ML20235A678

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Application for Amend to License DPR-36,consisting of Proposed Change 135,revising Offsite & Facility Organizational Charts.Fee Paid
ML20235A678
Person / Time
Site: Maine Yankee
Issue date: 01/06/1988
From: Randazza J
Maine Yankee
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235A681 List:
References
MN-88-01, MN-88-1, NUDOCS 8801120389
Download: ML20235A678 (5)


Text

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. A LineYankee RELIABLE ELFCTHICITY FOR MAINE SINCE 1972 EDISON DRIVE . AUGUSTA, MAINE 04330 .(207) 622 4868 l

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l January 6, 1988 MN-88-01 Proposed Change #135  ;

United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 I

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References:

(a) License No. DPR-36 (Docket No. 50-309)

(b) HYAPCo Letter to UF1RC dated February 3, 1986 (MN-86-10)

Proposed Change 109, Supplement 1 (c) USNRC Letter to MYAPCo dated February 10, 1987

Subject:

Proposed Change No. 135 - Organizational Charts Gentlemen:

In Reference (b), Maine Yankee requested, in part, the NRC to amend its operating license by removing the onsite and offsite organizational charts from the Technical Specifications (TS). This request was deferred pending the review of the retention of administrative requirements in technical specifications through the NRC's Technical Specification Improvement Program, Reference (c). The organization charts have been and will continue to be updated, as necessary, via the annual revisions to the Maine Yankee FSAR.

In the interim, Maine Yankee proposes, pursuant to 10 CFR 50.90, to revise the organizational charts in T.S. 5.2 to reflect a recent corporate i reorganization and title changes for a number of organizational positions. 1 1

The proposed changes, which are described in Attachment A, were discussed with Messrs. Higgins and Boger of the NRC Staff on December 31, 1987. A preliminary copy of the proposed chart of the offsite organization was also provided at that time to the Senior Resident Inspector.  ;

The proposed revised Offsite and Facility Organizational Charts are found in Attachment B.

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. ki3$11C [81N{CC United States Nuclear Regulatory Commission Page Two Attention: Document Control Desk MN-88-01 Maine Yankee has evaluated the proposed changes and has determined that they do not involve a significant increase in the probability or consequences of an accident previously evaluated; increase the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety. Therefore, these proposed changes do not include a significant hazards consideration as defined in 10 CFR 50.92. The evaluation is included in Attachment A.

This proposed change has been reviewed by the Plant Operation Review Committee and the Nuclear Safety Audit and Review Committee. The Plant Operations Review Committee has concluded that the proposed Technical Specification changes do not constitute an unreviewed safety question.

A State of Maine representative has been sent a copy of this proposed change.

A license amendment application fee of $150.00 is enclosed per 10 CFR 50.71.

Very truly yours, MAINE YANKEE John B. Randazza Executive Vice President JBR/bjp

Attachment:

(5 P'ges) cc: Mr. Richard H. Wessman Mr. William T. Russell Mr. Cornelius F. Holden Mr. Pat Sears Mr. Clough Toppan STATE OF MAINE I Then personally appeared before me, John B. Randazza, who being duly sworn did state that he is Executive Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.

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Mainehkee ATTACHMENT A Description of Prooosed Chanae The proposed changes presented in Attachment B 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 proposed:

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 Licensing Department and the Plant Engineering Department. The Vice President Engineering reports to the Executive Vice President.

b. Substitution of the title " Executive Vice President" for "Vice President - Operations".
c. Establishment of the position "Vice President-Finance and Administration" consolidating the functions previously performed by two Vice Presidents.
d. Replace the title " Manager of Operations" with "Vice President Operations".
e. Elimination of the function "Vice President - Production".
f. Substitution of the word " Manager" for " Director".

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

a. Substitution of the title " Manager" for " Department Head".
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 Department.

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. h}8kUh[80!(CO Significant Hazards Evaluation The proposed changes to the Technical Specifications to depict the l revisions to the organizational structures and title nomenclature have been evaluated against the standards of 10 CFR 50.92 and have been determined to ,

not involve a significant hazards consideration. These proposed changes do l not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

This proposed change to the organizational charts in TS 5.2 are administrative in nature and have no effect on the probability or '

consequences of an accident previously evaluated.

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 i the proposed changes in the technical specifications would not create the possibility of a new or different kind of accident from any previously evaluated.

3. Involve a significant reduction in a margin of safety.

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

Maine Yankee has concluded that the proposed changes to the Technical Specifications do not involve a significant hazards consideration as defined by 10 CFR 50.92.

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ATTACHMENT B l

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