ML20134P304

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Forwards Documentation of 25 Items Identified During 850429-0503 Insp Which Appear to Be Under NRR Cognizance. Info Re Final Draft Tech Specs Forwarded,Per
ML20134P304
Person / Time
Site: River Bend Entergy icon.png
Issue date: 05/13/1985
From: Denise R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Crutchfield D, Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20132C450 List:
References
FOIA-85-511 NUDOCS 8509060236
Download: ML20134P304 (14)


See also: IR 05000429/2005003

Text

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MEMORAtiDUM FOR: Dennis M. Crutchfield, Assistant Director for Safety

Assessment, Division of Licensing

Thomas M. Novak, Assistant Director for Licensing,

Division of Licensing

FROM:

Richard P. Denise. Director, Division of Reactor Safety and

Projects

SUBJECT:

FINAL DRAFT OF TFE RIVER BEr.D UNIT 1 TECHNICAL SPECIFICATIONS

This provides information on the Region IV review of the final draf t technical

specifications for River Eend.

It is forwarded as requested by your letter of

April 19, 1935.

A Region IV team inspection was concucted from April 29 through May 3,1985.

The results of this inspection were that some 25 items were identified, which

appear to be under 14RR cognizance. These are documented in the attached

inspection report forms. Except for the attached, no additional items were

identified wnich we feel require action on your part. There were, however,

over 300 items related to the licensee's implementing procedures. These will

be documented in Inspection Report 50-458/85-35.

Although our inspection of the draf t technical specifications was prim'artly

directed toward the licensees readiness to implement them, we did review the

technical specifications for cbvious discrepancies between them, the Safety

Evaluation Report (NUREG-0989, including Supplement 1), ano the Final Safety

Analysis Report (through Amendment 17). There were no problems fcund in this

area, which are not already noted in the attached report forms.

AO&

FCi Richard P. Denise, Director

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Division of Reactor Safety and

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Projects

Attachments:

As stated

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position.

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TECHNICAL SPECIFICATION REVIEW DATA SHEET

TS PARA: 3/'t 4.1. A /

PAGE NO.:

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TS REQUIREMENT:

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LIC. PROCEDURE NO.:

EP-09 -v(v ISSUE DATE:

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REY.:

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TITLE:

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YES

NO

Is there any difference between FSAR/SER and TS?

%

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Is installed system consistent with TS?

Are there any problems with the TS (factual or

editorial)?

l

Does procedure carry out TS requirement?

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Does the procedure walkdown indicate that it should

FA

work as written?

Has licensee completed procedure walkdown?

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REMARKS:

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INSPECTOR (S):

bs (1. 4cn e e #-

FOLLOWUP ACTION:

INSPECTION REPORT 50-458/

YES

N0

Were problems corrected?

Were any other problems identified?

STATUS OF ITEM

OPEN

CLOSED

REMARKS:

INSPECTOR (S):

INSPECTION REPORT 50-458/ 'Pi- U

PAGE NO.:

.

.

TECHNICAL SPEClf! CATION REVIEW DATA SHEET

'

TS PARA: .3/y,93,4.)

PAGE NO.: 3/y 3 -11

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LIC. PROCEDURE NO.: STF4581MI

ISSUE DATE:

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REV.:

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TITLE: # 545 -tWA' Vend kafe, lenf -6 W, La,de t, , W, 6, Lt.<l I,c4a..el G fh#3

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(6 4-Notl 4j 6 M-#6Pl 4) 0>t-NAT) A )

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YES

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Is there any difference between FSAR/SER and TS?

N/A

Is installed system consistent with TS?

F/A

Are there any problems with the TS (factual or

./

editorial)?

Does procedure carry out TS requirement?

Does the procedure walkdown indicate that it should

//A

work as written?

Has licensee completed procedure walkdown?

REMARKS:

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STATUS OF ITEM

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FOR "0 PENS", WHO MUST 00 WHAT BY WHEN?

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INSPECTOR (S):

W.fl.AcantY

FOLLOWUP ACTION:

INSPECTION REPORT 50-458/

YES

M

Were problems corrected?

Were any other problems identified?

STATUS OF ITEM

OPEN

CLOSED

REMARKS:

INSPECTOR (5):

INSPECTION REPORT 50-458/ 85-3f

PAGE NO.: