ML20136E391

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Amends 71,108 & 106 to Licenses DPR-61,DPR-21 & DPR-65, Respectively,Adding Subparagraph 6.2.2.g to Tech Specs Re Procedures Governing Use of Overtime Which Follow General Guidance of NRC Policy Statement on Working Hours
ML20136E391
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 12/10/1985
From: Charemagne Grimes, Thadani A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20136E351 List:
References
TAC-55328, TAC-59258, NUDOCS 8601060533
Download: ML20136E391 (14)


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e UNITED STATES 8,

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t CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-61 1.

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

i A.

The application for amendrnent by Connecticut Yankee Atomic Power Company, (the licensee), dated July 9, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

F.

and the Comission'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 Comission; 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 Comission's regulations; D.

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

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

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8601060533 851210 PDR ADOCK 05000213 P

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Accordingly, the license is amended by changes to the Technical' Specifications as indicated in the attachment to this license I

amendment and Paragraph 2.C(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B revised through Amendment No. 71, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION Cu>m4-I. Cgh

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Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate t

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Attachment:

Changes to the Technical Speci,fications i

Date of Issuance: December 10, 1985

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. ATTACHMENT TO LICENSE AMENDMENT NO. 71 I

FACILITY OPERATING LICENSE NO. DPR-61 i

DOCKET N0. 50-213 7

Replace the fc) lowing pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendnent number h'

and contain vertical lines indicating the area of change.

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ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued) 9 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).

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6-la Amendment No. 71

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4 UNITED STATES E

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The CONNECTICUT LIGHT AND POWER COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPANY AND NORTHEAST NUCLEAR ENERGY COMPANY l

MILLSTONE NUCLEAR POWER STATION, UNIT N0. 1 DOCKET N0. 50-245 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.108 License No. DPR-21 1.

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

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A.

The application for amendment by the Connecticut Light and Power Company, Western Massachusetts Electric Company and Northeast Nuclear Energy Company (the licensees), dated July 9,1985 complies with the standards and requirements of the Atomic Energy Act 1954, as amended (the Act), and the Comission's rules and regulations F. -

set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, L

the provisions of the'Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the common f'

defense and security or to the health and safety of the' public; and E.

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

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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 Provisional Operating License No. DPR-21 is hereby amended to read as follows:

i (2) Technical Specifications t

The Technical Specifications contained in Appendices A and B as revised through Amendment No. 108, are hereby 3

incorporated in the license. The Northeast Nuclear with L

the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION s-CueM I.

Christopher I. Grimes, Directo Integrated Safety Assessment Project Directorate Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications

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Date of Issuance: December 10, 1985 r

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ATTACHMENT TO LICENSE AMENDMENT N0.108 PROVISIONAL OPERATING LICENSE NO. DPR-21

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DOCKET NO. 50-245 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

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6-1 6-1 6-la 6-la f.

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6.0 ADMINISTRATIVE CONTROL.5 i

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6.1 RESPONSIBILITY 6.1.1 The Station Superintendent shall be responsible for overall eperation of i

the. I!!stene Station Site while the Unit Superintendent shall be rerpensible for M

cpera-ion of the unit. The Station Superintendent and Unit Superintendent shaU each delegate in writing the succession to these responsibilities during their absence.

l 6.2 ORC ANIZATION OFFSITE 6.2.1 The Offsite organization for' facility management and technical support shall be as shown on Figure 6.2-1.

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FACILITY STAFF 6.2.2 The Facility organization shallbe as shown on Figure 6.2-2 and:

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Each on dutf shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

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At least one licensed Operator shall be in the control room whe52uel is in the reactor.

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At least two licensed Operators shaU be present in the control room

[,7 during reactor start-up, scheduled react 6r shutdown and during recovery from reactor trips.

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An individual qualified in radiation protection procedures shall be on site when fuells'in the reactor.#

e.

ALL CORE AL ERATIONS after the initial fuel loading shall be directly supervised by either a licens'ed Senior Reactor Operator or

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Senior Reactor Operator Limited to Fuel Handlin who has no other concurrent responsibilities during this operation, r

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A site Fire Brigade of at least 5 members shall be maintained onsite at all times.# The Fire Brigade shall not include 2 members of the minimum shift' crew necessary tor safe shutdown of the unit or any personnel required '.for other essential functions during a 11re emergency.

g.

Administrative procedures shall be developed and

'i implemented to limit the working hours of unit

'l staff who perform safety-related functions. These l

Procedures should follow the general guidance of the NRC Policy Statement.on working hours (Generic Letter No. 82-12).

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t/ lee. Note on Page 6-4.

Amendment No. MS$66l76t(. E 108

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l 6.3 FACILITY STAFF QUALIFICATIONS

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i 6.3.1 Each member of the facility staff shall meet or exceed the minimum quaiifications of ANSI N18.1-1971 for comparable positions, except for (1) the i

Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, and (2) the Shift Technical Advisor who snall

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have a Bachelor Degree or equiv'alent in a scientific or engineering discipline l

with specific training in plant design, and response and analysis of the plant

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fcr transients and accidents.

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!i 6-la Amendment No. 95,108 l

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UNITED STATES 8

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k NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT 'AND POWER COMPANY l

THE WESTERN MASSACHUSETTS ELECTRIC COMPANY I

DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 106 License No. DPR-65 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated July 9,1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations

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set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the l

Comission; L

C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon g

defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Comission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by chances to the Technica1

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Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby I

amended to read as follows:

(2) Technical Specifications L

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106, are hereby incorporated in the l

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 hshok C. Thadani, Director t

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PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: December 10, 1985 r

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ATTACHMENT TO LICENSE AMENDMENT N0.106 5

FACILITY OPERATING LICENSE N0. DPR-65 DOCKET NO. 50-336 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is provided to maintain document completeness.

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Superintendent shall be responsible for overall operation of i

the Millstone Station Site while the Unit Superintendent shall-be responsible for operation of the unit. The Station Superintendent and Unit Superintendent shall each delegate in writing the succession to these responsibilities during their i

absence.

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6.2 ORGANIZATION OFFSITE L

6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

I FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in' Table 6.2-1.

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips, d.

An individual qualified in radiation protection procedures shall be o'n site when fuel is in the reactor.#

e.

All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator 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.# The Fire Brigade shall not include 2 members of the minimum shif t 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 Statementonworkinghours(GenericLetterNo.82-12).

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions, except for (1) the Radi-I ation Protection Manager who shall meet or exceed the qualifications of Regula-i tory Guide 1.8, Revision 1, and (2) the Shift Technical Advisor who shall have a i

Bachelor Degree or equivalent in a scientific or engineering discipline with I

specific training in plant design and response and analysis of the plant for l

transients and accidents.

  1. See Note on Page 6-4.

MILLSTONE - UNIT 2 6-1 Amendment No. #5.66.78.92. 106

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  • Overall Corporate Responsibility for Fire Protection j.
    • Provides Operating and Engineering Support by Contractual Arrangement r

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