ML082330062
| ML082330062 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/14/2008 |
| From: | Langley D Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML082330062 (9) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Adabama 35609-2000 August 14, 2008 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket No. 50-296 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION, SYSTEM PRESSURE TEST, CONTAINMENT INSPECTION (IWE), AND REPAIR AND REPLACEMENT PROGRAMS -
SUMMARY
REPORT FOR CYCLE 13 OPERATION In accordance with paragraphs IWA-6230, and IWA-6240 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, TVA is submitting the BFN Unit 3 outage summary reports for NRC review. The summary reports are for Inservice Inspection, System Pressure Test, and Containment Inspection, and Repair and Replacement activities for Unit 3 Cycle 13 operation.
The summary report contains an overview of the inservice examination results that were performed on ASME Class 1 and 2 components up to and including the Unit 3 Cycle 13 refueling outage during the first inspection period of the third 10-year inspection interval.
The enclosure contains the Owner's Activity Report, and abstract of examinations and tests (Table 1), evaluation of conditions for continued service (Table 2), repair and replacement activities (Table 3), and the ASME Section XI, Subsection IWE concrete containment inspections. This report is being provided in accordance with ASME Section Xl and Code Case N-532-4.
U.S. Nuclear Regulatory Commission Page 2 August 14, 2008 There are no new regulatory commitments in this letter. If you have any questions regarding these reports, please contact me at (256) 729-2636.
Sincerely, Manager of Licding and Industry Affairs Enclosure cc (see page 3)
U.S. Nuclear Regulatory Commission Page 3 August 14, 2008 Enclosure cc (Enclosure):
Mr. Eugene F. Guthrie, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME),
SECTION XI, THIRD TEN-YEAR INSPECTION INTERVAL INSERVICE INSPECTION (ISI), SYSTEM PRESSURE TEST (SPT), CONTAINMENT INSPECTION, AND AUGMENTED EXAMINATIONS PROGRAM
SUMMARY
REPORT FOR CYCLE 13 OPERATION (SEE ATTACHED)
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number BFNU3C13 Plant Browns Ferry Nuclear Plant. P.O. Box 2000, Decatur, AL 35602-2000 Unit No.
3 Commercial service date March 1. 1977 (it applicable)
Current Inspection Interval Third Ten Year Inspection Interval Refueling Outage no.
Cycle 13 (Ist, 2nd, 3rd, other)
Current Inspection Period First Period (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Date and Revision of inspection plan 3-SI-4.6.G Revision 027 6/18/2008 Edition and Addenda of Section X) applicable to repairs and replacements, if different than the inspection plan Same as above Code Cases used: N-532-4, N-686, N-460, N-526, N-552, N-577, N-586-1, N-613-1, N-624, N-648-1, N-658, N-695, N-605 (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 ction XI; and (c) the repair/replacement activities and evaluations supporting the completion of U3C13 (refueling outage number) conform to he equirements of Section Xl.
Signed zi J
Date_______
Ell Owner or Owners 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 Tennessee and employed by HSB CT of Hartford. Connecticut have inspected the items described in this Owner's Activity Report 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 requirement 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 lab any manner for any personal injury or property damage or a loss of any kind arising from or connected with this Inspection.
- r.Commissions 4/)
-V~'i/
C C-Inspectors signature Date National Board, State, Province and Endorsements Page 1 of 5
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3C13 Plant Browns Ferry Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
13 Current inspection interval 3rd Current inspection period 1st TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description B-M-2, Item B12.50 SLIGHT PHYSICAL DAMAGE TO EVALUATED ACCEPTABLE DISC AND SEAT OF VALVE (No Corrective Measures Required.
(3-FCV-75-25) [NOI U3C13-25]
Indication did not extend across seat and was not significant enough to require lapping during valve refurbishment. As-found and as-left leak rate tests were satisfactory.)
C-H, Item C7.10 VT-2 EXAM IDENTIFIED PERFORMED VT-1 EXAM OF LEAKAGE AT BOLTED WETTED BOLTING; CONNECTION IN A SYSTEM BOLTING ACCEPTABLE.
BORATED FOR CONTROL OF (Examination Number R-1 17, REACTIVITY. CYLINDER HEADS 05/01/2008)
OF 3B STANDBY LIQUID CONTROL PUMP (EXAM NO. R-01 9, 04/19/2008)
F-A, Item F1.20C SPRING CANS SETTINGS OUT EVALUATED ACCEPTABLE OF RANGE (3-47B452-1422)
(No Corrective Measures Required.
[NOI U3C13-003]
Support was reinspected per engineering request after system fill and was within range.)
F-A, Item F1.20C SPRING CANS SETTINGS OUT EVALUATED ACCEPTABLE OF RANGE (3-47B400-099)
(No Corrective Measures Required.
[NOI U3C13-015]
The total deviation in load on the pipe was a load reduction of 639 pounds.
Neither spring can was topped or bottomed out during operation. Stress calculation was reviewed and sufficient margin was available to accommodate the deviation in loading on the Main Steam piping. Spring cans were reset to setting specified.)
Page 2 of 5
FORM OAR-i OWNER'S ACTIVITY REPORT TABLES Report Number BFN Plant
-Browns Ferry U3C1 3 Unit No.
3 Commercial service date 03/01/1977 Refueling outage no.
13 Current inspection interval 3rd Current inspection period 1st TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number CODE CLASS 1 DEFORMATION OF BOLT REPLACED 05/14/2008 WO 07-723078-000 BOLT HEAD DURING REMOVAL (CRDN-3-1815-BC)
[NOI U3C13-9]
CODE CLASS 1 DEFORMATION OF BOLT REPLACED 05/14/2008 WO 07-723078-000 BOLT HEAD DURING REMOVAL (CRDN-3-4231 -BC)
[NOI U3C13-10]
CODE CLASS 1 PHYSICAL BOLTS REPLACED 05/23/2008 WO 08-711390-000 DAMAGE TO THREADS OF BOLTS 13 OF 16 (RSF-B-1 -BC)
[NOI U3C13-23]
CODE CLASS 1 PHYSICAL BOLT S AND NUTS 05/10/2008 WO 07-725121 -000 DAMAGE TO REPLACED THREADS AND CORROSION OF 7 BOLTS; 5 NUTS HAVE DEFORMATION OF THREADS (3-FCV-75-26-BC)
[NOI U3C13-24]
CODE CLASS 1 PHYSICAL BOLTS AND NUTS 05/12/2008 WO 08-713324-000 DAMAGE TO REPLACED BOLTS AND NUTS DURING DISASSEMBLY (3-CKV-3-568)
[NOI U3C13-30]
Page 3 of 5
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNL Plant Browns Ferry Unit No.
3 Current inspection interv J3C1 IC13 Commercial service date 03/01/1977 Refueling outage no.
13 al 3rd Current inspection period 1 st Summary of IWE Indications for U3C13 The summary table below is provided in accordance with the requirements of 10 CFR 50.55a(b)(2)(ix)(A) and 10 CFR 50.55a(b)(2)(ix)(D).
Examination Component Indication Acceptability/Corrective Inaccessible Additional Category and Identifier Description Action Area Samples Item Number (Location and Evaluation)
E-A E1.12 DW HD-3-1 Coating blistering, Loose coating removed.
None None peeling, rust and Exposed liner discoloration re-inspected. No
[U3C 13-0011 reportable conditions.
E-A E1.20 PSC INT-3-1A Mechanical Extent of damage is to the None None through 16A damage to coating coating. Acceptable as is.
[U3C1 3-002]
E-A E1.12 PSC EXT-3-B-1 Arc strikes, chips, No degradation present None None through 16 scratches, that could affect structural discoloration, white integrity or leak tightness residue, scrapes of the vessel. Acceptable
[U3C13-0041 as is.
E-A E1.12 DW LNR-3-3 Coating blistering Loose coating removed.
None None and flaking Exposed liner
[U3C13-011]
re-inspected. No reportable conditions.
E-A E1.12 DW LNR-3-2 Coating blistering Loose coating removed.
None None and flaking Exposed liner
[U3C13-012]
re-inspected: No reportable conditions.
E-A E1.12 DW LNR-3-6 Coating blistering Loose coating removed.
None None and flaking Exposed liner
[U3C13-013]
re-inspected. No reportable conditions.
E-A E1.12 DW LNR-3-5 Coating blistering Loose coating removed.
None None and flaking Exposed liner
[U3C13-014]
re-inspected. No reportable conditions.
E-D E5.30 MSB 3-1, MSB-Separation of seal No evidence of moisture None None 3-2, MSB-3-3 with rust at seal to intrusion in areas where liner interface seal was removed.
[U3C1 3-016]
Defective portions were replaced.
E-A E1.12 DW LNR-3-1 Coating flaking, Loose coating removed.
.peeling, blistering, Exposed liner and loose edges of re-inspected. No previously scraped reportable conditions.
areas
[U3C13-017]
E-A E1.20 PSC MVH 3-B-1 Coating flaking, Coating defects. No None None through 13 blistering, degradation present that (Downcomers) discoloration, rust could affect structural
[U3C1 3-018]
integrity or leak tightness of the vent header.
I_ _ _Acceptable as is.
Page 4 of 5
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNI Plant Browns Ferry Unit No.
3 Current inspection interv U3C13 Commercial service date 03/01/1977 Refueling outage no.
13 al 3rd Current inspection period 1st Summary of IWE Indications for U3C13 (Continued)
Examination Component Indication Acceptability/Corrective Inaccessible Additional Category and Identifier Description Action Area Samples Item Number (Location and Evaluation)
E-A E1.20 PSC MVH 3-B-1 Coating flaking, Coating defects. No None None through 13 blistering, degradation present that (Vent Header) discoloration, rust could affect structural
[U3C1 3-019]
integrity or leak tightness of the vent header.
Acceptable as is.
N/A PEN 3-X-22 Light surface rust Expected based on age None None on un-coated and service condition.
portion of Acceptable as is.
penetration sleeve to flued head
[U3C13-021]
E-D E5.30 MSB 3-1, Seal damage and No evidence of moisture None None MSB 3-3 separation intrusion in excavated
[U3C13-022]
areas. Acceptable as is.
E-A E1.12 PSC INT-3-1B Pits, scratches, Acceptable as is. Pits None None through 16B surface gouges, with metal loss of 30 mils and blisters or greater cleaned and
[U3C13-026]
recoated. Maximum pit depth was 67.2 mils.
E-C E4.11 PSC INT-3-1 C Pits, scratches, Conditions found same or None None through 16C mechanical similar to U3C11. No damage, blisters, degradation present that and staining, could affect structural
[U3C13-027]
integrity or leak tightness of the vessel. No accelerated degradation exhibited in this region.
Spots and pitting less than 30 mils depth.
Acceptable as is.
E-A E1.20 PSC INT-3-2B Pits, scratches, Acceptable as is. One pit None None through 68 and mechanical 35 mils (Downcomer #88) 8B through 16B damage, blisters, was cleaned and (Downcomers) and staining.
recoated remaining had
[U3C13-028]
less than 30 mils.
E-G E8.10 DW FLG-3-1 Corrosion and Pitting depth from 3 to 12 None None pitting in o-ring mils. Pitting in this area areas.
does not affect leak
[U3C13-029]
tightness of the vessel.
Satisfactory as-found leak rate test results.
Acceptable as is.
Page 5 of 5