ML11255A127

Transmittal of 2011 Owners Activity Report for the R. E. Ginna Nuclear Power Plant

ML11255A127
Person / Time
Site:	Ginna
Issue date:	08/30/2011
From:	-Neednewvalue, Mogren T Constellation Energy Group, EDF Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11255A127 (10)

Text

Thomas Mogren Manager - Engineering Services CENG a joint venture of Energ00 R.E. Ginna Nuclear Power Plant LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.5208 585.771.3392 Fax Thomas.Mogren@cengllc.com August 30, 2011 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 Transmittal of 2011 Owner's Activity Report for the R.E. Ginna Nuclear Power Plant Enclosed is a copy of the R.E. Ginna Owner's Activity Report for the refueling outage conducted in 2011.

This report is submitted as specified by ASME Code Section XI.

There are no regulatory commitments contained in this letter. Should you have questions regarding this matter, please contact Thomas Harding (585) 771-5219, or Thomas.HardingJrcengllc.corn.

Very truly yours, Thomas Mogre2

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Attachment:

(1) FIFTH INSERVICE INSPECTION (ISI) INTERVAL and SECOND CONTAINMENT INSPECTION INTERVAL, FIRST INSPECTION PERIOD, 2011 OWNER'S ACTIVITY REPORT FOR RFO-35 INSERVICE EXAMINATIONS, (April 23, 2011 through June 9, 2011) cc:

W.M. Dean, NRC D.V. Pickett, NRC Resident Inspector, NRC (Ginna)

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CENG a joint venture of FIFTH INSERVICE INSPECTION (ISI) INTERVAL and SECOND CONTAINMENT INSPECTION INTERVAL FIRST INSPECTION PERIOD 2011 OWNER'S ACTIVITY REPORT FOR RFO-35 INSERVICE EXAMINATIONS (April 23, 2011 through June 9, 2011)

For R. E. Ginna Nuclear Power Plant

.1503 Lake Road Ontario, NY 14519 Commercial Service Date:

June 1, 1970 NRC Docket Number:

50-244 Revision Number:

00 Date:

August 11, 2011 Prepared by:

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Frank A. Klepacki - Site ISI Prografn Owner - R E Ginna Reviewed by:

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/i, Bernie C. Rudell -Principal Eriginee - CENG Fleet Engineering Programs Approved by:

&LLkk W)/11/1 Ja Ii! - General Supervisor - Engineering Programs - R E Ginna

R. E. Ginna Nuclear Power Plant, Unit 1 1NI 5 th Interval Inservice Inspection and Rev.

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0811112011 2 nd Interval Containment Inservice a joint venture of Inspection Date: 0811/2011 On-4u:"

'eDF 2011 OWNER'S ACTIVITY REPORT Page i-2 of i -9 FOR INSERVICE EXAMINATIONS TABLE OF CONTENTS T a b le o f C o nte nts.............................................................................................................

i-2 A b s tra c t................................................................................................................................................

i-3 Form OAR-1 Owner's Activity Report for Fourth Interval Inservice Inspection Plan.......................

i-4 Form OAR-1 Owner's Activity Report for Fifth Interval Inservice Inspection Plan.........................

i-5 Form OAR-1 Owner's Activity Report for Containment Second Interval Inservice Inspection Plan... i-6 Table 1 Items with Flaws or Relevant Conditions that Require Evaluation for Continued Service..... i-7 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service..........................

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R. E. Ginna Nuclear Power Plant, Unit I C

E N

5 th Interval Inservice Inspection and Rev.

00 vENtr o 2 nd Interval Containment Inservice a joint venture of Inspection Date: 08/1112011 O r-eatk 7-, eDF 2011 OWNER'S ACTIVITY REPORT Page i-3 of 1-9 FOR INSERVICE EXAMINATIONS ABSTRACT This Owner's Activity Report (OAR) summarizes the results of the R. E. Ginna Nuclear Power Plant (GNPP),

Unit 1, American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection Examinations performed during the 2011 Refueling Outage (RFO), from April 23, 2011 through June 9, 2011. The OAR is for the Fifth Interval Inservice Inspection Program, First Period and the Second Interval Containment Inservice Inspection Program, First Period. This report also covers associated Reactor Pressure Vessel (RPV) Fourth Interval examinations that were deferred in accordance with the Fourth Interval Relief Request Numbers 18, 19, 20 and 21. The RPV examinations were performed in accordance with ASME Section Xl Code, 1995 Edition with the 1996 Addenda. The First Interval Containment Inservice Inspection Program was extended to align with the ISI Program interval in accordance with the Fourth Interval Inservice Inspection Program Relief Request Number 22.

As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC),Section XI, Article IWA-6000, GNPP has implemented ASME Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1". ASME Code Case N-532-4 is approved for use in Regulatory Guide 1.147. This Report complies with the requirements of Code Case N-532-4.

OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner's Activity Reports Form OAR-I's were prepared and certified upon completion of the GNPP Unit 1, 2011 refueling outage RFO-35 examination activity in accordance with the following inspection plans and schedules:

Inservice Inspection Program Plan(s) for the Fifth Inspection Interval for GNPP Unit 1 Long Term Plan for GNPP, Unit 1 ISI Program Plan ASME Xl, IWE/IWL Second Inspection Interval In addition to the Owner's Activity Report, Form OAR-i, the following Tables are also included:

a.

Items with Flaws or Relevant Conditions that Require Evaluation for Continued Service, Table 1, provides a listing of item(s) with inservice flaws or relevant conditions that required evaluation to determine acceptability for continued service, whether or not the flaw or relevant condition was discovered during a scheduled examination or test, and provides such information as Examination Category, Examination Item Number, Item Description, Flaw Characterization (as required by IWA-3300).

b.

Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 2, identifies those items containing flaws or relevant conditions that exceeded the ASME Section XI acceptance criteria IWX-3000. In the case of supports, the acceptance criteria is IWF-3000. The discovery of the flaw or relevant condition that necessitated the repair, replacement or corrective measure, may not have resulted from an examination or test required by Section Xl Code. Table 2 provides information such as Code Class, whether the item is a repair, replacement or corrective action, item description, description of work, if the flaw or relevant condition was found during a scheduled Section Xl Examination or test, date completed and the repair replacement plan number.

R. E. Ginna Nuclear Power Plant, Unit 1 1f i

5th Interval Inservice Inspection and Rev.

00 C E N G l

2 nd Interval Containment Inservice a joint venture of Inspection Date: 081112011 O

-atio 0,,eDF 2011 OWNER'S ACTIVITY REPORT Page i-4 of i -9 FOR INSERVICE EXAMINATIONS FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-4 Report Number GNPP-OAR-ISI-RPV-2011 Plant R. E. Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, New York 14519 (Name and Address of Plant)

Unit No.

1 Commercial Service Date June 1. 1970 Refueling Outage Number RFO-35 Current Inspection Interval Fourth Inservice Inspection Interval - January 1. 2000 to June 9. 2011.

(1st, 2nd, 3rd, 4th, Other)

Current Inspection Period Third Inservice Inspection Period -

January 1. 2007 to June 9, 2011 (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the Inspection Plan 1995 Edition, 1996 Addenda Date and Revision of Inspection Plan 4 October 2010. Revision 1 Edition and Addenda of ASME Section XI applicable to repairs/replacements, if different than the Inspection Plan N/A Code Cases used:

N-532-4. N-695, CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting completion of 2011 RFO (RFO-35) conform to the requirements of Section XI.

Certificate of Authorization No.

Signed Frank A Klepacki N/A Expiration Date N/A Date 0

//

N/A (Site ISI Program Owner) f CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by Hartford Steam Boiler (HSBCT) of Hartford. Connecticut have inspected the items described in this Owners Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any rsonal injury or perty damage or a loss of any kind arising from or connected with this inspection.

Bruce SawYer X

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Commissions NB10496. A. N. I: New York 4077 Inspector's Signature I

National Board, State, Province, and Endorsements Date g//,/,7_O//

R. E. Ginna Nuclear Power Plant, Unit 1 E

I 5th Interval Inservice Inspection and Rev.

00 2 nd Interval Containment Inservice a joint venture of Inspection Date: 08/1112011 Oe 1 0'eDF 2011 OWNER'S ACTIVITY REPORT Page i-5 of i -9 FOR INSERVICE EXAMINATIONS FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-4 Report Number GNPP-OAR-ISI-2011 Plant R. E. Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, New York 14519 (Name and Address of Plant)

Unit No.

1 Commercial Service Date June 1. 1970 Refueling Outage Number RFO-35 Current Inspection Interval Fifth Inservice Inspection Interval - January 1. 2010 to December 31, 2019.

(1st, 2nd, 3rd, 4th, Other)

Current Inspection Period First Inservice Inspection Period -

January 1. 2010 to December 31. 2012 (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the Inspection Plan 2004 Edition, No Addenda Date and Revision of Inspection Plan 4 October 2010. Revision I Edition and Addenda of ASME Section XI applicable to repairs/replacements, if different than the Inspection Plan N/A Code Cases used:

N-532-4. N-648-1. N-706, N-716, N-722, N-729-1 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting completion of 2011 RFO (RFO-35) conform to the requirements of Section XI.

Certificate of Authorization No.

N/A (fapplicable)

Expiration Date N/A Date 01/

/ W11 Signed Frank A KIAn*rPJci Frank A KlAnack!

(Site ISI Program Owner) f CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by Hartford Steam Boiler (HSBCT) of Hartford, Connecticut have inspected the items described in this Owners Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation di scribed in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any p~onal injury or pro rty d mage or a loss of any kind arising from or connected with this inspection.

Bruce Sawver t

GL Commissions NB10496, A. N. I New York 4077 Inspector's Signature National Board, State, Province, and Endorsements Date-___________

R. E. Ginna Nuclear Power Plant, Unit I 5 th Interval Inservice Inspection and Rev.

00 2 nd Interval Containment Inservice a joint venture of Inspection Date: 0811112011 0

r-

% 'eDF 2011 OWNER'S ACTIVITY REPORT Page i-6 of 1-9 FOR INSERVICE EXAMINATIONS FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-4 Report Number GNPP-OAR-IWE/L-2011 Plant R E Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, New York 14519 (Name and Address of Plant)

Unit No. _

_1 Commercial Service Date June 1. 1970 Refueling Outage Number RFO-35 Current Inspection Interval Second Containment Inspection Interval - January 1,2010 to December 31, 2019 (1st, 2nd, 3rd, 4th, Other)

Current Inspection Period First Inservice Inspection Period - January 1. 2010 to December 31, 2012 (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the Inspection Plans 2004 Edition, No Addenda Date and Revision of Inspection Plans 29 December 2009, Revision 0 Edition and Addenda of ASME Section XI applicable to repairs/replacements, if different than the Inspection Plan N/A Code Cases used:

N-532-4. N-686. N-739. N-753. N-686.

(if aoolicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting completion of 2011 RFO (RFO-35) conform to the requirements of Section XI.

Certificate of Authorization No.

NIA Expiration Date N/A Date 8'I' iho I I Signed Frank A KlInqe-ki (Site ISI Program Owner)

I CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by Hartford Steam Boiler (HSBCT) of Hartford. Connecticut have inspected the items described in this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluatiodescribed in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any Irsonal injury or pr~erty damage or a loss of any kind arising from or connected with this Inspection.

Bruce Sawyer 4

Commissions NB10496. A. N. I: New York 4077 Inspectoj"s Signature National Board, State, Province, and Endorsements Date 8/-//7' 0L"

R. E. Ginna Nuclear Power Plant, Unit I 5 th Interval Inservice Inspection and Rev.

00 2 nd Interval Containment Inservice a joint venture of Inspection Date: 0811112011 0asel

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ttW 4D 2011 OWNER'S ACTIVITY REPORT Page i-7 of i -9 FOR INSERVICE EXAMINATIONS TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATION FOR CONTINUED SERVICE As recquired by the provisions of the ASME Code Case N-532-4 EXAMINATION ITEM EVALUATION DESCCRIPTION CATEGORY AND ITEM NUMBER DESCRIPTION B-P, B15.80 Reactor Pressure Vessel (RPV) Bottom Engineering Analytical Evaluation was performed Code Case N-722 Mounted Instrumentation, Penetration #31 to satisfy the requirements of IWB-3660 ISI Fourth Interval Relief Request (A86/J-12), Ultrasonic (UT) examination demonstrates acceptance for a one additional Number 24 was performed as required by Relief cycle. A second Analytical Evaluation was ISI Summary Number 1411111 Request Number 24 and an indication performed by Westinghouse and justified identified that was determined to be operation for an additional 40 years until May rejectable in accordance with IWB-3000.

2051.

B-N-3, B13.70 Reactor Pressure Vessel (RPV) Core Engineering Analytical Evaluation was performed ISI Summary Number 1000800 Support Structure Baffle Bolt Replacement under ECP-10-000422. The evaluation shows Baseline VT examination notes that three the condition is acceptable until the next 10-Year (3) baffle bolt locations no longer have a ISI RPV Core Support Structure Examination.

bolt there. Bolt replacement attempts experienced problems resulting in the elimination of three bolts.

Reactor Vessel Internals Program Reactor Vessel Internals Program UT Engineering Analytical Evaluation was performed LR-RVI-PROGPLAN Revision 2, examinations of Baffle Former Bolts under ECP-10-000422. This plant specific Attachment D Baffle-Former Identified one bolt with a rejectable evaluation shows the baffle-former bolting Assembly Baffle Former Bolts.

indication, condition is acceptable for 10 additional years of operation when re-examination or replacement is planned.

4 4

4 ________________________

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R. E. Ginna Nuclear Power Plant, Unit 1 SNI 5 th Interval Inservice Inspection and Rev.

00 2 nd Interval Containment Inservice a joint venture of Inspection Date: 08/11/2011 O0

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7eDF 2011 OWNER'S ACTIVITY REPORT Page i-8 of i-9 FOR INSERVICE EXAMINATIONS TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 CODE ITEM DESCRIPTION DATE REPAIR/REPLACEMENT CLASS DESCRIPTION OF WORK COMPLETED PLAN NUMBER 2

AFU-227, Mechanical Snubber Functional Test June GORR 35-076 Snubber, PSA-3 Failure - Replaced Mechanical 2011 Snubber on component support (WO C90797825)

AFU-227.

1 Reactor Coolant Pump (RCP) "A", Stud # 8, ASME Category B-G-1 Item Number B6.180 ISI Summary Number 1600049.

Ultrasonic examination performed on all 24 studs identified an indication in one stud (#8) that could not be sized for evaluation. Therefore, stud

1. 8 was rejected and replaced with new stud #25. Stud #25 was a like-for-like replacement; UT baseline examination was performed and acceptable. UT bolting examination on the remaining 23 RCP "A" studs were acceptable. An expansion was performed to the 24 RCP "B" studs, UT examined and all acceptable.

June 2011 GORR 35-090 (WO C20900841) 4 4

R. E. Ginna Nuclear Power Plant, Unit I ISN 5 th Interval Inservice Inspection and Rev.

00 ventR 2 nd Interval Containment Inservice joint venture of Inspection Date: 0811112011 ODMW

ý4-%- eDF 2011 OWNER'S ACTIVITY REPORT Page i-9 of i -9 FOR INSERVICE EXAMINATIONS END OF INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR 2011 REFUELING OUTAGE (RFO-35)