation (NRR) project manager.


occurred because the ANS 5.1 standard was not fully utilized in the selection
Brian K. Grimes, Acting Director


of inputs. Attached Table 1 shows the various inputs to the codes to estimate decay heat.Attached Table 2 shows the effect of different
Division of Reactor Program Management


assumptions
Office of Nuclear Reactor Regulation


on best estimate calculations
Technical contacts:    W. L. Jensen, NRR


of decay heat 2 hours after shutdown of the reactor.The variation
(301) 415-2856 Internet:wljenrc.gov


in peak cladding temperatures
J. L. Birmingham, NRR


with various predictions
(301) 415-2829 Internet:jlb4@nrc.gov


of decay heat may be seen by comparing
Attachments:
1. Table 1, 'Decay Heat Options Using ANS 5.1, 1979"
2. Table 2, "Relative Importance of Options 7200 Seconds


the attached Figures 1 and 2. These figures are plots of the peak cladding temperatures
(2 hours) After Reactor Shutdown"
3. Figure 1, "Peak Core' Cladding Temperature Calculated by ORIGEN" and


for a hypothetical
Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1"
4. List of Recently Issued NRC Information Notices


beyond-design-basis
Reference:
"American National Standard for Decay Heat Power in Light Water Reactors,"
American Nuclear Society Standards Committee Working Group, ANS 5.1, Approved


loss-of-feedwater
August 29, 1979.


event. For Figure 1, values of decay heat predicted
/, III CT,09we,
  44A0ei


by the ORIGEN code were input directly into RELAP. Figure 2 is the same event with the decay heat internally
Attachment 1 IN 96-39 July 5, 1996 Table 1. Decay Heat Options Using ANS 5.1, 1979 l                              I                    l                    l Power      l Fissile


calculated
Codes      Actinides                  R-Factor                      G-Factor                  Si              History      Elements


by RELAP using the ANS 5.1 standard.Input assumptions
Vendor            Yes                        0.6                          Not ANS               1.347            3 Yrs.         3 RELAP1            No                        NA                          MAX                  NA                Infinite      All


to the standard were those that produced the highest values of decay heat denoted in Table 1 as RELAP 2.The difference
_    __ _ __  _    _    _    _    _    _        _  _ _    _  _ _  _ _ _ _  _ _ _U                    23 5 RELAP 2           Yes                        1.0                        MAX                  NA                Infinite      All


in predicted
_    _    _  _ _ _ _ _ _ _ _ __        __                        _  ___    ___U                      235 RELAP3            No                        NA                          No                  NA                Infinite      All


peak core cladding temperatures (approximately
_ _ __ __ _ _ _ _ __ __  _ _ __    _ __ _ _ _  _  _                _ _ _ _  _ _ _U                    23 5 MELCOR            Yes                        0.526                        Yes                  0.713              1.6 Yrs.      3 TRAC              No                        NA                          Yes                  1.0                Infinite      All


250° K [6300 F]) demonstrates
__ _ _ __ _ __ _ _ __  _ __    _ _    _ _    _ _    _ _  _ _  _ _  _    _  _ _  _ _  _    _ _ _ __I_    U235 Notes:
Actinides: Neutron capture by U238 produces U239 which decays into Np239 which also decays, adding to the total decay heat. Not all the above code inputs included actinide decay.


the importance
R-factor: The actinide production multiplier.                                                      The standard states that the value of R shall


of carefully
be supplied and justified by the user.


selecting
G-factor: A decay heat multiplier to account for the effect of neutron capture in fission


required input parameters
products. The standard provides the option of using a maximum value table for the G-factor or


when using ANS 5.1 because analytical
a best estimate equation for the first 10,000 seconds.


results may be significantly
Si:  Fissions per initial fissile atom.                                              Si is a multiplier applied to the G-factor equation.


affected.
Power History:      Length of full-power operation before shutdown.


Depending
Fissile Elements: The standard permits decay power to be fractionally attributed to the


on the input parameters
fission products of 3 fissile isotopes U235, U238, and Pu239. The vendor input attributed the


selected the results may be conservative
fractional fission product power as 0.487 from U235, 0.069 from U238, and 0.443 from U239. The


or nonconservative.
fractional fission product power input to MELCOR was 0.647 from U235, 0.0425 from U238, and


IN 96-39 July 5, 1996 This information
0.31 from Pu239. The other code inputs assumed all fission product power came from U235.


notice requires no specific action or written response.
Attachment 2
            *                                                                                                  IN 96-39 July 5, 1996 Table 2. Relative Importance of Options


If you have any questions
7200 Seconds (2 hours) After Reactor Shutdown


about the information
Complete Set For:                            Options as InDut and Varied                            Decay Heat in MWT


in this notice, please contact one of the technical
MELCOR                                  MELCOR assumptions (see Table 1)                                            20.70
______________________________________________________________________________
                                        Increase R from .526 to .6                                                  21.03 Increase Si from .713 to 1.347                                              21.13 Operation time from 1.6 years to 3 years                                    21.40
                                        Vendor fissile isotopes                                                    21.12 Vendor heavy element equation                                              21.86 Vendor code                            Vendor G-factor equation                                                  22.15
      _______________________________________                                _________________________ - ____________
                                        ANS 5.1 G-factor and heavy element eqs.                                    21.12 No actinides                                                                18.65 Gmax rather than equation                                                  19.44 Infinite operation                                                        20.53 RELAP1                                All fission from U235                                                      22.02 ----------------
RELAP2                                Add actinides with R=1                                                      26.13 RELAP 3                                Remove actinides and G-factor                                              20.82 TRAC                                    Include G-factor equation with Si-i                                        22.02 Note: This table illustrates the relative importance of the various options contained in the


contacts listed below or the appropriate
1979 ANS 5.1 standard. Starting with the decay heat rate calculated by MELCOR using the inputs


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Acting Director Division of Reactor Program Management
listed in Table 1, the options were changed in sequence to those used in the vendor computer


===Office of Nuclear Reactor Regulation===
code. The options were then changed to those used in the RELAP1 analyses, the RELAP2 analyses, the RELAP3 analyses, and the TRAC analyses.
Technical


contacts: W. L. Jensen, NRR (301) 415-2856 Internet:wljenrc.gov
Attachment 3
.i                                                                              IN 96-39 Figure 1 Peak Core Cladding Temperature                  July 5, 1996
    1400.0                                                                - 1200.0
2' 1000.0
CD


J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov
E


Attachments:
0    800.0
1. Table 1, 'Decay Heat Options Using ANS 5.1, 1979" 2. Table 2, "Relative
      600.0  L


Importance
400.0 -
            0.0              4000.0                            8000.0      12000.0
                                              Time (s)
                      Figure 2 Peak Core Cladding Temperature


of Options 7200 Seconds (2 hours) After Reactor Shutdown" 3. Figure 1, "Peak Core' Cladding Temperature
1400.0
                          Ug


Calculated
1L&...                    A& IC C  4 var.qy ntIvat    04,n..ulLwu  U)Y MIND ;.. I


by ORIGEN" and Figure 2, "Peak Core Cladding Temperature
Infinite Operati on


Calculated
1200.0 1-  All U235 Fissicin 1 G=Gmax


by ANS 5.1" 4. List of Recently Issued NRC Information
Actinides with IR=1/
£' 1000.0
0
a


Notices Reference: "American
E


National Standard for Decay Heat Power in Light Water American Nuclear Society Standards
02  800.0
    600.0
    400.0 L        .  .      . .          .              .      .  . .I


Committee
0.CD              4000.0                            8000.0      12000.0
                                              Time (s)


Working Group, ANS August 29, 1979.Reactors," 5.1, Approved 44A0eiIII
Attachment 4 IN 96-39 July 5, 1996 LIST OF RECENTLY ISSUED


Attachment
NRC INFORMATION NOTICES


1 IN 96-39 July 5, 1996 Table 1. Decay Heat Options Using ANS 5.1, 1979 l I l l Power l Fissile Codes Actinides
Information                                  Date of


R-Factor G-Factor Si History Elements Vendor Yes 0.6 Not ANS 1.347 3 Yrs. 3 RELAP 1  No NA MAX NA Infinite All_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _U 2 3 5 RELAP 2  Yes 1.0 MAX NA Infinite All_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ ___U 2 3 5 RELAP 3  No NA No NA Infinite All_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _U 2 3 5 MELCOR Yes 0.526 Yes 0.713 1.6 Yrs. 3 TRAC No NA Yes 1.0 Infinite All_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __I_ U 2 3 5 Notes: Actinides:
Notice No.           Subject                Issuance  Issued to
Neutron adding to the total capture by U238 produces U239 which decays into Np239 which also decays, decay heat. Not all the above code inputs included actinide decay.R-factor:
The actinide production


multiplier.
96-38          Results of Steam Generator    06/21/96    All holders of OLs or CPs


The standard states that the value of R shall be supplied and justified
Tube Examinations                          for pressurized water


by the user.G-factor:
reactors
A decay heat multiplier


to account for the effect of neutron capture in fission products.
96-37          Inaccurate Reactor Water      06/18/96    All pressurized water


The standard provides the option of using a maximum value table for the G-factor or a best estimate equation for the first 10,000 seconds.Si: Fissions per initial fissile atom. Si is a multiplier
Level Indication and Inad-               reactor facilities holding


applied to the G-factor equation.Power History: Length of full-power
vertent Draindown During                  an operating license or a


operation
Shutdown                                  construction permit


before shutdown.Fissile Elements:
96-36          Degradation of Cooling        06/12/96    All holders of OLs or CPs
The standard permits decay power to be fractionally


attributed
Water Systems Due to Icing                for nuclear power reactors


to the fission products of 3 fissile isotopes U235, U238, and Pu239. The vendor input attributed
96-35          Failure of Safety Systems      06/11/96    All U.S. Nuclear Regulatory


the fractional
on Self-Shielded Irradia-                  Commission irradiator


fission product power as 0.487 from U235, 0.069 from U238, and 0.443 from U239. The fractional
tors Because of Inadequate                licensees and vendors


fission product power input to MELCOR was 0.647 from U235, 0.0425 from U238, and 0.31 from Pu239. The other code inputs assumed all fission product power came from U235.
Maintenance and Training


Attachment
96-34          Hydrogen Gas Ignition          05/31/96    All holders of OLs or CPs


2* IN 96-39 July 5, 1996 Table 2. Relative Importance
during Closure Welding                    for nuclear power reactors


of Options 7200 Seconds (2 hours) After Reactor Shutdown Complete Set For: Options as InDut and Varied Decay Heat in MWT MELCOR MELCOR assumptions (see Table 1) 20.70______________________________________________________________________________
of a VSC-24 Multi-Assembly
Increase R from .526 to .6 21.03 Increase Si from .713 to 1.347 21.13 Operation


time from 1.6 years to 3 years 21.40 Vendor fissile isotopes 21.12 Vendor heavy element equation 21.86 Vendor code Vendor G-factor equation 22.15-__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_ _ _ _ _ _ _ _ _ _ _ _ANS 5.1 G-factor and heavy element eqs. 21.12 No actinides
Sealed Basket


18.65 Gmax rather than equation 19.44 Infinite operation
96-33          Erroneous Data From            05/24/96    All material and fuel cycle


20.53 RELAP 1  All fission from U235 22.02 ----------------
Defective Thermocouple                    licensees that monitor tem- Results in a Fire                          perature with thermocouples
RELAP 2  Add actinides


with R=1 26.13 RELAP 3  Remove actinides
96-32          Implementation of 10 CFR      06/05/96    All holders of OLs or CPs


and G-factor 20.82 TRAC Include G-factor equation with Si-i 22.02 Note: This table illustrates
50.55a(g) (6)(ii)(A),                      for nuclear power reactors


the relative importance
"Augmented Examination


of the various options contained
of Reactor Vessel"
96-31          Cross-Tied Safety Injec-      05/22/96    All holders of OLs or CPs


in the 1979 ANS 5.1 standard.
tion Accumulators                          for pressurized water


Starting with the decay heat rate calculated
reactors


by MELCOR using the inputs listed in Table 1, the options were changed in sequence to those used in the vendor computer code. The options were then changed to those used in the RELAP 1 analyses, the RELAP 2 analyses, the RELAP 3 analyses, and the TRAC analyses.
96-30          Inaccuracy of Diagnostic      05/21/96    All holders of OLs or CPs


.i Figure 1 Peak Core Cladding Temperature
Equipment for Motor-                      for nuclear power reactors


1400.0 1200.0 2'CD E 0 1000.0 800.0 Attachment
Operated Butterfly Valves


3 IN 96-39 July 5, 1996- 12000.0 600.0 L 400.0 -0.0 4000.0 8000.0 Time (s)1400.0 Figure 2 Peak Core Cladding Temperature
96-29          Requirements in 10 CFR        05/20/96    All holders of OLs or CPs


Ug 1L&... A& IC C 4 var.qy ntIvat 04 1200.0 1-Infinite Operati All U235 Fissic G=Gmax Actinides
Part 21 for Reporting and                  for nuclear power reactors


with I£'0 a E 02 1000.0 800.0 ,n..ulLwu
Evaluating Software Errors


U)Y MIND ;.. I on in 1 R=1/600.0 400.0 L 0.C.........I D 4000.0 8000.0 12000.0 Time (s)
OL = Operating License
Attachment


4 IN 96-39 July 5, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
CP - Construction Permit


NOTICES Information
IN 96-39 July 5, 1996 This information notice requires no specific action or written response. If


Date of Notice No. Subject Issuance Issued to 96-38 96-37 96-36 96-35 96-34 Results of Steam Generator Tube Examinations
you have any questions about the information in this notice, please contact


Inaccurate
one of the technical contacts listed below or the appropriate Office of


Reactor Water Level Indication
Nuclear Reactor Regulation (NRR) project manager.


and Inad-vertent Draindown
OrfIoaw Stgned by Brin K.Grimes


During Shutdown Degradation
Brian K. Grimes, Acting Director


of Cooling Water Systems Due to Icing Failure of Safety Systems on Self-Shielded
Division of Reactor Program Management


Irradia-tors Because of Inadequate
Office of Nuclear Reactor Regulation


Maintenance
Technical contacts:                  W. L. Jensen, NRR


and Training Hydrogen Gas Ignition during Closure Welding of a VSC-24 Multi-Assembly
(301) 415-2856 Internet:wl jnrc.gov


Sealed Basket Erroneous
J. L. Birmingham, NRR


Data From Defective
(301) 415-2829 Internet:jlb4@nrc.gov


===Thermocouple===
Attachments:
Results in a Fire Implementation
              1. Table 1, 'Decay Heat Options Using ANS 5.1, 1979"
 
              2. Table 2, 'Relative Importance of Options 7200 Seconds
of 10 CFR 50.55a(g)
(6) (ii)(A),"Augmented
 
Examination
 
of Reactor Vessel" Cross-Tied
 
Safety Injec-tion Accumulators
 
Inaccuracy
 
of Diagnostic
 
Equipment
 
for Motor-Operated Butterfly
 
Valves Requirements
 
in 10 CFR Part 21 for Reporting
 
and Evaluating
 
Software Errors 06/21/96 06/18/96 06/12/96 06/11/96 05/31/96 05/24/96 06/05/96 05/22/96 05/21/96 05/20/96 All holders of OLs or CPs for pressurized


water reactors All pressurized
(2 hours) After Reactor Shutdown"
            3. Figure 1, "Peak Core Cladding Temperature Calculated by ORIGEN" and


water reactor facilities
Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1"
              4. List of Recently Issued NRC Information Notices


holding an operating
Reference:
              "American National Standard for Decay Heat Power in Light Water Reactors,"
            American Nuclear Society Standards Committee Working Group, ANS 5.1, Approved


license or a construction
August 29, 1979.


permit All holders of OLs or CPs for nuclear power reactors All U.S. Nuclear Regulatory
*See previous concurrence


Commission
Tech Editor reviewed and concurred on 03/19/96 DOCUMENT NAME:            96-39. IN


irradiator
To eceiw a copy of this document, hdMcata In the box: 'C' - Copy wlo


licensees
attechmentenclosure E' - Copy w/attachment/.nclosure W - No copy              """7 91 OFFICE        TECH CONTS                I      C:PECB:DRPM        I                    I      1II


and vendors All holders of OLs or CPs for nuclear power reactors All material and fuel cycle licensees
NAME          WLJensen*                        AEChaffee*                    m


that monitor tem-perature with thermocouples
lJLBirmingham*                                                    C ,v_,
                                                                          07/1 /96
1 DATE          04/02/96
              103/19/96                        105/16/96              [                    1                1__


All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for pressurized
IN 96-xx


water reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors 96-33 96-32 96-31 96-30 96-29 OL = Operating
July xx, 1996 This information notice requires no specific action or written response. If


License CP -Construction
you have any questions about the information in this notice, please contact


Permit
one of the technical contacts listed below or the appropriate Office of


IN 96-39 July 5, 1996 This information
Nuclear Reactor Regulation (NRR) project manager.


notice requires no specific action or written response.
Brian K. Grimes, Acting Director


If you have any questions
Division of Reactor Program Management


about the information
Office of Nuclear Reactor Regulation


in this notice, please contact one of the technical
Technical contacts:    W. L. Jensen, NRR


contacts listed below or the appropriate
(301) 415-2856 Internet:wlj~nrc.gov


Office of Nuclear Reactor Regulation (NRR) project manager.OrfIoaw Stgned by Brin K. Grimes Brian K. Grimes, Acting Director Division of Reactor Program Management
J. L. Birmingham, NRR


===Office of Nuclear Reactor Regulation===
(301) 415-2829 Internet:jlb4enrc.gov
Technical
 
contacts: W. L. Jensen, NRR (301) 415-2856 Internet:wl
 
jnrc.gov J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov


Attachments:
Attachments:
1. Table 1, 'Decay Heat Options Using ANS 5.1, 1979" 2. Table 2, 'Relative
1. Table 1, "Decay Heat Options Using ANS 5.1, 1979"
2. Table 2, "Relative Importance of Options 7200 Seconds


Importance
(2 hours) After Reactor Shutdown"
3. Figure 1, "Peak Core Cladding Temperature Calculated by ORIGEN" and


of Options 7200 Seconds (2 hours) After Reactor Shutdown" 3. Figure 1, "Peak Core Cladding Temperature
Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1"
5. List of Recently Issued NRC Information Notices


Calculated
Reference:
"American National Standard for Decay Heat Power in Light Water Reactors,"
American Nuclear Society Standards Committee Working Group ANS 5.1, Approved


by ORIGEN" and Figure 2, "Peak Core Cladding Temperature
August 29, 1979.


Calculated
*See previous concurrence


by ANS 5.1" 4. List of Recently Issued NRC Information
OFFICE    SASG:DSSA:NRR  SASG:DSSA:NRR    l D/DSSA:NRR


Notices Reference: "American
NAME    l WLJensen*      RCaruso*          l GMHolahan*
  DATE      04/02/96          04/04/96          04/30/96 OFFICE    TECHED:RPB    1 PECB:DRPM:NRR  _ C/PECB:DRPM:NRR  AD/DRPM:NRR


National Standard for Decay Heat Power in Light Water American Nuclear Society Standards
NAME      B. Calure*      JBirmingham*        AEChaffee*      BKGrimes


Committee
DATE      03/19/96      103/19/96          1  05/16/96    1      /  /96 OFFICIAL DOCUMENT NAME:    G:\JLB\DKAY4.IN


Working Group, ANS August 29, 1979.Reactors," 5.1, Approved*See previous concurrence
m,4A


Tech Editor reviewed and concurred
IN 96-xx


on 03/19/96 DOCUMENT NAME: 96-39. IN To eceiw a copy of this document, hdMcata In the box: 'C' -Copy wlo attechmentenclosure
June xx, 1996 This information notice requires no specific action or written response. If


E' -Copy w/attachment/.nclosure
you have any questions about the information in this notice, please contact


W -No copy"""7  OFFICE TECH CONTS I C:PECB:DRPM
one of the technical contacts listed below or the appropriate Office of


I I 1II NAME WLJensen*
Nuclear Reactor Regulation (NRR) project manager.
AEChaffee*
m lJLBirmingham*
C ,v_, DATE 04/02/96 05/16/96 07/1 /96 1 1 03/19/96 1 [ 1 1 __
IN 96-xx July xx, 1996 This information


notice requires no specific action or written response.
Brian K. Grimes, Acting Director


If you have any questions
Division of Reactor Program Management


about the information
Office of Nuclear Reactor Regulation


in this notice, please contact one of the technical
Technical contacts:      W. L. Jensen, NRR


contacts listed below or the appropriate
(301) 415-2856 Internet:wljenrc.gov


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Acting Director Division of Reactor Program Management
J. L. Birmingham, NRR


===Office of Nuclear Reactor Regulation===
(301) 415-2829 Internet:jlb4@nrc.gov
Technical
 
contacts: W. L. Jensen, NRR (301) 415-2856 Internet:wlj~nrc.gov
 
J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4enrc.gov


Attachments:
Attachments:
1. Table 1, "Decay Heat Options Using ANS 5.1, 1979" 2. Table 2, "Relative
1. Table 1, Decay Heat Options Using ANS 5.1, 1979."
 
2. Table 2, Relative Importance of Options 7200 Seconds
Importance
 
of Options 7200 Seconds (2 hours) After Reactor Shutdown" 3. Figure 1, "Peak Core Cladding Temperature
 
Calculated
 
by ORIGEN" and Figure 2, "Peak Core Cladding Temperature


Calculated
(2 hours) After Reactor Shutdown'
3. Figure 1, "Peak Core Cladding Temperature Calculated by ORIGEN."
4. Figure 2, 'Peak Core Cladding Temperature Calculated by ANS 5.1.'
5. List of Recently Issued NRC Information Notices


by ANS 5.1" 5. List of Recently Issued NRC Information
Reference:
  American National Standard for Decay Heat Power in Light Water Reactors,"
American Nuclear Society Standards Committee Working Group ANS 5.1, Approved


Notices Reference: "American
August 29, 1979.


National Standard for Decay Heat Power in Light Water Reactors," American Nuclear Society Standards
*Sep  nrpvious  concurrence


Committee
OFFICE    SASG:DSSA:NRR    SASG:DSSA:NRR      D/DSSA:NRR


Working Group ANS 5.1, Approved August 29, 1979.*See previous concurrence
NAME      WLJensen*          RCaruso*          GMHolahan*
    nATF      0a4/02/96          04/04/96          04/30/96
                                                          _.-
    OFFICE    TECHED:RPB        PECB:DRPM:NRR      C/PECB:DRPM:NRR  AD/DRPM:NRR


OFFICE SASG:DSSA:NRR
NAME      B. Calure*      JBirmingham*        AEChaffeeX        BKGrimes


SASG:DSSA:NRR
DATE      03/19/96    .    03/19/96    .        05//b/96    1  05/  /96
  )FFICIAL DOCUMENT NAME:     G:\JLb\UKAY4.IN


l D/DSSA:NRR
mtEA,


NAME l WLJensen*
K-,-
RCaruso* l GMHolahan*
                                                                            IN 96-xx
DATE 04/02/96 04/04/96 04/30/96 OFFICE TECHED:RPB


1 PECB:DRPM:NRR
May xx, 1996 This information notice requires no specific action or written response. If


_ C/PECB:DRPM:NRR
you have any questions about the information in this notice, please contact


AD/DRPM:NRR
one of the technical contacts listed below or the appropriate Office of


NAME B. Calure* JBirmingham*
Nuclear Reactor Regulation (NRR) project manager.
AEChaffee*
BKGrimes DATE 03/19/96 103/19/96
1 05/16/96 1 / /96 OFFICIAL DOCUMENT NAME: G:\JLB\DKAY4.IN


m,4A
Brian K. Grimes, Acting Director


IN 96-xx June xx, 1996 This information
Division of Reactor Program Management


notice requires no specific action or written response.
Office of Nuclear Reactor Regulation


If you have any questions
Technical contacts:          W. L. Jensen, NRR


about the information
(301) 415-2856 Internet:wl jnrc.gov


in this notice, please contact one of the technical
J. L. Birmingham, NRR


contacts listed below or the appropriate
(301) 415-2829 Internet:jlb4@nrc.gov
 
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Acting Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts: W. L. Jensen, NRR (301) 415-2856 Internet:wljenrc.gov
 
J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov


Attachments:
Attachments:
1. Table 1, Decay Heat Options Using ANS 5.1, 1979." 2. Table 2, Relative Importance
1. Table 1, "Decay Heat Options Using ANS 5.1, 1979."
2. Table 2, "Relative Importance of Options


of Options 7200 Seconds (2 hours) After Reactor Shutdown'3. Figure 1, "Peak Core Cladding Temperature
7200 Seconds (2 hours) After Reactor Shutdown'
3. Figure 1, *Peak Core Cladding Temperature Calculated by ORIGEN."
4. Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1."
5. List of Recently Issued NRC Information Notices


Calculated
Reference:
'American National Standard for Decay Heat Power in Light Water Reactors,"
American Nuclear Society Standards Committee Working Group ANS 5.1, Approved


by ORIGEN." 4. Figure 2, 'Peak Core Cladding Temperature
August 29, 1979.


Calculated
*Sge      ntrvinut concurrence


by ANS 5.1.'5. List of Recently Issued NRC Information
OFFICE        SASG:DSSA:NRR      SASG:DSSA:NRR        D/DSSA:NRR


Notices Reference:
NAME            WLJensen*        RCaruso*              GMHolahan*
American National Standard for Decay Heat Power in Light Water Reactors," American Nuclear Society Standards
  DATE          04/02/96            04/04/96              04/30/96        4T\1o


Committee
OFFICE


Working Group ANS 5.1, Approved August 29, 1979.*Sep nrpvious concurrence
NAME


OFFICE SASG:DSSA:NRR
TECHED:RPB


SASG:DSSA:NRR
B


D/DSSA:NRR
B. Calure*
                                  1 PECB:DRPM:NRR


NAME WLJensen*  
JBirmingham*         AE
RCaruso* GMHolahan*
nATF 0a4/02/96 04/04/96 04/30/96_.-OFFICE TECHED:RPB


PECB:DRPM:NRR
CAE A


C/PECB:DRPM:NRR
a fel


AD/DRPM:NRR
AD/DRPM:NRR


NAME B. Calure* JBirmingham*
BKGrimes
AEChaffeeX
 
BKGrimes DATE 03/19/96 .03/19/96 .05//b/96 1 05/ /96)FFICIAL DOCUMENT NAME: G:\JLb\UKAY4.IN
 
mtEA,
K-,-IN 96-xx May xx, 1996 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Acting Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts: W. L. Jensen, NRR (301) 415-2856 Internet:wl
 
jnrc.gov J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov
 
Attachments:
1. Table 1, "Decay Heat Options Using ANS 5.1, 1979." 2. Table 2, "Relative
 
Importance
 
of Options 7200 Seconds (2 hours) After Reactor Shutdown'3. Figure 1, *Peak Core Cladding Temperature
 
Calculated
 
by ORIGEN." 4. Figure 2, "Peak Core Cladding Temperature
 
Calculated
 
by ANS 5.1." 5. List of Recently Issued NRC Information
 
Notices Reference:
'American
 
National Standard for Decay Heat Power in Light Water Reactors," American Nuclear Society Standards
 
Committee
 
Working Group ANS 5.1, Approved August 29, 1979.*Sge ntrvinut concurrence
 
OFFICE SASG:DSSA:NRR


SASG:DSSA:NRR
DATE      l 03/19/96            03/19/96                05/14/96    ;    05/  /96
    - rr  ..r  .


D/DSSA:NRR
---      ..  -      -        -
                                          .~. - t  . gA        I


NAME WLJensen*
JFIHUAL WLUMNI KAM:              U: \-JLt1\UA1Uq. IN
RCaruso* GMHolahan*
DATE 4T\1o 04/02/96 04/04/96 04/30/96 OFFICE TECHED:RPB


1 PECB:DRPM:NRR
AV0en&


CAE A AD/DRPM:NRR
K>-
                                                                      IN 96-xx


NAME B B. Calure* JBirmingham*
May xx, 1996 This information notice requires no specific action or written response. If
AE a fel BKGrimes DATE l 03/19/96 03/19/96 0 5/14/96 ; 05/ /96-rr .. ---r ... --.~. -t -.gA I JFIHUAL WLUMNI KAM: U: \-JLt1\UA1Uq.


IN AV0en&
you have any questions about the information in this notice, please conta t
K>-IN 96-xx May xx, 1996 This information


notice requires no specific action or written response.
one of the technical contacts listed below or the appropriate Office of


If you have any questions
Nuclear Reactor Regulation (NRR) project manager.


about the information
Brian K. Grimes, Acting Dire or


in this notice, please conta t one of the technical
Division of Reactor Progra Management


contacts listed below or the appropriate
Office of Nuclear Reacto egulation


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Acting Dire or Division of Reactor Progra Management
Technical contacts:          W. L. Jensen, NRR


Office of Nuclear Reacto egulation Technical
(301) 415-2856 Internet:wlj@nrc.gov


contacts:
J. L. Birmingham, NRR
W. L. Jensen, NRR (301) 415-2856 Internet:wlj@nrc.gov


J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov
(301) 415-2829 Internet:jlb4@nrc.gov


Attachments:
Attachments:
1. Table 1, "Decay Heat Options Using ANS 5 , 1979." 2. Table 2, 'Relative
1. Table 1, "Decay Heat Options Using ANS 5 , 1979."
2. Table 2, 'Relative Importance of Option


Importance
7200 Seconds (2 hours) Aft Reactor Shutdown."
3. Figure 1, "Peak Core Cladding Temper ure Calculated by ORIGEN."
4. Figure 2, 'Peak Core Cladding Tegmp ature Calculated by ANS 5.1.'
5. List of Recently Issued NRC 19o( ation Notices


of Option 7200 Seconds (2 hours) Aft Reactor Shutdown." 3. Figure 1, "Peak Core Cladding Temper ure Calculated
Reference:
'American National Standard fg ecay Heat Power in Light Water Reactors,"
American Nuclear Society Sta d ds Committee Working Group ANS 5.1, Approved


by ORIGEN." 4. Figure 2, 'Peak Core Cladding Tegmp ature Calculated
August 29, 1979.


by ANS 5.1.'5. List of Recently Issued NRC 19o( ation Notices Reference:
*See previous concu            e
'American


National Standard fg ecay Heat Power in Light Water Reactors," American Nuclear Society Sta d ds Committee
OFFICE        SASG:DA:NRR      SASG:DSSA:NRR    D/DSSA:NRR


Working Group ANS 5.1, Approved August 29, 1979.*See previous concu e OFFICE SASG:DA:NRR
NAME          WLJfaen*        I RCaruso*          GMHolahan*
  DATE .1.   I04 ..  *2/96
                      .          1 04/04/96
                                        *           I 04/30/96 OFFICE f        ECHED:RPB      PECB:DRPM:NRR    C/PECB:DRPM:NRR  AD/DRPM:NRR


SASG:DSSA:NRR
NAME- / B. Calure*              JBirmingham*      AEChaffee        BKGrimes


D/DSSA:NRR
DATE / 03/19/96                03/19/96            05/  /96        05/  /96 Tl


NAME WLJfaen* I RCaruso* GMHolahan*
bewIr-luzT      l  u    s ...   -1    -1              %vV
DATE I 04 2/96 1 04/04/96 I 04/30/96.1. .. .*OFFICE f ECHED:RPB


PECB:DRPM:NRR
UFFIGJAL UDUMEIN NAME:           W \)Lb\UKAY4. 11        &W


C/PECB:DRPM:NRR
IN 96-xx


AD/DRPM:NRR
May xx, 1996 This information notice requires no specific action or written response. If


NAME- / B. Calure* JBirmingham*
you have any questions about the information in this notice, please contact
AEChaffee


BKGrimes DATE / 03/19/96 03/19/96 05/ /96 05/ /96 bew Tl Ir-luzT l u .s .. -1 -1 %vV UFFIGJAL UDUMEIN NAME: W \)Lb \UKAY4. 11 &W
one of the technical contacts listed below or the appropriate Office of


IN 96-xx May xx, 1996 This information
Nuclear Reactor Regulation (NRR) project manager.


notice requires no specific action or written response.
Brian K. Grimes, Acting Director


If you have any questions
Division of Reactor Program Management


about the information
Office of Nuclear Reactor Regulation


in this notice, please contact one of the technical
Technical contacts:    W. L. Jensen, NRR


contacts listed below or the appropriate
(301) 415-2856 Internet:wlj@nrc.gov


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Acting Director Division of Reactor Program Management
J. L. Birmingham, NRR


===Office of Nuclear Reactor Regulation===
(301) 415-2829 Internet:jlb4@nrc.gov
Technical
 
contacts: W. L. Jensen, NRR (301) 415-2856 Internet:wlj@nrc.gov
 
J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov


Attachments:
Attachments:
1. Table 1, "Decay Heat Options Using ANS 5.1, 1979." 2. Table 2, wRelative
1. Table 1, "Decay Heat Options Using ANS 5.1, 1979."
2. Table 2, wRelative Importance of Options 7200 Seconds (2 hours) After


Importance
Reactor Shutdown.'
                                                                        3
3. Figure 1, wPeak Core Cladding Temperature Calculated by ORIGEN.


of Options 7200 Seconds (2 hours) After Reactor Shutdown.'
4. Figure 2, uPeak Core Cladding Temperature Calculated by ANS 5.1."
3. Figure 1, wPeak Core Cladding Temperature
5. List of Recently Issued NRC Information Notices


Calculated
Reference:
"American National Standard for Decay Heat Power in Light Water Reactors,"
American Nuclear Society Standards Committee Working Group ANS 5.1, Approved


by ORIGEN.3 4. Figure 2, uPeak Core Cladding Temperature
August 29, 1979.


Calculated
*See Drevious concurrence                                    A


by ANS 5.1." 5. List of Recently Issued NRC Information
OFFICE    SASG:DSSA:NRR    SASG:DSSA:NRR        D1XaS.a


Notices Reference: "American
NAME      W Wensen        RCaruso      k  M      - ahan


National Standard for Decay Heat Power in Light Water Reactors," American Nuclear Society Standards
DATE      04/02/96          04/04/96              i4/ 0/96 OFFICE    TECHED:RPB      PECB:DRPM:NRR        C/PECB:DRPM:NRR  D/DRPM:NRR


Committee
NAME      B. Calure*      JBirmingham*        AEChaffee        DLCrutchfield


Working Group ANS 5.1, Approved August 29, 1979.A*See Drevious concurrence
DATE    103/19/96        03/19/96            1  04/  /96    j 04/ /96 UNILIAL*:-UL  r                          W..DtuF


OFFICE SASG:DSSA:NRR
in


SASG:DSSA:NRR
WFICIAL UUCUMMN    NAM:   U: XJLt$UKU>Y4. IrN


D1XaS.a NAME W W ensen RCaruso k M -ahan DATE 04/02/96 04/04/96 i4/ 0/96 OFFICE TECHED:RPB
IN 96-xx


PECB:DRPM:NRR
April xx, 1996 This information notice requires no specific action or written response. If


C/PECB:DRPM:NRR
you have any questions about the information in this notice, please contact


D/DRPM:NRR
one of the technical contacts listed below or the appropriate Office of


NAME B. Calure* JBirmingham*
Nuclear Reactor Regulation (NRR) project manager.
AEChaffee


===DLCrutchfield===
Denni    . Crutchfield, Director
DATE 1 03/19/96 03/19/96 1 04/ /96 j 04/ /96 UN ILIAL UL r *:- W..DtuF in WFICIAL UUCUMMN NAM: U: XJLt$UKU>Y4.


IrN
Division f Reactor Program Management


IN 96-xx April xx, 1996 This information
Office of      lear Reactor Regulation


notice requires no specific action or written response.
Technical contacts:    W. L. Jensen, NRR


If you have any questions
(301) 415-2856 Internet:wlj~nrc.gov


about the information
J. L. Birmingham, NRR


in this notice, please contact one of the technical
(301) 415-2829 Internet:jlb4@nrc.gov
 
contacts listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Denni .Crutchfield, Director Division f Reactor Program Management
 
===Office of lear Reactor Regulation===
Technical
 
contacts:
W. L. Jensen, NRR (301) 415-2856 Internet:wlj~nrc.gov
 
J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov


Attachments:
Attachments:
1. Table 1, Decay Heat Options Using ANS 5.1, 1979.0 2. Table 2, "Relative
1. Table 1, Decay Heat Options Using ANS 5.1, 1979.0
 
2. Table 2, "Relative Importance of Options 7200 Seconds (2 hours) After
Importance
 
of Options 7200 Seconds (2 hours) After Reactor Shutdown." 3. Figure 1, NPeak Core Cladding Temperature
 
Calculated
 
by ORIGEN." 4. Figure 2, "Peak Core Cladding Temperature
 
Calculated
 
by ANS 5.1." 5. List of Recently Issued NRC Information
 
Notices Reference:
American National Standard for Decay Heat Power in Light Water Reactors," American Nuclear Society Standards
 
Committee
 
Working Group ANS 5.1, Approved August 29, 1979.*See previous concurrence
 
OFFICE SASG:DSSA!RR
 
SASQ: PSSA:NRR D/DSSA:NRR
 
NAME jW Jenkeg( RCaJ & GMHolahan DATE I 04/2 /96 I 04/10/96 I 04/ /96 OFFICE TECHED:RPB
 
PECB:DhPM:NRR
 
C/PECB:DRPM:NRR
 
D/DRPM:NRR


NAME B. Calure* JBirmingham*
Reactor Shutdown."
AEChaffee
3. Figure 1, NPeak Core Cladding Temperature Calculated by ORIGEN."
4. Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1."
5. List of Recently Issued NRC Information Notices


===DLCrutchfield===
Reference:
DATE 03/19/96 03/19/96 04/ /96 04/ /96 FFICIAL DOCUMENT NAME: G:\JLB\UKAY4.IN
American National Standard for Decay Heat Power in Light Water Reactors,"
American Nuclear Society Standards Committee Working Group ANS 5.1, Approved


5. List of RecentlySosued
August 29, 1979.


NRC Information
*See previous concurrence


Notices Reference:
OFFICE    SASG:DSSA!RR    SASQ:PSSA:NRR      D/DSSA:NRR
1. "American


National Standard for Decay Heat Power in Light Water Reactors," American Nuclear Society Standards
NAME    jW Jenkeg(        RCaJ  &          GMHolahan


Committee
DATE    I04/2 /96      I04/10/96          I 04/    /96 OFFICE    TECHED:RPB      PECB:DhPM:NRR    C/PECB:DRPM:NRR    D/DRPM:NRR


Working Group ANS 5.1. Approved August 29. 1979.OFFICE SASG:DSSA:NRR
NAME      B. Calure*      JBirmingham*    AEChaffee          DLCrutchfield


SASG:DSSA:NRR
DATE      03/19/96        03/19/96          04/  /96          04/  /96 FFICIAL DOCUMENT NAME:   G:\JLB\UKAY4.IN


D/DSSA:NRR
5. List of RecentlySosued NRC Information Notices


NAME WLJensen RCaruso GMHolahan DATE 03/ /96 03/ /96 03/ /96 03/ /96 OFFICE TECHED:RPB
Reference:
1.    "American National Standard for Decay Heat Power in Light Water


PECB:DRPM:NRR
Reactors,"  American Nuclear Society Standards Committee Working Group


C/PECB:DRPM:NRR
ANS 5.1. Approved August 29. 1979.


D/DRPM:NRR
OFFICE    SASG:DSSA:NRR                  SASG:DSSA:NRR    D/DSSA:NRR


NAME JBirmingham
NAME     WLJensen                        RCaruso          GMHolahan


AEChaffee
DATE      03/  /96        03/  /96      03/  /96        03/  /96 OFFICE    TECHED:RPB      PECB:DRPM:NRR  C/PECB:DRPM:NRR  D/DRPM:NRR


===DLCrutchfield===
NAME                      JBirmingham    AEChaffee        DLCrutchfield
DATE 03//7/96 03/ /96 03/ /96 03/ /96 OFFICIAL DOCUMENT NAME: G:\JLB\DECAY


HT.JLB}}
DATE      03//7/96        03/  /96      03/  /96        03/  /96 OFFICIAL DOCUMENT NAME:    G:\JLB\DECAY HT.JLB}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 04:38, 24 November 2019

Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly
ML031060021
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 07/05/1996
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-96-039, NUDOCS 9606250199
Download: ML031060021 (15)
v • d • e


KY/

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 July 5, 1996 NRC INFORMATION NOTICE 96-39: ESTIMATES OF DECAY HEAT USING ANS 5.1 DECAY

HEAT STANDARD MAY VARY SIGNIFICANTLY

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice to alert addressees to the sensitivity of analytical results to input

parameters used with American Nuclear Society standard 5.1 on decay heat

(Reference). It is expected that recipients will review the information for

applicability to their facilities and consider actions, as appropriate, to

avoid similar problems. However, suggestions contained in this information

notice are not NRC requirements; therefore, no specific action or written

response is required.

Background

American Nuclear Society standard 5.1 (ANS 5.1 standard) for decay heat

generation in nuclear power plants provides a simplified means of estimating

nuclear fuel cooling requirements that can be readily programmed into computer

codes used to predict plant performance. The ANS 5.1 standard models the

energy release from the fission products of U-235, U-238, and Pu-239 using a

summation of exponential terms with empirical constants. Corrections are

provided to account for energy release from the decay of U-239 and Np-239, and

for the neutron activation of stable fission products. Although the empirical

constants are built into the standard, certain data inputs are left to the

discretion of the user. These options permit accounting for differences in

power history, initial fuel enrichment, and neutron flux level.

Description of Circumstances

During a review of decay heat estimates calculated using various codes for the

same plant, the staff found that the predicted decay heat varied considerably.

This was unexpected because the analyses were made using the 1979 ANS 5.1 standard and were to be used in best-estimate" thermal-hydraulic analyses.

The staff compared calculations of decay heat using MELCOR, TRAC, RELAP, and

a vendor code for a pressurized water reactor operating at 1933 megawatts

thermal (MWT). The staff made 3 calculations using RELAP but varied certain

inputs. These calculations appear as RELAP,, RELAP2, and RELAP in the

following tables. The decay heat estimates in MWT calculated ?or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

PD& IC ';cs 95-o3q 9(.oqoS

9606250199 1 A

O

0o 161b'~'k ussOAf

IN 96-39 July 5, 1996 after shutdown of the reactor using the various codes and allowable inputs

were as follows:

MELCOR - 20.70 MWT

Vendor code - 22.15 MWT

RELAP1 - 22.02 MWT

RELAP 2 - 26.13 MWT

RELAP3 - 20.82 MWT

TRAC - 22.02 MWT

ORIGEN - 20.90 MWT

It should be noted that the differences in predicted decay heat resulted from

the parameters selected for input and not from the codes themselves.

The last entry in the table was not calculated by the ANS 5.1 standard but was

calculated by the ORIGEN computer code. ORIGEN does not use empirical methods

to calculate decay heat but tracks the buildup and decay of the individual

fission products within the reactor core during operation and shutdown.

ORIGEN also includes the effect of element transmutation from neutron capture, both in fissile isotopes and fission products. Because ORIGEN is a rigorous

calculation of all decay heat inputs, it was used in the calculations for

decay heat in attached Figure 1 and is contrasted with attached Figure 2 using

decay heat internally calculated by RELAP to the ANS 5.1 standard.

Discussion

The staff found that the different decay heat estimates occurred because the

ANS 5.1 standard was not fully utilized in the selection of inputs. Attached

Table 1 shows the various inputs to the codes to estimate decay heat.

Attached Table 2 shows the effect of different assumptions on best estimate

calculations of decay heat 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after shutdown of the reactor.

The variation in peak cladding temperatures with various predictions of decay

heat may be seen by comparing the attached Figures 1 and 2. These figures are

plots of the peak cladding temperatures for a hypothetical beyond-design-basis

loss-of-feedwater event. For Figure 1, values of decay heat predicted by the

ORIGEN code were input directly into RELAP. Figure 2 is the same event with

the decay heat internally calculated by RELAP using the ANS 5.1 standard.

Input assumptions to the standard were those that produced the highest values

of decay heat denoted in Table 1 as RELAP2 . The difference in predicted peak

core cladding temperatures (approximately 250° K [6300 F]) demonstrates the

importance of carefully selecting required input parameters when using ANS 5.1 because analytical results may be significantly affected. Depending on the

input parameters selected the results may be conservative or nonconservative.

IN 96-39 July 5, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wljenrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, 'Decay Heat Options Using ANS 5.1, 1979"

2. Table 2, "Relative Importance of Options 7200 Seconds

(2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After Reactor Shutdown"

3. Figure 1, "Peak Core' Cladding Temperature Calculated by ORIGEN" and

Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1"

4. List of Recently Issued NRC Information Notices

Reference:

"American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group, ANS 5.1, Approved

August 29, 1979.

/, III CT,09we,

44A0ei

Attachment 1 IN 96-39 July 5, 1996 Table 1. Decay Heat Options Using ANS 5.1, 1979 l I l l Power l Fissile

Codes Actinides R-Factor G-Factor Si History Elements

Vendor Yes 0.6 Not ANS 1.347 3 Yrs. 3 RELAP1 No NA MAX NA Infinite All

_ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _U 23 5 RELAP 2 Yes 1.0 MAX NA Infinite All

_ _ _ _ _ _ _ _ _ _ _ __ __ _ ___ ___U 235 RELAP3 No NA No NA Infinite All

_ _ __ __ _ _ _ _ __ __ _ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _U 23 5 MELCOR Yes 0.526 Yes 0.713 1.6 Yrs. 3 TRAC No NA Yes 1.0 Infinite All

__ _ _ __ _ __ _ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __I_ U235 Notes:

Actinides: Neutron capture by U238 produces U239 which decays into Np239 which also decays, adding to the total decay heat. Not all the above code inputs included actinide decay.

R-factor: The actinide production multiplier. The standard states that the value of R shall

be supplied and justified by the user.

G-factor: A decay heat multiplier to account for the effect of neutron capture in fission

products. The standard provides the option of using a maximum value table for the G-factor or

a best estimate equation for the first 10,000 seconds.

Si: Fissions per initial fissile atom. Si is a multiplier applied to the G-factor equation.

Power History: Length of full-power operation before shutdown.

Fissile Elements: The standard permits decay power to be fractionally attributed to the

fission products of 3 fissile isotopes U235, U238, and Pu239. The vendor input attributed the

fractional fission product power as 0.487 from U235, 0.069 from U238, and 0.443 from U239. The

fractional fission product power input to MELCOR was 0.647 from U235, 0.0425 from U238, and

0.31 from Pu239. The other code inputs assumed all fission product power came from U235.

Attachment 2

  • IN 96-39 July 5, 1996 Table 2. Relative Importance of Options

7200 Seconds (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After Reactor Shutdown

Complete Set For: Options as InDut and Varied Decay Heat in MWT

MELCOR MELCOR assumptions (see Table 1) 20.70

______________________________________________________________________________

Increase R from .526 to .6 21.03 Increase Si from .713 to 1.347 21.13 Operation time from 1.6 years to 3 years 21.40

Vendor fissile isotopes 21.12 Vendor heavy element equation 21.86 Vendor code Vendor G-factor equation 22.15

_______________________________________ _________________________ - ____________

ANS 5.1 G-factor and heavy element eqs. 21.12 No actinides 18.65 Gmax rather than equation 19.44 Infinite operation 20.53 RELAP1 All fission from U235 22.02 ----------------

RELAP2 Add actinides with R=1 26.13 RELAP 3 Remove actinides and G-factor 20.82 TRAC Include G-factor equation with Si-i 22.02 Note: This table illustrates the relative importance of the various options contained in the

1979 ANS 5.1 standard. Starting with the decay heat rate calculated by MELCOR using the inputs

listed in Table 1, the options were changed in sequence to those used in the vendor computer

code. The options were then changed to those used in the RELAP1 analyses, the RELAP2 analyses, the RELAP3 analyses, and the TRAC analyses.

Attachment 3

.i IN 96-39 Figure 1 Peak Core Cladding Temperature July 5, 1996

1400.0 - 1200.0

2' 1000.0

CD

E

0 800.0

600.0 L

400.0 -

0.0 4000.0 8000.0 12000.0

Time (s)

Figure 2 Peak Core Cladding Temperature

1400.0

Ug

1L&... A& IC C 4 var.qy ntIvat 04,n..ulLwu U)Y MIND ;.. I

Infinite Operati on

1200.0 1- All U235 Fissicin 1 G=Gmax

Actinides with IR=1/

£' 1000.0

0

a

E

02 800.0

600.0

400.0 L . . . . . . . . .I

0.CD 4000.0 8000.0 12000.0

Time (s)

Attachment 4 IN 96-39 July 5, 1996 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

96-38 Results of Steam Generator 06/21/96 All holders of OLs or CPs

Tube Examinations for pressurized water

reactors

96-37 Inaccurate Reactor Water 06/18/96 All pressurized water

Level Indication and Inad- reactor facilities holding

vertent Draindown During an operating license or a

Shutdown construction permit

96-36 Degradation of Cooling 06/12/96 All holders of OLs or CPs

Water Systems Due to Icing for nuclear power reactors

96-35 Failure of Safety Systems 06/11/96 All U.S. Nuclear Regulatory

on Self-Shielded Irradia- Commission irradiator

tors Because of Inadequate licensees and vendors

Maintenance and Training

96-34 Hydrogen Gas Ignition 05/31/96 All holders of OLs or CPs

during Closure Welding for nuclear power reactors

of a VSC-24 Multi-Assembly

Sealed Basket

96-33 Erroneous Data From 05/24/96 All material and fuel cycle

Defective Thermocouple licensees that monitor tem- Results in a Fire perature with thermocouples

96-32 Implementation of 10 CFR 06/05/96 All holders of OLs or CPs

50.55a(g) (6)(ii)(A), for nuclear power reactors

"Augmented Examination

of Reactor Vessel"

96-31 Cross-Tied Safety Injec- 05/22/96 All holders of OLs or CPs

tion Accumulators for pressurized water

reactors

96-30 Inaccuracy of Diagnostic 05/21/96 All holders of OLs or CPs

Equipment for Motor- for nuclear power reactors

Operated Butterfly Valves

96-29 Requirements in 10 CFR 05/20/96 All holders of OLs or CPs

Part 21 for Reporting and for nuclear power reactors

Evaluating Software Errors

OL = Operating License

CP - Construction Permit

IN 96-39 July 5, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

OrfIoaw Stgned by Brin K.Grimes

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wl jnrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, 'Decay Heat Options Using ANS 5.1, 1979"

2. Table 2, 'Relative Importance of Options 7200 Seconds

(2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After Reactor Shutdown"

3. Figure 1, "Peak Core Cladding Temperature Calculated by ORIGEN" and

Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1"

4. List of Recently Issued NRC Information Notices

Reference:

"American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group, ANS 5.1, Approved

August 29, 1979.

  • See previous concurrence

Tech Editor reviewed and concurred on 03/19/96 DOCUMENT NAME: 96-39. IN

To eceiw a copy of this document, hdMcata In the box: 'C' - Copy wlo

attechmentenclosure E' - Copy w/attachment/.nclosure W - No copy """7 91 OFFICE TECH CONTS I C:PECB:DRPM I I 1II

NAME WLJensen* AEChaffee* m

lJLBirmingham* C ,v_,

07/1 /96

1 DATE 04/02/96

103/19/96 105/16/96 [ 1 1__

IN 96-xx

July xx, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wlj~nrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4enrc.gov

Attachments:

1. Table 1, "Decay Heat Options Using ANS 5.1, 1979"

2. Table 2, "Relative Importance of Options 7200 Seconds

(2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After Reactor Shutdown"

3. Figure 1, "Peak Core Cladding Temperature Calculated by ORIGEN" and

Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1"

5. List of Recently Issued NRC Information Notices

Reference:

"American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group ANS 5.1, Approved

August 29, 1979.

  • See previous concurrence

OFFICE SASG:DSSA:NRR SASG:DSSA:NRR l D/DSSA:NRR

NAME l WLJensen* RCaruso* l GMHolahan*

DATE 04/02/96 04/04/96 04/30/96 OFFICE TECHED:RPB 1 PECB:DRPM:NRR _ C/PECB:DRPM:NRR AD/DRPM:NRR

NAME B. Calure* JBirmingham* AEChaffee* BKGrimes

DATE 03/19/96 103/19/96 1 05/16/96 1 / /96 OFFICIAL DOCUMENT NAME: G:\JLB\DKAY4.IN

m,4A

IN 96-xx

June xx, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wljenrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, Decay Heat Options Using ANS 5.1, 1979."

2. Table 2, Relative Importance of Options 7200 Seconds

(2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After Reactor Shutdown'

3. Figure 1, "Peak Core Cladding Temperature Calculated by ORIGEN."

4. Figure 2, 'Peak Core Cladding Temperature Calculated by ANS 5.1.'

5. List of Recently Issued NRC Information Notices

Reference:

American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group ANS 5.1, Approved

August 29, 1979.

  • Sep nrpvious concurrence

OFFICE SASG:DSSA:NRR SASG:DSSA:NRR D/DSSA:NRR

NAME WLJensen* RCaruso* GMHolahan*

nATF 0a4/02/96 04/04/96 04/30/96

_.-

OFFICE TECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR AD/DRPM:NRR

NAME B. Calure* JBirmingham* AEChaffeeX BKGrimes

DATE 03/19/96 . 03/19/96 . 05//b/96 1 05/ /96

)FFICIAL DOCUMENT NAME: G:\JLb\UKAY4.IN

mtEA,

K-,-

IN 96-xx

May xx, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wl jnrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, "Decay Heat Options Using ANS 5.1, 1979."

2. Table 2, "Relative Importance of Options

7200 Seconds (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After Reactor Shutdown'

3. Figure 1, *Peak Core Cladding Temperature Calculated by ORIGEN."

4. Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1."

5. List of Recently Issued NRC Information Notices

Reference:

'American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group ANS 5.1, Approved

August 29, 1979.

  • Sge ntrvinut concurrence

OFFICE SASG:DSSA:NRR SASG:DSSA:NRR D/DSSA:NRR

NAME WLJensen* RCaruso* GMHolahan*

DATE 04/02/96 04/04/96 04/30/96 4T\1o

OFFICE

NAME

TECHED:RPB

B

B. Calure*

1 PECB:DRPM:NRR

JBirmingham* AE

CAE A

a fel

AD/DRPM:NRR

BKGrimes

DATE l 03/19/96 03/19/96 05/14/96  ; 05/ /96

- rr ..r .

--- .. - - -

.~. - t . gA I

JFIHUAL WLUMNI KAM: U: \-JLt1\UA1Uq. IN

AV0en&

K>-

IN 96-xx

May xx, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please conta t

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Acting Dire or

Division of Reactor Progra Management

Office of Nuclear Reacto egulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wlj@nrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, "Decay Heat Options Using ANS 5 , 1979."

2. Table 2, 'Relative Importance of Option

7200 Seconds (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) Aft Reactor Shutdown."

3. Figure 1, "Peak Core Cladding Temper ure Calculated by ORIGEN."

4. Figure 2, 'Peak Core Cladding Tegmp ature Calculated by ANS 5.1.'

5. List of Recently Issued NRC 19o( ation Notices

Reference:

'American National Standard fg ecay Heat Power in Light Water Reactors,"

American Nuclear Society Sta d ds Committee Working Group ANS 5.1, Approved

August 29, 1979.

  • See previous concu e

OFFICE SASG:DA:NRR SASG:DSSA:NRR D/DSSA:NRR

NAME WLJfaen* I RCaruso* GMHolahan*

DATE .1. I04 .. *2/96

. 1 04/04/96

  • I 04/30/96 OFFICE f ECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR AD/DRPM:NRR

NAME- / B. Calure* JBirmingham* AEChaffee BKGrimes

DATE / 03/19/96 03/19/96 05/ /96 05/ /96 Tl

bewIr-luzT l u s ... -1 -1 %vV

UFFIGJAL UDUMEIN NAME: W \)Lb\UKAY4. 11 &W

IN 96-xx

May xx, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wlj@nrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, "Decay Heat Options Using ANS 5.1, 1979."

2. Table 2, wRelative Importance of Options 7200 Seconds (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After

Reactor Shutdown.'

3

3. Figure 1, wPeak Core Cladding Temperature Calculated by ORIGEN.

4. Figure 2, uPeak Core Cladding Temperature Calculated by ANS 5.1."

5. List of Recently Issued NRC Information Notices

Reference:

"American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group ANS 5.1, Approved

August 29, 1979.

  • See Drevious concurrence A

OFFICE SASG:DSSA:NRR SASG:DSSA:NRR D1XaS.a

NAME W Wensen RCaruso k M - ahan

DATE 04/02/96 04/04/96 i4/ 0/96 OFFICE TECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR D/DRPM:NRR

NAME B. Calure* JBirmingham* AEChaffee DLCrutchfield

DATE 103/19/96 03/19/96 1 04/ /96 j 04/ /96 UNILIAL*:-UL r W..DtuF

in

WFICIAL UUCUMMN NAM: U: XJLt$UKU>Y4. IrN

IN 96-xx

April xx, 1996 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Denni . Crutchfield, Director

Division f Reactor Program Management

Office of lear Reactor Regulation

Technical contacts: W. L. Jensen, NRR

(301) 415-2856 Internet:wlj~nrc.gov

J. L. Birmingham, NRR

(301) 415-2829 Internet:jlb4@nrc.gov

Attachments:

1. Table 1, Decay Heat Options Using ANS 5.1, 1979.0

2. Table 2, "Relative Importance of Options 7200 Seconds (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) After

Reactor Shutdown."

3. Figure 1, NPeak Core Cladding Temperature Calculated by ORIGEN."

4. Figure 2, "Peak Core Cladding Temperature Calculated by ANS 5.1."

5. List of Recently Issued NRC Information Notices

Reference:

American National Standard for Decay Heat Power in Light Water Reactors,"

American Nuclear Society Standards Committee Working Group ANS 5.1, Approved

August 29, 1979.

  • See previous concurrence

OFFICE SASG:DSSA!RR SASQ:PSSA:NRR D/DSSA:NRR

NAME jW Jenkeg( RCaJ & GMHolahan

DATE I04/2 /96 I04/10/96 I 04/ /96 OFFICE TECHED:RPB PECB:DhPM:NRR C/PECB:DRPM:NRR D/DRPM:NRR

NAME B. Calure* JBirmingham* AEChaffee DLCrutchfield

DATE 03/19/96 03/19/96 04/ /96 04/ /96 FFICIAL DOCUMENT NAME: G:\JLB\UKAY4.IN

5. List of RecentlySosued NRC Information Notices

Reference:

1. "American National Standard for Decay Heat Power in Light Water

Reactors," American Nuclear Society Standards Committee Working Group

ANS 5.1. Approved August 29. 1979.

OFFICE SASG:DSSA:NRR SASG:DSSA:NRR D/DSSA:NRR

NAME WLJensen RCaruso GMHolahan

DATE 03/ /96 03/ /96 03/ /96 03/ /96 OFFICE TECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR D/DRPM:NRR

NAME JBirmingham AEChaffee DLCrutchfield

DATE 03//7/96 03/ /96 03/ /96 03/ /96 OFFICIAL DOCUMENT NAME: G:\JLB\DECAY HT.JLB


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