ML17221A751

Amends 93 & 29 to Licenses DPR-67 & NPF-16,respectively, Replacing Organizational Charts in Tech Spec W/More General Organization Requirements

ML17221A751
Person / Time
Site:	Saint Lucie
Issue date:	04/28/1988
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML17221A752	List: ML17221A751 ML17221A753
References
NUDOCS 8805050014
Download: ML17221A751 (39)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POMER

& LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No.

DPR-67 1.

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

A.

The application for amendment by Florida Power 8 Light Company, et al. (the licensee),

dated February 22,

1988, as supplemented by letter dated April 20,

1988, complies with the standards and require-ments 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.

8800050014 8~0'I~033/

P i

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

93

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Speci,ications.

3.

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

D'OR THE NUCLFAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date o~ Issuance:

April 28~

1938 rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.93 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 XIV 6-1 6-2 6-3 6-5 6-7 6-8 6-9 6-12 6-13

<<P XIV 6-1 6-2 6-3 6-5 6-7 6-8 6-9 6-12 6-13

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INDEX ADMINISTRATIVE CONTROLS

)

SECTION PAGE 6.1 RESPONS I8 ILIT

6. 2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATION....

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6.2. 3 SHIFT TECHNICAL ADVISOR.......

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6. 3 UNIT STAFF UALI F ICATIONS.

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6 6 6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW GROUP UnCtl On ~

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.- 6-6 Composition.............

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Alternates..............

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Responsibilities............................................

6-7 uthorlty........................

A Records..................

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... 6-8 6-8 6.5.2 COMPANY NUCLEAR REVIEW BOARD unction...................................................

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Composition.........

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Meeting Frequency..........................

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6 1 2 ST.

LUCIE - UNIT 1

XIV Amendment No. gl,93

6.0 ADMINISTRATIVE CONTROLS 6.1

!?ESPONS IB ILITY 6.1.1 The Plant!1anager 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 Senior Vice president - Nuclear shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION OHSITE AND OFFSITE ORGANIZATION An onsite and an of, site organi2ation shall be estdblished 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 author'ity," 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 Senior Vice President - Nuclear 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 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 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 wor k activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

ST.

LUGIE - UNIT 1

6-1 Amendment No.

g$,py, g3

5.0 ADhlININSTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF 6.2.7 The unit organization shall be subject to the following:

a.

b.

c ~

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 t<OOE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

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.

e.

A Site Fire Brigade<of at least five members shall be maintained onsite at all times The Fire Brigade shall not include the shift supervisor, the STA, nor the two other members of the The health physics technician and 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, provided immediate action is taken to fill the required positions.

ST.

LUGIE - UNIT 1

6-2 Amendment No. Jg,g$,$ $,59, g3

OELETEO ST.

LUGIE - UNIT 1

6-3 Amendment No.

g$,$ 5~52.$ 9.

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

SRO RO AO STA MODE 1, 2, 3 or 4 la 1

2 2

1 MODE 5 or 6 la None 1

2b None POSITION WITH UNIT 2 IN MODE 1, 2, 3, or 4

NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION SS (SRO)

SRO RO AO STA MODE 1, 2, 3, or 4 1 a 1

2 2a 1

MODE 5 or 6 la None 1

1 None SS

- Shift Supervisor with a Senior Reactor Operator's License on Unit 1

SRO - Individual with a Senior Reactor Operator's License on Unit 1

STA - Shift Technical Advisor RO

- Individual with a Reactor Operator's License on Unit 1

AO

- Auxiliary Operator Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 Composi-tion 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.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid SRO or RO license shall be designated to assume the Control Room command function.

a/ Individual may fill the same position on Unit 2.

b/ One of the two required individuals may fill the same position on Unit 2.

ST.

LUCIE - UNIT 1

6-4 Amendment No. $7,$1,N.69

ADMINISTRATIVE CONTROLS minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a

fire emergency.

f.

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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2.

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

3.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 Manager or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individ-ual overtime shall be reviewed monthly by the Plant 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 Super visor shall hold a Senior Reactor Operator license.

SHIFT TECHNICAL AOV1SOR 6..3 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.

E.

ST.

LUCIE - UNIT 1

6-'5 Amendment No. Q, g3

ADMINISTRATIVE CONTROLS 6

3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica tions of ANSI/ANS-3.1-1978 as endorsed by Regulatory Guide 1.8, September 1975 (reissued May 1977), except for (1) the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8.,

September 1975 (2) the Shift Technical Advisor who shall have a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant 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 I

be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS-3.1-1978 and Appendix "A" of 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 FACILITY REVIEW GROUP FRG FUNCTION 6.5.1.1 The Facility Review Group shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Facility Review Group shall be composed of the:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Plant Manager Operations Superintendent Operations Supervisor Maintenance Superintendent Instrument

& Control Supervisor Reactor Supervisor Health Physics Supervisor Technical Supervisor Chemistry Supervisor guality Control Supervisor Assistant Plant Supt. Mechanical Assistant Plant Supt. Electrical The Chairman shall be a member of the FRG and shall be designated in writing.

ST.

LUCIE - UNIT 1

6-6 Amendment No. 25,87~69

ADMINISTRATIVE CONTROLS

'LTERNATES 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.

MEETING 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 respons-ibility 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:

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 Manager to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear

, safety.

C.

d.

e.

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 Senior Vice President - Nuclear 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.

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

ST.

LUCIE - UNIT 1

6-7 Amendment No.

$9, pp

ADMINISTRATIVE CONTROLS Review of the Security Plan and implementing procedures and submittal 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.

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 Senior Vice President - Nuclear 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.

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.

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a.

b.

C.

Recommend in writing to the Plant Manager, approval or disapproval of items considered under Specifications 6.5.1.6.a through d above.

Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6-a through e

above constitutes an unreviewed safety question.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice President - Nuclear and the Company Nuclear Review Board of disagreement between the'RG and the Plant Manager;

however, the Plant'Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 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 Soecifications.

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

ST.

LUCIE - UNIT 1

6-8 Amendment No. Q,Tf~ 93

ADMINISTRATIVE CONTROLS 6.5.2 COMPANY NUCLEAR REVIEW BOARD (CNRB FUNCTION The Company Nuclear Review Board shall function to provide indepen-dent 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.

mechnical and electrical engineering h.

quality assurance practices COMPOSITION 6.5.2.2 The CNRB shall be composed of the following members:

Member:

Member:

Member:

Member:

Member:

Member:

Member.:

Member:

Member:

Member:

Group Vice President Senior Vice Presideht - Nuclear Vice President - Engineering, Projects 8 Construction Vice President - Nuclear Energy Director - Nuclear Licensing Director - guality Assurance Chief Engineer - Power Plant Engineering Manager - Nuclear Energy Services Manager - Nuclear Fuel Manager - Power Plant Engineering The Chairman shall be a member of the CNRB and shall be designated in writing.

ALTERNATES 6.5.2."3 All alternate members shall be appointed in writing by the CNRB Chair-man to serve on temporary basis;

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

ST.

LUCIE - UNIT 1

6-9 Amendment No. Jg,$ $,59, PP,

AOMINISTRATIVE CONTROLS 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.

UORUM 6.5,2.6 The quorum of the CNRB necessary for the performance of the CNRB review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four CNRB members including alternates.

No more than a minority of the quorum shall have line responsibility for operation of the facility.

REVIEW 6.5.2.7 The CNRB shall review:

The safety evaluations for (1) changes to procedures, equipment, or systems and

(.2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

c ~

d.

Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

v Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

Proposed changes to Technical Specifications or this Operating License.

e.

ViolCions of codes, regulations,

orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

ST.

LUGIE - UNIT 1

6-10 Amendment No. 78,$ $,

ADMINISTRATIVE CONTROLS g.

All REPORTABLE EVENTS.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affect nuclear safety.

Reports and meeting minutes of the Facility Review Group.

AUDITS 6.5.2,8 Audits of unit activities shall be performed under the cognizance of I

the CNRB.

These audits shall encompass:

a

~

b.

C.

d.

e.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

The performance, training and qualifications of the entire unit staff at least once per 12 months.

The results of actions taken to correct deficiencies occurring in unit equipment, structures,

systems, or method of operation that affect nuclear safety at least once per 6 months.

The performance of activities required by the quality Assurance Program to meet the criteria of Appendix 8, 10 CFR Part 50, at least once per 24 months.

Any other area of unit operation considered appropriate by the CNRB or the Executive Vice President.

9 h.

The fire protection programatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.

The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.,

An outside independent fire protection consultant shall be used at least every third year.

The radiological environmental monitoring program and the results thereof at least once per 12 months.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for,dewater-ing of radioactive bead resin at least once per 24 months.

ST.

LUGIE - UNIT 1

6-11 Amendment No. g$,$9,69

AOMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 lhe CNRB spall report to and advise the Executive Vice President on those areas of responsibility specifed in Specifications 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of CNRB activities shall be prepared, approved and distrib-uted as indicated below:

a.

Minutes of each CNRB meeting shall be prepared, approved and forwarded to the Executive Vice President within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be

prepared, approved and forwarded to the Executive Vice President within 14 days following completion of the review.

c.

Audit reports encompassed by Specification 6.5.2.8

above, shall be forwarded to the Executive Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.6 REPORTABLE EVENT 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 FRG, and the results of the review shall be submitted to the CNRB, and the Senior Vice President - Nuclear.

6.'7 SAFETY LIMIT VIOLATION 6.7.1 The following,actions shall be taken in the event a Safety Limit is violated:

a.

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

The Senior Vice President - Nuclear and the CNBR sh'all be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

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 violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

ST.

LUCIE - UNIT 1

6-12 Amendment No l8> g3

ADMINISTRATIVE CONTROLS.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the

CNRB, and the Senior Vice President - Nuclear 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 Mritten procedures shall be established, implemented and maintained covering the activities referenced below:

a

~

b.

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.

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.

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

j.

guality Control Program for environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.

6.8.2 Each procedure of Specification 6.8.1a through i. above, and changes

thereto, shall be reviewed by the FRG and shall be approved by the Plant 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.

LUGIE - UNIT 1

6-13 Amendment No. g$,$9, N~

~3

AOMINISTRATIVE CONTROLS c.

The change is documented, reviewed by the FRG and approved by the Plant 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.

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 m'aintenance and periodic visual inspection requirements, and (ii)

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

b.

In-Plant Radioiodine Monitorin C.

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.

Secondar

'Water 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 variables 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 1

6-14 Amendment No. 69.

R<euc Wp0 0O

+0 qO

++**+

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

'S f

FLORIDA POWER 5 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. pg, License No.

NPF-16 1.

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

A.

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

dated February 22,

1988, as supplemented by letter dated April 20,

1988, complies with the standards and require-ments 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 wi 11 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.

4 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:

Technical Specifications The Technical Specifications contained in Appendices A and B.

as revised through Amendment No. 29

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGDLATORY COMMISSION

Attachment:

Charges to the Technical Specificatinns Date of Issuance:

April 28, 1988 rbert N. Berkow, Director Protect Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

j g")

II

ATTACHMENT TO LICENSE AMENDMENT NO. 29 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 Pages XVIII XXII 6-1 6-2 6-3 6-4 6-8 6-9 6-10 6-13 Insert Pa es XVIII XXII 6-1 6-2 6-2a 6-3 6-4 6-8 6-9 6-10 6-13

DESIGN FEATURES INOEX SECTION

5. 1 SITE 5.1.1 5.1.2 EXCLUSION AREA.....'.........,

LOW POPULATION ZONE......

PAGE

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5. 2 CONTAINMENT

5. 2.1 5.2.2 CONFIGURATION.~..........

DESIGN PRESSURE AND TEMPERATURE..............

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5. 3 REACTOR CORE

5. 3.1 5 ~ 3.2 FUEL ASSEMBLIES.........,....,,

CONTROL ELEMENT ASSEMBLIES

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5-4 DESIGN PRESSURE AND TEMPERATURE...................

5-3

5. 5 METEORLOGICAL TOWER LOCATION...........................

5-4

5. 6 FUEL STORAGE 5.6.1 5.6.2 5.6.3 CRITICALITYo ~

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5-4 5-4 5-4 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.

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5-4 ST.

LUCIE - UNIT 2 XVII

ADMINISTRATIVE CONTROLS SECTION

6. 1 RESPONSIBILITY.

INDEX PAGE 6"1

6. 2 ORGANIZATION.

2. 1 ONSITE AND OFFSITE ORGANIZATION,...

6. 2. 2 UNIT STAFF.

6.2

~ 3 INDEPENDENT SAFETY ENGINEERING GROUP...

FUNCTION.

COMPOSITION.

RESPONSIBILITIES AUTHORITY..........................

4

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6-1 6"1 6-1 6-1 6"6 6-6 6-6 6-6 ECORDS

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6. 2. 4 SHIFT TECHNICAL ADVISOR.

6-6 6-6

6. 3 UNIT STAFF UALIFICATIONS.............................

6-6

6. 4 TRAINING.

6"7

6. 5 REVIEW AND AUDIT

6. 5. 1 FACILITY REVIEW GROUP FUNCTION......;........

COMPOSITION...........

ALTERNATES.

MEETING FREQUENCY..

gUORUMe

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RESPONSIBILITIES.

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R 6"7 6"7 6-7 6-7 6-7 6-8 6-8 6-8 6-9 6-9 ST.

LUCIE - UNIT 2 XVIII Amendment No.29

LIST OF FIGURES INDEX FIGURE 2.1-1

2. 2-1

2. 2-2

2. 2-3

2. 2-4 B 2.1-1 PAGE REACTOR CORE THERMAL MARGIN SAFETY LIMIT LINES FOUR REACTOR COOLANT PUMPS OPfRATING........................

2-3 LOCAL POWER DENSITY - HIGH TRIP SETPOINT PART 1

(FRACTION OF RATED THERMAL POWER VERSUS QR2)................

2-7 LOCAL POWER DENSITY - HIGH TRIP SETPOINT PART 2

( gR2 VfRSUS Yl '''''''''

... 2-8 THERMAL MARGIN/LOW PRESSURE TRIP SETPOINT PART 1

( Y] VERSUS A])..............................................

2-9 THERMAL MARGIN/LOW PRESSURE TRIP SETPOINT PART 2 (FRACTION OF RATED THERMAL POWER VERSUS gR] '

2 10 AXIAL POWER DISTRIBUTION FOR THERMAL MARGIN SAFETY LIMITS...............................................

B 2-2 3.1-1 3.1-]a 3.1-2 3.2-1 3.2-2

3. 2-3

4. 2-1

3. 2-4 3.4-1 3.4-2 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TfMPERATURE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION............

ALLOWABLE TIME TO REALIGN CEA VS INITIAL F.................

3/4 1-15 3/4 1-19a I

AXIAL SHAPE INDEX VS FRACTION OF MAXIMUMALLOWABLE POWER LEVEL PER SPECIFICATION 4.2.1.3.......................

ALLOWABLE COMBINATIONS OF THERMAL POWER AND F, F

AUGMENTATION FACTORS VS DISTANCE FROM BOTTOM OF CORE........

3/4 2-4 3/4 2-5 3/4 2-6 AXIAL SHAPE INDEX OPERATING LIMITS WITH FOUR REACTOR COOLANT PUMPS OPERATING.....................................

3/4 2-12 DOSE EqUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMITS VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >

1 NCAA/GRAM DOSE EQUIVALENT I-131............................................

3/4 4-28 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 0 TO 2 YEARS OF FULL POWER OPERATION....................

3/4 4-31 CEA INSERTION LIMITS VS THERMAL POWER WITH FOUR REACTOR COOLANT PUMPS OPERATING...............

3/4 1-28 ALLOWABLE PfAK LINEAR HEAT RATE VS BURNUP...................

3/4 2-3 ST.

LUGIE - UNIT 2 XXI Amendment No.8

INDEX LIST OF FIGURES Continued FI RE

3. 4-3 3.4-4 PAGE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 2

TO 10 YEARS OF FULL POWER OPERATION..........,...,...,

3/4 4 32 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 10 TO 40 YEARS OF FULL POWER OPERATION..........,,

3/4 4 33

4. 7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST...................

3/4 7-25 8 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E)l MeV) NEUTRON FLUENCE (550'F RRADIATION)...""."."".".""""..."...........

I B 3/4 4-10 5.1-1

6. 2-1 ITE AREA MAP.....................................

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5-2 6-3 6 ~ 2 2 DELETED........... ~.........................................

6-4 ST.

LUCIE - UNIT 2 XXII Amendment No. P, 29

ADMINISTRATIVE CONTROLS 6 ~ 1 RESPONSIBILITY 6.1.1 The plant 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 dir ective to this effect,'signed by the Senior Vice President - Nuclear

, shall be r'eissued to all station personnel on an annual basis.

6.2 ORGANIZATION ONSITE ANP OFFSITE ORGANIZATION 6.".1 An onset te and an offsite organization shall be established for unit oper ation corporate management.

The onsite and offsite'rganization shal'i include the oositions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility and communcation 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. Senior Vice President - Nuclear 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 ih the plant so that continued nuclear safety is assured.

c.

The. Plant 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 fdnctions may repor t to the appropriate manager onsite, they shall have sufficient organiza-tional freedom to be independent from operating pressure es.

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'uthority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

ST.'OCIE - UNIT 2 Amendment No. J),2g

ADMINISTRATIVE CONTROLS

6. 2 ORGANIZATION (Continued)

UNIT STAFF 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 show~ in Table 6.2-1.

b.

C ~

d.

e.

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 MOOE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

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

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 flexi-bility to directly supervise at either the refueling deck or the spent fuel pool.

A si te Fire Brigade ~f at least five members shall be maintained onsite at all times.

The Fire Brigade shall not include the Shift Supervisor, the STA, nor the tAo other members of the minimum shift crew necessary for safe shutdown of the unit and any personhel required for other essential functions during a fire emergency.

Administrative procedures shall be developed and. implemented to limit the working hours of unit staffWho 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 over time.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the'lant 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:

O'The health physics technician and 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, provided immediate action is taken to fill the required pos itions.

ST.

LUGIE - UNIT 2 6-2 Amendment No. 2g

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) a.

An hand'ividual should not be permitted to'ork more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

b.

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

c.

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

periods, including shift turnover time.

d.'xcept 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 Manager or his deputy, or higher levels of management, in accordance 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 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.

ST.

LUGIE - UNIT 2 6-2a Amendment No. 2~

DELETED ST.

LUCIE - UNIT 2 6-3 Amendment No. J8, 29

DELETED ST.

LUCIE - UNIT 2 6-4 Amendment No.

$,Jg,

ADMINISTRATIVE CONTROLS

6. 3 UNIT STAFF VALIFICATIONS (Continued) 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 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS 3.1-1978 and Appendix "A" of 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 FACILITY REVIEW GROUP FRG FUNCTION

6. 5. l. 1 The Facility Review Group shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOS IT ION

6. 5. 1. 2 The Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

The Chairman ALTERNATES Facility Review Group shall be composed of the:

Plant Manager Operations Superintendent Operations Supervisor Maintenance Superintendent Instrument 8 Control Supervisor.

Reactor Supervisor Health Physics Supervisor Technical, Supervisor Chemistry Supervisor equality Control Supervisor Assistant Plant Supt. Electrical Assistant Plant Supt.

Mechanical shall be a member of the FRG and shall be designated in writing.

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 member s in FRG activities at any one time.

ST.

LUCIE - UNIT 2 6"7 Amendment No.

13

ADMINISTRATIVE CONTROLS MEETING 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 designa'ted alternate.

gUORUM 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.

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

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

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

Review of all proposed tests and ex'periments that affect nuclear safety.

C.

d.

e.

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 Senior Vice President - Nuclear and to the Chairman of the Company Nuclear Review Board.

Review of all REPORTABLE EVENTS.

Review ot unit operations to detect potential nuclear safety hazards.

h.

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

Review of the Security Plan and implementing procedures'nd submittal 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.

$ 8~

~

ADMINISTRATIVE CONTROLS RESPONSIB[l ITIES (Continued)

Review of every unplanned onsite 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 Senior Vice president

- Nuclear and to the Company Nuclear Review Board.

1.

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.

AUTHORITY

6. 5.1.7 a.

b.

C.

The Facility Review Group shall:

Recommend in 'writing to the Plant Manager approval or disapproval of items considered under Specifications 6.5.1.6a.

through d.

and m.

above.

Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6a.

through e.

above constitutes an unreviewed safety question.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice President

- Nuclear'nd the Company Nuclear Review Board of disagreement between the FRG and the Plant Manager;

however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to SpeCification 6.1.1 above.

RECORDS 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 specifica-tions.

Copies shall be provided'o the Senior Vice President - Nuclear and the Chairman of the Company Nuclear Review Board.

6.5 '

COMPANY NUCLEAR REVIEW BOARD CNRB FUNCTION 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.

LUGIE - UNIT 2 6-9 Amendment No.M, 29

ADMINISTRATIVE CONTROLS FUNCTION (Continued) e.

ge COMPOSITION instrumentation and control radiological safety mechanical and electrical engineering quality 'assurance practices 6.5.2.2

.he CNRB shall be composed of the following members:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Group Vice President".

Senior Vice President - Nuclear Vice President - Engineering, Projects

& Construction Vice President - Nuclear Energy Director - Nuclear Licensing Director - equality Assurance Chief Engineer - Power Plant Engineering Manager - Nuclear Energy Services Manager - Nuclear Fuel Manager - Power Plant Engineering The Chairman shall be a member of the CNRB and shall be designated in writing.

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 6.5.2e4 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.

UORUM 6.5.2.6 he quorom of the CNRB necessary for the performance of the CNRB review and audit functions of these Technical Specifications shall consist of the Chairman and his designated alternate and at least four CNRB members including alternates.

No more than a minority of the quorum shall have line responsibility for operation of the uni t.

ST.

LUGIE - UNIT 2 6-10 Amendment No. 7g, ~N 2g

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

a.

The Commission shall be notified and a report submitted pul suant 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 of this review shall be submitted to the CNRB, and the Senator Vice President - Nuclear.

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

a.

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

The Senior Vice President-Nuclear and the CNRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

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 violation 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 Commission, the CNRB, and the Senior Vice President - Nuclear within 14 days of the violation.

d.

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

6.8 PROCEOURES 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.

Refuel ing operations.

c ~

Surveillance and test activities of safety-related equipment.

d.

Secur ity Plan implementation.

e.

Emergency Plan implementation.

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LUCIE - UNIT 2 6-13 Amendme'nt No. f5~

E

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation h.

OFFSITE DOSE CALCULATION MANUAL implementation.

i.

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

j.

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

6.8.2 Each procedure of Specification 6'. la.

through i. above, and changes

thereto, shall be reviewed by the FRG and shall be approved by the Plant Manager prio~ 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.

c.

The change is documented, reviewed by the FRG and approved by the Plant 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 4 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 requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

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.

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LUCIE - UNIT 2 6"14