IR 05000312/1977013
| ML19309A353 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/06/1977 |
| From: | Spencer G, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A348 | List: |
| References | |
| 50-312-77-13, NUDOCS 8003270811 | |
| Download: ML19309A353 (4) | |
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U. S. NUCLEAR REGULATORY COPEISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No. 50-312/77-13 Docket No. 50-312 License No.
DPR-54 Safeguards Group Licensee:
Sacramento Municipal Utility District P. O. Box 15830 Sacramento. California 95813 Facility Name:
Rancho Seco inspection at:
Rancho Seco inspection conducted:
September 2. 14 and 15, 1977 Inspectors is
.D 1o /4 /77 Date Signed p
L. E. Vor% rbrueggen, Reactor Inspector Date Signed Date Signed g
Approved by:
2A4+ "
/0/6/77 G. S. Spencer. Gief, Reactor Construction and Date Signed Engineering Support Branch Inspection on September 2,14 and 15,1977 (Report No. 50-312/77-13)
Areas Inspected: Routine, unannounced inspection of inservice inspection program, procedures, nondestructive examination activities, and quality records. This inspection involved 19 on-site inspection hours by one NRC inspector.
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Results: No items of noncompliance or deviations were identified during the inspection.
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IE:V Form 219 (2)
8003270 f/f
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V DETAILS 1.
Persons Contacted
- R. Rodriguez, Plant Superintendent
- R. Columbo, Technical Assistant A. Schweiger, Quality Assurance Director
- J. Sullivan, Senior Quality Assurance Engineer
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- W. Garrett, Plant Mechanical Engineer D. Abbott, Plant Mechanical Engineer C. Know, I!.I Supervisor (Atomics International ISI Contractor)
- Denotes these present at the exit interview.
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General i
The date identified as the start of comercial operation for Ra'ncho Seco is April 17, 1975. Therefore, the "l/3 interval" (40 months)
date by which at least 25% of the ASME'Section IX code required
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examinations must be completed is August 17, 1978. Consequently,
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considerable latitude in defining the items to be examined durinc, the current refuelina outage was available, except for tne steam O
generator tubes which have specifically defined inspection :.equire-ments in the technical specifications.
The plant was shut down on August 19, 1977. Because of unexpectedly high radiation levels associated with primary system piping and components, several substitutions were made in the list of items scheduled for examination during this outage.
Except for the steam generator tube inspection, the performance of this segment of the inservi e inspection program was contracted to j
the Atomics International (AI) Division of Rockwell International Corporation. AI then obtained the services of qualified examiners and the necessary equipment from Ebasco Services, Inc. for accomplishing the nondestructive examinations. AI provided super-vision for the conduct of the operations and will provide the final report. The eddy-current examination of the steam generator tubes was contracted to Zetec, Inc. of Seattle, Washington, who will also provide a final report on this -examination.
The authorized inspection agency engaged by the licensee is Hartford Steam Boiler Insurance Company.
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3.
Program Plan and Procedures The approach taken by the licensee for this segment of the ISI
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program was to prepare one special test procedure (STP) for piping and components and a separate STP for the steam generator tube i
inspection. The use of STP's is a standard provision of the licensee's administrative procedures..The procedures used for the
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nondestructive examinations were~ prepared by the respective
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contractors. The inspector noted that all procedures had been approved by the licensee's Technical Support Group, Quality Assurance, and the Plant Review Committee (PRC).
It was also noted
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4.
Observation of Work The inspector observed the penetrant examinatica of the weld
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joining the reactor coolant pump "D" suction to the 28-inch outlet
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l line from steam generator
"A."
It was noted that the work was
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j performed in full accord with the applicable procedure.
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5.
Record Review The qualification records of the NDE personnel were inspected.
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was noted that all examiners had current qualifications in accordance
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with the Society for Nondestructive Testing (SNT) standards. The NDE procedures were also examined. The inspector concluded that they satisfied ASME Section V requirements.
The certifications for the UT couplant, t id the cleaner, developer and dye for the penetrant examinations were examined, as were the i
calibration certifications and checks for the UT instruments. No discrepancies were noted.
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The records of the examinations performed on the piping and components were examined on a random basis. Standard forms had been used to record the data. The records appeared neat, properly indexed, and the reportable indications satisfactorily described. No discrepancies were noted. The licensee stated that the extent of the program, as modified from the original scope because of inaccessibilities and high radiation level problems, had been accomplisned and that this amounted to approximately 25% of the examinations required by the ASME code for the Nrst 10 year intervaI. The remaining required 81/3% will be performed during the summer 1978 refueling outage..
The raw data pertaining to the eddy-current testing of the tubes of the two steam generators were not examined because of ongoing O
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O-3-off-site evaluation by 'the contractor at the time of the inspection.
The results, however, were discussed with the licensee's cognizant engineer for that phase of the ISI program. He informed the inspector as follows:
Steam generator "B" displayed no reportable indications from the l
520 tubes which were examined.
(The technical specifications required that 3% of the tubes be examined
.03 x 15,457 = 464 tubes)
Steam generator "A" displayed six questionable tubes (20 - 60%
degraded) in the first 3% that were examined, but none with imperfection i
indications greater than 20% in the additional 6% that had to be examined. A total of 1391 tubes were examined. In all six degraded tubes, the deficiency was located in the vicinity of support plate
no.15 which is the first support plate telow the upper tube sheet.
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This is similar to the wastage anomaly found in the B&W steam generators at the Oconee Nuclear Plant.
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The inspector verified that the technical specification requirements pertaining to steam generator tube examination had been met. The licensee is evaluating the test results and has not determined whether or not all six of the degraded tubes in steam generator "A" will require plugging.
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