ML17326A037

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Discusses Meeting Conducted at Region III Senior Reactor Analysts at Plant Re Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee
ML17326A037
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/06/1999
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Powers R
AMERICAN ELECTRIC POWER CO., INC.
References
NUDOCS 9907140022
Download: ML17326A037 (5)


Text

CATEGORY c REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9907140022 DOC.DATE: 99/07/06 NOTARIZED: NO DOCKET ¹ FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION GROBE,J.A.

Region 3

(Post 820201)

RECZP.NAME RECIPIENT AFFILIATION POWERS,R.P.

American Electric Power Co., Inc.

SUBJECT:

Discusses meeting conducted at Region IIZ Senior Reactor Analy'sts at plant re initiatives in risk area 6 to establish dialog between SRAs 6 licensee.

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TITLE: General (50 Dkt)-Znsp Rept/Notice of Violation Response NOTES:

E RECIPIENT ID CODE/NAME LPD3-1 PD INTERNAL: AEODJA CENT P

NUDOCS -ABSTRACT OGC/RP EXTERNAL: LMITCO MARSHALL NRC PDR COPIES LTTR ENCL RECIPIENT ZD CODE/NAME STANG,J DEDRO NRR/DZPM/IIPB NRR/DRIP/REXB OE RGN3 FILE 01 NOAC NUDOCS FULLTEXT COPIES LTTR ENCL 0

N NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE

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ON EXTENSION C15-2083 TOTAL NUMBER OF COPIES REQUIRED:

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July 6, 1999 Mr. R. P. Powers Senior Vice President Nuclear Generation Group American Electric Power Company 500 Circle Drive Buchanan, Ml 49107-1395

SUBJECT:

SENIOR REACTOR ANALYSTSITE VISIT

Dear Mr. Powers:

This refers to a meeting conducted by the Region III Senior Reactor Analysts (SRA) at your D. C. Cook, Units 1 and 2 reactor facilities in Stevensville, Michigan, on June 28, 1999. The purpose of the visit was to meet with your Probabilistic Risk Assessment (PRA) staff to discuss your initiatives in the risk area, and to establish a dialog between the SRAs and your PRA staff.

Also discussed were your specific risk insights and risk tools used at the plant.

As you are aware, the Nuclear Regulatory Commission is transitioning to a risk-informed framework for its inspection and oversight program for commercial nuclear power plants. The new program willfocus our inspections on activities and systems where potential risks are greater using site-specific PRA insights. The meeting between your staff and our risk anlaysts provided a basis for better agreement on the importance of issues on which we willroutinely interact during the risk-informed inspection and oversight program.

In accordance with Section 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures willbe placed in the NRC's Public Document Room.

Ifyou have any questions regarding this meeting please contact me at (630) 829-9700.

Sincerely, Original /s/ J.

A. Grobe John A. Grobe, Director Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 See Attached Distribution DOCUMENT NAME: G:DRS'tDCC070 9.WPD To tecelve a co of thla document Indicate ln the boxt W ~

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R. Powers cc:

A. C. Bakken III, Site Vice President T. Noonan, Acting Plant Manager M. Rencheck, Vice President, Nuclear Engineering R. Whale, Michigan Public Service Commission Michigan Department of Environmental Quality Emergency Management Division Ml Department of State Police D. Lochbaum, Union of Concerned Scientists Distribution:

RRB1 (E-Mail)

RPC (E-Mail)

Project Mgr., NRR J. Caldwell, Rill B. Clayton, Rill SRI D. C. Cook DRP DRS RIII PRR PUBLIC IE-01 Docket File GREENS IEO (E-Mail)

DOCDESK (E-Mail)

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