ML20148G051

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Notice of Consideration of Issuance of Amend to License NPF-4 & NPF-7 & Proposed NSHC Determination & Opportunity for Hearing.Amends Revise Tech Specs Section 6 as Listed
ML20148G051
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 03/22/1988
From: Engle L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148G056 List:
References
NUDOCS 8803290024
Download: ML20148G051 (8)


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t IINITED STATES N!! CLEAR DrGULATDRY C0W4ISSICr!

VIRRINIA ELECTRIC AND POWER COMPANY t

_PCC_K_ET NOS_._50-33A AND 50-339 d

NOTICE OF CONSIDEEAT?ON OF ISSUANCE OF A5ENONFNTS TO t

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FACILITY OPERATING LitENSES AND PROPOSED NO SIGNIFTCANT 4AZARDS COMSIDERATION CETERMINAT?ON AND OPPORTUNITY FN HEARING I he Commission) is The United States Nuclear Regulatory Comission t

considering issuance of amendments to Faci 11ty Operating License Nos. NPF-4 i

and NPF-7, ist. sed to Virginia Electric and Power Company (the licensee), for s

operation of the 'dorth Anna Power Station, Un;tt No. ~1 and Fo. ? (NA-1&2) located in Louisa County, Virginia.

The amendments xculd revise the NA.1&? Technica) Specifications (TS),

t Section 6 as folitas:

(1) delete the organi ation chan.s and replece them

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re general PUsition descriptions,

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and (3) revise certain adMinistrativa requeremnts 'ir order to brino them into

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closer conformance with the correspnnding requirerant.s current?y specified in the NRC-approved TS for Wert1nghouse plants (HU4EG-0452, Revision 4, 1981).

On March 8, 1988, the licensee announced Company-wide organizational changes wMch will become effective in April 1908.

Specifically, nuclear operations will be strengthened by bringing 15e Engineering and Power Ope.ra tions n Dartments within a single orcanintion hecded by a Senior Vice e

i President.

Nuclear Site Services and Nuclear Training will be includod in oy $

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the Puclear Operations Department.

A single group responsible for nuclear transient and fuel analysis will be created within the Engineering n partment.

e Also within the Engineering Department, Inservice Inspection and Non-Destructive Exanination servicee will be ccmbined under a single manager.

In addition, the number of system engineers assigned to NA-1&? will be increased.

The licensee has concluded that organization charts and/or titles by themselves play little or no role in assessing the safety significance of changes for NA-1&?. Conversely, specific operational requirements that bear more directly on sa'ety matters of concern than the organization charts and titles are explicitly provided elsewhere in the NA-182 TS.

For example, the orcanizational element responsible for control room comand function is identified separately in the TS, as are the requirements for minimum staffing under various operating modes.

The organizational management functions for independent reviews and audits, onsite safety review comittee, and irdependent safety engineering group, while revised by this change recuest to conform more closely with the current acceptable TS for Westinghouse plants, are also specified in other parts of the NA-1&? TS.

Therefore, the organization charts and certain position titles themselves are not needed to support any future finding that the licensee's organization will operate NA-182 in a safe manner.

In addition to being required by the NA-1&2 TS, the important organiza-tional features illustrated by organization charts and certain position citlee are also required or controlled by other mechanisms subject to NRC control.

Specifically, the chapter entitled "Conduct of Operations" of the NA-1&?

Updated Final Safety /

3 Re;, orts (UFSAR) contains a detailed organizational structure and a descriptien of the conduct of operations. The information in this chapter is raquired by 10 CFR 50.71(e) to be maintained and updated

3 annually.

In addition, the licensee's Topical Report, "Cuality Assurance Prcqram Operations Phase," is recuired by 10 CFR 50, Apcendix B, to include similar information velating to the organizational structure, and is recuired by 10 CFR 50.54 to be maintained in a current status.

Before issuarce of the proposed license amendments, the Comission will have made findings required by the Atomic Energy Act of 195a, as amended (the Act) and the Comission's reoulations.

The Comission has made a proposed determination that the renuest for arendments involves no significant hazards considerations.

Under the Comission's regulations in 10 CFR 50.99, this means that operation of the facilities in accordance with the proposed amendrients would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (?) create the possibility of a new or different kind of accident from ~.ny accident previously evaluated; or (3) involve a significant reduction in a rargin of safety.

The licensee has stated that the proposed chances to the NA-la? TS involve no significant hazards considerations because operation of NA-1&?. in accordance with these changes would not:

(1)

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

The changes merely reflect administrative considerations and do not change the plant design or operations.

As in the past, the Comission will continue to be inforwed of organizational changes through other required controls.

The Code of Federal Regulations, Title 10. Part 50.34(b)(6)(1) requires that the licensee's organizational structure be included in the UFSAR.

Accordingly, the "Conduct of Operations" chapter of the UFSAR provides a description of the organization and detailed

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organization charts.

As required by 10 CFP 50.71(e), the Compary submits annual updates to the llFSAR.

Finally, Appendix B to 10 CFR Part 50 and 10 CFR 50.54(a)(3) govern changes to organization described in the Quality Assurance Topical Pecort.

(21 Cret.te the possibility of a rew or dif9 rent kind of accident from any accident previously evaluated, because as noted above, neither the plant design nor cperation is af#ected by these changes.

(3)

Inynive a significant reduction in a margin of safety.

These changes do not alter the functions, responsibilities, or minimum shift crew composition of the staff as defined by the Administrative Controls of the NA-182 TS.

Through strong quality assurance programs and comitment to maintain only qualified personnel in positions of responsibility, it is assured that safety functions performed by the on-site and the corporate organizations will continue to be performed at a high level of competence.

The NRC staff agrees that the proposed changes to the Technical Specifications meet the criteria specified in 10 CFR 50.92(c) and, hence, proposes to determine that they involve no significant hazards considerations.

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 deterinination. The Comission will not normally make a final determination unless it receives a request for a hearing.

Written coments may be submitted by mail to the Rules and Procedures Branch, Division of Pules and Records, Office of Administration, U.S. Nuclear Reoulatory Comission, Washington, D.C. 20555, and should cite the publica-tion date and page number of this FEDERAL. REGISTER notice. Written connents

0 may also be delivered to Room 4000, Maryland National Bank Ruilding, 7735 Old Georgetown Road, Bethesda, Meryland, from 8:15 a.m. to 5:00 p.m.

Copies of written comments received may be examined at the NRC Public Docurent Room, 1717 H Street, N.W., Washington, D.C.

The filirp of requests for hearino and petitions for leave to intervene are discussed below.

By April 27, 1988

. the 1 censee may file a request #or a hearirn with respect to issuance of the amendments to the subiect facility operating licerses and any person whose interest may be affected by this proceeding and who wishes to participate as a carty in the proceeding must file a request for hearing and a written petition for leave to intervene.

Requests for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's "Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

If a request for a hearing or petition for i

leeve to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairmar of the Atomic Safety and Licensing Board Panel, will rule on the request 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 62.71a, a petition for leave to intervene shall set forth with particularity the interest of the petitioner 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 nermitted with particuler reference to the following factors:

(1) the nature of the petitioner's richt 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

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be entered in the proceedino on the petitioner's interest.

The petition should also identify the specific aspect (s) of the sub,iect matter of the proceeding as to which petitioner wishes to intervene.

Any person who has *iled a petition for leave to intervene or who has been admitted as e party may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first pre-hearing 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 that are sought to be litigated in the tratter, and the bases for each contention set forth with reasonable specificity.

Contentions shall be limited to matters within the scope of the amendments under consideration.

A petitiorer who fails to file such a supplement which satisfies these requirernents with resoect to at least one contention will not be permitted to participate as a party.

Those permitted to intervene become parties to the proceeding, sub,4ect to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, includino 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 considerations.

The final determination will serve to decide when the hearing is held.

If the final determination is that the request for amendments involves no significant hazards considerations, 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.

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If the final determination is that the amendments involve significant hazards considerations, any hearing held would take place be#cre the issuance of any amendment.

flormally, the Commission will not issue the amendments until the expira-tion of the 30-day notice period. However, should circumstances change during the notice period such that #ailure to act in a timelv way would result, for example, in derating or shutdown of one or both of the facilities, the Comission may issue the license amendments be# ore the expiration of the 30-day notice period, provided that its final detennination is that the amendments involve no sionificant hazards considerations.

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 for a hearing after issuance. The Comission expects

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that the r.eed to take this action will occur very infrequently.

A reouest for hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Cormission.

Washington, D.C. 20555, Attention: Decketing and Service Branch, or may be j

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 last ten (10) days of the notice period, it is requested that the petitioner i

prenptly so infonn the Comission by a toll-free telephone call to Western 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 Herbert N. Berkow:

(petitioner's name and telephone numberl; (date petition was mailed); (plant name); and (publication date and page number of this FEDEPAL REGISTER notice.

A copy of the petition shculd also be sent

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to the Office of the General Counsel, U.S. Nuclear Regulatory Comission, Washington, D.C.

20555, and to Michael W. Maupin, Esq., Hutton and Williams, P. O. Box 1535, Richmond, Virginia 23219, attorney for the licensee.

Nontirely filings of petitions for leave to intervene, amended petitiers, supplemental petitions and/or requests for hea*ing will not be entertained absent a determination by the Commission, the presiding o "icer or the Atomic Sa#ety and Licensing Board, designated to rule on the petition and/or request, that the b.itioner has made a substantial shcwing of good cause for the grantino of a late petition and/or request.

That determination will be based upon a balancino of the factors specified in 10 CFR 2.714(a)(1}(i)-(v) and 2.714(d).

For further details with respect to this action, see the application for amerdment dated March 17, 1988, which is available for oublic inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D. C.

20555, and at the Board of Supervisors Office, Louisa County Courthouse, Louisa, Virginia 23093 and the Alderman Library, Manuscripts repartment, University of Virginia, Charlottesville, Virginia ??901.

Dated at Rockville, Maryland, this 22nd day of March, 1988.

FOR THE NUCLEAR REGULATORY COWISSION bkv1b.5 Leon B. Engle eject Manager Project Direc ra e 11-7 Division of Rea r Projects I/II Office of Nuclear Reactor Regulation l