ML20248E902

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Amend 125 to License DPR-35,deleting Onsite & Offsite Organization Charts from Tech Spec Section 6.0 Per Generic Ltr 88-06
ML20248E902
Person / Time
Site: Pilgrim
Issue date: 09/25/1989
From: Wessman R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248E903 List:
References
GL-88-06, GL-88-6, NUDOCS 8910060097
Download: ML20248E902 (7)


Text

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g4-UNITED STATES j

k NUCLEAR REGULATORY COMMISSION j'

WASHINGTON. D. C,20655 k..... pf BOSTON. EDISON COMPANY DOCKETNO.50-2p PILGRIM NUCLEAR-POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 0

License No. DPR-35 1.

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

j A.

The application for amendment filed by the Boston Edison Company (thelicensee)datedJuly 31, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

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 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 set forth in 10 CFR Chapter I; 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly,-the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

, 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 its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION NL:

wuses Richard H. Wessnan, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

SEP 2 5 %29 i'

ATTACHMENT TO LICENSE AMENDMENT NO. 125 FACILITY OPERATING LICENSE 140. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical. Specifications with 1

the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

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Remove Insert 208 208 208a 208a 209 209 210 210 l

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d.'0 l ADMINISTRATIVE CONTROLS

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6.1 RESPONSIBILITY The Station Director shall be accountable for overall facility-1 operation.

In his absence, the Station Director shall designate, in writing, the individual to assume this responsibility.

i 6.2 ORGANIZATION l

A.

OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

1.

Lins of authority, responsibility, and communication shall be e nablished and defined for the highest manyEment levels through intermediate levels to and including all operating organ 17ation positions.

These relationships shall be docume-d and updated, as appropriate, in the form of organi.M : ion charts, functional descriptions of departmental respons'ailities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in Pilgrim Station Final Safety Analysis Report.

2.

The Station Director shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

3.

The Senior Vice President - Nuclear shall have corporate responsibility for overall plant nuclear safety and shali take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical supnort to the plant to ensure nuclear safety.

4.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

B.

FACILITY 1.

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

Amendment No. 69, 80, BB, J77,125 208

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'i6.0 ADMINISTRATIVE CONTROLS d

2.

When the unit is in an operational mode other than cold

~ hutdown or refueling, a person holding a Senior Reactor s

u Operator License shall be present in the control room at all-g times. In addition to this Senior Operator, a Licensed s

Operator or Senior. Operator shall be present at the controls when fuel is in the vessel.

3.

At least two Licensed Operators shall be present in the control room during reactor startup, schedaled reactor shutdown and during' recovery from reactor trips.

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

5.

ALL CORE ALTERATIONS performed while fuel is in the reactor vessel after the initial fuel loading shall be directly supervisad by either a licensed Senior Reactor Op6rator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

6.

A Fire Brigade of 5 members including a Fire Brigade Leader shall be maintained on site at all times.- This excludes 3 members of the minimum shift crew necessary for safe shutdown and any personnel required for other essential functions during_

a fire emergency.

7.

The Technical Section Manager, Chief Operating Engineer, Nuclear Watch Engineers,.and Nuclear Operations Supervisors shall hold a Senior Reactor Operator License. _The Nuclear Plant Reactor Operators shall hold a Reactor Operator License.

6.3 FACILITY STAFF 00ALIFICATIONS The qualifications with regard to educational and experience backgrounds of the facility staff at the time of appointment to the active position shall meet the requirements as described in the American National Standards' Institute N18.1-1971, " Selection and Training of Personnel for Nuclear Power Plants." In addition, the individual performing the function of Radiation Protection Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September,1975.

6.4 TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Department Manager.

The training programs for the licensed personnel shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10CFR Part 55. The training programs for the Fire Brigade shall meet or exceed the requirements of NFPA Standard No. 27-1975 " Private Fire Brigade".

Fire Protection Training sessions will be held quarterly.

I Amendment No. U, 46, D, 88, J77,125 208a

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This Page Intentionally Left Blank Acendment No. 74. gg, Jyy,125 209

,r-I This Page Intentionally left Blank i,

Amendment No. 74, EE ///2,125 210

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