ML20151P136

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Proposed Tech Specs Figures 3.1,3.2,6.2.1 & 6.2.2 Reflecting Administrative Changes to Organization Charts
ML20151P136
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 04/15/1988
From:
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML20151P094 List:
References
NUDOCS 8804260093
Download: ML20151P136 (7)


Text

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l PRESIDENT EXECUTIVE

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VICE PRESIDENT SAFETY COMMITTEE I

SENIOR VICE PRESIDENT

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CENTRAL OPERATIONS ASSISTANT VICE PRESIDENT VICE PRESIDENT NUCLEAR POWER 1

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Figure 3.1 Independent Safety e

Amendment No.

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VICE PRESIDENT NUCLEAR POWER GENERAL MANAGER GENERAL MANAGER GENERAL MANAGER GENERAL MANAt,ERe NUCLEAR POWER EPMRONMENTAL TECHNICAL ADblNISTRATIVE GENERATION HEALTH AND SAFETY SUPPORT SERVICES OPERATIONS CHIEF PLANT NUCLEAR P.AlrdlNG WANAGER & STAFF RADLATION PROTECTION ENGINEER & STAFF MANAGER & STAFF WANAGER & STAFF SRO

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NUCLEAR PLANT NUCLEAR PLANT NUCLEAR ANALYSIS OPERATORS OPERATORS

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INSTRUuCNT & CONTROL ENGINEER & STAFF Figure 3.2 Facility Organization

PRESIDENT EXECUTIVE NUCLEAR FACluTIES

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NUCLEAR POWER QUAUTY ASSURANCE Figure 6.2.1 Independent Safety Amendment No.

Review ond Audit Orgonization

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I VICE PRESIDENT NUCLEAR POWER w

GENERAL MANAGER GENERAL MANAGER GENERAL MANAGER GENERAL MANAGERe NUCLEAR POWER EtMRONMENTAL TECHNICAL ADM:NISTRArrVE GENERATION HEALTH AND SAFETY SUPPORT SERVICES OPERATIONS MANAGER & STAFF RAO:ATION PROTECTION CH!FT Pt. ANT FAJCLEAR TRAINING MANAGER & STAFT ENGINEER & STAFF MANAGER & STAFF I

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rActunES MANAGER & STAFF SENOR REACTOR EMERGENCY PLANNING SHIFT TECHNICAL (S)

Or'ERATORS MANAGER & STAFF ADVISORS (CCR1 l

REACTOR CHEMISTRY SAFETY ASSESSuCNT (3)

OPERATORS uANAGER & STAFF MANAGER & STAFF (CCR1 I

NULLEAR PLANT NUCLEAR PLANT OPERATORS OPERATORS NUCLEAR ANALYSIS MANAGER & STAFF (s) j l REACTOR ENQNEERl uAINTENANCE MANAGER & STAFF CENERATION SUPPORT MANAGER & STAFF PROJECTS & PtANNING

  • ResponsitM for the performance and monitoring of the Fire Protection Prograns WMR & STAFF Responsible for the Fire Protection Program Activities (CCR) - Centrol Contree Room Positen (s) - Coatines sh.ft Coverage AMENDMENT NO.

INSTRUMENT & CONTROL Figure 6.2.2 Facility Organization s

d Attachment B Safety Assessment Consolidated Edison Company of New York, Inc.

Indian Point Units No. 1 and 2 Docket Nos. 50-03 and 50-247 April, 1988 l

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Safety Assessment 4

Discussion:

A proposed technical specification revision is set forth in Attachment A to this application.

Several changes are being initiated by Consolidated Edison to incorporate certain administrative changes to the Facility Organization. The proposed revision is reflected in Figures 3.1 and 3.2 of the Indian Point Unit No. 1 Technical Specification and Figures 6.2.1 and 6.2.2 of the Indian Point Unit No. 2 Technical Specification.

The proposed revision to Figures 3.1 and 3.2 and 6.2.1 and 6.2.2 reflect several recent Consolidated Edison technical support organization and facility organization changes.

As reflected in Figure 3.1 and Figure 6.2.1, the Director, Power Generation Services, has been promoted to the title Assistant Vice President, Power Generation Fervices, reporting directly to the Senior Vice President, Central Operations. The Senior Vice President, Central Operations, reports to an Executive Vice President, whose responsibilities, while not indicated in the

Figure, have been expanded.

The offsite Engineering and Construction Organizations continue to support Indian Point while reporting to the Senior Vice President, Central Operations.

As reflected in Figure 3.2 and Figure 6.2.2, changes have also been accomplished in the Nuclear Power organization at Indian Point.

The Chemistry Manager and staff, formerly reporting to the General Manager, Technical Support, now report to the General Manager, Environmental Health and Safety.

Additionally, the Test and Terformance group now reports to the Chief Plant Engineer who continues to report to the General Manager, Technical Support.

These changes are being made with the intent of more productively providing the desired technical support of the Indian Point facility.

Basis For No Significant Hazards Consideration Determination The proposed change does not involve a significant hazards consideration because Operating of Indian Point Unit Nos. 1 and 2 in accordance with this change would nots (1) involve a significant increase in the probability or consequences of an accident previously evaluated.

This is an administrative change which reflects a recent facility re-organization with consolidation and realignment of responsibilities.

The reorganization has been reviewed and a conclusion reached that this change does not increase the probability or consequences of an accident.

(2) create the possibility of a new or different kind of accident from any previously analyzed.

It has been determined that a new or different kind of accident will not be possible due to this change.

An administrative change such as a facility re-organization does not create the possibility of a new or different kind of accident.

F (3) involve a significant reduction in a margin of safety.

The administrative change as described above in the safety assessment discussicn has been determined not to impact the preservation or reduction of any margin of safety.

The Conmission has provided guidance concerning the application of the standards for determining whether a significant hazards censideration exists by providing certain examples (48 FR 14070) of amendments that are considered not likely to involve significant hazards consideration.

Example (i) relates to a purely administrative change to Technical Specifications:

for example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature.

In this case, the proposed change described in Attachments A are related to Example (i),

i.e.,

a purely administrative change.

Therefore, since the application for amendment involves a proposed change that is similar to an example for which no significant hazards consideration exists, we have determined that the application involves no significant hazards consideration. The proposed changes have been reviewed by the Station Nuclear Safety Committee. This Committee concurs that these changes do not represent a significant hazards consideration.

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