ML20136C266

Requests Encl Listed Drawings for Regulatory Effectiveness Review Scheduled for Wk of 860714-17.Drawings Needed by 851201.Review Will Evaluate Overall Effectiveness of Safeguards Program

ML20136C266
Person / Time
Site:	Yankee Rowe
Issue date:	11/05/1985
From:	Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Heider L YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 8511210064
Download: ML20136C266 (4)

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- NOV 0 5 1968 Docket No: 50-29 Yankee Atomic Electric Company ATTN: Mr. L. H. Heider Vice President of Operations 1671 Worcester Road Framingham, Massachusetts 01701 Gentlemen:

Subject:

Safeguards Regulatory Effectiveness Review at the Yankee Atomic Nuclear Power Station The NRC's Office of Nuclear Material Safety and Safeguards (NMSS) is in the process of conducting a Regulatory Effectiveness Review (RER) at operating nuclear power plants. .The Yankee Atomic Power Station is scheduled for such a review during the week of July 14-17, 1986.

The purposes of the RER are to evaluate the overall effectiveness of the safeguards program and to determine whether existing safeguards regulations yield the level of protection intended by NRC. The RER supports the NRC's quality assurance program for safeguards, as it applies to both the Yankee Atomic security systems and the NRC's regulations. The RER will complement but will be independent of the licensing and inspection functions. Specific details regarding the conduct of the RER, including identification of the team members, will be provided to you at a later date.

So that NMSS can prepare for the RER at the Yankee Atomic Power Station, you are requested to provide the information identified on the enclosed list directly to Mr. Robert Dube, Chief, Safeguards Evaluation Section, of that -

office by December 1, 1985. If you have any questions regarding this request, please contact R. R. Keimig of my staff at (215) 337-5255.

The response directed by this letter is not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

Your cooperation with us in this matter is appreciated.

Sincerely, o tn d S cp gcl (oy!

Thomas T. Martin, Director Division of Radiation Safety and Safeguards

Enclosure:

As stated

^""""L RECORD COPY I e511210064 851105 1 g PDR ADOCK 05000029 (

PDR F _;

i GPU Nuclear Corporation 2 NOV 051985 cc:-(w/enci)

N. N. St. Laurent, Plant Superintendent J. E.. Tribble, President J. A. Kay, Senior Engineer - Licensing Public Document Room (PDR)

< Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Comonwealth of Massachusetts (2) bec: (w/ encl)

Region I Docket Room (with concurrences)

Section Chief, DRP

- M. McBride, SRI, Pilgrim W. Raymond, SRI, Vermont Yankee J. Clifford, LPM, NRR Robert Dube, NMSS E wyy ss &J l'/Y/ W. h y b SQf K od w,lkA .=%m r Mk.

I:DRSS RI: SS RTd)RSS RI D3SS Smith Kei b Joyner M tin .-

Oh6/85- 10/Je/85 10/31/85 1/ //85 0FFICIAL RECORD COPY

YANKEE R0WE LIST OF DRAWINGS NEEDED FOR RER

1. Equipment Layout Drawings 9699-FM-18A Machine Location Plan Operating Floor - Turbine Room f

! 9699-FM-18B Machine Location Plan Ground Floor - Turbine Room ,

9699-FM-18C Machine Location - Section Turbine Room 9699-FM-18D Machine Location Plan Mezzanine Floor - Turbine Room 2

9699-FM-57A Machine Location Plan Primary Aux. Building - Sheet 1 9699-FM-57B Machine Location Plan Primary Aux. Building - Sheet 2 9699-FM-81A Machine Location Diesel Generating Building

2. Piping and Instrument Diagrains M-1 Main Coolant System M-2 Pressure Control & Relief System-M-3 Charging & Volume Control System

M-5 LPST, Shutdown & SFP Cooling M-6 Chemical Shutdown System M-7 Safety Injection System

~

M-9 MC Drain & Samples Systems

.M-14 Feedwater System M-15 S. G. Feedwater & Blowdown M-16 Purification & VC Recirculation System M-20 Main Steam Lines M-24 Auxiliary & Heating Steam t

9699-FM-83A Flow Diagram - Low Press. Safety Inj. High Press. Safety Inj. and Nitrogen 9699-FM-8A-SC Flow Diagram - Charging and Bleed and Chemical Shutdown l

System.

l 9699-FM-4A-SC Flow Diagram Condensate and Feedwater Line -

i 9699-FM-3A Flow Diagram - Main and Aux. Steam Lines and Steam Generator Blowdown

. . _ _ _ . _.- _ . , .-. ._ . _ ~ .. .

Page 2

3. Electrical One Line Diagrams I E-1 Station Service AC,' DC and Vital Instrumentation Supply l E-14 Bus No. 5-2 480 VAC E-15 Bus No. 4-1 480 VAC E-16 Bus No. 6-3 480 VAC

. 4. Miscellaneous Drawings j FSAR. Figure No. 1.2-1 Plant General Arrangement

• I FSAR Figure No. 1.2-2 Site Building Arrangement

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• Need equivalent engineering drawings for the FSAR Figure numbers listed j above.

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