NLS2011082, Inservice Inspection Owner'S Activity Report (OAR-1) Owner'S Activity Report

Inservice Inspection Owner'S Activity Report (OAR-1) Owner'S Activity Report

ML11221A229
Person / Time
Site:	Cooper
Issue date:	08/05/2011
From:	Vanderkamp D Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2011082
Download: ML11221A229 (6)

Text

N Nebraska Public Power District Always there when you need us NLS2011082 August 5, 2011 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 Spring 2011 Refueling Outage at Cooper Nuclear Station (CNS). 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-I 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 P0. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

.......... Foim OAR-I10wner'sArtivlty Report ..

Report Number RE26-1 Plant Cooper Nuclear Station. P.O. Box 98. 72676 648A Ave, Brownvllle, NE 68321 (Name and Addrews of Plant)

Unit No. 1 Commercial Service Date 71111974 Refueling Outage No. RE26 (if applkable)

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

(11.2nd. 3rd, 4th, other)

Current Inspection Period 2nd Period (Class 1.2. 3); 1st Period (Class MC)

(Is, 2nd, 3rd)

Edition and Addenda of Section X1 applicable to the Inspection plans 2001 Edition, 2003 Addenda Date and Revision of Inspection plans Rev 2.5 for Class 1, 2, 3 approved on 31712011; Rev 1.1 for Class MC approved on 91/92010 Edition and Addenda of Section Xl 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of RE26 conform to the requirements of Section Xl. (Refueling Outage Number)

Signed Kent Sutton-Engineering Support Manag*ac.-- '-1;;ý Date - - /'

Owners or 0-&e's Designee. Moe-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 ActivityRepor, 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 Xl.

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, PatdckMcCarth * ~7 "*,-' Commissions iuM* 3I/12

• NL( I'e__/ ~

tnspecloxs Signature National Board, Stale, Province. and Endorsements Date - " ,* I I 8/2/2011 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/F1.10B RR-SB1-A - Sway Strut two (2), A loose lock nut was identified during a VT-3 examination per work order 4737600. Load settings Reactor Recirculation (RR) System were noted and evaluated as acceptable using the methodology contained in Cooper Nuclear Station (CNS) Procedure 7.2.57. A loose lock nut does not constitute a "loose support item" since it is not a load carrying member therefore the Acceptance Standards of IWF-3410(a)(2) were not exceeded and examination is considered SAT. The relevant indication was documented in the CNS Corrective Action Program per CR-CNS-2011-4144.

F-A/F1.20C MSH-1 21 - Variable Spring Excessive clamping force was reported during a VT-3 examination per work order 4768348. The Trapeze, Main Steam (MS) System relevant indication was documented in the CNS Corrective Action Program per CR-CNS-201 1-2185 and evaluated by engineering as acceptable.

E-A/E1.11 SP-EXT - Suppression Chamber Multiple suspect areas were identified with blistering paint, arc strikes, peeling paint, etc. during a Exterior Accessible Surface Areas, General Visual examination of the accessible areas of the Torus shell. The following provides a Primary Containment (PC) System detailed summary of issues in consideration with the requirements of 50.55a(b)(2)(ix)(A):

CR-CNS-2011-2269 and -2505 were generated in the CNS Corrective Action Program to document various indications on the torus exterior. Sixteen (16) locations were identified. Seven indications associated with coating degradation did not meet the requirements of IWE-3510.1 and therefore needed to be cleaned, re-examined to VT-1 requirements to further assess condition of torus shell, then repaired as needed. It should be noted that no Repair/Replacement activities were required.

Repairs were considered more cosmetic in nature and did not impact the overall structural integrity of the torus shell. The following summarizes the review of these indications CR-CNS-2011-2269 documented the following six (6) indications:

• EXT.TOR-1: Flaking and blistering paint identified with some bare metal spots showing, however, no metal loss was observed. WO 4819959 initiated to further assess condition of the base metal and to recoat as necessary. A VT-1 post cleaning examination of the bare metal area was performed SAT and the area was recoated.

• EXT.TOR-2: Two weld attachment sites discovered with and evaluated as not impacting the structural integrity of shell. WO 4819959 initiated to smooth out the attachment sites without disturbing the base metal, assess the condition of the bare metal surface and recoat as necessary. A VT-1 post cleaning examination of the bare metal area was performed SAT and the area was recoated.

• EXT.TOR-3: Several scratches to the paint were observed. WO 4819959 was initiated to assess and recoat as necessary. A VT-1 post cleaning examination of the bare metal area was performed SAT and the area was recoated.

" EXT.TOR-4: Stained area determined to be acceptable as is. No additional actions were

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 required.

• EXT.TOR-5: Previously identified location. Area determined to be acceptable as primer is still intact. No additional actions were required.

" EXT.TOR-6: Coating at this area appears to have been heated when a welded attachment was installed to the interior side of the torus shell causing a discoloration of the coating.

Inspections on the inside of the Torus confirmed the installation of a piping hanger welded to the inside of the Torus. WO 4819959 was initiated to assess and recoat as necessary.

VT-1 post cleaning examination performed SAT and the area was subsequently recoated.

CR-CNS-2011-2505 documented the following seven (7) indications:

" EXT.TOR-7: Previously identified indication with no change from previous examination.

Indication previously evaluated by CNS analysis. Therefore no additional actions were required.

• EXT.TOR-8: Previously identified indication with no change from previous examination.

Indication previously evaluated by CNS analysis. Therefore no additional actions were required.

• EXT.TOR-9, EXT.TOR-10, EXT.TOR-1 1: Arc strikes were new indications. These indications are minor in nature and are bounded by the CNS analysis that previously accepted the arc strike identified in photo EXT.TOR-1 2. Therefore no additional actions were required.

" EXT.TOR-1 3: New indication that appeared to be a concrete or grout type material. Areas of the base metal adjacent appear to be intact with areas of the top coat missing but no degradation of the base metal was evident. WO 4819959 was initiated to clean and recoat as necessary. A VT-1 post cleaning examination of the bare metal area was performed SAT and the area was recoated.

" EXT.TOR-14: New indication where base metal was exposed and coating is stained.

Degradation of the coating appears to be from leakage of a Service Water (SW) valve located directly above the area. WO 4819959 was initiated to clean and recoat as necessary. A VT-1 post cleaning examination of the bare metal area was performed SAT and the area was recoated.

" EXT.TOR-15: New indication that appeared to be similar to the indication identified in photo EXT.TOR-1 3. WO 4819959 initiated to assess and recoat as necessary. A VT-1 post cleaning examination of the bare metal area was performed SAT and the area was recoated.

• EXT.TOR-16: Indication previously identified and evaluated by CNS as acceptable.

Therefore no additional actions were recauired.

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 B-N-2/B13.40 TPGD-HDWARE Top Guide Indications were identified on the top guide aligner pins during VT-1 (BWRVIP-26-A) and VT-3 Hardware and Rim Weld: (Hold (ASME Section XI) examinations requiring evaluation for continued operation in accordance with Down Latches and Horizontal IWB-3142.4. The evaluation concluded the indications were acceptable for one cycle of operation Alignment Pins at 0, 90, 180, and until the next re-examination is performed. The indications were evaluated documented in the CNS 270 degree azimuth), bolting, rim Corrective Action Program per CR-CNS-2011-3909 and -4619.

pins, rim weld.

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Description of Repair/Replacement Plan Code Class Item Description Work Date Completed Number 3 SW-Pipe Replace Piping 3/29/2011 11-008 1 RCIC-MOV-MO15 Weld Repair Valve 7/6/2011 11-020

ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© 4 i ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS©0 Correspondence Number: NLS2011082 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

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