ML070430462

Containment Inservice Inspection Program First Interval, Third Period, Refueling Outage 15 Owner'S Activity Report

ML070430462
Person / Time
Site:	Wolf Creek
Issue date:	01/31/2007
From:	Moles K Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 07-0011 WCRE-11, 11-P3-RF-15
Download: ML070430462 (7)

Text

W@LF CREEK 'NUCLEAR OPERATING CORPORATION January 31, 2007 Kevin J. Moles Manager Regulatory Affairs RA 07-0011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

References:

1) Letter ET 95-0112, dated October 31, 1995, from R. C.

Hagan, WCNOC, to USNRC

2) Letter WO 95-0189, dated December 27, 1995, from 0.

L. Maynard, WCNOC, to USNRC

3) NRC Letter dated February 9, 1996, from USNRC to N.

S. Carns, WCNOC

Subject:

Docket No. 50-482: Containment Inservice Inspection Program First Interval, Third Period, Refueling Outage 15 Owner's Activity Report Gentlemen:

This submittal provides the Owner's Activity Report for Refueling Outage 15 (RF15),

which is the first outage of the third period of the first interval of the Wolf Creek Nuclear Operating Corporation (WCNOC) Containment Inservice Inspection Program. American Society of Mechanical Engineers (ASME) Code Case N-532, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000," requires that an Owner's Activity Report (Form OAR-i) be prepared and certified upon completion of each refueling outage. Each Form OAR-1 prepared during an inspection period shall be submitted following the end of the inspection period. The RF15 Form OAR-1 is also submitted in accordance with Wolf Creek Generating Station (WCGS)

Technical Requirements Manual 3.6.1, which requires the submittal of the Form OAR-1 within 90 days of the completion of the refueling outage for the operational cycle in which tendon surveillance testing was performed.

In References 1 and 2, WCNOC requested use of ASME Code Case N-532 in lieu of current ASME Section Xl reporting requirements. In Reference 3, the Nuclear Regulatory Commission (NRC) concluded that the proposed alternative to use Code Case N-532 and the clarifications contained within References 1 and 2 provide P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET 40vK

RA 07-0011 Page 2 of 2 an acceptable level of quality and safety and approved the use of Code Case N-532 for use at WCGS.

The enclosure provides the Owner's Activity Report (Form OAR-i) for the period of May 20, 2005 through November 10, 2006 (RF14 ended May 19, 2005 and RF15 ended November 10, 2006). This timeframe constitutes operational cycle 15, which is the first operational cycle of the third period of the first interval of the WCNOC Containment Inservice Inspection Program. The enclosed Form OAR-1 (Report WCRE-11, I1-P3-RF15) corresponds to this cycle.

There are no commitments contained within this letter.

If you have any questions concerning this matter, please contact me at (620) 364-4126 or Ms. Diane Hooper at (620) 364-4041.

Very truly yours, Kevin J. Moles KJM/rlt Enclosure cc: J. N. Donohew (NRC), w/e V. G. Gaddy (NRC) w/e B. S. Mallett (NRC), w/e Senior Resident Inspector (NRC), w/e

FORM OAR-I OWNER'S ACTIVITY REPORT Report Number -WCRE- 11, 11l-P3-RF- 15 Owner Wolf Creek Nuclear Operating Corporation. 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Owner)

Plant Wolf Creek Generating Station, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Plant)

Unit No. I Commercial service date 9-3-85 Refueling outage no. 15 (If applicable)

Current inspection interval I" Interval for the Containment Inservice Inspection Program (1st. 2nd. 3rd. 4th. other)

Current inspection period 3 'n period for the Containment Inservice Inspection Program

• (Ift. 2nd. 3rd)

Edition and Addenda of Section XI applicable to the inspection plan 1998 edition with no addenda Date and revision of inspection plan WCRE-I I Rev. 3, dated 9-21-2006 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan 1992 edition with 1992 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 rebort conform to the requirements of Section XI.

Certificate of Authorization No. N/A Expiration Date N/A (If antlicable)

Signed Dennis E. Tougaw "FZ1rd Engineer Date January 25, 2007 OKnr o'r Owner's- Def~gnee, 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 Kansas and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period May 20, 2005 to November 10, 2006 , 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 req uirements of Section XI.

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.

,-(J*'*l- f 1- . Commissions KS#594 A, N, I ln'*pet*c s Signature National Board, State, Province, and Endorsements Date Date fo rS This form (E00127) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 OAR-I II-P3-RF-15 Page I of 5

TABLE I ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-15 (I-1, P-3)

Total TotalTtl Tota6":Exminat'o'n~s

--d Examinations Examinations Examinations Credited,,(%),

Eaiain Required For Credited for This C red'ited (%) for bate for the Categor6 Tinteral Perio& e Period* interval Remarks E-A 823 5 1 67 tNote I E-C 8 1 12 50 Note 2 L-A 12. 6 50 100 Note 3 L-B 26 26 100 100 Notes 3, 4 t*

This column is interpretedto represent the cumulative number of exams performed to date in this period.

Note 1: 100% of the Accessible Surface Areas of Category E-A are required to be inspected each Inspection Period per Table IWE-2500-1 Note 2: In accordance with IWE-1241, 4 components were reclassified as Category E-C in Period 2 resulting in 8 examinations in this Category being required for the Interval.

Note 3: The IWL components (Categories L-A and L-B) are'examined on a 5 year period basis at this point in the WCGS plant life. The IWL periods in the current Containment Inservice Program Plan correspond to the 15th and 20' year anniversary.

Note 4: As permitted by 10 CFR 50.55a, the initial examination of the tendons was conducted in accordance with the existing Tech Spec program. Thus only the tendon examinations after revision of the Tech Specs to utilize IWL (the 20'h year anniversary) are listed.

OAR-I I1-P3-RF'-15 Page 2 of 5

TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATIONFOR CONTINUED SERVICE Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization (IWA- During Scheduled Section Xi Category Number 3300) Examination or Test (Yes or No)

L-A L 1.12 Tendon Anchorage Areas Small amount of grease Yes of Tendon Access Gallery; leakage noted.

Vertical Grease Caps L-B L2.40 Tendon 22CB; Corrosion The absolute difference Yes Protection Medium between the amount removed and the amount replaced exceeded 10 percent of the tendon netduct volume.

L-B L2.40 Tendon IAC; Corrosion The absolute difference Yes Protection Medium between the amount removed and the amount replaced exceeded 10 percent of the tendon net duct volume.

L-B L2.40 Tendon 46BA Corrosion The absolute difference No Protection Medium between the amount removed and the amount replaced exceeded 10 percent of the tendon net duct volume.

L-B L2.40 Tendon V65 Corrosion The absolute difference Yes Protection Medium between the amount removed and the amount replaced exceeded 10 percent of the tendon net duct volume.

Attachment 1 provides further information as required by the Containment Inservice Inspection Program.

OAR-I II-P3-RF-15 Page 3 of 5

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/

Replacement, Section XI Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description of Work Test (Yes/No) Complete Number There were no repairs, replacements, or corrective measures performed on any Class MC or CC items during the period of this report, which were required due to an item containing a flaw or relevant condition that exceeded acceptance criteria.

OAR-I I1-P3-RF-J5 Page 4 of 5

Attachment 1 RF-15 IWL Examination

1. The condition noted in Table 2 of the absolute difference between the amount removed and the amount replaced exceeding 10 percent of the tendon net duct volume for Tendons 22CB, lAG, 46BA and V65 was evaluated in CCP 11852. The amounts replaced ranged from 10.7%

to 17.35% of the net duct volume. This evaluation noted that the leak-tightness and structural integrity of containment is maintained.

2. All de-tensioned tendons were re-tensioned with acceptable elongations. The re-tensioning force of tendons were within the limit of 10% from that recorded during the last measurement.

3. The sheathing filler (grease) samples were tested and found to contain less than 10 percent by weight of chemically combined water (Chlorides, Nitrates, and Sulfides) or the presence of free water.

4. All tendons were resealed and re-greased.

5. During general visual examination of the containment surface, no grease leakage was on the containment surface. However; as noted in Table 2, grease leakage was noted on the tendon anchorage areas of the grease caps in the Tendon Access Gallery. This was evaluated in SWO 05-275375-001. The evaluation finds that this small leakage is not a non-conformance.

6. Tendon 46BA is not part of original 2 0 th year tendon inspection scope. The tendon was regreased due to the grease can being changed out at this location.

OAR-I IJ-P3-RF-15 Page 5 of 5