3F1198-04, Forwards Second Ten-Year Insp Interval Closeout Summary Rept. Rept Includes Insps & repair-replacements That Occurred 960517-980813
| ML20155J264 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/06/1998 |
| From: | Rencheck M FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20155J267 | List: |
| References | |
| 3F1198-04, 3F1198-4, NUDOCS 9811120073 | |
| Download: ML20155J264 (6) | |
Text
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@ E1.TS" Fl rida Pswer Nng LNee No. DPR-72 November 6,1998 3F1198-04 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
INSERVICE INSPECTION
SUMMARY
REPORT
References:
Dear Sir:
The purpose of this letter is to submit a summary of the inservice inspections performed at Florida Power Corporation's (FPC) Crystal River Unit 3 (CR-3) since the conclusion of Refueling Outage 10, through the end of the Second Ten-Year Inspection Interval (May 17,1996 through August 13,1993.)
in Reference 1 FPC committed to submit a summary report to the NRC by March 15, 1997, to closeout the Second Ten-Year inspection Interval. However, in September of 1996, CR-3 entered an outage that extended past the end of the inspection interval ending in February 1998. In Reference 2, FPC notified the NRC of the Second Ten-Year Inspection Interval extension to August 13,1998, and committed to submit a summary report 90 days following the conclusion of the inspection interval.
The attached summary report includes inspections and repair / replacements that occurred May 17,1996 through August 13,1998. The report includes: NIS-1 Form,
" Owners Report for Inservice Inspections;" a summary and listing of examinations 1
performed on American Society of Mechanical Engineers (ASME) Code Class 1 and 2 i
i pressure retaining components and supports: NIS-2 Forms, " Owners Report of Repair f
I and Replaceme its;" Code Cases utilized; and Relief Requests granted by the NRC.
I Two of the Rehef Requests granted by the NRC (90-20 and 91-10) were superseded by a later Relief Request,95-020.
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CRYSTAL RIVER ENERGY COMPLEX: 15760 W. Power Line Street
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U. S. Nuclear Regulatory Commission 3F1198-04 Page 2 of 2 This summary report concludes the Second Ten Year Inservice Inspection Interval activities for CR-3. FPC has updated the ISI program for the third Ten-Year Inservice inspection Interval to meet the requirements of ASME Code,Section XI,1989 Edition, with no Addenda, as described in Reference 3.
If there are any questions on this summary report, please contact Ms. Sherry Bernhoft, Manager, Nuclear Licensing at (352) 563-4566.
Sincerely, l
l M. W. Rencheck Director Nuclear Engineering and Projects -
MWR/pmp Attachment 1
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Regional Administrator, Region ll Senior Resident Inspector NRR Project Manager k
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1 U.S. Nuclear Regulatory Commission 3F1198-04 Attachmtnt SECOND TEN-YEAR INSPECTION INTERVAL CLOSEOUT
SUMMARY
REPORT INTRODUCTION:
The following report documents the American Society of Mechanical Engineers (ASME)Section XI Code, inservice inspection (ISI) examinations and repairs / replacements performed from the conclusion of Refuel Outage 10 through the end of the Second Ten-Year Inspection Interval (May 17,1996 through August 13, 1998), which includes the Extended Outage. The Extended Outage was the last outage for the Second Ten-Year Inspection Interval.
Examinations performed during this time period satisfy the requirements of ASME Section XI,1983 Edition, Summer 1983 Addenda. Refueling Outage summary reports for the Second Ten-Year Inspection Interval have been previously submitted and are not summarized in this report.
NRC regulations (10CFR50.55a) require that ISI examinations are performed in accordance with the latest edition and addenda of the ASME Code,Section XI, incorporated by reference,12 months prior to the start of the 120 month interval. This report contains an abstract of the examination activities conducted during this period. The detailed records of these examinations are on file and available at the plant site for review. ASME Code Cases utilized by the Florida Power Corporation (FPC) during this period are documented within this report and have been approved for use either through inclusion in NRC Regulatory Guide 1.147 or by NRC approved Relief Requests.
The Second Ten-Year Inspection Interval was scheduled to end March 13,1997. Refuel Outage 10 was expected to be the last outage of the Second Ten-Year Inspection Interval. However, due to an unplanned extended outage, the Second Ten-Year Inspection Interval was extended to August 13, 1998. The interval extension is allowed as described in ASME Code,Section XI 1983 Edition with Summer 1983 Addenda, Article IWA-2400(c) which states,"For power units that are out of service continuously for 6 months or more, the inspection interval during which the outage occurred may be extended for a period equivalent to the outage." The extended outage began September 4,1996 and ended February 5,1998. Therefore, the end of the Second Ten-Year inspection Interval was extended from March 13,1997 to August 13,1998.
EXAMINATIONABSTRACT:
Comconents One hundred forty-six (146) components were examined during this time period. A summary listing of examinations conducted on ASME Class 1,2, and 3 components is provided in Table 1 of this report. These examinations were conducted in accordance with the 1983 Edition with the Summer 1983 Addenda of the ASME Code,Section XI. For some code categories, the number of examinations conducted were adjusted as necessary to assure code requirements were satisfied for the closure of the Second Ten-Year Inspection Interval. There were no indications identified during this inspection period that exceeded the acceptance tables of ASME Section XI,1983 Edition with Summer 1983 Addenda.
U.S. Nucicar Ragulatory Commission 3F1198-04 Atttchmint Steam Genemtor Eddy Current Examinations Eddy curmnt examinations were conducted on 100% of the tubes in both steam generators during the Extended Outage.
A summary repon for these examinations was previously submitted to the NRC within 90 days of the end of the outage as mquimd in Impmved Technical Specification 5.7.2.C.
Snubbers Them were no snubber examinations perfonned during the time period described by this repon.
Comoonent Sucoorts There were eight (8) component suppons examined during the Extended Outage to meet the mquirements of ASME Section XI as modified by ASME Code Case N-491, "Altemative Rules for Examination of Class 1,2,3 and MC Component Supports of Light Water Cooled Power Plants." A summary listing of these exams is provided in Table 1 of this report.
Pressure Testina Relief Request 95-020 was issued (appmved April 14, 1996) for use of ASME Code Case N-498-1, "Altemative Rules for 10-Year System Hydrostatic Pmssure Testing for Class 1, 2, and 3 Systems". This code case incorporates those requirements pmviously appmved and documented in Relief Requests 90-20 and 91-10. As such, Relief Request 95-020 supercedes Relief Requests 90-20 and 91-10. Relief Requests 90-20 and 91-10 are no longer necessary and am hence voided.
There were no system pressure tests conducted to meet the ASME Section XI code mquirements during the Extended Outage. Pressure testing for each Repair' Replacement of ASME Class 1 and 2 coraponents is documented on the applicable NIS-2 form attached to this mport. A summary listing of these Repairs / Replacements is pmvided in Table 2 of this report.
Renairand Realacement There wem seven (7) ASME Class 1 and forty-five (45) AShE Class 2 Repairs / Replacements perfonned since the last summary report. A summary listing of these Repairs / Replacements is pmvided in Table 2 of this report. Additionally, there are 18 NIS-2 forms for ASME Class 1 and Class 2 Repairs / Replacements that were not previously submitted with the 90 day Summary Report from Refuel Outage 10 (See Table 3). This oversight was discovered as pan of the AShE Section XI self-assessment perfonned by Nuclear Engineering Pmgrams in order to assure proper close out of the Second Ten-Year Inspection Interval.
L
U.S. Nuclear Rigulatory Commissien 3 F1198-04 i
Attichm:nt Auamented Plan Examinations:
The four (4) High Pressure Injection (HPI) nozzles and associated piping up to the first isolation valve were examined by both ultrasonic and radiographic techniques. These examinations were perfonned in accordance with Babcock & Wilcox Topical Report, "HPI/MU Nozzle Component Cracking." There were no detrimental conditions identified during these examinations.
EXAMINATION
SUMMARY
This section contains a listing of all ASME Section XI Code Cases, NRC approved Relief Requests applicable to the examinations tabulated, and a summary of Non-Destructive Examinations perfomied during the Extended Outage. Table I provides the unique identification numbers for the examinations, the component examined, and the type of examinations performed.
Section XICode Cases Used Code Case N-356, Certification Period for Level III NDE Personnel.
Code Case N-416, Alternative Rules for Hydrostatic Testing of Repair or Replacement of Cass 2 Piping Section XI Division 1.
Code Case N-424, Qualification of Visual Examination Personnel.
Code Case N-446, Recertification of Visual Examination Personnel.
Code Case N-460, Alternative Examination Coverage for Gass 1 and 2 Welds.
Code Case N-491, Alternative Rules for Examination of Cass 1,2,3, and.MC Components Supports of Light Water Cooled Power Plants.
Code Case N-498-1, Alternative Rules for 10 Year System Hydrostatic Testing for Class 1,2, and 3 Systems.
Code Case N-509, Alternative Rules for the selection and Examination of Cass 1,2, and 3 Integrally Welded Attachments.
Code Case N-523, Mechanical Camping Devices for Cass 2 and 3 Piping.
Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Gass 1 and 2 Piping.
U.S. Nuclear Regulatory Commission 3F1198-04 AttcchmInt-ReliefReauests88-100 IWA-2300(a)/IWA-2300(a)(1) Recertification of Level III personnel by examination on a triennial basis. Use extended certification period of 5 years as detailed in Code Case N-356.
90-10 Core Flood nozzle Item Bl.6 examination category B-F Surface Examination. Relief from performing the surface examination.90-020 Hydrostatic pressure test and visual examination of specific limited class 2 components. *** VOID *** Superceded by 95-020.90-050 Volumetric examination of pump casing welds and visual examination of pump casing intemal surfaces, IWB-2500-1 Cat. B-L-1, Item B12.10, and Cat. B-L-2, Item B 12.20.90-060 Visual inspection of the Reactor Vessel support skirt, IWF-2500-1 Cat. F-A, Item F1.30.91-010 Code Case N-498, inservice leak testing in lieu of hydrostatic testing. *** VOID ***
Superceded by 95-020.92-010 Use of OM-4 as an alternative to the sample selection requirements of ASME Section XI, IWF-5400(c), Snubbers That Fail inservice Tests.93-030 Volumetric or surface examination performed on any 6 CRDMS removed for maintenance or cleaning in lieu of 10% of the peripheral drives.95-010 Alternate examination requirements for the core flood nozzle surface examinations.
See also RR-90-10.95-020 Use of ASME Code Case N-498-1.
Altematim Rules for 10 Year System Hydrostatic Testing for Class 1,2, and 3 Systems.95-030 Relief from examination of the Reactor Vessel lower head to transition piece weld, ISI inspection number Bl.2.2.95-040 Relief to use flat ultrasonic calibration blocks in lieu of curved blocks.
.95-055 Relief to use ASME Code Case N-523 for temporary repair to the Emergency Feedwater (EF) System.
96-001-11 Request to use ASME Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping.
97-001-11 Request to use ASME Code Case N-509, Altemative Rules for the selection and Examination of Class 1,2, and 3 Integrally Welded Attachments.
98-001-RR GL90-05 Evaluation of through wall flaw in Raw Water System.
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