IR 05000623/2008009
| ML20133E251 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, 05000623 |
| Issue date: | 09/26/1985 |
| From: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| Shared Package | |
| ML20133E255 | List: |
| References | |
| EA-85-103, NUDOCS 8510090324 | |
| Download: ML20133E251 (3) | |
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NUCLEAR REGULATORY COMMISSION g
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REGION V
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WALNUT CREE K. CALIFoRNI A 94596 SEP 2 61985 Docket No. 50-312 y ;; C y.t 6 "
g EA 85-103
Sacramento Municipal Utility District
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P. O. Box 15830 Sacramento, California 95813 Attention:
R. J. Rodriguez Executive Director for Nuclear Operations Gentlemen:
This refers to the special inspection conducted by Messrs. J. L. Crews, J. H. Eckhardt, and other members of the NRC staff during the period June 23, 1985 through August 9, 1985, of activities authorized by NRC License No. OPR-54 The findings of the inspection were transmitted to you by letter dated August 26, 1985, along with Inspection Report No. 50-312/85-19.
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Enforcement Conference was held at the Region V office on September 6, 1985, with you and other members of your staff.
Based on the results of this inspection and as discussed during the enforcement conference, it appears that certain of your licensed activities were not conducted in full compliance with NRC requirements.
Violation A in the enclosed Notice involves your failure to establish design and installation control measures to ensure the integrity of the Quality Class I, Seismic Class I portion of the nitrogen supply and vent header system.
The violation was identified as a result of the June 23, 1985 discovery of a crack in the reactor coolant system's high point vent line which led to a 17 gpm non-isolable primary coolant leak.
That discovery prompted a walkdown and inspection in July 1985 of 349 safety-related pipe supports.
Violation B.1 in the enclosed Notice describes the two seismic supports which were not installed in accordance with design drawings issued in 1983 during modifications of the reactor coolant system's 3/4 inch high point vent lines on the "A" and "B" loops.
As a result, the code allowable limits for a seismic design basis event were exceeded.
Violation B.2 involves 223 other safety-related supports which were not installed in accordance with design drawings.
The violations described in the attached Notice reflect serious deficiencies in the control of engineering design, installation, and quality control inspections.
Many of these program deficiencies resulted in failures to identify hardware deficiencies some of which appear to have existed since 1974.
They were not detected by your QA/QC audits and surveillance activities which, if properly planned and implemented, should have detected them.
CERTIFIED MAIL RETURN RECEIPT REQUESTED i
8510090324 850926 i
PDR ADOCK 05000312
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Sacramento Manicipal Utility-2-SEP 2 61985
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District It should be noted that findings of a similar nature in recent NRC inspections i
underscore our concerns regarding the control of engineering design (e.g.,
ineffective control of the design and installation of auxiliary feedwater flow transmitters discussed in Inspection Report No. 50-312/84-15), and modification
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.and inspection activities (e.g., inadequate modification and ineffective QC
. inspections associated with the Nuclear Service Electric Building discussed
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in Inspection Report No. 50-312/85-01), which we have previously brought to your attention in our correspondence and meetings with you over the past several months.
We recognize that substantial steps to improve your QA/QC program have been taken by you, commencing in 1984 with the commissioning of a comprehensive consultant study of all aspects of your nuclear operations.
The recommendations of this study have been ranked by priority, responsibility assigned for each, and implementation has proceeded on a priority basis.
Short and long-term actions by you relating to the high point vent piping crack are described in your letter to this office dated August 6, 1985.
The actions that you have i
initiated since the beginning of this year in response to your consultant's study, together with those actions described in your letter of August 6, 1985
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should, if fully implemented, substantially address the root causes of problems identified in your past performance relating to design control, i
installation, and quality control / assurance activities.
To emphasize the need to improve your engineering design, installation, and quality control inspections, I have been authorized, after consultation with the Director, Office of Inspection and Enforcement, to issue the enclosed i
Notice of Violation and Proposed Imposition of Civil Penalty in the amount of Fifty Thousand Dollars ($50,000) for the violations described in the enclosed
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Notice.
The violations have been categorized in the aggregate as a Severity i
Level III problem in accordance with the " General Statement of Policy and
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Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985).
In assessing the civil penalty we have taken into account the corrective actions and no adjustment to the civil penalty has been deemed appropriate.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response.
In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence.
After reviewing your response to this Notice, including your propcsed corrective actions, the NRC will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosure
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will be placed in the NRC Public Document Room.
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Sacramento Municipal Utility-3-SEP 2 61985
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District
i The responses directed by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of Management and Budget as required
by the Paperwork Reduction Act of 1980, PL 96-511.
Sin ly,
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//Ysf John B. Martin Regional Administrator i
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