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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT:        PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985)


==Dear Mr. Molden:==
==Dear Mr. Molden:==
By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
 
J. Molden -If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2.
Sincerely, Docket Nos. 50-282 and 50-306  
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
 
J. Molden                                   - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, Docket Nos. 50-282 and 50-306


==Enclosure:==
==Enclosure:==


Request for Additional Information cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION (RAI) PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review. This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response").
Request for Additional Information cc w/encl: Distribution via ListServ
Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading. A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber.
 
NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading. NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis.
REQUEST FOR ADDITIONAL INFORMATION (RAI)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review.
This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response").
Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading.
A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber. NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading.
NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis.
RAI-SRXB-2:
RAI-SRXB-2:
The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly).
The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly). Show that the selected design basis assembly remains limiting for Array G.
Show that the selected design basis assembly remains limiting for Array G. Enclosure
Enclosure
-2 The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh What is the basis for 4 percent 235U assumption? What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis?
 
                                                -2 RAI-SRX8-3:
The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh fuel.
: a. What is the basis for 4 percent 235U assumption?
: b. What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis?
RAI-SRX8-4 (Axial blankets):
RAI-SRX8-4 (Axial blankets):
Show that neglecting the hollow annular pellets in the blankets is always conservative.
Show that neglecting the hollow annular pellets in the blankets is always conservative.
RAI-SRX8-5 (Axial Provide the analysis results that support the selection of the axial burnup profiles used in analysis (e.g., k-effective results and corresponding "shape depletion RAI-SRX8-6 (Operation with control In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design cases and the "Rodded" RAI-SRX8-7 (Criticality code validation fission product The specifics of the referenced Turkey Point analysis differ from the PINGP analysis.
RAI-SRX8-5 (Axial profile):
Show the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance.
Provide the analysis results that support the selection of the axial burnup profiles used in the analysis (e.g., k-effective results and corresponding "shape depletion factors").
J. Molden -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
RAI-SRX8-6 (Operation with control rods):
Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306  
In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design basis" cases and the "Rodded" cases?
RAI-SRX8-7 (Criticality code validation fission product bias):
The specifics of the referenced Turkey Point analysis differ from the PINGP analysis. Show that the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance.
 
J. Molden                                   -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306


==Enclosure:==
==Enclosure:==


Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 RtF RidsNrrPMPrairielsland Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsNrrDorlDpr Resource TNakanishi, NRR KWood, NRR ADAMS Accession Number: ML12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlSRXB/BC(A)
PUBLIC           LPL3-1 RtF             RidsNrrDorlLpl3-1 Resource   RidsNrrDorlDpr Resource RidsNrrPMPrairielsland Resource         RidsNrrLABTully Resource     TNakanishi, NRR RidsAcrsAcnw_MailCTR Resource            RidsOgcRp Resource            KWood, NRR RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource ADAMS Accession Number: ML12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA               NRRlSRXB/BC(A)
BTully/SRohrer If I SMiranda 08/06/12 08/06/12 LPL3-1/PM NAME SFrankl TWengert DATE 08/07/12 08/07/12 OFFICIAL RECORD COpy}}
BTully/SRohrer IfI    SMiranda 08/06/12               08/06/12 LPL3-1/PM NAME         SFrankl             TWengert DATE         08/07/12           08/07/12 OFFICIAL RECORD COpy}}

Latest revision as of 01:15, 12 November 2019

Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes
ML12215A252
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/07/2012
From: Thomas Wengert
Plant Licensing Branch III
To: Molden J
Northern States Power Co
Wengert T
References
TAC ME6984, TAC ME6985
Download: ML12215A252 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985)

Dear Mr. Molden:

By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

J. Molden - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.

Sincerely, Docket Nos. 50-282 and 50-306

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION (RAI)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review.

This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response").

Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading.

A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber. NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading.

NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis.

RAI-SRXB-2:

The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly). Show that the selected design basis assembly remains limiting for Array G.

Enclosure

-2 RAI-SRX8-3:

The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh fuel.

a. What is the basis for 4 percent 235U assumption?
b. What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis?

RAI-SRX8-4 (Axial blankets):

Show that neglecting the hollow annular pellets in the blankets is always conservative.

RAI-SRX8-5 (Axial profile):

Provide the analysis results that support the selection of the axial burnup profiles used in the analysis (e.g., k-effective results and corresponding "shape depletion factors").

RAI-SRX8-6 (Operation with control rods):

In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design basis" cases and the "Rodded" cases?

RAI-SRX8-7 (Criticality code validation fission product bias):

The specifics of the referenced Turkey Point analysis differ from the PINGP analysis. Show that the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance.

J. Molden -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.

Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:

PUBLIC LPL3-1 RtF RidsNrrDorlLpl3-1 Resource RidsNrrDorlDpr Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource TNakanishi, NRR RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource KWood, NRR RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource ADAMS Accession Number: ML12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlSRXB/BC(A)

BTully/SRohrer IfI SMiranda 08/06/12 08/06/12 LPL3-1/PM NAME SFrankl TWengert DATE 08/07/12 08/07/12 OFFICIAL RECORD COpy

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