|
---|
Category:E-Mail
MONTHYEARML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23156A3042023-05-31031 May 2023 Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from Pressure Temperature Limits and Low Temperature Over Pressure Protection Curves ML23109A1862023-04-19019 April 2023 and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1 ML23066A1892023-03-0303 March 2023 OEDO-22-00419: Email Dated 3-3-2023 to Petitioner on Seabrook ASR Petition ML23066A0892023-02-24024 February 2023 OEDO-22-00419 - Email Dated 02/24/2023 to Petitioner on Seabrook Unit 1 ASR Petition ML23020A9392023-01-19019 January 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Cooling Tower Service Water Loop or Cell Requirements (EPID L-2022-LLA-0183) (Email) ML23011A3082023-01-11011 January 2023 Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074) ML22341A0012022-12-0606 December 2022 Acceptance of Requested Licensing Action Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) ML22333A7452022-11-22022 November 2022 OEDO-22-00419 - Email: C-10 Response on PRB Initial Assessment - C-10 Petition on Seabrook ASR Concrete Degradation ML22287A1472022-10-13013 October 2022 2.026 Petition Screen-in Email ML22228A0552022-08-15015 August 2022 Request for Additional Information Steam Generator Tube Inspection Report Review ML22200A1082022-07-19019 July 2022 Acceptance Review for TSTF-577 Amendment ML22153A4152022-05-31031 May 2022 Request for Additional Information Re 120V Inverter LAR from TS Branch - Final ML22116A2442022-04-26026 April 2022 Acceptance of Requested Licensing Action Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage ML22048B5522022-02-17017 February 2022 LTR-22-0010 Reply to Geoff Gilbert Email Concern About Seabrook Station Concrete Degradation ML22062B6642022-02-0707 February 2022 Request for Additional Information 120V Inverter LAR from the Electrical Branch ML22063A0002022-01-25025 January 2022 Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR ML22020A2542022-01-20020 January 2022 LTR-22-0010 Geoff Gilbert, E-mail Concern About Seabrook Station Concrete Degradation ML21097A2512021-04-0707 April 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Report Review for RFO 20 (EPID L-2020-LRO-0066) (Email) ML21054A0482021-02-23023 February 2021 Request for Additional Information Regarding Heat Flux Hot Channel Requirement Amendment Request ML20343A0942020-12-0303 December 2020 Request for Additional Information Regarding Seabrook (COVID-19) Part 73 Force-on-Force Exemption Request (L-2020-LLE-0219) ML20273A2812020-09-22022 September 2020 Acceptance of Requested Licensing Action License Amendment Request to Resolve Non-Conservative Heat Flux Hot Channel Factor Requiments ML20258A1502020-09-14014 September 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding One-Time Change to the AC Sources Operating TS ML20260H4932020-09-11011 September 2020 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Request to Use Later Code Edition of ASME OM Code ML20230A2962020-08-14014 August 2020 Acceptance of Requested Licensing Action License Amendment Request to Allow a One-Time Change to the AC Sources Operating TS ML20167A1842020-06-11011 June 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding TSTF-411 and TSTF-418 (L-2019-LLA-0237) ML20124A0012020-05-0101 May 2020 Cancellation of Call with Seabrook on Steam Generator Tube Inspections ML20114E1592020-04-23023 April 2020 Email and Request for Additional Information Related to Seabrook License Amendment Request to Degraded Voltage Time Delay Setpoint (L-2020-LLA-0012) ML20101N0932020-04-10010 April 2020 Acceptance of Requested Licensing Action Re Relief Request to Defer ASME Inspections Due COVID-19 (EPIDs L-2020-LLR-0055, -56, and -57) ML20101L0402020-04-10010 April 2020 Acceptance of Requested Licensing Action Relief Request to Use Code Case OMN-13 with 2012 Edition of the OM Code ML20101H3912020-04-0808 April 2020 Verbal Authorization for Seabrook Relief Request 3IIR-7 ML20087K8262020-03-27027 March 2020 Upcoming Steam Generator Tube Inservice Inspection ML20063J9792020-02-28028 February 2020 Acceptance of Requested Licensing Action Amendment Request to Revise Degraded Voltage Time Delay Setpoint ML19347C6732019-12-13013 December 2019 Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-418 ML19296D9122019-10-23023 October 2019 NRR E-mail Capture - Request for Additional Information Related to Seabrook Inverter Amendment (L-2019-LLA-0216) ML19295F5422019-10-15015 October 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Amendment Request to Revise Onsite Power Distribution Requirements ML19275G7832019-10-0101 October 2019 Limited Appearance Statement from New Hampshire State Representative, Robert Harb Regarding the Seabrook Station Unit 1 License Amendment Application ML19270E6512019-09-27027 September 2019 Limited Appearance Statement from Joanna Hammond Regarding the Seabrook Station Unit 1 License Amendment Application ML19270E6542019-09-26026 September 2019 Limited Appearance Statement from Brian Campbell Regarding the Seabrook Station Unit 1 License Amendment Application ML19196A3592019-07-15015 July 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Amendment Request to Revise the Emergency Core Cooling System Accumulator Technical Specifications ML19169A2412019-06-13013 June 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Relief Requests for the Containment Building Spray Pump Flow and Vibration Testing (Epids L-2019-LLR-00 and L-2019-LLR-00) ML19162A0662019-06-0404 June 2019 Reply to Mr. Rick Jakious'S E-mail of 5-29-2019 to Stephen B. Comley Sr., We the People with Attachments ML19112A1782019-04-22022 April 2019 NRR E-mail Capture - Point Beach; Seabrook; Turkey Point - Acceptance of Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-563 ML19101A4042019-04-11011 April 2019 NRR E-mail Capture - Point Beach; Seabrook; St. Lucie; Turkey Point - Acceptance of Licensing Action Relief Request to Use Encoded Phased Array Ultrasonic Examination Techniques for Ferritic and Austenitic Welds ML19070A2382019-03-10010 March 2019 LTR-19-0088 Maura Healey, Attorney General, the Commonwealth of Massachusetts, Ltr NextEras Requests for a License Amendment and Twenty-year Extension Prior to Issuance of a Final Decision in Adjudicatory Hearing on Concrete Degradation at ML19056A4522019-02-25025 February 2019 Comment from Philip Hurzeler Regarding the Emergency Petition Filed by C-10 on February 13, 2019 ML19056A4582019-02-25025 February 2019 Comment from Deborah A. Jones Regarding the Emergency Petition Filed by C-10 on February 13, 2019 ML19056A4602019-02-25025 February 2019 Comment from Lisa Conti Regarding the Emergency Petition Filed by C-10 on February 13, 2019 ML19050A2212019-02-19019 February 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Relief Request Proposed Alternative 3IR-17 Implementation of an Extended Reactor Vessel Inservice Inspection Interval ML19050A3202019-02-13013 February 2019 Package from Stephen B. Comley, Sr. at February 13, 2019 Seabrook Station, Unit 1, Public Meeting 2023-06-22
[Table view] |
Text
From: Gray, Mel Sent: Monday, May 19, 2014 9:21 AM To: Debbie Grinnell Cc: Barkley, Richard; Dentel, Glenn; Cook, William; Heater, Keith
Subject:
Response to Questions Regarding NRC Documents Describing our Oversight of Seabrook Containment Liner Examination Activities Based on your conversations with Mr. Rich Barkley of NRC Region I, the following responds to specific questions related to NRC reviews of the containment liner at the Seabrook Station.
Specifically, the following questions are associated with NRC Inspection Report 05000443/2012005 dated February 11, 2013 (ADAMS ML3042A058) and NRC Safety Evaluation Report with Open items Related to the License Renewal of Seabrook Station, (ML12160A374), pages 3-28 to 3-32.
If you have further questions, please contact myself at 610-337-5209 or Mr. Rich Barkley at 610-337-5328.
Myself and Mr. Bill Cook are also available today to discuss our recent NRC inspection report regarding Seabrook Station. Please contact me at the above number.
Sincerely, Mel Gray Chief, Engineering Branch 1 NRC Region I Office
- 1) What was the elevation of the water in the Containment Enclosure Building and at what azimuth?
Response: The bottom of the Containment Enclosure Building is -30 feet; the bottom floor of containment is -26 feet. The water level in the annulus area was found to be up to 6 feet deep.
Thus the water in the annulus was at most 2 feet above the floor level of the containment. The annulus runs 360 degrees around containment, with the exception of areas where there are penetrations into the containment, such as the fuel transfer tube and its associated concrete shielding. The containment is described in terms of angular measurement (azimuth) from 0 to 360 degrees.
- 2) In 2009, NextEra noted an area of the containment liner near the fuel transfer tube that was corroded and had a thickness of between 0.484 - 0.411 inches (a variation of 18 percent). You indicated that you had seen another document which indicated an area of the containment liner (presumably this same one) was 0.409 - 0.400 inches in early 2011. You also noted that in a February 2013 Inspection Report that another area was 0.375 inches thick, although we verified that this location (-26 foot elevation at azimuth 317 degrees) was definitely different than the 2009 measurement. You asked the location of all of these measurements, as well as whether the 2009 measurement would be repeated 3 times as indicated in an NRR license renewal document?
Response: The fuel transfer tube passes through the containment liner inside the transfer tube shielded vault. This area is located at azimuth 180 degrees near the containment floor. A
reinforcing transition plate, welded to the transfer tube, is then welded to the containment liner.
The transition plate is 0.75 inches thick and the liner plate is 0.375 inches thick. The weld joining these two pieces varies in thickness; however, the welded area thickness is greater than the required 0.375 inch thickness of the containment liner.
In 2009, the licensee noted an area of the containment liner near the fuel transfer tube was inspected and surface rust was evident. UT thickness readings verified that all areas with surface rust or coating anomalies showed thicknesses greater than 0.375 inches. The 0.484 and the 0.411 thickness readings were not taken in the same location. The two thickness readings were taken at different locations in the fuel transfer tube area, which varied in thickness due to the weld. However, both locations had thickness greater than the required 0.375 inches.
You indicated that you had seen another document which indicated an area of the containment liner (presumably this same one) was 0.409 - 0.400 inches in early 2011. Without knowing the document that identifies these numbers, we cannot provide a location or the context for these numbers.
- 3) You asked about a commitment by NextEra to inspect much more extensive portions of the containment liner, as well as urged the NRC to require NextEra to UT examine the thickness of 100% of the liner to detect any possible degradation as you do not feel the required visual inspection of the internal surface of the liner is adequate. You asked the location of all of these measurements, as well as whether the 2009 measurement would be repeated 3 times as indicated in an NRR license renewal document?
Response: As part of our ongoing license renewal review process, the NRC issued a Safety Evaluation Report (SER) with open items (ML12160A374). The NRC SER pages 3-30 and following describe licensee commitments to measure specific areas of the containment liner.
Regarding the fuel transfer tube vault area measured in 2009, the licensee stated that it will complete augmented exams of this area under Subsection IWE,Section XI of the ASME B&PV Code for the next three exam cycles (every 3 1/3 years). The licensee also committed to complete inspections of the containment liner area within 10 inches of the moisture barrier at the containment basement floor (-25 to -26 foot elevation). This was the area of the liner potentially affected by standing water in the annulus which is now maintained in a dewatered state. The licensee committed to measure the liner thickness at 10 degree increments and complete these examinations by December 31, 2015, and thereafter at intervals of no more than five refuel outages as described in the SER. The licensees containment liner examination actions during the recent April 2014 refuel outage will be described in the next NRC inspection report for the Seabrook Station to be issued in early August 2014.
NRC safety requirements for completing inservice inspections of the containment liner are located in 10CFR50.55a, paragraph g which requires licensees implement ASME Section XI of the Boiler and Pressure Vessel Code inservice inspections related to containment liners. Our reviews at the Seabrook Station to date have determined the licensee has complied with our requirements related to containment liner inspections.
I would note that while the thickness of the containment liner is not extensively measured, the integrity of the containment liner is confirmed via periodic testing during a Containment Integrated Leak Rate Test (ILRT). This test verifies the ability of the containment to withstand the highest pressure expected following a design basis accident by pumping up the building with high pressure air. It also verifies that when at this pressure, the containment will not leak more
than a very small fraction of its volume per day. The main purpose of the liner is to ensure the containment structure is able to meet this stringent leakage provision as noted in 10 CFR 50, Appendix J.