ML17296B029
| ML17296B029 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/10/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8010290404 | |
| Download: ML17296B029 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 September 10, 1980 Docket Nos. 50-528, 50-529, 50-530 Arizona Public Service Company P.
0.
Box 21666
- Phoenix, Arizona 85036 Attention:
Hr.
E.
E.
Van Brunt, Jr.
'Vice President, Nuclear Projects Gentlemen:
The enclosed 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.
Sincerely,
/~i~
<6'.
H. Engelken Director
Enclosures:
l.
IE Circular No. 80-21 2.
Recently issued IE Circulars cc w/enclosures:
F. II. Hartley, APS so ioaool> f q
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT llASHINGTON, D.C.
20555 September 10, 1980 IE Circular No. 80-21:
REGULATION OF REFUEI ING CREHS SS INS No.:
6820 Accession No.:
8006190081 IEC 80-21 Descri tion 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 Re uirements 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; 10 CFR 55.4:
"Operator" is any individual who manipulates a control of a facility.
An individual is deemed to manipulate a control if he directs another to manipulate 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.
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 resea'rch or training reactor as part of his training as a student in a
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IEC 80-21 September 10, 1980 Page 2 of 3 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 of 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 comounication 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 supervision over all other fuel handling operations.
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.
I
e IEC 80-21 September 10, 1980 Page 3 of 3 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.
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RECENTLY ISSUED IE CIRCULARS IEC 80-21 September 10, 1980 Circu ar No.
80-20 80-19 80-18 80-17 80-16 80-15 80-14 80-13 80-12 80-11 80-10 Subject Changes in Safe-Slab Tank Dimensions Noncompliance with License Requirements for Medical Licensees 10 CFR 50.59 Safety Evaluations for Changes to Radioactive Waste Treatment Systems Fuel Pin Damage Due to Water Jet from Baffle Plate Corner Operational Deficiencies In Rosemount Model 510DU Trip Units And Model 1152 Pressure Transmitters Loss of Reactor Coolant Pump Cooling and Natural Circula-tion Cooldown Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel Grid Strap Damage in Westinghouse Fuel Assemblies Va1 ve-Shaf t-To-Actuator Key May Fall Out of Place When Mounted Below Horizontal Axis Emergency Diesel Generator Lube Oil Cooler Failures Failure to Maintain Environmental qualification of Equipment Date of Issue 8/21/80 8/26/80 8/22/80 7/23/80 6/27/80 6/20/80 6/24/80 5/18/80 5/14/80 5/13/80 4/29/80 Issued to All Part
- 50. and Part 70 fuel fac'ility licensees All medical licensees All power reactor facilities with an OL or CP All holders of PWR OLs and PWR CPs All power reactor facilities with an OL or a CP All power reactor facilities with an OL or CP All holders of power and research reactor licenses (operating and construction permits),
and fuel cycle licensees All holders of reactor OLs and CPs All holders of reactor OLs and CPs All holders of a power reactor OL or CP All holders of reactor OLs and Cps
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