RNP-RA/14-0137, Response to NRC Request for Additional Information Related to Forced Outrage R229F3 Steam Generator Tube Inspection Report
| ML14365A192 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/15/2014 |
| From: | Peavyhouse S Duke Energy Corp, Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/14-0137, TS 5.6.8 | |
| Download: ML14365A192 (3) | |
Text
Sharon W. Peavyhouse H. B. Robinson Steam Electric Plant Unit 2 ENERGY9 Director-NuclearOrganization Effectiveness Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0: 843 857 1584 F: 843 857 1319 Sharon.Peavyhouse@duke-energy.com TS 5.6.8 Serial: RNP-RA/14-0137 DEC 1 5 2014 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO FORCED OUTAGE R229F3 STEAM GENERATOR TUBE INSPECTION REPORT Ladies and Gentlemen:
By letter dated September 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14282A020), Duke Energy Progress, Inc., submitted information summarizing the results of the spring 2014 steam: generator tube inspections performed at H. B.
Robinson Steam Electric Plant (HBRSEP),:Unit No. 2.:The NRC staff reviewed the submittal and determined that additional information was needed in order to complete its review. The enclosed document describes this request for additional information (RAI). The RAI was mailed to the HBRSEP, Unit No. 2 on December 1, 2014 (ADAMS Accession No. ML14329B212), with a response requested by December 15, 2014. The enclosure to this letter contains Duke Energy Progress, Inc.'s response for the HBRSEP, Unit No. 2 Steam Generator Inspection Report RAIs.
There are no regulatory commitments made in this submittal. If you have any questions regarding this submittal, please contact Mr. R. Hightower at (843) 857-1329.
Sincerely, Sharon W. Peavyhouse Director - Nuclear Organization Effectiveness SWP/msc Enclosure cc:
Mr. V.-M. McCree, NRC, Region II Ms. Martha Barillas,'NRC -Project Manager, NRR NRC Resident Inspector, HBRSEP, Unit No. 2 cc~L~t~~c~
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United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0137 Page 1 of 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION FORCED OUTAGE R229F3 STEAM GENERATOR TUBE INSPECTION REPORT The following information is provided in response to the NRC request for additional information (RAI) regarding Forced Outage R229F3 Steam Generator Tube Inspection Report (ADAMS ML14329B212) dated December 1,2014:
RAI 1
During the March 24, 2014 conference call, it was stated that visual inspections were planned for the tubesheet and the downcomer region of the "C" steam generator. Please discuss the results of these inspections.
Response to RAI 1:
Both the hot leg and cold leg tubesheets were inspected down every column, 150 of 152 machining remnants identified were removed. The two remaining remnants were lost in the sludge pile but were determined to be too small to become lodged between tubes. The downcomer annulus was in inspected on a best effort basis. No foreign material was identified.
RAI 2
Was an eddy current inspection performed on the leaking tube after the in-situ pressure test? If so, please discuss whether there was any change in the eddy current data pre-and post-test.
Response to RAI 2:
Yes. The eddy current voltage on the array increased after the in situ pressure test. The visual appearance of the data also suggested a change. The in-situ leak rate data also increased at the higher in-situ pressures. Due to the circumferential nature of the flaw the growth was limited.
RAI 3
Please discuss the extent of the array probe inspections. For example, were the inspections performed from the H-star distance below the top of the tubesheet to the first tube support plate?
Response to RAI 3:
All array probe inspections were conducted either from the first tube support plate or flow distribution baffle to the tube end.
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/1 4-0137 Page 2 of 2
RAI 4
Please confirm that all service-induced indications have been reported, including those which may not have shown changes since prior inspections (e.g., HNC indications).
Response to RAI 4:
All service induced indications were reported in letter dated November 13, RNP-RA /14-0125, "Response To NRC Request For Additional Information Related To Refueling Outage 28 Steam Generator Tube Inspection Report," including the results of the Spring 2014 outage.