ML20113F066

Safety Evaluation and Supporting Analysis Regarding the Algonquin Incremental Market Project Pipeline Near the Indian Point Energy Center, Units 2 and 3

ML20113F066
Person / Time
Site:	Indian Point
Issue date:	04/23/2020
From:	Jimi Yerokun Division of Reactor Safety I
To:	Vitale A Entergy Nuclear Generation Co
Yerokun J
References
Download: ML20113F066 (3)

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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 April 23, 2020 Mr. Anthony J. Vitale Site Vice President Entergy Nuclear Operations, Inc.

450 Broadway, Generation Support Building P.O. Box 249 Buchanan, NY 10511-0249

SUBJECT:

SAFETY EVALUATION AND SUPPORTING ANALYSIS REGARDING THE ALGONQUIN INCREMENTAL MARKET PROJECT PIPELINE NEAR THE INDIAN POINT ENERGY CENTER, UNITS 2 AND 3

Dear Mr. Vitale:

In February 2020, the NRC Office of Inspector General (OIG) issued a report (ML20056F095) on its inquiry pertaining to NRCs oversight of Entergys modification review, safety evaluation, and supporting hazard analysis associated with the Algonquin Incremental Market (AIM) natural gas pipeline near the Indian Point site. In response, the NRCs Executive Director for Operations tasked an Expert Evaluation Team comprised of NRC and external experts to review the findings in the OIG event inquiry and to document the results of its review in a report (ML20058E354).

On April 8, 2020, the Expert Evaluation Team issued its report (ML20100F635) identifying that Entergy used optimistic assumptions in analyzing the potential impacts to the IPEC site from a postulated rupture of the 42-inch AIM natural gas transmission pipeline. The team determined that, despite the optimistic assumptions adopted in analyzing the potential rupture of the 42-inch natural gas transmission pipeline, the Indian Point reactors remain safe, concluding specifically that a rupture of the pipeline is unlikely and, even if a rupture were to occur on the stretch of 42-inch pipeline near Indian Point, the nuclear power plant would remain protected.

Related to this issue, you have provided several analyses to the NRC. In August 2014, Entergy submitted the 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project Indian Point Nuclear Generating Unit Nos. 2 & 3 (ML14245A110). In April 2015, Entergy submitted the Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project Indian Point Nuclear Generating Unit Nos.

2 & 3 (ML15104A660).

In 2014, the NRC completed inspections of your 10 CFR 50.59 modification review and safety evaluation, and supporting hazard analysis, associated with the AIM natural gas pipeline. The NRC documented its inspection in November 2014 in inspection report 05000247/2014004 and 05000286/2014004 (ML14314A052), with additional information in a feeder report (ML14307B748) and an analysis summary (ML15070A086). As a result of the inspection activities, the NRC determined in 2014 that Entergy had appropriately concluded that the proposed pipeline does not introduce significant additional risk to safety-related structure,

A. Vitale 2 system, and components (SSCs) and SSCs important-to-safety at IPEC, Units 2 and 3; and, therefore, the change in the design bases external hazards analysis associated with the proposed pipeline did not require prior NRC review and approval.

In light of the issues identified by the NRC Expert Evaluation Team, the NRC requests that you update your evaluation and supporting analyses as necessary and assess the validity and materiality of the assumptions made in support of your conclusions regarding the consequences of a postulated rupture of the 42-inch gas pipeline. Please include the impact of updated information from the pipeline operator, Enbridge, as described in the Expert Evaluation Team report, regarding the time needed for operators to close valves in the event of a pipe rupture and the length of pipe that would need to be isolated. If an updated external hazards analysis is conducted, please reconcile any differences in the results.

The NRC plans to conduct an inspection of how you considered these issues with respect to your 10 CFR 50.59 evaluation. To support our inspection planning, please respond to this letter within 30 days indicating when you plan to complete your review.

This letter and your response will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

If you have any questions, please contact me as soon as possible.

Sincerely, X /RA/

Jimi T. Yerokun Signed by: Jimi T. Yerokun Jimi T. Yerokun, Director Division of Reactor Safety Docket Nos.05-247 and 05-286 License Nos. DPR-26 and DPR-64 cc: Distribution via ListServ

ML20113F066 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS

• via email RI/RC

• via email RI/DRS

• via email NAME MGray/*MG BKlukan/*BK JYerokun/*JTY DATE 04/22/2020 04/22/2020 04/23/2020