IR 05000255/1996016
| ML18066A812 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/03/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18066A811 | List: |
| References | |
| 50-255-96-16, NUDOCS 9701080118 | |
| Download: ML18066A812 (7) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION REGION I I I Docket No:
License No:
Report No:
Licensee:
Facility:
Location:
Dates:
Inspectors:
Approved by:
9701080118 970103 PDR ADOCK 05000255 G
PDR 50-255 DPR-20 50-255/96016(DRS)
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Palisades Nuclear Generating Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 November 19-21, and December 16, 1996 D. Jones, Reactor Inspector W. J. Kropp, Chief, Engineering Branch 1 Division of Reactor Safety
Report Details II. Maintenance M3 Maintenance Procedures and Documentation M Inservice Inspection (ISi) Inspection Scope (73753. 73051, 73052, 73755)
The inspector reviewed and evaluated the ISi program, procedures, ISi personnel certifications, and ISi data taken during the 1996 refueling outage for compliance with technical specifications, ASME Code, ASNT SNT-TC-lA, "Nondestructive Testing Personnel Qualification and Certification," and NRC requirement Observations and Findings The inspector's review of the ISi' program concluded that it met the ASME Code Section V, 1989 Editio The ISi plan was well organized with augmented inspections of applicable welds scheduled and distinguished by separate, well defined inspection categories based on the requirement sourc Review of the licensee's inspection program, procedures, analysis guidelines, examiners certifications, and graphics and inspection data concluded that the licensee's steam generator (SG) performance was good and the inspection program was conservativ The program utilized state-of-the-art equipment and inspection techniques including the Westinghouse TC 6700 remote data acquisition unit (RDAU) controlled by the Westinghouse ANSER acquisition softwar The NRC inspector observed portions of SG eddy current testing. Testing was performed in accordance with commitments to Generic Letter 95-0 Although an inspection sample of only 3% of the tubes was required, the licensee inspected 20% of the tube The sample was expanded in the "A" steam generator to include 100% of the tubes in rows 1 and 2 to the top of the U-bend, and 100% of the top of the tubesheet area using the motorized rotating pancake coil (MRPC) plus point prob The twenty-percent sample using the bobbin coil found no pluggable indications, however the MRPC examination using the plus point probe found four indications in SG "A", two axial crack indications and two volumetric indications, which were plugge Engineering analysis, performed by Westinghouse, of the two axial cracking indications demonstrated past structural integrit The engineering structural integrity analysis report concluded that the burst pressures at the two axial cracking indications would be greater than five times the normal operating differential pressur In addition, the steam generators were subjected to sludge lancing and a visual examination of the tubesheet are The inspector reviewed the video tape of the removal operation of a small piece of foreign material
(similar in size to a wire tie) from the "A S The licensee determined that the material was from a flexitallic gasket used on the flange-to-flange joint on the main steam line Conclusions The ISi program complied with NRC and ASME Code requirements and no violations or deviations were identified. The inspector considered the ISi plan particularly well organized and documente The use of "state of the art" equipment to perform eddy current examinations for the Inservice Inspection Program demonstrated an important element of a quality progra The steam generator eddy current inspection program was conservative with a positive management oversigh M Inservice Inspection (lnconel Alloy 600 components) Inspection Scope (73753, 73051, 73052, 73755)
The inspector reviewed and evaluated the Inconel Alloy 600 ISi program, procedures, ISi personnel certifications, and ISi data taken during the 1996 refueling outage for compliance with technical specifications, ASME Code, SNT-TC-lA and NRC requirement Observations and Findings ISi procedures used in support of the Alloy 600 Project Plan were reviewed by the NRC inspector The ISi procedures were found to be acceptable and in accordance with ASME Section V, 1989 Edition as modified by requirements of the Alloy 600 Inspection Specification, Revision The inspector reviewed qualifications and certifications of all licensee personnel performing ISi, verifying conformance with the licensee's Alloy 600 specification Revision 0 requirement The engineering department's performance of the Alloy 600 project was excellen The licensee's use of mockups to demonstrate and qualify nondestructive examination techniques, including automated data acquisition using optimized angles and transducers for dissimilar metal welds, was a strengt The licensee qualified the techniques under the EPRI performance demonstration initiative (POI}, although the POI was only required for similar metal weld Also, the ALARA goal for the
- Alloy 600 project was set at 30% of the last Alloy 600 inspection dose, which was unexpectedly hig At the end of the inspections, the licensee was well within the goal with a total dose of 75% of the projected dos The licensee's Alloy 600 Project Plan, represented a sound technical approach to managing primary water stress corrosion cracking (PWSCC) in Inconel Alloy 600 materials within the primary coolant system (PCS).
The nondestructive testing (NOE) techniques and acceptance criteria used were reasonable and consistent with analysis and industry practices. *
The NOE inspections completed this outage assured components in the most susceptible category, Group I, and the more susceptible components category, Group II, received ultrasonic (UT) or dye penetrant (PT) and visual inspection (VT).
All identified Alloy 600 locations in the PCS
received a visual inspection as a m1n1mu No PWSCC was found during inspections performed this outag The Alloy 600 plan included, as one of several goals, the development of an inspection program to identify and to characterize PWSCC in Inconel Alloy 600 components.* Toward this goal, the plan identified 251 Inconel Alloy components potentially susceptible to PWSCC in the plant. These components were grouped into three levels of inspection priority based on susceptibility to PWSCC, consequence of failure, detectability and ALARA consideration During this outage, all planned inspections were complete During the last outage the original scope of planned inspections was reduced to save total project radiation dose expenditur However, the completed inspections covered all Inconel Alloy 600 components listed as the highest priority (group I) in the pla The licensee will perform the lower priority ihspection categories listed in the original plan, which were deleted during the last outage, over the 10-year inspection interva The following observations were noted as strengths associated with the planned inspection of Inconel Alloy 600 components:
During the last outage, an unidentified flow diverter plate in the pressurizer spray line prevented a planned I.D. penetrant inspection (l.D. PT) on the pressuriz~r spray safe en However, during this outage an external UT and PT was performed in lieu of the l.D. PT;
To address the possibility of exterior fatigue cracking, the licensee used PT inspections on outside surfaces of components to augment the UT or VT performed;
The ALARA planning effort resulted in a significant radiation dose reduction associated with planned inspection activities at approximately 23% of the last Alloy 600 inspection dose;
The use of mockups, EPRI POI qualified NOE techniques, and scanning equipment designed and bui~t specifically for Palisades component Conclusions The Engineering Department's planning and implementation of the Alloy 600 project was observed to be positiv The UT and PT examination data reviewed was found to be in accordance with the applicable ISi procedures and the Alloy 600 Specification, Revision *
III. Engineering E2 Engineering Support of Facilities and Equipment E Inspector Review of Updated Safety Analysis Report (UFSAR)
Xl While performing the inspections discussed in this report, the inspector reviewed UFSAR sections: Inservice Inspection Primary Coolant System-System Design and Operation Primary Coolant System-Tests and Inspections Inservice Inspection of Class 1, 2 and 3 Components The inspector did not identify any UFSAR discrepancies as a result of this special revie V. Management Meetings Exit Meeting Summary The inspector presented the inspection results to members of licensee management during an exit meeting on November 21, 1996. The licensee acknowledged the findings presented.
The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietar No proprietary information was identifie PARTIAL LIST OF PERSONS CONTACTED Licensee
- J. Beer, Health Physics Support Supervisor
- D. Fadel, Systems Engineering Manager
- J. Ford, Systems Engineering Supervisor
- T. Fouty, Senior Technical Analyst
- B. Gerling, Design Engineering Deputy Manager
- K. Powers, General Services Manager
- T. Rexius, Technical Analyst
- B. Roberts, Licensing
- B. Vincent, Licensing Supervisor
- F. Yanik, NPAD U.S. NRC
- M. Parker, Senior Resident Inspector, Palisades
- W. Kropp, Chief, Engineering Specialists Branch l, DRS Westinghouse B. Pollice, Eddy Current Coordinator
- Present at exit meeting on November 21, 1996.
- IP 73051:
IP 73052:
IP 73753:
IP 73755:
ALARA ASME ASNT PWR CPCO DRS EPRI GL ID IR ISi MRPC NOE NRC UT PCS POI PDR PT PWSCC RDAU RT SG UFSAR VT INSPECTION PROCEDURES USED Inservice Inspection - Review of Program Inservice Inspection Review of Procedures Inservice Inspection Inservice Inspection - Data Review and Evaluation LIST OF ACRONYMS USED As Low As Reasonably Achievable American Society of Mechanical Engineers American Society of Nondestructive Testing Pressurized Water Reactor Plant Consumers Power Company Division of Reactor Safety Electric Power Research Institute Generic Letter Inside Diameter
Inspection Report
lnservice Inspection
Motorized Rotating Pancake Coil
Nuclear Regulatory Commission
Ultrasonic Testing*
Primary Coolant System
Performance Demonstration Initiative
NRC Public Document Room
Dye Penetrant Test
Primary Water Stress Corrosion Cracking
Remote Data Acquisition Unit
Radiographic Testing
Updated Final Safety Analysis Report
Visual Testing
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