ML17258A964

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Comments on Proposed Changes to Inservice Insp Program Re Steam Generator Tubes for 1980-89 Interval,Requested 801106. Approves Plan Contingent Upon Satisfactory Response to Listed Comments at 810421 Meeting
ML17258A964
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/08/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Maier J
ROCHESTER GAS & ELECTRIC CORP.
References
LSO5-81-04-009, LSO5-81-4-9, NUDOCS 8104200047
Download: ML17258A964 (7)


Text

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Paragraph 5.7.1.1 should be revised to criteria (a) and (b) must be met prior plant operation.

Criterion (b) should to read l... <10K.", and, state that both to resumption of u~

also be corrected (4)

Line 3 of Paragraph 3.5 should be changed to coi rectly state Reference 5 instead of Reference 1.

We will be ready to discuss these changes with you at our meeting scheduled for Tuesday, April 21, 1981.

As noted above, we have only reviewed the Steam Generator Tube Inservice Inspection Program.

We have no problem with your proceeding with this portion of the overall Inservice Inspection Program, contingent on your satisfactory response to our comments above.

The remainder of your Program for the Ginna Station will be reviewed on a schedule being established by the staff.

Sincerely, cc:

See next page Original signed by Dennis M. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing D~IS RIBUTION V~

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p Docket No. 5h-244 LS05-81-04-009 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 8, 1981 I

John E.

Maier Vice President Electric 8 Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

)

Dear Mr. Maier:

By letter dated November 6, 1980, you requested changes to the R.

E. Ginna Nuclear Power Plant Inservice Inspection Program for the 1980-1989 interval.

The program had been previously submitted by Rochester Gas and Electric Corporation letter dated July 2, 1979.

The requested changes dealt only with the potential sleeving of up to ten steam generator tubes.

The sleeving, already accomplished on five tubes at Ginna, is an alternative repair effort to plugging defective tubes.

We have reviewed only that portion of the inservice inspection program con-cerning the steam generator tubes because we are aware that you are consider-ing additional sleeving of tubes during the refueling outage presently scheduled to commence April 18, 1981.

We have the following comments:

(1)

Paragraphs 5.7.1.1 and 6.5 of the Inservice Inspection program address a sleeving limit of ten tubes.

You have already informed us that you are considering sleeving more than five additional tubes during the forthcoming out-age in order to prove that revised production techniques are satisfactory.

Therefore, we suggest that you modify the language of the Program to increase the maximum number of sleeved tubes and to include the statement that NRR approval is necessary prior to accomplishment of any additional sleeving.

We presently anticipate no problem in approval of limited additional sleeving (up

'o about 25 tubes) and of course will be interested in

feedback, from future inspections, regarding the efficacy of the sleeving repair technique.,

(2)

A plugging limit for the "sleeved" tubes should be established and included in the Ptogram, along with the means to determine degradation of these

tubes,

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(3)

Paragraph 5.7.1.1 should be revised to state that both criteria (a) and (b) must be met prior to resumption of plant operation.

Criterion (b) should also be corrected to read:"... ~10%.,", and, (4)

Line 3 of Paragraph 3.5 should be changed to correctly state Reference 5 instead of Reference l.

We will be ready to discuss these changes with you at our meeting scheduled for Tuesday, April 21, 3981.

As noted above, we have only reviewed the Steam Generator Tube Inhervice Inspection Program.

We have no problem with your proceeding with this portion of the overall Inservice Inspection

Program, contingent on'our satisfactory response to our comments above.

The remainder of your Pro'gram for the Ginna Station will be reviewed on a schedule being established by the staff.

Sincerely, cc:

See next page Denn)s H. Crutchfse d, Ch f Operating Reactors Branc 85 Division of Licensing

Mr. John E. Maier 3-April 8, 1981 CC Harry H. Voigt, Esquire.

LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue,'.

W.

Suite 1100 Washington, D. C.

20036 Mr. Michael Slade 12 Tra i 1wood Circl e Rochester, New York 1461 8 Rochester Coranittee for Sci ent ific Informat i on Robert E. Lee, Ph.D.

P. 0.

Box 5236 River Canpus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1,

Second Floor Empire State P 1 az a

Albany, New York 12223 Director, Techni ca 1 Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West
Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.

NRC 1503 Lake Road

Ontario, New York 14519 Ezra I. Bialik Ass is tant Attorney G enera 1

En vi ronmenta1 P rotect ion B ureau New York State Department of Law 2 World Trade Center New York, New York 10047 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)

U. S. Environmental Protection Agency Washington, D. C.

20460 U. S. Environmental Protection Agency Region II Office ATTN:

EIS COORDINATOR 26 Federal Plaza New

York, New York 10007 Herbert Grossman, Esq.,

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

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

20555 Dr.

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

20555 Mr. Thomas B. Cochran Natur'al Resources Defense Council, !nc.

1725 I Street, N.

W.

Suite 600 Washington, D. C.

20006

APR 15 1981