ML060380567

Inservice Inspection Program - Owner'S Activity Report

ML060380567
Person / Time
Site:	Millstone
Issue date:	01/24/2006
From:	Price J Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-031
Download: ML060380567 (11)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station w7VDominion-Rope Ferry Road Waterford, CT 06385 JIN 24 Wm U.S. Nuclear Regulatory Commission Serial No.06-031 Attention: Document Control Desk MPS Lic/RWM RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT., INC.

MILLSTONE POWER STATION UNIT 3 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT Dominion Nuclear Connecticut, Inc. (D1NC), hereby submits the American Society of Mechanical Engineers (ASME), Section Xl, Form OAR-1, Owner's Activity Report for Refueling Outage 10 for Millstone Power Station Unit 3. The enclosure is in accordance with the requirements of Code Case N-532.

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

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

Very truly yours, J. rice Si ce President - Millstone Enclosure(s):

1. Millstone Power Station Unit 3, Owners Activity Report for Refueling Outage 10 Commitments made in this letter: None.

40q 7

Serial No.06-031 Owner's Activity Report Page 2 of 2 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.: 06-031 Docket No.: 50-423 Enclosure I INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 10 MILLSTONE UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Page I of 8 MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 10 Revision 0 Contents:

OAR-I Report Number: MP-3, 3R010 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: ci ,oo46 ISI ProgrqaCoordinaltor Reviewed By:

Aithorizedt lear Inservice Inspector

Page 2 of 8 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number MP-3. 3RO10 Owner Dominion Nuclear Connecticut. Ro Feir Road. Waterord (ame {m Owner)Orford Connecticut Conetiu 06385 Plant Millstone Nuclear Power Station. Rome Ferry Road Waterford Connecticut (Name anOAddress 0n Inlantj Unit Number 3 Commercial Service Date_ Aoril 23, 1986 Refueling Outage Number 10 (it applicable)

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

Current Inspection Period 2nd (Ist, 2nd, 3rd, 4th, oiher)

Edition and Addenda of Section Xl Applicable to the Inspection Plan 1989 Edition. No Addenda Subsection IWE/IWL - 1998 Edition. No Addenda Date and Revision of Inspection Plan January 15. 2005, Revision 01. Change 6.

Subsection IWE/IWL - January 30. 2001. Revision 1 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 inthis 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 ale Expiration Date N/A Signed IL-V A -

SnPlgn, Zto l e r o d00Dat Date Dae CERTIFICATE OF IINSERVICE 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 inthis Owner's Activity Report, during the period May 9, 2004 to October 26. 2005 , and state to the best of my knowledge and belief, the Owner has performed all activities represented by this report inaccordance with the requirements of Section Xl.

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 inthis report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions_ - o

_,,01( aroF I;Z c a Na~ionalBr,' W, rowce ana naorsemens

Page 3 of 8 Table 1 ABSTRACT OF EXAMINATIONS AND TESTS (See Note 1)

Total Total Examinations Examinations Total Examinations Total Examinations Examination Required for Credited for Credited (%) Credited (%) To Date Category The Interval This Period For The Period for The Interval Remarks B-A 24 1 4 25 Note 2 B-B 3 0 0 66 B-D 44 2 4 45 Item numbers B3.90 and B3.100 utilize Code Case N-521 which allows deferral to the end of the Interval.

B-E 2 0 0 0 See Note 2 B-F 4 0 0 100 See Note 3 B-G-1 221 2 1 58 B-G-2 62 18 29 82 B-H 9 0 1u Reiief Request iR-2-4 granted to perform aii (9) examinations in one period.

B-J 60 0 0 100 See Note 3 B-K-1 9 2 22 78 B-L-1 N/A N/A N/A N/A There are no components under this

._ Category at Millstone Unit 3.

B-L-2 0 0 0 0 Required only if disassembled during maintenance activity, B-M-1 N/A N/A N/A N/A There are no components under this Category at Millstone Unit 3.

B-M-2 4 0 0 100 Required only if disassembled during maintenance activity.

B-N-1 3 0 0 66 100% are examined each Inspection period.

(1/Period)

B-N-2 7 0 0 0 See Note 2

Page 4 of 8 Table 1 ABSTRACT OF EXAMINATIONS AND TESTS (See Note 1)

Total Total Examinations Examinations Total Examinations Total Examinations Examination Required for Credited for Credited (%) Credited (%) To Date Category The Interval This Period For The Period for The Interval Remarks B-N-3 2 0 0 0 See Note 2 B-O 4 0 0 100 See Note 2 B-P 36 6 16 83 Required for examination each refueling outage. Number and percentage are based on the number of refueling outages

_ ___ _ anticipated during the Interval.

C-A 6 0 0 50 C-B 13 2 15 76 See Note 6 C-C 39 14 35 92 C-D 2 0 0 50 See Note 4 C-F-2 38 8 21 84 C-G 11 0 0 55 C-H 86 10 11 74 See Note 6 D-A 30 6 20 83 See Note 6 D-B 124 28 22 79 See Note 6 D-C 4 0 0 75 See Note 6 E-A 105 0 0 66 100% of the items are examined each (35/Period) Inspection Period. TheTotal Examinations Required reflects the total for all (3) Periods.

E-C 44 0 0 50 See Note 7 22/Period L-A 34 0 0 100 See Note 5

Page 5 of 8 Table 1 ABSTRACT OF EXAMINATIONS AND TESTS (See Note 1)

Total Total Examinations Examinations Total Examinations Total Examinations Examination Required for Credited for Credited (%) Credited (%)To Date Category The Interval This Period For The Period for The Interval Remarks L-B N/A N/A N/A N/A There are no components under this I_ I_ IICategory at Millstone Unit 3.

F-A 262 58 22 83 1 R-A 91 15 16 71 See Note 9, Note 10 Notes:

1. This report represents a summary of the Inservice Inspection activities performed at Dominion Nuclear Connecticut's Millstone Unit 3 power station during the Fall of 2005 refueling outage (RFO1 0). This is the first refueling outage of the second inspection period of the second inspection interval.

2. For this Examination Category, deferral of examinations to later in the interval is permissible, in accordance with ASME Section Xl, IWB-7500-1

3. Examination Category B-F and B-J have been replaced with the implementation of the Risk Informed inspection program for Class 1 piping Examination Category R-A. The number of examinations listed under the Total Examinations Required for the Interval for these categories reflect the number of examinations completed meeting the percentage requirements for the first inspection period.

4. Percentage requirements in this category cannot be met for each period due to only 2 items in the category.

5. Examination frequency for this Category is once every five years. The total examinations listed for the interval reflect completion for the first five-year interval. Examinations for the second five-year interval are scheduled to be completed in March of 2006.

6. This examination Category includes VT-2 (Pressure Test) inspection items required to be completed once each period.

7. This Category reflects locations identified during the 15t period that are required for examination during period 2 and period 3.

8. Relief requests shall be submitted for those examinations in which limitations exist such that at least 90% examination coverage could not be obtained.

9. Category increased by an additional (8) welds based on the Class 1 Risk Informed Program period review.

10. Five (5) Pressurizer nozzle to safe-end dissimilar metal welds were examined using a combination of RT and UT methods as an augmented inspection scope based on Millstone's commitment to Regulatory Bulletin 2004-01.

Page 6 of 8 Table 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE 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 F1.30 3-SWP-PSST040 Pipe support Loose lock nut evaluated as acceptable for continued YES service. Tightened nut to restore support to original design condition.

F-A F1.20 3-SIH-PSST377 Pipe support Loose lock nut evaluated as acceptable for continued YES service. Tightened nut to restore support to original design condition.

F-A F1.10 3-RCS-1-PSR416 Pipe support Missing clip evaluated as acceptable for continued YES service. Replaced clip to restore support to original condition.

C-F-2 C5.51 FWS-12-FW-3-DM Feedwater System piping weld Planar indication evaluated as an acceptable NO (1)

Non-relevant indication.

C-F-2 C5.51 MSS-31-FW-1-CM Main Steam System piping weld Base metal surface indication evaluated by Engineering NO (1) as an original fabrication lap. Blended and reexamined as acceptable.

C-F-2 C5.51 MSS-35-FW-1 Main Steam System piping weld Inclusion type indication evaluated as acceptable to NO (1)

IWB-3000 acceptance criteria B-G-2 B7.70 SIL*V932 Valve body to bonnet bolting Identified leakage evaluated as originating from valve YES packing, cleaned and reexamined as acceptable.

B-P B 15.70 SIL*V006 Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B 15.70 SIL*V007 Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B 15.70 SIL*V012 Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

Page 7 of 8 Table 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Characterization Flaw or relevant Examination Item Component Item Description (IWA-3300) Condition Found Category Number ID During Scheduled Section Xl Examination or Test (Yes or No)

B-P B 15.70 SIL*V017 Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B15.70 SIL*V015 Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B15.70 SIL*V987 Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES l_ _ lcriteria of Code Case N-566-1.

B-P B15.70 RCS*AV8037A Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B 15.70 RCS*AV8037B Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B15.70 RCS*AV8037D Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B 15.70 RCS*MV8003A Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B 15.70 RCS*MV8003C Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES

__ criteria of Code Case N-566-1.

B-P B15.70 RCS*MV8003D Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

B-P B 15.70 RHS*MV8701A Valve body to bonnet bolting Leakage at bolted connection. Evaluated using the YES criteria of Code Case N-566-1.

Note: (1) C-F-2 welds identified above were examined for High Energy Line Break augmented examination program

Page 8 of 8 Table 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or relevant Condition Found Repair, During Replacement, Description Scheduled Repair/

Code or Corrective Item Description of Work Section Xi Date Replacement Plan Class Measure Examination or Completed Number Test (Yes/No)

I Repair Pressurizer spray Machine and perform Yes 10/18/2005 M3-05-14478 nozzle to safe-end, weld overlay per dissimilar metal weld approved Relief 03-X-5641-E-T Request IR-2-39 2 Replacement Valve Replace Valve due to Yes 10/09/2005 M3-01-22351

_ _ _ _ _ v'o

_t_IA A Lt sL Id,,u I-e 3 Replacement Valve Replace Valve No 07/09/2004 M3-04-09727 3WTC*V846 3 Replacement Valve Install Temporary blind No 08/12/2004 M3-04-11702 3SWP*V697 flange in place of valve 2 Replacement Snubber Replace snubber Yes 10/12/2005 M3-04-17234 3MSS-1-PSSP0555 .

2 Repair Line No. Blend out base metal Yes 10/15/2005 M3-05-14196 3MSS-008-51-2 indication found during surface examination of weld MSS-31 -FW-1 -CM