IR 05000289/1980026
| ML19345B613 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/01/1980 |
| From: | Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345B611 | List: |
| References | |
| 50-289-80-26, NUDOCS 8012020216 | |
| Download: ML19345B613 (4) | |
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O U. S. NUCLEAR REGULATORY COMMISSION OFFICF OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-289/80-26 Docket No.
50-289 License No.
DPR-50 Priority Category C
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Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania Facility Name:
Three Mile Island Nuclear Station, Unit 1 Inspection At:
Middletown, Pennsylvania Inspection Conducted:_ September 10-12, 1980 Inspectors:
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/d' /'F G R;' J.
aolino, Reactor Inspector date S. D. Ebneter, Chief
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date Engineering Support Section #2 date Approved by:
L.
/vkdf0 T. D. Ebneter, Chief, Engineering Support date Section 2, RC&ES branch Inspection Summary:
Inspection on September 10-12, 1980 (Report No. 50-289/80-26)
Areas Inspected:
Routine unannounced inspection by one re.gional based inspector of work activities and quality records associated with the Unit 1 Restart Program.
Specific area selected:
Task LM-9, relocation of pressurizer transmitters above flood level; Task RM-13A, emergency feedwater controls.
The inspection involved 24 inspection hours on site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 1977)
8022o20 21G
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DETAILS
1.
Persons Contacted GPUSC
- J. Wright, QC Manager
- J. Fritzen, Project Engineer - Technical Functions Metropolitan Edison Company W. Shumaker, Lead QC Electrical Engineer
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- W. Shaffer, Technical Analyst - Unit 1 Restart
- R. Harding, Supervisor of Licensing
R. Summers, Mechanical Engineer A. Makitka, Senior Engineer - Mechanical Section (Parsippany)
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H. Wilson, Maintenance Foreman GilbertAssociates!Inc.
Dan Biss, Structural Engineer
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Construction Engineering Consultants L. Lohnes, Lead Civil Engineer U. S. Nuclear Regulatory Commission
- D. Haverkamp, Senior Resident Inspector TMI-1
- Denotes personnel present at exit interview.
2.
Pressurizer Level Transmitters (Task LM-9)-Records Review The inspector reviewed pertinent work and quality records for safety related modifications pertaining to the TMI-1 Restart Prograr,
to determine whether the records reflect work accomplishments consistent with NRC requirements and licensee commitments.
Documents reviewed for this determination included:
A.
Task LM-9 (Relocation of Presse, 'r Transmitters)
Drawing No!s A-9459-01-lH-1,
-2,
-4,
-5,
-7, -10. -11, -12, -13 and -14
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Engineering Change Memo S-014, Revision D,1 & 2
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I, Quality Control Inspection Report SI-631, 632.
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Engineering Memo No:s GEM 2289, 2436 2531 and 3397.
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Purchase Requisition No:s 86531 & 86528.
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Environmental Impact Statement dated June 20, 1969.
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Drawing No. B-308-854, Revision IA-0
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Field Questionaire No. R-33.
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Design Change Request No. CS2-143.
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(1) The inspector noted an apparent discrepancy between the information presented on the Type 11 standard instrument bracket drawing (number A-9459-01-14-11) and the quality control inspection report numbers SI-631 and SI-632.
The inspection report shows that 1/2 in.self-tapping anchor bolts were used.
The drawing calls for 3/8 in. holes, typical 4 places.
The supervisor responsible for relocating and installation of the brackets claims 3/8 in.self-tapping (. Red Head type) anchor bolts were used.
QC personnel sent out for verification insist the 1/2 in. bolt was used.
Tnis item is unresolved pending NRC verification of actual installation.
(50-289/80-26-01).
(2) Drawing A-9459-01-0H-14, type 14 mounting bracket fer the low level transmitter calls for a 5/8 in.RAWLS (similiar to Phillips Red Head) self-tapping anchor bolt.
The hole spacing on the drawing is 4 in.
Section 1:07-9 of Soecification SP-1101X-503 indicates spacing between bolts in concrete to be 12 bolt diameters.
This would mean a 6 1/4 in. spacing for this application.
In addition, table 1 of Procedure No.1410-Y-57 only addre 'is use of 3/8 in.and 1/2 in, self-tapping anchor bolts.
For applications requiring larger bolt diameters, the expansion type anchor bolt is specified.
Discussions with cognizant licensee personnel iridiciate that a test program is being conducted as a result of NRC Bulletin 79-14 and 79-02 (pipe supports) to establish minimum bolt diameter spacing and anchor pull out d,ata.
This program has resulted in replacJment of all Red Head type bolts used in pipe supports.
This item is unresolved pending NRC review of licenses evaluation and corrective action.
(50-289/80-26-02)
8.
Task RM-13A (Emergency Feedwater Auto-Start)
Surveillance Reports El-123 thru El-136, El-141 thrJ
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El-144.
Engineering Change No.'s 5-008, S-012 and S-021.
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Field Questionaire FQ-40.
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Safety Evaluation Report, dated September 29, 1979.
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Wiring diagram SS-208-203 and 205.
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No items of noncompliance were identified.
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1 3.
Unresolved Items l
Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, or items of noncompliance.
Unresolved item (s) identified during this inspection are discussed in Details, Paragraph 2
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4.
Exit Interview The inspector met with licensee and contractor representatives (denoted in Details, Paragraph 1) at the conclusion of the inspection on September 12, 1980.
The inspector summarized the scope and
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findings of this inspection as describad in the report.
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