ML070520402

Inservice Inspection Program - Owner'S Activity Report

ML070520402
Person / Time
Site:	Millstone
Issue date:	02/12/2007
From:	Jordan A Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
07-0081
Download: ML070520402 (13)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Dominion-Rope Ferry Road Waterford, CT 06385 FEB 1 2 20017 U.S. Nuclear Regulatory Commission Serial No. 07-0081 Attention:-. Document Control Desk MPS Lic/GJC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION, NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT Dominion Nuclear Connecticut, Inc. (DNC), hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-i, Owner's Activity Report for Refueling Outage 17 for Millstone Power Station Unit 2. The enclosure is in accordance with the requirements of Code Case N-532-1.

If you have any questions or require additional information, please contact Mr. David W.

Dodson at (860) 447-1791, extension 2346.

Very truly yours, A. J. Jhrdan Plant Manager - Nuclear

/IC4c 7

Serial No. 07-0081 MP2 Owner's Activity Report Page 2 of 2 Attachments:

1. Millstone Power Station Unit 2, Owner's Activity Report for Refueling Outage 17 Commitments made in this letter: None.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Serial No.: 07-0081 Docket No.: 50-336 Attachment 1 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 MILLSTONE UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Page 1 of 10 MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 Contents:

OAR- I Report Number: MP2-2R17 Table 1: Abstract of Examinations and Tests Table 2: Items With Flaws or Relevant Conditions That Required Evaluation for Continued Service.

Table 3: Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service Prepared By: Date: L,/o/

IISI Program Co0rdinator Reviewed By: Date:

Au*orized l~uclear Inservie inspector

Page 2 of 10 FORM OAR-I OWNER'S ACTIVITY REPORT Report Number MP9-2R1 7 MP2-2R17 Owner Dominion Nuclear Connecticut. RO, e Ferrv Road, Wat rford, Connecticut 06385 of 10 (Nam an drs t Ter Page 2 Plant (Nam and Addr~e~ss ot ant Unit Number 2 Commercial Service Date 12/26/1 975 Refueling Outage Number 17 (it applicamle)

Current Inspection Interval_ 3rd (lst, 2nd, 3rd,)

Current Inspection Periotd 3rd (I st, 2nd, 3rd, 4th, other)

Edition and Addenda of Section XI Applicable to the Inspection Plan 1989 Edition, No Addenda and 1998 Edition, No Addenda for Subsection IWE/IWL Date and Revision of Inspection Plan 12/21/2005 Revision 2. Change 5 Edition and Addenda of Section XI Applicable to Repairs and replacements, if Different 1998 Edition, No Addenda CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section XI.

Certificate of Authorization No. N/A Expiration Date N/A (It applicable)

... mteDa e 0 / / 7

.. ..

• er1or uwnerru.esigne Signed iidA "v, -i,#Sli Date 01 1:3 0/0 7 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 Connecticut and employed by HSB CT of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period May 19, 2005 to November 18, 2006 , and state 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 X1.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures 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 this inspection.

Commissions 12r/// 4'41 btate,A4- A*lI7 Provlfl e and Lndorsements ias ptonalr e / ord, Date ima)ý-L,2

Page 3 of 10 Table 1 ABSTRACT OF EXAMINATIONS AND TESTS (See Note 1)

(Page 1 of 2)

Total Examinations Total Total Total Examinations Credited (%) To Date Examinations Examinations Credited (%) for The Interval Examination Required for Credited for For The Period Category The Interval This Period Remarks B-A 20 0 0% 0% See Note 2, Note 7 B-B 9 3 33% 89%

B-D 34 0 0% 65%

B-E N/A 0 0% 0% Tracked under B-P pressure tests per approved Relief Request RR-89-16.

B-F 8 0 0% 100% See Note 4 B-G-1 219 73 33% 100%

B-G-2 79 7 8% 68% See Note 7 B-H 1 0 0% 0% Not required for Third Interval, MP-2 has elected to perform examination of one support skirt due to SG replacement in1992.

B-J 52 0 0% 100% See Note 4 B-K-1 0 0 0% 0% There are no items under this Category.

B-L-1 2 0 0% 100% See Note 2 B-L-2 1 0 0% 100% See Note 5 B-M-2 3 0 0% 100% See Note 5 B-N-1 3 0 0% 66%

B-N-2 15 0 0% 0% See Note 2 B-N-3 33 0 0% 0% See Note 2 B-O 15 0 0% 0% See Note 2 B-P 12 2 16% 83% Required for examination each refueling outage. The total examinations are based on 6 refueling outages anticipated during the interval.

C-A 7 0 0% 57%

C-B 6 2 33% 100%

C-C 45 6 13% 82%

C-D 0 0 0% 0% There are no items under this Category.

C-F-1 78 12 15% 78%

Page 4 of 10 Table 1 ABSTRACT OF EXAMINATIONS AND TESTS (See Note 1)

(Page 2 of 2)

Total Total Total Examinations Total Examinations Examinations Examinations Credited (%) Credited (%) To Date Examination Required for Credited for For The Period for The Interval Category The Interval This Period Remarks C-F-2 29 7 24% 90%

C-H 71 0 0% 64% Note 6 D-A 6 0 0% 66% Note 6 D-B 21 0 0% 66% Note 6 D-C 12 0 0% 66% Note 6 E-A 96 (32/ Period) 32 33% 100% 100% of the items are inspected each period E-C 43 (22 / 2n' Period) 21 48% 100% No Category E-C exams were required (21 / 3rd Period) during the 1 st inspection period.

L-A 30 30 100% 100% See Note 3 L-B 9 9 100% 100% See Note 3 F-A 277 60 21% 86%

R-A 82 29 35% 62% See Note 4, Note 8 Notes:

1. This report represents a summary of the inservice inspection activities performed at Dominion Nuclear Connecticut's Millstone Unit 2 power station during the Fall of 2006 refueling outage (2R17). This is the 1st outage in the third period of the third inspection interval.

2. For this examination Category, deferral of examinations to later in the interval is permissible in accordance with ASME Section XI, IWB-2500-1 requirements.

3. The required examination frequency for this category is every 5 years. The total examinations credited to date for the interval reflect examinations completed for the 2nd 5-Year Interval.

4. The Class 1 Risk Informed program was approved for use at Millstone Unit 2 by NRC correspondence dated 4/1/2005 and implemented during the 2nd period.

Based on this approval, Examination Category B-F and B-J have been replaced with Examination Category R-A during the 2nd period.

The total examinations required of the interval listed for category B-F and B-J now reflect the examinations that have been completed in these categories which met the 0 period percentage requirements.

5. Examinations in this category are required only if the pump or valve is disassembled for maintenance, repair, or volumetric examination.

Page 5 of 10 Notes: (continued)

6. The system pressure tests in this Category are required for examination each Period. The total examinations are based on the 3 Periods during the interval.

7. The Total Examinations Required for the Interval under Category B-A and B-G-2 reflect a decrease since last reporting due to a replacement of the Reactor Vessel Head and associated components during refueling outage 2R16.

8. The Total Examinations Required for the Interval under Category R-A reflect an increase since last reporting due to the addition of bare metal visual examinations for Alloy 600 welds based on MRP 139 requirements. The number of examinations does not reflect the VT-2 examinations that are performed each outage in conjunction with the Category B-P Class 1 pressure test.

Page 6 of 10 Table 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE (Page 1 of 3)

Flaw Characterization Flaw or relevant Examination Item Component Item Description (IWA-3300) Condition Found Category Number ID During Scheduled Section XI Examination or Test (Yes or No)

F-A F 1.30 60223A Pipe support Incomplete thread engagement of bolted connection YES evaluated as acceptable for continued service F-A F1l.40 X-23A-1-S-B Component support Missing cotter pin evaluated as acceptable for continued YES service. Replaced pin to restore support to original design condition.

F-A F1.20 410077 Pipe support Incomplete thread engagement of bolted connection YES evaluated as acceptable for continued service F-A F11.30 413122 Pipe support Incomplete thread engagement of bolted connection YES evaluated as acceptable for continued service F-A F1.20 404010 Pipe support Incomplete thread engagement of bolted connection YES evaluated as acceptable for continued service F-A F1.10 310049 Pipe support Support member in contact with conduit with minor YES corrosion evaluated by engineering as acceptable for continued service.

F-A F1.10 410032 Pipe support Incomplete thread engagement of bolted connection YES evaluated as acceptable for continued service F-A F1.30 405898 Pipe support Corrosion identified on piping and support. Cleaned YES and evaluated as acceptable for continued service.

F-A F11.30 405806 Pipe support Corrosion identified on piping and support. Cleaned YES and evaluated as acceptable for continued service F-A F1.10 510016-A' Pipe support Incomplete thread engagement of bolted connection YES evaluated as acceptable for continued service

Page 7 of 10 Table 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE (Page 2 of 3)

Flaw Characterization Flaw or relevant Examination Item Component Item Description (IWA-3300) Condition Found Category Number ID During Scheduled Section XI Examination or Test (Yes or No)

F-A F 1.20 412014 Pipe support Engineering evaluation of load setting found acceptable YES F-A F1.10 410063-R Pipe support Engineering evaluation of load setting found acceptable YES F-A F1.10 491385-E Pipe support Support missing a shim evaluated as acceptable for YES continued service. Replaced missing shim to restore support to its original design condition.

B-P B 15.70 2-SI-651 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

B-P B 15.70 2-SI-237 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

B-P B 15.70 2-SI-217 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

B-P B 15.70 2-SI-227 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

B-P B 15.70 2-SI-706A Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-114 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-615 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-625 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-635 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-645 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

Page 8 of 10 Table 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE (Page 3 of 3)

Flaw Characterization Flaw or relevant Examination Item Component Item Description (IWA-3300) Condition Found Category Number ID During Scheduled Section XI Examination or Test (Yes or No)

C-H C7.70 2-SI-452 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-456 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-SI-414 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.70 2-CS-26 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.10 X23A Heat exchanger cover bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.10 X23B Heat exchanger cover bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

• C-H C7.70 2-CH-316 Valve body to bonnet bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.50 P41A Pump flange bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

C-H C7.50 P41B Pump flange bolting Evidence of leakage at bolted connection. Evaluated YES using the criteria of Code Case N-566-1.

Page 9 of 10 Table 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE (Page 1 of 2)

Flaw or relevant Condition Found Description During Scheduled Code Repair, Item Description of Work Section Xl Date Repair/

Class Replacement, Examination or Test Completed Replacement or Corrective (Yes/No) Plan Number Measure 1 Repair Valve 2-RC-416 Repair Base Metal Indication No 06/09/2005 M20402573 1 Repair Pressurizer Repair nozzle to safe-end weld Yes (PSI) 08/15/2006 M20606471 preservice UT indications at AREVA facility 2 Repair Valve 2-SSP-1 6.1 Overhaul valve No 12/12/2006 M20503192 3 Repair Valve 2-MS-4B Repair sealing surface No 06/09/2005 M20406812-3 3 Repair RBCCW Heat Exchanger Repair area of corrosion No 12/15/2005 M20407255 3 Repair Valve 2-SW-1A Repair area of corrosion No 11/07/2006 M20406847 1 Replacement Support HGR-491291 Install new fasteners No 11/02/2006 M2-06-10372 1 Repair Valve 2-RC-233 Perform valve overhaul No 10/25/2006 M2-06-02526 2 Replacement Valve 2-FW-5A Replace valve bolting No 10/18/2006 M2-04-06844 3 Replacement RBCCW Heat exchanger X18C Replace degraded bolting No 02/02/2006 M2-05-06985 1 Replacement Pressurizer Install Replacement Pressurizer No 11/14/2006 M2-05-08280 3 Replacement Valve 2-SW-90C eplace degraded bolting No 06/20/2006 M2-05-12049

Page 10 of 10 Table 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE (Page 2 of 2)

Flaw or relevant Condition Found Description During Scheduled Code Repair, Item Description of Work Section XI Date Repair/

Class Replacement, Examination or Test Completed Replacement or Corrective (Yes/No) Plan Number Measure 3 Replacement Valve 2-FW-1 OA Replace degraded bolting No 11/17/2006 M2-05-05677 3 Repair Valve 2-SW-1A Replace degraded valve No 10/25/2006 M2-04-06847 3 Replacement Valve 2-SW-8A Replace degraded bolting No 10/31/2006 M2-05-12309 3 Replacement Valve 2-SW-1A and 2A Replace degraded bolting No 11/07/2006 M2-04-06539 3 Replacement Valve 2-SW-1B and 2B Replace degraded bolting No 11/08/2006 M2-04-06174 3 Replacement Valve 2-SW-3A Replace degraded bolting No 10/31/2006 M2-04-06540