ML19341C727
| ML19341C727 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/07/1981 |
| From: | Faulkenberry B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19341C720 | List: |
| References | |
| 50-312-80-35, NUDOCS 8103040027 | |
| Download: ML19341C727 (2) | |
Text
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O-APPENDIX A NOTICE OF VIOLATIONS Sacramento Municipal Utility District Docket No. 50-312 As a result of the inspection conducted on December 8 - 12, 1980, and in accordance with the Interin Enforcement Policy, 45 FR 66754 (October 7,1980),
the following violations were identified:
A.
Section XVIII of Appendix B to 10 CFR 50 states, in part:
"A comprehensive system of planned and periodic audits shall be carried out to verify compliance with all aspects of the quality assurance program and to determine the effectivanoss of the program."
Contrary to the above,the licensee had not, prior to this inspection, conducted comorehensive, planned and periodic audits in the areas of Centrol of Special Processes Inspection and Preventive Maintenance and had not conducted periodic audits in the area of Document Control to assure that current drawings were maintained at reference locations and that obsolete drawings were removed. Although some audits, such as Inservice Inspection, dealt with control of special processes and inspection for that area, these quality factors were not regularly audited in other areas such as general repairs and modifications.
This is a Severity Level IV violation (Supplement I).
B.
Section 6.8.1 of the Rancho Seco Technical Specifications states, in part:
"Uritten procedures shall be established, implemented and mafntained covering the ectivities referenced below:
1 a.
The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, November 1972."
1 Section H.2.a of Appendix "A" of Regulatory Guide 1.33 (Safety Guide 33),
November 1972 reconzends preparation of the following procedures (among others):
(20) Infrequent Inspection of Reactor Coolant System Pressure Boundary (21) Inspection of Pipe Hanger Settings Section 6.8.2 of the Rancho Seco Technical Specifications states, in part:
"Each procedure...of 6.8.1 above, and changes thereto, shall be reviewed by the Fi<C.
Those matters pertaining to items 6.8.la, b and c, above shall be approved by the Plant Superintendent prior to impl ementation...."
810so4om a
. Contrary to the above, the Inservice I spection Program for Rancho Seco (B&W Construction Ccmpany 1980 Inservice Inspection Manual for Rancho Seco Unit No. 1, Rev. No. 1, January 15,1980) which includes procedures for inspection of the reactor coolant pressure boundary and pipe hangers and which had been implemented during the Spring 1980 refueling outage, had not been reviewed by the PRC or approved by the Plant Superintendent.
This is a Severity Level V violation (Supplement I).
i Pursuant to the provisions of 10 CFR 2.201 the Sacramento Municipal Utility District is required to submit to this office within twenty-five days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further items of noncompliance; and (3) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affinnation.
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Dated B. H. Faulke. berry, C#i Reactor Projects Section #2
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