ML19338D859
| ML19338D859 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/10/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8009240050 | |
| Download: ML19338D859 (1) | |
Text
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(-4 yp jenator,q'o UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION 5,
'- l REGION i 0
631 PARK AVENUE 4, * * * * *,o',c 4
KING OF PRUSSIA, PENNSYLVANIA 19406 September 10, 1980 Docket No. 50-29 Yankee A'tomic Electric Company ATTN:
Mr. James A. Kay Senior Engineer - Licensing 25 Research Drive Westborough,-Massachusetts 01581 1
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, O 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) cc e 'ancls:
H. Autio, Plant Superintendent J. E. Tribble, President I
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8006190081 IEC S0-21
-UNITED STATES
. NUCLEAR REGULATORY COMMISSION
'0FFICE OF' INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555
. September e10,1980 IE Circular No. 80-21:
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.
10 CFR'50.54(i):
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.
i 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
4, 10 CFR 55.4:
l
- Operator"Lis 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 4
activities of licensed operators.
- 5.
10 CFR 55.9:
j.
Nothing in this nart shall be de;.ed-to require a license for:
a.
An individual whoLmanipulates the controls.of a research or
~
training reactor-as part of'his training as a' student.in a
g IEC 80-21 i
September 10, 1980-J Page 2 of 3 nuclear engineering:courseLunder the direction and.in the.
4 presence of a licensed operator or senior operator; b.
AnLindividual who manipulates the controls of a facility as a L
. part of his training to qualify for an operator license under Ethis 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 op2/ation.
The NRC interprets the term "directly supervised" to nean 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 resp..sible 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.
t 4.
Direct communication will be maintained with a licensed individual in the control room when fuel movements over the core are being made.
i-5.
The foreman will exereire 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 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 2
Room with' appropriate' communications established with personneloon 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 Actfon for Licensee Consideration Our routine inspection program for refueli'ig activities is based on the above NRC requirements.
Therefore, we recommens that all reactor licensees review procedures and practices to assure that ',he 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.
~
IE Circular 80-21 Encl sura 2 1
Septemb:r 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 j
80-18 10 CFR 50.59 Safety 8/22/80 All holdi.rs of a Evaluations for Changes to power reactor Radioactive Waste Treatment OL or CP Systems j
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 510DU 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 Contamination of 6/24/80 All holders of a Plint 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 80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of a Hay 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 80-10 Failure to Maintain 4/29/80 All holders of a Environmental Qualification power reactor of Equipment OL or CP
.