HNP-14-099, Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information

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Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information
ML14251A274
Person / Time
Site: Harris 
(NPF-063)
Issue date: 09/08/2014
From: Waldrep B
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-14-099, TAC MF4113
Download: ML14251A274 (4)
v • d • e


Text

Benjamin & Waldrep

'8.( Vice President ENERGY Harris Nuclear 3ODQW 5413 Shearon Harris Rd New +LOONC 

919-362-2502

CFR D 6(3 - 8 2014 6HULDOHNP-14-099 ATTN: Document &RQWURODesk 861XFOHDU5HJXODWRU\Commission Washington, DC 

Shearon Harris 1XFOHDUPower 3ODQW Unit 1 Docket No. / Renewed License No. NPF-63

Subject:

5HOLHIRequest ,5'HIHUUDOof Reactor 9HVVHO,QVSHFWLRQV

,QVHUYLFHInspection Program- Third Ten-Year ,QWHUYDO Response to Request for $GGLWLRQDO,QIRUPDWLRQ(TAC 12MF4113)

Ladies and Gentlemen:

By letter dated April 25,  $'$06Accession Number ML14115A419), Duke Energy Progress, ,QFsubmitted a UHOLHIrequest for Shearon Harris Nuclear Power 3ODQWUnit 1 (HNP).

The proposed relief request would defer the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section ;, required volumetric examination of the HNP reactor vessel full penetration pressure retaining Category B-A and B-D welds for the third inservice inspection ,6, interval, currently scheduled for 2015, until the fourth ,6, interval, and to perform the required examinations in plus or minus one refueling outage. The U.S. Nuclear Regulatory Commission staff reviewed the submittal and determined that additional information was needed in order to complete their review, which was transmitted in a letter dated August 27, 2014 (ADAMS Accession Number ML14234A385). Enclosed is HNP's response to the NRC staff request.

This document contains no new regulatory commitments.

Please refer any questions regarding this submittal to John Caves at (919) 362-2406.

Sincerely,

Enclosure:

Relief Request ,5 Response to Request for Additional Information cc: Mr. J.D. Austin, NRC Sr. Resident Inspector, HNP (email)

Ms. M. Barillas, NRC Project Manager, HNP (email)

Mr. V. M. McCree, NRC Regional Administrator, Region II (EIE)

Benjamin C. Waldrep Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-2502 10 CFR 50.55a Serial: HNP-14-099 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63

Subject:

Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information (TAC NO. MF4113)

Ladies and Gentlemen:

By letter dated April 25, 2014 (ADAMS Accession Number ML14115A419), Duke Energy Progress, Inc. submitted a relief request for Shearon Harris Nuclear Power Plant, Unit 1 (HNP).

The proposed relief request would defer the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI required volumetric examination of the HNP reactor vessel full penetration pressure retaining Category B-A and B-D welds for the third inservice inspection (lSI) interval, currently scheduled for 2015, until the fourth lSI interval, and to perform the required examinations in 2024, plus or minus one refueling outage. The U.S. Nuclear Regulatory Commission staff reviewed the submittal and determined that additional information was needed in order to complete their review, which was transmitted in a letter dated August 27, 2014 (ADAMS Accession Number ML14234A385). Enclosed is HNPs response to the NRC staff request.

This document contains no new regulatory commitments.

Please refer any questions regarding this submittal to John Caves at (919) 362-2406.

Sincerely, Benjamin C. Waldrep

Enclosure:

Relief Request I3R-14, Response to Request for Additional Information cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP (email)

Ms. M. Barillas, NRC Project Manager, HNP (email)

Mr. V. M. McCree, NRC Regional Administrator, Region II (EIE)

U.S. Nuclear Regulatory Commission Relief Request I3R-14 RAI Response HNP-14-099 Enclosure Page 1 of 2 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63 Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information By letter dated April 25, 2014 (ADAMS Accession Number ML14115A419), Duke Energy Progress, Inc. submitted a relief request for Shearon Harris Nuclear Power Plant, Unit 1 (HNP).

The proposed relief request would defer the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI required volumetric examination of the HNP reactor vessel full penetration pressure retaining Category B-A and B-D welds for the third inservice inspection (lSI) interval, currently scheduled for 2015, until the fourth lSI interval, and to perform the required examinations in 2024, plus or minus one refueling outage. The U.S. Nuclear Regulatory Commission staff reviewed the submittal and determined that additional information was needed in order to complete their review, which was transmitted in a letter dated August 27, 2014 (ADAMS Accession Number ML14234A385). The following is HNPs response to the NRC staff request.

Request:

Regarding evaluation of indications identified in past lSI examinations, Table 2 of Relief Request I3R-14 states that both of the indications found were acceptable per Table IWB-3510-1 of Section XI of the ASME Code. Please provide the information used to support this conclusion.

Response

Reactor vessel (RV) inservice inspection data are reviewed to confirm that satisfactory inspections have been performed on the reactor vessel and that the flaw distributions used in the pilot plant analyses are bounding. In accordance with the analyses in NUREG-1874, which is the probabilistic fracture mechanics basis for the Alternate PTS Rule, the only flaws of concern are those that are within the inner three-eighths of the reactor vessel thickness and in the beltline region adjacent to the reactor core. These flaws must meet the allowable sizes in Table IWB-3510-1 of Section XI of the ASME Code. Only those flaws found in an ASME Section XI, Appendix VIII inspection in the inner one-tenth thickness or one inch, whichever is greater, must also meet the allowable flaw limits. Two indications with the potential to be located in the beltline region of the Shearon Harris Unit 1 RV were recorded during the last ISI. These indications were evaluated using the process described above.

The details of the flaw location evaluation are shown below. It was determined that these indications are located in the beltline region, but neither of these two indications fall within the inner three-eighths of the RV thickness. These indications were allowable per Table IWB-3510-1 of Section XI of the ASME Code.

U.S. Nuclear Regulatory Commission Relief Request I3R-14 RAI Response HNP-14-099 Enclosure Page 2 of 2 Evaluation attribute Indication 1 Indication 1 (Weld LSW-RV-08) (Weld LSW-RV-10)

1. Determine if the flaw is located Located in the CRV and in Located in the CRV and in within the code required volume the weld the weld (CRV), and if in the weld or adjacent plate material
2. Characterize the flaw (planar, Planar Planar non-planar, or laminar)
3. Determine orientation Oriented parallel to weld Oriented parallel to weld axis axis
4. Further characterize the flaw as Subsurface Subsurface surface, surface by proximity, or subsurface (in relation to the pressure-loaded surface)
5. Determine flaw depth (TWE) and Depth: 0.125 Depth: 0.15 length Length: 1.0 Length: 0.5
6. Calculate the aspect ratio and a/t Aspect ratio: 0.06 Aspect ratio: 0.15 value (%) a/t (%): 0.81 a/t (%): 0.97
7. Using the applicable Table (IWB- 4 to 12 4 to 12 3510-1) select the appropriate thickness range for acceptance criteria
8. Determine the maximum Max acceptable a/t (%): Max acceptable a/t (%):

acceptable a/t (%) value using Table 2.26 2.9 IWB-3510-1 by application of the calculated aspect ratio

9. Determine if the indication is Acceptable Acceptable acceptable (or not) per Table IWB-3510-1
10. Determine if the flaw lies in the Located in the beltline Located in the beltline beltline region adjacent to the region adjacent to the core region adjacent to the core core(140.94- 288.44 from the top (184.3 from the top flange (240.8 from the top flange flange surface) surface) surface)
11. Determine if the flaw is within Located 5.51 from the Located 4.12 from the the inner 3/8 thickness (2.906) of pressure-loaded surface pressure-loaded surface component thickness adjacent to the and therefore not within and therefore not within pressure-loaded surface the inner 3/8 component the inner 3/8 component thickness thickness
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