ML110550646
| ML110550646 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/22/2011 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML110550646 (10) | |
Text
Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing February 22, 2011 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner's Activity Report for Cycle 8 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for Unit 1 Cycle 8 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section Xl, Division 1."
The report is an overview of the inservice examination results that were performed on components within the ASME Section Xl boundary, up to and including the Unit 1 Cycle 8 refueling outage, during the first inspection period of the second 10-year inspection interval.
AOLF-7 printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 February 22, 2011 There are no new regulatory commitments in this letter. If you have any questions regarding these reports, please contact Tom Matthews at (423) 751-2687.
Respectfich R. M. Krich
Enclosure:
American Society of Mechanical Engineers,Section XI, Second 10-Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Cycle 8 Operation cc (Enclosure):
Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit I American Society of Mechanical Engineers,Section XI, Second 10-Year Inspection Interval Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs Owner's Activity Report for Cycle 8 Operation
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number
- BFNU1Q8 Plant Browns Fern, Nuclear Plant,. PO. Box 2000. Decalur. AL 36602-20M0 Unit No.
I Commercial service date AIGust 1. 1974 Refueling Outage no.
Crcte a Current Inspection Interval Second Ten Year Inasection Interval Current Inspection Period First Period Edition and Addenda of Section XI applicable to the Inspection plans 2001 Edition through 2003 Addenda Date and Revision of Inspection plan 1 -SI-4.6.-. Revision 019. 02Q15 201 1 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan Same as above Code Cases used: N-460. N-513n2. N-526. N-532-4. N-552. N-586-1. N-613-1. N-624. N-648-1. N-683. N-S95. N-700, N-504-3. N-86-1. and N-702 (it wlraie)
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 XI; and (c) the repairtreplacement activities and evaluations supporting the completion of Cvwla 8 conform to the requirements of I.
S).* nD Slgned4 Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boller and Pressure Vessel Inspectors and the State or Province of Tnessee and employed by1jL9 of Hartford. Connwtict 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 liable in 7a manner for any personal Injury or property damage or a loss of any kind arising from or connected with this Inspection.
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Date 16 11 Page I of 7
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C8 Plant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no. 8 Current inspection interval 2nd 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 N/A N/A N/A There were no items with flaws or relevant conditions that required evaluations for continued service.
Page 2 of 7
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1 C8 Plant Browns Ferry Unit No.
I Commercial service date 08/01/1974 Refueling outage no. 8 Current inspection interval 2nd Current inspection period 1st TABLE 2 ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Corrtpleted Plan Number 2
Seal Water Heat Replaced heat 12/08/2009 07-721058-001 Exchanger exchanger 1-HEX-074-0016 3
Valve Replaced valve and 05/0&/2009 09-711929-000 I-SHV-067-0655 associated piping 2
Valve Replaced valve disc 11/20/2010 111571105 1 -FCV-074-0066 2
Flow Element Replaced pipe and 111142010 111625531 1-FE-063-0011 coupling 2
Flow Element Repaired socket weld 11/11/2010 111632698 1-FE-063-0011 Page 3 of 7 I
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FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNUIC8 Plant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no. 8 Current inspection interval 2nd Current inspection period 1st Summary of IWE Indications for UIC8 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 E1.30 MSB-I-1 Gouges and Moisture seal barrier None. Entire None surface replaced. Drywell liner MSB was irregularities in examined (VT-3 and UT)
Inspected.
Moisture Seal in areas excavated for VT-3 Barrier (MSB) repair.
examinations
[NOI U1R8-001]
conducted of liner in areas where portions of MSB excavated for repair.
E-A E1.11 GEN-VTE Ductwork in contact Interference removed.
None None with drywell liner Liner re-examined. No
[NOI UIRB-0021 damage to liner.
E-A E1.11 GEN-VTE Arc strikes on torus Engineering accept-as-is.
None None exterior Indications on the torus
[NOI Ul R8-003]
exterior consisting of arc strikes and pitting less than 1/32" were identified.
Minor surface indications consisting of scrapes, dings, dents, arc strikes, etc. are expected based on the age and service conditions of the Steel Containment Vessel (SCV). The arc strikes noted had no appreciable depth and were determined to be acceptable. None of the conditions noted are considered suspect and do not impact the structural integrity or leak tightness of the SCV.
There is no Indication that an adverse condition exists that may be present in inaccessible areas.
Page 4 of 7
FORM OAR-I OWNER'S ACTIVITY REPORT TABLES Report Number BFNUIC8 Plant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no. 8 Current inspection interval 2nd Current inspection period 1st Examination Component Indication AcceptabilitylCorrective Inaccessible Additional Category and Identifier Description Action Area Samples Item Number (Location and Evaluation)
E-A E1.11 "DW-LNR-1-1A Pit in MSB seal Engineering accept-as-Is.
None. Entire None area at Grid 17.75 Conditions noted do not MSB was in area excavated impact structural integrity inspected.
for repair.
or leak tightness of the VT-3
[NOI UIR8-004J Steel Containment Vessel examinations (SCV). The conditions conducted of identified are expected liner in areas based on the age and where portions service conditions of the of MSB SCV in the area under the excavated for MSB. There is no repair.
indication that an adverse condition exists that may be present in inaccessible areas. The drywell liner in the area beneath the MSB is monitored when portions of the MSB are excavated for repair.
E-A E1.11 GEN-VTE Gouges in drywell Engineering accept-as-is.
None None liner Conditions noted do not
[NOI UIR8-005]
impact structural integrity or leak tightness of the Steel Containment Vessel (SCV). Indication appears to be the result of removal of an attachment at some point in the past. The indications were coated with no indication of service induced degradation. There is no indication that an adverse condition exists that may be present in inaccessible areas.
E-A E1.11 GEN-VTE Grind marks on Engineering accept-as-Is.
None.
None outside radius of Conditions noted do not ECCS ring header.
impact structural integrity
[NOI UI R8-006]
or leak tightness of the Steel Containment Vessel (SCV). No coating damage, flaking, or corrosion was present.
The ECCS ring header is accessible for examination. There is no indication that an adverse condition exists that may be present in inaccessible areas.
Page 5 of 7
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FORM OAR-I OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C8 Plant Browns Ferry Unit No.
I Commercial service date 08/01/1974 Refueling outage no.
8 Current inspection interval 2nd Current inspection period 1st Examination Component Indication Acceptability/Corrective Inaccessible Additional Category and Identifier Description Action Area Samples Item Number (Location and
,..Evaluation)
E-A E1.11 FLG-HD-1-1 Pitting in lower Engineenng accept-as-is.
None. 100% of None (Lower Flange) flange gasket Pitting on the lower flange the Drywell sealing surface, of the drywell head is a Head sealing
[NOI U1 R8-007]
known condition and has surface is existed since restart of accessible for Unit I and was addressed examination.
by Design Change DCN 68136. The condition noted was not caused by a degradation mechanism that could affect the structural integrity or leak tightness of the Steel Containment Vessel (SCV). There is no indication that an adverse condition exists that may be present in inaccessible areas.
Page 6 of 7
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU1C8 Plant Browns Ferry Unit No.
1 Commercial service date 08/01/1974 Refueling outage no. 8 Current inspection interval 2nd Current inspection period 1st Attachment A The following welds were calculated to have ASME Section XI Code examination coverage less than 90 percent. TVA will submit requests for relief for these weld examinations in separate correspondence.
WELD ID CONFIG Limitation Report RWR-1-001-003 Elbow to Valve Single Side Exam 50%
UT-10-024 RWR-1-001-S023A Branch Connection to Pipe Single Side Exam 50%
UT-10-028 RWR-1-002-012 Pipe to Valve Single Side Exam 50%
UT-1 0-026 RWCU-1-001-019 Pipe to Valve Single Side Exam 50%
UT-10-030 NiA-NV Nozzle to Vessel Component Design 27%
UT-1 0-037 N2D-NV Nozzle to Vessel Component Design 38.26%
UT-10-038 N2E-NV Nozzle to Vessel Component Design 38.26%
UT-10-039 N2G-NV Nozzle to Vessel Component Design 38.26%
UT-10-040 N3D-NV Nozzle to Vessel Component Design 33.4%
UT-10-041 N5A-NV Nozzle to Vessel Component Design 31.72%
UT-10-042 N5B-NV Nozzle to Vessel Component Design 31.72%
UT-,0-043 N6A-NV Nozzle to Vessel Component Design 37%
UT-10-044 N8A-NV Nozzle to Vessel Component Design 80.33%
UT-10-044 N2D-IR RPV Inner Radius Section Jet Pump Riser 60%
VT-10-004 N2E-IR RPV Inner Radius Section Jet Pump Riser 60%
VT-10-007 N2G-IR RPV Inner Radius Section Jet Pump Riser 60%
VT-10-008 N5A-IR RPV Inner Radius Section Thermal Sleeve And 50%
VT-10-011 Tee Box N5B-IR RPV Inner Radius Section Thermal Sleeve And 60%
VT-10-012 Tee Box N8A-IR RPV Inner Radius Section Core Shroud Support 75%
VT-10-010 Page 7 of 7