ML19338D820

Forwards IE Circular 80-21, Regulation of Refueling Crews. No Written Response Required

ML19338D820
Person / Time
Site:	Oyster Creek
Issue date:	09/10/1980
From:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
References
NUDOCS 8009230782
Download: ML19338D820 (1)

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UNITED STATES g

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' NUCLEAR REGULATORY COMMISSION r.

j REGION I 8,

S31 PARK AVENUE

,d,4 KING OF PRUSSIA, PENNSYLVANIA 19406 September 10, 1980 Docket No. 50-219 Jersey Central Power and Light Company ATTN:

Mr. Ivan R. Finfrock, Jr.

Vice President Madison Avenue at Punch Bowl Road Morristown,- New Jersey 07960 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, Boy e H. Grier Director

Enclosures:

1.

IE Circular No. 80-21 2.

List of Recently Issued IE Circulars CONTACT:

D. L.'Caphton

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(215-337-5266) s.

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J. T. Carroll, Station Manager 18009230jg

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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':

Recentl 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 alteri fons~which include reactivity

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manipulations that may result from the handling of fuel elements, control rods,.etc.

A.

10 CFR Requirements i

1.

10 CFR 50.2(f) and 10 CFR 55.4:

Co'ntrols"' 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 anycne wb 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 cf 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.

M' 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:

La;

An~ individual who' manipulates the controls' of a1research or Straining ~ reactor;as-part of his training;as a. student in a, z

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a..

c-s IEC 80-21--

September 10, 1980 Page'2 of 3 nuclear engineering course under the direction and.in the presence of ailicensed 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 Gherator 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 facili " 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 are being made.

5..

The foreman will-exercise indirect supervision over all other fuel handling' operations.~

Based on the NRC1 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 c

-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

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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.

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1 IECircu1Ar80N Enc 1csuhe *

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15eptember 10, 1980:

RECENTLY. ISSUED-IE CIRCULARS-

~

Circular.

- Date of

-No.

-Subject Issue-

- Issudd to d

80-20~

~ Changes inLSafe-Slab 8/21/80

. All. holders of LTank Dimensions a Part 50 or

~ Part 710 Fuel Facility License l80-19 Noncompliance with'.

8/26/80.

- All holders of Licensee Requirements a medical.11 cense.

80 -10 CFR 50.59 Safety.

8/22/80 All holders of a Evaluations-for Changes toi power: reactor t-Radioactive Waste Treatment

. 0L 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 F

Rosemount Model 51000 Trip.

OL'or CP power reactor Units And Model 1152 Pressure 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 holder's of a Plant Domineralized Water power or research System and Resultant Internal reactor OL or-CP, Contamination of-Personnel and fuel cycle licensees b

80-13 Grid Strap Damage ~in 5/18/80 All holders of a power l

- 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-J Mounted Below Horizontal Axis-OL or CP l

l 80-11

Emergency Diesel Generator 5/13/80-All holders of a L

Lube Oil Cooler Failures power reactor OL L

or CP 80-10l Failure to Maintain 4/29/80 All holders of a Environmental Qualification' power reactor

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.of Equipment _

OL or CP s

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