ML19338D858
| ML19338D858 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/10/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8009240048 | |
| Download: ML19338D858 (1) | |
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UNITED STATES j.
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g-NUCLEAR REGULATORY COMMISSION a
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KING OF PRUSSIA, PENP<SYLVANIA 19406 September 10, 1980 Docket No. 50-244 Rochester Gas and Electric Corporation ATTN:
- i. eon D. White, Jr.
Vice President Electric and Steam Production 89 East Avenue-Rochester, New York 14649 Gentlemen:
The enclosed IE Circular No. 80-21, " Regulation of Refueling Crews," is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this affice.
Sincerely, Boy e H. Grier Director
Enclosures:
1.
IE Circular No. 80-21 2.
List of Recently Issued IE Circulars
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CONTACT:
D. L. Caphton (215-337-5266) cc w/encls:
B. A. Snow, Plant Superintendent T. R. Schuler, QC Engineer Harry H. Voigt, Esquire J. T. St. Martin, Technical Assistant, Operations Engineer 8,009240 g4
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'SSINS No.:
6820 Accession No.:
8006190081 IEC 80-21 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555-September 10, 1980 IE Circular No. 80-21:
REGULATION OF REFUELING CREWS
~ Description of Circumstances:
Recent inspections of refueling activities indicat'e 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.
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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 i
Part 55'of this chapter.
3.
10 CFR 55.3-No oerson may perform the function of an operator as-defined in this pf : except as authorized by a license issued by the Commission; i
4.
10 CFR 55.4:
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" Operator" is eny individual who manipulates a control of a facility.
An individual 1s 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:
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'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
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IEC 80-21 September 10, 1980
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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 f rility 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 Licenst.1 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
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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 i
facility administered training programs and be facility certified to perform their duties.
4.
Direct communication will be maintained with a licensed individual
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.in the control room when fuel movements over the core are being made.
5.
The foreman wil1~ exercise indirect supervision over all other fuel i
. handling operations.
L 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 SR0 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 y'
handling equipment.
In addition, personnel participating directly in the core alternations must meet the qualification and training requirements committed-tofin'the F5AR or fuel loading application, i.e.,-ANSI N18.1-1971 or ANSI /ANS 3.1-1978.
1; IEC 80 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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SCptembCr 10, 1980-RECENTLY ISSUED-IE CIRCULARS Circular Date of No.
Subject Issue Issued to 80-20 Changes'in Safe-Slab 8/21/80 All holders of-Tank Dimensions a Part 50 or Part 70 Fuel Farility License 80-19 Noncompliance with 8/26/80 All holders of Licensee Requirements a medical license 80-18 10.CFR 50.59 Safety 8/22/80 All P ilders of a Evaluations for Changes to power reactor Radioactive Waste Treatment OL or CP Systems 80-17 Fuel Pin Damage Due to Water 7/23/80 All holders of a PWR Jet from Baffle Plate Corner power reactor OL or CP 80-16 Operational Deficiencies In 6/27/80 All holders of a Rosemount Model 51000 Trip power reactor Units And Model 1152 Pressure OL or CP Transmitters 80-15 Loss of Reactor Coolant Pump 6/20/80 All holders of a Cooling and Natural Circula-power reactor tion Cooldown OL or CP 80-14 Radioactive (,ontamination of 6/24/80 All holders of a Plant Demineralized Water power or research System and Resultant Internal reactor OL or CP, Contamination of Personnel and fuel cycle licensees 80-13 Grid Strap Damage in 5/18/80 All holders of a power Westinghouse Fuel Assemblies reactor OL or CP 1
80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of a May Fall Out of-Place When power reactor Mounted Below Horizontal Axis OL or CP 80-11 Emergency Diesel Generator 5/13/80 All holders of a Lube Oil Cooler Failures power reactor OL or CP 1
80-10 Failure to Maintain 4/29/80 All holders of a l
Environmental Qualification power reactor l
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