LR-N07-0279, Response to Request for Additional Information, Relief Request HC-RR-I2-W02, Proposed Alternative Repair Method: Difference between revisions

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{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 1 OCFR50.55a OCT 2 9 2007 LR-N07-0279 0 PSEG Nuclear LLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354  
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 10CFR50.55a OCT 2 9 2007 LR-N07-0279                                                                         0 PSEG Nuclear LLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354


==Subject:==
==Subject:==
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION, RELIEF REQUEST HC-RR-12-W02 PROPOSED ALTERNATIVE REPAIR METHOD  
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION, RELIEF REQUEST HC-RR-12-W02 PROPOSED ALTERNATIVE REPAIR METHOD


==References:==
==References:==
(1) PSEG Letter LR-N07-0273 RELIEF REQUEST HC-RR-12-W02 PROPOSED ALTERNATIVE REPAIR METHOD Dated: October 19, 2007 In Reference 1, PSEG Nuclear LLC (PSEG) proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components. This proposed alternative would permit the use of a full structural weld overlay repair for an indication identified in the N2A recirculation inlet nozzle safe-end to nozzle weld joint.
On October 24, 2007, the NRC provided PSEG a draft Request for Additional Information (RAI) on the Reference 1 submittal. PSEG and the NRC discussed the draft RAI in a conference call on October 25, 2007. The response to the RAI is provided in the attachment to this letter.
If you have any questions or require additional information, please contact Mr. Philip J.
Duca at (856) 339-1640.
Sinc George P. Barnes Site Vice President - Hope Creek Attachment                                                                                      4-7 95-2168 REV. 7/99


(1) PSEG Letter LR-N07-0273 RELIEF REQUEST HC-RR-12-W02 PROPOSED ALTERNATIVE REPAIR METHOD Dated: October 19, 2007 In Reference 1, PSEG Nuclear LLC (PSEG) proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components.
Document Control Desk                    -2  -
This proposed alternative would permit the use of a full structural weld overlay repair for an indication identified in the N2A recirculation inlet nozzle safe-end to nozzle weld joint.On October 24, 2007, the NRC provided PSEG a draft Request for Additional Information (RAI) on the Reference 1 submittal.
LR-N07-0279 CC   Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 Mr. P. Mulligan Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 USNRC Senior Resident Inspector - Hope Creek (X24)
PSEG and the NRC discussed the draft RAI in a conference call on October 25, 2007. The response to the RAI is provided in the attachment to this letter.If you have any questions or require additional information, please contact Mr. Philip J.Duca at (856) 339-1640.Sinc George P. Barnes Site Vice President
 
-Hope Creek Attachment 4-7 95-2168 REV. 7/99 Document Control Desk LR-N07-0279 CC Mr. S. Collins, Administrator  
Document Control Desk   LR-N07-0279 ATTACHMENT (2 Pages)
-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 Mr. P. Mulligan Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 USNRC Senior Resident Inspector  
 
-Hope Creek (X24)
Attachment LR-N07-0279 RESPONSE TO RAI #1 FOR RELIEF REQUEST HC-RR-12-W02 NRC RAI #1: PSEG has stated that the weld overlay of the safe end-to-nozzle weld may require welding on more than 100 square inches of surface on the low alloy steel base material. The NRC has not approved any request over 300 square inches. What is the maximum area of the P-3 material that will be welded on? This should be stated in Relief Request HC-RR-12-W02. The Relief Request mentions 500 square inches, but not as the maximum that is to be welded on during this welding.
Document Control Desk LR-N07-0279 ATTACHMENT (2 Pages)
PSEG RESPONSE:
Attachment LR-N07-0279 RESPONSE TO RAI #1 FOR RELIEF REQUEST HC-RR-12-W02 NRC RAI #1: PSEG has stated that the weld overlay of the safe end-to-nozzle weld may require welding on more than 100 square inches of surface on the low alloy steel base material.
Total area of coverage over P3 material (using 3.55" length of overlay measured from nozzle/buttering HAZ to last bead on nozzle, see Figure 1):
The NRC has not approved any request over 300 square inches. What is the maximum area of the P-3 material that will be welded on? This should be stated in Relief Request HC-RR-12-W02.
Neglecting the slight curvature of 14" O.D. nozzle; 3.55" from nozzle HAZ to toe of last bead on P3 material; 14" X 3.14 X 3.55" - 160 in2 of overlay surface area
The Relief Request mentions 500 square inches, but not as the maximum that is to be welded on during this welding.PSEG RESPONSE: Total area of coverage over P3 material (using 3.55" length of overlay measured from nozzle/buttering HAZ to last bead on nozzle, see Figure 1): Neglecting the slight curvature of 14" O.D. nozzle; 3.55" from nozzle HAZ to toe of last bead on P3 material; 14" X 3.14 X 3.55" -160 in 2 of overlay surface area Attachment LR-N07-0279 Figure 1 N2A actual field measurements on P3 area Neglecting the sliqht curvature of 14" O.D. nozzle;3.55" from nozzle HAZ to toe of last bead on P3 material;14" X 3.14 X 3.55" = 160 in 2 of overlay surface area Not To Scale 2}}
 
Attachment LR-N07-0279 Figure 1 N2A actual field measurements on P3 area Neglecting the sliqht curvature of 14" O.D. nozzle; 3.55" from nozzle HAZ to toe of last bead on P3 material; 14" X 3.14 X 3.55" = 160 in2 of overlay surface area Not To Scale 2}}

Revision as of 01:09, 23 November 2019

Response to Request for Additional Information, Relief Request HC-RR-I2-W02, Proposed Alternative Repair Method
ML073100369
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 10/29/2007
From: Barnes G
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HC-RR-I2-W02, LR-N07-0279
Download: ML073100369 (5)
v • d • e


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 10CFR50.55a OCT 2 9 2007 LR-N07-0279 0 PSEG Nuclear LLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354

Subject:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION, RELIEF REQUEST HC-RR-12-W02 PROPOSED ALTERNATIVE REPAIR METHOD

References:

(1) PSEG Letter LR-N07-0273 RELIEF REQUEST HC-RR-12-W02 PROPOSED ALTERNATIVE REPAIR METHOD Dated: October 19, 2007 In Reference 1, PSEG Nuclear LLC (PSEG) proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components. This proposed alternative would permit the use of a full structural weld overlay repair for an indication identified in the N2A recirculation inlet nozzle safe-end to nozzle weld joint.

On October 24, 2007, the NRC provided PSEG a draft Request for Additional Information (RAI) on the Reference 1 submittal. PSEG and the NRC discussed the draft RAI in a conference call on October 25, 2007. The response to the RAI is provided in the attachment to this letter.

If you have any questions or require additional information, please contact Mr. Philip J.

Duca at (856) 339-1640.

Sinc George P. Barnes Site Vice President - Hope Creek Attachment 4-7 95-2168 REV. 7/99

Document Control Desk -2 -

LR-N07-0279 CC Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 Mr. P. Mulligan Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 USNRC Senior Resident Inspector - Hope Creek (X24)

Document Control Desk LR-N07-0279 ATTACHMENT (2 Pages)

Attachment LR-N07-0279 RESPONSE TO RAI #1 FOR RELIEF REQUEST HC-RR-12-W02 NRC RAI #1: PSEG has stated that the weld overlay of the safe end-to-nozzle weld may require welding on more than 100 square inches of surface on the low alloy steel base material. The NRC has not approved any request over 300 square inches. What is the maximum area of the P-3 material that will be welded on? This should be stated in Relief Request HC-RR-12-W02. The Relief Request mentions 500 square inches, but not as the maximum that is to be welded on during this welding.

PSEG RESPONSE:

Total area of coverage over P3 material (using 3.55" length of overlay measured from nozzle/buttering HAZ to last bead on nozzle, see Figure 1):

Neglecting the slight curvature of 14" O.D. nozzle; 3.55" from nozzle HAZ to toe of last bead on P3 material; 14" X 3.14 X 3.55" - 160 in2 of overlay surface area

Attachment LR-N07-0279 Figure 1 N2A actual field measurements on P3 area Neglecting the sliqht curvature of 14" O.D. nozzle; 3.55" from nozzle HAZ to toe of last bead on P3 material; 14" X 3.14 X 3.55" = 160 in2 of overlay surface area Not To Scale 2

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