ML20072C149

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Amend 178 to License DPR-65,revising TSs to Change Administrative Controls Section to Require Individual Who Serves as OM to Hold Plant SRO License
ML20072C149
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/11/1994
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co
Shared Package
ML20072C151 List:
References
DPR-65-A-178 NUDOCS 9408170100
Download: ML20072C149 (6)


Text

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a%g UNITED STATES g

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20565-0001

'+9 +. * * *,o NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.178 License No. DPR-65 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated Junr. 24, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cunmission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordanca with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

i 9408170100 940811 PDR ADOCK 05000336 p

PDR

, 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.178, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION FT F.StlIz,Direc r

P oject Directorate

-4 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 11, 1994 8

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ATTACHMENT TO LICENSE AMENDMENT N0.178 FACILITY OPERATING LICENSE N0. DPR-65 DOCKET N0. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 6-2 6-2 6-3 6-3 i

't

i ADMINISTRATIVE CONTROLS FACILITY STAFF (CONTINUED) d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

(Table 6.2-1) e.

ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Opera-tor or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times.

(Table 6.2-1) The Fire Brigade shall not include 2 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

g.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).

6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:

a.

If the Operations Manager does not hold a senior reactor operator license for Millstone Unit No. 2, then the Operations Manager shall have held a senior reactor operator license at a Pressurized Water Reactor other than Millstone Unit No. 2 and an individual serving in the capacity of the Assistant Operations Manager shall hold a senior reactor operator license for Millstone Unit No. 2.

b.

The Shift Technical Advisor (STA) who shall meet the requirements of Specification 6.3.1.b.1 or 6.3.1.b.2.

1.

Dual-role individual: Must hold a senior reactor operator's license at Millstone Unit No. 2, meet the STA training criteria of NUREG-0737, Item I.A.1.1, and meet one of the following educational alternatives:

a.

Bachelor's degree in engineering from an accredited institution, b.

Professional Engineer's license obtained by the successful completion of the PE examination; i

Millstone - Unit 2 6-2 Amendment No. J77. JJ7, JJ7,178 0163

ADMINISTRATIVE CONTROLS c.

Bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mathematical, or engineering sciences; d.

Bachelor's degree in a physical science from an accredited institution, including course work in the physical, mathematical, or engineering sciences; e.

Successful completion of the Memphis State University (MSU) STA program.

(Note:

This alternative is only acceptable for individuals who have completed the program prior to December 31, 1986); or f.

Successful completion of the Thames Valley State Technical College associate's degree in Nuclear Engineering Technology program, provided that the individual was enrolled in the program by October 1, 1987.

2.

Dedicated STA: Must meet the STA training criteria of NUREG-0737, Item I.A.1.1, and have received specific training in plant design, and response and analysis of the plant for transients and accidents.

c.

The Health Physics Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1.

1 1

M,,ijlstone. Unit 2 6-3

" **"# NO 191,Jpp,373 j

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