ML15016A115

Response to Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations

ML15016A115
Person / Time
Site:	Pilgrim
Issue date:	01/08/2015
From:	Perkins E Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.15.001, TAC MF4187
Download: ML15016A115 (6)

Text

SEntergy Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 January 8, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Response to Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations (TAC No. MF4187)

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35

REFERENCE:

LETTER NUMBER:

Dear Sir or Madam:

NRC Letter to Energy, "Pilgrim Nuclear Power Station - Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations (TAC No. MF4187),

dated December 17, 2014 (NRC Letter 1.14.085) 2.15.001 Pursuant to the request by the U.S. Nuclear Regulatory Commission 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.

Sincerely, Everett P. (Chip) Perkin-s Regulatory Assurance Manager EPP/pjm : Response to Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations (TAC No.

MF4187)

Letter Number: 2.15.001 Page 2 of 2 cc:

Mr. Daniel Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-1415 Ms. Nadiyah Morgan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission MS O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station

Attachment I To PNPS Letter 2.15.001 Response to Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations (TAC No. MF4187)

Letter Number: 2.15.001 RAI-PRR-24 Page 1 of 3 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Request for Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

PNPS 4 th Interval ISl Program Request No. PRR-24 Response to Request for Additional Information - Attachment I NRC Request 1 Please verify and state the specific values for the RPV inner radius and wall thickness provided in proposed alternative PRR-24. Also, explain why there is an inconsistency between the values provided in the BWRVIP-108 and BWRVIP-241 reports, and those provided in your March 12, 2014, letter. If the current submission is based on incorrect geometry information, please revise it.

Response

The value provided in proposed alternative PRR-24 and Table 2-1 of BWRVIP-241 for the RPV wall thickness is [6.5] inches. The value provided in BWRVIP-1 08, Table 3-1 for the RPV wall thickness is [5.531] inches. The value provided in BWRVIP-241 Section 4.1 on page 4-1 for the RPV wall thickness is [7] inches.

The March 12, 2014 Request for Alternative is based on correct geometry information. The specific values for the RPV inner radius [113.4063] inches and wall thickness [6.5] inches that were provided in the proposed alternative PRR-24 are the values that were used in the calculations in BWRVIP-241 as well as PRR-24. The value of-[6.5] inches is the minimum wall thickness of the lower shell course where the recirculation inlet nozzles are located.

The inconsistency in the reported values is in the BWRVIP-241 report on page 4-1 section 4.1 and figure 4-1, on page 4-12 which lists the wall thickness as [7] inches is a typographic error.

The value provided in BWRVIP-108 of [5.531] inches was taken from upper and lower intermediate shell course values, when it should have been the lower shell course. The value used in the calculations was the correct value [6.5] inches as shown on Pilgrim Nuclear Power Station design drawings.

Letter Number: 2.15.001 RAI-PRR-24 Page 2 of 3 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Request for Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

PNPS 4h Interval ISI Program Request No. PRR-24 Response to Request for Additional Information - Attachment I NRC Request 2 Please provide a list of what inspections have already been performed on the Recirculation Inlet nozzle-to-vessel welds and inner radius sections listed in Attachment 1 of PRR-24, for which this alternative is requested. Also, describe any indications that were found and how these indications were dispositioned.

Response

Table of ASME Code Components Affected at PNPS Component ID Description Code Category Code Item Inspections Indications (see notes below)

RPV-N2A-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1977,1984, 1977 (note 1),

1999, 2009 1984 (note 6)

RPV-N2A-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1977,1984, NRI 1999, 2009 RPV-N2B-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1980,1984, 1984 (note 7) 1999, 2009 RPV-N2B-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1980,1984, NRI 1999, 2009 RPV-N2C-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1974,1984, NRI 1999, 2009 RPV-N2C-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1974,1984, NRI 1999, 2009 RPV-N2D-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1974, 1995, 2003 NRI RPV-N2D-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1974,1995, 2003 NRI RPV-N2E-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1980, 1995, 2003 1980 (note 3)

RPV-N2E-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1980,1995 2003 NRI RPV-N2F-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1977,1982, 1977 (note 2) 1995, 2003

Letter Number: 2.15.001 RAI-PRR-24 Page 3 of 3 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Request for Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

PNPS 4 th Interval ISl Program Request No. PRR-24 Response to Request for Additional Information - Attachment 1 RPV-N2F-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1977, 1982, NRI 1995, 2003 RPV-N2G-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1977, 1993, 2005 2005 (note 8)

RPV-N2G-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1977, 1993, 2005 NRI RPV-N2H-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1980,1993, 2005 1980 (note 4),

2005 (note 9)

RPV-N2H-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1980,1993, 2005 NRI RPV-N2K-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.90 1981,1993, 2005 2005 (note10)

RPV-N2K-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.100 1981,1993,2005 NRI RPV-N2J-NIR 12" Recirc Inlet Nozzle to Inner Radius B-D B3.90 1980,1995, 2003 NRI RPV-N2J-NV 12" Recirc Inlet Nozzle to Vessel Weld B-D B3.100 1980,1995, 2003 1980 (note 5)

Notes:

1. N2A (NV) - 1977, Code acceptable slag inclusions - acceptable.

2.

N2F (NV) - 1977, Code acceptable reflectors were observed - acceptable.

3.

N2E (NV) - 1980, Geometric reflectors - acceptable.

4. N2H (NV) - 1980, Indications are geometric reflectors from the nozzle ID surface - acceptable.

5.

N2J (NV) - 1980, Indications are geometric reflectors from the nozzle ID surface - acceptable.

6.

N2A (NV) - 1984, Reflectors were seen, same inclusion as 1977 no change in size - acceptable.

7.

N2B (NV) - 1984, Indications found but are allowable and not recordable - acceptable.

8.

N2G (NV) - 2005, (3) indications, were acceptable per requirements of ASME Section Xl.

9. N2H (NV) - 2005, (4) indications, were acceptable per requirements of ASME Section XI

10. N2K (NV) - 2005, (3) indications were acceptable per the requirements of ASME Section Xl