0CAN109706, Forwards Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements. Rev Consistent W/ NRC

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Forwards Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements. Rev Consistent W/ NRC
ML20211N486
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 10/14/1997
From: Mims D
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211N489 List:
References
0CAN109706, CAN109706, NUDOCS 9710160168
Download: ML20211N486 (2)


Text

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a], k(JfY)V Entirgy Oper:tions,Inc.

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1448 S R 333 D/

Nr.soMe. AR 72831 16 60185BROD SIR 94-080 A l

October 14,1997 l

OCAN109706 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OPI-17 Washington, DC 20555

Subject:

_ Arkansas Nuclear One Units 1 and 2 i

Docket Nos. 50-313 and 50-368 License Nos. DPR 51 and NPF.6 C E Owners Group Submittal of Topical Report SIR 94 080 A,

" Relaxation of Reactor Coolant Pump Flywheel Inspection Requirements" i

Gentlemen:

1 3-Enclosed are twelve (12) copies of an ABB Combustion Engineering Owners Group (CEOO)

Topical Report, SIR 94 080-A, Revision 1, " Relaxation of Reactor Coolant Pump Flywheel inspection Requirements."

Consistent with the NRC's request in their letter dated

}

May 21,1997, the cover page has been revised to include an -A (designatirg accepted) and '

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the following documents have been added between the original cover page of the report and the Executive Summary (Abstract):

1)

Letter from B. W. Sheron (USNRC) to D. C. Mims (Entergy Operations) dated May 21,1997, Acceptance for Referencing ofTopical Report SIR-94 080, Relaxation of Reactor Coolant Pump Flywheel Inspection Requirements.

2)

Safety Evaluation by Office of Nuclear Reactor Regulation (enclosed with the May 21,1997, letter noted above) Topical Report on Relaxation of Reactor Coolant Pump FlywheelInspection Requirements, Arkansas Nuclear One 1 & 2, Materials and Chemical Engineering Branch, Division of Engineering.-

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3)

Entergy Operations Response dated December 9,1996, AdditionalInformation Regarding Technical Specifications Charge Request to Delete Reactor Coolant Pump FlywheelInspections.

9710160168 971014 PDR ADOCK 05000313

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U. S. NRC N October 14,1997 OCAN109706 Page 2 a

The CEOO appreciates the NRC's review of this report. Should you have questions or comments, please contact me.

j Very truly yours, ShC.71(4 Dwight C. Mims Director, Nuclear Safety DCM/dwb enclosures cc w/o encl:

Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Reynlatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IV/ANO 1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-113 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Stewart Magruder Project Manager U. S. Nuclear Regulatory Commission NRR Mail Stop 010HS One White Flint North -

11555 Rockville Pike Rockville, MD 20852

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