IR 05000333/1989001
| ML20235H017 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/27/1989 |
| From: | Kaplan H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235G999 | List: |
| References | |
| REF-GTECI-A-07, REF-GTECI-CO, TASK-A-07, TASK-A-7, TASK-OR 50-333-89-01, 50-333-89-1, NUDOCS 8902230443 | |
| Download: ML20235H017 (6) | |
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c, U.S. NUCLEAR REGULATORY COMMISSION'
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Report No.
'50-333/89-01 Docket No.
50-333
' License No.
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Licensee:
Power Authority of the State of New York P.O. Box 41-
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Lycoming, New York 13093 Facility Name: James A.- FitzPatrick Nuclear Power Plant Inspection At:
Scriba, New York Inspection Conducted: January 3-6, 1989 7kf Inspector:
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J. Kaplan, Lead Reactor Engineer date Approved by:
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R. Strosnider, Chief, Materials date and Processes Section, EB, DRS Inspection' Summary:
Routine, announced inspection on January 3-6, 1989 i
(Inspection Report No. 50-333/89-01)
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Area Inspected: A special inspection was conducted to determine if the licensee i
had modified the FitzPatrick primary containment boundary in accordance with l
the licensee's commitments to the Unresolved Safety Issue A-7.
The inspection was focused on the QA aspects of the modification covering materials, welding,
and NDF..
l Results: The inspector concluded that the work was performed using proper l
materials, qualified welding procedures and appropriate NDE methods. No l
violations or deviations were identified.
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1.0' Persons Contacted
' 1.1 NewIork'PowerAuthority R. Converse, Site Manager T. Moskalyk, Tech. Service R. Patch, QA Superintendent V. Walz, Tech. Service Superintendent W. Fernandez, Superintendent of Power
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P. 0kas, Nuclear Engineering-1.2 US Nuclear Regulatory Commission R. A. Plasse, Resident Inspector 2.0 Inspection Purpose and Scope The purpose of this inspection was to determine if the licensee had modified-the James A. FitzPatrick Nuclear Power Plant containment in accordance with p'evious commitments to the NRC as part of the. resolution of Unresolved r
Safety Issue A-7 (USI-A-7).
USI-A-7 involved performing modifications to the Mark I containment to accomodate hydrodynamic loads on the Mark I containment that could occur from a postulated loss of coolant accident or a Safety Relief Valve (SRV) discharge in the torus structure. The licensee's bases for the necessary modifications were provided by Teledyne Engineering, Waltham, Massachusetts, in the Plant Unique Analysis Report (PUAR) Revision 1, dated September 25, 1984. The modifications made by the licensee were in accordance with the generic acceptance criteria contained in NUREG-0661.
The criteria used to evaluate the torus structure are the ASME Boiler &
Pressure Vessel Code,Section III, with addenda through Summer 1977 and Code Case N-197. Modifications were done under Section XI of the ASME Code and Summer 1978 Edition of Section III for design, materials, fabrica -
tions and inspection.
The modifications are shown in figure 1 and 2.
This inspection focused on the review of documentation and QA records covering materials, welding and NDE related to the torus modifications to verify conformance to specified code requirements. The external modifica-tions were performed by Chicago Bridge and Iron (CBI). The internal modifications were performed by C. N. Flagg.
3.0 Findings i
The inspector reviewed the QA documentation for the installation of torus saddles as performed by CBI and installation of twenty-eight thermowells performed by C. N. Flagg.
It is noted that prior to welding directly on the torus the licensee provided operational logs that indicated the torus was drained as noted in the log dated May 17, 1980. Welding of the saddle to the torus was performed during May-June 1980; welding of the thermowells to the torus was accomplished in January 1982.
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The following additional information pertaining to the~ saddle and thermowell installation was derived from a review of the CBI and C. N. Flagg documenta-tion.
Certified mill test reports indicated that the 1 1/2" thick saddle plate material was produced by Bethlehem Steel-and conformed to-the require-ments of SA 516 Gr 70 as specified in_the owners specification 05-2138-2.
A review of certified mill test reports. (CMTR) for Bethlehem heats 823J68770, 802J36050 and 490H3761 also showed acceptable charpy impact properties at-40 F.
The records showed that attaching the saddle plates directly to the torus was avoided by prebuttering the attachment areas of the torus with weld deposit. Also, magnetic particle inspection of these areas was performed a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after welding.
This procedure and welding with the torus empty were employed to preclude brittle areas in the heat affected zone (HAZ)'of_the torus and delayed cracking due to hydrogen.
The inspector verified that the CBI shielded manual. metal arc welding procedures E7018-3 and E7018-4 which were employed in the installation of the saddles conformed to the ASME IX and III Code qualification requirements as recorded in Procedure Qualification Record 4400.- The record showed satisfactory impact tests at 0 F for weld metal, base metal and HAZ.
Representative E7018 electrode test reports were reviewed and found to
'I conform to SFA 5.1 requirements along with satisfactory impact requirements at -20 F as shown in Alloy Rods certified test report for material heat 421E4911.
The inspector reviewed appropriate C. N. Flagg welding records covering the thermowell installation and concluded that the type 316 stainless thermowells were welded to the SA-516 Gr 70 to torus with an acceptable Section IX welding procedure 8-33 utilizing the Tungsten Inert Gas (TIG)
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process with type 309 filler metal. A review of CMTR's (2527 & 2504),
indicated conformance to AWS-5.9 requirements. A review of travelers showed evidence of inspection at fit-up and liquid penetrant inspection after welding.
Two apparent deficiencies were noted in the review of the CBI and C. N. Flagg documents which were subsequently resolved by the licensee. The first involved a nonconformance covering SA-193 B7 alloy steel anchor bolts supplied to CBI by Williams Form Engineering. The bolts were originally required to be impact tested at 0 as required by FS-23861, Rev. 1, but instead the tests were performed at 32 F and considered acceptable without apparent engineering approval. The licensee provided additional documenta-tion that showed that the engineer (Teledyne) had been contacted for an evaluation.
He also provided technical justification for the higher temperature on the basis of minimum operating temperatures. A review of the CMTR for the type 316 stainless steel heaterwells supplied by Carpenter Technology revealed an absence of Molybdenum (2.00-3.00 specified).
The licensee provided evidence that the subject CMTR was a reissue in which the molybdenum was inadvertently omitted.
The original CMTR as presented to the inspector had a molybdenum content of 2.34.
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.The inspector performed an inspection of the outside of the torus during
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operation to determine if the torus support column anchor bolts were defermed as recently observed at Hatch 1 & 2.
No perceptible distortion was observed by the inspector.
The inspector also examined the welds forming the saddle plates to the torus. Although the welds were painted, they did not show evidence of cracking.
4.0 Conclusion Based on the review of the saddle and thermowell document packages the inspector concluded that modifications of the FitzPatrick containment were performed with acceptable quality using proper materials, qualified welding procedures and appropriate NDE methods.
No violations or deviations were identified.
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l At no time during the inspection was written material provided to the I
licensee by the inspector.
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