ML17221A648

Proposed marked-up Tech Specs,Revising Section 6.0, Administrative Controls, by Deleting Figures 6.2-1 & 6.2-2 & Adding More General Organizational Requirements to Tech Spec 6.2

ML17221A648
Person / Time
Site:	Saint Lucie
Issue date:	02/22/1988
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17221A647	List: ML17221A646 ML17221A648
References
NUDOCS 8802290098
Download: ML17221A648 (34)

Text

INDEX ADHINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY..........................................;.... 6-1 6.2 IQ O+go+ Q/ giles RS'&N~

Q EE~Q 6.2.1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 1 6.2.2 U NIT STAFF.................................................. 6-1 6.2.3 SHIFT TECHNICAL ADVISOR..................................... 6-5 6.3 UNIT STAFF UALIFICATIONS.................................... 6-6 6o4 T RAINING~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 'o ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6 6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW GROUP F UnctiOn ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6 C omposition................................................. 6-6 Alternates.......................... ~ ~ ~ ~ ~ ~ ~ 6 7 M t Frequency...........................................

eetlng 6-7 UOrumo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 7 Responsibilities............................................ 6-7 AUthOri tyo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o 6 8 R ecords ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 8 6.5.2 COMPANY NUCLEAR REVIEW BOARD F UllCtiOn ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 9 C omposition................................................. 6-9 Alternates.................................................. 6-9 C onsultants................................................. 6-10 Meeting Frequency........................................... 6-10 Q uorum...............................................,...... 6-10 R eVieWo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ l ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ... 6-10 A udits...................................................; ... 6-11 AUthOrl ty o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ... 6-12 R ecords.................................................. ... 6-12 ST. LUCIE - UNIT 1 XIV Amendment No. 69 P,PDR 8802290098 880222 PDR ADOGK 05000335

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6. 0 AOMINISTRATI VE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The'lant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility d absence. $ gug'ad Qarg ar~k.

nude< o+'ccrc 6.1.2 The Shift Supervisor, or during his absence from the c ntro room a designated individual, shall be responsible for the control ro m command f t . d g df tf t ttt ff . tg d gy t shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION X~ca~+ AH iIcd OFFSITE UNIT STAFF g cp 4jcc 4 ) 0 fXc gl II04J/wQ ~

6.2.2 The unit or ganization shall be

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

co 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 dur ing this operation. The SRO in charge of fuel handling normally supervises from the control room and has the flexibility to 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, ieclude the shift superviso~. the STA, nor the two other members of the 0 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 accoamodate unexpected ahsence, provided ineediate action is taken to fill the required positions.

ST. LUCIE - UNIT 1 6-1 Amendment No. 2$ > 6>

Onsite and Offsite Or anization 6, 2.I An onsite and an offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a. Liges of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. Those re-lationships shall be documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented iQ 4 c. Top'col @uAI:Q Auu/4~ac. Qyet+ a d p44cd >'< ~~ndn~cc 4 'K IQc<R, Jp.5 'f(4)(>).

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

c. There shall be an individual management position in the onsite organiza-tion having responsibility for overall unit safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

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

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

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

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TIEK L2 2 H. LLR:4 ILART, aITR 1 2 ST. LUCIE - NIT I 6-3 Amendment No:2$ .$ $ N. 69

ADMINISTRATIVE 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=-

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:

a 0 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~ Review of all proposed changes to Appendix A Technical Specificatfons.

d. Review of all proposed changes or modifications to unit s tems or equipment that affect nuclear safety. Sunni'o~ <<<P4~" +

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e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-tf d dtf t p t t th

, and to the Chairman of the Company Nuclear Review Board.

Review of all REPORTABLE EVENTS.

T Review of unit operations to detect potential nuclear safety hazards.

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h. of special reviews. investigations or arelyses and r.'erformance reports thereon as requested by the Plant Manager or;the Company Nuclear Review Board.

ST. LUCIE - UNIT 1 6-7 Amendment No. $ g, 6g

ADMINISTRATIVE CONTROLS

i. Review of the Security Plan and implementing procedures and submittal of recomended 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 rel'ease of radioactive material to the enviro'ns including the preparation of reports covering .

evaluation, recommendations and disposition of the corrective actfon to prevent recurrence and the forwarding of these reports to the nd o the Company Nuclear Revfew Board. SC'~ior Cor porn@.

nacc4Ene. o FIVE.er:

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE 00SE CALCULATION MANUAL and RADMASTE TREATMENT SYSTEMS.

e

m. Review and documentation of judgment concerning prolonged operation fn bypass, channel trip, and/or repair of defective "

protection channels of process variables placed fn bypass 'since the last FRG meeting.

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a 0 Recomend fn writing to the Plant Manager, approval or disapproval of items considered under. Specifications 6.5.1.6.a through d above.

b. Render determinations fn writing with regard to whether or not each item considered under Specifications 6.5.1.6 a through e above constitutes an unrevfewed safety question. Scngor Carfornk, n~C ~ Ogce~

C. 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 nd the Review Board of disagreement between the FRG

'nd the PlantNuclear Company Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specfffcatfon 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 Fgt activities performed under the responsibility and authority provisions ef these T dd ddd tft td . ddd did d d dddt td and the Chairman of the Company Nuclear Review Board. gddd d ddd~ dddk.

g~clg a r CS ST. LUCIE - UNIT 1 6-8 Amendment No. N.72

ADMINI STRATI VE CONTROL 6.5;2 COMPANY NUCLEAR REVIEW BOARD (CNRB PUNCTION 6.5.2.1 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 COMPOS IT ION 6.5.2.2 The C hall be composed of the following members:

nor Member: ro Vice President Member: &esp- Vice President - Nuclear -Ea~y-Member: Vice President - Engineerin Pro e s 8 Construction Member: Vice President - Nuclear Ene Member: Director - Nuclear Licensing Member: Director - guality Assurance Member: Chief Engineer - Power Plant Engineering Member: Manager - Nuclear Energy Services Member: M a er - uclear Fuel Member:. 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 alter nate members shall be appointed in writing by the CNRB Chair-man to serve on temporary basis; however, no mor e than two alternates shall participate as voting members in CNRB activities at any one time.

ST. LUG IE - UNIT 1 6-9 Amendment No. 78,$ 5,$ 9, B6

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The CNRB shall 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. l 6.6 REPORTABLE EVENT 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 of the review shall be submitted to the CNRB d th 6.7 5'end'Or <0r d""

SAFETY LIMIT VIOLATION uclMg. dR eel; 6.7.1 The following actions shall be taken in the event a Safety Limit violated:

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a. The NRC Operations Center shall be notified by lep one as soon 1 ttl d\ 11 lthl th . Th and the CNRB shall be notified within 24 hours.

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 ghe violation upon facility components. systems or structures, and t3) corrective action taken to prevent recurrence.

ST. LUCIE - UNIT 1 6-12 Amendment No. 69

a " J ADMINISTRATI VE CONTROLS

c. The Safety Limit Vfolatfon Report shall be submitted to the Commission, the CNRB, and the within 14 days of the vio ation. sc<,oi corp~ n<

nucleon cgCer- If

d. Critical operation o the unit shall not be resumed until authorized by the Comnission.

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 fn Appendix "A" of Regulatory Guide 1.33, Revision 2. February 1978, and those wequfred for implementing the requirements of NUREG 0737.

b. Refueling operations.

c. Surveillance and test actfvftfes 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 fmplementatfon.

f. equality Control Program for effluent monftorfng, using the guidance fn Regulatory Guide 1.21, Revision 1, dune 1974.

gualfty Control Program for environmental monitoring using the gufdance fn Regulatory Gufde 4.1, Revision 1, April 1975.

6.8.2 Each procedure of Specification 6.8.1a through f. above, and changes thereto, shall be revfewed by the FRG and shall be approved by the Plant Manager prior to fmplementatfon and shall be reviewed periodically as set forth fn admfnfstrative 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 fs not altered.

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b. The change fs 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. LUCIE - UNIT 1 6-13 Amendment Ko. g$ .N. 69

ATTACHMENT 2 Marked-Up Technical Specification Pages, St. Lucie Unit 2:

XVIII XXII 6-1 (plus insert) 6-3 6-4 6-8 6-9 6-10 6-13 E JW/021. PLA

LP INOEX ADMINISTRATIVE CONTROLS SECTION PAGE

6. 1 RESPONSIBILITY....... ~ ~ ~ ~ ~ ~ ~ 6-1

6. 2 ORGANIZATION.: 6-1 6.2.1 NFL~ .......

0~s.'k. a~d ~'4 <~g>>

6-1 6.2.2 UNIT STAFF. 6-1

6. 2. 3 INDEPENDENT SAFETY ENGINEERING GROUP .. 6-1 FUNCTION........... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-6 COMPOSITION...

RESPONSIBILITIES. 6-6 AUTHORITY........ 6-6 RECORDS L ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-6

6. 2.4 SHIFT TECHNICAL ADVISOR..

6. 3 UNIT STAFF UALIFICATIONS. 6-6

6. 4 TRAINING.. 6-7 6.5 REVIEW AND AUDIT...................... 6-7

6. 5. 1 FACILITY REVIEW GROUP..... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-7 FUNCTION. ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6"7 COMPOSITION .. 6-7 ALTERNATES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-7 MEETING FREQUENCY............ 6-8

'QUORUM o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-8 RESPONSIBILITIES......... 6-8 I

AUTHOR TY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6" 9 R ECORDS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-9 ST. LUCIE - UNIT 2 XVIII

INDEX LIST OF FIGURES Continued FIG RE PAGE 3.4-3 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 2 TO 10 YEARS OF FULL POWER OPERATION................... 3/4 4-32 3.4-4 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) NEURON FLUENCE (550'F I RRADIAT ION)....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-'10 5.1-1 SITE AREA tlAP........... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6. 2-1

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 3

6. 2-2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 4 ST. LUCIE - UNIT 2 XXII Amendment .No. 8

AOMINISTRATI VE CONTROLS

6. 1 RESPONSIBILITY

6. 1. 1 The Plant Manager shall be responsfble for overall unit operation and shall delegate fn writing the succession to this responsibility durf absence. gg~ gy r cor pDr nk uc(ea4. o ff'cc~

6.1.2 The Shift Supervisor, or during hfs absence from the c ntrol room, a designated individual, shall be responsible for the control ro m command function. A management directive to this effect sfgned by the shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION Zngg~+ 3$ 4clc.l OFFSITE UNIT STAFF

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6.2.2 The unit organization shall b

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

b. At least one licensed Reactor Operator shall be fn the control room when fuel fs fn the reactor. In addition, while the reactor is fn MOOE 1, 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 fs fn the reactor.

d. All CORE ALTERATIONS shall be observed by a licensed operator and supervised by either a licensed Senior Reactor Operato~ or Senior

~

Reactor Operator Lfafted to Fuel Handling who has no other concurrent responsibilities during this operation. The SRO fn 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.

e. A site Fire Brigade of at least five members shall be maintained onsfte at all times. The Fire Brfgade shall not include the Shift Supervfsor, the STA, nor the two. other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

f. Administrative procedures shall be developed and fwplein4nted to limit the working hours of unit staff who perform safety. related functions; e. g., senior reactor operators, reactor operators, health physfcfsts, auxiliary operators, and key maintenance personnel.

The health physics technician and Fire Brfgade composition may be less than the mfnfmum 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 />, fn order to accoenodate unexpected absence, provided immediate action fs taken to the required positions.

fill ST. LUCIE - NIT 2 6-1 Amendment No. 13

Onsite and Offsite Or anization

4. z. I An onsite and an offsite organization shall be established for unit oper ation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a. Liges of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and/Nial'Q including all operating organization positions. Those re-lationships shall be documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented (pp Ac. 70f cAI Assun~~cc ~M a d used W i~ n 0 Coe&w~ 4 Ill, /o CCR 5'o. SV (~3 (0).

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

c. There shall be an individual management position in the onsite organiza-tion having responsibility for overall unit safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

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

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

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

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4 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 designated alternate.

UORUM

'I 6.5.1.5 The quo~um 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. 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. Revie~ of all proposed changes to Appendix A Technical Specifications.

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

e. 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

, and to the Chairman of the Company Nuclear Review Board.

gg~.or Car porn

f. Review of all REPORTABLE EVENTS. n <<c <un. o %ca~

g. 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 and submittal of recommended changes to the Company Nuclear Review Board.

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

ST. LUCIE - UNIT 2 6-8 Amendment No. 13

ADMINISTRATIVE CONTROLS Sunni'or Co~Pe RESPONS I B IL IT IES (Continued) na clCn R agiC,Cr

k. Review of every unplanned onsite release of radioac ive material to the environs including the preparation of reports co ering evaluation, recommendations and disposition of the corrective ac ion to prevent recurrence and the forwarding of these reports to the and to the Company'uclear 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.

AUTHORITY 6.5.1.7 The Facility Review Group shall: 0

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

above.

b. 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.

C. P id Itt ~ fI tb MtM 24 h t th and the I 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 to the

, and the Chairman of the ompany Nuclear 5enEo~ COP rnid 6.5.2 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. LUCIE - UNIT 2 6-9 Amendment No. 13

ADMINISTRATIVE CONTROLS FUNCTION (Conei need)

e. instrumentation and control radiological safety ge mechanical and electrical engineering

h. quality assurance practices COMPOSITION 6.5.2.2 .he CNRB shall be composed of the following members:

Suer Member: Gr ice President Member: 4m'-Vice President - Nuclear Member: Vice President - Engineering, Pro ects 8 Construction Member: Vice President I Huc1ear oner Member: Director - Nuclear Licensing Member: Director - guality Assurance Member:

Member:

Member:

~N Chief Engineer - Power Plant Engineering Manager - Nuclear Energy Services

%he Chairman shall be clear Fuel a member g

of the CNRB and 1

shall Egi be Ig 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 6.5.2.4 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 initi'al 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 quorom of the CNRB necessary for the performance of the CNRB review and audit functions of these Technical Specifications shalt 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 unit.

ST. LUCIE - UNIT 2 6-10 Amendment No. Jg, 25

1'l ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENTS ACTION

. 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Comnissfon 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 this review shall be submitted to the CNRB and the Sgn;Or CorP0r<

nuc f~< c Q;cci-.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken fn the event a Saf t fm is violated: g P,'Or CPr YIrh&-

a. The NRC Operations Center shall be notified b telephone as soon as possible and fn all cases within 1 hour. The and the CNRB shall be notified within 24 hours.

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 vfolatfon upon facility components, systems or structures, and (3) corr c v action taken to prevent recurrence. ~q~;Or 44~ Q ocr i'OrPOrhIY'>o/~n

c. The Safety Limit Violation Report shall be submitted t t e omnfssfon, the CNRB 4 th thht tt d 4 4 th 4 4 tt

d. Critical operation of the unit shall'ot be resumed until authorized by the Coamfssfon.

~y 6.8 PROCEDURES AND PROGRAMS 6.8.1 Wrftten procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended fn Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978. and those required for fmplementfng 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.

ST. LUCIE - UNIT 2 6-13 Amendment No. 13

ATTACHMENT 3 DESCRIPTION OF PROPOSED CHANGES The proposed amendments revise Section 6.0, Administrative Controls, of the St. Lucie Units 1 and 2 Technical Specifications to reflect proposed organizational changes affecting the offsite organization, delete offsite and onsite organizational charts and add general organizational requirements and titles, as well as revise the titles for members of the Company Nuclear Review Board (CNRB).

St. Lucie Unit 1 Pa es 6-1 6-7 6-8 6-12 and 6-13 References to the "Vice President-Nuclear Operations" and/or "Group Vice President-Nuclear Energy" in Specifications 6.1.2, 6.5.1.6e., 6.1.5.6k., 6.5.1.7c., 6.5.1.8, 6.6.1b.,

6.7.la. and 6.7.1c. are changed to "senior corporate nuclear officer" to reflect proposed organizational changes. The proposed changes are consistent with the intent of the current Technical Specifications.

Pa es XIV 6-1 6-2 and 6-3 The proposed amendment revises Specification 6.2.1 and 6.2.2 by deleting Figure 6.2-1, "Off-Site Organization For Facility Management And Technical Support" and Figure 6.2-2, "Unit Organization St. Lucie Plant, Units 1 and 2", and replaces them with general organizational requirements. These general organizational requirements reflect the signif icant organizational features currently presented in Figures 6.2-1 and 6.2-2 for ensuring safe plant operation. Deletion of Figures 6.2-1 and 6.2-2 will eliminate the need to process Technical Specification changes for changes in the offsite and onsite organizations which are administrative and do not affect the safe operation of the plant.

Organizational relationships and responsibilities will continue to be described in detail in the FPL Topical Quality Assurance Report. Appendix B to 10 CFR 50 and 10 CFR 50.54(a)(3) govern changes to the organizations described in the Topical Quality Assurance Report. Changes to this program description which reduce commitments previously accepted by the NRC will require NRC approval prior to implementation.

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The Company Nuclear Review Board (CNRB) composition specified in Specification 6.5.2.2 is revised to indicate the title change of "Group Vice President-Nuclear Energy" to "Senior Vice President-Nuclear". The title of "Member: Senior Project Manager Power Plant Engineering" should be changed to "Member: Manager Power Plant Engineering". The title "Senior Project Manager" is no longer used in FPL's Power Plant Engineering organization. This change is purely titular; there is no change in the collective talents on the CNRB and the quality and scope of independent review will be unchanged from the current high quality.

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St. Lucie Unit 2 Pa es 6-1 6-8 6-9 and 6-13 References to the "Vice President-Nuclear Operations" and/or "Group Vice President-Nuclear Energy" in Specifications 6.1.2, 6.5.1.6e., 6.1.5.6k., 6.5.1.7c., 6.5.1.8, 6.6.lb.,

6.7.1a. and 6.7.1c. are changed to "senior corporate nuclear officer" to reflect proposed organizational changes. The proposed changes are consistent with the intent of the current Technical Specifications.

Pa es XVIII XXII 6-1 6-2 and 6-3 The proposed amendment revises Specification 6.2.1 and 6.2.2 by deleting Figure 6.2-1, "Off-Site Organization For Facility Management And Technical Support" and Figure 6.2-2, "Unit Organization St. Lucie Plant, Units 1 and 2", and replaces them with general organizational requirements. These general organizational requirements reflect the significant organizational features currently presented in Figures 6.2-1 and 6.2-2 for ensuring safe plant operations. Deletion of Figures 6.2-1 and 6.2-2 will eliminate the need to process Technical Specification changes for changes in the offsite and onsite organizations which are administrative and do not affect the safe operation of the plant.

Organizational relationships and responsibilities will continue to be described in detail in the FPL Topical Quality Assurance Report. Appendix B to 10 CFR 50 and 10 CFR 50.54(a)(3) govern changes to the organizations described in the Topical Quality Assurance Report. Changes to this program description which reduce commitments previously accepted by the NRC will require NRC approval prior to implementation.

Pa e 6-10 The Company Nuclear Review Board (CNRB) composition specified in Specification 6.5.2.2 is revised to indicate the title change of "Group Vice President-Nuclear Energy" to "Senior Vice President-Nuclear". The title of "Member: Senior Project Manager Power Plant Engineering" should be changed to "Member: Manager Power Plant Engineering". The title "Senior Project Manager" is no longer used in FPL's Power Plant Engineering organization. This change is purely titular; there is no change in the collective talents on the CNRB and the quality and scope of independent review will be unchanged from the current high quality.

E JW/02 1 ~ PLA

ATTACHMENT 4 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission s regulations, 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated or (3) involve a significant reduction in a margin of safety. Each standard is discussed as. follows:

(1) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

The changes being proposed are administrative in nature and do not affect assumptions contained in plant safety analyses, the physical design and/or operation of the plant, nor do they affect Technical Specifications that preserve safety analysis assumptions. Therefore, the proposed changes do not affect the probability or consequences of accidents previously analyzed.

(2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.

The changes being proposed are administrative in nature and will not lead to material procedure changes or to physical modifications. Therefore, the proposed changes do not create the possibility of a new or different kind of accident.

(3) Use of the modified specification would not involve a significant reduction in a margin of safety.

The changes being proposed are administrative in nature and do not relate to or modify the safety margins defined in and maintained by, the Technical Specifications.

EJW/021. PLA

Deletion of the figures displaying offsite and onsite organizational structures and other organizational changes will not decrease the effectiveness of the offsite and onsite organizations to manage the St. Lucie Plant. These organizations will continue to operate, manage and provide technical support to the St. Lucie Plant.

The NRC will continue to be informed of organizational changes through other controlled mechanisms. The Topical Quality Assurance Report provides a detailed description of organization and responsibilities as well as detailed organizational charts. Changes to the Topical Quality Assurance Report are governed by 10 CFR 50.54(a)(3) . Changes to the Topical Quality Assurance Report description that reduce commitments previously accepted by the NRC require NRC approval prior to implementation. FPL will continue to inform the NRC of organizational changes affecting St. Lucie Plant.

Changes to the composition of the Company Nuclear Review Board (CNRB) reflect only title changes and are administrative in nature. There is no change in the collective talents on the CNRB and the scope of independent review conducted by the CNRB will be unchanged from the current high quality.

Therefore, the proposed changes do not involve any reduction in a margin of safety.

Based on the above, we have determined that the amendment request does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the probability of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety; and therefore does not involve a significant hazards consideration.

EJW/021. PLA

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