ML20149H283

Safety Evaluation Supporting Amend 103 to License DPR-36

ML20149H283
Person / Time
Site:	Maine Yankee
Issue date:	02/17/1988
From:	Office of Nuclear Reactor Regulation
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ML20149H239	List: ML20149H236 ML20149H269 ML20149H283
References
NUDOCS 8802190201
Download: ML20149H283 (4)

Text

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SAFETY EVAL.UATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REl.ATED TO AMENDMENT NO.103 TO FACILITY OPEATING LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER PLANT DOCKET NO. 50-309

1.0 INTRODUCTION

By letter dated January 6,1988, Maine Yankee Atomic Power Company (MYAPCO) reouested changes in Section 5.2 "Organization" of the Technical Specifications for the Maine Yankee Atomic Power Plant. The requested changes are to the corporate organization, depicted on Technical Specification Figures 5.2-1 and 5.2-2.

DESCRIPTION The proposed changes would update Figure 5.2-1 and Figure 5.2-2 in Technical Specification 5.2 "Organization" depicting the Company's offsite and facility organization, respectively.

In Figure 5 2-1, Offsite Organization, the following changes are l proposed: I

a. A new position of "Vice President Engineering".

This organizational change will provide for an additional level of {

upper management for the Nuclear Engineering and I.icensing Department and :

the Plant Engineering Departinent. The Vice President Engineering I reports to the Executive Vice President. )

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b. Substitution of the title "Executive Vice President" for "Vice l President - Operations",

c. Establishment of the position "Vice President-Finance and 1 Administration" consolidating the functions previously performed by l

.. two Vice Presidents. I x  ;

d. Replace the title "Manager of Operations" with "Vice President l Operations",

e. Elimation of the function "Vice President - Production".

f. Substitution of the word "Manager" for "Director".

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2 The following changes are proposed for Figure 5.2-2, Facility Organization:

a. Substitution of tha title "Marager" for "Department Pead".

b. Reactor Engineering Function will be consolidated with the Nuclear Engineering Function reporting to the Manager, Nuclear Engineering and Licensing,

c. Consolidation of the Fire Protection with Plant Services function, both reporting to the Manager, Technical Support,

d. Identification of the Computer Section function, reporting to the Manager, Technical Support.

e. Identification of the Outage Planning Function within the Maintenance Departirent.

EVALUATION The staff has encouraged utilities to strengthen their organizational structures including the approach described in MYAPCo's January 6,1988 letter. A new position of Executive Vice President is established with Vice President-0perations, Vice President-Engineering and the Manager Quality Assurance reporting directly to the Executive Vice President. The position of Vice President-Engineering replaces the position of Vice-President Operations and the nuclear engineering, licensing and plan engineering functions report to that position. Those functions fomerly reported to Vice President Operations.

These changes, while retaining significant management strengths at the l facility will more evenly utilize upper level management at corporate  !

headquarters. The span of control for individual managers is acceptable. l The grouping of similar activities under a particular manager should allow '

effective control of these activities. The NRC staff believes this change will strengthen the corporate and facility organizational structures and will l provide more effective use of personnel, resulting in a net increase in the safety i of operations.

Overall, we find that the changes proposed by the licensee add to the effectiveness of the Maine Yankee corporate and site organizations and that 1 the resulting organizations at both the plant and corporate levels are in l accordance with the Standard Review Plan.

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We have reviewed these proposed changes and find that they are administrative in nature, that they do not adversely affect the support to plant operations, and that the resulting organization meets the guidelines of Section 13.1.1 of the Standard Review Plan, NUREG-0800.

ENVIRONMENTAL CONSIDERATION This amendment involves a change to recordkeeping, reporting or administrative procedures or requirements. The staff has determined that the amendaent involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation  !

exposure. The Comission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no NO SIGNFICANT HAZARDS CONSIDERATION  ;

The changes to the Technical Specifications to depict the revisions to the organizatinnal structures and title nomencluature have been evaluated against '

i the standards of 10 CFR 50.92 and have been determined to not involve a significant hazards consideration. These changes do not: l

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. This change to the organizational charts in Technical Specification 5.2 are administrative in nature and have no effect on the probability or consequences of an accident previously ,

evaluated. l

2. Create the possibility of a new or different kind of accident from any previously evaluated. Since there are no changes in plant design or operation, inclusion of changes in the Technical Specifications would not create the possibility of a new or different kind of accident from I any previously evaluated. J

3. Involve a significant reduction in a margin of safety. For the reasons previously stated, adoption of the change would not involve l a significant reduction in safety margin for the plant. l I

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_4 The changes to the Technical Specifications are administrative in nature, should increase the effectiveness of the utility's management controls, and should provide a positive contribution to the safety of plant and corporate activities. Consequently, the staff has concluded that the changes in the Technical Specifications do not involve a significant hazards consideration as defined by 10 CFR 50.92.

Mr. W. Clough Toppan of the State of Maine was consulted concerning the proposed exigent technical specification change on January 22, 1988. Mr.

Toppan has no comments.

CONCLUSION The staff has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Accordingly, we conclude that the proposed changes are acceptable.

Dated: February 17, 1988 Principal Contributor: Patrick Sears 1

AMENDf1ENT NO.103 TO DPR MAINE YANKEE ATOMIC POWER STATION DISTRIBUTION

• Docket File NRC P['P.

Local PDR PRC System PDJI-3 Reading M. Rushbrook P. Sears S. Varga S. Boger W. Jones D. Hagan T. Barnhart (4)

E. Jordan J. Partlow C. Miles, PA R. Diggs, LFMB OGC-Bethesda ACRS (10)

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