IR 05000546/1979001
| ML19282C314 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 02/12/1979 |
| From: | Hayes D, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282C312 | List: |
| References | |
| 50-546-79-01, 50-546-79-1, 50-547-79-01, 50-547-79-1, NUDOCS 7903220515 | |
| Download: ML19282C314 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-546/79-01; 50-547/79-01 Docket No. 50-546; 50-547 License No. CPPR-170; CPPR-171 Licensee:
Public Service of Indiana 1000 East Main Street Plainfield, IN 46168 Facility Name: Marble Hill Nuclear Generating Station, Units 1 and 2 Inspection At: Marble Hill Site, Jefferson County, Indiana Inspection Conducted:
January 10-12, 1979
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y Inspector:
E. R.
Schweibinz t)
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Accompanying Personnel:
S. R. Lasuk C
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Approved By.
D. W.
Hayes, Chi f 2 -ll-7'i Projects Section Inspection Summary Inspection on January 10-12, 1979 (Report No. 50-546/79-01; 50-547/79-01)
Areas Inspected:
Licensee action on previous inspection findings; radiographic testing activities; and, licensee evaluation of a potential 10 CFR 50.55(e) reportable iten.
This inspection involved a total of 17 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted Public Service of Indiana (PSI)
- R. M. Brown, Construction Project Engineer F. R. Hodges, Manager, Quality Assurance
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L. McLarty, Quality Assurance Construction Supervisor
- W.
T. Smith, Construction Field Of fice Supervisor W. W. Jones, Document Control Supervisor Chicano Bridge and Iron (CB61)
F. Lusch, Project Welding and QA Superintendent J. Anderson, Radiographer D. Lusch, Radiographer C. McArther, Radiographer The inspector also contacted and interviewed other licensee and contractor personnel, including craftsmen, QA/QC, technical and engineering staff members.
- Denotes those attending the exit meeting.
Licensee Action on Previous Inspection Findings (open) Unresolved Item (546/78-02--06) - Length identification mark use on the head of the concrete expansion anchor bolt and use of air driven impact wrenches for applying torque to the concrete expansion anchor bolt.
The licensee has committed to purchase concrete expansion anchor bolts with the end stamped to identify the length.
They further agreed to contact the manufacturer relative to the use of the air driven impact wrenches.
This item remains open.
(0 pen) Noncompliance (546/78-03-01) - Failure to adequately segregate nonconforming safety related piping from conforming material in storage.
The licensee had previously committed to achieve ful?
ccmpliance by February 1, 1979.
The following portion of the corrective action will be completed by February 16, 1979.
Those pipes which have yellow " retained tags" and which are too large to be moved by hand will be wrapped in place with a yellow tape to further distinguish that they are in a "rctained" status.
This item remains open.
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(Open) Noncompliance (546/78-04-03) - Inadequate storage of B-type cadweld sleeves. The licensee committed to have the desiccant paper and caps in the cadweld sleeves by December 22, 1978.
The tape was-2-
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removed from three cadweld sleeves and all three were found not to have any desiccant paper and one of the sleeves had some snow in it.
The licensee has committed to insure that desiccant paper is in all of the cadweld sleeves and that the sleeves are securely capped or taped closed. This item remains open.
(Closed) Unresolved Item (546/78-06-01) - Defective welds identified on structural steel shipment from INRYCO, Inc.
Field corrective action request No. 401, dated October 30, 1978, was reviewed and determined to address the defective welds on the pieces of structural steel that were identified by the RIII inspector and additional structural steel which did not meet the requirements of AWS DI.1.
The corrective action taken was to add additional welds on the pieces identified and to tighten the inspection at the plant to prevent recurrence.
This item led to additional inspections by PSI QA personnel at the INRYC0 shop. The following deviation was noted by the licensee.
"During in-process surveillance it was noted that INRYCO's shop and inspection personnel were improperly interpreting the fillet weld size measurements when using a fillet weld gauge.
This deficiency resulted in the rejection by PSI of an estimated 95% of the completed work in the suppliers facility." INRYC0 has committed to reen'.ve the above situation by increasing all their welds by 1/1, above the drawing requirement. A deviation control record has been initiated to control the above situation.
INRYC0 has committed to a three point inspection program, and that all structural steel for Marble Hill will be inspected at three diffev'nt check points (1) right after welding, (2) right after blasting, at.
(3) after painting and prior to loading. This item was reviewed with the RIII inspector that originally identified the item.
This item is closed.
Funtional or Program Areas Inspected 1.
Radiographic Testing of Containment Welds On January ll, 1979, the radiographic testing by CB&I of welds in three locations of the containment dome for Unit No. I was observed.
The following observations were made:
The sources were each locked in an individual container which was shielded with lead; these containers were inside a larger container which was also locked. The keys for these containers were controlled by the radiographers.
The radiography was performed during the lunch period. No one was allowed in the area except the licensee personnel and the RIII inspectors.
The three radiographers-3-
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maintained constant surveillance over the roped _off work area.
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" Caution Radiation Area" and " Caution High Radiation Area" signs were used as required. Calibrated and operable Eberline E-130G GM survey meters were used. Radiation levels at the edge of the roped off area were observed to be less than two mR/hr.
Surveying of the source to establisn that it had retracted back into its container after each use was observed.
No items of noncompliance or deviations were identified.
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Evaluation of Potential 10 CFR 50.55(e)
A 10 CFR 50.55(e) notification was made to the Region III inspector on December 4, 1978, and retracted on January 2, 1979.
This item was in regard to the manganese centent of embedments which were installed in the auxilary building.
The manganese content of these embedments was reported to be 0.78% rather than the ASTM A-36 specification require-ment of between 0.80% to 1.2%.
The following documentation was reviewed:
Nonconformance Report No. 300, dated November 30, 1978, Identifi-cation No. 0108795027; an engineering evalution by Sargent and Lundy engineers dated December 15, 1978, Identification No. 1221780030; Field Nonconformance Report No. 096 dated December 12, 1978, Identification No. 0108795002, and the laboratory test reports of two independent test laboratories which indicated an acceptable manganese content.
Through review of the above documentation, it was determined that the criteria governing a reportable deficiency had not been met, therefore, the retraction of this 10 CFR 50.55(e) notification is acceptable.
No items of noncompliance or deviations were identified.
Exit Meeting The inspector met with the licensee's representatives (denoted in the Persons Contacted paragraph) on January 12, 1979, at the conclusion of the inspection and summarized the scoae and findings of the inspection.
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