ML17255A815

Informs That Tests to Incorporate Lead Test Assembly in Reload Cycle 15 Core Design May Be Conducted W/O Prior NRC Approval Per 10CFR50.59.Future Fuel Reload of Fuel Design Should Be Submitted for NRC Review

ML17255A815
Person / Time
Site:	Ginna
Issue date:	05/09/1984
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Kober R ROCHESTER GAS & ELECTRIC CORP.
References
LSO5-84-008, LSO5-84-8, NUDOCS 8405110028
Download: ML17255A815 (5)

Text

Docket No.

50-244 LS05-84-008 Mr. Roger H. Kober, Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

LEAD TEST ASSEMBLY PROGRAM Re:

R.

E. Ginna Nuclear Power Plant May 9, 1984

~0ocket Fi,le NRC PDR Local PDR ORB P5 Reading NSIC DCrutchfield GDick OELD RLobel EJordan JGrace ACRS (10)

SEPB Your letter of April 10, 1984 informed us that as part of an agreement with the Empire State Electric Energy Research Company (ESEERCO),

Rochester Gas and Electric Corporation (RGSE) plans to insert four lead test assemblies (LTAs) in the Ginna Cycle 15 core (Spring 1985).

These assemblies were designed by Exxon Nuclear and incorporate a number of advanced fuel design concepts including:

(1) annular fuel pellets, (2) zirconium barrier cladding, (3) reduced fuel rod diameter (to the moderator to fuel ratios),

and (4) segmented fuel rods

( to allow sub-sequent power ramp experiments in test reactors).

Me are aware of previous experimental or commercial applications of these advanced fuel design concepts at other facilities, although not all in the same application.

The safety analysis of the LTA application was performed by Exxon Nuclear and by the current fuel supplier, l<estinghouse, using information supplied by Exxon.

Under the provisions of 10 CFR 50.59, a licensee may conduct tests or experiments (i.e., incorporate LTAs in a reload core design) without prior NRC notification or approval.

One of the provisions is that the proposed test or experiment does not involve a change in the plant Technical Specifications.

Your letter stated that the plant Technical Specifications will not be affected by the inclusion of the ESEERCO lead assemblies and that, pending final review, no unreviewed safety questions are expected with regard to these assemblies.

Although the loading of these four lead test assemblies satisfies the staff guidelines for acceptability (that is, limited in number, not loaded in a limiting position, expected behavior considered by the licensee under 10 CFR 50.59) we expect RGSE to submit any future fuel reload of this fuel design for a complete staff review.

Sincerely, Original signed by Thomas Wambach for Dennis M. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing c :g e next page O' pg DL:ORB P5 GDick:jc DCrutchfield 4 lT f84 Sl Il84 8405i>OOaB 840509 PDR ADOCK 05000244

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Docket No.

50-244 LS05-84-05-008 O

UNITED STATES NUCI.EAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Hay 9, 1984 Hr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Hr. Kober:

SUBJECT'EAD TEST ASSEHBLY PROGRAM Re:

R.

E.

Ginna Nuclear Power Plant Your letter of April 10, 1984 informed us that as part of an agreement with the Empire State Electric Energy Research Company (ESEERCO),

Rochester Gas and Electric Corporation (RG&E) plans to insert four lead test assemblies (LTAs) in the Ginna Cycle 15 core (Spring 1985).

These assemblies were designed by Exxon Nuclear and incorporate a number of advanced fuel design concepts including:

(1) annular fuel pellets, (2) zirconium barrier cladding, (3) reduced fuel rod diameter (to the moderator to fuel ratios),

and (4) segmented fuel rods

( to allow sub-sequent power ramp experiments in test reactors).

We are aware of previous experimental or commercial applications of these advanced fuel design concepts at other facilities, although not all-in the same application;-

The safety analysis of the LTA application was performed by Exxon Nuclear and by the current fuel supplier, Westinghouse, using information supplied by Exxon.

Under the provisions of 10 CFR 50.59, a licensee may conduct tests or experiments (i.e., incorporate LTAs in a reload core design) without prior NRC notification or approval.

One of the provisions is that the proposed test or experiment does not involve a change in the plant Technical Specifications.

Your letter stated that the plant Technical Specifications will not be affected by the inclusion of the ESEERCO lead assemblies and that, pending final review, no unreviewed safety questions are expected with regard to these assemblies.

Although the loading of these, four lead test assemblies satisfies the staff guidelines for acceptability (that is, limited in number, not loaded in a limiting position, expected behavior considered by the licensee under 0

CFR 50.59) we expect RG&E to submit any future fuel reload of this fuel design for a complete staff,review.

. Sincerely,

~~vf p '7/~M~(r~~~

Dennis H.'rutchfield, Chief r

Operating Reactors Branch f5 Division of Licensing P

cc:

See, next page-

Mr. Roger W; Kober CC Hanry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire

Avenue, N.W.

Suite 1100

,Washington, D.C.

20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E. Ginna Plant c/o U.S.

NRC 1503 Lake Road

Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Dr. Thomas E. Murley Regional Administration Nuclear Regulatory Commission Region I Office 631 Park Avenue King of Prussia, Pennsylvania 19406 Dr.

Emmeth A. Luebke Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.

20555 U.S. Environmental Protection Agency Region II Office ATTN:

Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Supervisor of the Town of Ontario 107 Ridge Road West

Ontario, New York 14519 Jay Dunkleberger New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223

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