ML19338D817
| ML19338D817 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/10/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| NUDOCS 8009230779 | |
| Download: ML19338D817 (1) | |
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D UNITED STATES 85 NUCLEAR REGULATORY COMMISSION 3
j REGION I 0,
631 PARK AVENUE
,#,4 KING OF PRUSSIA, PENNSYLVANIA 19406
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September 10, 1980 Docket No. 50-213 Connecticut Yankee Atomic Power Company ATTN: Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 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 office.
Sincerely,
.67 Boy e H. Grier Director
Enclosures:
1.
IE Circular No. 80-21 2.'
List of Recently Issued IE Circulars CONTACT:
D. L. Caphton
~
(215-337-5266) l cc w/encls:
R. Graves, Plant Superintendent D. G. Diedrick, Manager of Quality Assurance
-J. R. Himmelwright, Licensing Safeguards Engineer 8.009230 g
i L,o II SSINS No.:
6820
-Accession No.:
4 8006190081 IEC 80-21 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 f
September 10, 1980 lu 1 IE Circular No.- 80-21: ' REGULATION OF REFUELING CREWS
-Descrig ion of Circumstances:
Recent 6nspections of refueling activities ~ indicate that some licensees he.ve misinterpreted the regulatory requirements applicable to fuel handling activi-ties. Therefore, i.t 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" wP.En used with respect to a nuclear reactor means 4
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:
" 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"Lis-any individual designated by a facility licensee under.Part 50 of this chapter to direct the licensed Lactivities of licensed operators.
5.
10 CFR 55.9:
Nothing inithis part shall be deemed to require a license for:
^
a'. -
An individual who manipulates the controls ofj a research or 1 training reactor as_part of'.his training as a student in.a~
2 w
IEC 80-21 September 10, 1980 Page 2 of 3 nuclear engineering.coursa 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 tr-ining 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 communication will be maintained with a licensed individual in the control room when fuel movements over the core a a 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 t.ie reactor must be an NRC 1
Licensed Reactor Operator (RO) unless the facility Technical Specifications y
inclut.:e 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 wit _h' 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.
~
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L.
IEC 80-21 September 10, 1980 Page 3 of 3 Recommended Action for Licensee Cc.isideration 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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IE Circular 80-21 Enc 1csure 2 September 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 Facility License 80-19 Noncompliance with 8/26/80 All holders of Licensee Requirements a medical license
&~18 10 CFR 50.59 Safety 8/22/80 All holders 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 5100U Trip power reactor Units And Model 1152 Pressure OL or CP Transmitters 80-15 Loss of Reactor Coclant Pucp 6/20/80 All holders of a Cooling and Natural Circula-power reactor tion Cooldown OL or CP 80-14 Radioactive Contamination of 6/24/80 All holders of a Plant Demineralized Water power er 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 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 CL or CP 80-11 Emergency Diesel Generator 5/13/80 All holders of a Lube Oil Cooler Failures power reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of a Environmental-Qualification power reactor of Equipment ~
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