IR 05000483/1987030

Safety Insp Rept 50-483/87-30 on 870922-24.No Violations or Deviations Noted.Major Areas Inspected:Snubber Surveillance & Functional Testing Program & Training

ML20235K031
Person / Time
Site:	Callaway
Issue date:	09/29/1987
From:	Danielson D, James Gavula NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20235K015	List: IR 05000483/1987030 ML20235K012
References
50-483-87-30, NUDOCS 8710020205
Download: ML20235K031 (5)

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U.S. NUCLEAR REGULATORY COMMISSION i

REGION III

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Report No. 50-483/87030(DRS)

Docket No. 50-483 License No. NPF-25 i l Licensee: The Union Electric Company l l Post Office Box 149 St. Louis, MO 63166 Facility Name: Callaway Plant, Unit 1 Inspection At: Callaway Site, Callaway County, M0 Inspection Conducted: September 22-24, 1987 M

InspectorA J. A. Gavula 9!E#1O l Date Approved By: D. H. Danielson, Chief 9/2fky '  ;

Materials and Processes Section Date l

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Inspection Summary Inspection on September 22-24, 1987 (Report No. 50-483/87030(DRS))

Areas Inspected: Routine, unannounced safety inspection of the licensee's snubber surveillance and functional testing program (70370), and training (41400).

Results: No violations or deviations were identifie I l

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I DETAILS , Persons Contacted Union Electric (UE)

l l J. D. Blosser, Manager Cailaway Plant l J. V. Laux, Superintendent Technical Support

• G. N. Belchik, Assistant Superintendent Maintenance C. E. Slizewski, Supervising Engineer, QA Technical Support D. H. Zimmerman, Supervising Engineer

• P. W. Godt, Quality As'surance Engineer

! *D. M. Pado, Engineer, Nuclear Engineering  !

D. C. Honse, Test Technician

• W. R. Camdell, Manager Nuclear Engineering

• D. M. Stepanovic, ISI Engineer

• D. Peters, QC Inspector

• C. Pilkington, Outage Supervisor, Engineer

• T. McFarland, Superintendent Design Control

• D. H. Zimmerman, Supervising Engineer

• L. Zahara, Assistant QC Supervisor

• L. H. Kanuckel, Supervising Engineer - Quality Assurance

• Denotes those attending the exit meeting on September 24, 1987. l Snubber Visual Inspection and Functional Testin Background The Callaway Plant has approximately 1033 safety related mechanical snubbers and 16 steam generator hydraulic snubbers. The Technical Specification (Tech Spec) functional tests utilized sampling plans 4.7.8.e.1 and 4.7.8.c.2 for the hydraulic and mechanical snubbers respectively. Functional tests for the previous outage found one mechanical snubber that exceeded the specified acceptance criteri The' evaluation of this failure concluded that the system was still operable and that it would have performed its intended functio ' Procedure Review The relevant portions of the following procedures were reviewed to determine compliance with NRC requirements.and licensee commitment (1) No EDP-ZZ-01007, " Mechanical and Hydraulic Snubber Program",

Revision 2, May 7, 198 ,

(2) No. MSM-ZZ-QWOO4, " Hydraulic Snubber Functional Test",

Revision 3, January S,198 (3) No. MSM-ZZ-QW005, " Mechanical Snubber Functional Test",

Revfsion 5, September 17, 198 i

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> (4) No. QSP-ZZ-65043, " Hydraulic Snubber Visual and Transient Event Inspection 8, Revision 0, March 6, 198 (5) No. QSP-ZZ-65044 ." Mechanical Snubber Visual and Transient Event Inspection", Revision 1. April 24, 198 It was noted that for item (5) above, the visual examination specified in the procedure was " limited to pin-to-pin in scope". On this basis, the snubber support from the pin to the structural attachment and from the pin to the component attachment were excluded from the Tech Spec visual examinations. Discussions with UE engineers indicated that these portions of the snubber supports were part of the Inservice Inspection (ISI) component support progra No adverse findings were noted during the review of the above procedures, Calibration Documentation-  !

I The calibration data for the following test equipment and components using during the snubber functional tests was reviewe (1) MHCI Snubber Test Stand, No. TS2010MT, Model No. 524, S/N M-83-001, calibration date September 9, 198 (2) Load Cell, No. TD-2004-MT, S/N 1071, calibration date September 11, 198 (3) Load Cell, No. TD-2005-MT, S/N 1065, calibration date September 11, 198 (4) Load Cell, No. TD-2006-MT, S/N 1072, calibration date September 11, l 198 All calibration data was current and appeared to be well organized i and complet J No adverse conments were made concerning the above documentation, l 1 Test Results l One of the two steam generator hydraulic snubbers tested during this .

outage failed to meet the specified acceptance criteria. The

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additional sample of two snubbers met the appropriate criteria. The initial failure was due to an excessive bleed rate on snubber i BB00R602C. At the time of the inspection, the engineering evaluation '

had not been finalized. However, since the bleed rate was only marginally exceeded, no significant corrective action is anticipate All 37 of the initial sample of mechanical snubbers met the appropriate acceptance criteria. In addition, the snubber for support BB04-R006/241, which failed last outage, met all the specified acceptance criteria during its retest tnis outag _ _ - _-__ .

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No adverse comments were made 'concerning the above informatio Training and Qualification The training and qualification records were reviewed for the following -

UE personne A. L. Vaught 4 D. C. Honse Observations made during the functional tests indicated that the test technicians were familiar with the test procedures and equipmen No adverse coments were made concerning the above informatio . ISI Components Support Visual Inspections i l Document Review ]

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The relevant portions of the following documents were to determine compliance with NRC requirements and licensee commitment j (1) No. 83A1003, " Support Assembly Inservice Examination Program Plan", Revision 2, July 9, 1985, '

(2) No. 83A1004, " Support Assembly Inservice Examination Program Data", Revision 4, September 9, 198 l It was noted by the NRC inspector that approximately 20 supports with snubbers were specified as requiring visual examinations under the program plan. However, the current list of component supports .,

examined during this outage did not contain any of the prescribed ]

snubbers. During discussions with UE engineers, it was indicated i that although the Tech Spec visual.examiantions were limited to the pin-to-pin portion of the snubber support, it could be possible to take credit for this in the ASME Section XI ISI program without requiring any additional inspection on the snubber support structur ;

Pending a review of the justification for not requiring additional '

visual examinations to meet ASME Section XI ISI requirements, or a review of the necessary visual examination data, this is considered an Open Item (483/87030-01).

Other than noted above, no comments or :oncerns were identified by the NRC inspecto Training and Qualif' cation The training and qualification records for the following UE personnel were reviewe M. J. Major Level II VT 1, 2, 3, 4 D. R. Delrichs Level II VT 1, 2, 3, 4

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All certifications were current and appropriate for the component support visual examinations being performed.. No adverse comments were made by the NRC inspecto . Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involves some cction on the part of the NRC or licensee or both. Open item (s) disclosed during this inspection are discussed in Paragraph . Exit Interview The Region III inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on September 24, 198 The inspection summarized the. purpose and findings of the inspection. The licensee representatives acknowledged this information. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed during the inspection. The licensee representatives did not identify any such documents / processes as <

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