NL-17-1505, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

ML17304B382
Person / Time
Site:	Vogtle
Issue date:	10/31/2017
From:	Wheat J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-1505, TAC MF3770, TAC MF3771
Download: ML17304B382 (5)

Text

.t. Southern Nuclear Justin T. Wheat Nuclear Licensing Manager 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 5998 tel 205 992 7601 fax OCT 3 1 2011 jtwheat@southcmco.com Docket Nos.: 50-424 NL-17-1505 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant- Units 1 and 2 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

References:

1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 ADAMS Accession Number ML12053A340.

2. NRC Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)

Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015.

3. NEI Letter, transmits EPRI 3002009564 for NRC endorsement, dated January 31, 2017, ADAMS Accession Number ML17031A171.

4. EPRI 3002009564, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, dated January 2017.

5. NRC Letter, provides endorsement of EPRI 3002009564, dated February 8, 2017, ADAMS Accession Number ML17034A408.

6. Southern Company, Letter NL-14-0344 to the U.S. Nuclear Regulatory Commission, Vogtle Electric Generating Plant- Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites, dated March 31, 2014, ADAMS Accession Number ML14092A019.

7. NRC Letter, Vogtle Electric Generating Plant, Units 1 and 2- Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 of The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (Tac Nos.

MF3770 And MF3771 ), April 20, 2015, ADAMS Accession Number ML15054A296.

U.S. Nuclear Regulatory Commission NL-17-1505 Page 2 Ladies and Gentlemen:

On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f) (Reference 1) to all power reactor licensees. By letter dated October 27, 2015 (Reference 2), the NRC transmitted final seismic information request tables which identified that Vogtle Electric Generating Plant- Units 1 and 2 (Plant Vogtle) is to conduct a limited scope Spent Fuel Pool Evaluation. By Reference 3, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation (EPRI 3002009564) (Reference 4) for NRC review and endorsement. NRC endorsement was provided by Reference 5.

EPRI 3002009564 provides criteria for evaluating the seismic adequacy of a spent fuel pool (SFP) to the reevaluated ground motion response spectrum (GMRS) hazard levels. Section 4.3 of EPRI 3002009564 lists the parameters to be verified to confirm that the results of the report are applicable to Plant Vogtle, and that the Plant Vogtle SFP is seismically adequate in accordance with NTTF 2.1 Seismic evaluation criteria.

The enclosure to this letter provides the data for Plant Vogtle Units 1 and 2 that confirms applicability of the EPRI 3002009564 criteria and confirms that the SFP is seismically adequate in accordance with NTTF 2.1 Seismic evaluation criteria.

This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments. If you have any questions, please contact Matt Euten at 205.992.7673.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 31st day of October 2017.

Respectfully submitted, S9~-r.c.J2:s};-

Justin T. Wheat Nuclear Licensing Manager Southern Nuclear Operating Company JTW/MREIGLS

Enclosure:

Site-Specific Spent Fuel Pool Criteria for Vogtle Electric Generating Plant-Units 1 and 2 cc: Regional Administrator, Region II NRR Project Manager- Vogtle 1 & 2 Senior Resident Inspector- Vogtle 1 & 2 State of Georgia Environmental Protection Division RType: CVC7000

Vogtle Electric Generating Plant- Units 1 and 2 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Enclosure Site-Specific Spent Fuel Pool Criteria for Vogtle Electric Generating Plant- Units 1 and 2

Enclosure to NL-17-1505 Site-Specific Spent Fuel Pool Criteria for Vogtle Electric Generating Plant- Units 1 and 2 Introduction The 50.54(f) letter requested that, in conjunction with the response to NTTF Recommendation 2.1, a seismic evaluation be made of the SFP. More specifically, plants were asked to consider "all seismically induced failures that can lead to draining of the SFP." Such an evaluation would be needed for any plant in which the ground motion response spectrum (GMRS) exceeds the safe shutdown earthquake (SSE) in the 1 to 10 Hz frequency range. The staff confirmed through References 2 and 7 that the GMRS exceeds the SSE and concluded that a SFP evaluation is merited for the Vogtle Electric Generating Plant Units 1 and 2 (Plant Vogtle). By letter dated February 8, 2017 (Reference 5) the staff determined that EPRI 3002009564 was an acceptable approach for performing SFP evaluations considering the GMRS hazard levels.

The table below lists the criteria from Section 4.3 of EPRI 3002009564 along with data for Plant Vogtle that confirms applicability of the EPRI 3002009564 criteria and confirms that the SFP is seismically adequate in accordance with NTTF 2.1 Seismic evaluation criteria.

SFP Criteria from EPRI 3002009564 Site-Specific Data Site Parameters

1. The site-specific GMRS should be The Plant Vogtle GMRS peak spectral acceleration the same as that submitted to the in Reference 6 as accepted by the NRC in NRC between March 2014 and July Reference 7 is 1.09g. Therefore. this criterion is 2015, which the NRC has found met for Plant Vogtle Units 1 and 2.

acceptable for responding to the NRC 50.54(f) letter (Reference 7).

Structural Parameters

2. Site-specific calculations, performed Site-specific calculations, performed in accordance in accordance with Section 4.1 of with Section 4.1 of EPRI 3002009564, EPRI 3002009564 should demonstrate that the limiting SFP HCLPF is 0.681 g demonstrate that the limiting SFP PGA, which exceeds the GMRS 0.436g PGA.

HCLPF is greater than the site- Therefore 1 this criterion is met for Plant Vogtle specific GMRS in the frequency Units 1 and 2.

range of interest (e.g., 10-20Hz).

3. The SFP structure should be The SFP structure is included in Plant Vogtle Units included in the Civil Inspection 1 and 2 Civil Inspection Program in accordance Program performed in accordance with 10 CFR 50.65. In accordance with NMP-ES-with Maintenance Rule. 021 V1 0.0, the Fuel Handling Building (including the SFP structure) is within scope of the inspection program. Therefore~ this criterion is met for Plant Vogtle Units 1 and 2.

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Enclosure to NL-17-1505 Site-Specific Spent Fuel Pool Criteria for Vogtle Electric Generating Plant- Units 1 and 2 Non-Structural Parameters

4. To confirm applicability of the piping The maximum depth of piping below the water evaluation in Section 4.2 of EPRI surface is less than 6 ft, as shown in SFP liner 3002009564, piping attached to the plate and piping isometric drawings (1X4DB130, SFP should have penetrations no 2X4DB130, AX2009J03 and AX2D09J004).

more than 6 ft below water surface. Therefore 1 this criterion is met for Plant Vogtle Units 1 and 2.

5. To confirm ductile behavior under The SFP gate and hinge components are increased seismic demands, SFP constructed from a stainless-steel alloy, as shown gates should be constructed from in gate design drawings (AX2AH13-00030, either aluminum or stainless steel AX2AH 13-00031 , AX2AH 13-00032 and AX2AH 13-alloys. 00033). Therefore 1 this criterion is met for Plant Vogtle Units 1 and 2.

6. Anti-siphoning devices should be The SFP has two 10-inch heat exchanger return installed on any piping that could lines that extend down to 6 feet above the fuel lead to siphoning water from the assembly. However, these lines have anti-SFP. In addition, for any cases siphoning holes located 2' below the low water where active anti-siphoning devices level per piping isometric drawings 1X4DB130 and are attached to 2-inch or smaller 2X4DB130.

piping and have extremely large As described, anti-siphoning devices are installed, extended operators, the valves therefore this criterion is met for Plant Vogtle.

should be walked down to confirm adequate lateral support.

There are no .lines with active anti-siphoning devices.

Therefore 1 this criterion is met for Plant Vogtle Units 1 and 2.

7. To confirm applicability of the The Plant Vogtle Units 1 and 2 SFP has a length of sloshing evaluation in Section 4.2 of 50.0 ft, a width of 34.0 ft, and a depth of 39.5 ft EPRI 3002009564, the maximum based on AX2009A005, AX2009A006, and SFP horizontal dimension (length or AX4DR023. Therefore I this criterion is met for width) should be less than 125 ft and Plant Vogtle Units 1 and 2.

the SFP depth should be greater than 36ft.

8. To confirm applicability of the The Plant Vogtle Units 1 and 2 SFP has a surface evaporation loss evaluation in area of 1703 ft 2 which is greater than 500 ft2 and Section 4.2 of EPRI 3002009564, the licensed reactor thermal power for Plant Vogtle the SFP surface area should be Units 1 and 2 is 3,625.6 MWt per unit which is less greater than 500 ft2 and the licensed than 4,000 MWt per unit. Therefore 1 this criterion reactor core thermal power should is met for Plant Vogtle Units 1 and 2.

be less than 4,000 MWt per unit.

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