NLS2010016, Inservice Inspection OAR-I Owner'S Activity Report for the Fall 2009 Refueling Outage

Inservice Inspection OAR-I Owner'S Activity Report for the Fall 2009 Refueling Outage

ML100470200
Person / Time
Site:	Cooper
Issue date:	02/02/2010
From:	Vanderkamp D Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2010016
Download: ML100470200 (5)

Text

N Nebraska Public Power District "Always there when you need us" NLS2010016 February 2, 2010 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Inservice Inspection OAR- I Owner's Activity Report Cooper Nuclear Station, Docket No. 50-298, DPR-46

Dear Sir or Madam:

The purpose of this letter is to provide to the Nuclear Regulatory Commission the Inservice Inspection OAR-I Owner's Activity Report for the Fall 2009 Refueling Outage at Cooper Nuclear Station. This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Code Case N-532-4. The enclosure contains the completed OAR-1 Owner's Activity Report form, a table identifying the description of items with flaws or relevant conditions that required evaluation for continued service, and a table providing an abstract of repair/replacement activities required for continued service..

Should you have any questions regarding this matter, please contact me at (402) 825-2904.

Sincerely, David W. Van Der Kamp Licensing Manager

/dm Enclosure cc: Regional Administrator w/enclosure NPG Distribution w/o enclosure USNRC - Region IV Senior Resident Inspector w/enclosure CNS Records w/enclosure USNRC - CNS Cooper Project Manager w/enclosure USNRC - NRR Project Directorate IV-1 COOPER NUCLEAR STATION 04-7 PO. Box 98/ Brownville, NE 68327-0098 Telephone: (402) 825-387 / Fax: (402) 825-5211 ý.s www nppd.corn

or*Cooper Nuclear Saion FormOAR-I Owner's Activity Report Report Number RE25-1 Plant Cooper Nuclear Station, P.O. Box 98, 72676 648A Ave, Brownville, NE 68321 (Name and Address of Plant)

Unit No. 1 Commercial Service Date 7/1/1974 Refueling Outage No. RE25 (if applicable)

Current Inspection Interval 4th Interval (Class 1, 2, 3); 2nd Interval (Class MC)

(1st. 2nd, 3rd, 4th, other)

Current Inspection Period 2nd Period (Class 1, 2, 3); 1st Period (Class MC)

(1st. 2nd, 3rd)

Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition, 2003 Addenda Date and Revision of inspection plans Rev 2 for Class 1, 2, 3 approved on 6125/09; Rev 1 for Class MC approved on 4/7/09 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Case used: N-460, N-686 (approved via Relief Request RI-37); N-532-4 (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 by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of RE25 conform to the requirements of Section XI. (Refueling Outage Number)

Signed Todd Hottovy-Engineering Support Manager/ _r( 6T /0 Date . - 6 -, C Owners 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 Nebraska and employed by HSBCT of Hartford, Connecticut have inspected the items described in this Owner's ActivityReport, 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 loss of any kind arising from or connected with this inspection.

Kurt Saltzman/ Commissions NBI1047A, N, I, C, NS NE10094 4

Inspector's Signa/ re National Board. State, Province, and Endorsements Date 1/d 2fC 1/612010 ScheduleWorks V. 8.1 Page I - I

Cooper Nuclear Station Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number F-A/F1.20A RHH Residual Heat Removal Class 2 Loose anchor bolts were reported by the examiner during a VT-3 examination per work order hanger. 4654056. The examiner reported the presence of a gap between a portion of the support base plate and concrete ceiling assuming the bolting was loose. This examination was performed as a successive examination when the bolting was discovered to be loose during a scheduled ISI examination in the previous outage. The work order was revised to determine the cause of the base plate gap and confirm whether the bolting was loose or tight. Cooper Nuclear Station (CNS)

Maintenance confirmed the bolting was tight and the partial gap was due to irregularities between the base plate and concrete so no condition actually existed. The relevant indication was entered into the CNS Corrective Action Program per CR-CNS-2009-6435.

F-A/F1.20B HPH-1 1 - High Pressure Coolant Injection Missing washers were identified during a VT-3 examination per work order 4654051. The relevant Class 2 stanchion support. indication was evaluated by Engineering as acceptable as the missing washers were not "load support items" therefore scope expansion was not required. The relevant indication was entered into the CNS Corrective Action Program per CR-CNS-2009-6856.

F-A/F1.30A HPH High Pressure Coolant Injection Missing paint was identified on the support during a VT-3 examination per work order 4654051.

Class 3 stanchion support. Engineering evaluation determined that the loss of paint was a non-relevant indication and therefore did not need repair or scope expansion. The relevant indication was entered into the CNS Corrective Action Program per CR-CNS-2009-6756.

F-A/Fl.20B PSA Scram Discharge Volume Class 2 One of the anchor bolts was identified as not having full thread engagement during a VT-3 Restraint Box Frame. examination per work order 4654059. Engineering evaluated the condition as acceptable therefore no scope expansion was required. The relevant indication was entered into the CNS Corrective Action Program per CR-CNS-2009-6855.

E-A/E1.30 DWI-MB - Drywell Moisture Barrier. A 4 1/2" long section of the moisture barrier (MB) was identified as degraded during a VT General Visual examination. The entire MB was examined so no scope expansion was required. Engineering evaluation concluded the section of the MB needed to be replaced. The degraded condition was documented in CR-CNS-2009-7281. Work order 4640510 was revised to repair the section of MB.

The work order was revised to clean the area of the drywell liner prior to repair. The liner was not degraded so only the MB needed to be repaired based on discussions between the Coatings Engineer and Maintenance individual that prepped the area for the MB repair. A visual VT-3 examination of the repaired area was subsequently performed as satisfactory.

Cooper Nuclear Station Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Date Completed Repair/Replacement Work Plan Number 3 SW Pipe Tee & Repair Pipe Tee & 10/20/2009 08-011 Flange Flange by Welding 2 RHR-CV-19CV Blend Grind 11/05/2009 09-051 Indications on Replacement Valve 3 SW-P Refurbish Pump 8/06/2009 09-056 Columns and Discharge Head 3 SW-Pipe Replace local Pipe 12/15/2009 09-068 Section due to Wall Thinning 3 SW-Pipe Replace Local Pipe 12/14/2009 09-069 Section due to Wall Thinning MC Drywell Head Replace Nut & 12/15/2009 09-073 Washer Damaged during Disassembly 2 RW-AOV-A095 Repair Valve to 12/15/2009 09-075 Remove Pits from Bonnet Seal Area MC PC-PENT-X1A Replace Three 11/05/2009 09-077 Eyebolts

4 ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS@4 Correspondence Number: NLS2010016 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None N/A N/A PROCEDURE 0.42 REVISION 24 PAGE 18 OF 25