ML22202A430

Submittal of Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events

ML22202A430
Person / Time
Site:	Davis Besse
Issue date:	07/21/2022
From:	Tony Brown Energy Harbor Nuclear Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML22202A429	List: L-22-141, Enclosure D: Affidavit of Elliott Gayle ML22202A430 ML22202A433 ML22202A436 ML22202A437
References
L-22-141
Download: ML22202A430 (3)

Text

Withhold from Public Disclosure Under 10 CFR 2.390(a)(4)

Energy Harbor Nuclear Corp.

Davis-Besse Nuclear Power Station 5501 N. State Route 2 Oak Harbor, Ohio 43449

Terry J. Brown 419-321-767 6 Site Vice President, Davis-Besse Nuclear

July 21, 2022 L-22-141

ATTN: Document C ontrol D esk U.S. Nuclear Re gulatory Co mmission Washington, D C 2 0555- 0001

SUBJECT:

Davis-Besse Nuclear P ower S tation, Unit No. 1 Docket No. 50-3 46, License No. N PF-3 Submittal of Reanalysis f or P rotection A gainst Low T emperature Reactor C oolant System Overpressure Events

On January 28, 2011, the U.S. N uclear R egulatory C ommission (NRC) staff issued Amendment No. 282 (ADAMS A ccession No. M L103610148) t o Facility O perating License No. N PF-3 for t he Davis-Besse Nuclear P ower S tation, U nit No. 1 (DBNPS). This amendment approved changes t o the licensing basis for D BNPS ass ociated with the methodology use d for t he development of the reactor co olant system pressure-temperature limit c urves i n the units Pressure -Temperature Li mits R eport (PTLR). This amendment al so updated License Condition 2.C(3)(d) t o state that prior t o operation beyond 32 Effective Full Power Y ears (EFPY), [ FirstEnergy N uclear Operating Company]

FENOC shall provide to the NRC a reanalysis and pr oposed modifications, as necessary, to ensure continue d means of pr otection against low t emperature reactor syst em overpressure (LTOP) events.

In accordance with License Condition 2.C (3)(d), Energy H arbor N uclear C orp. hereby submits the enclosed reanalyses to ens ure continu ed means of protection against low temperature reactor co olant sys tem ov erpressure events f or t he Davis-Besse Nuclear Power St ation, Unit No. 1. No modifications h ave been conducted nor ar e any modifications sch eduled. Davis-Besse Nuclear P ower S tation, Un it No. 1 is estimated to be at 3 2 EFPY by October 10, 2022.

Enclosures B a nd E c ontain information to be w ithheld from pu blic di sclosure under 10 CFR 2.390(a)(4). Upon r emoval o f E nclosures B an d E, this letter i s uncontrolled.

Withhold from Public Disclosure Under 10 CFR 2.390(a)(4)

Davis-Besse Nuclear Power Station, Unit No. 1 L 141 Page 2

Enclosure A to this letter is affidavit A NP-2718-007 for Enclosure B prepared in accordance with 10 CFR 2.390 requesting that the confidential commercial information provided in Enclosure B be withheld from public disclosure.

Enclosure B contains Framatome Inc. document ANP-2718P-007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station. This document was prepared to summarize analyses c ompleted to extend DBNPS operation from 32 EFPY to 52 EFPY. This analysis was prepared using the methodologies listed in DBNPS Technical Specification 5. 6.4, as supplemented by NUREG-2193, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, dated August 2015, Section 3.0.3.2.14. The limit cu rves include explicit modeling of the reactor vessel inlet and outlet nozzle welds and the reference temperature shift for these materials based on the expected fluence at 52 EFPY.

Enclosure C contains Framatome Inc. document ANP-2718NP-007, which is the non-proprietary version of Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station.

Enclosure D to this letter is affidavit 32 -9271138- 001 pursuant to 10 CFR 2.390 requesting that the confidential commercial information provided in Enclosure E be withheld from public disclos ure.

Enclosure E contains Areva document 9271138- 001 Updated inputs to 52 EFPY P-T Operating Curves. This document generates inputs to the procedural Non-destructive testing (NDT) LTOP limits using the location corrected NDT/LTOP pressure-temperature curves and the uncertainties in pressure and temperature measurement.

This document identifies that the most l imiting aspect of the mat erial analyses prepared for the 52 EFPY PTLR curves is t he inlet nozzle (cold leg) forg ings where they meet the nozzle belt and the welds at the same location.

Enclosure F contains Areva document 32-9344638-000 Updated inputs to 52 EFPY P-T Operating Curves. This is the nonproprietary version of Enclosure E.

Enclosures B and E contain information to be withheld from public disclosure under 10 CFR 2.390(a)(4). Upon removal of Enclosures B and E, this letter is uncontrolled.

Withhold from Public Disclosure Under 10 CFR 2.390{a)(4)

Davis-Besse Nuclear Power Station, Unit No. 1 L-22-141 Page 3

During the spring of 2018, Energy Harbor removed the DBNPS reactor cavity dosimetry that was installed the spring of 2014 and discovered that the assumption used for fluence projects previously used for Enclosure B was incorrect. This was documented in the corrective action program. As a result, Framatome was contacted to perform a reconciliation of the new analysis for "Appendix G Pressure-Temperature limits for 52 EFPY" to account for increased reactor vessel fluence projections resulting from cycle 19 through 20 reactor cavity dosimetry analysis results. This is Enclosure G Framatome document 86-9344 713-000, "Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years. " The analyzed fluence for these locations will be reached at 43.5 EFPY based on fast leakage flux data for fuel cycles 19 and 20. The DBNPS Pressure and Temperature Limits Report is being revised to reflect 43.5 EFPY.

There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.

Sincerel~J n C(AT~ fb~ y -'3-ow...:>

Terry J. Brown O.:1, S. *-po/

Enclosures:

A. Affidavit Pursuant to 10 CFR 2.390 for ANP-2718-007 B. Framatome Inc. document ANP-2718P-007, "Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station." Proprietary C. Framatome Inc. document ANP-2718NP-007 "Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station." Nonproprietary D. Affidavit Pursuant to 10 CFR 2.390 for 32-9271138-001 E. Areva document - 32-9271138-001 "Updated inputs to 52 EFPY P-T Operating Curves." Proprietary F. Areva document 32-9344638-000 "Updated inputs to 52 EFPY P-T Operating Curves." Nonproprietary G. Framatome Inc. document 86-9344713-000, "Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years"

cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board