ML17223B047

Proposed Tech Specs Re Organizational Titles

ML17223B047
Person / Time
Site:	Saint Lucie
Issue date:	01/02/1991
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17223B046	List: ML17223B045 ML17223B047
References
NUDOCS 9101090120
Download: ML17223B047 (26)

Text

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Attachment 1 Maxked-up Technical Specificatians Pages, St. Lucie Unit 1 6-1 6-7 6-8 6-9 6-11 6-12 6-13 Pi01090i20 f10102

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G.Q AD iINISTRATIVE CQNTROLS oeSPONS 18 IL ITY 5

' 7+e Plant '1anager shall be responsible .or overall uni ~ operation and snail delegate in writing the succession to this r esponsibility during his

')sence.

5.l.~ 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 ~~.

~~mpresident - Nuclear shall be reissued to all station personnel on an annual basis.

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6. 2 '3RGAN I ZATION 0.')SITE'.'l0 OFFSITE ORGANIZATION An onsi te and an of, site organi2ation shall be established for uni t, operation and corporate management. This onsite and offsi te 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 quality Assurance Report and updated in accordance:with 10 CFR 50.54(a)(3).

b. id - . i h 11 b p ib1 plant nuclear safety. This indivi ual 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 r esourCes 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 shal'. have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

'ST. LJCIE - UNIT 1 6-1 Amendment No. gg,pg, ~3

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ADMINISTRATIVE CONTROLS

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6.5.1.3 All alternate members shall be appointed in writing by the FRG Chair-basis; however, no more than two alternates shall

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-.an to serve on a temporary

'articipate 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 "y the FRG Chairman or'is designated alternate.

QUORUM 6.5.1.5 The quorum of the FRG necessary for the performance of the FRG respons ibi lity 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.

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

C. 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.

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 the4enim NucIear President - Nuclear and to the 'Chairman of the Company Review Board. QUAL:o~

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, g3 pp,

'DMINISTRATIVE CONTROLS

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

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

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Board.

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 Id h 1 -" I d h C p 111 Review Board.

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I Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE d

I Pd DOSE CALCULATION MANUAL and RAOWASTE 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. ~a I

- AUTHORITY

'.5.1.7 The Facility Review Group shall:

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

b. Render determinations in writing with regard to whether or not j each item considered under Specifications .6.5.1.6 a through e above constitutes an unreviewed safety question.

c. Provide written notiffcatfon within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to President - Nucle the~~

and the Company Nuclear Review Board e ween the'RG and the Plant Hanager; however,

'f di e Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS i 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 I hf 11 *ff CI . Cpf President - Nuclear and the Chairman of the h111 p Idd<<h Company Nuclear Review Board.

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ST. LUCIE - UNIT 1 6-8 Amendment No. N~Q~ 93

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ADMINISTRATIVE CONTROLS 6.5.2 COMPANY NUCLEAR REVIEW BOARD CNRB)

FUNCTION 6.5.2.1 The Company Nuclear Review Board shall function to provide indepen-dent review and audit of designated activities in the ar eas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy'.

instrumentation and control f.

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radiological safety

g. mechnical and electrical engineering

h. quality assurance practices COMPOSITION

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t.t.t.t tt tt t tt t t t. t ttt of five members to the CNRB and shall designate from this membership, in writing, a .hairman. The membership shall function to. provide independent review and audit in the areas listed in Specification 6.5.2.1. The Chairman shall meet the requirements of ANSI/ANS-3.1-1987, Section 4.7.1.

The members of the CNRB shall meet the educational requirements of the ANSI/ANS-3.1-1987, Section 4.7.2, and have at least 5 years of professional level experience in one or more of the fields listed in Specification 6.5.2.1. CNRB members who do not possess the educational requirements of ANSI/ANS-3.1-1987, Section 4.7.2 (up to a maximum of 2 members) shall be evaluated, and have their membership approved ' and documented, in writing, on a case-by-case basis by the Presiden considering the alternatives to educational requirements of ANSI/ANS- .1-1987, Sections 4.1.1 and 4.1.2.

ALTERNATES 6.5.2.3" ",ll 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. LUG IE - UNIT 1 6-9 '

Amendment No. 7g $ 5,59,.5$ ,.

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ADMINISTRATIVE CONTROLS 9 All REPORTABLE EVENTS.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems., ar 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. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

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

C. 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.

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

e. Any h~Pdd t.-~gp other area of unit operation considered ap ro riate

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

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g. 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.

h. 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.

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ST. LUCIE - UNIT 1 6-11 Amendment No. 2$ .$ 8~69

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Specifications 6.5.2.7 and Id 6.5.

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RECORDS of activities shall prepared, approved and distrib

~P 6.5.2.10 Records CNRB be uted as indicated below:

a. Minutes of each CNRB meeting shall be prepared, approved and I dd<<h meeting.

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b. Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared, approved arid 'forwarded to the c.

f ~P President ithin 14 days following completion of the review.

Audit reports encompassed by Specification 6.5.2.8 above, shall be dd<<h fd t dt th positions responsible for the areas audi d within 30 days after completion of the audit by the auditing, rganization.

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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 ~kgr.

%bee=President - Nuclear

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op 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 Itt df 11 I ht I h . Th President - Nuclear and the CWB sh'all be notified within 24 hours.

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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. H. P 102

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c. The Safety Limit Violation Report shall be submitted to the

( ( ( , ( RB, of the violation.

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d. Critical operation of the unit shall not be resumed until authorized J

by the Comnissfon.

c.8 PROCEOURES AND PROGRAMS 6.8.1 dritten procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February l978,'and those required for implementing the requirements of NUREG 0737.

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b. Refueling operations. (

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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.

OFFSITE OOSE CALCULATION MANUAL implementation.

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

gualfty 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 f. above, and changes hereto, shall be reviewed by the FRG and shall be approved by the Plant

1anager prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

5.8.3 Temporary changes to procedures of Specfffcatfon 6.8.1a through i.

above may be made provided:

a. The intent of the original procedure fs not altered.

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. I ST. LUCIE - UNIT 1 6-13 Amendment No. g$ ,$ 9, N ~

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Attachment 2 Marked-up Technical Specifications Pages, St. Lucie Unit 2 6-1 6-8 6-9 6-10 6-12 6-13

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 Super visor, 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 4esk~

4kea President - Nuclear , shall be reissued to all station personnel on an annual basis.

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6. 2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.."...1 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. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate. levels to and'including all operating

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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 equality Assurance Report and updated in accordance with 10 CFR 50.54(a)(3). Qe~sgiOA Th id -N 1 hd1b'" p" Ib1 f 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.

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d. Althaegh the individuals who train the operating staff and those who carry out the quality assur ance fdnctions may report to the appropriate manager onsite, they shall have sufficient organiza-tional freedom to be independent from operating pressures.

e. Although health physics individuals may report.to any appropriate manager onsi te, 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.

,~'T.'LUCIE - UNIT 2 6-l Amendment No. 7g,~~'5

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.

QUORUM 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.

RE 5 PONS I B I LITIES 6.5.1.6 The Facility Review Group shall be responsible for:

Review of (1) all procedures required by Specification 6.B 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.

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

C. Review 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.

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e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-t t i t t i t President - Nuclear and to the Chairman of the. Company Nuclear Review Board.

Review of all REPORTABLE EVENTS. Q,u ~'$/0 4

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.

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

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

ST. LUCIE - UNIT 2 6-B Amendment No. 0, 29

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

Review Q f every unpl armed ons i te rel ease of radioactive materi al to one environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent 4 f df 2 f h 2 0;o 's'o> President - 'lu and to the Company Nuclear Review Board.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE OOSE CALCULATION MANUAL and RADMASTE 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.

AUTHOR ITY 6.5.1.7 The Faci 1ity Review Group shall:

a. Recommend i'n 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 ~ 2 fd 1 fff 1'hhf f4h <<h President - Nuclear'nd the Company Nuclear Review Board of Q)u e$ eO~

disagreem een the FRG and the Plant Manager; however, the P , anager 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 the Chairman 211 h112 of the Company fdd<<h~

under the responsibility and authority provisions of these technical specifica-Nuclear Review Board.

fd - 1 d 6.5.2 COMPANY NUCLEAR REVIEM 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.M, 29

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e. instrumentation and control

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radiological safety

g. mechanical and electrical engineering

h. quality assurance practices A/hhtjohht Q V d 0+

COMPOSITION II II Th 16 I 11 Ih I I, I I I I, o f five members to the CNRB and shall designate from this membership, in

'writing, a Chairman. Tbe membership shall function to provide independent review and audit in the areas listed in Specification 6.5.2.1. The Chairman

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shall meet the requirements of ANSI/ANS-3.1-1987, Section. 4.7.1.'he members of the CNRB shall meet the educational requirements of the ANSI/ANS-3.1-1987, Section 4.7,2,. and have at least 5 years of professional level experience in one or more of the, fields listed in Specification 6.5.2.1. CNRB members who do not possess the educational tequirements of ANSI/ANS-3.1-1987, Section 4.7.2 (up to a maximum. of 2'embers) shall be evaluated, and have their membership approved .and documented, in wr'iting, on a case-by-case basis by h I I I h I I" I requirements of ANSI/ANS-3. -1987, Sections 4.1.1 and 4.1.2.

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ALTERNATES 6.5.2.3 All alternate members s'hall be appointed in writing by the CNRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in CNRB activities at any one time.

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

MEETING FRE UENCY

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

QUORUM 6.5.2.6 he quor um 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 a majority of CNRB members including alternates. No more than a minority. of the quorom shall have line responsibility fear operation of the unit.

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ST. LUG IE - UNIT 2 6-10 Amendment No. 7$ , 2@N 28 45 j

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AOMINISTRATIVE CONTROLS AUDITS (Continued)

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

other area of unit operation considered appropriate by the CNRB

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e. Any or the 'resident.

Q;p eS eu> The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.

g. 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.

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

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

The PROCESS CONTROL PROGRAM and implementing procedures for dewatering of radioactive bead resin at least once per 24 months.

AUTHORITY Alucf&A-Qe"uf4e+~

6. 5. 2. 9 The CNRB shall report to and advise the President on those areas of, responsibility specified in Specifications 6. 5, 2. 7 and 6. 5. 2. 8.

RECOROS 6.5.2. 10 Records of CNRB activities shall be prepared, approved, and ~

distributed as indicated below: JAclcgi Q;u Se'4~

a. Minutes of each CNRB meeting shall be pre ared, approved, and forwarded to the President within 14 days following each meeti ng.

Reports of reviews encompassed by Specification 6. 5. 2. 7 above shall be prepared, approved, and forwarded to the 'resident within 14 days following completion of the review.

C. Audit reports encompassed by Specificatio'n 6.5.2.8 above shall be

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positions responsible for the areas completion of the audit by the audi au 'd within 30 days after g organization.

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ST. LUCIE - UNIT 2 6-12

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ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVFNTS ACTION 6.6.1 ;he 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 this review shall be submitted to the CNRB, and the Sea='~

~re: President - Nuclear lutho04 6.'7 SAFETY LIMIT VIOLATION 4

6.7.1 The following actions shall be taken. in the event a Safety Limit is vio1ated:

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a. The NRC 141 and d I the 11 CNRB shall I hl I h . Th ~P.

Operations Center shall be notified by telephone as soon as be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Id'uclear

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

~P action taken to prevent recurrence.

Safety Limit Violation Report shall be submitted to the Coomission,

c. The h PRRR, d h Id -I I ""111 ldd of the violation.

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

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

a. . The applicable procedures recoamended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978, and those required for implementing the requirements of NUREG 0737.

b. Refueling operations.

c. Surveillance and test activities of safety-related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

4 4 ST. LUCIE - UNIT 2 6-13 Amendment No. flan 29

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