ML20203C955

Proposed Tech Spec Section 6 Reflecting Company Reorganization

ML20203C955
Person / Time
Site:	Surry
Issue date:	07/14/1986
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18149A219	List: ML20203C955
References
NUDOCS 8607210108
Download: ML20203C955 (8)

Text

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SURRY POWER STATION UNIT NOS. 1 AND 2 i

8607210108 860714 PDR ADOCK 05000200 P

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1 TS 6.1-2 13.

The Process Control Program and implementing procedures for processing and packaging of radioactive waste at least once per 24 months.

b.

Authority The Quality Assurance Department shall report to and advise the 2.xecutive Manager - Quality Assurance, who shall advise the Senior Vice President - Engineering and Construction on those areas of responsibility specified in Specification 6.1.C.3.a above.

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I E X E C UTIVE VICE PRESEDENT POWER I

i SENIOR SENIOR VICE PRESIDENT VICE PRESIDENT POWER ENGINEERING AND OPE R ATIONS CONSTRUCTION VICE PRESIDENT I

NUCLEAR OPERATIONS E X E CUTIVE MANAGER MANAGER M AINTEtJ ANCE &

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ASSlJRANCE SERVICES MANAGER NUCLEAR NUCLEAR MANAGER I

NUCLEAR STATION STATION NUCLEAR MANAGER OPERATIONS MANAGER MANAGER PROGRAMS AN3 MANAGER POWER TR AINING SUPPORT SURRY NORTH ANNA LICENSING QUAllTY I

ASSURANCE SERVICES I

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DIRECTOR DRECTOFI SUPERVISOR DRECTOR DIRECTOR OPERATIONS AND SAFETY g

ADMMISTRATIVE EMERGENCY HEALTH PHYSICS MAINTENANCE EVALUATION IUPERINTENDENT SUPPORT SE RVICE S PLANNING AND CONTROL a

NUCLEAR M

m TR AINING 6

E OFF-SITE ORGANIZATION FOR

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FACILITY MANAGEMENT AND TECHNICAL SUPPORT

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ATTACHMENT 2 SAFETY EVALUATION SURRY POWER STATION UNIT NOS. 1 AND 2

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h Description of Change This proposed change will modify Section 6 of the Surry Technical Specifica-tions to reflect a company reorganization in which the Quality Assurance organization will now report to the Senior Vice President - Engineering and Construction, rather than the Senior Vice President - Power Operations.

It also corrects the titles of several on-site and off-site supervisors. As the major emphasis of the Company's nuclear program is on operations rather than construction, it is appropriate that the QA organization report to Engineering and Construction to enhance the independence of the QA organization.

Basis for No Significant Hazards Consideration The proposed amendment does not involve a significant hazards consideration because operation of Surry Units 1 & 2 in accordance with the change would not:

(1) involve a significant increase in the probability or consequences of an accident previously evaluated.

This change merely revises where the QA organization reports to enhance independence and corrects titles in the on-site and off-site organization charts.

'hus this change does not change plant design or operation and cannot 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.

Realigning the QA organization with Engineering and Construction and revising supervisor titles do not create the possibility of a new or different kind of accident.

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

This change doesn't involve a change in the basis for any Technical Specification or the Updated Final Safety Analysis Report accident analysis.

Therefore, the change doesn't involve a significant reduction in the margin of safety.

50.59 Safety Review The proposed change does not involve a unreviewed safety question because operation of Surry Units 1 and 2 in accordance with this change would not:

(1) increase the probability of occurrence or consequences of an accident or malfunction of equipment previously evaluated in the safety analysis report because these organizational changes and titles do not effect plant design or operations; (2) increase the possibility of an accident or malfunction of a different type than previously evaluated in the safety analysis report because the organization change does not effect plant design or operations.

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g-Pags 2 (3) reduce the margin of safety as defined in the basis for a Technical Specification because the change does not effect the basis of any Technical Specification or the Updated Final Safety Analysis Report safety analysis.

Pursuant to 10 CFR 50.59 and 50.92, it has been determined that this change does not involve a unreviewed safety question or a significant safety hazards consideration.

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ATTACHMENT 3 VOUCHER CHECK SURRY POWER STATION UNIT NOS. 1 AND 2

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