ML16351A247

Review of SIA Calculation 1601004.301, Cooper High Pressure RHRSW Thinning Evaluation Per Code Case N-513

ML16351A247
Person / Time
Site:	Cooper
Issue date:	12/12/2016
From:	Mcclure T Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16351A264	List: ML16351A247 ML16351A248 ML16351A249 ML16351A250 NLS2016076, 10 CFR 50.55a Request No. RR5-02 for Fifth Ten-Year Inservice Inspection Interval
References
NLS2016076 ER 2016-053, Rev 0
Download: ML16351A247 (5)

Text

Enclosure 7.a of Attachment to NLS2016076

.a RR5-02, Page 1 of 22

. '!lb NUCLEAR QUALITY RELATED 3-EN-DC-147 I REV. 5C1

-====-Entergy MANAGEMENT INFORMATIONAL USE PAGE 1 of4 MANUAL Engineering Reports ATTACHMENT9.1 ENGINEERING REPORT COVER SHEET & INSTRUCTIONS SHEET 1OF2 Engineering Report No. _E_R_2_0_I_6--05_'_3__ Rev Q Page _l_ _ of 4 Engineering Report Title;

~of SIA Calculation 1601004.301, Cooper High Piressure RHRSW Thinning Evaluation per Code Case N,50-3 Engineering !<<part Type::

Revfoioo 0 Cancelled 0 Superseded 0 Superseded by:

Repo.rt Origin: 0 CNS f&l Vendor Ve-ndor Oocument No ..:_ _ _ _ _ _ __

Quality-Related: § Yes 0 No Prepared by: Tim McClure/ i;Jttkt--

ResponsibeEngineer {Print Name/Sign)

Date: fl-12,-((p NiA Date:

Reviewed by:

Date: 1Z-/Z;-/l,.

.**~

Approved by: Stan Domikaitis/ Date: /2--1z-!6 Supervisor 7 Manager (Print Page 1of4 ER 2016-053REV. 0

Enclosure 7.a RR5-02, Page 2 of 22 ENGINEERING REPORT HNPPD ER 2016-053 COOPER NUCLEAR STATION RHRSW Thinning Evaiuation TABLE OF CONTENTS Section

1.0 INTRODUCTION

........................................................................... 3 2.0 PURPOSE ..................................................................................... 3 3.0 TECHNICAL APPROACH ............................................................. 3 4.0 DESIGN INPUTS ........................................................................... 3 5.0 EVALUATION ................................................................................ 4 6.0 RES UL TS ..................................................................................... 8 7.0 REFFERENCES ............................................................................ 8 8.0 ATTACHMENTS ............................................................................ 8 ATTACHMENT 8.1 SIA CALCULATION 1601004.301 Page 2 of 4 ER 2016-053REV. 0 I

Enclosure 7.a RR5-02, Page 3 of 22 ENG~NEERING REPORT HNPPD ER 2016-053

cooPER NUCLEAR STATION RHRSW Thinning Evaluation

1.0 INTRODUCTION

This report is to accept a vendor developed evaluation as a result of multiple thinned locations in the Residual Heat Removal Service Water (RHRSW) system piping. The piping is designated as ASME Section XI Class 3 piping and therefore requires an evaluation under ASME Section XI, 2007 Edition, 2008 Addenda (Current CNS Code or Record). The thinned locations were documented in the CNS Corrective Action Program per CR-CNS-2016-05558 and CR-CNS-2016-05628.

2.0 PURPOSE The purpose of this report is to review and accept a vendor developed structural evaluation as an alternative to ASME Section XI Acceptance Standards using the ASME Section XI Code Case N-513-3. Code Case N-513-3 is conditionally approved by the NRC for moderate energy systems. Because the scope of N-513-3 is limited to moderate energy systems, and the subject piping is considered high energy (maximum operating pressure greater than 275 psig), this calculation provides the technical justification for an NRC submittal seeking relief from the moderate energy limitation. The RHRSW design pressure is 490 psig.

3.0 TECHNICAL APPROACH The SIA evaluation uses the methodology in ASME Section XI Code Case N-513-3.

4.0 DESIGN INPUTS/ASSUMPTIONS Section 3.0 of the SIA evaluation provides a list of design inputs. The design inputs have been reviewed and are considered acceptable. Section 4.0 provides a list of Assumptions that are considered reasonable.

5.0 EVALUATION Section 5.0 of the SIA evaluation provides the detailed calculations per N-513-3. Review of the calculations as compared to the requirements of N-513-3 are considered acceptable.

Page 3 of 4 ER 2016-053REV. 0

Enclosure 7.a RRS-02, Page 4 of 22 ENGINEERING REPORT HNPPD ER2016-053 COOPER NUCLEAR STATION RHRSW Thinning Evaluation 6.0 RES ULTS/CONCLUSIONS Section 6.0 of the SIA evaluation provides the result of the analysis. Table 4 shows the allowable axial and circumferential through-wall flaw lengths. The most limiting allowable flaw length is 2.2 inches in the axial direction and 3.9 inches in the circumferential direction. The conservatively characterized through-wall flaw is 1.5 inches in the axial and circumferential directions. The allowable flaw size is larger than the conservatively characterized flaw, which satisfies the structural evaluation of Code Case N-513-3.

Section 7 .0 of the SIA evaluation concludes all the flaws meet the N-513-3 separation requirements and are evaluated independently. The evaluation meets ASME Section XI requirements by demonstrating the allowable through-wall flaw lengths bound the conservatively characterized flaws.

The results and conclusions have been reviewed and are considered acceptable.

7 .0 REFERENCES The references in Section 8.0 of SIA Evaluation 1601004.301 have been reviewed and are considered acceptable. Reference 14 in the SIA evaluation has been formally accepted at CNS per ER2016-054.

8.0 ATTACHMENTS 8.1 Structural Integrity Calculation 1601004.301, Rev 0, Cooper High Pressure RHRSW Thinning Evaluation, Dated 12-12-2016 8.2 Attachment 9.3, Engineering Report Technical Review Comments and Resolutions Form Page 4 of 4 ER 2016-053REV. 0