ML19336A536
| ML19336A536 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8010300025 | |
| Download: ML19336A536 (1) | |
Text
TO DAC:ADM:
CENTRAL FILES a
UNITED STATES
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PDR:HQ NUCLEAR REGULATORY COMMISSION LPDR f.e r %
REGloN IV
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611 RY AN Pt.AZA oRIVE. SulTE 1000 MC 7
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September 10, 1980 STATE Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
The enclosed IE Circular No. 80-21 is forwarded to you for information.,No written response is required.
Should you have any questions related to your understanding of the recommendations on this matter, please contact this office.
i Sincerely,-
/
k.-k.I
J Karl V. Seyfrir/e Director
'/
J Inclosures:
1.
IE Circular No. 30-21 2.
List of Recently issued IE Circulars cc:
James ?. O'Hanlon Plant Manager Arkansas Nuclea One
?. 0. 3ox 608 Russellville, Arkansas 72801
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03 ou e9 zu SSINS No.:
6820 Accession No.:
8006190081 IEC 80-21 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.
20555 IE Circular No. 80-21 Date:
September 10, 1980 Page 1 of 3 REGULATION OF REFUELING CREWS Description of Circumstances:
Recent inspections of refueling activities indicate that some licensees have misinterpreted the regulatory requirements applicable to fuel handling activi-ties.
Therefore, it appears appropriate to identify those specific regulatory requirements that are applicable to core alterations which include reactivity manipulations that may result from the handling of fuel elements, control rods, etc.
A.
10 CFR Requirements 1.
10 CFR 50.2(f) and 10 CFR 55.4:
" Controls" when used with respect to a nuclear reactor means apparatus and mechanisms, the manipulation of which directly affect the reactivity or power level of the reactor.
2.
Except as provided in 55.9 of this chapter, the licensee shall not permit the manipulation of the controls of any facility by anyone who is not a licensed operator or senior operator as provided in Part 55 of this chapter.
3.
10 CFR 55.3:
No person may perform the function of an operator as defined in this part except as authorized by a license issued by the Commission; 4.
10 CFR 55.4:
"Op -
" is any individual who manipulates a control of a facility.
An i il is deemed to manipulate a control if he directs another*
to
-.voiate a control.
" Senior Operator" is any individual designated by a facility licensee under Part 50 of this chapter to direct the licensed activities of licensed operators.
IE Circular No. 80-21 Date:
September 10, 1980 Page 2 of 3 5.
10 CFR 55.9:
Nothing in this part shall be deemed to require a license for:
a.
An individual who manipulates the controls of a research or training reactor as part of his training as a student in a nuclear engineering course under the direction and in the presence of a licensed operator or senior operator; b.
An individual who manipulates the controls of a facility as a part of his training to qualify for an operator license under this part under the direction and in the presence,f a licensed operator or senior operator.
B.
Technical Specifications Standard Technical Specifications require that all core alterations be directly supervised by either a Licensed Senior Reactor Operator or a Senior Reactor Operator limited to fuel handling, who has no other con-current responsibilities during this operation.
The NRC interprets the term "directly supervised" to mean that the SRO is supervising the core alterations from the refueling deck.
We note that the Licensed Senior Reactor Operator limited to fuel handling classification was developed for specialized fuel handling crews.
In this case an individual identified as a Refueling Foreman is responsible for refueling activities subject to the following provisions:
1.
The foreman shall have a Senior Operator's License limited to the fuel handling duties.
2.
The foreman shall directly supervise (from the refueling deck) the movement of fuel in and out of the reactor.
3.
The unlicensed members of the crew shall participate in appropriate facility administered training programs and be facility certified to perform their duties.
4 Direct communication will be maintained with a licensed individual in the control room when fuel movements over the core are being made.
5.
The foreman will exercise indirect superv.sion over all other fuel handling operations.
l l
I
IE Circular No. 80-21 Date:
September 10, 1980 Page 3 of 3 Based on the NRC regulations delineated in Item A above, the individual manipulating the fuel-handling equipment over the reactor must be an NRC Licensed Reactor Operator (RO) unless the facility Technical Specifications include provisions for the operation to be supervised by an SRO or SRO limited to fuel-handling as described in Item B.
During any core alteration, a licensed individual must also be observing reactivity monitors in the Control Room with appropriate communications established with personnel on the fuel handling equipment.
In addition, personnel participating directly in the core alternations must meet the qualification and training requirements committed to in the FSAR or fuel loading application, i.e., ANSI N18.1-1971 or ANSI /ANS 3.1-1978.
Recommended Action for Licensee Consideration Our routine inspection program for refueling activities is based on the above NRC requirements.
Therefore, we recommend that all reactor licensees review procedures and practices to assure that the individuals responsible for and participating in refueling activities are in conformance with the above requirements.
No written response to this Circular is required.
If you require additional information with regard to this subject, please contact this office.
t
i IE Circular No. 80-21 September 10, 1980 l
RECENTLY ISSUED 1
IE CIRCULARS 1
1 Circular Subject Date Issued To No.
Issued 1,
80-13 Grid Strap Damage in 5/18/80 All holders of Reactor Westinghouse Fuel Operating Licenses (OLs) y Assemblies and Construction Permits (cps) 80-14 Radioactive Contamination 6/24/80 All holders of Power and of Plant Demineralized Research Reactor Licensees Water System and Resultant (Operating and Construction Internal Contamination of Permits), and Fuel Cycle Personnel licensees 80-15 Loss of Reactor Coolant 6/20/80 All power reactor facilities Pump Cooling and Natural with an Operating License (OL)
Circulation Cooldown or Construction Permit (CP) 80-16 Operational Deficiencies 6/27/80 All power reactor facilities in Rosemount Model 510DU with an Operating License (0L)
Trip Units and Model 1152 or a Construction Permit (CP)
Pressure Transmitters 80-17 Fuel Pin Damage Due to 7/23/80 All holders of PWR Operating Water Jet from Baffle Licenses (OLs) and PWR Plate Corner Construction Permits (cps) 80-18 10 CFR 50.59 Safety 8/22/80 All power reactor facilities Evaluations for Changes to with an Operating License (OL)
Radioactive Waste or Construction Permit (CP)
Treatment Systems 80-19 Noncompliance with 8/26/80 All medical licensees License Requirements for Medical Licensees 80-20 Changes in Safe-Slab S/21/80 All Part 50 and Part 70 Dimensions fuel facility licensees Enclosure y
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