ML19350E044
| ML19350E044 | |
| Person / Time | |
|---|---|
| Site: | Cooper, Arkansas Nuclear, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 06/08/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| IEC-81-04, IEC-81-4, NUDOCS 8106160340 | |
| Download: ML19350E044 (1) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION E
REGION IV 611 RYAN PLAZA DRIVE, SUITE 1000 g
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ARLINGTON, TEXAS 70011 dhg June 8, 1981 g$
MEMORANDUM FOR: Those Listed Below s
FROM:
G. L. Madsen, Chief, Reactor Projects Branch, RIV
SUBJECT:
IE CIRCULAR N0. 81-04 Subject IE Circular has been sent to the following listed licensees. A copy of the IE Circular is attached for your information.
Arkansas Power & Light Company ANO-1 & 2 (50-313; 50-368)
Nebraska Public Power District Cooper Nuclear Station (50-298)
Omaha Public Power District Ft. Calhoun (50-285)
Public Service Conpany of Colorado Fort St. Vrain (50-267) f/f$&
G. L. Madsen, Chief Reactor Projects Branch
Attachment:
As stated DISTRIBUTION:
IE/DMS MPA/L0EB IE/RPRIB IE/ REB IE/SRSI IE/EP ADM/DMI.
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8106166840
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SSINS No.:
6830 Accession No:
8011040278 lEC 81-04 i
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0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Circular No. 81-04 Date: April 30, 1981 Page 1 of 2
Purpose:
The purpose of this circular is to focus attention on several problems NRC has identified in licensee implementation of the shift technical advisor (STA) program and the program for reporting operational events.
Problems in both of these areas have been' identified, and to varying degrees, are believed to be fairly wide-spread.
Shift Te'chnical Advisor (STA) Program:
The STA posicion is a TMI-2 Action Plan Requirement clarified in NUREG-0737 and also in the letter from.Mr. H. R. Denton, Director of the Office of Nuclear Reactor Regulation, "To All Operating Nuclear Power Plant Licensees," dated October 30, 1979.
The STA position was established'to provide additional on-shift techqical support and knowledge to the shift supervisors in the areas of operational event evaluation and accident asseasment.
The primary-duties of the STA include providing technical and engineering advice in assuring safe operations of the plant. This is to be accomplished through additional reviews and evaluations of operating avents and accident and incident assessments. As the title implies, the position is one of advisor. The' duties of the STA should include the review and evaluati~on of off-normal events. The STA should also provide advice or recommendations to the shift supervisor on the safety significance and reportability of these events as they occur.
Based n: results of a recent investigation, NRC has concluded that the STA position is not being utilized to the extent envisioned.
It is brportant that the STA be kept well informed of off-normal events and of safety-related activities being performed by others.
By strengthening the STA program, an additional margin of safety can be realized.
Specific areas, identified by cur inspection and investigative activities, where it appears that the STA program can be strengthened, include the following:
1.
STAS are not routinely being called upon for advice when potential safety problems are identified.
The threshold for identifying off-normal condi-tions the STA should evaluate appears to be too high.
It is recommended that licensees review their guidance to STAS and shift supervisors in this area so that use of the STA will be optimized.
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IE Circular No. 81-04 Date: April 30, 1981 Page 2 of 2 2.
Basic organizational structures and procedures do not suitably define, in many cases, the functional duties of the STA during operating or shutdown conditions. The working relationships between the STA, who function's in an advisory capacity, and the shift supervisors must be clear in order to achieve improvements in overall safety.
Protras for Reporting Operational Events t Reports of operational events are essential for NRC to carry out its ongoing review and analysis of operating problems.
Information provided to NRC auut represent a complete picture of the event, the cause, and corrective actions taken. This does not mean that a lengthy description is required.
Descriptions may be -brief but must be sufficient to reflect the situatiou as understood at the time of the report. Supplementary reports adding additional facts or reflecting significant changes in the facts surrounding the event must be made on a priority basis commensurate with the significance of the additional facts or changes to facts previously reported.
An evaluation of each off-normal condition and any change in that condition should be made to determine reportability.
It is recommended that licensees review with their staffs the importance of ensuring that initial and subse-quent Laportant Laformation on off-normal events is reported to NEC as required by conditions of operating licenses and YRC regulations.
Although it is important to keep the NRC resident inspector informed of each event, the official NRC notification must be made in accordance with the requirements as stated in the license and NRC regulations.
It is essential that reporting to NRC and other government office's does not detract from the response to the event. Reporting cannot be allowed to degrade safety.
It is therefore essential that sufficient shift staffing be provided to meet both event response and reporting requirements.
No written response to this circular is required.
If additional information regarding this matter is needed, licensees should contact the director of the apprepriate NRC regional office.
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IE Circular No. 81-04 April 30,1981 l
RECENTLY ISSUED IE CIRCULARS Circular Subject Date Issued To No.
Issued 80-23 Potential Defects in 10/31/80 All power reactor facilities Beloit Power Systems with Operating License (OL)
Emergency Generators or Construction Permit (CP) 80-24 AECL Teletherapy Unit 12/2/80 All teletherapy licensees Mal function 81-01 Design Problems Involving 1/23/81 All power reactor Indicating Pushbutton facilities with an Switches Manufactured by Operating Licenses (OL)
Honeywell Incorporated or Construction Permit (CP) 81-02 Performance of NRC-2/9/81 All power reactor facilities Licensed Individuals (research and test) with an While on Duty Operating License (OL) or Construction Permit (CP) 81-03 Jnoperable Seismic 3/2/81 All power reactor facilities Monitoring Instru-(reasearch and test) with an mentation Operating License (OL) or Construction Permit (CP) 81-05 Self-Aligning Rod End 3/31/81 All power reactor facilities Bushings for Pipe with an Operating Licenses Suoports (OL) or Construction Permit (CP) 81-06 Potential Deficiency 4/14/81 All power reactor facilities Affecting Lertain with an Operating License Foxboro 10 to 50 (OL) or Construction Permit Milliampere Transmitters (CP)
Enclosure
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