LR-N08-0012, Inservice Inspection Activities - 90 Day Report Fourteenth Refueling Outage

Inservice Inspection Activities - 90 Day Report Fourteenth Refueling Outage

ML080510696
Person / Time
Site:	Hope Creek
Issue date:	02/14/2008
From:	Possessky F Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N08-0012
Download: ML080510696 (14)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG NuclearLLC 10 CFR 50.55a LR-N08-0012 February 14, 2008 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 FOURTEENTH REFUELING OUTAGE This letter submits the ninety (90) day report for Inservice Inspection (ISI) activities conducted at the Hope Creek Generating Station during the fourteenth refueling outage.

This report is submitted in accordance with 10 CFR 50.55a(g) and Section XI of the ASME Boiler and Pressure Vessel Code, 1998 Edition 2000 Addenda and 1998 Edition 1998 Addenda for IWE and Regulatory Guide 1.147 Acceptable Code Case Number N-532-1.

The enclosures to this letter are as follows: : Form OAR-i, Owners Activity Report : Table 2 - Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service : Table 3 - Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service (for period May 7, 2006 to December 12, 2007) : Table 1 - Examination Allocation Summary - Abstract of Examinations and Tests 95-2168 REV. 7/99

Document Control Desk LR-N08-0012 Page 2 Should you. have any questions regarding this request, please contact Francis D.

Possessky at 856-339-1160.

Sincerely, Francis D. Poss y Manager (Ac* g) - Hope Creek Regulatory Assurance Enclosures (4)

Document Control Desk LR-N08-0012 Page 3 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager - Hope Creek Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector- Hope Creek (X24)

Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 Mr. Milton Washington Chief Inspector NJ Department of Labor Division of Public Safety, Occupational Safety and Health Bureau of Boiler and Pressure Vessel Compliance P. 0. Box 396 101 South Broad Street Trenton, NJ 08625-0392

Document Control Desk LR-N08-0012 ENCLOSURE I (Pages - 1)

FORM OAR-1 OWNERS ACTIVITY REPORT

HCRF#14 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: HCRF#14 Owner: Public Service Electric & Gas Company Plant: Hope Creek Nuclear Generating Station Unit No. : 1 Commercial Service Date: 12/20/86 Refueling Outage No.: RF#14 Current inspection interval: Second

• Current inspection period: Third Edition and Addenda of Section XI applicable to the inspection plan: 1998 Edition 2000 Addenda and 1998 Edition 1998 Addenda For IWE.

Date and revision of inspection plan: 11/97, Rev. 0 / Chg. 0 Edition and Addenda of Section XI applicable repairs and replacements, if different than the inspection plan:

Class 1, 2, & 3 - 1998 Edition, 2000 Addenda Class MC - 1992 / 92 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 examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.

Certificate of Aut tion No.: N/A Expiration Date: N/A Signed: -.-- 0 4wQX.Q-\ . Date )21 JD

\ ]

• Owner or Owner's D~bsignee, 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 providence of New Jersey and employed by Hartford Steam Boiler Inspection & Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, during the period 05/06/2006 to 12/12/2007 , 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 any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

6nsp c6or'sNnatuaT 'Ntiofil Bdard, State, Province, and Enlorsenents Date /____/____

Document Control Desk LR-N08-0012 ENCLOSURE 2 (Pages - 1)

TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE

HCRF#14 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Item Flaw Flaw or Relevant Condition Category Number Description Characterization Found:

During Scheduled Section XI Examination or Test (Yes or No),

R-A Sum# RPV1- One Circumferential Flaw No (Augmented-emergent) 100645 N2ASE Ultrasonic Examination Noted PSEG Notification #.

Rejectable Indications and a 20341672 & 20339389 Weld Overlay was Performed A-E Sum# Jet Pump 09 Cracked Tack Welds. Yes 502340 shroud side Setscrew shows no PSEG Notification. 20342064 setscrew movement. Staked setscrew.

A-E Sum# Jet Pump 16 Slight Wedge Wear and Yes 500757 Wedge setscrew gap. Installed PSEG Notification. 20341129 Bearing auxiliary wedge. and 20341381 Surface A-E Sum# Core 5 Indications, all less than Yes 502032 Shroud 2 inches in length. PSEG Notification. 20342263 Weld H4 Represents less than 10% of examined weld. Use-as-is disposition evaluation for 10 years.

A-E Sum# Core 1 Indication 4.3 inches in Yes 502034 Shroud length. Represents less than PSEG Notification. 20342263 Weld H5 10% of examined weld. Use-as-is disposition evaluation for 10 years.

Document Control Desk LR-N08-0012 ENCLOSURE 3 (Pages - 2)

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE (FOR PERIOD MAY 7, 2006 TO DECEMBER 12, 2007)

HCRF#14 Table 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Hope Creek Generating Station (For the period 05/07/2006 TO 12/12/2007)

Repair, Flaw or relevant Replacement, Condition Found Code or Corrective Item Description of During Scheduled Date Repair/Replacement Plan Class Measure Description Work Section XI Completed Number Examination or Test (yes/no) 3 Replacement Degraded FSK-P-1-EA-672 NO 10/05/2006 60059475 Bolting H06, H07, replace 70053239 2 Replacement 1" piping thru HOBC -P-BC-V9950 NO 11/09/2007 60073283 wall leak Replace by Welding 70076414 2 Replacement Configuration Replaced Valve with NO 01/08/2008 60069039 discrepancy blind flange 70067533 3 Abandon In Leakage due HIEA T-544 NO 11/02/07 60068390 Place to MIC 80088855 3 Replacement Tubing Fitting HOEA -P-EA-V9963 NO 3/17/2007 60061485 leak Replace adapter 70055012 3 Abandon In Leakage due HIEA T-543 NO 10/25/2007 60068414 Place to MIC 80088855 3 Replacement Tubing Fitting HOEG -P-EG-V9881 NO 2/06/2006 60060868 leak 70053555 3 Repair Corroded H1EA -1C-F-509 NO 3/10/2006 60059694 1 1" Flange 70054800

HCRF#14 Table 3 (Cont.) ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Hope Creek Generating Station For the period 05/07/2006 TO 12/1212007)

Repair, Flaw or Replacement relevant Code , or Item Description Description of Work Condition Date Repair/Replacement Plan Class Corrective Found During Completed Number Measure Scheduled Section XI Examination or Test (yes/no) 3 Repair Strainer Lid HIEA -IA-F-509 NO 12/08/2006 60055899 80032450 70060750 3 Repair Min Wall H1EA EA-019-S01 NO 12/04/2007 30119379 Weld repair 70075133 3 Replace Leak HOEA -P-EA-V9947 NO 4/22/2006 60062335 70055312 1 Repair Rx Recirc Inlet N2A HIBB S-201 YES 2//2008 70075632 Nozzle Structural Overlay 60072513 80094209 1 Use As Is Wrong Class HIAB -IABV-030 NO 07/06/2006 60055573 Bolting Material 70056677

Document Control Desk LR-N08-0012 ENCLOSURE 4 (Pages - 3)

Table 1 - Examination Allocation Summary -

Abstract of Examinations and Tests

HCRF#14 Examination Allocation Summary During HC/RF-13, PSEG Nuclear implemented Risk Informed Inservice Inspection (RI-ISI) of Nuclear Class 1 and 2 Piping Welds, formerly known as ASME Section XI Exam Category B-F, B-J, and C-F-2. The bases of the Hope Creek RI-ISI Program are documented in the Hope Creek Nuclear Generating Station - Final Report.- Risk Informed Inservice Inspection Application (VTD-326046). The ISI Department implemented Risk Inform during the Second Interval, Third Period, and Second Outage. See ISI examination summary table.

ISI implemented The IWE program in 2000 (RF#09) and a separate data base was created in 2004 (RF# 12) to clearly identify the inspection interval and to track examinations. See the IWE Examination summary for the I st interval.

ALL EXAMS REQUIRED TO COMPLETE THE 2ND ISI INTERVAL AND THE 1ST CISI INTERVAL HAVE BEEN COMPLETED.

Description ISI Examination Summary for 2nd Interval 3rd Period 1998 Code Edition 2000 Addenda IWE Examination Summary 1st Interval 1998 Code Edition 1998 Addenda.

HCRF#14 Hope Creek Nuclear Generating Station ISI Program Long Term Plan Table 1 Inservice Inspection Examination Summary For The Second Interval ASME 1998 Code Edition - 2000 Addenda F Table 1 PERIOD 1 PERIOD 2 PERIOD 3 Total Total Total Exams Exam % Total Total Total Total Exam %

Total Credited Credited Exams Exam Exams Exam Credited Required for for Credited for % Credited Credited  % Credited to Date Examination For This This This for This for This for This for Category Population Interval Period Period Period Period Period Period Interval Remarks B-A 39 39 3 8% 3 8% 33 84% 100% See Note #1 B-D 68 68 18 27% 11 16% 39 57% 100% See Note #2 B-E 3 3 0 0% 0 0% 3 100% 100% See Note #1 B-F 29 29 11 38% 5 17% 0 0% 56% See Note #4 B-G-1 10 9 2 23% 0 0% 5 55% 77% See Note #1 B-G-2 105 105 3 3% 11 10% 7 7% 20%

B-J  %  % 0 0%  % See Note #4 B-K 61 9 3 34% 4 44% 3 33% 111%

See Note#3 &

B-L-2 2 2 0 0% 0 0% 1 50% 50% Note #5 See Note#3 &

B-M-2 68 68 2 3% 1 1% 2 3% 7% Note #5 B-N-1 7 7 7 0 0 0% 100%

B-N-2 67 67 10 15% 5 7% 35 52% 75% See Note #1 B-O 1 1 0 0% 0 0% 1 100% 100% See Note #1 B-P  % 0 0% 0 0%  %

C-A 10 10 1 10% 3 30% 0 0% 40% See Note #5 C-B 8 8 1 13% 2 25% 1 13% 50% See Note #5 C-C 92 11 3 27% 3 27% 4 36% 91% See Note #5 C-F-2  %  % 0 0%  % See Note #4 C-G 52 52 2 4% 3 5% 5 10% 19% See Note #5 C-H 42 42 40 96% 0 0% 0 0% 96%

C-H/D-B  % 0 0% 0 0%  %

D-A 312 86 12 14% 15 17% 15 17% 42%

D-B 39 39 39 100% 0 0% 0 0% 100%

E-D 3 0 0 0 0 0 F-A 2287 301 94 31% 105 35% 119 39% 105%

R-A 2304 92 126 137% 108 117% 39 42% 296% See Note #4 Notes

1) Deferral Permissible 4) Category R-A Risk Informed which replaces categories B-A B-G-1 B-F, - B-J, & C-F-2 was implamented 2-3-1 (RFO-12)

B-E B-L-1 Categories B-F,- B-J, & C-F-2 percentage of exam completions B-N-2 B-O are for the 1st % 2nd periods only. Category R-A percentage B-M-1 B-N-3 of exam completions are for the 3rd period only.

2) Ref. Table IWB-2500-1, Exam 5) For Multiple Pumps, Valves, and Vessels of Similar Design, Category B-D, Program (B) Note 2 service, and function only one of the multiple components shall be selected for examination.

3) To be examined only if disassembled for maintenance, repair or volumetric examination.

(Ref. Table IWB-2500-1, Category B-L-2 & B-M-2 Note 2)

HCRF#14 Hope Creek Nuclear Generating Station ISI Program Long Term Plan Table 1 IWE Examination Summary for the First Interval ASME 1998 Code Edition 1998 Addenda Table 1 PERIOD 1 PERIOD1 2

• PERIOD 3 Examination:,. Required for Cfeclite for foi This C-re2dited for fo Ohs redited for, forThis Date for.

C a Le o..

ry pulationi .. interval.Thi~s.Perjo, Pe~riod.Tbiý Prid ~Pýýrid This Poiiod IPeriod IInterval.Remnarks E-A 318 954 299 31% 263 .27% 273 29% 1 87% See Note #1 E-C 6 18 0 0% 6 33% 0 0% 33% See Note #1 Notes

1) Inaccessible components will be examined when accessible.