SVPLTR 09-0007, Owner'S Activity Report Submittal Fourth 10-Year Interval 2008 Refueling Outage Activities

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Owner'S Activity Report Submittal Fourth 10-Year Interval 2008 Refueling Outage Activities
ML090440204
Person / Time
Site: Dresden Constellation icon.png
Issue date: 02/11/2009
From: Wozniak D
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #09-0007
Download: ML090440204 (13)
v • d • e


Text

Exelon Generation Company, LLC www.exeloncorp.com Exelkn.

Dresden Nuclear Power Station NUCear 65oo North Dresden Road Morris, IL6045o-9765 February 1I, 2009 SVPLTR #09-0007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Owner's Activity Report Submittal Fourth 10-Year Interval 2008 Refueling Outage Activities This letter submits the Owner's Activity Report (i.e., Form OAR-i) and Invessel Visual Inspection (IVVI) Report for the Dresden Nuclear Power Station (DNPS) Unit 3 refueling outage (D3R20) which began on November 3, 2008, and was completed on November 21, 2008. This is the second refueling outage conducted in the second inspection period of the fourth 10-year inservice inspection interval for DNPS Unit 3. A copy of the Owner's Activity Report and IVVI Report are provided as attachments to this letter.

This Owner's Activity Report is submitted in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission," and Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 15. Code Case N-532-4 requires an Owner's Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. In accordance with the conditions of Code Case N-532-4, this OAR-1 form is being submitted within ninety days of the completion of the refueling outage.

The IVVI results are provided to report vessel internal inspections and to support B-N-1 and B-N-2 relief request exam completion.

,O'--/7

February 11, 2009 U. S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments contained in this letter.

Should you have any questions concerning this letter, please contact Mr. Steve Taylor, Regulatory Assurance Manager, at (815) 416-2800.

Respectfully, David Wozniak Site Vice President Dresden Nuclear Power Station Attachments: Owner's Activity Report, Form OAR-1 Dresden Unit 3 In-Vessel Visual Inspection Report Refueling Outage D3R20 cc: Regional Administrator - Region III NRC Senior Resident Inspector, Dresden Station

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Refueling Outage D3R20 OAR-1 Plant Dresden Nuclear Power Station, 6500 N. Dresden Road, Morris, IL 60450 Unit No. 3 Commercial Service Date 11/16/1971 Refueling Outage Number D3R20 (if applicable)

Current Inspection Interval 4th Inspection Interval (1 st, 2 nd, 3 rd, 4 th, other)

Current Inspection Period 2 nd Inspection Period (1't, 2m, 3md)

Edition and Addenda of Section XI applicable to the Inspection Plans 1995 Edition with 1996 Addenda Date / Revision of Inspection Plans 05/23/2008/ Revision 6 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-416-3, N-649, N-496-2 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of D3R20 conform to the requirements of Section XI (ryfueling outage number)

Signed J 14L A (/KV* ,ISI Coordinator Date ___l ____l_

(Owner or Owner's designee. Title)

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 Illinois and employed by The HSBCT of Hartford , Connecticut have inspected the items described in this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI By signing this certificate neither the Inspector nor his employer makes any warranty expressed or implied concerning the repair/

replacement activities and 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 this inspection Commissions IL 1546 (Inspector's Signature) National Board, State, Province, and Endorsements Date __ _ /_ __/0_J Page 1 of 3

D3R20 OAR-1 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description N/A N/A N/A I. 4 Page 2 of 3

D3R20 OAR-1 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/

Class Description Of Work Completed Replacement Plan Number 2 Indication Found During MT On 3A LPCI Heat Removed Indication Thru Surface Conditioning 11/15/08 RRP 3-08-051 Exchanger 3 Leak Found On Unit 2 CCSW Pipe Replaced Leaking Pipe 10/06/08 RRP 2-08-018 3 Leak Found On Unit 2 CCSW Pipe Replaced Leaking Pipe 10/06/08 RRP 2-08-019 3 Leak Found On Safety Related Service Water Replaced Leaking Pipe 4/04/08 RRP 2-08-009 Line Page 3 of 3

Dresden Unit 3 In-Vessel Visual Inspection Report Refueling Outage D3R20 The ASME Section XI inspections credited during D3R20 IWI activities include the once-per-period B-N-1 inspection of the reactor vessel interior and B-N-2 inspections of reactor vessel interior attachments. Credit is being taken for these examinations in accordance with Relief Request, "Alternative Requirements to ASME Section XI, B-N-1 and B-N-2 using BWRVIP Guidelines, Fleet Relief," submitted April 19, 2007, as approved in the Safety Evaluation dated April 30, 2008.

To implement the requirements of the Boiling Water Reactor Vessel Internals Program (BWRVIP), GE was contacted to perform the In-Vessel Visual Inspections (IWI). The following components and assemblies were examined:

  • 21 welds and components on jet pump assemblies in accordance with the BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (BWRVIP-41)
  • Two shroud vertical welds in accordance with the BWR Core Shroud Inspection and Flaw Evaluation Guidelines (BWRVIP-76)
  • Two shroud horizontal welds in accordance with the BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38)
  • Two top guide aligner pins and rim weld in accordance with BWR Vessel and Internals Project Top Guide Inspection and Flaw Evaluation Guidelines (BWRVIP-26-A)
  • Nine Control Rod Guide Tubes in accordance with BWR Vessel and Internals Project Lower Plenum Inspection and Flaw Evaluation Guidelines (BWRVIP-47-A)
  • Attachment welds for two core spray piping brackets, all dryer and separator guide rod brackets, and all surveillance capsule brackets in accordance with BWR Vessel and Internals Project Lower Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines (BWRVIP-48-A)
  • First time dryer examinations were performed after one cycle of operation (new dryer installed in D3R19). All critical inspections were completed with only one relevant indication. The indication was caused by contact between the dryer and a moisture separator guide rod. This indication did not affect the structural integrity of the dryer or ability to remove moisture.

Dryer inspections were performed in accordance with BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines (BWRVIP-139)

Page 1 of 2

Dresden Unit 3 In-Vessel Visual Inspection Report Refueling Outage D3R20 The following augmented examinations were also performed as part of the D3R20 IVVI activities:

" Five jet pump swing gate bolting tack welds were inspected for evidence of weld failure. These inspections were performed in response to previous tack weld failures.

  • Inspected the eight feedwater sparger end bracket surfaces for evidence of wear. These inspections were a follow-up to evidence of wear from the pins observed during D3R19. Five of the eight brackets showed evidence of wear similar to that observed during D3R1 9. Dresden will continue to monitor this condition while long-term repair options are being evaluated.
  • Six SRM/IRM dry tubes were inspected in accordance with SIL 409 guidance.
  • Beams, transition piece, and sensing lines for two jet pumps. These inspections were performed to address changes in jet pump flows as identified during the previous cycle trending.

" Three auxiliary wedges installed during the last two refuel outages. Wear was noted on two of the wedges. Dresden will continue to monitor this condition until repairs/replacements are performed.

The above BWRVIP and augmented examinations resulted in no indications requiring repair in D3R20. Additionally, there were no indications identified in the reactor interior surface as defined in B-N-1 or the reactor interior attachments as defined by B-N-2.

Page 2 of 2

OAR-1 Summary 2-05-004 00687606-01 3 2-3903 Replace DGCW pump with new SS pump. No (EC 347742) 2-06-002 00648380-01 2 2-23-Mi 151 D273 Replace bolting due to insufficient thread No engagement.

2-06-005 00903941-01 3 2-5700-30A Install T-Mod on CCSW room cooler piping No to isolate room cooler 2-5700-B.

2-06-011 00903941-04 3 2-5700-30B This plan is for repairs that are No contingencies for the CCSW room cooler.

The options are replacement of headers 2) replacement of tube bends and 3) capping of tube circuits. The option chosen will depend on what is found when the cooler is disassembled.

2-07-008 98037205-01 1 2-0203-2B Replace main disc assembly with No refurbished spare disc assembly based on results of as found internal inspections, also will replace liner with upgraded assembly.

May also replace bolting if needed if found to be worn or lost during dis-assembly/assembly. -

2-07-009 00774928-01 1 2-0305-102 Replace 102 valve and piping on Unit 2 drive No 22-31.

2-07-010 00864109-01 1 2-0305-101 Replace 101 valve and associated piping on No Unit 2 drive 38-43.

2-07-013 00894704-01 1 2-0220-62B Contingency to replace existing disc/seat No assembly with a refurbished spare to add groove for.O-ring or install new disc/seat assembly.:

2-07-021 00865029-01 1 2-305-101 Replace 101 valve and associated piping on No Unit 2 drive 50-31.

2-07-022 00925316-01 1 2-305-101 Replace 101 valve and associated piping on No Unit 2 HCU 4671.1.

2-07-023 00994918-01 1 2-305-101. Replace 101 valve and associated pip[ing No for Unit 2 HCU G-1.

OAR-i Summary 2-07-024 00881015-01 1 2-0203-3A Replace Target Rock and bolting if No necessary due to it being worn or lost during disassembly/assembly.

2-07-031 00644106-01 2 2-1105B Replace valve for IST purposes. Inlet flange No bolting may also be replaced if needed.

2-07-036 00818236-03 1 M-1 156D-2 Modify support M-1 156D-2 per EC 354971. No 2-07-037 00864830-01 1 2-305-42-19-101 Replace 101 'valve and associated piping on No HCU 42-19 on Unit 2.

2-07-039 00818236-02 1 M-1 157D-1 Modify pipe support M-1 157D-1 per EC No 354971 to facilitate the 2B recirc pump motor replacement.

2-07-040 00973006-01 MC 2-4724 Install additional AOV2-4724 and check No valve toeliminate SCRAM single point vulnerability issue. EC 351639 2-07-042 01035121-01 MC 2-2001-5 Troubleshoot valve and replace diaphragm No and bolting as needed.,

2-07-043 01035121-04 MC 2-2001-6 Troubleshoot. valve and replace diaphragm No as needed. Replace bolting as needed.

2-07-047 00818236-01 1 M-1 152D-5 Modify support M-1 152D-5 to facilitate 2B No reactor re-circ pump motor replacement per EC 354971.

2-07-049 01065522-01 3 2/3-1599-101 Replace val.ve disc (gate) and bolting as No needed based on dis-assembly and inspection.

2-07-062 01061705-01 3 LINE 2-1510-16D Replace 5'of CCSW piping in U2 Reactor No Building including: elbow that is inlet for 2A LPCI heat exchanger and upstream of 4A valve.

2-07-063 01061705-04 3 LINE 2-1510-16D Replace 5 foot of CCSW pipe in Unit 2 No Turbine Building.

2-07-064 01061705-15 3 LINE2-39308-1.5 Replace line 2-39308-1-1/2" in Unit 2 No Turbine Building.

OAR-1 Summary 2-07-065 01035258-01 3 2-1514-16"-D Perform repair on corroded CCSW line by No grinding away corrosion and welding back up.

2-07-069 01077358-01 2 2-1301 Reweld the splash baffle support bracket to No shell interior 2-07-071 01035258-09 3 2-1514-16" Repair of min wall ihdication on line by No welding branch connection 2-07-075 01079263-01 1 SPT X-105B Modify support.X-1 05B per EC 1079263. No 2-08-001 00908785-01 3 2-5747 Replace inlet' Jnioh to-HPCI room cooler if No necessary durinjg performance of PM's.

2-08-003 00637538-01 2 2-2301-71 Dis-assemble .and inspect 2-2301-71 valve. No RRP prepared after.work done. See IR 724101. -

2-08-004 00983828-01 2 2-1105A Replace-SBLC relief valve and the inlet No bolting if necessary.

2-08-005 01080352-01 2 2-1105B Rebuildthe SBLC relief valve that was No removed from Unit 2, 2B train under WO 644106-01 and return to Stores.

2-08-006 01083310-01 2 SPR FDWTR CHK Refurbish spare feedwater check valve No assembly removed under WO 644107-01.

2-08-007 01087103-01 1 2-305-38-03-107 Replace valve disc based on seat leakage. No 2-08-023 00983828-07 2 2-1105A Rebuild valve if required after pop test. No 3-06-005 00756524-01 2 3-1501-63A Inspection of valve for license renewal could No involve replacement of entire valve. Bolting may also be replaced if needed.

3-06-007 00763064-01 1 3-0220-62B Contingency to replace existing disc/seat No assembly with a refurbished spare modified to add groove for O-ring or install new disc/seat assembly.

OAR-i Su mmhary Contingencyto replace existing disc/seat assembly with a refurbished spare modified to add-groove for O-ring or install new disc/seat assembly.

3-06-056 99207934-05 3 3-6669A & B PM replacement of DGCW heat No exchangers. Extento'f replacement will be based-onas'found: condition. Bolting may be replaced iifdamagedduring removal or to facilitate installattion. Include replacement of SW supply and return flex hoses in this repair. :

3-06-057 00920390-01 3 3-39245-2"-0 Replace line 3-39245-2-0 that was No identified as having thinning walls per NDE.

Also valves. 3-3999-342 and 3-3999-344 will also be replaced.

3-06-061 00955183-01 1 3-0299-113A TCCP to add instrument between reference No leg inside Class I boundary 3-07-004 01019346-01 2 3-2301-3 Replace valve bonnet on 3-2301-3 valve. No 3-07-013 01035225-01 1 3-305-58-23-138 Replace ball on check valve 138 for HCU 58- No 23.

3-07-015 99019536-01 2 3-1501-17A Replace valve for IST purposes. Bolting may No be replaced if necessary.

3-07-016 99244566-01 2 3-1402-28A Replace relief valve for IST purposes. No Bolting may be replaced if needed.

3-08-002 00996486-01 3 3-3933-502 Replace 3-3933-502 valve and bolting as No required.

3-08-003 00568410-01 2 3-2301-23 Replace 3-2301-23 relief valve and inlet No bolting if necessary.

3-08-004 00911669-12 3 2/3-6669-B Replace 2/3 DG 'B' cooling water heat No exchanger~and bolting if necessary.

3-08-005 00911669-15 3 2/3-6669-A Replace 2/3.'A' cooling water heat No exchanger and bolting if necessary.

3-08-006 01108194-01 3 3-1514-16" Replace,degraded; section of CCSW pipe as No identified in NDEreport 08-044.

OAR-l Summary Irual0u,PAW. I I I I 3-08-009 00880955-01 2 3-2301-7 Replae'va6lve disc ifrequired based on No ult8s inspecti6n res*s 3-08-011 01127494-01 2/3 3-1503-B Contingency to replace LPCI heat No exchanger bolting if lost or damaged.

3-08-012 00996870-01 3 3-5746-B Replac.e, rom c6oler boil and union as No needed bn.3B'LPCI room cooler.

3-08-013 00767123-01 2/3 3-1503-A Contingency to replace 3A LPCI heat No exchanger bolting if lost or damaged during inspection:* - " . ý "

3-08-014 00771004-01 1 3-0203-3E Replace ERV relief valve 3E. Bolting may be No replaced if required. ..

3-08-016 00773054-01 1 3-0203-3B Replace ERV relief valve 3B. Bolting may be No replaced if required.

3-08-017 00773036-01 1 3-0203-4H Replace Unit 3 MSSV 4H for IST purposes. No Inlet flange may also .be machined if found damaged or pitted per Task 05.

3-08-018 00773039-01 1 3-0203-4F Replace Unit 3 MSSV 4F for IST purposes. No Inlet flange may also be machined if found damaged or pitted per Task 05.

3-08-020 00773058-01 1 3-0203-4E Replace Unit 3 MSSV 4E for IST purposes. No Inlet flange may also be machined if found damaged or pitted per Task 05.

3-08-021 00993086-01 1 3-0203-3A Replace Unit 3 Target Rock valve 3A for IST No purposes. Inlet flange may also be machined if found damaged or pitted per Task 05.

3-08-022 00974093-01 1 3-305-30-23-102 Replace Unit 3 "102" valve on HCU 30-23, No 3-08-027 99237611-01 MC 3-4399-915 Replacerelief valve for IST purposes. Inlet No flange bolting may also be replaced if damaged worn 6r.lost.

3-08-034 01160392-01 MC 3-2001-106 Replace*valve;diaphargm and troubleshoot No interneil,: Replace .asirequired. Valve bolting may be replace. as:'needed.

3-08-035 01160392-04 MC 3-2001-105 Replace'v'alve dia'Ohragm, spindle and No bolting asrequired.. ,

OAR-i1Summnary Page: 6

-1 Descriptionh of: Repair/Replacement II OAR-1 Reporable Dbase Record 3-08-037 00996944-01 MC 3-2001-05 Replace valvaedia~phragm and overhaul. No 3-08-038 00996947-01 MVC 3-2001-06 Replace valve-diaphragm and overhaul. No 3-08-040 00989661-01 3 3-5747 Replace inlet union to HPCI room cooler if No necessary during performance of PM's.

3-08-041 01005909-05 1 CRDM'S Replace, CQRDM'sduring D3R20 per tasks 5 No thr 24.

3-08-052 989684-01 1 3-0205-27 Remove, inspect, repair and ifrequired No replace Head Cooling check valve and bolting.

3-08-056 00978519-22 MC TORUS HATCH Bolting missing and will be replaced No

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