HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses

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Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses
ML18047A730
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 02/16/2018
From: Hamilton T
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-18-020
Download: ML18047A730 (26)


Text

Tanya M. Hamilton Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 10 CFR 50.90 February 16, 2018 Serial: HNP-18-020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63

Subject:

Supplement to Response to Request for Additional Information Regarding License Amendment Request For Spent Fuel Storage Pool Criticality Analyses

Reference:

1. Duke Energy letter, Shearon Harris Nuclear Power Plant, Unit 1, Response to Request for Additional Information Regarding License Amendment Request For Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996; EPID L-2017-LLA-0303), dated January 18, 2018 (Agencywide Document Access and Management System (ADAMS) Accession Nos. ML18018B974, ML18018B975).

Ladies and Gentlemen:

By application dated June 28, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17193B165), Duke Energy Progress, LLC (Duke Energy),

submitted a license amendment request (LAR) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP), regarding spent fuel storage pool criticality analyses.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the LAR and determined that additional information was needed to complete their review. Duke Energy received requests for additional information (RAIs) from the NRC by letters dated December 20, 2017 (ADAMS Accession No. ML17339A566), and January 8, 2018 (ADAMS Accession No. ML18005A548).

Responses to these requests were provided in Reference 1.

Duke Energy has been requested to provide a nonproprietary version of Attachment 2 of the Reference 1 Enclosure. This nonproprietary copy is provided as Attachment 1 to this letter.

The content of this supplemental correspondence does not change the No Significant Hazards Consideration provided in Reference 1.

No regulatory commitments are contained in this letter.

In accordance with 10 CFR 50.91(b), HNP is providing the state of North Carolina with a copy of this supplemental correspondence.

U.S. Nuclear Regulatory Commission Page2 HNP-18-020 Should you have any questions regarding this submittal , please contact Jeffrey Robertson, HNP Regulatory Affairs Manager, at (919) 362-3137.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on February I(o , 2018.

Sincerely, Tanya M. Hamilton

Attachment:

1. Holtec International Report No. Hl-2167295, "Structural Evaluation of Harris Dream Insert,"

Revision 3 (Nonproprietary) cc: J. Zeiler, NRC Senior Resident Inspector, HNP W. L. Cox, 111, Section Chief N.C. DHSR M. Barillas, NRC Project Manager, HNP C. Haney, NRC Regional Administrator, Region II

U.S. Nuclear Regulatory Commission Page 2 HNP-18-020 Should you have any questions regarding this submittal, please contact Jeffrey Robertson, HNP Regulatory Affairs Manager, at (919) 362-3137.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on February , 2018.

Sincerely, Tanya M. Hamilton

Attachment:

1. Holtec International Report No. HI-2167295, Structural Evaluation of Harris Dream Insert, Revision 3 (Nonproprietary) cc: J. Zeiler, NRC Senior Resident Inspector, HNP W. L. Cox, III, Section Chief N.C. DHSR M. Barillas, NRC Project Manager, HNP C. Haney, NRC Regional Administrator, Region II

U.S. Nuclear Regulatory Commission HNP-18-020 SERIAL HNP-18-020 ATTACHMENT 1 HOLTEC INTERNATIONAL REPORT NO. HI-2167295, STRUCTURAL EVALUATION OF HARRIS DREAM INSERT, REVISION 3 (NONPROPRIETARY)

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 22 PAGES PLUS COVER

Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INT ER NATIONAL Fax (856) 797 - 0909 STRUCTURAL EVALUATION OF HARRIS DREAM INSERT FOR SHEARON HARRIS NUCLEAR PLANT Holtec Report No: Hl-2167295 Holtec Project No: 2635 Sponsoring Holtec Division: NPD Report Class: SAFETY RELATED

Project 2635 ID-2167295 TABLE OF CONTENTS TABLE OF CONTENTS ................................................................................................................. i

SUMMARY

OF REVISIONS ........................................................................................................ ii 1.0 PURPOSE AND SCOPE ..................................................................................................... I 2.0 METHODOLOGY .............................................................................................................. 1 3.0 ACCEPTANCE CRITERIA ................................................................................................ !

4.0 ASSUMPTIONS .................................................................................................................. 2 5.0 INPUT DAT A ...................................................................................................................... 3 6.0 COMPUTER CODES .......................................................................................................... 5 7.0 CALCULATIONS ............................................................................................................... 5 7.1 Normal Handling Condition .................................................................................... 5 7.2 Deflection of L-Shaped Cross Section ..................................................................... 8 7 .3 Seismic Conditions ................................................................................................ 10 7.4 BucklingAnalysis .................................................................................................. 12 7.5 Withdrawal Analysis .............................................................................................. 14 8.0 COMPUTER FILES .......................................................................................................... 15

9.0 CONCLUSION

S ................................................................................................................ 15

10.0 REFERENCES

.................................................................................................................. 15 APPENDIX A - APPROVED COMPUTER PROGRAM LIST (4 pages)

APPENDIX B - MATERIAL PROPERTY DATA FOR METAMIC (3 pages)

Page i

Project 2635 ID-2167295

SUMMARY

OF REVISIONS Revis ion 0: -

Revision 1:

Revision 2:

Revision 3:

Page ii

Project 2635 1 of 16 Hl-2167295 1.0 PURPOSE AND SCOPE The spent fuel racks in the Shearon Harris Nuclear Plant pools contain Boraflex, which over time tends to degrade and loses its neutron absorbing capability. To offset the loss of Boraflex, Duke Energy (Duke) plans to install DREAM inserts in the interstitial spaces between the stored fuel assemblies and the rack cell walls. The DREAM inserts are manufactured from aluminum and Metamic . The dimensions of the inserts are provided in [1].

The purpose of this calculation is to evaluate the structural integri ty of the inserts under normal o eratin i.e., installation and handli and accident condition i.e., seismic event loads.

2.0 METHODOLOGY a) b)

c) d)

e) 3.0 ACCEPTANCE CRITERIA The aluminum to alumi num weld at the top of the DREAM insert, where the support blocks are welded to the locati dowels , shall be ualified accordin to ASME Subsection NF stress limits 4.

Project 2635 2 of 16 Hl-2167295 4.0 ASSUMPTIONS The following assumptions are made in this report:

4.5.-

Project 2635 3 of 16 Hl-2167295 5.0 INPUT DATA

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9.0 CONCLUSION

S The DREAM i nserts are found to be structurally adequate to perform their i ntended design function under both norm al and seismic conditions.

10.0 RE FERENCES

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