ULNRC-05422, Owner'S Activity Report (Form OAR-1) for Refuel 14

Owner'S Activity Report (Form OAR-1) for Refuel 14

ML071770133
Person / Time
Site:	Callaway
Issue date:	06/18/2007
From:	Graessle L AmerenUE, Union Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05422
Download: ML071770133 (10)

Text

Union Electric PO Box 620 CallawayPlant Fulton, MO 65251 June 18, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-05422 DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 VAmeren UNION ELECTRIC CO.

OWNER'S ACTIVITY REPORT UE (FORM OAR-i) FOR REFUEL 14 Attached for submittal is the Owner's Activity Report (Form OAR-1) for Refuel 14 at the Callaway Plant. The report is submitted pursuant to the provisions of ASME Boiler and Pressure Vessel 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."

In accordance with Code Case N-532, attached Form OAR-1 includes an abstract of applicable Code examination and tests (Table 1A) along with an abstract of augmented examinations and tests (Table 1B), a listing of items with flaws or relevant conditions that required evaluation for continued service (Table 2) - of which there were none for Refuel 14, and an abstract of repairs, replacements, or corrective measures required for continued service (Table 3).

For any questions regarding the attached information, please contact me at 573-676-8129 or David E. Shafer at 573-676-4722.

Sincerely, Luke H. Graessle P-Manager - Regulatory Affairs TBE/jdg Attachment 4PC a subsidiaryof Ameren Corporation PRA

ULNRC-05422 June 18, 2007 Page 2 cc: Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-7D 1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360

i

ULNRC-05422 June 18, 2007 Page 3 bcc: C. D. Naslund L. M. Belsky (NSRB)

A. C. Heflin K. A. Mills L. H. Graessle T. B. Elwood T. E. Herrmann G. A. Forster D. M. Stepanovic M. G. Hoehn II G. A. Hughes S. A. Maglio D. E. Shafer A160.0761 S. L. Gallagher (100)

Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)

Send to the following without attachments:

Ms. Diane M. Hooper Mr. Dennis Buschbaum Supervisor, Licensing TXU Power WCNOC Comanche Peak SES P.O. Box 411 P.O. Box 1002 Burlington, KS 66839 Glen Rose, TX 76043 Mr. Scott Bauer Mr. Stan Ketelsen Regulatory Affairs Manager, Regulatory Services Palo Verde NGS Pacific Gas & Electric P.O. Box 52034, Mail Stop 104/5/536 Mail Station 7636 P.O. Box 56 Phoenix, AZ 85072-2034 Avila Beach, CA 93424 Mr. Scott Head Mr. John O'Neill Supervisor, Licensing Pillsbury Winthrop Shaw Pittman LLP South Texas Project NOC 2300 N. Street N.W.

Mail Code N5014 Washington, DC 20037 P.O. Box 289 Wadsworth, TX 77483

Attachment to ULNRC-05422 FORM OAR-1 OWNER'S ACTIVITY REPORT FOR REFUEL 14 CALLAWAY PLANT

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number 14 Owner AmerenUE, P.O. Box 149, St. Louis. MO 63166 (Name and Addreas of Owner)

Plant Callaway Plant. P.O. Box 620, Fulton, MOD 65251 (Name and Address of Plant)

Unit No. 1 Commercial Service Date 12/19/84 Refueling Outage No. 14 (If applicable)

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

Current Inspection Period 3rd (ist. 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plan 1989 Edition Date and revision of inspection plan Rev. 4. Januarv 27. 2003 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan 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 report conform to the requirements of Section XI.

Certification of Authorization No. N/A Expiration Date N/A S ig n ed W,*; 14 I*4} *

• Owner or O'*r's Desigr~e, Title Vr Date 3J/ 07 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 Missouri and employed by Hartford Steam Boiler of CT have inspected the items described in this Owner's Activity Report, during the period 6/14/04 to 11/19/05, 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 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.

kvo/6AuAA., Commissions A/AL 0 -1 L4 Inspector's Signaturt National Board, State, Province, and Endorsements Date .3_- i-- 2__ 0 This form (E00127) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

Callaway Plant Refuel 14 ISI Summary Report TABLE 1A ABSTRACT OF CODE EXAMINATIONS AND TESTS Examination Total Total Total Total Remarks Category Examinations Examinations Examinations Examinations Required for Credited for Credited (%) Credited (%)

the Interval this Period for the Period to Date for the Interval B-A 24 24 100% 100%

B-B 8 8 100% 100%

B-D 36 30 100% 100%

B-E 215 0 0% 100% Note 1 B-F 5 5 100% 100% Note 2 B-G-1 219 64 100% 100%

B-G-2 46 15 100% 100%

B-J 55 21 100% 100% Note 2 B-K 1 1 100% 100%

B-L-2 1 0 0% 100% Note 3 B-M-2 7 1 100% 100% Note 4 B-N-1 3 1 100% 100%

B-N-2 6 6 100% 100%

B-N-3 1 1 100% 100%

B-O 4 4 100% 100%

B-P .... 100% 100% Note 5 B-Q ........ Note 6 C-A 4 4 100% 100% Note 7 C-B 5 5 100% 100% Note 8 C-C 15 6 100% 100% Note 9 C-D 1 1 100% 100%

C-F-1 53 23 100% 100% Note 2 C-F-2 2 8 100% 100% Note 2 C-G 4 1 100% 100%

C-H Note 10 Note 10 Note 10 Note 10 Note 10 D-A 27 10 100% 100% Note 9 F-A 253 76 100% 100% Note 11 Notes:

• • indicates that this field is non applicable to this Code Category, for example B-P is required to be performed on a refueling cycle basis, not an Interval or Period basis.

1. Code requires only 25% of vessel nozzles to be examined and 100% of pressurizer penetration welds to be examined during the system VT-2 examination.

2. Number indicates RI-ISI R-A Selected welds. Number also includes those welds which were chosen under the RI-HELB, but which were C-F-1 and C-F-2 previously.

This results in the Total Examinations Credited column containing greater than 100%

of the "required" examinations in the C-F-1 and C-F-2 Categories.

3. Only the first pump disassembled for maintenance, repair, or other inspection requiresSection XI internal surface examination.

4. Only the first valve in each group disassembled for maintenance, repair, or other inspection requiresSection XI internal surface examination. Examination is required to be performed when valve is disassembled, therefore the code category maximum percentages do not apply.

Page 1 of2

Callaway Plant Refuel 14 ISI Summary Report

5. Exam category B-P VT-2 Examinations are performed each refueling outage.

6. The extent and frequency of Steam Generator tubing will be in accordance with Callaway Technical Specification 3/4.4.5.

7. Represents required examinations following replacement of all 4 S/Gs in RF14.

Category consists of two examinations on "A" RHR HX and two examinations on "B" S/G.

8. Total examinations represents required examinations following replacement of all 4 Steam Generators (S/Gs) in Refuel 14 (RF14). C-B selected examinations consist of 4 examinations on "B" S/G (FW Nozzle to Shell weld, Recirc Nozzle to Shell weld, FW Nozzle Inside Radius (IR), MS Nozzle IR, and "A" RHR HX Nozzle A to Shell weld.

9. Utilizing Code Case N-509 in lieu of this examination category. The schedule for the second ten-year interval follows the previous schedule so as not to exceed 10 years between examinations

10. Visual Exams are performed as required for a fuel cycle, 40-month and 10-year system hydrostatic testing basis. All required exams have been performed for this fuel cycle.

11. Utilizing Code Case N-491 in lieu of this examination category. Snubber numbers have decreased since the beginning of the interval due to snubber reduction program.

Page 2 of 2

Callaway Plant Refuel 14 ISI Summary Report TABLE 1B ABSTRACT OF AUGMENTED EXAMINATIONS AND TESTS Examination Total Total Total Total Remarks Category Examinations Examinations Examinations Examinations Required for the Credited for Credited (%) Credited (%)

Interval this Period for the Period to Date for the Interval NRC Standard 497/19 177 100% 100% Note 1 Review Plan Sections 3.6.1 and 6.6 Regulatory 4 4 100% 100% Note 2 Guide 1.14 Regulatory 54 0 100% 100% Note 3 Guide 1.65 Regulatory 2 2 100% 100% Note 4 Guide 1.137 Regulatory 2 7 100% 100% Note 5 Guide 1.150 Notes:

1. 497/19 refers to Original 2nd Interval ISI Plan vs. RI-HELB plan. 497 welds were originally required for the second interval, RI-HELB project reduced that number to 19.

2. Reactor Coolant Pump Flywheel examinations are performed at approximately once per ten years in accordance with Tech Spec 5.5.7 during the removal-refurbishment-reinstallation cycle.

3. This augmented requirement is not required to meet the ASME Section XI percentage limitations.

4. Regulatory Guide requires the periodic VT-2 of the Fuel System for the Standby Diesel Generators. Therefore, 100% of the examination is complete for the period.

5. All welds in this category are now examined in accordance with ASME Sec Xl Appendix VIII except for the RPV head and Shell flange welds.

Page 1 of 1

Callaway Plant Refuel 14 ISI Summary Report TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE No indications were detected Refuel 14 that required evaluation for continued service.

Page 1 of I

Table 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE (REFUEL/CYCLE 14)

Flaw or Relevant Condition Found Repair, During Scheduled Repair!

Code Replacement, Item Description Section XI Date Replacement Class or Corrective Description of Work ex tion or Completed Plan Number Measure Examination or Test (Yes[No) 3 Repair/ EFV0005 Replace 30" dia. upstream and downstream pipe spools at EFV0005 No 4/19/2005 05103454 Replacement due to significant corrosion. Task 460 = Prefabrication; Task 500 =

Installation.

Includes EMPRV Tasks 460, 500 30" Pipe: Ht. No. C9449; 30"Flanges: Ht No. 227B566.

Failure: Yes -System was declared INOP due to extent of pipe wall thinning. Detected by local pinhole leak.

3 Repair/ EFV0065 Mitigate pinhole leak in 4" ESW line by installation of NPS 1 No 2/25/2005 05102462 Replacement Nipolet and cap.

Includes EMPRV Task 0 Failure: Yes - CAR 20051124 declared System INOP due to extent of wall thinning.

Page 1 of 1