ML17056A966

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Rev 7 to Odcm.
ML17056A966
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 02/27/1990
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17056A964 List:
References
PROC-900227, NUDOCS 9009110047
Download: ML17056A966 (6)


Text

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TECHNICAL REVIEW AND COAAROL

'""EVALUATION OF NEED FOR SAFETY ANALYSIS Qf ACCORDANCE WITH 10 CFR 50.59 (Documents that require General Supt. approval per Tech Spec 6.8)

FOR DOOONENT NO. P CCrtrt cc. REF.~ DAZE W DF C The Author (A) and four SORC Members (Minimum 2 regular members, 2 alternates) are to respond to each of the questions belo~.

NO YES+

Does the document/revision result in a change to the facility A lF 0 or procedures described in the FSAR?++ 1 0 0 2 0 0 3 0 0 4, 0 0 Does the document/revision deviate from compliance to Tech

'- Specs, or is the margin of safety defined in the basis A W o 1 0 0 reduced? P 2 3 0 0 4 0 0 Does the document/revision increase the probability of A O occurrence, or the consequences of an accident, or malfunction 1 0 0 of equipment important to safety (Class 1) evaluated in the 2 0 0 FSAR increased? 3 0 0 4 0 O Does the document/revision create the possibility for an A 0 accident or malfunction of a different type than any evaluated 1 0 0 in the FSAR? 2 3 0 0

""" """+A""MAYBE" 4 0 0 lcoastitutes a "YES". response.

Recoamend Nuclear Engineering or Tech Services perform a safety LYSIS ta present to SORC (noted by a 'YES" 2 4 response:to any of the: above questions).

1 0 0 0,0 3

Recomaend of need full SORC ccmmittee review for Safety Analysis.

this Evaluation 1 0

2 0 0 3,40 approval - This not involve L//2 //

Recoaanend unreviewed safety question.

document does an

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SORC Member Signatur Date 1 ~

SORC meeting 2

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REFERENCE azvizv DOCUMENTS ann con Tao'.

The items entered below have been included in the preparation and/or review of the attached reference document aad are presented in place of a specific check sheet for the document..

MAME The followiag persons were consulted about this procedure

~c Tl Procedure is in compliance with the folfo<<ing Technical Specifications

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MENDMENT~Y-P

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Compliance <<ith: CFR US-NRC Compliance <<ith REGULATORY GUIDES(s) DATED ANSI STANDARD(s) DATED

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BY Compliance with: ASME Bolter and is consistent with the following Station Pressure Vessel Code(s) or Site procedures:

0 D U R B Ar/ Q5 OTHER INFORMATION

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