IR 05000395/1979018
| ML19249A651 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/18/1979 |
| From: | Conlon T, Hardwick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249A640 | List: |
| References | |
| 50-395-79-18, NUDOCS 7908240096 | |
| Download: ML19249A651 (4) | |
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UNITED STATES E ', 3.,, gf( 7, NUCLEAR REGULATORY COMMISSION
Ac E REGION 11
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101 M ARIETT A sT., N W., sulT E 3100 g'
ATL ANT A, GEORGI A 30303
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Report No. 50-395/79-18 Licensee:
South Carolina Electric and Gas Company Columbia, South Carolina 29218 Facility Name:
V. C. Summer Nuclear Station, Unit 1 Docket No. 50-395 License No. CPPR-9e Inspection at Summer Site near Columbia, South Carolina Inspector
7 6 M 79 R.
.Hardwick, Jr.
a te 'Sigried 6/M 77 Approved b p n
T. E. Conlon, Section Chief, RCES Branch D~ ate Signed SLWiARY Inspection on May 22-25, 1979 Areas Inspected This routine, unannounced inspection involved 24 inspector-hours onsite in the areas of licensee identified items, inspector follow-up items, safety-related instrumentation installation QC records, and safety-related electrical cable installation and QC records.
Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified in three arcos; one apparent item of noncompliance was found in one area. (Deficiency 395/79-18-02; Failure to follow procedures for cable tray support installation.
See paragraph 8).
S'S530.IIS 7 90824009b
DETAILS 1.
Persons Contacted Licensee Employees
- J. Algar, Nuclear Site Manager
- D. Nauman, Hansger QA and Security
- A. Smith, Site QA Coordinator
- D. Moore, Director Surveillance Systems
- E. Evans, QA Enrineer F. Cain, QC Engineer D. Dawkins, QC Specialist Other Organizations Gilbert Associates Incorporated (GAI)
A. Hartman, Resident Electrical Engineer R. Molchan, Resident Instrumentation and Control Engineer
- Attended cxit interview 2.
Exit Interview The inspection scope and findings were summarized on May 25, 1979, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are
discussed in Paragraph 6.
5.
Licensee Identified Item (10 CFR 53.55(c))
(Open) Licensee Identified Item 395/79-18-01:
Insuf ficier.t electrical cable connector insulation for 7.2 KV motor connections. The Electrical Construction Guidelines for Cable Installation, drawing number S-200-912, sheet A10, is being revised to specify a correct method for ir. stalling insulating tape on 7.2KV motor electrical connections. The licensee is formulating a plan of corrective action for those 7.2 KV motor electrical connections which had been previously completed. This item will remain open pending NRC review on subsequent inspections.
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-2-6.
Inspector Follow-up Items (Open) Inspector Follow-up Item 395/79-09-01: Documentation of Separa-tion Conflicts. Field Quality Control Procedure (FQCP) 7.1.6, " Installation of Exposed Conduit and Conduit Supports" is being revised to provide QC inspection requirements to ensure that separation criteria is met.
Revised Cable Installation Instruction Guidelines, drawing S-200-926, Rev.
2, were issued on May 3, 1979 providing additional instructions for separation distance criteria.
This revision allows cable trays for redundant equipment in " Cable Spreading Areas" to be separated by a minimum horizontal distance of I foot and a minimum vertical distance of 3 feet without fire resistant barriers. The Final Safety Analysis Report
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(FSAR) requirement for separation between cable trays of redundant equipment without fire resistant barriers is a minimum horizontal distance of 3 feet and a minimum vertical distance of 5 feet.
The licensee stated that an amendment to the FSAR was being evaluated.
This item is identified as Unresolved item 395/79-18-03, Cable installation instruction guidelines for cable tray installation in cable spreading areas. NRC will review this item on subsequent inspections.
7.
Independent Inspection The inspector conducted a walk-through inspection in the reactor building, auxiliary building, intcrmediate building, control building, and diesel generator building.
Safety-related equipment storage and construction activities were observed.
The inspector examined power cable installation in safety-related inverter cabinet numbers 5901, 5902, and 5903. Deficiency Notice (DN) 2556E has been issued for inverter cabinet number 5902 identifying a deviation from the separation criteria for redundant cables within control cabinets. A discussion of this problem with the Architect / Engineer (A/E) indicated that several different methods of providing a fire resistant barrier are being evaluated. This item is identified ar Inspector Follow-up Item 395/79-18-04, Safety-related cable separation in inverter cabinets.
8.
Electrical (Cables and Terminations II) - Review of Quality Records The inspector selected safety-related cable numbers ESL-397B, EFM-24B, ESL-402B, and ESL-401A for QC records review.
Cable termination QC records were reviewed to ensure nondestructive examinations were performed and results were satisfactocy.
Cable tray support and anchor bolt QC records were reviewed.
It was determined that for Cable ESL-397B all required sections of the expansion bolt installation checklist, Form 7.1.5-1, had not been completed for the following safety-related cable tray supports:
Support number 304 for c2bie tray number 2058 a.
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Support number 42-15 for cable tray number 2032 The expansion bolt checklist had been signed by the QC inspector and had been reviewed and approved by the QC supervisor.
This is a noncompliance and is identified as Deficiency 395/79-18-02, Failure to follow procedures for cable tray support installation.
Deficiency ar tices (DN) 1640E, 2004E, 2008E, 2030E, and 2058E were selected to astur3 that the current status is identified, that they are legible, complet<., retrievable, and that the corrective action had been identified and appr.oved.
9.
Instrumentation (Components and Systems I) - Observation of Work and Work Activities.
The inspector selected safety-injection flow transmitter IFT 0934 for examination. The vendor calibration data, quality control release, material receiving report, and receiving inspection report were examined.
Within the areas examined, there were no items of noncompliance or devia-tion identified.
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