ML16333A005
| ML16333A005 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/18/2016 |
| From: | Perkins E Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.16.072, CAC MF8095, CAC MF8096, PNPS-ISl-004, PNPS-ISl-005 | |
| Download: ML16333A005 (8) | |
Text
- ~-* EntergY.
November 18, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. MA 02360
SUBJECT:
Response to Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISl-004 & 005 (CAC NO. MF8095 and MF8096)
Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35
REFERENCE:
NRC to Entergy Transmittal, "Pilgrim: Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISl-004 & 005 (CAC NO.
MF8095 and 8096)" (1.16.057)
LETTER NUMBER: 2.16.072
Dear Sir or Madam:
Pursuant to the request by the U.S. Nuclear Regulatory Commission Staff for additional information contained in the Reference, please find attached the Pilgrim Nuclear Power Station response.
{
Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have any questions.
There are no ~egulatory commitments included in this letter.
Sincerely, Everett P. Pe~~ p ~)s Manager, Regulatory Assurance EPP/mw Attachments:
- 1. Response to Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISl-004
- 2. Response to Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISl-005
(
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station cc:
Mr. Daniel H. Dorman Regional Administr~tor, Region I
.U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Letter No. 2.16.072 Page 2 of 2 to Letter Number 2.16.072 Response to Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISl-004 (1 Page) to Letter No. 2.16.072 Page 1 of 1 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST ON VOLUMETRIC EXAM REQUIREMENTS, PNPS-ISI- 004 PILGRIM NUCLEAR POWER STATION ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-293 (CAC NO. MF8095)
Request for Additional Information CRAil 1 Please describe the relevant Editions and Addenda of ASME Code Section XI that apply to Appendix VIII and non-Appendix VIII examinations.
Response to RAI 1 All the welds listed were performed as Appendix VIII examinations using the ASME Code and Addenda as listed on the following table.
Cat Item Comp ID Date ASME Edition Item Description NO Performed C-F-1 C5.11 DC 4/25/2011 01 Edition w/03 Pipe-to-Valve Weld, Line # 18"-
F10R Addenda GB-10 C-F-1 C5.11 DC-14-F31 5/6/2009 98 Edition w/00 Pipe-to-Valve Weld, Line# 10-DC-Addenda 14 RAl2 Please describe the specific systems associated with welds DC-10-F10R and DC-14-F31.
Response to RAI 2 DC-10-F10R is associated with the Residual Heat Removal System.
DC-14-F31 is associated with the Core Spray System.
to Letter Number 2.16.072 Response to Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISl-005 (3 Pages)
l to Letter No. 2.16.072 Page 1 of 3 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST ON VOLUMETRIC EXAM REQUIREMENTS, PNPS-ISI- 005 PILGRIM NUCLEAR POWER STATION ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-293 (CAC NO. MF8096)
Request for Additional Information CRAil 1 Please describe the relevant Editions and Addenda of ASME Code Section XI that apply to Appendix VIII and non-Appendix VIII examinations.
Response to RAI 1 All the welds listed were performed as Appendix VIII examinations using the ASME Code and Addenda as listed on the following table.
Cat Item Comp ID Date ASME Item Description No.
Performed Edition 98 Edition R-A R1.20 2R-HB-3 4/22/2009 w/00 Cross-to-Header Weld, Line# 22"-DCA-2
~
Addenda 01 Edition R-A R1.20 12-0-24 4/26/2011 w/03 Pipe-to-Flued Head Weld Addenda 01 Edition R-A R1.20 14-A-10A 4/28/2011 w/03 Valve-to-Pipe DM Weld Addenda 01 Edition R-A R1.20 14-B-10A 4/25/2011 w/03 Valve-to-Pipe DM Weld, Line# 1 O"-DBA-14 Addenda 01 Edition R-A R1.11 10R-IA-6 4/28/2011 w/03 Pipe-to-Valve Weld, Line# 18"-DCA-10 Addenda 01 Edition R-A R1.11 10R-IA-7 4/28/2011 w/03 Valve-to-Pipe Weld, Line# 18"-DCA-10 Addenda 98 Edition R-A R1.20 10R-IB-14 4/22/2009 w/00 Pipe-to-Flued Head Weld Addenda 01 Edition R-A R1.20 14R-A-11 4/27/2015 w/03 Pipe-to-Valve Weld, Line# JO"-DBA-14 Addenda to Letter No. 2.16.072
- Page 2 of 3 Please describe the specific systems associated with welds 2R-HB-3, 12-0-24, 10R-IB-14, and 14R-A-1.
Response to RAI 2 2R-HB-3 is associated with the Recirculation System.
12-0-24 is associated with the Reactor Water Clean-Up System.
10R-IB-14 is associated with the Residual Heat Removal System.
14R-A-11 is associated with the Core Spray System.
The coverage diagrams supplied for welds 14-A-10A and 14-B-10A do not appear to be consistent with the claimed code coverage of 50 percent. Please describe how the 50 percent code coverage was determined.
Response to RAI 3 Table 5-1 of the Relief Request submittal was in error. The correct code coverage obtained was properly documented on the data sheet as follows:
14-A-10A-28.4% CRY obtained.
14-B-10A-24.2% CRY obtained.
Please discuss the operational experience for the other core spray dissimilar metal welds and the results of other dissimilar metal core spray weld inspections.
Response to RAI 4 There are four (4) other Core Spray dissimilar metal welds and the results.of these inspections are shown below. There was no leakage, repairs or evaluations for acceptability for continued service on any of these weld inspections.
Weld ID Exam Results Comments RFO NRI I Auto PA +
Limited Coverage 93.9% PRV/
14-A-3 Manual I Acceptable I 97.6% CRV 18 Limited 100% Axial I 95.2% Circumferential NRI I Auto PA +
Limited Coverage 92.5%
14-8-3 Manual I Acceptable I PRV/96.6% CRV 18 Limited 93.2% Axial /100% Circumferential DB/DC-14-3002-5-1 Acceptable 100% CRV 18 DB/DC-14-3001-4-1 Acceptable 100% CRV 18 to Letter No. 2.16.072 Page 3 of 3.
Please describe any surface examinations performed on welds 14-A-10A and 14-B-10A.
Response to RAI 5 These welds are Category R-A, Item R1.20 - A surface exam is not required.