ML100960277: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[NG-10-0191, NextEra Energy Duane Arnold, LLC - Supplemental Information Regarding the Duane Arnold Energy Center License Renewal Application]]
| number = ML100960277
| issue date = 04/02/2010
| title = NextEra Energy Duane Arnold, LLC - Supplemental Information Regarding the Duane Arnold Energy Center License Renewal Application
| author name = Costanzo C R
| author affiliation = NextEra Energy Duane Arnold, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000331
| license number = DPR-049
| contact person =
| case reference number = NG-10-0191
| document type = Letter
| page count = 8
| project =
| stage = Supplement
}}
 
=Text=
{{#Wiki_filter:NExTera m ENERG 7 AROL April 2, 2010 NG-10-0191 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Supplemental Information Regarding the Duane Arnold Energy Center License Renewal ADDlication
 
==References:==
: 1. Letter, Richard L. Anderson (FPL Energy Duane Arnold, LLC) to Document Control Desk (USNRC), "Duane Arnold Energy Center Application for Renewed Operating License (TSCR-1 09)," dated September 30, 2008, NG-08-0713 (ML082980623)
: 2. Letter, Richard L. Anderson (FPL Energy Duane Arnold, LLC) to Document Control Desk (USNRC), "License Renewal Application, Supplement 1: Changes Resulting from Issues Raised in the Review Status of the License Renewal Application for the Duane Arnold Energy Center," dated January 23, 2009, NG-09-0059 (ML090280418)
By Reference 1, FPL Energy Duane Arnold, LLC submitted an application for a renewed Operating License (LRA) for the Duane Arnold Energy Center (DAEC). Reference 2 provided Supplement 1 to the application.
During the course of the NRC review, several questions have been raised in conference calls and other interactions with the Staff that warrant clarifications or changes to the LRA. The enclosure provides these clarifications and changes.This letter contains no new commitments or changes to existing commitments If you have any questions or require additional information, please contact Mr. Kenneth Putnam at (319) 851-7238.&)ra NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324 Document Control Desk NG-10-0191 Page2 I declare under penalty of perjurythat the foregoing is true and correct.Executed on April 2, 2010.Christopher R. Costanzo Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC
 
==Enclosure:==
 
LRA Changes and Clarifications cc: Administrator, Region III, USNRC Project Manager, DAEC, USNRC Senior Resident Inspector, DAEC, USNRC License Renewal Project Manager, USNRC License Renewal Inspection Team Lead, Region III, USNRC M. Rasmusson (State of Iowa)
Enclosure to NG-10-0191 LRA Changes and Clarifications NRC Request -Clarification Regarding Table 3.3-1, Item Number 3.3.1-49 By email dated March 22, 2010, the NRC Staff requested clarification regarding the discussion of Item Number 3.3.1-49 provided in LRA Table 3.3-1, Summary of Aging Management Evaluations in Chapter VII of NUREG-1801 Auxiliary Systems.Item Number 3.3.1-49, addresses loss of material due to microbiologically influenced corrosion (MIC) of stainless steel and steel with stainless steel cladding heat exchanger components exposed to closed cycle cooling water. The aging management program listed in Table 3.3-1 for those components is the Closed-Cycle Cooling Water System Program. The discussion provided for Item Number 3.3.1-49 states that it is not applicable at DAEC. The Staff requested clarification of this item.DAEC Response Further review shows that there are no stainless steel heat exchanger components exposed to closed-cycle cooling water in scope for License Renewal. The following revisions are therefore made to the LRA: On page 3.3-53, in Table 3.3-1 Summary of Aging Management Evaluations in Chapter VII of NUREG-1801 Auxiliary Systems, the discussion for Item Number 3.3.1-49 is revised to read: Not applicable at DAEC. DAEC does not have any components in scope for License Renewal in this category.On page 3.3-17, in LRA Section 3.3.1.14 Hydrogen Water Chemistry System, the following is added to Materials:
*Copper. Alloy On page 3.3-156, Table 3.3.2-14, Summary of Aging Management Review Results Hydrogen Water Chemistry System, the following line item is added: Component Intended Material Environment Aging Aging NUREG- Table Notes Type Function Effects Management 1801 3.x-1 Requiring Program Volume 2 Item Management Line Item Heat Leakage Copper Air -indoor None None VIII.1-2 3.4.1- C exchanger, boundary alloy uncontrolled (SP-6) 41 condenser, (spatial) (external) cooler, fan coil On page 3.3-156, Table 3.3.2-14, Summary of Aging Management Review Results Hydrogen Water Chemistry System, the line item for "Heat exchanger, condenser, cooler, fan coil" with aging management program of Closed-Cycle Cooling Water System Program is revised as follows: 1 of 6 Enclosure to NG-10-0191.
LRA Changes and Clarifications Component Intended Material Environment Aging Aging NUREG- Table Notes Type Function Effects Management 1801 3.x-1 Requiring Program Volume 2 Item Management Line Item Heat Leakage Copper Closed cycle Loss of Closed-Cycle VII.F1-8 3.3.1- B exchanger, boundary alloy cooling water material Cooling Water (AP-34) 51 condenser, (spatial) (internal))
System cooler, fan Program coil On page 3.3-203, Table 3.3.2-24, Summary of Aging Management Review Results Reactor Water Cleanup System, the line item for "Heat exchanger, condenser, cooler, fan coil" with material of "Stainless steel" with aging management program of Closed-Cycle Cooling Water System Program is deleted.NRC Request -Clarification of Section 3.3.2.2.3-3 By email dated March 8, 2010, the Staff requested clarification of the rationale of being"in the standby mode of operation" with respect to cracking in stainless steel components exposed to diesel exhaust. The Staff was concerned that, although the duration of operating time wasshort, excluding this aging mechanism entirely was inconsistent with the Generic Aging Lessons Learned (GALL) Report.DAEC Response LRA Section 3.3.2.2.3-3 concerns cracking which could occur in stainless steel diesel exhaust piping, piping components, and piping elements exposed to diesel exhaust. At DAEC a short section of stainless steel flexible coupling is installed in the diesel turbocharger exhaust and thus is exposed to diesel exhaust during engine operation.
Engine operation normally occurs for approximately three hours per month during required generator surveillances and the engine is in standby operation for the remainder of the month and these components are at normal room temperatures.
The following LRA revisions are made to reflect the above information.
On page 3.3-32, in LRA Section 3.3.1.29 Standby Diesel Generators, the following is added to Aging Effects Requiring Management:
* Cracking On page 3.3-37, Section 3.3.2.2.3-3 is revised to replace the existing statement:
At DAEC, the stainless steel diesel exhaust components exposed to diesel exhaust are normally in the standby mode of operation and do not have temperatures
>1400F.2 of 6 Enclosure to NG-10-0191 LRA Changes and Clarifications with the following:
At DAEC, the stainless steel piping components exposed to diesel exhaust in the Standby Diesel Generator System will be managed for stress corrosion cracking by the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program as described in Section B.3.28.On page 3.3-45, Table 3.3-1, Summary of Aging Management Evaluations in Chapter VII of NUREG-1 801 Auxiliary Systems, Item Number 3.3.1-6 is revised to replace the statement "Not applicable at DAEC." with the following:
Consistent with NUREG-1801.
Stress corrosion cracking of stainless steel diesel engine exhaust piping exposed to diesel exhaust is managed by Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program.On page 3.3-238, Table 3.3.2-29, Summary of Aging Management Review Results Standby Diesel Generators, for "Pipe, pipe fittings, hoses, tubes, rupture disk" with an environment of Diesel exhaust (internal), Note 207 is deleted.On page 3.3-240, Table 3.3.2-29, Summary of Aging Management Review Results Standby Diesel Generators,-
the following line item is added: Component Intended Material Environment Aging Aging NUREG- Table Notes Type Function Effects Management 1801 3.x-1 Requiring Program Volume 2 Item Management Line Item Pipe, pipe Pressure Stainless Diesel Cracking Inspection of VII.H2-1 3.3.1-6 E fittings, boundary steel exhaust Internal (AP-33)hoses, (internal)
Surfaces in tubes, Miscellaneous rupture disk Piping and Ducting Components Program On page B-56, B.3.28.1 Program Description, the first sentence of the second paragraph is revised to read as follows: The program consists of inspections of the internal surfaces of metallic piping, piping components, ducting, and other components that are not covered by other aging management programs.3 of 6 Enclosure to NG-1 0-01-91 LRA Changes and Clarifications NRC Request Regarding Section 3.5.2.2.2.8, Numbering By email dated March 8, 2010, the Staff pointed out that LRA Section 3.5.2.2.2.8 details Quality Assurance for Aging Management of Nonsafety-Related Components, whereas, the Standard Review Plan (SRP) has this section numbered as 3.5.2.2.3.
DAEC Response In order to provide consistency with the SRP, the following revision to the LRA is made: Section 3.5.2.2.2.8 Quality Assurance for Aging Management of Nonsafety-Related Components on page 3.5-24 of the LRA is revised to 3.5.2.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components.
Follow-up to RAI 3.5.2.1-a By email dated March 17, 2010, the Staff requested additional information regarding the Defective Fuel Storage Container.
The Original LRA referenced AP-79 (pipe etc, Water Chemistry recommended) and the LRA Aging Management Program (AMP) was Section XI with generic note E and Water Chemistry with generic note C.Revised LRA referenced TP-10 (support members, Water Chemistry and Section XI recommended) and the LRA AMP Section Xl was deleted and Water Chemistry is the only AMP.The Staff- stated that although the change to TP-10 is acceptable, it was not clear why Section Xl was deleted without using the Structural Monitoring Program or possibly the One Time Inspection Program to confirm the Water Chemistry Program with a generic note E and meet the TP-1 0 recommended GALL AMP for visual monitoring of the rack after periods of being immersed in the spent fuel pool.The response to this RAI also included an applicant initiated change for the Holtec Fuel Racks. It was not clear why the Water Chemistry AMP was not listed as a generic note A versus E.DAEC Response The defective fuel storage container is a cylindrical stainless steel component designed to contain leakage from one fuel assembly.
This is a separate component and not part of a spent fuel rack. There are no aging effects for these components when exposed to an air-indoor uncontrolled environment.
Currently at DAEC, none of the defective fuel storage containers are in use, but two empty containers are in the cask pool portion of the spent fuel pool.4 of 6 Enclosure to NG-10-0191 LRA Changes and Clarifications To better meet the GALL for these components, the following LRA changes are made: On page 3.5-11 of the LRA, Section 3.5.1.10 Supports, Aging Management Programs is revised by adding the following:
* One Time Inspection Program On page 3.5-112 of the LRA, in Table 3.5.2-10, Summary of Aging Management Review Results Supports, the line item "Defective fuel storage container in treated water" with AMP of ASME Section XI, Subsection IWF Program was deleted in response to RAI 3.5.2.1-a in letter NG-09-0825 dated December 14, 2009. In addition, in the line item for "Defective fuel storage container in treated water" with AMP of Water Chemistry Program., the entry for NUREG-1801 Volume 2 was changed to I1.B1.1-11 (TP-1 0). This item is revised to read as follows: Component Intended Material Environment Aging Aging NUREG- Table Notes Type Function Effects Management 1801 3.x-1 Requiring Program Volume 2 Item Management Line Item Defective Structural Stainless Treated water Loss of Water VII.A4-11 3.3.1- C fuel storage Support steel (external) material Chemistry (A-58) 24 container in Program treated water One-Time Inspection Program On 'page 3.5-1 12 of the LRA, in Table 3.5.2-10, Summary of Aging Management Review Results Supports, the line item for "Holtec spent fuel rack support" which cites the Water Chemistry Program, the Notes entry was previously changed from A to E in response to RAI 3.5.2.1-a in letter NG-09-0825 dated December 14, 2009. The Notes entry for this item is changed back from E to A.Torus Recoat Commitment Follow-up By telephone call on March 15, 2010, the Staff requested additional detail regarding the torus recoating, in particular regarding the rationale for only recoating the torus below the water line. The Staff requested the following:
: 1) Quantify the density/distribution of coating repairs above and below the water line.2) Provide a brief description of the currentcoating configuration.
: 3) Briefly define/describe "below" the water line. The Staff concern is that the recoat not be cut off where the water line fluctuates above/below the planned recoating.
5 of 6 Enclosure to NG-10-0191 LRA Changes and Clarifications DAEC Response 1. Inspections of the coatings of the shell of the suppression chamber air space (above the water line) performed in recent outages have not identified any coating deficiencies that warranted coating repairs.Inspections performed since 1995 below the waterline have identified areas of coating deficiencies that required repair in approximately 5 percent of the under water surface area of the suppression chamber shell. In the DAEC response to RAI 3.4-7 provided in letter NG-09-0825 dated December-14, 2009, it was stated that the total number of suppression chamber internal coating repairs since. 1995 is 15,487. All of these repairs have been made below the water line, primarily at the very bottom of the shell area.2. As'stated in DAEC Updated Final Safety Analysis Report (UFSAR) Section 6.1.2: "All interior surfaces of the containment received an inorganic zinc primer coat of 3-5 mils thickness.""The torus received two topcoats of the modified phenolic coating along a 2-ft-wide splash band at the water level." 3. Below the water line in the suppression chamber is defined as at the point just below the water to air interface.
The current project plan ensures recoating Will extend well above any fluctuations in water level, including the phenolic splash band.6 of 6}}

Latest revision as of 16:06, 16 April 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML100960277&oldid=1463670"