ML19338G469
| ML19338G469 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/10/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8010290400 | |
| Download: ML19338G469 (1) | |
Text
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,o UNITED STATES
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,yA g'g NUCLEAR REGULATORY COMMISSION
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o, 1990 N. CALIFORNIA BOULEVARD o
SulTE 202, WALNUT CREEK PLAZA 4u,*
WALNUT CREEK, CALIFORNIA 94596 September 10, 1980 Docket No. 50-344 Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention: Mr. Charles Goodwin, Jr.
Assistant Vice President 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, nOhnd(ri R. H. Engelken Director
Enclosures:
1.
IE Circu:ar flo. 80-21 2.
Recently issued IE Circulars cc w/ enclosures:
C. P. -Yundt, PGE F. C. Gaidos, PGE J. W. Lentsch, PGE I
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SSINS No.: 6820 Accession No.:
4 8006190081 IEC 80-21 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTICN AND ENFORCEMENT T
D' 9 HASHINGTON, D.C. 20555 u bi o a e9 September 10, 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 aoolicable to fuel handling activi-i 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.
l A.
10 CFR Recuirements 1.
10 CFR 50.2(f) and 10 CFR 55.4:
l
" 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:
" 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 research or training reactor as part of his training as a student in a e
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i 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 4
l this part under the direction and in the presence of a licensed operator or senior operator.
B.
Technical Specifications t
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-4 current responsibilities during this operation.
The NRC interprets the term "directly supervised" to mean that the SR0 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:
f 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
-l movement of fuel in and out of the reactor.
3.
The ullicensed members of the crew shall participate in appropriate facility administered training programs and be facility certified to perfcm their duties.
4.
Direct communicition will be maintained with a licensed individual in the control com when fuel movements over the core are being 4
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 equipment over the reactor must be an NRC manipulating the fuel-handling) unless the facility Technical Specifications Licensed Reactor Operator (RO 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 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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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, l
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IEC 80-21 September 10, 1980 3
i RECEtiTLY ISSUED IE CIRCULARS Circular Date of rio.
Subject Issue Issued to 80-20 Changes in Safe-Slab Tank 8/21/80 All Part 50 and t
Dimensions 70 fuel facility 2
licensees l
80-19 Noncompliance with 8/26/80 All medical licensees 4
License Require:nents for Medical Licensees 80-18 10 CFR 50.59 Safety 8/22/80 All power reactor Evaluations for Changes to facilities with an Radioactive Waste Treatment OL or CP Systems
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80-17 Fuel Pin Damage Due to Water 7/23/80 All holders of PWR Jet from Baffle Plate Corner OLs and PWR cps 80-16 Operational Deficiencies In 6/27/80 All power reactor Rosemount Model 510D0 Trip facilities with an Units And Model 1152 Pressure OL or a CP Transmitters 80-15 Loss of Reactor Coolant Pump 6/20/80 All power reactor Cooling and Natural Circula-facilities with an tion-Cooldown OL or CP l
80-14 Radioactive Contamination of 6/24/80 All holders of power t
Plant Demineralized Uater and research reactor System and Resultant Internal licenses (operating Contamination of Personnel and construction
~
permits), and fuel cycle licensees 80-13 Grid Strap Damage in 5/18/80 All holders of reactor Westinghouse Fuel Assemblies OLs and cps 80-12 Valve-Shaf t-To-Actuator Key 5/14/80 All holders of reactor May Fall Out of Place When OLs and cps f' unted Belou Horizontal Axis 80-11 Emergency Diesel Generator 5/13/80 All holders of a power Lube Oil Cooler Failures reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of reactor l
Lavironmentt.1 Qualification OLs and cps
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