ML18249A080

From kanterella
Jump to navigation Jump to search

Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9431 and MF9430; EPID L-2016-LRC-0001)
ML18249A080
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 09/26/2018
From: Doug Broaddus
Special Projects and Process Branch
To: Stoddard D
Dominion Nuclear Connecticut
Wall S, NRR/DORL/LPLI, 415-2855
References
CAC MF9430, CAC MF9431, EPID L-2016-LRC-0001, GL-16-001, OMB 3150-0231
Download: ML18249A080 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 26, 2018 0MB Control No. 3150-0231 Mr. Daniel G. Stoddard Senior Vice President & Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Millstone Power Station Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNITS 2 AND 3 - CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS" (CAC NOS. MF9431 AND MF9430; EPID L-2016-LRC-0001)

Dear Mr. Stoddard:

On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials (NAMs) in wet storage systems for reactor fuel at power and non-power reactors.

The generic letter requested that licensees provide information to allow the NRC staff to verify continued compliance through effective monitoring to identify and mitigate any degradation or deformation of NAMs credited for criticality control in spent fuel pools (SFPs).

By letter dated November 1, 2016 (ADAMS Accession No. ML16312A064), as supplemented by letter dated November 22, 2017 (ADAMS Accession No. ML17338A057), Dominion Nuclear Connecticut, Inc. (the licensee), responded to GL 2016-01 for Millstone Power Station, Units 2 and 3 (MPS 2&3). In the licensee's response to GL 2016-01, the licensee stated that, for MPS2, the licensee credits Borated stainless steel (BSS) for criticality control and has an established NAM monitoring program. The NRC staff's review determined that the provided response sufficiently addressed the five areas of information described in Appendix A of GL 2016-01 for BSS. In particular, the described monitoring program for the BSS includes the following key features:

Visual inspection of rodlets.

Established processes to ensure that the licensee will take the appropriate corrective actions if any potentially non-conforming material is discovered.

A testing frequency not to exceed 10 years.

Acceptance criteria to ensure maintenance of the 5-percent subcriticality margin for the SFP.

The NRC staff found that the licensee intends to continue monitoring the condition of its NAMs as described in its response for MPS2.

In the licensee's response to GL 2016-01, as supplemented, the licensee stated that, for MPS3, the licensee credits Boral for criticality control and has an established NAM monitoring program.

The NRC staff's review determined that the provided response sufficiently addressed the five areas of information described in Appendix A of GL 2016-01 for Boral. In particular, the described monitoring program for the Boral includes the following key features:

Neutron attenuation testing of coupons.

Established processes to ensure that the licensee will take the appropriate corrective actions if any potentially non-conforming material is discovered.

A testing frequency not to exceed 5 years.

Acceptance criteria to ensure maintenance of the 5-percent subcriticality margin for the SFP.

The NRC staff found that the licensee intends to continue monitoring the condition of its NAMs as described in its response MPS3.

For MPS 2&3, the NRC staff's review determined that the information provided sufficiently addressed the five areas of information described in Appendix A to GL 2016-01. Based on the review of the information provided, the NRC staff concludes no further information is requested regarding GL 2016-01.

Docket Nos. 50-336 and 50-423 cc: Listserv Sincerely, Douglas A. Broaddus, Chief Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ML18249A080 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LPL 1/PM*

NAME SWall RGuzman DATE 9/25/18 9/17/18 OFFICE NRR/DMLR/MCCB/BC* NRR/DIRS/IRGB/BC*

NAME SBloom BPham DATE 9/25/18 9/17/18 NRR/DORL/LAiT PTalukdar 9/12/18 NRR/DSS/SNPB/BC*

Rlukes 9/17/18