ML19327A884

Amend 122 to License DPR-72,replacing Figures 6.2-1 & 6.2-2 W/Narrative Descriptions & Requirement That Members of Plant Review Committee Have Specific Job Titles W/Supervisors from Various Disciplines

ML19327A884
Person / Time
Site:	Crystal River
Issue date:	10/10/1989
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML19327A885	List: ML19327A884 ML19327A886
References
NUDOCS 8910180357
Download: ML19327A884 (10)

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION j

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FLORIDA POWER CORPORATION-CITY OF ALACHUA i

CITY OF BUSHNELL o

CITY OF GAINE5VILLE t

CITY OF KISSIMMEE i

T CITY OF LEE 5 BURG

. CITY OF-NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES NRT!3TOTARD CITY OF ORLANDO -

SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.

CITY OF TALLAHASSEE DOCKET NO. 50-302 L

CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.122-License No. DPR-72 4-1.

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

'A.

The application for amendment by Florida Power Corporation, et al.

(the licensees) dated July 26, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission'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 (1) that the activities authorized by this amendannt 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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Accordingly, the license is amended by changes to the Technical 2.-

7 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License' No. DPR-72 is hereby amended to read as follows:'

Technical' Specifications L

- The Technical Specifications contained in Appendices A and B, as

' revised through Amendment No.122, are hereby incorporated in the license.

Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and

- shall be implemented within 30 days e.' issuance.

FOR THE NUCLEAR REGULATORY COMMISSION rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation -

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Attachment:

Changes to the Technical

-t Specifications Date of Issuance:

October 10, 1989 J

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ATTACHMENT TO LICENSE AMENDMENT NO.122 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302

~ Replace the following pages of the Appendix "A" Technical' Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 6-1 6-1 6-la 6-la 6-2 6-3 6-5 6-5 L

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY-

- i 6.1.1"The Director, Nuclear Plant Operations shall be responsible for overall facility operation and shall delegate in writing-the succession to' this

-responsibility during his absence.

6.1.2 The Director, Nuclear Plant Operations shall be responsible for an annual fire protection inspection which shall be performed utilizing either qualified offsite licensee persohnel-or an outside fire protection firm. The inspection shall consist of:

a) an inspection of safety related areas of the Plant to i

verify that they are-in conformance with the fire hazards analysis; and b) a review of the Fire Brigade organization, training, and drills to verify their conformance with the requirements of.Section 27 of the NFPA Code-1976.

i 6.1.3 The. Director, Nuclear Plant Operations shall be responsible ~ for an inspection of the fire protection program to de performed by a qualified outside fire consultant at least once per 36 months.

6.2 ORGANIZATION.

l-0FFSITE 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting.the safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through l

p intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the form of organization

charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the Final Safety Analysis Report.

b.

The Director, Nuclear Plant Operations shall be re'ponsible for overall s

Unit safe operation and shall have control over those onsite activities p

necessary for' safe operation and maintenance of the plant.

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CRYSTAL RIVER - UNIT 3 6-1 Amendment No. 5,73,75,777,122

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The Vice President, Nuclear-Operations shall-. have corporate-responsibility for overall-plant-nuclear safety and-shall take any a

measures needed to.- ensure acceptable performance of the staff - in eperating, maintaining, and providing technical support to the plant i

to ensure nuclear safety

-d.

.The individuals who train th'e' operating staff and those who carry out

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health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient 4

organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF 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.

on site when fuel'is in the reactor.

All CORE ALTERATIONS after the initial fuel loading shall be directly e.

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 5 members of the minimum shift crew necessary-for' safe shutdown-of the unit and any personnel. required for other essential functions during a-fire emergency, g.

The shift supervisors shall hold a senior reactor operator license.

The operators required to have a license shall hold at least a reactor operator license.

Fire. Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

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L CRYSTAL RIVER - UNIT 3 6-la Amendment No. Zf, 122

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M ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUAllelCATIONS

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6.3 FACI,LITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of AN$1 N18.1-1971 for comparable positions, except for the Chemistry and Radiation Protection Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Operations Technical Advisor, who shall have a Bachelor's I

degree, or the equivalent, in a scientific or engineering discipline i

with specific training in plant design and response and analysis of the plant for transients and accidents.

6.4 TRAINING.

6.4.1 A retraining and replacem>nt training program for the facility staff shall be maintained under the direction of the Vi:e President, Nuclear Operations and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1 1971 and 10 CFR Part 55.

l 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Vice President, Nuclear Operations and shall meet or exceed the requirements of Section 27 of the NFPA Code 1976. except for Fire Brigade training sessions which shall be held at least quarterly, 6.5 REVIEW AND AUDIT m

6.5.1 PLANT REVIEW COMMITTEE (PRC)

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FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Director, Nuclear Plant Operations- (DNPO) on all matters related to nuclear i

safety.

COMPOSITION I

6.5.1.2 The Plant Review Committee shall be composed of nine members and one chairman from Nuclear Operations Supervisory Personnel responsible for the following areas:

operations, health

physics, security, meintenance, modifications, engineering, nuclear safety, and quality.

These positions will be designated by the DNPO in Administrative Procedures.

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; no more than two alternates shall participate as voting members in PRC activities at any one time.

MEETING FRE00ENCY TAI 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman or his designated alternate.

CRYSTAL RIVER - UNIT 3 65 AmendmentNoI.IS.IA.58.51, 111,122

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m:.-u.f f %. $--$ &7.Q--9:,' I a, 2 . w ~ ,fy J-W-.. ~ ^ .h.;.h,]:'?.$;...m,!:N ( ?A5l&2~& l.Y, .e a., my ;. svN~k&$* ' ' GQ.-4 g4 O%.h i ADR!ntffRht!?E CONff48~ e -r a m cs i a nnimessema ssumammr E rn; ;-i i . _ %;rQ. -JD 6 ny ' y.. - *:' : 34~ _): QUQgQg.77 y. }-  ;- [: Yg3ium o't the PRC shall consist of the Chairman or his designated _; i 6.5.1.5 ~ alternate and five aesbers including alternateo. i RE!POM11RILITIES j i 6.5.1,.6 The plant Review Consittee shall be responsible for ~~ a. Review of 1) all procedures and changes thereto as. required by' ' f U Specification 6.4.2, 2) and other proposed procedures or changes l thereto as determined by the Director,-Muclear plant Operations ' l' to a!!ect nuclear safety. i b. Review of all proposed tests and esperiments that affect nuclear safety. l c. Review of all proposed changes to the Appendia

• A'" Technical i
• pecifications.

i d. Mview of all proposed changes or modifications to plaat systees-or equipment that af fect nuclear safety, and changes to raduaste systems which cculd significantly alter their ability to seet Appendia I. e. Investigation of all violations of tho' Technical Specifications I ancluding the review and forwarding of reports covering l evaluation and recommendations to prevent recurrerte to the Vice president, Nuclear Operations and to the Chairman Of the Wuclear General Review Consittee. 3 f. Review of all REPORTABLE EVENTS. l L g. Review of f acility operations to detect potential nuclear safety j l harards. l h. performance of special reviews, investigations, or analyses and reports thereon as requested by the Chairman of the Nuclear General Review Consittee. i Review of the plant Security plan and implementing procedures. j. Review of the Energency plan and implementing procedures. l CRYSTAL RIVER - UNIT 3' 6-6 Amendment No. p.25.57.ff.

99. 111 NAY. 51989 J.. - -...-

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