ML13308A642

Responds to Encl to President Carter Expressing Concern for Safety of Nuclear Power Plants.Discusses NRC Regulations to Prevent Recurrence of TMI-type Accident. Facility OL Amended to Improve Fire Protection

ML13308A642
Person / Time
Site:	San Onofre
Issue date:	02/15/1980
From:	Harold Denton Office of Nuclear Reactor Regulation
To:	Olsen R AFFILIATION NOT ASSIGNED
References
NUDOCS 8003250387
Download: ML13308A642 (4)

Text

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£ NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 15, 1980 Mr. Robert Olsen 301 Garfield Avenue Placentia, California 92670

Dear Mr. Olsen:

Your letter to President Carter expressing your concern about safety at nu clear power plants in general and the San Onofre plant in particular has been referred to me for response. I regret that this answer has been delayed. The accident at Three Mile Island and its consequences have created a substantial increase in the agency's workload, which has prevented us from responding to you as promptly as we would have liked.

Let me assure you that high priority attention has been given to eliminating the possibility of a Browns Ferry-type fire at San Onofre and at all other operating nuclear power plants in the United States. The San Onofre Unit 1 operating license was amended on July 19, 1979, to require facility modifica tions and implementation of fire protection procedures. These requirements were imposed to assure that the plant can be safely shut down in the event of any postulated fire. A copy of the July 19, 1979, amendment and our safety evaluation of the fire protection modifications is enclosed for your information.

The accident at Three Mile Island Unit 2 showed that more special features and instruments to aid in accident diagnosis and control are needed. Accordingly, the NRC is revising Regulatory Guide 1.97, which deals with this subject, and plans to expedite its implementation at all operating plants and plants under construction. Until the revision is implemented, several interim provisions are recommended at all plants:

(1) improve post-accident sampling capability, (2) increase the range of radiation monitors, and (3) improve in-plant iodine instrumentation.

Several human errors have been identified as contributing to the accident at Three Mile Island. Accordingly, steps have been taken to address short-term and long-term procedural changes necessary to assist operators.

Immediate changes were required of all Babcock and Wilcox facilities prior to restart after the Commission ordered shutdown. Also, the Lessons Learned and the Bulletins and Orders Task Forces have recommended design and operating requirements on all facilities in operation or under construction to be implemented in the near future. Longer term modifications for all facilities are presently under con sideration by the Lessons Learned Task Force.

Mr. Robert Olsen February 15, 1980 The human errors experienced at Three Mile Island stemmed In part from the in correct interpretation of reactor coolant system instrumentation.

Operator training had not previously addressed the system and operator response to the set of conditions experienced during the March 28, 1979, transient. As a result, all licensed operators at Babcock and Wilcox facilities received special train ing and a written examination on the transient. Additionally, these operators attended training sessions on the Babcock and Wilcox simulator to reinforce the operator response required during similar transient situations. All training was completed before operators could resume their duties during power operations.

Long-term commitments on operator training and licensing are being developed by NRC's Operator Licensing Branch.

I am pleased to provide you with this information.

Sincerely, U..gi:J signed by Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosure:

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