ML19296C334
| ML19296C334 | |
| Person / Time | |
|---|---|
| Site: | 05000394 |
| Issue date: | 02/01/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Gordon R CALIFORNIA POLYTECHNIC STATE UNIV., SAN LUIS OBISPO |
| References | |
| NUDOCS 8002250608 | |
| Download: ML19296C334 (1) | |
Text
{{#Wiki_filter:/"ye arc, -{Ik. o 'o UNITED STATES ! "y,.,,, ',j NUCLEAR REGULATORY COMMISSION C REGION V 0, [ 1990 N. CA LIFORNIA BOULEVARO f SulTE 202. WALNUT CREEK PLAZA N'
- .,,a WALNUT CR EEK, CALIFORNIA 94596 February 1,1980 Docket flo. 50-394 California Poly. State University San Luis Obispo, California 93401 Attn: Mr. R. G. Gorcon, Department Head Mechanical Engineering Department Gentlemen:
The enclosed Circular 80-02 is forwarded to you for information. If there are any questions related to your understanding of the suggested actions, please contact this office. Sincerely, f. O R. H. Engel ken Director Enclosures : 1. IE Circular No. 80-02 2. List of IE Ci:culars Recently Issued 8002250
SSINS No.: 6330 Accession fio.: UNITED STATFS 7912190657 NUCLEAR REGULATORY JMf1ISSION OFFICE OF INSDECTICN AND ENFORCE'1ENT WASHINGTON, D.C. 20555 February 1, 1980 j IE Circular No. 80-02 flUCLEAR POWER PLANT ST/FF WORK HOURS Description of Circunstances: Studies indicate that with fatigue, especially b cause of loss of sleep, an individual's detection of visual signals deteriorates markedly, the tine it takes for a person to make a decision increases and more errors are made, and reading rates decrease. Other studies show that fatique results in personnel ignoring some signals because they develop their own subjective standards as to what is important, and as they become more faticued they ignore more signals. Inspections of personnel performance and training since the accident at Three Mile Island, have shown that in certain situations facility cersonnel are either reouired or allowed to remain on duty for extended periods of time. Also, corplaints have been received from some licensed nuclear power plant operators concerning the number of continuous hours they have been on duty. Licensee nanagement is responsible for providing a sufficient number of trained personnel who are in the proper physical condition to operate and maintain the plant. Licensee canagement should review their administrative procedures covering the working hours of nuclear nower plant staff. These procedures should establish a sound policy covering workino hours for plant staff who perform safety related functions (e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, I&C technicians, key maintenance personnel, etc.) Subconmittee ANS-3 is currently developing criteria te address the subject of operator work hours. These guidelines will become a cart of ANSI N18.7. The NRC is also considering issuing requirements for administrative procedures that would control staff overtine. Until either the ANSI Standard is issued and endorsed by NRC (via a Regulatory Guide) or separate requirements are issued by NRC, it is recommended that the following guidance be used. The guidance should be aoplied to all personnel perfonning a safety related function: 1. Scheduled work shoCd be limited to the following maxinum work hours: a. An individual should not be oermitted to work more than 12 hours s traigh t.
IE Circular No. 80-02 February 1, 1980 Pace 2 of 2 b. There should be at least a 12-hour break between all work ceriods. c. In individual should not work more than 72-hours in any 7-day period. d. An individual should not work nore than 14 consecutive days without having 2 consecutive days off. 2. In the event that soecial circumstances arise that require deviation from the above, such deviations should be authorized by the Station Manager with approcriate documentation of the cause. Plants should be staffed and schedules developed to operate such that exceptions are not recuired. 3. If an operator is required to work in excess of 12 continuous hours, his duties should be carefully selected. It is preferable that he not be assioned any task that affe:ts core reactivity or could possibly endanger the safe operation of the plant. No written rescanse to this Circular is required. If you desire additional inforration regarding this matter, contact the Director of the aopropriate NRC Regional Office.
IE Circular Mo. 80-02 Enclosure February 1, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date of Issued to No. Issue 80-01 Service Advice for GE 1/17/80 All licensees of Induction Disc Relays nuclear power reactor operating facilities and holders of nuclear power reactor cps 79-25 Shock Arrestor Strut 12/20/79 All licensees and Assembly Interference holders of power reactor cps 79-24 Proper Installation and 11/26/79 All Holders of a Calibration of Core Spray Power Reacter CL or Pipe Break Detection CP Equipment on BWRs. 79-23 Motor Starters and 11/26/79 All Power Reactor and Contactors Failed Operating Facilities to Operate and Holders of Reactor cps 79-22 Stroke Times for Power 11/16/79 All Power Reactor Operated Relief Valves Operating Facilities and all Utilities having a CP 79-21 Prevention of Unplanned 10/19/79 All holders of Power Releases of Radioactivity Reactor OLs and cps 79-20 Failure of GTE Sylvania 9/24/79 All holders of Power Relay, Type PM, Bulletin Reactor OLs and cps 7305, Catalog SU12-11-AC with a 12V AC Coil 79-19 Loose Locking Devices 9/13/79 All Holders of Power on Ingersoll-Rand Pumps Reactor OLs and cps 79-18 Proper Installation of Target 9/10/79 All Holders of Power Rock Safety-Relief Valves Reactor Ols and cps 79-17 Contact Problem in SB-12 8/14/79 All Power Reactor Switches on General Electric Licensees with a CP Company Metalclad Circuit and/or OL Breakers}}