ML17342B194

Proposed Tech Specs,Revising Section 6, Administrative Controls to Delete Figure 6.2-1 & 6.2-2 & Replace W/More General Organizational Requirements

ML17342B194
Person / Time
Site:	Turkey Point
Issue date:	02/19/1988
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17342B193	List: ML17342B191 ML17342B194
References
NUDOCS 8802290064
Download: ML17342B194 (19)

Text

ATTACHMENT 2 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES PDR P -. 'DR 8802290064 8802i9,I ADOCK 05000250 TCG4/024/7

I A CHMENT TO LICENSE AMENDM TURKEY POINT UNITS 3 AND 4 Docket Nos. 50-250 and 50-25 I Marked-up Technical Specification Pages VI 6-I Figure 6.2- I Figure 6.2-2 Table 6.2- I 6-5 6-7 6-8 6-9 6-l4 TCG4/024/8

I' LIST OF FIGURES

~Fi ure Title 2.1-1 Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation 2.l-la Deleted 2.1-1b Deleted 2.1-2 ~ Reactor Core Thermal and Hydraulic Safety L'imits, Two Loop Operation 3.1-1 DOSE EQUIVALENTI-131 Primary Coolant Specific Activity Limit Versus Percent of RATED POWER with the Primary Coolant Specific Activity > 1.0 P Ci/gram Dose Equivalent I-131 3.l-la Reactor Coolant System Heatup and Cooldown Pressure Limits 3.1-lb Reactor Coolant System Heatup and Cooldown Pressure Limits 3.l-lc Reactor Coolant System Heatup and Cooldown Pressure Limits

3. 1-id Reactor Coolant System Heatup and Cooldown Pressure Limits 3.1-2 Radiation Induced Increase in Transition Temperature for A302-B Steel 3.1-2c Radiation Induced Increase in Transition Temperature for A302-B Steel 3.1-2d Radiation Induced Increase in Transition Temperature for A302-B Steel 3.2-1 Control Group Insertion Limits for Unit 0, Three Loop Operation 3.2-la Control Group Insertion Limits for Unit 0, Two Loop Operation 3.2-lb Control Group Insertion Limits for Unit 3, Three Loop Operation 3.2-lc Controi Group Insertion Limits for Unit 3, Two Loop Operation 3.2-2 Required Shutdown Margin 3%2 3 K (z) vs Core Height 3i2 3a Deleted 3.2-0 Maximum Allowable Local KW/FT 0.12-1 Sampling Locations 5.1-1 FPL Turkey Point Site Area Map 6.2-1 6.2-2 B3.1-1 Effect of Fluence and Copper Content on Shift of RTNDT for Reactor Vessel Steels Exposed to'550 F Temperature B3.1-2 Fast Neutron Fluence (E > 1MEV) as a function of Effective Full Power Years B3.2-1 Target Band on Indicated Flux Difference as a Function of Operating Power Level B3.2-2 Permissible Operating Band on Indicated Flux Difference as a Function of Burnup (Typical)

<<vg>> Amendment Nos. 123 and l16

6.0 ~ . ADMINISTRATI CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager - Nuclear shall be responsible for overall licensed facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 C)QSITW A~A 0 n5 R&an &AWOKE ad-technic~

6.2.2 FACILITYSTAFF

~b'~+She Q llouoin The Facility organization shall be

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 trip.

Amendment Nos and

p An onsite and an offsite organization shall be established-for<

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operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

Liges of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. Those re-lationships shall be documented and updated; as appropriate, in the form of organizational charts. These organizational charts will be documented in the ~and updated in accordance with 10 CFR 50. 54+(g)

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b. There shall be an individual executive position (corporate officer) in the offsite organization having corporate responsibility for overall plant nuclear safety. This individual shall take any measures needed 'to ensure acceptable 'performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.

c. There shall be an individual management position in the onsite organiza-tion having responsibility for overall unit safe operation and shall have

, . control over those onsite resources necessary for safe operation and maintenance of the plant.

d. Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

e. Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the health physics manager shall have direct access to that onsite individual having responsibility for overall unit management.

Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

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MfFt&NSTICWOA Amendment Nos 123 and116

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TABLE 6.2-1 UM SI'iIFT CREW COMPOSITIO LICENSE CATEGORY ONE OR TW'O QUALIFICATIONS UMTS OPERATINGA ALL UNITS SHUTDOWN SRO%

RO 3 Non-Licensed Auxiliary rators Shift Technical Advisor 1+ None Required

+ This position may be filled by one of the SROs above, provided the individual meets the qualification requirements of 6.3.1.

Includes the licensed Senior Reactor Operator serving as Shift Supervisor.

Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising the movement of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel.

Operating is defined as Keff 20.99, 96 thermal power excluding decay heat greater than or equal to zeros and an average coolant temperature Tavg ? 200 F.

Shift cr'ew composition may be one 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 on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

Amendment Nos. 123 and 116

An individual qualified in radiation~rotection procedures shall be on site when fuel is in the reac>>

e. ALL CORE ALTERATIONS 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 shift crew necessary for safe shutdown of the unit and any personnel required for other we. 6 a. eM Supe v-vt5gr +al) g~g, a Eev io~

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63 FACILITYSTAFF UAL CATIO P ectly' 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 the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents.

6.3.2 Health Ph sics isor ications 6.3.2.1 The Health Physics Supervisor at the time of appointment to the position, shaH, except as indicated below, meet the followingi He shall have a bachelor's degree or equivalent in a science or engineering subject, including some formal training in radiation protection.

2. He shall have five years of professional experience in applied radiation protection; where a master's degree in a related field is equivalent to one year experience and a doctor's degree in a related field is equivalent to two years of experience.

3. Of his five years of experience, three years shall be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to

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those encountered at Turkey Point Plant.

6.3.22 %hen the Health Physics Supervisor does not meet the above requirements, compensatory action shall be taken which the Plant Nuclear Safety Committee determines and the< NRC Office of Nuclear Reactor Regulation concurs that the. action meets the intent of Specification..

6.3.2.1.,

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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 accomodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

Amendment Nos. 123 and ll6

1.5 QUORUM t

A quorum of the PNSC shall consist of the Chairman or yice Chairman and four (0) members including alternates.

6.5.1.6 RESPONSIBILITIES The Plant Nuclear Safety Committee shall be responsible for:

a. Review of 1) all procedures and changes thereto required by Section 6.8 and 2) any other proposed procedures or changes thereto as determined by the Plant Manager - Nuclear to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to the Technical Specifications in Appendix A of the license.

d. Review of all proposed changes or modifications to plant systems or equipment that 'af feet nuclear saf etym

e. Investigation of all violations of the Technical Specifications and preparation and forwarding a report covering evaluation and recommendations to prevent recurrence to the Ope Enology and to the Chairman the Company Nuclear Review Board.

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~v Amendment Nos.123 and 116

t Review of facility oper safety hazards.

ns to detect potential

g. Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Company Nuclear Review Board.

h. Review of the Plant S urity Plan and implementing procedures and submitting recommended changes to the Chairman of the Company Nuclear Review Board.

i. Review of the Emergency Plan and implementing procedures and submitting recommended changes to the Chairman of the Company Nuclear Revie~ Board.

j. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

k. Review of all REPORTABLE EVENTS.

6.9 1.7 AUTHORITY The Plant Nuclear Safety Committee shall<

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a. Recommend to the Plant Manager - Nuclear writte~

approval or disapproval (ln minutes of PNSC meeting of items considered under 6.$ .1.6(a) through (d) j above.

b. Render determinations in writing (in minutes of PNSC meetings) with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes r iewed safety question.

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c. Provide written notification to the Viee-and the Com any Nuclear Review Board of disagreement between the PNSC and the Plant Manager - Nuclear; however, the Plant Manager - Nuclear shall have responsibility for resolution of such disagreements pursuant to 1.1 above.

gg ~ +VS'M Qepr 0 Amendment Nos. 123 and 116

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~ ~ RECORDS ~r<OW~Or<~ ~pleo.v c4 i0-v The plant Nuc ar Safety ommittee shall maintain written minute of each meeting and copies shall be provided to the and Chairman of thc Company Nuclear Review Board.

6 54 COMPANY NUCLEAR REVIEW BOARD (CNRB) 6.5.2.1 FUNCTION The Company Nuclear Review Board shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations.

b. Nuclear engineering.

c. Chemistry and radiochemistry.

d. Metallurgy.

e. Instrumentation and control.

f. Radiological safety.

g. Mechanical and electrical engineering.

h. Quality assurance practices.

6.5.2.2 COMPOSmON The C all ec o Qem~v Sav4ev- U'see d

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2. Member: Vice President - Nuclear

3. Member: Vlcc President - Engineering, Prol Management, and Constr uction

0. Member: Chief Engineer - Power Plant Engineering

5. Member: Director - Nuclear Licensing

6. Member: . Director - Quality Assurance

7. Member: Manager - Nuclear Energy Services

8. Member: ' r - Nuclear Fuels

9. Member: Manager - Power Plant Eny cerning 10; Member: Group Vice President

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i@A.fief Amendment Nos. 123 and 116

6.6 ~

• REPORTABLE E' ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PNSC, and the results of this review shall be submitted to the CNRB, o d +he Wri>~

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6.7 SAFETY LIMITVIOLA 0 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36(cXIXi) shall be complied with immediately.

b. The Safety Limit violation shall be reported immediately to the Commission, the. c42v" and to the CNRB. s Co A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PNSC. This report shall describe 1) applicable circumstances preceding the violation,

2) effects of the violation upon facility components, systems or structures, and 3) corrective action tak t re t c4ae 6& p&<oW AUc&ILw~cev

d. The Safety mit Violation Report shall be submitted to the CNRB, th and the Commission within ten (10) days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5.1 and 5.3 of ANSI NIL7-I972, Appendix "A" of USNRC.Regulatory Guide 1.33, PROCESS CONTROL . PROGRAM, OFFSITE DOSE CALCULATION MANUAL, Quality Control Program for effluent monitoring using the guidance in Regulatory Guldens'1.21, Revision 1, Dune 1970, Quality Control Program for environmental .

monitoring using the guidance in Regulatory Guide 0.1, Revision 1, April 1975, and the Facility Fire Protection Program except'as" provided in 6.8.2 and 6.8.3 below.

Amendment Nos. 123 and 116