PNP 2012-069, ASME Section XI 90-Day Inservice Inspection Summary Report
| ML12219A248 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/03/2012 |
| From: | Gustafson O Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PNP 2012-069 | |
| Download: ML12219A248 (5) | |
Text
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-===-Entergy PNP 2012-069 August 3, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel 269 7642000 Otto W Gustafson Licensing Manager
SUBJECT:
ASME Section XI 90-Day Inservice Inspection Summary Report Palisades Nuclear Plant Docket 50-255 License No. DPR-20
Dear Sir or Madam:
In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Article IWA-6000, "Records and Reports," and applicable code cases, attached is the Entergy Nuclear Operations, Inc. (ENO) Owner's Activity Report for the Palisades Nuclear Plant (PNP). The report contains a listing of seven examination indications that required evaluation for continued service, and an abstract of six repair replacement activities that were required for continued service.
These activities were performed during the twenty-second fuel cycle and the 2012 refueling outage. ENO completed the PNP refueling outage on May 12, 2012.
This letter identifies no new commitments and no revisions to existing commitments.
owg/jlk
Attachment:
- 1. Palisades Nuclear Plant Owner's Activity Report cc:
Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
ATTACHMENT 1 Palisades Nuclear Plant Owner's Activity Report 3 pages follow
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number PLP-1 R22-0AR-1 Plant PALISADES NUCLEAR PLANT Unit No.
Commercial service date 12131 /1971 Refueling outage no.
1R22
(~ applicable)
Current inspection interval (1st'. 2nd, 3rd, 4th, other)
Current inspection period
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(1 st. 2nd. 3rd)
Edition and Addenda of Section XI applicable to inspection plans 2001 with 2003 Addenda Date and revision of inspection plans 01/1212011, Revision 20 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Code Cases used:
N-460, N-513-2, N-532-4, N-566-2, N-624, N-629, N-663, N-695, N-705, N-706.
N-639 with conditions in Regulatory Guide 1.147 Revision 16.
N-722-1, N-729-1, and N-770-1 as required with conditions, in accordance with 10CFR50.55a.
(~ applicable)
CERTIFICATE OF CONFORMANCE Not Applicable 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 repair/replacement activities supporting the completion of
_1:.:.R.:.:2:.:2=--======= __ _
(refueling outage number)
Date 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 Michigan and employed by HSB Global Standards of
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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 requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/
replacement activities and evaluation 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 loss of any kind arising from or connected with this inspection.
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- § Commissions Nfl> (311)..
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National rd, State, Province, and Endorsements Inspector's Signature ~
Date J Pro <0 I 'L
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description ASME Code Case N-729-1 Reactor Vessel Closure Head Indications of boron staining, Code Item B4.10 scaling, and general corrosion.
Acceptable for continued service in accordance with N-729-1, Paragraph 3142.3.
Category B-F PCS-4-PRS-1P1-1 UT indication of a non-service Code Item B5.40 Power Operated Relief Valve induced discontinuity in the ASME Code Case N-770-1 Safe End to Nozzle Weld carbon steel nozzle base metal, Inspection Item A-1 Class 1, NPS 4 with no significant measurable dimension in the through-wall direction.
Acceptable.
Category B-J PCS-2-LDL -2B 1-1 UT indication of a non-service Code Item B9.21 Letdown Nozzle to Pipe Weld induced weld discontinuity, with ASME Code Case N-770-1 Class 1, NPS 2 no significant measurable Inspection Item B dimension in the through-wall direction.
Acceptable.
Category C-H T-58 Leakage from tank.
Code Item C7.1 0 Safety Injection Refueling Evaluation in accordance with Exempt under IWC-Water Tank ASME Code Case N-705.
1221 (c)
Class 2, Statically Pressurized Category D-B Service Water Elbow Leakage through elbow Code Item D2.1 0 Class 3 pressure boundary.
Evaluation in accordance with ASME Code Case N-513-2.
Leaking elbow was replaced.
Category F-A ESS-2-SIS-1 B1-7PR(H-780)
Vertical hanger rod in contact Code Item F1.1 OA High Pressure Safety with an adjacent pipe.
Injection Pipe Restraint Evaluation determined that Class 1, NPS 2 restraint remained operable.
Acceptable.
Category F-A DMW-6-CST-AWS-Moderate to heavy rust with Code Item F1.30B PSS1(H1.2) flaking and thickness reduction Auxiliary Feed Suction Pipe due to flooding. Evaluation Restraint determined that restraint Class 3, NPS 6 remained operable.
Acceptable.
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work ComJJleted Plan Number 1
E-50A, "A" Steam Plug 38 tubes due to 4/25/12 PLP52325944 Generator indications found during Eddy Current Testing.
E-50B, "B" Steam Plug 11 tubes due to 4/24/12 PLP52325951 Generator indications found during Eddy Current Testing.
W052325951 2
RV-0719, Main Steam Disassemble, inspect, 5/10/12 PLP00260093 Relief Valve replace valve nozzle Rev 1 due to indication found in nozzle seating surface. Replacement of nozzle included performing seal weld of nozzle to valve body.
T-58, Safety Injection Inspect tank bottom 5/3/12 PLP00306107 and Refueling Water welds for leaks and Rev 1 Tank repair. Welded patch PLP00306107A plate over drain Nozzle Rev 1 N due to obstructions observed in nozzle piping and being suspected leak path.
Fasteners on both top and side manways were replaced due to damage noted during previous refueling outage 1 R21.
SNB-70, Snubber for Snubber was replaced 4/20/12 PLP00257396 CC-4-12" Line from in 1 R21 and the Rev 1 Safety Injection Tank removed snubber failed T-82O as found testing.
Snubber was replaced again in 1 R22 to allow for required as found testing.
HB-23-16" piping Replace elbow 5/1/12 PLP00282307 downstream of CV-downstream of CV-Rev 2 0824, Service Water 0824 due to pin hole from Containment leaks in elbow.
Downstream side flange to CV-0824, piping between flange and elbow, and section of piping between elbow and 24" discharge header were also replaced. As part of this RlR activity, four cap screws for CV-0824 were replaced with longer screws to accommodate an insulating gasket.
WOO0282307