IR 05000312/1981010
| ML19345H155 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/01/1981 |
| From: | Kirsch D, Wagner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19345H153 | List: |
| References | |
| 50-312-81-10, NUDOCS 8105010071 | |
| Download: ML19345H155 (5) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No.
50-312/81-10 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 Site Inspection conducted:
March 9-13, 1981 Inspectors:
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$l h. Wagner Reactor Inspector
/ Dafe Signed
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Date Signed Approved by:
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D.F.Kiri5I, Acting, Chief,ReactorProjectsSection1 Date W gned
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Reactor Construction Projects Branch Summary:
Inspection on March 9-13, 1981 (Report No. 50-312/81-10]
Areas Inspected:
Routine, announced inspection by regional based inspector of inservice inspection activities including review of new and revised nondestructive examination procedures, and inservice inspection data review and evaluation.
The inspection involved 36 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
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DETAILS 1.
Individuals Contacted a.
Sacramento Municipal Utility District (SMUD)
T. Perry, On-Site Quality As>arance Supervisor J. Uhl, Plant Mechanical Engineer G. Coward, Maintenance Supervisor H. Heckert, Nuclear Engineering Technician R. Colombo,-Technical Assistant S. Rutter, Quality Assurance Engineer P. Oubre', Plant Superintendent D. Whitney, Engineering and Quality Control Supervisor R. Rodriguez, Manager, Nuclear Operations b.
Other
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H. L. Canter, NRC Senior Resident Inspector All the above persons were present at the exit interview.
2.
Licensee Action on IE Information Notice No. 81-04:
Cracking in Main Steam Lines IE Information Notice 81-04 notified operators of nuclear generating plants of a cracking problem identified on main steam line fittings.
The information notice recommended that licensees having plants with similar steam line configurations perform ultrasonic and/or radiographic examinations of the weld joints.
The licensee determined that the configuration of the "A" Main Steam line was of a type addressed by the notice.
The ISI contractor, B&W, performed ultrasonic examinations on all three weld joints of the tee. These examinations found all the welds to be clear of any recordable indications.
The inspector visually examined the "A" Main Steam line where the ultrasonic examination was performed.
The "B" loop, which contains the safety relief valves, has no tee, and consequently did not require examination.
The volumetric test data of this examination (performed 3/7/81) was reviewed and evaluated by the inspector for compliance with requirements of the governing ASME code.
No items of noncompliance or deviations were identified.
3.
Review of Quality Implementing Procedures The following inservice inspection (ISI) procedures were examined i
for compliance with technical specification and applicable code requirements:
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151-120, Revision 12, dated 1-8-81, " Ultrasonic Examination of Piping and Vessel Welds Joining Similar and Dissimilar Materials".
b.
ISI-240, Revision 11, dated 12-10-80, " Penetrant Examination of Weld and Base Materials Including Studs and Nuts".
The inspector questioned the qualifications of the procedure which allows the work piece and penetrant to be at a temperature g
g between 44 F and 125 F during the penetrant examination.
ASME Section V, Article 6 requires liquid penetrant procedure requalification if the technique is to be used at less than 600 F.
The qualification data was not available to the inspector during this inspection.
However, the ISI contractor, B&W, said they would forward this information to the licensee.
This item will be re-examinated during a future inspection.
(50-312/81-10/01)
c.
ISI-270, Revision 8, dated 12-11-80, " Wet or Dry Methods of Magnetic Particle Examination of Welds, Studs, Bolts, and Pump Motor Flywheels".
d.
ISI-350, Revision 12, dated 10-6-80, " Visual Examination of Welds and Surface Conditions". Section 4, second paragraph states:
"Whenever necessary, surface conditir.ning shall be accomplished by a mechanical process such as ruchining, grinding, or belt sanding to provide a suitable surface finish".
This appears to be counter productive to the purpose of visual examination in that any indications could be masked or adverse surface conditions could be smoothed out. Discussions with l
the licensee indicated that this paragraph would be deleted.
This item will be examined during a future ir,spection.
(50-312/81-10/02)
e.
ISI-353, Revision 3, dated 10-6-80, " Visual Examination of Pipe Hangers, Supports, and Hangers".
f.
ISI-401, Revision 11, dated 2-12-80, " Eddy Current Examination for Defects in OTSG Tubing".
No items of noncompliance or deviations were identified.
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4.
Data Review and Evaluation The inspector reviewed and evaluated the following nondestructive test data records for compliance with requirements of the ISI i
program:
a.
Examination Bl.3.2 (1980) Reactor Pressure Vessel - Ultrasonic examination of closure head flange to head.
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Examination 82.3.1 (1980) - Visual examination of pressurizer heater penetrations.
c.
Examination B4.1.35 Reactor Coolant Pump - Ultrasonic examination of pipe to safe end.
d.
Examination B4.1.36 Reactor Coolant Pump - Penetrant examination of pipe to safe end.
e.
Examination B4.1.56 Pressurizer Surge - Ultrasonic examination of surge nozzle to pipe weld.
f.
Examination B4.1.57 Pressurizer Surge - Penetrant examination of surge nozzle to pipe weld.
g.
Examination 84.1.66 Reactor Coolant System - Ultrasonic examination of pipe to resistance thermal element.
h.
Examination B4.1.67 Reactor Coolant System - Penetrant examination of pipe to resistance thermal element.
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Examination B4.5.140 High Pressure Injection - Ultrasonic examination of pipe to tee.
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Examination C2.1.11 Feedwater - Ultrasonic examination of
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elbow to tee.
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Examination Bl.8.4 Reactor Vessel - Magnetic particle examination of closure head nuts.
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Examination C1.3.1 Steam Generator A - Magnetic particle examination of feedwater header brackets to shell.
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Examination C2.5.37 Piping Main Steam A - Magnetic particle
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examination of support attachment.
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Examination C2.6.64 Piping Main Steam B - Visual examination of rigid support.
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Examination B6.9.9 Decay Heat Removal - Visual examination of valve bonnet bolting.
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Examination B6.9.23 High Pressure Injection - Visual examination of valve cover bolting.
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Examination B2.6.66 Piping Main Steam B - Visual examination l
of rigid support.
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Examination LO.3.3 Spent Fuel Supply - Visual examination of l
15 hangers and supports.
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Examination X0.1.1 Steam Generator A - Eddy current examination in OTSG tubing.
The 929 tubes examined were all from steam generator "A" which represents the required 6 percent tube inspection. The calibration sheets were also reviewed by the inspector.
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The B&W ISI Evaluation Report Log was perused for reports in which indications were reported. The purpose was to identify any potentiaf areas of concern to the NRC and to review B&W/SMUD evaluation ar.i final disposition of the indication.
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No items of noncompliance or deviations were identified.
5.
ISI Status Rancho Seco is in its first inspection interval which covers the ten year period since the plant was initially placed into commercial-operation (March 1975).
During the first 40 months of this inspection, int-
.1 inservice examination was performed during outages 1, 2 an The current ISI is in the 4th outage which is the start of the ad 40 month period.
Inservice examination for outages 5 and
'l be combined and performed in 1982 due to the long outage For TMI modifications.
expes
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6.
Exit Interview The inspector met with the licensee representatives denoted in paragraph I at the conclusion of the inspection.
The scope and findings of the inspection were discussed.
The licensee acknowledged the inspection findings and will resolve the open items. The licensee also agreed to keep the inspector informed, on an informal basis, as to the actual dates future ISI activities will take place during normal operation or shutdown.
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