IR 05000333/1993003
| ML20034G876 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/24/1993 |
| From: | Gray E, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20034G873 | List: |
| References | |
| 50-333-93-03, 50-333-93-3, NUDOCS 9303120038 | |
| Download: ML20034G876 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION l
REGION I
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REPORT / DOCKET NO.:
50-333/93-03
LICENSE NO.:
DPR-59 P
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LICENSEE:
New York Power Authority.
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FACILITY NAME:
James A. Fitzpatrick Nuclear Plant l
INSPECTION AT:
White Plains, New York i
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I INSPECTION DATES:
January 25-29,1993 i
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Z/2 f/FJ INSPECTOR:
i R. A. McBrearty, Reaffor Engineer Date Materials Section, EB, DRS APPROVED BY:
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E/4V/93 E. Harold Gray, Chief, Materials Section, Date j
Engineering Branch, DRS r
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9303120038 930305
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PDR ADDCK 05000333
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Agas Inspected: The licensee's inservice inspection (ISI) program and associated activities were reviewed to ascertain that the program was implemented in compliance with code and regulatory requirements and that the established program controls were effective. Emphasis was placed on the licensee's evaluation and disposition of nonconforming examination results and on the planning and scheduling of examinations for the last refueling outage.
Additionally, the licensec's crosion/ corrosion program was selected for inspection.
Rclults: The ISI program is being implemented in compliance with ASME Code Section XI and regulatory requirements. The evaluation of examination results was clearly documented, and the disposition of nonconforming results was technically justified and supported by the related documentation.
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The erosion / corrosion monitoring program is based on EPRI and industry guidelines and uses j
the EPRI developed CHEC/CHECMATE family of computer codes for selection and
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prioritization of the E/C inspection sample. The E/C responsible engineer maintains the IVC program and is made aware of related industry problems by various means including the Operating Experience Report established by the licensee to document industry and plant experiences.
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1.0 INSERVICE INSPECTION (ISI) PROGRAM (Inspection Procedure 7305I)
This inspection was performed at the corporate office of the New York Power Authority at
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White Plains, New York to ascertain that appropriate controls and responsibilities regarding the ISI program had been established by the licensee.
The Fitzpatrick plant is in its 2nd 10-year inspection interval which is governed by the
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1980 Edition through winter 1981 Addenda of the ASME Boiler and Pressure Vessel Code,Section XI.
The licensee has established Plant Standing Order (PSO) No. P30-31 A, Revision 6, "ISI Program for Piping, Supports and Pressure Retaining Components," to provide administrative
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i controls for the implementation of ISI of safety-related piping, supports and other pressure retaining components. The PSO establishes responsibilities to ensure program i
implementation in compliance with applicable code and regulatory requirements. Augmented ISI, the Section XI mandated repair program and the licensee's responsibilities regarding i
10 CFR 50.55a for performing inservice inspection of nuclear plant pressure boundary
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systems and components classified as safety Class 1,2 and 3 are included in the document as part of the ISI program. An ISI engineer has been designated by the licensee to perform various functions regarding the administration and implementation of the program. Among the responsibilities of the ISI engineer are:
Control of the ISI program data base.
- Development of the inspection scope for upcoming outages.
- Reporting to the site manager of evaluated discrepancies that may compromise system
structural integrity, or that appear to be service induced. The report must be made as soon as the evaluation is completed. (The ISI engineer is notified of discrepancies via an Adverse Quality Control Report (AQCR) issued by the licensee's Level II or Level III individual).
Ensuring that all scheduled examinations have been completed prior to plant stanup
from an outage.
The Plant Operations Review Committee (PORC) review and acceptance of PSO-31 A, Revision 6 is documented by the minutes of PORC meeting No.92-026 and, additionally, the PSO is approved by the Fitzpatrick plant resident manage _.
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2.0 INSEltVICE INSPECTION PROGitAM IMPLEMENTATION (IP 73051,73753)
Various attributes of the ISI program were selected for inspection to determine whether the established controls were effective. Included in the inspection were the licensee's process for the evaluation and disposition of ISI results, planning and scheduling of examinations that were performed during the spring 1992 refueling outage, and the quali6 cation /ccrtification records of NDE personnel who performed examinations during the 1992 refueling outage.
2.1 Evaluation / Disposition of ISI Results Data identifying examination results requiring evaluation related to the reactor pressure vessel system, reactor recirculation system, residual heat removal system and the main steam system were inspected to ascertain that the basis on which discrepant results were dispositioned was technically correct.
The plots of the location of ultrasonic reflectors and, in the case of surface defects, the removal of the defect and subsequent examination to verify defect removal were documented and included in the various data packages to support the resulting disposition by the licensec.
Additionally, during the surface examination of main steam weld 24-39-602, examination personnel reported that drawing Il825-MSK-3032 incorrectly showed supports associated with the piping. Indication Noti 0 cation Report No. INR-075 and Drawing Change Request No. DCR-92-271 were prepared to document the discrepancy and to affect the drawing revision to correct it. Those documents resulted in the update of the questioned drawing which now depicts the correct configuration.
l 2.2 Nondestructive Examination (NDE) Personnel Qualification / Certification Records Qualification /CertiGcation records of National Inspection and Consultants, Inc. and Ebasco personnel responsible for performing inservice inspection examinations at Fit 7 patrick were inspected to determine whether those personnel were qualified and certiGed in compliance with SNT-TC-1 A and the licensee's program to perform their assigned responsibilities.
The records confirmed that the examiners were properly certi6cd to the appropriate level of competence commensurate with their assigned respcmsibilities.
Condmien The ISI program at Fitzpatrick is being implemented in compliance with applicable ASME Code and regulatory requirements.
Examination results are clearly documented, questionable results are evaluated by qualified individuals and dispositions are technically justified and supported by the associated documentation.
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Vendor examiners who performed ISI at Fitzpatrick were properly qualified and certified to the appropriate level of competence commensurate with their assigned responsibilities.
3.0 EROSION / CORROSION PROGRAM (IP 49001)
3.1 Background Concerns regarding crosion and corrosion in balance of plant piping systems has been heightened as a result of the December 9,1986, feedwater line rupture that occurred at Surry Unit 2. This event was the subject of NRC Information Notice 86-17,Bulletin 87-01 and Generic Letter (GL) 89-08. The GL specifies that all licensees provide assurances that a program, consisting of systematic measures to ensure that E/C does not lead to degradation of single and two phase high energy carbon steel systems; these requirements have been implemented.
An effective E/C program provides a means for early detection of erosion of high energy carbon steel piping before the pipe wall is significantly reduced below the design or piping code minimum wall thickness. The program should reduce risk to the plant staff and prevent unnecessary system transients, thereby contributing to the safety of the public.
3.2 Erosion / Corrosion Program Responsibilities The E/C program is maintamed by the designated responsible engineer as delir cated by Plant Standing Order (PSO) No. PSO-14, Revision 4, " Erosion / Corrosion Inspection Program."
The PSO establishes administrative controls for the program implementation and identifies individual responsibilities. The duties of the raponsible engineer include: periodic review of completed plant modifications to assess their effect on the scope of the E/C program, ensuring that appropriate corrective action is taken when significant wall thinning has been identified, the revision and/or expansion of the E/C program scope to incorporate industry and in-house experiences, and ensuring that wall thinning evaluations are performed prior to plant startup.
l 3.3 Evaluation of E/C Results
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The New York Power Authority Engineering Standards Manual (ESM) P ocedure ESM #CES-7, Revision 0, " Procedure for Structural Evaluation of Erosion-Corrosion Thinning in Carbon Steel Piping " r,rovides guidance to evaluate pipe wall thinning as a result of erosion-corrosion.
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f Acceptance criteria are based on piping primary stress requirements of USAS B31,1 code,
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seismic piping stress requirements applicable to the Fitzpatrick facility and acceptance
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standards of ASME Code Case N-480. Pipe wall thinning evaluation is based on a three step process. Progressing from step to step is determined by the results of each step of the evaluation and is clearly defined by the procedure. Results that show wall reduction to less thaa 87.5% of the nominal wall thickness must be reported to the responsible engineer within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the determination, and an Adverse Quality Condition Report (AQCR) must be issued by the responsible engineer to ensure that the appropriate corrective action is taken.
All E/C inspection data must be reviewed and signed by the re.ponsible engineer and, as discussed above, he is responsible for ensuring that wall thinning evaluations are completed prior to plant startup. Subsequent to completion of the scheduled inspections and upon issuance of the outage report, the responsible engineer is required to update the E/C computer code (CHEC/CHECMATE) with the most recent inspect;on data. The inspector confirmed that the update of feedwater system piping information was completed and update of extraction steam system data was in progress during this inspection.
Approximately 118 items were inspected for E/C during the 1992 refueling outage of which two lines on the moisture separator reheater drain system were replaced because of wall reduction which was attributed to fit-up and erosion / corrosion. The pipirg was replaced with P-22 material (chromium-molybdenum), which is considered resistant to ecosion/ corrosion.
Additionally, the licensee is considering the replacement of additional piping during the 1994 refueling outage based on recent inspection results.
3.4 Selection of Inspection Locations The selection of systems and components for E/C inspection is accomplished with the use of the Electric Power Research Institute (EPRI) developed CHEC/CHECMATE computer codes. In 1992, the licensee converted to the CHECMATE code from CHEC, which was used originally. The conversion was recommended by EPRI guidelines.
The following systems are included in the Fitzpatrick E/C program:
Feedwater Heater Drain *
Main Feedwater
Reheater Drain *
Moisture Separation Drain *
Condensate
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RBCLC and TBCLC Service Water
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Emergency Service Water Minimum Flow Line
RHR Fuel Pool Cooling Assist Line
HPCI, RCIC, RHR, Core Spray Minimum Flow Line
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Valves subject to cavitation per memorandum #JAF-90-0623
Includes smaller diameter (< 4") lines, for exampic vents, drains, etc., based on
plant or industry experience.
NRC Information Notice 92-35 alerted the industry to an E/C problem in an unisolable l
reactor coolant pressure boundary piping inside containment at a boiling water reactor. The
New York Power Authority factored the appropriate information into its CHEC computer i
analysis and determined that the identified locations were low priority inspection points at Fitzpatrick. The licensee has added those locations to its E/C inspection scope for the next
scheduled (1994) refueling outage.
In addition to information provided by the NRC and the CHEC/CHECMATE Users Group (CHUG), the E/C responsible engineer is made aware of industry problems by the in-house
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Operating Experience Report so that he can determine whether conditions at Fitzpatrick are similar or if the problem is likely to occur at the plant.
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Conclusion
The licensee has established an effective erosion / corrosion (E/C) monitoring program that is
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based on industry and Electric Power Research Institute (EPRI) guidelines regarding sample selection, and evaluation / analysis of inspection results.
t In response to EPRI recommendations and a desire to strengthen its pr'r, ram, the New York Power Authority (NYPA) converted its E/C computer code from CHEC to the newer
CHECMATE in late 1992. The newer code is now used for selection and prioritization of the inspection sample and for analyzing inspection results.
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Its response to NRC Information Notice (IN) 92-35 is further evidence of the licensee's -
desire to improve and strengthen its E/C program and enhance plant safety, Based on the notice, NYPA modeled inspection points in its FJC computer program similar to those
identified by the IN and, although the analysis identified the locations as low priority inspection points, they have been added to the E/C inspection scope for the next scheduled (1994) refueling outage.
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4.0 EXIT MEETING
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The inspector met with licensee representatives, denoted in Attachment 1, at the conclusion of the inspection on January 29,1993. The inspector summarized the scope and findings of
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the inspection.
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ATTACHMENT 1
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t Persons Contacted
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New York Power Authority
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- H. Fish, Licensing
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- D. Franger, Senior Quality Assurance Frigineer
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- R. Lauman, Acting Vice President Nuclear - Operations & Maintenance
- R. Penny, Nuclear Maintenance Engineer - Supervisor
- F. Pesce, Director Quality Assurance
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- D. Sancic, Manager Nuclear Planning l
- A. Smith, Nuclear Maintenance Specialist
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Indicates those present at the exit meeting.
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