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| issue date = 11/20/2012
| issue date = 11/20/2012
| title = Corrected Copy of 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
| title = Corrected Copy of 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
| author name = Swift P M
| author name = Swift P
| author affiliation = Constellation Energy Nuclear Group, LLC, EDF Group, Nine Mile Point Nuclear Station, LLC
| author affiliation = Constellation Energy Nuclear Group, LLC, EDF Group, Nine Mile Point Nuclear Station, LLC
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:CENG.a joint venture of Consteltation
{{#Wiki_filter:CENG.
: eDFe EnerWg0 1Q NINE MILE POINT NUCLEAR STATION P.O. Box 63 Lycoming, NY 13093 November 20, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
a joint venture of P.O. Box 63 Lycoming, NY 13093 Consteltation     :   eDFe EnerWg0             1Q NINE MILE POINT NUCLEAR STATION November 20, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:           Document Control Desk


==SUBJECT:==
==SUBJECT:==
Document Control Desk Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-4 10 Corrected Copy of 2012 Owner's Activity Report for Refueling Outage 13 Inservice Examinations (a) Letter from P. M. Swift (NMPNS) to Document Control Desk (NRC), dated August 16, 2012, 2012 Owner's Activity Report for Refueling Outage 13 Inservice Examinations
Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-4 10 Corrected Copy of 2012 Owner's Activity Report for Refueling Outage 13 Inservice Examinations


==REFERENCE:==
==REFERENCE:==
(a) Letter from P. M. Swift (NMPNS) to Document Control Desk (NRC), dated August 16, 2012, 2012 Owner's Activity Report for Refueling Outage 13 Inservice Examinations By letter dated August 16, 2012 (Reference a), Nine Mile Point Nuclear Station, LLC (NMPNS) submitted the 2012 Owner's Activity Report (OAR) for Nine Mile Point Unit 2 (NMP2) summarizing the results of examinations performed during the NMP2 spring refueling outage (RFO13). NMPNS subsequently discovered that an incorrect version of Form OAR-1 (page 6 of 12 of the OAR) had been included in the submittal in that the certification signatures were missing. To correct this error, NMPNS hereby submits the enclosed corrected OAR.
This letter contains no new regulatory commitments. Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours, Paul M. Swift Manager Engineering Services PMS/DEV


By letter dated August 16, 2012 (Reference a), Nine Mile Point Nuclear Station, LLC (NMPNS)submitted the 2012 Owner's Activity Report (OAR) for Nine Mile Point Unit 2 (NMP2) summarizing the results of examinations performed during the NMP2 spring refueling outage (RFO13). NMPNS subsequently discovered that an incorrect version of Form OAR-1 (page 6 of 12 of the OAR) had been included in the submittal in that the certification signatures were missing. To correct this error, NMPNS hereby submits the enclosed corrected OAR.This letter contains no new regulatory commitments.
Document Control Desk November 20, 2012 Page 2
Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.Very truly yours, Paul M. Swift Manager Engineering Services PMS/DEV Document Control Desk November 20, 2012 Page 2  


==Enclosure:==
==Enclosure:==
Nine Mile Point Unit 2, Third Inservice Inspection Interval, Second Inservice Inspection Period, 2012 Owner's Activity Report for RFO 13 Inservice Examinations (Corrected Copy) cc:    Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC


Nine Mile Point Unit 2, Third Inservice Inspection Interval, Second Inservice Inspection Period, 2012 Owner's Activity Report for RFO 13 Inservice Examinations (Corrected Copy)cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC ENCLOSURE NINE MILE POINT UNIT 2 THIRD INSERVICE INSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2012 OWNER'S ACTIVITY REPORT FOR RFO13 INSERVICE EXAMINATIONS (CORRECTED COPY)Nine Mile Point Nuclear Station, LLC November 20, 2012 Nine Mile Point Nuclear Station THIRD INSERVICEINSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2012 OWNER'S ACTIVITY REPORT FOR RFO13 INSERVICE EXAMINATIONS Prepared For Nine Mile Point Nuclear Station Unit 2 P.O. Box.63, Lake Road Lycoming, New York 13093 Commercial Service Date: NRC Docket Number: Document Number: Revision Number: 00 April 5, 1988 50-410 CNG-NMP2-OAR-003-013 Date: July 15,,20.12 Prepared by: 1A ý.- X Jeffreýý.\tevtson NS ISI Program Owner Reviewed by: Todd L. Davis -NIrVMNS Site ISI & CISI Program Implementer Reviewed by: Carlo Mc ay NMPN ReWir & Replacement Program Owner Reviewed b i Briggs -Subervis Si ngineering Programs Approved by: F io Todd Fiorenza e eral Supe sor Site'Engineering Programs Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile P t 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR INSERVICE EXAMINATIONS Page 2 of 12 TABLE OF CONTENTS T a ble of C o nte nts ....................................................................................................................................................
ENCLOSURE NINE MILE POINT UNIT 2 THIRD INSERVICE INSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2012 OWNER'S ACTIVITY REPORT FOR RFO13 INSERVICE EXAMINATIONS (CORRECTED COPY)
2 R eco rd of R evisio n .....................................................................................................................................................
Nine Mile Point Nuclear Station, LLC November 20, 2012
3 A b stra ct ......................................................................................................................................................................
 
4 Form OAR-1 Owner's Activity Report for ASME Section XI Inspection
Nine Mile Point Nuclear Station THIRD INSERVICEINSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2012 OWNER'S ACTIVITY REPORT FOR RFO13 INSERVICE EXAMINATIONS Prepared For Nine Mile Point Nuclear Station Unit 2 P.O. Box.63, Lake Road Lycoming, New York 13093 Commercial Service Date:                          April 5, 1988 NRC Docket Number:                                50-410 Document Number:                                  CNG-NMP2-OAR-003-013 Revision Number: 00                        Date:  July 15,,20.12 Prepared by:    1A ý.-      X Jeffreýý.\tevtson            NS ISI Program Owner Reviewed by:
& Testing Plans ....................................
Todd L. Davis - NIrVMNS Site ISI & CISI Program Implementer Reviewed by:
6 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service ....................
Carlo Mc  ay  NMPN    ReWir & Replacement Program Owner Reviewed b i  Briggs - Subervis    Si    ngineering Programs Approved by:       F    io Todd Fiorenza      e eral Supe    sor Site'Engineering Programs
7 Table 2 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service ........ 11 Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 Energy Groulp THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR INSERVICE EXAMINATIONS Page 3 of 12 July 15,2012 00 Entire Document Initial issue of Owner's Activity Report for ASME Section XI Inservice Inspection, Containment Inservice Examinations, and Pressure Tests and Alternate Risk-Informed Inspection in accordance with the requirements of ASME Code Case N-532-4.
 
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Pt 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 4 of 12 ABSTRACT ASME Section Xl Code Case N-532-4 requires submission of the Owner's Activity Report to the regulatory and enforcement authorities having jurisdiction at the plant site within 90 calendar days of the completion of each refueling outage.This Owner's Activity Report summarizes the results of the Nine Mile Point Nuclear Station (NMPNS), Unit 2, American Society of Mechanical Engineers (ASME) Section XI In-service Inspection, Risk-Informed Inspection, Containment In-service Examinations, and Pressure Tests performed since the last report dated May 4, 2010 through Refueling Outage Thirteen (RFO13) ending June 9, 2012. RFO13 is the first of two outages scheduled during the Second In-service Inspection Period that started on April 5, 2011 and is scheduled to end on April 4, 2015.The attached Table 1 and 2 include flaws and conditions (those meeting the requirements of Code Case N-532-4) identified since the last Owner's Activity Report following Refueling Outage RFO 12.As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC), Section XI, Article IWA-6000, NMPNS is implementing ASME Code Case N-532-4, Alternative Requirements to Repair and Replacement Documentation Requirements and In-service Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section XI, Division 1". Regulatory Guide 1.147, Revision 15, approved ASME Code Case N-532-4 for use. This Report complies with the requirements of Code Case N-532-4 and the conditions identified in RG 1.147.OWNER'S ACTIVITY REPORTS -FORM OAR-1 Owner Activity Report Form OAR-1 was prepared and certified upon completion of the Nine Mile Point Unit 2, 2012 refueling outage (RFO13) examination activity in accordance with the following NMPNS inspection plans and schedules:
Nine Mile Point Nuclear Station Unit 2                                                  CNG-NMP2-OAR-003-13 0        Constellation Energy Group                              THIRD INSERVICE INSPECTION INTERVAL                                                      Rev.           00 Nine Mile P t                                      2012 OWNER'S ACTIVITY REPORT Nuclear Station                                                                  FOR INSERVICE EXAMINATIONS                                                    Page              2      of    12 TABLE OF CONTENTS T a ble of C o nte nts ....................................................................................................................................................           2 R eco rd of R evision .....................................................................................................................................................             3 A b stra ct ...................................................................................................................................................................... 4 Form OAR-1 Owner's Activity Report for ASME Section XI Inspection & Testing Plans ....................................                                                                  6 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service .................... 7 Table 2 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service ........                                                                             11
CNG-NMP2-ISI-003, Third Ten-Year In-service Inspection Plan and Implementing Schedule, (includes the Alternate Risk-Informed Inspection Program)CNG-NMP2-CISI-002, Second Containment In-service Inspection Plan and Implementing Schedule NMP2-PT-008, Inservice Pressure Testing Program Plan 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 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).
 
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 5 of 12 b. Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 2, identifies those items containing flaws or relevant conditions that exceeded Division 1 acceptance criteria.
Nine Mile Point Nuclear Station Unit 2          CNG-NMP2-OAR-003-13 Energy Groulp              THIRD INSERVICE INSPECTION INTERVAL            Rev.     00 Nine Mile Point              2012 OWNER'S ACTIVITY REPORT Nuclear Station                              FOR INSERVICE EXAMINATIONS                  Page      3  of    12 00                July 15,2012          Entire      Initial issue of Owner's Activity Report for ASME Document      Section XI Inservice Inspection, Containment Inservice Examinations, and Pressure Tests and Alternate Risk-Informed Inspection in accordance with the requirements of ASME Code Case N-532-4.
This information is required even if the discovery of the flaw or relevant condition that necessitated the repair/replacement activity did not result from an examination or test required by Division 1. If the acceptance criterion for a particular item is not specified in Division 1, the provisions of IWA-3100(b) shall be used to determine which repair/replacement activities are required to be included in the abstract.In accordance with ASME Section XI, IWB-2412(a), IWC-2412, IWD-2412 IWE-2412(a), and IWF-2410(b) and with the exception of the examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, IWC-2500-1, IWD-2500-1, IWF-2500-1 and IWE-2500-1, including those examinations which NMPNS has requested and received approval in the form of proposed alternatives in accordance with 10CFR50.55a(a)(3), the required examinations in each examination category have been completed for the First In-service Inspection Period in accordance with Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, IWE-2412-1, and IWF-2410-2.
 
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 ,IFnerwcade INSERVICE INSPECTION INTERVAL Rev. 00 Nine MiteFPOnt 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS.
Nine Mile Point Nuclear Station Unit 2           CNG-NMP2-OAR-003-13 0      Constellation Energy Group            THIRD INSERVICE INSPECTION INTERVAL               Rev. 00 Nine Mile Pt                2012 OWNER'S ACTIVITY REPORT Nuclear Station                               FOR                         Date: July 15, 2012 INSERVICE EXAMINATIONS                   Page     4 of       12 ABSTRACT ASME Section Xl Code Case N-532-4 requires submission of the Owner's Activity Report to the regulatory and enforcement authorities having jurisdiction at the plant site within 90 calendar days of the completion of each refueling outage.
Page 6 of 12 FORM OAR-1 OWN ER'S ACTIVITY REPORT As required provisions of the ASME Code Case N-532-4 Report Number: CNG-NMP2-OAR-003-0-13 Plant Nine Mile Point Nuclear Station, P. 0. Box 63, Lycominhq.
This Owner's Activity Report summarizes the results of the Nine Mile Point Nuclear Station (NMPNS), Unit 2, American Society of Mechanical Engineers (ASME) Section XI In-service Inspection, Risk-Informed Inspection, Containment In-service Examinations, and Pressure Tests performed since the last report dated May 4, 2010 through Refueling Outage Thirteen (RFO13) ending June 9, 2012. RFO13 is the first of two outages scheduled during the Second In-service Inspection Period that started on April 5, 2011 and is scheduled to end on April 4, 2015.
New York 13093 (Name andAddress of Plant)Plant Unit 2 Commercial Service Date April 5. 1988 Refueling Outage Number RFO13 Current Inspection.
The attached Table 1 and 2 include flaws and conditions (those meeting the requirements of Code Case N-532-
Interval 3rd Interval for ISI & PT, 2 nd Interval forCISI April 5. 2008 to April 5; 2018 (1st, 2nd, 3rd, 4th, Other)Current Inspection Period Second In-service Inspection Period April 5. 2011 to AprilS, 2015 (1st, 2nd, 3rd)Edition-and Addenda of.Section Xl applicable to the Inspection Plans 2004 Edition, No Addenda Date and Revision of Inspection Plans CNG-NMP2-ISI-003, Revision 01, August 28, 2009 (ISI), CNG-NMP2-CISI-002, Revision 01. AuQust 28. 2009 (Containment ISI), NMP2-PT-008 Revision 05, March 10, 2010 (Pressure Test)Edition and Addenda of ASME Section XI applicable to Repair/Replacement activities, if different than the Inspection Plan N/A (same Code Edition/Addenda)(if applicable)
: 4) identified since the last Owner's Activity Report following Refueling Outage RFO 12.
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 b de, Section XI; and (c) the repair/replacement activities and evaluations supporting the completion RFO1 conform to the requirements of Section XI./" (efueingoutale pumber)Signed Date. ;.(CGeneral rgram'9T' 1 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 t/J-' A145AV and employed by /-/S. e-7 d- of 4.4Lqý 7-"'- 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 XLI 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 personal injury or property damage.or a loss of any kind arising from or connected with %s inspection.
As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC), Section XI, Article IWA-6000, NMPNS is implementing ASME Code Case N-532-4, Alternative Requirements to Repair and Replacement Documentation Requirements and In-service Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section XI, Division 1". Regulatory Guide 1.147, Revision 15, approved ASME Code Case N-532-4 for use. This Report complies with the requirements of Code Case N-532-4 and the conditions identified in RG 1.147.
Commissions A/W/ iS6'1 l A. IV A/,v S3WK/l s- por's Signature National Board," State, Province, and Endorsements Date Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 S Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR INSERVICE EXAMINATIONS Page 7 of 12 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A F1.10A Sway Strut (Pipe Condition Report CR-2012-002984 documents the identification of a Support) relevant condition exceeding the acceptance criteria of IWF-3410.While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST348A1 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.The initial additional examinations (a.k.a. scope expansion), required of ASME Section X1 IWF-2430(a), identified one of four additional supports as having the condition of misalignment and binding. This additional condition is documented in Condition Report CR-2012-003568 and resulted in the need for further additional examinations as required by ASME Section XI IWF-2430(b). All nine additional supports were found to be free of the misalignment condition.
OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner Activity Report Form OAR-1 was prepared and certified upon completion of the Nine Mile Point Unit 2, 2012 refueling outage (RFO13) examination activity in accordance with the following NMPNS inspection plans and schedules:
CNG-NMP2-ISI-003, Third Ten-Year In-service Inspection Plan and Implementing Schedule, (includes the Alternate Risk-Informed Inspection Program)
CNG-NMP2-CISI-002, Second Containment In-service Inspection Plan and Implementing Schedule NMP2-PT-008, Inservice Pressure Testing Program Plan 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 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).
 
Nine Mile Point Nuclear Station Unit 2               CNG-NMP2-OAR-003-13 0 Constellation Energy Group             THIRD INSERVICE INSPECTION INTERVAL                 Rev.     00 Nine Mile Point             2012 OWNER'S ACTIVITY REPORT Nuclear Station                               FOR                           Date: July 15, 2012 INSERVICE EXAMINATIONS                     Page       5 of       12
: b. Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 2, identifies those items containing flaws or relevant conditions that exceeded Division 1 acceptance criteria. This information is required even if the discovery of the flaw or relevant condition that necessitated the repair/replacement activity did not result from an examination or test required by Division 1. If the acceptance criterion for a particular item is not specified in Division 1, the provisions of IWA-3100(b) shall be used to determine which repair/replacement activities are required to be included in the abstract.
In accordance with ASME Section XI, IWB-2412(a), IWC-2412, IWD-2412 IWE-2412(a), and IWF-2410(b) and with the exception of the examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, IWC-2500-1, IWD-2500-1, IWF-2500-1 and IWE-2500-1, including those examinations which NMPNS has requested and received approval in the form of proposed alternatives in accordance with 10CFR50.55a(a)(3), the required examinations in each examination category have been completed for the First In-service Inspection Period in accordance with Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, IWE-2412-1, and IWF-2410-2.
 
Nine Mile Point Nuclear Station Unit 2                     CNG-NMP2-OAR-003-13
            ,IFnerwcade C*THIRD                  INSERVICE INSPECTION INTERVAL                       Rev. 00 Nine MiteFPOnt                   2012 OWNER'S ACTIVITY REPORT Nuclear Station                                       FOR                                 Date: July 15, 2012 INSERVICE EXAMINATIONS.                             Page     6 of     12 FORM OAR-1 OWN ER'S ACTIVITY REPORT As required by*the provisions of the ASME Code Case N-532-4 Report Number:             CNG-NMP2-OAR-003-0-13 Plant                         Nine Mile Point Nuclear Station, P. 0. Box 63, Lycominhq. New York 13093 (Name andAddress of Plant)
Plant Unit       2         Commercial Service Date     April 5. 1988           Refueling Outage Number RFO13 Current Inspection. Interval 3rd Interval for ISI & PT, 2 nd Interval forCISI             April 5. 2008 to April 5; 2018 (1st, 2nd, 3rd, 4th, Other)
Current Inspection Period             Second In-service Inspection Period               April 5. 2011 to AprilS, 2015 (1st, 2nd, 3rd)
Edition-and Addenda of.Section Xl applicable to the Inspection Plans                   2004 Edition, No Addenda Date and Revision of Inspection Plans CNG-NMP2-ISI-003, Revision 01, August 28, 2009 (ISI), CNG-NMP2-CISI-002, Revision 01. AuQust 28. 2009 (Containment ISI), NMP2-PT-008 Revision 05, March 10, 2010 (Pressure Test)
Edition and Addenda of ASME Section XI applicable to Repair/Replacement activities, if different than the Inspection Plan N/A (same Code Edition/Addenda)
(if applicable)
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 b                   de, Section XI; and (c) the repair/replacement activities and evaluations supporting the completion                 RFO1                             conform to the requirements of Section XI.
                  /" (efueingoutale pumber)
Signed (CGeneral Supervi*'"E=nginee              rgram'9T'1                     Date.;.
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 A145AV t/J-'             and employed by /-/S. d-      e-7             of 4.4Lqý Ž 7-"'-     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 XLI 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 personal injury or property damage.or a loss of any kind arising from or connected with %s inspection.
Commissions A/W/ iS6'1 l A. IV                   A/,v S3WK/l s-por's Signature                                     National Board," State, Province, and Endorsements Date
 
Nine Mile Point Nuclear Station Unit 2               CNG-NMP2-OAR-003-13 S       Group         THIRD INSERVICE INSPECTION INTERVAL                   Rev.     00 Nine Mile Point               2012 OWNER'S ACTIVITY REPORT Nuclear Station                                 FOR INSERVICE EXAMINATIONS                         Page       7   of   12 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION       ITEM             ITEM CATEGORY       NUMBER         DESCRIPTION F-A             F1.10A   Sway Strut (Pipe           Condition Report CR-2012-002984 documents the identification of a Support)                   relevant condition exceeding the acceptance criteria of IWF-3410.
While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST348A1 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).
A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.
The initial additional examinations (a.k.a. scope expansion),
required of ASME Section X1 IWF-2430(a), identified one of four additional supports as having the condition of misalignment and binding. This additional condition is documented in Condition Report CR-2012-003568 and resulted in the need for further additional examinations as required by ASME Section XI IWF-2430(b). All nine additional supports were found to be free of the misalignment condition.
Both supports identified as having the out of alignment condition were corrected via maintenance, were re-inspected (pre-service examination), and have been scheduled for Code required successive examinations.
Both supports identified as having the out of alignment condition were corrected via maintenance, were re-inspected (pre-service examination), and have been scheduled for Code required successive examinations.
F-A F1.30A Sway Strut (Pipe Condition Report CR-2012-003402 documents the identification of a Support) relevant condition exceeding the acceptance criteria of IWF-3410.While performing an ISI examination in the NMP2 Service Water Screen Well it was noted that ASME Class 3 sway strut pipe support 2SWQ-PSST54OB3 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.The initial additional examinations (a.k.a. scope expansion), required of ASME Section XA IWF-2430(a), found all five additional supports to be free of the misalignment condition.
F-A             F1.30A   Sway Strut (Pipe           Condition Report CR-2012-003402 documents the identification of a Support)                   relevant condition exceeding the acceptance criteria of IWF-3410.
As such, no further additional examinations were required.2SWQ-PSST540B3 was corrected via maintenance, was re-inspected (pre-service examination), and has been scheduled for Code required successive examinations.
While performing an ISI examination inthe NMP2 Service Water Screen Well it was noted that ASME Class 3 sway strut pipe support 2SWQ-PSST54OB3 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 SConst-ilation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT NuclearStation FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 8 of 12 TABLE I (continued)
A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A F1.10A Sway Strut (Pipe Condition Report CR-2012-003568 documents the identification of a Support) condition unacceptable for continued service in accordance with IWF-3410.
The initial additional examinations (a.k.a. scope expansion),
While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST346A1 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).This condition was identified during the additional examinations (scope expansion) required of Condition Report CR-2012-002984 discussed above.A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.As indicated above, the out of alignment condition was corrected via maintenance, the support was re-inspected (pre-service examination), and has been scheduled for Code required successive examinations.
required of ASME Section XA IWF-2430(a), found all five additional supports to be free of the misalignment condition. As such, no further additional examinations were required.
F-A F1.10A Sway Strut (Pipe Condition Report CR-2012-003648 documents the identification of a Support) condition unacceptable for continued service in accordance with IWF-3410.
2SWQ-PSST540B3 was corrected via maintenance, was re-inspected (pre-service examination), and has been scheduled for Code required successive examinations.
While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST987A1 showed evidence of misalignment.
 
An Engineering evaluation concluded that the identified condition, though undesirable, was in fact acceptable for continued service in accordance with ASME Section Xl IWF-3122.3(a).
Nine Mile Point Nuclear Station Unit 2               CNG-NMP2-OAR-003-13 SConst-ilation Energy Group           THIRD INSERVICE INSPECTION INTERVAL                     Rev.     00 Nine Mile Point             2012 OWNER'S ACTIVITY REPORT NuclearStation                                 FOR                             Date: July 15, 2012 INSERVICE EXAMINATIONS                         Page       8   of   12 TABLE I (continued)
Since the condition was acceptable for continued service no further additional Code examinations were required.
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION       ITEM           ITEM CATEGORY       NUMBER       DESCRIPTION F-A             F1.10A Sway Strut (Pipe           Condition Report CR-2012-003568 documents the identification of a Support)                   condition unacceptable for continued service in accordance with IWF-3410. While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST346A1 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).
The support was restored to original design configuration in accordance with IWF-3122.3(b).
This condition was identified during the additional examinations (scope expansion) required of Condition Report CR-2012-002984 discussed above.
A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.
As indicated above, the out of alignment condition was corrected via maintenance, the support was re-inspected (pre-service examination), and has been scheduled for Code required successive examinations.
F-A             F1.10A Sway Strut (Pipe           Condition Report CR-2012-003648 documents the identification of a Support)                   condition unacceptable for continued service in accordance with IWF-3410. While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST987A1 showed evidence of misalignment.
An Engineering evaluation concluded that the identified condition, though undesirable, was in fact acceptable for continued service in accordance with ASME Section Xl IWF-3122.3(a). Since the condition was acceptable for continued service no further additional Code examinations were required. The support was restored to original design configuration in accordance with IWF-3122.3(b).
The subject support was re-inspected and found acceptable following corrective maintenance.
The subject support was re-inspected and found acceptable following corrective maintenance.
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 Conms-teilation G0s Oy p THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mi rout 2012 OWNER'S ACTIVITY REPORT Nine Mile Point Date: July 15, 2012 Nuclear Station FOR INSERVICE EXAMINATIONS Page 9 of 12 TABLE 1 (continued)
 
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A FI.10C Variable Spring (Pipe Condition Report CR-2012-004124 documents the identification of a Support) condition unacceptable for continued service in accordance with IWF-3410.
Nine Mile Point Nuclear Station Unit 2                 CNG-NMP2-OAR-003-13 Conms-teilation NineMi G0srout  Oyp        THIRD   INSERVICE     INSPECTION INTERVAL             Rev.     00 2012 OWNER'S ACTIVITY REPORT Nine Mile Point                                                                   Date: July 15, 2012 Nuclear Station                                   FOR INSERVICE EXAMINATIONS                       Page       9   of     12 TABLE 1 (continued)
While performing an ISI examination in the NMP2 Secondary Containment it was noted that ASME Class 1 variable spring pipe support 2WCS-PSSH698A1 setting exceeded allowable deviation.
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION       ITEM               ITEM CATEGORY       NUMBER           DESCRIPTION F-A             FI.10C     Variable Spring (Pipe       Condition Report CR-2012-004124 documents the identification of a Support)                   condition unacceptable for continued service in accordance with IWF-3410. While performing an ISI examination in the NMP2 Secondary Containment it was noted that ASME Class 1 variable spring pipe support 2WCS-PSSH698A1 setting exceeded allowable deviation.
An Engineering evaluation concluded that the identified condition, though undesirable, was in fact acceptable for continued service in accordance with ASME Section Xl IWF-3122.3(a).
An Engineering evaluation concluded that the identified condition, though undesirable, was in fact acceptable for continued service in accordance with ASME Section Xl IWF-3122.3(a). Since the condition was acceptable for continued service no further additional Code examinations were required. The support was restored to original design configuration inaccordance with IWF-3122.3(b).
Since the condition was acceptable for continued service no further additional Code examinations were required.
The subject support was re-inspected and found acceptable following corrective measures.
The support was restored to original design configuration in accordance with IWF-3122.3(b).
B-P             B15.10     Pressure Retaining         The ASME Class 1 end of refueling outage vessel leakage test Components (Bolted         identified leakage exceeding the level that requires a Design Mechanical                 Engineering Evaluation in accordance with station procedures.
The subject support was re-inspected and found acceptable following corrective measures.B-P B15.10 Pressure Retaining The ASME Class 1 end of refueling outage vessel leakage test Components (Bolted identified leakage exceeding the level that requires a Design Mechanical Engineering Evaluation in accordance with station procedures.
Connections)               Station procedures require Design Engineering Evaluation for any leakage originating from a bolted connection.
Connections)
Condition Report CR-2012-005096 documents an undesirable condition associated with 60 drops per minute leakage from the ASME Class 1 valve 2RCS*HYV1 7B body-to-bonnet bolted flange connection. A Design Engineering Evaluation concludes that the identified leakage is acceptable as-is for continued service. Work Order C91907821 has been generated to address this condition.
Station procedures require Design Engineering Evaluation for any leakage originating from a bolted connection.
Condition Reports CR-2012-005094 and CR-2012-005113 document undesirable conditions associated with leakage from Control Rod Drive bolted flange connections. The as-found leakage ranged from 2 drops per minute to 108 drops per minute.
Condition Report CR-2012-005096 documents an undesirable condition associated with 60 drops per minute leakage from the ASME Class 1 valve 2RCS*HYV1 7B body-to-bonnet bolted flange connection.
The as-left leakage was reduced significantly following scramming of control rod drives. Furthermore, during the final 900 psi drywell closeout inspection Under-vessel leakage had fallen to 1 drop every 2 - 3 minutes and no leakage was observed from the 2RCS*HYV17B bonnet as captured in CR-2012-005613.
A Design Engineering Evaluation concludes that the identified leakage is acceptable as-is for continued service. Work Order C91907821 has been generated to address this condition.
Condition Reports CR-2012-005094 and CR-2012-005113 document undesirable conditions associated with leakage from Control Rod Drive bolted flange connections.
The as-found leakage ranged from 2 drops per minute to 108 drops per minute.The as-left leakage was reduced significantly following scramming of control rod drives. Furthermore, during the final 900 psi drywell closeout inspection Under-vessel leakage had fallen to 1 drop every 2 -3 minutes and no leakage was observed from the 2RCS*HYV17B bonnet as captured in CR-2012-005613.
A Design Engineering Evaluation concludes that the identified leakage is acceptable as-is for continued service.
A Design Engineering Evaluation concludes that the identified leakage is acceptable as-is for continued service.
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 neorgy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine MiPoit 2012 OWNER'S ACTIVITY REPORT Nine Mile Point Date: July 15, 2012 Nuclear Station FOR INSERVICE EXAMINATIONS Page 10 of 12 TABLE 1 (continued)
 
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A FI.30A Sway Strut and Restraint Condition Report CR-2012-003085 documents the identification of (Pipe Supports) an unacceptable condition requiring engineering evaluation for continued service. While performing Structural Maintenance Rule Walk-Down of Service Water piping located in the NMP2 Service Water tunnel it was noted that ASME Class 3 sway strut pipe supports 2SWP-PSST1425A3 and 2SWP-PSST1426A3 are deteriorated having heavy surface corrosion.
Nine Mile Point Nuclear Station Unit 2                 CNG-NMP2-OAR-003-13 neorgy Nine MiPoit Group         THIRD INSERVICE INSPECTION INTERVAL                       Rev. 00 2012 OWNER'S ACTIVITY REPORT Nine Mile Point                                                                     Date: July 15, 2012 Nuclear Station                                   FOR INSERVICE EXAMINATIONS                         Page     10     of   12 TABLE 1 (continued)
Work Order C91856316 has been initiated to address this condition.
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION       ITEM             ITEM CATEGORY       NUMBER         DESCRIPTION F-A             FI.30A   Sway Strut and Restraint     Condition Report CR-2012-003085 documents the identification of (Pipe Supports)             an unacceptable condition requiring engineering evaluation for continued service. While performing Structural Maintenance Rule Walk-Down of Service Water piping located in the NMP2 Service Water tunnel it was noted that ASME Class 3 sway strut pipe supports 2SWP-PSST1425A3 and 2SWP-PSST1426A3 are deteriorated having heavy surface corrosion. Work Order C91856316 has been initiated to address this condition.
A Design Engineering evaluation concluded that the identified condition, though undesirable, is not a nonconformance and as such is acceptable for continued service in accordance with ASME Section X1 IWF-3122.3(a).
A Design Engineering evaluation concluded that the identified condition, though undesirable, is not a nonconformance and as such is acceptable for continued service in accordance with ASME Section X1 IWF-3122.3(a). Since the condition was acceptable for continued service no further additional Code examinations were required. The evaluation recommends performing maintenance to restore the support to original design configuration.
Since the condition was acceptable for continued service no further additional Code examinations were required.
Condition Report CR-2012-002953 documents a similar condition on additional safety-related Service Water pipe supports located in the Service Water pipe tunnel. Service Water supports 2SWP-PSR777A3, 2SWP-PSST776A3 2SWP-PSR775A3, 2SWP-PSR774A3, 2SWP-PSR732A3 and 2SWP-PSR733A3 were observed to have heavy corrosion and structural steel metal loss of up to 20% of the original thickness. The Design Engineering evaluation associated with this condition concludes that the support conditions remain functional but do not meet the current pipe support design requirements therefore the identified condition is a nonconformance. Maintenance is currently planned and scheduled to perform additional NDE (thickness readings) to verify condition of support members and clean and coat support steel. The supports identified within CR-2012-002953 are safety-related but exempt from ASME Section X1 examination requirements. Work Order C91855634 has been initiated to address this condition.
The evaluation recommends performing maintenance to restore the support to original design configuration.
 
Condition Report CR-2012-002953 documents a similar condition on additional safety-related Service Water pipe supports located in the Service Water pipe tunnel. Service Water supports 2SWP-PSR777A3, 2SWP-PSST776A3 2SWP-PSR775A3, 2SWP-PSR774A3, 2SWP-PSR732A3 and 2SWP-PSR733A3 were observed to have heavy corrosion and structural steel metal loss of up to 20% of the original thickness.
Nine Mile Point Nuclear Station Unit 2             CNG-NMP2-OAR-003-13 Nne Mi2012 THIRD INSERVICE           INSPECTION INTERVAL           Rev. 00 OWNER'S ACTIVITY REPORT Nine Mile PointDaeJuy1,22 Nuclear Station                                   FOR                         Date: July 15, 2012 INSERVICE EXAMINATIONS                     Page   11     of     12 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 REPAIR/REPLACE DESCRIPTION                                       MENT CODE                   ITEM                             OF                       DATE           PLAN NUMBER CLASS               DESCRIPTION                       WORK                     COMPLETED None 4                                 4-                 4 I                             4                                 4.                 $
The Design Engineering evaluation associated with this condition concludes that the support conditions remain functional but do not meet the current pipe support design requirements therefore the identified condition is a nonconformance.
 
Maintenance is currently planned and scheduled to perform additional NDE (thickness readings) to verify condition of support members and clean and coat support steel. The supports identified within CR-2012-002953 are safety-related but exempt from ASME Section X1 examination requirements.
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group     THIRD INSERVICE INSPECTION INTERVAL     Rev. 00 Nine Mile Point     2012 OWNER'S ACTIVITY REPORT NuclearStation                       FOR                   Date: July 15, 2012 INSERVICE EXAMINATIONS           Page     12 of     12 1
Work Order C91855634 has been initiated to address this condition.
Page   of'1 END OF INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR REFUELING OUTAGE THIRTEEN (RFO13)}}
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nne Mi2012 OWNER'S ACTIVITY REPORT Nine Mile PointDaeJuy1,22 Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 11 of 12 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 REPAIR/REPLACE DESCRIPTION MENT CODE ITEM OF DATE PLAN NUMBER CLASS DESCRIPTION WORK COMPLETED None 4 4- 4 I 4 4. $
Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT NuclearStation FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 12 of 12 Page 1 of'1 END OF INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR REFUELING OUTAGE THIRTEEN (RFO13)}}

Latest revision as of 20:21, 11 November 2019

Corrected Copy of 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
ML12335A288
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 11/20/2012
From: Swift P
Constellation Energy Nuclear Group, EDF Group, Nine Mile Point
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNG-NMP2-OAR-003-13
Download: ML12335A288 (15)


Text

CENG.

a joint venture of P.O. Box 63 Lycoming, NY 13093 Consteltation  : eDFe EnerWg0 1Q NINE MILE POINT NUCLEAR STATION November 20, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-4 10 Corrected Copy of 2012 Owner's Activity Report for Refueling Outage 13 Inservice Examinations

REFERENCE:

(a) Letter from P. M. Swift (NMPNS) to Document Control Desk (NRC), dated August 16, 2012, 2012 Owner's Activity Report for Refueling Outage 13 Inservice Examinations By letter dated August 16, 2012 (Reference a), Nine Mile Point Nuclear Station, LLC (NMPNS) submitted the 2012 Owner's Activity Report (OAR) for Nine Mile Point Unit 2 (NMP2) summarizing the results of examinations performed during the NMP2 spring refueling outage (RFO13). NMPNS subsequently discovered that an incorrect version of Form OAR-1 (page 6 of 12 of the OAR) had been included in the submittal in that the certification signatures were missing. To correct this error, NMPNS hereby submits the enclosed corrected OAR.

This letter contains no new regulatory commitments. Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.

Very truly yours, Paul M. Swift Manager Engineering Services PMS/DEV

Document Control Desk November 20, 2012 Page 2

Enclosure:

Nine Mile Point Unit 2, Third Inservice Inspection Interval, Second Inservice Inspection Period, 2012 Owner's Activity Report for RFO 13 Inservice Examinations (Corrected Copy) cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC

ENCLOSURE NINE MILE POINT UNIT 2 THIRD INSERVICE INSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2012 OWNER'S ACTIVITY REPORT FOR RFO13 INSERVICE EXAMINATIONS (CORRECTED COPY)

Nine Mile Point Nuclear Station, LLC November 20, 2012

Nine Mile Point Nuclear Station THIRD INSERVICEINSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2012 OWNER'S ACTIVITY REPORT FOR RFO13 INSERVICE EXAMINATIONS Prepared For Nine Mile Point Nuclear Station Unit 2 P.O. Box.63, Lake Road Lycoming, New York 13093 Commercial Service Date: April 5, 1988 NRC Docket Number: 50-410 Document Number: CNG-NMP2-OAR-003-013 Revision Number: 00 Date: July 15,,20.12 Prepared by: 1A ý.- X Jeffreýý.\tevtson NS ISI Program Owner Reviewed by:

Todd L. Davis - NIrVMNS Site ISI & CISI Program Implementer Reviewed by:

Carlo Mc ay NMPN ReWir & Replacement Program Owner Reviewed b i Briggs - Subervis Si ngineering Programs Approved by: F io Todd Fiorenza e eral Supe sor Site'Engineering Programs

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile P t 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR INSERVICE EXAMINATIONS Page 2 of 12 TABLE OF CONTENTS T a ble of C o nte nts .................................................................................................................................................... 2 R eco rd of R evision ..................................................................................................................................................... 3 A b stra ct ...................................................................................................................................................................... 4 Form OAR-1 Owner's Activity Report for ASME Section XI Inspection & Testing Plans .................................... 6 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service .................... 7 Table 2 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service ........ 11

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 Energy Groulp THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR INSERVICE EXAMINATIONS Page 3 of 12 00 July 15,2012 Entire Initial issue of Owner's Activity Report for ASME Document Section XI Inservice Inspection, Containment Inservice Examinations, and Pressure Tests and Alternate Risk-Informed Inspection in accordance with the requirements of ASME Code Case N-532-4.

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Pt 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 4 of 12 ABSTRACT ASME Section Xl Code Case N-532-4 requires submission of the Owner's Activity Report to the regulatory and enforcement authorities having jurisdiction at the plant site within 90 calendar days of the completion of each refueling outage.

This Owner's Activity Report summarizes the results of the Nine Mile Point Nuclear Station (NMPNS), Unit 2, American Society of Mechanical Engineers (ASME)Section XI In-service Inspection, Risk-Informed Inspection, Containment In-service Examinations, and Pressure Tests performed since the last report dated May 4, 2010 through Refueling Outage Thirteen (RFO13) ending June 9, 2012. RFO13 is the first of two outages scheduled during the Second In-service Inspection Period that started on April 5, 2011 and is scheduled to end on April 4, 2015.

The attached Table 1 and 2 include flaws and conditions (those meeting the requirements of Code Case N-532-

4) identified since the last Owner's Activity Report following Refueling Outage RFO 12.

As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC),Section XI, Article IWA-6000, NMPNS is implementing ASME Code Case N-532-4, Alternative Requirements to Repair and Replacement Documentation Requirements and In-service Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1". Regulatory Guide 1.147, Revision 15, approved ASME Code Case N-532-4 for use. This Report complies with the requirements of Code Case N-532-4 and the conditions identified in RG 1.147.

OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner Activity Report Form OAR-1 was prepared and certified upon completion of the Nine Mile Point Unit 2, 2012 refueling outage (RFO13) examination activity in accordance with the following NMPNS inspection plans and schedules:

CNG-NMP2-ISI-003, Third Ten-Year In-service Inspection Plan and Implementing Schedule, (includes the Alternate Risk-Informed Inspection Program)

CNG-NMP2-CISI-002, Second Containment In-service Inspection Plan and Implementing Schedule NMP2-PT-008, Inservice Pressure Testing Program Plan 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 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).

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 5 of 12

b. Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 2, identifies those items containing flaws or relevant conditions that exceeded Division 1 acceptance criteria. This information is required even if the discovery of the flaw or relevant condition that necessitated the repair/replacement activity did not result from an examination or test required by Division 1. If the acceptance criterion for a particular item is not specified in Division 1, the provisions of IWA-3100(b) shall be used to determine which repair/replacement activities are required to be included in the abstract.

In accordance with ASME Section XI, IWB-2412(a), IWC-2412, IWD-2412 IWE-2412(a), and IWF-2410(b) and with the exception of the examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, IWC-2500-1, IWD-2500-1, IWF-2500-1 and IWE-2500-1, including those examinations which NMPNS has requested and received approval in the form of proposed alternatives in accordance with 10CFR50.55a(a)(3), the required examinations in each examination category have been completed for the First In-service Inspection Period in accordance with Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, IWE-2412-1, and IWF-2410-2.

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13

,IFnerwcade C*THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine MiteFPOnt 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS. Page 6 of 12 FORM OAR-1 OWN ER'S ACTIVITY REPORT As required by*the provisions of the ASME Code Case N-532-4 Report Number: CNG-NMP2-OAR-003-0-13 Plant Nine Mile Point Nuclear Station, P. 0. Box 63, Lycominhq. New York 13093 (Name andAddress of Plant)

Plant Unit 2 Commercial Service Date April 5. 1988 Refueling Outage Number RFO13 Current Inspection. Interval 3rd Interval for ISI & PT, 2 nd Interval forCISI April 5. 2008 to April 5; 2018 (1st, 2nd, 3rd, 4th, Other)

Current Inspection Period Second In-service Inspection Period April 5. 2011 to AprilS, 2015 (1st, 2nd, 3rd)

Edition-and Addenda of.Section Xl applicable to the Inspection Plans 2004 Edition, No Addenda Date and Revision of Inspection Plans CNG-NMP2-ISI-003, Revision 01, August 28, 2009 (ISI), CNG-NMP2-CISI-002, Revision 01. AuQust 28. 2009 (Containment ISI), NMP2-PT-008 Revision 05, March 10, 2010 (Pressure Test)

Edition and Addenda of ASME Section XI applicable to Repair/Replacement activities, if different than the Inspection Plan N/A (same Code Edition/Addenda)

(if applicable)

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 b de,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion RFO1 conform to the requirements of Section XI.

/" (efueingoutale pumber)

Signed (CGeneral Supervi*'"E=nginee rgram'9T'1 Date.;.

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 A145AV t/J-' and employed by /-/S. d- e-7 of 4.4Lqý Ž 7-"'- 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 XLI 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 personal injury or property damage.or a loss of any kind arising from or connected with %s inspection.

Commissions A/W/ iS6'1 l A. IV A/,v S3WK/l s-por's Signature National Board," State, Province, and Endorsements Date

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 S Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT Nuclear Station FOR INSERVICE EXAMINATIONS Page 7 of 12 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A F1.10A Sway Strut (Pipe Condition Report CR-2012-002984 documents the identification of a Support) relevant condition exceeding the acceptance criteria of IWF-3410.

While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST348A1 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).

A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.

The initial additional examinations (a.k.a. scope expansion),

required of ASME Section X1 IWF-2430(a), identified one of four additional supports as having the condition of misalignment and binding. This additional condition is documented in Condition Report CR-2012-003568 and resulted in the need for further additional examinations as required by ASME Section XI IWF-2430(b). All nine additional supports were found to be free of the misalignment condition.

Both supports identified as having the out of alignment condition were corrected via maintenance, were re-inspected (pre-service examination), and have been scheduled for Code required successive examinations.

F-A F1.30A Sway Strut (Pipe Condition Report CR-2012-003402 documents the identification of a Support) relevant condition exceeding the acceptance criteria of IWF-3410.

While performing an ISI examination inthe NMP2 Service Water Screen Well it was noted that ASME Class 3 sway strut pipe support 2SWQ-PSST54OB3 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).

A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.

The initial additional examinations (a.k.a. scope expansion),

required of ASME Section XA IWF-2430(a), found all five additional supports to be free of the misalignment condition. As such, no further additional examinations were required.

2SWQ-PSST540B3 was corrected via maintenance, was re-inspected (pre-service examination), and has been scheduled for Code required successive examinations.

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 SConst-ilation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT NuclearStation FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 8 of 12 TABLE I (continued)

ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A F1.10A Sway Strut (Pipe Condition Report CR-2012-003568 documents the identification of a Support) condition unacceptable for continued service in accordance with IWF-3410. While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST346A1 showed evidence of misalignment and binding (strut rod end in contact with pipe clamp).

This condition was identified during the additional examinations (scope expansion) required of Condition Report CR-2012-002984 discussed above.

A Design Engineering evaluation concluded that the condition of axial misalignment is not acceptable for continued service and as such required correction prior to return to service.

As indicated above, the out of alignment condition was corrected via maintenance, the support was re-inspected (pre-service examination), and has been scheduled for Code required successive examinations.

F-A F1.10A Sway Strut (Pipe Condition Report CR-2012-003648 documents the identification of a Support) condition unacceptable for continued service in accordance with IWF-3410. While performing an ISI examination in the NMP2 drywell it was noted that ASME Class 1 sway strut pipe support 2RHS-PSST987A1 showed evidence of misalignment.

An Engineering evaluation concluded that the identified condition, though undesirable, was in fact acceptable for continued service in accordance with ASME Section Xl IWF-3122.3(a). Since the condition was acceptable for continued service no further additional Code examinations were required. The support was restored to original design configuration in accordance with IWF-3122.3(b).

The subject support was re-inspected and found acceptable following corrective maintenance.

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 Conms-teilation NineMi G0srout Oyp THIRD INSERVICE INSPECTION INTERVAL Rev. 00 2012 OWNER'S ACTIVITY REPORT Nine Mile Point Date: July 15, 2012 Nuclear Station FOR INSERVICE EXAMINATIONS Page 9 of 12 TABLE 1 (continued)

ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A FI.10C Variable Spring (Pipe Condition Report CR-2012-004124 documents the identification of a Support) condition unacceptable for continued service in accordance with IWF-3410. While performing an ISI examination in the NMP2 Secondary Containment it was noted that ASME Class 1 variable spring pipe support 2WCS-PSSH698A1 setting exceeded allowable deviation.

An Engineering evaluation concluded that the identified condition, though undesirable, was in fact acceptable for continued service in accordance with ASME Section Xl IWF-3122.3(a). Since the condition was acceptable for continued service no further additional Code examinations were required. The support was restored to original design configuration inaccordance with IWF-3122.3(b).

The subject support was re-inspected and found acceptable following corrective measures.

B-P B15.10 Pressure Retaining The ASME Class 1 end of refueling outage vessel leakage test Components (Bolted identified leakage exceeding the level that requires a Design Mechanical Engineering Evaluation in accordance with station procedures.

Connections) Station procedures require Design Engineering Evaluation for any leakage originating from a bolted connection.

Condition Report CR-2012-005096 documents an undesirable condition associated with 60 drops per minute leakage from the ASME Class 1 valve 2RCS*HYV1 7B body-to-bonnet bolted flange connection. A Design Engineering Evaluation concludes that the identified leakage is acceptable as-is for continued service. Work Order C91907821 has been generated to address this condition.

Condition Reports CR-2012-005094 and CR-2012-005113 document undesirable conditions associated with leakage from Control Rod Drive bolted flange connections. The as-found leakage ranged from 2 drops per minute to 108 drops per minute.

The as-left leakage was reduced significantly following scramming of control rod drives. Furthermore, during the final 900 psi drywell closeout inspection Under-vessel leakage had fallen to 1 drop every 2 - 3 minutes and no leakage was observed from the 2RCS*HYV17B bonnet as captured in CR-2012-005613.

A Design Engineering Evaluation concludes that the identified leakage is acceptable as-is for continued service.

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 neorgy Nine MiPoit Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 2012 OWNER'S ACTIVITY REPORT Nine Mile Point Date: July 15, 2012 Nuclear Station FOR INSERVICE EXAMINATIONS Page 10 of 12 TABLE 1 (continued)

ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A FI.30A Sway Strut and Restraint Condition Report CR-2012-003085 documents the identification of (Pipe Supports) an unacceptable condition requiring engineering evaluation for continued service. While performing Structural Maintenance Rule Walk-Down of Service Water piping located in the NMP2 Service Water tunnel it was noted that ASME Class 3 sway strut pipe supports 2SWP-PSST1425A3 and 2SWP-PSST1426A3 are deteriorated having heavy surface corrosion. Work Order C91856316 has been initiated to address this condition.

A Design Engineering evaluation concluded that the identified condition, though undesirable, is not a nonconformance and as such is acceptable for continued service in accordance with ASME Section X1 IWF-3122.3(a). Since the condition was acceptable for continued service no further additional Code examinations were required. The evaluation recommends performing maintenance to restore the support to original design configuration.

Condition Report CR-2012-002953 documents a similar condition on additional safety-related Service Water pipe supports located in the Service Water pipe tunnel. Service Water supports 2SWP-PSR777A3, 2SWP-PSST776A3 2SWP-PSR775A3, 2SWP-PSR774A3, 2SWP-PSR732A3 and 2SWP-PSR733A3 were observed to have heavy corrosion and structural steel metal loss of up to 20% of the original thickness. The Design Engineering evaluation associated with this condition concludes that the support conditions remain functional but do not meet the current pipe support design requirements therefore the identified condition is a nonconformance. Maintenance is currently planned and scheduled to perform additional NDE (thickness readings) to verify condition of support members and clean and coat support steel. The supports identified within CR-2012-002953 are safety-related but exempt from ASME Section X1 examination requirements. Work Order C91855634 has been initiated to address this condition.

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 Nne Mi2012 THIRD INSERVICE INSPECTION INTERVAL Rev. 00 OWNER'S ACTIVITY REPORT Nine Mile PointDaeJuy1,22 Nuclear Station FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 11 of 12 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 REPAIR/REPLACE DESCRIPTION MENT CODE ITEM OF DATE PLAN NUMBER CLASS DESCRIPTION WORK COMPLETED None 4 4- 4 I 4 4. $

Nine Mile Point Nuclear Station Unit 2 CNG-NMP2-OAR-003-13 0 Constellation Energy Group THIRD INSERVICE INSPECTION INTERVAL Rev. 00 Nine Mile Point 2012 OWNER'S ACTIVITY REPORT NuclearStation FOR Date: July 15, 2012 INSERVICE EXAMINATIONS Page 12 of 12 1

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