ML092180730: Difference between revisions

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{{Adams
#REDIRECT [[LR-N09-0163, Submittal of Inservice Inspection Activities - 90 Day Report Fifteenth Refueling Outage]]
| number = ML092180730
| issue date = 07/30/2009
| title = Hope Creek, Submittal of Inservice Inspection Activities - 90 Day Report Fifteenth Refueling Outage
| author name = Perry J F
| author affiliation = PSEG Nuclear, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000354
| license number = NPF-057
| contact person =
| case reference number = LR-N09-0163
| document type = Inservice/Preservice Inspection and Test Report, Letter
| page count = 8
}}
 
=Text=
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC JUL, 3 0 2009 10 CFR 50.55a LR-N09-0163 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Facility Operating License No. NPF-57 Docket No. 50-354
 
==Subject:==
INSERVICE INSPECTION ACTIVITIES
-90 DAY REPORT FIFTEENTH REFUELING OUTAGE This letter submits the ninety (90) day report for Inservice Inspection (ISI)activities conducted at the Hope Creek Generating Station during the fifteenth refueling outage. This report is submitted in accordance with 10 CFR 50.55a(g)and Section Xl of the ASME Boiler and Pressure Vessel Code (2001 Edition 2003 Addenda and 2001 Edition 2003 Addenda for IWE) and Regulatory Guide 1.147 Acceptable Code Case Number N-532-4.The enclosures to this letter are as follows: 'Enclosure 1: Form OAR-i, Owners Activity Report Enclosure 2: Table 1 -Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Enclosure 3: Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service (for the period December 12, 2007 to May 4, 2009)There are no regulatory commitments contained in this correspondence.
Should you have any questions regarding this correspondence, please contact Philip J. Duca at 856-339-1640.
John F. Perry Hope Creek Plant Ianager Enclosure (3)95-2168 REV. 7/99 Document Control Desk LR-N09-0163 Page 2 C. Mr. S. Collins, Administrator-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager -Hope Creek U. S. Nuclear. Regulatory Commission Mail Stop 08 B1A Washington, DC 20555-0001 USNRC Senior Resident Inspector-Hope Creek (X24)Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering P0 Box 415 Trenton, New Jersey 08625 Hope Creek Commitment Coordinator (H02)
Document Control Desk LR-N09-0163 Enclosure 1 Page 1 ENCLOSURE 1 FORM FORM OAR-1 OWNERS ACTIVITY REPORT (2 Pages including this Page)
Document Control Desk LR-N09-0163 Enclosure 1 Page 2 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number HCRFOJ5 Owner PSEG Nuclear LLC. PO Box 236. Hancocks Bridge, NJ 08038 Plant Hope Creek Generating Station Unit No. I Commercial Service Date 12/20/86 Refueling Outage No. 15 Current Inspection Interval Third (3rd) {IWE (2nd)}Current Inspection Period Third (1st) {IWE (lst)}Edition and Addenda of Section XI Applicable to the inspection plan 2001 Edition 2003 Addenda;IWME -2001 Edition, 2003 Addenda: Date and revision of inspection plan 7/2009, Revision 0 ; Change 0 Edition & Addenda of Section Xl Applicable to repairs and replacements, if different than the inspection plan ASME Class 1, 2, 3 and MC -2001 Edition, 2003 Addenda (Unless specifically identified in the individual repair plan)CERTIFICATE OF CONFORMANCE I certify, that the statements made in this Owner's Activity Report are correct, and that the exaninations, 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 Signed 1-'-i PaS- -fini L)ývJisW-©ate 71ýI 26, 2000 Owner or Owner's 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 New Jersey and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, during the period December 12. 2007 to MaIa 4. 2009, 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 a manner for any pe onal injury or property damage or a loss of any kind arising from c/onn cted with t.-a ~ ~ rtetin.*Cormmissions i-0 Inspector's signatye NationalBoard, State, Province, and Endorsements Date L,;27 3 S Document Control Desk LR-N09-0163 Enclosure 2 Page 1 ENCLOSURE 2 Table 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE (2 Pages including this Page)
Document Control Desk LR-N09-0163 Enclosure 2 Page 2 TABLE I -TTEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRPED EVALUATION FOR CONTINUED SERVICE Exam I Item Item Description Flaw Flaw or Relevant Condition Category Number Characterization Found During Scheduled (IWA-3300)
Section XI Examination or Test in e (Yes or No)R-A RI. 14-2 N2G nozzle- Recirculation Inlet at 240Deg. Weld, Indication is 10.9" No Examination completed to BWRVIP letter 2008-293.
long in the Sum# 100675- N2G nozzle circumferential Weld.direction and is Scheduled BWRVIP 2008-0.4" from the 293 letter, Engineering outside surface, at a Evaluation (Fatigue Crack depth of 0.5" and Growth Analysis).
the depth to length ration, 2a/l, is 0.092. Indication is classified as subsurface per ASME Section XI, IWA33 10.R-A RI.14-2 N2H nozzle -Recirculation Inlet at 270 Deg. Weld, Indication is 1.7" No Examination completed to BW3rRVIP letter 2008-293.
long in the Sum# 100680 -N2H nozzle circumferential Weld.direction and is Scheduled BWRVIP 2008-0.5" from the 293 letter, Engineering outside surface, at a Evaluation (Fatigue Crack depth of 0.4" and Growth Analysis).
the depth to length ration, 2a/l, is 0.24.Indication is classified as subsurface per ASME Section XI, MIA33 10.R-A RI. 14-2 N5A nozzle- Core Spray Inlet at 120 Deg. Weld, Indication is 8.8" No Examination completed to BWRVIP letter 2008-293.
long in the Sum# 100745 -N5A nozzle circumferential Weld.direction and is S hediied RWRVIP 2009-0.3" from the 293 letter, Engineering outside surface, at a Evaluation (Fatigue Crack depth of 0.4" and Growth Analysis).
the depth to length ration, 2a/l, is 0.046. Indication is classified as subsurface per ASME Section XI, IWA33 10.
Document Control Desk LR-N09-0163 Enclosure 3 Page 1 ENCLOSURE 3 ABSTRACT OF REPAIRS, REPLACEMENTS OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE (For the Period December 12, 2007 to May 4, 2009)(2 Pages including this Page)
Document Control Desk LR-N09-0163 Enclosure 3 Page 2 TABLE 2 -ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Repair. Item Description Description of Work Flaw or Relevant Date Repair/Class Replacement, or Condition Found Completed Replacemenw Corrective During Scheduled Plan wimber Measure Section X]Examination oi n Test (Yes or No)nOne}}

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