ML20137X880

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Notice of Consideration of Issuance of Amends to Licenses DPR-53 & DPR-69 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Tech Spec Section 6.0 Re Reorganization of Onsite & Offsite Mgt
ML20137X880
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 11/18/1985
From: Butcher E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19276C968 List:
References
NUDOCS 8512100656
Download: ML20137X880 (8)


Text

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7590-01 i

UNITED STATES NUCLEAR REGULATORY COPNISSION i-BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NOS. 50-317 AND 50-318 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Comission (the Conunission) is considering issuance of amendments to Facility Operating License Nos. DPR-53 and DPR-69 issued to Baltimore Gas and Electric Company (the licensee), for operation l

of the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 located in Calvert j

j County, Maryland.

The amendments proposed by the licensee would change the Technical Specifications (TS) as follows:

(1) TS 6.2.1 and 6.2.2, " Organization",

I would be changed via TS Figures 6.2-1 and 6.2-2 to reflect an extensive

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corporate reorganization; (2) the titles of a number of individuals, as reflected in TS Section 6.0, " Administrative Controls", would be changed as a result of the reorganization; and (3) TS 6.5.1, " Plant Operations and Safety Review Committee (POSRC)", would be changed to reflect the elimination of f-i one member from the POSRC. These changes to the TS were proposed by the i

licensee in an application dated November 1,1985.

Before issuance of the proposed license amendments, the Comission l

wi'.1 have made findings required by the Atomic Energy Act of 1954, as amended l

(the Act), and the Comission's regulations.

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. The Comission has made a proposed detennination that the amendment request involves no significant hazards consideration. Under the Comission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendments would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

The proposed reorganization represents a significant change in the off-site and on-site organizational structure as reflected in TS 6.2.1 and 6.2.2, respectively. The Vice President-Supply and Vice President-Engineering and Constr.rction positions would be eliminated. A new position of Vice President-Nuclear Energy would be created which would encompass the present responsibilities of the above two eliminated positions with respect to BG&E's nuclear program. Reporting to the Vice President-Nuclear Energy would be four managers: Manager-Nuclear Operations (The Manager-Nuclear Operations would assume the current responsibilities of the Plant Superintendent with respect to nuclear safety); Manager-Nuclear Engineering Services (The Manager-Nuclear Engineering Services would be established to consolidate all of the engineering support staff into a single department); Manager-Quality Assurance and Staff Services (The Manager-Quality Assurance and Staff Services would assume the responsibilities of the present Manager-Quality Assurance with exception of the Quality Control function); and Manager-Nuclear Maintenor,ce (The Manager-Nuclear Maintenance would be responsible for the electrical

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3 instrument control, and mechanical maintenance / modification crafts and technicians and their associated quality control inspectors.)

The proposed reorganization would be expected to improve management at Calvert Cliffs by allowing key functions to report to a single BGAE Vice President while maintaining independent oversight. Since an equivalent or improved level of management would be maintained at Calvert Cliffs, no degradation in the maintenance or testing of safety-related equipment or structures would occur; thus, the proposed reorganization would not involve a significant increase in the probability or consequences of accidents previously evaluated or create the possibility of a new or different type of accident. Since no changes in plant design or operation are involved, no reduction in safety margins would occur. Accordingly, the Comission proposes to detemine that the proposed changes to TS 6.2.1 and 6.2.2 involve no significant hazards considerations.

Consistent with the proposed changes to TS 6.2.1 and 6.2.2, the licensee has proposed a number of changes to TS Section 6.0 to reflect changes in job titles.

In all cases, the job function remains the same and only the title would change.

On April 6, 1983, the NRC published guidanc= in the Federal Register (48 FR 14870) concerning examples of amendments that are not likely to involve significant hazards considerations. Onesuchexample(1) involves "A purely administrative change to technical specifications: for example, a changetoachieveconsistencythroughoutthetechniglspecifications, correction of an error, or a change in nomenclature." "The proposed changes to Section 6.0 are administrative in nature in light of the

4 proposed deteminations concerning TS 6.2.1 and 6.2.2.

Accordingly, the l

Comission proposes to detemine that the proposed changes to Section 6.0, l

which would change position titles consistent with proposed changes to TS 6.2.1 and 6.2.2, involve no significant hazards considerations.

i Finally, the licensee has proposed to eliminate one member from the POSRC as specified in TS 6.5.1.

This comittee provides a substantial degree of oversight concerning safety-related activities related to plant operation; TS 6.5.1.6 enumerates these responsibilities. At the present time, TS 6.5.1.2 requires that the POSRC be composed of eight members and a chaiman. The licensee has proposed that the POSRC be composed of seven members and a chaiman.

The proposed elimination of a POSRC member does not eliminate any technical discipline necessary to carry out the function of the POSRC or in any other way hamper the function of the POSRC..Since the POSRC will continue to maintain adequate oversight concerning activities that affect safety-related equipment or structures, change in POSRC membership would l

not involve a significant increase in the probtbility or consequences of accidents previously evaluated or create the possibility of a new or different type of accident. Finally, since no changes in plant design or operation are involved, no reduction in safety margins would occur.

Accordingly, the Comission proposes to detemine that the proposed change l

to TS 6.5.1.2, which eliminates one member from the POSRC, involves no t

j significant hazards considerations.

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0 The Comission is seeking public coments on this proposed determination. Any coments received within 30 days after the date of publication of this notice will be considered in making any final deteminaticn. The Comission will not normally make a final determination unless it receives a request for a hearing. Coments should be addressed to the Rules and Procedures Branch, Division of Rules and Records. Office of Administration, U.S. Nuclear Regulatory Comission Washington, DC 20555.

By December 26, 1985, the licensee may file a request for a hearing with respect to issuance of the amendments to the subject facility operating licenses and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene. Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or in Atomic Safety and Licensing Board, designated by the Comission or by th* Chairman of the Atomic Safety and Licensing Board Panel, will rule on the reiuest and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.

As required by 10 CFR 62.714, a petition for leave to intervene shall set forth with particularity the interest of the petit'oner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be pemitted with particular reference to the following factors:

(1)thenature

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' of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prict to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.

Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be Ifmited to matters within the scope of the amendments under consideration. A petitioner who fails to file such a supplement which utisfies these requirements with respect to at least one contention will not be permitted to participate as a party.

Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.

If a hearing is requested, the Comission will make a final determination on the issue of no significant hazards consideration. The final detemination will serve to decide when the hearing is held.

7 4 If the final determination is that the amendment request involves no significant hazards consideration, the Comission may issue the amendments and make them effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendments.

If the final detemination is that the amendments involve a significant hazards consideration, any hearing held would take place before the issuance of any amendment.

Normally, the Comission will not issue the amendments until the expir-ation of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Comission may issue the license amendments before the expiration o.' the 30-day notice period, provided that its final detemination is that the amendments involve no significant hazards consideration. The final determination will consider all public and State coments received. Should the Comission take this action, it will publish a notice of issuance and provide for opportunity 4

for a hearing after issuance. The Comission expects that the need to take this action will occur very infrequently.

A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission U.S. Nuclear Regulatory Comission, Washington, D.C.

20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room,1717 H Street, N.W.,

Washington, D.C., by the above date. Where petitions are filed during the lastten(10)daysofthenoticeperiod,itisrequestedthatthepetitioner promptly so inform the Comission by a toll-free telephone call to Western

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8-Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Edward J. Butcher:

(petitioner's name and telephone number),

(date petition was mailed), (plant name), and (publication date and page number of this FEDERAL REGISTER notice). A copy of the petition should also be sent to the Executive Legal Director, U.S. Nuclear Regulatory Connission. Washington, D.C.

20555, and to James A. Biddison, Jr., General Counsel, G and E Building, Charles Center, Baltimore, Maryland 21203, attorney for the licensee.

Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a detennination by the Comission, the presiding officer or the Atomic Safety and Licensing Board, that the petition and/or request should be granted based upon a balancing of the factors specified in 10CFR2.714(a)(1)(f)-(v)and2.714(d).

For further details with respect to this action, see the application for amendment dated November 1,1985 which is available for public inspection at the Comission's Public Document Room,1717 H Street, N.W.,

Washington, D.C., and at the Calvert County Library, Prince Frederick, Maryland.

Dated at Bethesda, Maryland this 18th day of November,1985 FOR THE NUCLEAR REGULATORY COMMISSION Edward J. Butcher, Acting Chief Operating Reactors Branch # 3 Division of Licensing i

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