Text

Amends 126 & 65 to Licenses DPR-67 & NPF-16,respectively, Changing TS Section 6.0, Administrative Controls
	ML17228A474
Person / Time
Site:	Saint Lucie
Issue date:	03/02/1994
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
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ML17228A475	List: ML17228A474; ML17228A476;
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UNITED STATES NUCLEAR REGULATORY COIVlMISSION WASHINGTON. O.C. 20555.0001 FLORIDA POWER Ei LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No.

DPR-67 1.

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

A.

The application for amendment by Florida Power 5 Light Company, et al. (the licensee),

dated June 21,

1993, 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 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 accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, Facility Operating License No.

DPR-67 is amended by changes to the Technical Specifications. as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 126, 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 its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 2, 1994 rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

~I

ATTACHMENT TO LICENSE AMENDMENT NO.

126 TO FACILITY OPERATING LICENSE NO.

DPR-67 DOCKET NO. 50-335 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 area of change.

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

Remove Pa es 6-1 6-5 6-6 6-7 6-8 6-13 6-14 Insert Pa es 6-1 6-5 6-6 6-7 6-8 6-13 6-14

6. 0 ADMINISTRATIVE CONTROLS

6. 1 RESPONSIBILITY

6. 1. 1 The Plant General Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the control room a

designated individual, shall be responsible for the control room command function.

A management directive to this effect, signed by the President-Nuclear Division, shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZA ION ONSITE AND OFFSITE ORGANIZATION 6.2. 1 An onsite and an offsite organization shall be established for unit operation and corporate management.

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

'a ~

b.

C.

d.

e.

Lines 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 relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the Topical guality Assurance Report and updated in accordance with 10 CFR 50.54(a)(3).

The President Nuclear Division shall be responsible 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.

The Plant General Manager shall be responsible for overall unit safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

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.

Although health physics individuals may report to any appropriate manager onsite, for matter s relating to radiological health and safety of employehs and the public, the Health Physics Supervisor 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.

ST.

LUCIE UNIT I 6-1 A,d, t N

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6. 0, ADMINISTRAT CONTROLS S 00 S S S 0 8 S S 8s S S S S s S 00 0 8 0 0 ZS 00 0 R S 0 4 0 2$ S 0 8 s 0 8 R0 0 S 4~gg~g ~ ~g ~ ~~ ~ ~ g g gg ~ g g g ~ +++++++

6~66666 AT 6 (6 tt d)

~66 T TATA 6.2.2 The unit organization shall be subject to the following:

a.

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

b.

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

In addition, while the reactor is in NODE I, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

c.

A health physics technician$ shall be on site when fuel is in the reactor.

d.

All CORE ALTERATIONS shall be observed by a licensed operator and 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.

The SRO in charge of fuel handling normally supervises from the control room and has the flexibilityto.directly supervise at either the refueling deck or the spent fuel pool.

SThe health physics technician may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accomaodate unex-pected

absence, provided immediate action is taken to fill the required positions.

ST.

LUCIE - UNIT 1 6-2 d Ad.~ ttt JU.'J 1 1 19"2

6.0 ADMINISTRATIVE CONTROLS Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g.,

senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

l.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2.

3.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work

periods, including shift turnover time.

4.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant General Manager or his deputy, or higher levels of management, in accordance I

with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individ-ual over time shall be reviewed monthly by the Plant General Manager or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

g.

The Operations Supervisor shall hold a Senior Reactor Operator license.

SHIFT TECHNICAL ADVISOR 6.2.3 The'hift Technical Advisor function is to provide on shift advisory technical support in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

ST.

LUGIE UNIT I 6-5 Amendment No. 69-,9."~,126

6. 0 ADMINISTRATIVE CONTROLS

'.3 UNIT STAFF UALIFICATIONS 6.3. 1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS-3.1-1978, except for (1) the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8.,

September

1975, and (2) the Shift Technical Advisor who shall have a

bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design and plant operating characteristics, including transients and accidents.

6. 4 TRAINING 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS-3.1 1978 and 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 FACI ITY REVIEW GROUP FRG)

FUNCTION 6.5. 1. 1 The Facility Review Group shall function to advise the Plant General Manager on all matter s related to nuclear safety.

COM OSI ION 6.5. 1.2 The FRG shall have voting members composed of individuals from each of the following disciplines:

Operations Reactor Engineering Health Physics Chemistry Licensing Instrument and Control Electrical Maintenance Mechanical Maintenance Technical Support guality Assurance/Control Services The Plant General Manager shall appoint the FRG members, in writing, and from this membership shall designate, in writing, an FRG Chairman.

Members shall meet or exceed the qualifications required for Managers, Super-visors, or Professional-Technical, as appropriate, pursuant to Specifica-tion 6.3. 1.

ST.

LUGIE UNIT 1 6-6 Amendment No

>%-3;~126

6. 0 ADHINISTRATIVE CONTROLS ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the FRG Chair-man to serve on a temporary basis;

however, no more than two alternates shall participate as voting members in FRG activities at any one time.

ETING FRE UENCY 6.5. 1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.

QUORUM 6.5. 1.5 The quorum of the FRG necessary for the performance of the FRG responsibility and authority provisions of, these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5. 1.6 The Facility Review Group shall be responsible for:

'a ~

b.

c ~

d.

e.

Review of (1) all procedures required by Specification 6.8 and changes

thereto, (2) all programs required by Specification 6.8 and changes

thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant General Manager to affect nuclear safety.

Review of all proposed tests and experiments that affect nuclear.

safety.

Review of all proposed changes to Appendix A Technical Specifications.

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the President-Nuclear Division and to the Chairman of the Company Nuclear Review Board.

f.

Review of all REPORTABLE EVENTS.

g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant General Nanager or the Company Nuclear Review Board.

ST.

LUGIE UNIT 1 6-7 d

d t

N

6. 0 ADMINISTRATIVE CONTROLS i.

Review of the Security Plan and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.

j.

Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.

k.

Review of every unplanned on-site release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the President Nuclear Division and to the Company Nuclear Review Board.

l.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RADWASTE TREATMENT SYSTEMS.

m.

Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last FRG meeting.

n.

Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.

~UTHORITY 6.5.1.7 The Facility Review Group shall:

a.

Recommend in writing to the Plant General

Manager, approval or disapproval of items considered under Specifications 6.5.1.6.a through d above.

b.

Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6 a, b, d, and e

above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s to the President-Nuclear Division and the Company Nuclear Review Board of disagree-ment between the FRG and the Plant General Manager;

however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6. 1. 1 above.

R CORDS 6.5. 1.8 The Facility Review Group shall maintain written minutes of each FRG meeting that, at a minimum, document the results of all FRG activities performed under the responsibility and authority provisions of these Technical Specifications.

Copies shall be provided to the President-Nuclear Division and the Chairman of the Company Nuclear Review Board.

ST.

LUCIE UNIT 1

6-8 Amendment No.

.126

6. 0 ADMINISTRATIVE CONTROLS c.

The Safety Limit Violation Report shall be submitted to the Commis-sion, the

CNRB, and the President - Nuclear Division within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8. 1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February

1978, and those required for implementing the requirements of NUREG 0737.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

i.

Quality Control Program for effluent monitoring, using the guidance in Regulatory Guide 1.21, Revision 1; June 1974.

j.

Quality Control Program for environmental monitoring using the guidance in Regulatory Guide 4. 1, Revision 1, April 1975.

I 6.8.2 Each procedure of Specification 6.8. la through i. above, and changes

thereto, shall be reviewed by the FRG and shall be approved by the Plant General Manager prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1a through i.

above may be made provided:

a.

The intent of the original procedure is not altered.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

ST.

LUGI E UNIT 1 6-13 A

d td.~,

A

Jl

6. 0 ADMINISTRATIVE CONTROLS c.

The change is documented, reviewed by the FRG and approved by the Plant General Hanager within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the CNRB at least once per 24 months:

a.

Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a

serious transient or accident to as low as practical levels.

The systems include the Shutdown Cooling System, High Pressure Safety Injection System, Containment Spray System, and RCS Sampling.

The program shall include the following:

(i)

Preventive maintenance and periodic visual inspection require-

ments, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant'Radioiodine Monitorin A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i)

Training of personnel, (ii)

Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.

c.

Secondar Mater Chemistr A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.

This program shall include:

(i)

Identification of a sampling schedule for the critical vari-ables and control points for these variables, (ii)

Identification of the procedures'used to measure the values of the critical variables, (iii) Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, ST.

LUCIE UNIT I 6-14 Amendment No. 6g,126

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER

& LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.

LUCIE PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

65 License No. NPF-16 1.

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

A.

The application for amendment by Florida Power

& Light Company, et al. (the licensee),

dated June 21,

1993, 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 Commi ss10n; 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 accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, Facility Operating License No.

NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:

2.

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 6g

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

FOR THE NUCLEAR REGULATORY COMMISSION He bert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 2, 1994

ATTACHMENT TO LICENSE AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO.

NPF-16 DOCKET NO. 50-389 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 area of change.

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

Remove Pa es 6-1 6-2a 6-6 6-7 6-8 6-9 6-14 Insert Pa es 6-1 6-2a 6-6 6-7 6-8 6-9 6-14

ADMINISTRATIVE CONTROLS

'd.t I dddlld TY

6. 1. 1 The Plant General Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the control

room, a

designated individual, shall be responsible for the control room command function.

A management directive to this effect, signed by the President-Nuclear Division, shall be reissued to all station personnel on an annual basis.

6.

ORGANIZATION 0

S TE A D

FFSITE ORGANIZATIO 6.2.1 An onsite and an offsite organization shall be established for unit operation and corporate management.

This onsite and offsite organization 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 intermediate levels to and including all operating organization positions.

Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the Topical guality Assurance Report and updated in accordance with 10 CFR 50.54(a)(3).

b.

The President Nuclear Division shall be responsible 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.

The Plant General Manager shall be responsible 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 organiza-tional 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 Supervisor 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.

ST.

LUCIE - UNIT 2 6-1 d d, I d

. Id.,dd-,dddd,

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N T TAF 6.2.2 a ~

b.

The unit organization shall be subject to the following:

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

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

In addition, while the reactor is in MODE I, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

c.

A health physics technicianf shall be on site when fuel is in the reactor.

d.

e.

All CORE ALTERATIONS shall be observed by a licensed operator and 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.

The SRO in charge of fuel handling normally supervises from the control room and has the flexf-bility to directly supervise at either the refueling deck or the spent fuel pool.

DEI,ETED

'dministrative procedures shall be developed and implemented to limit the working hours of'nit staff who perfortw safety-related functions;. e.g.,

senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

PThe health physics technician may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accoaaodate unexpected

absence, provided iaeediate action is taken to fill the required positions.

ST.

LUCIE - UNIT 2 6-2 Amendment No. 8955 JUN 1 1 1992

ADMINISTRATIVE CONTROLS

'NIT STAFF (Continued) a.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

b.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

c.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work

periods, including shift turnover time.

d.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant General Manager or his deputy, or higher levels of management, in accordance I

with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that

~ individual overtime shall be reviewed monthly by the Plant General Manager or I

his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

g.

The Operations Supervisor shall hold a Senior Reactor Operator License.

ST.

LUCIE UNIT 2 6-2a Amendment No. 89,65

Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH TWO SEPARATE CONTROL ROOMS WITH UNIT 1 IN MODE 5 OR 6 OR DEFUELED POSITION NUMBER OF INDIVIDUALS RE/UIRED TO FILL POSITION MODE 1, 2, 3, or 4 MODE 5 or 6 SS (SRO)

SRO RO AO STA 1a 1

2 2

1 1a None None POSITION WITH UNIT 1 IN MODE 1, 2, 3

OR 4 NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE1,2,3, or4 HODE 5 or 6 SS (SRO)

SRO RO AQ STA 1

2 2

1a None 1

1 None SS Sh)ft Supervisor with a Senior Reactor Operator's License on Un)t 2 SRG -

Indfv)dual with a Sen)or Reactor Operator's Ucense on Unit 2 RO Indkv)dual with a Reactor Operator's License on Un)t 2 AO Aux)1)ary Operator STA -

Shrift Technical Advisor Except for the Shrift Supervisor, the Shrift Crew Compos)t)on may be one less than the min)mum requirements of Table 6.2-1 for a period of t$me not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

$n order to accommodate unexpected absence of on-duty shrift crew members provided faeedkate action

$ s taken to restore the Sh)ft Crew Composftfon to within the m$ n$ mum requirements of Table 6.2-1.

Thfs provision does not permit any shrift crew posit)on to be unmanned upon shift change due to an oncoming shrift crewman be$ ng late or absent.

During any absence of the Sh)ft Supervisor from the Control Room wh)le the un$t is ln HOOE 1, 2, 3 or 4, an fndlv)dual (other than the Sh1ft Techh1cal Advisor} with a val)d SRQ license shall be designated to assume the Control Room command function.

During any absence of the Sh)ft Superv)sor from the Control Room wh$ le the unlt

$ s

$ n HODE 5 or 6, an fndfv)dual with a val)d SRO or RO 1$ cense shall be designated to assume the Control Room coaeand function.

a Individual may f)ll the same pos$ tfon on Un)t 1 b/

One of the two required hnd1v)duals may f111 the same pos1t$ on on Unit 1.

ST. LUt'IE.- UNIT 2 6-5

ADMINISTRATIVE CONT 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP ISEG

~FUNCT ON 6.2.3. 1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of five dedicated, full-time members with varied backgrounds and disciplines related to nuclear power plants.

Three or more of the members shall be engineers with a bachelor degree in engineering or a related science, with at least 2 years of professional level experience in the nuclear field.

Any nondegreed ISEG members will either be licensed as a Reactor Operator or Senior Reactor Operator, or will have been previously licensed as a Reactor Operator or Senior Reactor Operator within the last year at the St. Lucie Plant site; or they will meet the qualifications of a department head as specified in Specification 6.3.1 of the St. Lucie Unit 2 Technical Specifications.

The qualifications of each nondegr eed candidate for the ISEG shall be approved by the Chairman, Company Nuclear Review Board (CNRB) prior to joining the group.

R SPONSIB T

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of selected plant activities to provide independent verification* that these activities are performed correctly and that human errors are reduced as much as practical.

The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety to the Chairman, CNRB.

AUT~HOl~

6.2.3.4 The ISEG is an onsite independent technical review group that reports offsite to the Chairman, CNRB.

The ISEG shall have the authority necessary to perform the functions and responsibilities as delineated above.

RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-tained and a report of the activities forwarded each calendar month to the

Chairman, CNRB.

6.2.4 SH ADV S The Shift Technical Advisor function is to provide on shift advisory technical support in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

6.3 UNIT STAF UA IFIC TIONS 6.3. 1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI/ANS-3. 1-1978, except for the (I) Health Physics Supervisor who

)

Not responsible for sign-off function.

ST.

LUCIE - UNIT 2 6-6 Amendment No.

5-, 49,65

ADMINISTRATIVE CONT S

6.3 UNIT STAFF UALIFICATIONS (Continued)

'hall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) 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 plant operating characteristics, including transients and accidents.

6.4 TRAI ING 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Manager and shall meet or f

exceed the requirements and recommendations of Section 5.5 of ANSI/ANS-3.1-1978 and 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operation-al experience.

65 RVI WAN AUDIT 6.,

Y R VI W GROUP FRG)

~UNC~IO 6.5.1.1 The Facility Review Group shall function to advise the Plant General Manager on all matters related to nuclear safety.

COMPOS IT ION 6.5. 1.2 The FRG shall have voting members composed of individuals from each of the following disciplines:

Operations Reactor Engineering Kealth Physics Chemistry Licensing Instrument and Control Electrical Maintenance Mechanical Maintenance Technical Support guality Assurance/Control Services The Plant General Manager shall appoint the FRG members, in writing, and from this membership shall designate, in writing, an FRG Chairman.

Members shall meet or exceed the qualifications required for Managers, Super-

visors, or Professional-Technical, as appropriate, pursuant to Specifica-tion 6.3.1.

A~ETEAAAT E 6.5. 1.3 All alternate members shall be appointed in writing by the FRG Chairman to serve on a temporary basis;

however, no more 'than two alternates shall participate as voting members in FRG activities at any one time.

ST.

LUCIE - UNIT 2 6-7 Amendment No. 48~65

. ~

~'

ADMINISTRATIVE CONTI

~NN TING TNI IINIIGT

'.5. 1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.

UORU 6.5. 1.5 The quorum of the FRG necessary for the performance of the FRG responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIB LITI S 6.5. 1.6 The Facility Review Group shall be responsible for:

a ~

b.

C.

Review of (I) all procedures required by Specification 6.8 and changes

thereto, (2) all programs required by Specification 6.8 and changes

thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant General Manager to affect nu-clear safety.

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

Review of all proposed changes to Appendix A Technical Specifica-tions.

d.

e.

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the President-Nuclear Division and to the Chairman of the Company Nuclear Review Board.

f.

Review of all REPORTABLE EVENTS.

g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant General Manager or the Company Nuclear Review Board.

Review of the Security Plan and implementing procedures and submit-tal of recommended changes to the Company Nuclear Review Board.

Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.

ST.

LUCIE UNIT 2 6-8 Amendment No. 43-,89-,47.,65

"ADMINISTRATIVECONTRO

~EEPONSIB ITINB (C I

dt

'k.

n.

AUTHORITY Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evalua-tion, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Presi-dent - Nuclear Division and to the Company Nuclear Review Board.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RADWASTE TREATMENT SYSTEMS.

Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last FRG meeting.

Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the, Company Nuclear Review Board.

6.5.1.7 The Facility Review Group shall:

a.

Recommend in writing to the Plant General Manager approval or disap-proval of items considered under Specifications 6.5. 1.6a.

through ct.

and

m. above.

b.

Render determinations in writing with regard to whether or not each item considered under Specifications 6.5. 1.6a, b,

d and e above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Pr esident-Nuclear Division and the Company Nuclear Review Board of disagreement between the FRG and the Plant General Manager;

however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1. I above.

R CORD 6.5. 1.8 The Facility Review Group shall maintain written minutes of each FRG meeting that, at a minimum, document the results of all FRG activities performed under the responsibility and authority provisions of these technical specifi-cations.

Copies shall be provided to the President - Nuclear Division and the Chairman of the Company Nuclear Review Board.

6.5.2 COMPANY NUCLE R

R VI BOARD CNRB)

~FUMCT 0 6.5.2. 1 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 ST.

LUCIE - UNIT 2 6-9 d

I N TB-,BBTBTB

AOHINISTRATIVE CONTROLS FUNCTION (Continued) e.

ge h.

COMPOSITION instrumentation and control radiological safety mechanical and electrical engineering quality assurance practices 6.5.2.2 The President

- Nuclear Oivision shall appoint, in>>riting, a minimum of five members to the CNRB and shall designate from this membership, in

'writing, a Chairman.

Tie membership shall function to provide independent review and audit in the areas listed in Specification 6.5.2.1.

The Chairman shall meet the requirements of ANSI/ANS-3.1-1987, Section: 4.7.1.'he members of the CNRB shall meet the educational requirements of the ANSI/ANS-3.1-1987, Section 4.7.2,. and have at least 5 years of professional level experience in one or more of the fields listed in Specification 6.5.2.1.

CNRB members who do not possess the educational

'requirements of ANSI/ANS-3.1-1987, Section 4.7.2 (up to a maximum of 2'embers) shall be evaluated, and have their.

membership approved and documented, in writing, on a case-by-case basis by the President - Nuclear Division, considering the alternatives to educational requirements of ANSI/ANS-3.1-1987, Sections 4.1.1 and 4.1.2.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRB Chairman to serve on a temporary basis;

however, no more than two alternates shall participate as voting members in CNRB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the CNRB Chairman to provide expert advice to the CNRB.

MEETING FRE UENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter and as convened by the CNRB Chairman or his designated alternate.

QUORUM 6.5.2.6 he quorum of the CNRB necessary for review and'udit functions of these Technical the Chairman oe his designated alternate and members including alternates.

No more than a

have line responsibility fear operation of the the performance of the CNRB Specifications shall consist of at least a ma)ority of CNRB minority: of. the quorom shall unit.

ST.

LUCIE - UNIT 2 6-10 Amendment No. Jg, 29 >> ~S.

4Ns 47,

ADMINISTRATIVECONTROLS 6.6 REPORTABLE EVENTS ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Comnission 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 FRG, and the results'f this review shall be submitted to the CNRB, and the President-Nuclear Division.

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

a ~

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The President - Nuclear Division and the CNRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the FRG.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violatfon upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Coamission, the CNRB, and the President - Nuclear Division within'14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Coaeission.

6.8 PROCEDURES AND PROGRAMS 6.&.1 Mritten procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February

1978, and those required for implementing the requirements of NUREG Q737.

b.

Refueling operations.

c.

Surveillance and test activities of safety-related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

ST.

LUCIE - UNIT 2 6-13 Amendment No. f$.

leap g

('

ADMINISTRATIVE CONTR PROCEDURES AND PROGRAMS (Continued) f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

guality Control Program for effluent monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974.

guality Control Program for environmental monitoring using the guid-ance in Regulatory Guide 4. 1, Revision 1, April 1975.

6.8.2 Each procedure of Specification 6.8. la. through i. above, and changes

thereto, shall be reviewed by the FRG and shall be approved by the Plant General Manager prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8. la. through i. above may be made provided:

a.

The intent of the original procedure is not altered.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator 's License on the unit affected.

c.

The change is documented, reviewed by the FRG and approved by the Plant General Manager within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the CNRB at least once per 24 months:

a ~

b.

Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the Shutdown Cooling System, High Pressure Safety Injection System, Containment Spray System, and RCS Sampling.

The program shall include the following:

(i)

Preventive maintenance and periodic visual inspection require-

ments, and (ii)

Integrated leak test requirements for each system at refueling cycle intervals or less.

In-Pl nt Radioiod e

Mo to i A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident condi-tions.

This program shall include the following:

(i)

Training of personnel, (ii)

Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.

ST.

LUGIE UNIT 2 6-14 Amendment No.

65

ML17228A474

Text

Attachment:

Attachment:

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