CY-23-012, Comment (4) of Rob Desmarais on Behalf of Connecticut Yankee Atomic Power Co., on Draft Regulatory Guide: Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations
| ML23181A031 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/29/2023 |
| From: | Desmarais R Connecticut Yankee Atomic Power Co |
| To: | Office of Administration |
| References | |
| CY-23-012, NRC-2023-0107, 88FR36514 00004 | |
| Download: ML23181A031 (1) | |
Text
6/30/23, 7:30 AM blob:https://www.fdms.gov/5d1a2dbc-1ccb-43da-b303-234b7c88b528 SUNSI Review Complete As of: 6/30/23, 7:30 AM Template=ADM-013 Received: June 29, 2023 PUBLIC SUBMISSION E-RIDS=ADM-03 ADD: John -Chau Nguyen, Harriet Karagiannis, Bridget Status: Pending_Post Tracking No. ljh-ldmg-kqqf Curran, Mary Neely Comments Due: July 05, 2023 Comment (4) Submission Type: Web Publication Date: 6/5/2023 Citation: 88 FR 36514 Docket: NRC-2023-0107 Draft Regulatory Guide: Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations Comment On: NRC-2023-0107-0001 Draft Regulatory Guide: Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations Document: NRC-2023-0107-DRAFT-0006 Comment on FR Doc # 2023-11895 Submitter Information Email: sday@3yankees.com Organization: Connecticut Yankee Atomic Power Company General Comment See attached file(s)
Attachments CY-23-012 (Comments on DG-3057 R1) blob:https://www.fdms.gov/5d1a2dbc-1ccb-43da-b303-234b7c88b528 1/1
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD
- EAST HAMPTON, CT 06424-3099 June 29, 2023 CY-23-012 U.S. Nuclear Regulatory Commission ATTN: Program Management, Announcements and Editing Staff Office of Administration, Mail Stop: TWFN-7-A60M Washington, DC 20555-000 Connecticut Yankee Atomic Power Company Haddam Neck Plant Independent Spent Fuel Storage Installation NRC License No. DPR-61 (NRC Docket Nos. 50-213 and 72-39)
Subject:
Comments on Draft Regulatory Guide DG-3057 On June 5, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued for public comment a draft regulatory guide (DG), DG-3057, Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations. Connecticut Yankee Atomic Power Company (CY) offers the following comments for consideration:
Overall, the draft Regulatory Guide DG-3057 provides a prescriptive methodology for managing the performance of Outdoor Dry Cask Storage Operations. Over numerous years, licensees have successfully applied administrative controls to minimize the risks associated with the performance of Outdoor Dry Cask Storage Operations. A risk-informed and performance-based approach should be adopted without introducing a new significant level of effort.
Clarification #5 effectively requires a design review to determine what weather conditions are analyzed in order to then determine what weather conditions are unanalyzed, to then determine qualitative or quantitative criteria that define/outline a safe condition and forecast. A significant level of effort would be required to meet the prescriptive requirements of this clarification. If the concern is that activities/equipment/personnel used to support the operation need to be considered, then this clarification could be simplified to specify that review. This clarification has been written to be an overly prescriptive task which can be re-written to require that the given project has considered all supporting work and has applied stop work criteria for the limitations specific to those activities/equipment/personnel.
In addition, how would a licensee properly apply the appropriate error margin? Did the NRC intend for this to permit licensees to take credit for using cranes with extra capacity and setting wind speed thresholds that are less than the specified limits by the crane manufacturer or industry standards? This term is vague and subject to interpretation and the sentence that contains this term should be deleted. The sentence that precedes it provides enough additional guidance to licensees.
Although Clarification #6 allows for justification to use an equivalent weather service to the national weather service (NWS), the NRC should recognize that the closest NWS to a site may not represent the weather at the site. In these cases, the user would enter the sites zip-code and
Connecticut Yankee Atomic Power Company CY-23-012/June 29, 2023/Page 2 the NWS usually provides a forecast based on data from the closest airport, not from NWS data.
Does the utilization of this data provided through the NWS meet the intent of the NRCs clarification?
Exception #8 is too open ended and could be subject to differing opinions on how well a site has addressed contingencies. What a licensee develops as a sufficient contingency policy for a site may not seem sufficient to an inspector/auditor. Consideration should also be given to Independent Spent Fuel Storage Installation (ISFSI) only sites that do not have access to plant equipment like single failure proof cranes. Aging management inspections performed to date have proved to have sufficient contingencies. Examples that have been used in typical planning activities include; using mobile cranes with double the capacity for the heaviest lift and documented in the crane certifications; using single failure proof rigging; identifying sources for a suitable backup crane with an acceptable response time to the site; maintaining redundant torque wrenches on site for torquing requirements; obtaining tooling to address stuck bolts; utilizing personnel with multiple qualifications to address personnel absences; limiting load lift height when removing/reinstalling components over casks; requiring load transit paths that avoid other casks and safety related hardware; and obtaining multiple spare parts for inspection robots and cameras.
Typically, malfunctions and delays are addressed in technical support documents. As a result of these considerations, limitations are included in the work order controlling the work that include contingency steps for malfunctions and delays. All such events would also be documented in the sites corrective action program. This is standard practice for licensees using existing programs and processes which already occur without reliance on the NEI guidance or the NRC exception.
We think the NEI guidance adequately highlights the consideration to licensees engaged in these activities.
If you have any questions regarding this submittal, please do not hesitate to contact me at (860) 267-6426, extension 306.
Respectfully, Rob Desmarais ISFSI Manager