NL-07-067, Submittal of Reactor Vessel Lower Head Inspection Results for Spring 2007 Refueling Outage: Difference between revisions

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| issue date = 05/22/2007
| issue date = 05/22/2007
| title = Submittal of Reactor Vessel Lower Head Inspection Results for Spring 2007 Refueling Outage
| title = Submittal of Reactor Vessel Lower Head Inspection Results for Spring 2007 Refueling Outage
| author name = Dacimo F R
| author name = Dacimo F
| author affiliation = Entergy Nuclear Northeast
| author affiliation = Entergy Nuclear Northeast
| addressee name =  
| addressee name =  
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==Dear Sir or Madam:==
==Dear Sir or Madam:==
Entergy Nuclear Operations, Inc (ENO) is voluntarily providing the Reactor Vessel Lower Head Inspection Report (Attachment  
Entergy Nuclear Operations, Inc (ENO) is voluntarily providing the Reactor Vessel Lower Head Inspection Report (Attachment
: 1) for Indian Point Unit 3 (IP3). The inspection was performed during refueling outage 3R14 that was completed on March 30, 2007. The inspection consisted of a visual examination of the lower head region adjacent to each bottom mounted instrumentation (BMI) penetration including the annulus region between the penetration and the Alloy 600 weld pad.Based on the results of this inspection, ENO concludes that there is no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld (i.e. no"popcorn-like" evidence of boron deposits at the annulus between the penetration and the weld pad).No new commitments are being made in this letter. If you have any questions, please contact Mr. T.R. Jones, Manager, Licensing at (914) 734-6670.Sinc ely, rred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-286 NL-07-067 Page 2 of 3 Attachment 1 (Reactor Vessel Lower Head Inspection Results; Indian Point Unit 3, Spring 2007 Refueling Outage (3R14))cc: see next page Docket No. 50-286 NL-07-067 Page 3 of 3 cc: Mr. John P. Boska, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Resident Inspector's Office Indian Point Unit 3 Nuclear Power Plant U.S. Nuclear Regulatory Commission Mr. Paul Eddy New York State Dept. of Public Service ATTACHMENT 1 TO NL-07-067 REACTOR VESSEL LOWER HEAD INSPECTION RESULTS;INDIAN POINT UNIT 3, SPRING 2007 REFUELING OUTAGE (3R14)ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 Docket No. 50-286 NL-07-067 Attachment 1 Page 1 of 2 REACTOR VESSEL LOWER HEAD INSPECTION RESULTS;INDIAN POINT UNIT 3, SPRING 2007 REFUELING OUTAGE (3R14)(1) Summary of Inspections Performed During the recently completed 3R14 refueling outage, Indian Point Unit 3 (IP3)performed a bare metal visual (BMV) examination of the lower head region adjacent to each of the 58 lower head penetrations including 3600 of the annulus region between the penetration and the Alloy 600 weld pad.(2) Extent of the Inspections As discussed in item (1) above, each of the 58 lower RPV head penetrations were inspected including the Alloy 600 weld pad and 3600 of the annulus between the penetration and the weld pad.(3) Method Used This inspection was a visual examination performed with remote video equipment and provided a resolution equivalent to the ASME Section Xl VT-2 requirements as a minimum. The inspection results were reviewed by certified VT-2 personnel meeting the requirements of ASME Section Xl.(4) Description of the As-Found Condition of the Lower Head The inspections were performed in the beginning of the refueling outage (i.e. prior to refueling operations) and identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld (i.e. no "popcorn-like" evidence of boron deposits at the annulus between the penetration and the weld pad). No penetrations were identified with boron residue at or adjacent to the annulus region.(5) Findings of Relevant Indications of Through Wall Leakage The inspections performed during 3R14 identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld.(6) Summary of the Disposition of any Findings of Boric Acid Deposits and any Corrective Actions taken as a Result of Indications Found As discussed above, the inspections performed during 3R14 identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld. No penetrations were identified with boron residue at or adjacent to the annulus region. No corrective actions were necessary as a result of these inspections.
: 1) for Indian Point Unit 3 (IP3). The inspection was performed during refueling outage 3R14 that was completed on March 30, 2007. The inspection consisted of a visual examination of the lower head region adjacent to each bottom mounted instrumentation (BMI) penetration including the annulus region between the penetration and the Alloy 600 weld pad.Based on the results of this inspection, ENO concludes that there is no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld (i.e. no"popcorn-like" evidence of boron deposits at the annulus between the penetration and the weld pad).No new commitments are being made in this letter. If you have any questions, please contact Mr. T.R. Jones, Manager, Licensing at (914) 734-6670.Sinc ely, rred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-286 NL-07-067 Page 2 of 3 Attachment 1 (Reactor Vessel Lower Head Inspection Results; Indian Point Unit 3, Spring 2007 Refueling Outage (3R14))cc: see next page Docket No. 50-286 NL-07-067 Page 3 of 3 cc: Mr. John P. Boska, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Resident Inspector's Office Indian Point Unit 3 Nuclear Power Plant U.S. Nuclear Regulatory Commission Mr. Paul Eddy New York State Dept. of Public Service ATTACHMENT 1 TO NL-07-067 REACTOR VESSEL LOWER HEAD INSPECTION RESULTS;INDIAN POINT UNIT 3, SPRING 2007 REFUELING OUTAGE (3R14)ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 Docket No. 50-286 NL-07-067 Attachment 1 Page 1 of 2 REACTOR VESSEL LOWER HEAD INSPECTION RESULTS;INDIAN POINT UNIT 3, SPRING 2007 REFUELING OUTAGE (3R14)(1) Summary of Inspections Performed During the recently completed 3R14 refueling outage, Indian Point Unit 3 (IP3)performed a bare metal visual (BMV) examination of the lower head region adjacent to each of the 58 lower head penetrations including 3600 of the annulus region between the penetration and the Alloy 600 weld pad.(2) Extent of the Inspections As discussed in item (1) above, each of the 58 lower RPV head penetrations were inspected including the Alloy 600 weld pad and 3600 of the annulus between the penetration and the weld pad.(3) Method Used This inspection was a visual examination performed with remote video equipment and provided a resolution equivalent to the ASME Section Xl VT-2 requirements as a minimum. The inspection results were reviewed by certified VT-2 personnel meeting the requirements of ASME Section Xl.(4) Description of the As-Found Condition of the Lower Head The inspections were performed in the beginning of the refueling outage (i.e. prior to refueling operations) and identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld (i.e. no "popcorn-like" evidence of boron deposits at the annulus between the penetration and the weld pad). No penetrations were identified with boron residue at or adjacent to the annulus region.(5) Findings of Relevant Indications of Through Wall Leakage The inspections performed during 3R14 identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld.(6) Summary of the Disposition of any Findings of Boric Acid Deposits and any Corrective Actions taken as a Result of Indications Found As discussed above, the inspections performed during 3R14 identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld. No penetrations were identified with boron residue at or adjacent to the annulus region. No corrective actions were necessary as a result of these inspections.
Docket No. 50-286 NL-07-067 Attachment 1 Page 2 of 2 References
Docket No. 50-286 NL-07-067 Attachment 1 Page 2 of 2 References
: 1. NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity", dated August 21, 2003 2. Entergy letter to NRC (NL-03-178);  
: 1. NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity", dated August 21, 2003 2. Entergy letter to NRC (NL-03-178);  
"90-Day Response to NRC Bulletin 2003-02 Regarding Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity", dated November 13, 2003}}
"90-Day Response to NRC Bulletin 2003-02 Regarding Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity", dated November 13, 2003}}

Revision as of 23:30, 12 July 2019

Submittal of Reactor Vessel Lower Head Inspection Results for Spring 2007 Refueling Outage
ML071510183
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 05/22/2007
From: Dacimo F
Entergy Nuclear Northeast
To:
Document Control Desk, NRC/NRR/ADRO
References
FOIA/PA-2009-0192, NL-07-067
Download: ML071510183 (6)
v • d • e


Text

Enter-qy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Fred Dacimo Site Vice President Tel 914 734 6700 May 22, 2007 Re: Indian Point Unit 3 Docket No. 50-286 NL-07-067 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

Reactor Vessel Lower Head Inspection Results;Indian Point Unit 3. Spring 2007 Refueling Outage (3R14)

Dear Sir or Madam:

Entergy Nuclear Operations, Inc (ENO) is voluntarily providing the Reactor Vessel Lower Head Inspection Report (Attachment

1) for Indian Point Unit 3 (IP3). The inspection was performed during refueling outage 3R14 that was completed on March 30, 2007. The inspection consisted of a visual examination of the lower head region adjacent to each bottom mounted instrumentation (BMI) penetration including the annulus region between the penetration and the Alloy 600 weld pad.Based on the results of this inspection, ENO concludes that there is no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld (i.e. no"popcorn-like" evidence of boron deposits at the annulus between the penetration and the weld pad).No new commitments are being made in this letter. If you have any questions, please contact Mr. T.R. Jones, Manager, Licensing at (914) 734-6670.Sinc ely, rred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-286 NL-07-067 Page 2 of 3 Attachment 1 (Reactor Vessel Lower Head Inspection Results; Indian Point Unit 3, Spring 2007 Refueling Outage (3R14))cc: see next page Docket No. 50-286 NL-07-067 Page 3 of 3 cc: Mr. John P. Boska, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Resident Inspector's Office Indian Point Unit 3 Nuclear Power Plant U.S. Nuclear Regulatory Commission Mr. Paul Eddy New York State Dept. of Public Service ATTACHMENT 1 TO NL-07-067 REACTOR VESSEL LOWER HEAD INSPECTION RESULTS;INDIAN POINT UNIT 3, SPRING 2007 REFUELING OUTAGE (3R14)ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 Docket No. 50-286 NL-07-067 Attachment 1 Page 1 of 2 REACTOR VESSEL LOWER HEAD INSPECTION RESULTS;INDIAN POINT UNIT 3, SPRING 2007 REFUELING OUTAGE (3R14)(1) Summary of Inspections Performed During the recently completed 3R14 refueling outage, Indian Point Unit 3 (IP3)performed a bare metal visual (BMV) examination of the lower head region adjacent to each of the 58 lower head penetrations including 3600 of the annulus region between the penetration and the Alloy 600 weld pad.(2) Extent of the Inspections As discussed in item (1) above, each of the 58 lower RPV head penetrations were inspected including the Alloy 600 weld pad and 3600 of the annulus between the penetration and the weld pad.(3) Method Used This inspection was a visual examination performed with remote video equipment and provided a resolution equivalent to the ASME Section Xl VT-2 requirements as a minimum. The inspection results were reviewed by certified VT-2 personnel meeting the requirements of ASME Section Xl.(4) Description of the As-Found Condition of the Lower Head The inspections were performed in the beginning of the refueling outage (i.e. prior to refueling operations) and identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld (i.e. no "popcorn-like" evidence of boron deposits at the annulus between the penetration and the weld pad). No penetrations were identified with boron residue at or adjacent to the annulus region.(5) Findings of Relevant Indications of Through Wall Leakage The inspections performed during 3R14 identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld.(6) Summary of the Disposition of any Findings of Boric Acid Deposits and any Corrective Actions taken as a Result of Indications Found As discussed above, the inspections performed during 3R14 identified no evidence of leakage resulting from a breach of the lower head penetrations or the attaching j-groove weld. No penetrations were identified with boron residue at or adjacent to the annulus region. No corrective actions were necessary as a result of these inspections.

Docket No. 50-286 NL-07-067 Attachment 1 Page 2 of 2 References

1. NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity", dated August 21, 2003 2. Entergy letter to NRC (NL-03-178);

"90-Day Response to NRC Bulletin 2003-02 Regarding Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity", dated November 13, 2003

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