1CAN110702, Inservice Inspection (ISI) Summary Report

Inservice Inspection (ISI) Summary Report

ML073270064
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/13/2007
From:	James D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
1CAN110702 OAR-1332
Download: ML073270064 (5)

Text

Entergy Operations, Inc.

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...... 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4819 Dale E. James Mai;ager L'c',unin, 1CAN 110702 November 13, 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Inservice Inspection (ISI) Summary Report Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51

Reference:

1. Entergy letter to NRC dated August 13, 2007, Inservice Inspection (ISI) Summary Report, Arkansas Nuclear One - Unit 1, (1CAN080701)

Dear Sir or Madam:

On August 13, 2007, Entergy submitted the above referenced Inservice Inspection (ISI)

Summary Report for ASME Class 1, 2, and 3 pressure retaining components and their supports for Arkansas Nuclear One, Unit 1 (ANO-1). In that report, Entergy committed to provide a follow-up revision to Table 1 of the original report in order to present the remaining information related to the progress of examinations in certain categories for the applicable inspection interval and period. The attached table provides the completed abstract of examinations and tests associated with Owners Activity Report OAR-1 332.

There are no new commitments contained in this correspondence. Should you have any questions regarding this report, please contact Fred Van Buskirk of my staff at (479) 858-3155.

Sincerely, DEJ/fpv A 0LO Attachment

1CAN 110702 Page 2 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan Wang Mail Stop O-7D1 Washington, DC 20555-0001

, I Attachment

.1CAN110702 Table 1 of OAR-1332

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number OAR-1332 Rh1 Owner Enteray Arkansas, Inc./ P.O. Box 551, Little Rock, AR. 72203 (Name and Address of Owner)

Plant Arkansas Nuclear One/ 1448 S.R. 333, Russellville, AR. 72802 (Name and Address of Plant)

Unit No. 1 Commercial service date December 19. 1974 Refueling outage no. 1R20 (If applicable)

Current inspection interval Third (3rd) Inspection Interval (1st. 2nd, 3rd, 4th. other)

Current inspection period Third (3nd) Inspection Period (1St, 2nd, 3rd)

Edition and Addenda of Section X1applicable to the inspection plan 1992 Edition, Portions of 1993 Addenda for Pressure Testinq Date and revision of inspection plan July 26, 20051 Revision 304: through PCN-18 Edition and Addenda of Section XAapplicable to repairs and replacements, if different than the inspection plan Same CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, test, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section Xl, Certificate of Authorization No. N/A Expiration Date N/A (Ifapplicable) o DManager, g Proorams&

TtI Components Date fl-

'/C v er or Owner's Designee, Tidie I 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 Arkansas and employed by HSBCT of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period December 24, 2005 to May 12. 2007 . and state that to the best of my knowledge and belief, the Owner has performed all activites 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 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.

L ý

,ax Commissions NS-9985. ARK-1054"A B "N" "" NS Inspector's Signature I National Board, State, Province, and Endorsements Date II- 2. - )'.L0"1 I ;Nm mllm*nr This form (EO01 27) may be obtained from the Order Dept, ASME. 22 Law Drive, Box 2300, Fairfield. NJ 07007-2300.

Entergy South/ANO-1 Page 1 of I TABLE I R/1 (Note 1)

ABSTRACT OF EXAMINATIONS AND TESTS Interval: 3 Period: 3 Total Examinations Total Examinations Total Examinations Total Examinations Examination Required for The Third Credited for The Third Credited (%) for The Credited (%) To Date Remarks Category Interval Period Third Period for The Third Interval B-A 13 0 0% 0% Relief Request ANO-1-ISI-005 B-B 7 3 100% 100%

B-D 32 2 12.50% 50.00% Note 3 B-F 7 0 0% 57.14% Relief Request ANO-l-ISI-006 B-G-1 31 21 100% 100%

B-G-2 18 2 100% 100%

B-J 40 5 50.00% 78.00% Relief Request ANO-ISI-004 8-K 4 3 100% 100% Steam Generator replacement and multiple vessels B-L-1 0 0 0% 0%

B-L-2 0 0 0% 0%

B-M-1 0 0 0% 0%

B-M-2 1 0 0% 100%

B-N-1 3 0 0% 66.67% Relief Request ANO-1-ISI-007 B-N-2 2 0 0% 0%

B-N-3 1 0 0% 0%

B-O 12 0 0% 0% Head replaced in 3rd period B-P 7 2 100% 100%

B-Q 0 0 0% 0%

C-A 8 2 100% 100%

C-B 7 2 100% 100%

C-C 14 4 100% 100%

C-F-1 93 5 19.23% 65.00% Relief Request ANO-1-ISI-008 C-F-2 28 4 36.36% 72.00% Relief Request ANO-1-ISI-008 C-H 165 55 100% 100%

D-A 10 4 100% 100%

D-B 51 17 100% 100%

F-A 138 41 100% 100% Steam Generator replacement E-A 120 40 100% 100% Note 2 E-C 9 3 100% 100%

E-D 3 1 100% 100%

E-G 11 4 100% 100%

L-A 57 0 0% 100%

L-B 10 0 0% 100%

F-C 3.10-40 525 126 100% 100% Snubbers Per TRM Table 5.5.1-1 F-C 3.50 103 26 100% 100% Snubbers Per TRM 5.5.1.d Note 1 - Revision ito this table per ICAN080701 Commitment.

Note 2 - Column 1 & 2 numbers increased from last cycle's OAR due to this category splitting up into smaller more manageable inspection areas.

Note 3 - 6 Steam Generator welds were replaced therefore not requiring examination and 16 Reactor Vessel welds extended by Relief Request ANO-ISI-004.