ML20013C076

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Forwards SER Accepting Topical Rept SIR-94-080, Relaxation of Rc Pump Flywheel Insp Requirements, for Referencing in License Amend Applications to Extent Specified & Under Limitations in Rept & SER
ML20013C076
Person / Time
Site: Millstone, Palisades, Saint Lucie, Arkansas Nuclear, Waterford  Entergy icon.png
Issue date: 05/21/1997
From: Sheron B
NRC (Affiliation Not Assigned)
To: Mims D
ENTERGY OPERATIONS, INC.
Shared Package
ML20013C077 List:
References
NUDOCS 9706230099
Download: ML20013C076 (4)


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UNITED STATES

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I May 21, 1997 Mr. Dwight C. Mims, Director Nuclear Safety Division Entergy Operations, Inc.

1448 SR 333 Russellville, Arkansas 72901

SUBJECT:

ACCEPTANCE FOR REFERENCING OF TOPICAL REPORT SIR-94-080,

" RELAXATION OF REACTOR COOLANT PUMP FLYWHEEL INSPECTION REQUIREMENTS"

Dear Mr. Hims:

We have completed our review of the subject topical report submitted in a letter dated April 4, 1995 by Entergy Operat u s, Inc. (Entergy) for Arkansas Nuclear One (ANO) -l & -2 as lead plants. The. re; ort is acceptable for referencing in license amendment applications to the extent specified and under the limitations delineated in the report and the enclosed safety evaluation (SE). The staff concluded that the flywheel inspection period could be lengthened from the current 3 years to 10 years for the plants identified in the SER. Total elimination of flywheel inspections is not justified.

j We do not intend to repeat our review of the matters described in the report when the report appears as a reference in license amendment applications, except to ensure that the material presented is applicable to the specific plant involved as indicated in the conclusion section of the SE. Our acceptance applies only to the matters described in the report.

In accordance with procedures established in NUREG-0390, it is requested that Entergy coordinate with the ABB Combustion Engineering Owners Group and publish this report within three months of receipt of this letter.

The final version shall incorporate this letter, the enclosed evaluation, and Entergy's response dated December 9,1996 to the NRC request for additional information, between the title page and the abstract. The final version shall include an

-A (designating accepted) following the report identification symbol.

Licensees for ANO-2, Palisades, Millstone 2, Waterford 3, and St. Lucie 1 & 2

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need to verify the reference temperature RT for their reactor coolant pump

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m (RCP) flywheels and demonstrate, with plant-specific test results if pessible, 9-

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230024 9706230099 970521 CF SUBJ RD-8-2TOPRP CE CF

Dwight C. Mins e that the corresponding fracture toughness (K ') values are equivalent to those reported in the topical report. AND-1, whicb already has a 10-year inspection interval for its flywheels, will not be affected. The topical report indicated that flywheels for Waterford 3 could lose shrink fit at the accident speed. The staff will pursue this issue with Waterford 3 on a plant-specific basis.

Sincerely,

/s/

Brian W. Sheron, Director Division of Engineering Office of Nuclear Reactor Regulation

Enclosure:

As stated DISTRIBUTION:

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that the corresponding fracture toughness (K ') values are equivalent to those reported in the topical report. ANO-1, whicb alr2ady has a 10-year inspection interval for its flywheels, will not be affected. The topical report indicated that flywheels for Waterford 3 could lose shrink fit at the accident speed.

The staff will pursue this issue with Waterford ? on a plant-specific basis.

c Sincerely,

/S/

Brian W. Sheron, Director Division of Engineering Office of Nuclear Reactor Regulation 4

Enclosure:

As stated i

DISTRIBUTION:

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  • corresponding' fracture toughness (K,) values are equivalent to those reported

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in the topical-report. ANO-1, which already has a 10-year inspection interval r its flywheels,_will not be affected. Licensees for Millstone 2 and Waterford 3 are denied the benefit of the 10-year interval for RCP flywheel ins).ections approved by the staff in this SE.

Sincerely, Brian W. Sheron, Director Division of Engineering Office of Nuclear Reactor Regulation

Enclosure:

As sta d DISTRIBUTION:

File Center EMCB RF DE RF l

FMiraglia GKalman G:\\SHENG\\97\\FLYWHLCE.SER To receive a copy of this docummt, indic 2te in the box C= Copy w/o s}teshment/ enclosure E= Copy with attachment / enclosure N = No co y

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