ML17304B153
| ML17304B153 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Saint Lucie, Watts Bar, Susquehanna, Turkey Point, Callaway  |
| Issue date: | 12/18/2017 |
| From: | Doug Broaddus Special Projects and Process Branch |
| To: | |
| Wall S, NRR/DORL/LSPB, 301-415-2855 | |
| References | |
| CAC MF9406, CAC MF9407, CAC MF9408, CAC MF9412, CAC MF9413, CAC MF9418, CAC MF9419, CAC MF9421, CAC MF9422, CAC MF9451, EPID L-2016-LRC-0001, OMB 3150-0231 | |
| Download: ML17304B153 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 18, 2017 0MB Control No. 3150-0231 To Those on the Attached List
SUBJECT:
GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS" -REQUEST FOR SUPPLEMENTAL INFORMATION (CAC NOS. MF9406, MF9407, MF9408, MF9412, MF9413, MF9418, MF9419, MF9421, MF9422, AND MF9451; EPID L-2016-LRC-0001)
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 (NAM) in wet storage systems for reactor fuel at power and non-power reactors.
The GL 2016-01 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 NAM credited for criticality control in spent fuel pools.
To facilitate each licensee's response, GL 2016-01 established four categories (Category 1, Category 2, Category 3, and Category 4). Categories 1, 2, and 3 were established to identify situations where a detailed response to the GL 2016-01 would not be required. The categorization criteria were generally based on if a licensee does not credit NAM for criticality control, or if a licensee has, or will soon have, an approved monitoring program for NAM in the plant technical specifications or as a license condition. A full description of the categories can be found in Enclosure 1. provides a list of GL 2016-01 responses by plant. To complete its review, the NRC staff requests that licensees provide the supplemental information requested in Enclosures 3 and 4. It is requested that you would provide a response by May 31, 2018.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, "Public inspections, exemptions, requests for withholding," a copy of this letter will be available electronically in the NRC Library, in the ADAMS Public Documents Collection from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
If you have any questions, please contact the Project Manager, Scott Wall, at 301-415-2855 or via e-mail at Scott.Wall@nrc.gov.
Docket Nos. 50-250, 50-251, 50-335, 50-387, 50-388, 50-389, 50-482, 50-483, 50-390, and 50-391
Enclosures:
- 1. List of GL 2016-01 Categories
- 3. Request for Supplemental Information -
Generic Boral Question 1
- 4. Request for Supplemental Information -
Generic Boral Question 2 cc: Listserv Sincerely, Douglas A Broaddus, Chief Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LETTER TO THOSE ON THE ATTACHED LIST DATED DECEMBER 18, 2017 Callaway Plant, Unit 1 Union Electric Company Docket No. 50-483 License No. NPF-30 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Union Electric Company Callaway Plant P.O. Box 620 Fulton, MO 65251 St. Lucie Plant. Units 1 and 2 Florida Power and Light Company Docket Nos. 50-335 and 50-389 License Nos. DPR-67 and NPF-16 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408 Susquehanna Steam Electric Station, Units 1 and 2 Susquehanna Nuclear, LLC Docket Nos. 50-387 and 50-388 License Nos. NPF-14 and NPF-22 Mr. Brad Berryman Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467 Turkey Point Nuclear Generating Units 3 and 4 Florida Power & Light Company Docket Nos. 50-250 and 50-251 License Nos. DPR-31 and DPR-41 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408 Watts Bar Nuclear Plant. Units 1 and 2 Tennessee Valley Authority Docket Nos. 50-390 and 50-391 License Nos. NPF-90 and NPF-96 Mr. Joseph. W. Shea Vice President, Nuclear Regulatory Affairs and Support Service Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 Wolf Creek Generating Station, Unit 1 Wolf Creek Nuclear Operating Corporation Docket No. 50-482 License No. NPF-42 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
LIST OF GENERIC LETTER 2016-01 CATEGORIES Category 1:
Power reactor addressees that do not credit neutron-absorbing materials other than soluble boron in the analysis of record (AOR). In some cases, no neutron-absorbing material is present in the spent fuel storage racks, and in other cases, credit for the neutron-absorbing material has been removed through a regulatory action (e.g., approved license amendment). Those addressees may submit a response letter confirming that no neutron-absorbing materials are currently credited to meet U.S. Nuclear Regulatory Commission (NRC) subcriticality requirements in the spent fuel pool (SFP).
Category 2:
Power reactor addressees that have an approved license amendment to remove credit for existing neutron-absorbing materials and that intend to complete full implementation no later than 24 months after the issuance of this generic letter.
Licensees may request extensions to this implementation timeframe if there are extenuating circumstances. Those addressees may submit a response letter affirming that they will implement the approved license amendment request within the specified time. However, they must still provide information equivalent to Category 3 or Category 4 for any other neutron-absorbing material credited in the SFP criticality AOR after the license amendment has been fully implemented.
Category 3:
Power reactor addressees that have incorporated their neutron-absorbing material monitoring programs into their licensing basis through an NRG-approved technical specification (TS) change or license condition. Those addressees may submit a response letter referencing their approved TS change or license condition and affirming that no change has been made to their neutron-absorbing material monitoring program, as described in the referenced license amendment request. If a change has been made since NRC approval of the reference, the response letter should also describe any such changes. (Licensees with a monitoring program approved as part of a license amendment request or license renewal application that was not incorporated as a TS change or license condition are considered to belong in Category 4.)
Category 4:
All other power reactor addressees. The NRC seeks information in five areas depending upon the type of neutron absorber material used by the licensee in the SFP.
LIST OF PLANTS, INCOMING LETTERS. COST ACTIVITY CODE NUMBERS.
AND ENTERPRISE PROJECT IDENTIFIERS Incoming Letter (ADAMS Plant Accession No.)
CAC No(s).
EPID Callaway Plant, Unit 1 ML16308A443 MF9451 L-2016-LRC-0001 St. Lucie Plant, Units 1 and 2 ML16312A050 MF9421 L-2016-LRC-0001 MF9422 Susquehanna Steam Electric ML163548569 MF9418 L-2016-LRC-0001 Station, Units 1 and 2 MF9419 Turkey Point Nuclear Generating ML16312A050 MF9412 L-2016-LRC-0001 Units 3 and 4 MF9413 Watts Bar Nuclear Plant, Units 1 and ML163548569 MF9407 L-2016-LRC-0001 2
MF9408 Wolf Creek Generating Station, ML16313A080 MF9406 L-2016-LRC-0001 Unit 1
REQUEST FOR SUPPLEMENTAL INFORMATION - GENERIC BORAL QUESTION 1 For the plants listed below, the following information is needed for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review.
Callaway Plant, Unit 1 St. Lucie Plant, Units 1 and 2 Turkey Point Nuclear Generating, Units 3 and 4 Watts Bar Nuclear Plant, Units 1 and 2 Wolf Creek Generating Station, Unit 1 Generic Boral-RAl-1 Title 10 of the Code of Federal Regulations (10 CFR) Section 50.68, "Criticality accident requirements," and 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 62, "Prevention of criticality in fuel storage and handling," provide the requirements for licensees with regard to maintaining subcriticality in the spent fuel pool (SFP). For licensees that utilize neutron absorbing materials (NAM) in the SFP, the boron-10 (1°8) areal density (AD) of the NAM must be known so that the assumption for the 108 minimum AD in the SFP nuclear criticality safety (NCS) analysis of record (AOR) is supported. In order for the NRC staff to verify the requirements of 10 CFR 50.68 and GDC 62 are met, the staff needs to ensure that licensees are taking appropriate action to confirm that the 108 AD of their NAM can reasonably be expected to remain above the minimum assumed in the SFP NCS AOR. In addition, the condition of the NAM must be considered in the SFP NCS AOR. In order to verify whether or not the requirements of 10 CFR 50.68 and GDC 62 will continue to be met, the staff needs to verify that the potential reactivity changes due to degradation or physical changes to the NAM are accounted for in the SFP NCS AOR. This includes any changes that would affect the neutron spectrum for the SFP in addition to any loss of neutron attenuation capability.
Industry operating experience, as described in Information Notice (IN) 2009-26, "Degradation of Neutron Absorbing Materials in the Spent Fuel Pool," dated October 28, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092440545), and IN 1983-29, "Fuel Binding Caused by Fuel Rack Deformation," dated May 6, 1983 (ADAMS Accession No. ML14043A291 ), has demonstrated that certain manufacturing processes and plant conditions (dose, chemistry, length of time installed, and installation configuration) have resulted in material deformation as a result of blisters or bulging associated with Baral.
[Plant name above] does not have a site-specific monitoring program, and consequently, is relying on general industry operating experience as a surrogate for the condition of the Baral installed in the SFP.
- a. Please describe whether industry operating experience bounds the condition of the Baral at [plant name above], thereby ensuring that any degradation or deformation that may affect the Boral at [plant name above] is identified.
- b.
In addition, discuss the criticality impact due to relevant material deformation identified in general industry operating experience, and whether it can be accommodated by the NCS AOR for [plant name above] without exceeding NRC subcriticality requirements.
REQUEST FOR SUPPLEMENTAL INFORMATION -GENERIC BORAL QUESTION 2 For the plant listed below, the following information is needed for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review.
Susquehanna Steam Electric Station, Units 1 and 2 (SSES)
Generic Boral-RAl-2 Title 1 O of the Code of Federal Regulations (1 O CFR) Section 50.68, "Criticality accident requirements," and 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 62, "Prevention of criticality in fuel storage and handling," provide the requirements for licensees with regards to maintaining subcriticality in the spent fuel pool (SFP).
For licensees that utilize neutron absorbing materials (NAM) in the SFP, the properties of the NAM must be known so that the assumptions in the SFP nuclear criticality safety (NCS) analysis of record (AOR) are supported. In order to verify whether or not the requirements of 10 CFR 50.68 and GDC 62 will be met, the staff needs to verify that the potential reactivity changes due to degradation or physical changes to the NAM are accounted for in the SFP NCS AOR. This includes any changes that would affect the neutron spectrum for the SFP in addition to any loss of neutron attenuation capability.
Industry operating experience, as described in Information Notice 2009-26, "Degradation of Neutron-Absorbing Materials in the Spent Fuel Pool," dated October 28, 2009 (ADAMS Accession No. ML092440545), has demonstrated that certain manufacturing processes and plant conditions (dose, chemistry, length of time installed, and installation configuration) have resulted in material deformation as a result of blisters associated with Boral.
SSES has indicated that similar operating experience was identified as a result of its site-specific monitoring program. Please discuss the criticality impact due to the material deformation identified at SSES, and whether it can be accommodated by the NCS AOR at SSES without exceeding NRC subcriticality requirements.
ML173046153 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LSPB/LAiT NAME SWall
!Betts DATE 11/06/17 11/02/17 OFFICE NRR/DPR/PGCB/BC(A)* NRR/DSS/SNPB/BC*
NAME AGarmoe RLukes DATE 9/22/17 9/21/17
- via email NRR/DORL/LSPB/LA JBurkhardt 11/06/17 NRR/DORL/LSPB/BC DBroaddus 12/18/17