ML19317G162
| ML19317G162 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/27/1972 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G152 | List: |
| References | |
| 50-302-71-05, 50-302-71-5, NUDOCS 8002280752 | |
| Download: ML19317G162 (2) | |
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(J ENCLOSURE DOCKET NO. 50-302 9
Certain activities under your license appear to be in noncompliance with AEC regulations and with the Final Safety Analysis Report (FSAR) as identified below:
1.
Criterion VIII, Appendix B, 10 CFR 50, states in part, " Measures shall be established for the identification and control of materials, parts, and components, including partially fabricated assemblies. These measures shall assure that identification of the item is maintained by heat number, part number, serial number, or other appropriate means either on the item or on records traceable to the item.
Criterion VII, Appendix B, 10 CFR 50, states in part, " Measures shall be established to assure that purchased material, equipment, and services.
. conform to the procurement documents. These measures shall include... objective evidence of quality furnished by the contractor or subcontractor, inspection at the contractor or subcon-tractor source, and examination of products upon delivery. Documentary evidence that material and equipment conform to the procurement require-ments shall be available at the nuclear pover-plant site prior to in-c Q
stallation or use of such material or equipment.
Para 6raph 1.'i.6.h.5 of the FSAR states, "During manufacture the vendor maintains all required quality documents including material identifica-tion,... At the completion of the manufacturing the documents are distributed and stored as specified by the Owner.
Cor.trary to the above requirements, apparent deficiencies were identi-fled in the material and fabrication certifications for the decay heat pumps and the reactor building spray pumps.
In particular:
From the information contained in the file, the inspector determined a.
the decay heat pumps had serial numbers 1624920 and 162h923 and the reactor building spray pumps had serial numbers 162h922 and 162h923; however, it was not possible for the inspector or Florida Power Corporation site representatives to relate a specific pump to a specific serial number.
b.
The certifications labeled DH-P1A (decay heat pump 1A) contained the following pages which, although labeled DH-P1A, were traceable to other pumps:
(1) One pump curve identified by serial number 162h921, which is S
the serial number for DH-P1B (decay heat pump 1B).
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N.s (2) j A hydrostatic test certification and a materials certification identified by serial numbers 1624922 and 1624923, which are the serial numbers of the reactor building spray pumps.
i (3) Two pages of chemical analysis and physical test reports marked
" Reactor Building Spray Pumps."
c.
The certifications labeled DH-P1B contained the following pages which, although labeled DH-P1B, were traceable to other pumps:
(1) Two pump curves identified by serial number 1624920, which is the serial number for DH-P1A.
(2) A hydrostatic test certification and a materials certification identified by serial numbers 1624922 and 1624923, which are the serial numbers of the reactor building spray pumps.
(3) Two pages of chemical analysis and physical test reports marked
" Reactor Building Spray Pumps."
I d.
The quality assurance data package for each reactor building spray 9
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pump contained three pump curves. Two pump curves were identified by serial number 1624923 and one pump curve was identified by serial number 1624922. In the material and fabrication certifications for RB-P1A, all three pump curves were labeled RB-PlA.
In the material and fabrication certifications for RB-P1B, all three pump curves were labeled RB-P1B.
2.
Criterion XVI, Appendix B, 10 CFR 50, states in part, " Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected."
1 Contrary to this requirement, the inspector was unable to find evidence of measures to ascure the investigation, documentation, and correction of the aggregate separation and void observed in the exterior surface of the containment building concrete, pour 263 RB between but tresses 6 and 1 at elevation 103 to 110, or similar concrete deficiencies.
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