IR 05000302/1979032
| ML19254D403 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/31/1979 |
| From: | Herdt A, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19254D402 | List: |
| References | |
| 50-302-79-32, NUDOCS 7910250450 | |
| Download: ML19254D403 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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o ATLANTA, GEORGIA 30303 Report No. 50-302/79-32 Licensee: Florida Power Company 3201 34th Street, South St. Petersburg, Florida 33733 Facility Name: Crystal River Docket No. 50-302 License No. DPR-72 Inspection at Crystal River Site near Crystal River, Florida
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Inspector:
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L. ModEEo Date Signed
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Approved by:
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A. Herdt, Section Chief, RCES Branch Ddte Signed SUMMARY Inspection on August 20-22, 1979 Areas Inspected This special, unannounced inspection involved 17 inspector-hours onsite in the areas of seismic analysis for as-built safety related piping systems.
Results No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. R. Westafer, Maintenance Superintendent
- J. E. Colby, Production Engineerir.g Mcchanical Engineer
- G. M. Williams, Nuclear Compliance Plant Engineer
- J. Hill, Nuclear Compliance Auditor Other licensee employees contacted included designers and Gilbert Associ-ates, Inc. engineers.
Other Organizations
- J. F. Ward, Construction Engineer, Gilbert Associates, Inc.
- S. E. Fox, Piping Engineer, Gilbert Associates, Inc.
- Attended exit interview.
2.
Exit Interview The inspection secpe and findings were summarized on August 22, 1979 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Seismic Analysis for As-Bu;1t Safety-Related Piping Systems In response to IE Bulletin 79-14 Florida Power Company (FPC) submitted their 30 day response on August 2, 1979. Their program was to inspect all systems outside containment for the 60 day response. On August 17, 1979 the unit was down due to a turbine trip and was to remain down until repairs on a reactor coolant pump seal are completed. With the unit down they decided to inspect as much of the itaccessible systems inside contain-ment as possible. The number of isometric (IS0) drawings that represent all of the safety related systems have been estimated at about 1700 outside containment and 900 inside containment. As of August 22, 1979, 168 IS0's inside containment and 121 IS0's outside containment had been inspected but had not been checked by engineering. The list of IS0's was provided by.
Gilbert Associates, Inc. (GAI).
It could not be verified that this list covered all safety related systems that FPC identified in their 30 day response. FPC was asked to make this check.
They agreed they would and could accomplished this by the use of thpfr flow diagrams.
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FPC requested exemption from inspecting the Reactor Coolant (RC) system due to the high radiation levels. The RC systems does not utilize hangers for supports but geometry configuration has to be verified. FPC considers they have enough QC documentation by B&W for shop and erection documentation, and they will verify that the actual "as-built" dimensions were utilized for the stress analysis. A subsequent supplemental response to IE Bulletin 79-14, issued on August 23, 1979, identified this problem which IE and NRR will evaluate.
The following inspected IS0's had been reviewed for compliance with the requirements of the bulletin. The inspector verified that the supports listed below had been checked for location and as-built details:
PI 305-838 RWH-10 Rev. C 5/31/74 RWH-11 RWH-36 RWH-73 PI 305-938 SWH-161 REV. D 9/7/76 SWH-186 SWH-497 PR 305-753 MSH-227 Rev. A 12/17/74 MSH-122 Stress Report: CR-6 MSH-123 Stress report (CR-6) dated 4/23/74 was inspected for verification of support locations, loadings and prcper orientation.
ISO PI 305-909, Rev. C. dated 3/18/75, was reviewed by the inspector and found that all supports had not been checked off and that the details for anchor MSA-5 was not verified.
Items like this should suosequently be picked up by engineering when c7aluating the marked ISO. These discrep-ancies were pointed out to FPC and they instructed their personnel to verify all supports and make notations on the IS0's in order to point out to the engineers any areas requiring clarification.
The inspector observed the inspection of ISO PI 305-947, Rev. B. dated 6/17/74. Supports SWH-133, SWH-134, SWH-135, SWH-168, and SWH-170 were verified as being properly installed in accordance with detailed drawings.
The persounel performing the inspection were GAI employees who have pipe design experience and were familiar with the supports and piping systems.
The NRC inspector interviewed designers J. Lenortauager, W. Block, and quality specialist D. Hornberger, who were performing this inspection.
Compliance Procedure CP-114, " Procedure for Control of Permanent Modifica-tion, Temporary Modifications, and D <iations", Rev. 21 was to be reviewed by FPC to assure that is procedure or other engineering procedures would cover proper input of future modifications into design documents and the seismic analysis.
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-3-The 30 day response of the bulletin required the licensee to submit a list of design documents, including title identifi. cation number, revision and date. This was not included in their resporse and it was pointed out to them that it was required and should b= mad. available as soon as possible.
This IE Bulletin 79-14 remains open until s.1 inspections and evaluations are completed and evaluated by NRC.
No items of noncompliance or deviations were identified.
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