ML17229A119

Proposed Tech Specs 6.0 Re Administrative Controls

ML17229A119
Person / Time
Site:	Saint Lucie
Issue date:	10/31/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A118	List: ML17229A117 ML17229A119
References
NUDOCS 9611060188
Download: ML17229A119 (19)

Text

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St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 6-7 Page 6-8 Page 6-13 INSERT A, B Page 6-14 96ii060188'961031 PDR ADOCK 05000335 P PDR

S.O 'DMINISTRATIVE 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.

~UORUM 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: al( vocedvve new

a. Review of {I) all procedures required by Specification 6.8 and chan es , (2) all programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant General Manager to affect nuclear

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evsew o 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.

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

f. Review of all REPORTABLE EVENTS.

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

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

ST. LUCIE - UNIT I 6-7 A d tN.~

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HQUJssi k, Review of every unplanned on-site release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the President-Nuclear Oivision and to the Company Nuclear Review Board, I. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATiONMANUALand RAOWASTE TREATMENT SYSTEMS.

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

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

6.5.1.7 The Facility Review Grau shall: '+ P<<vtgz.

II ~WE of items co idered u I lk WP I Ch P

'ations 6.5.1.6. through d above a s cert et-c< wry+I ~ FAG ~4-m~ oI's desi ~ Mrnake.,

b. Ren er determinatIons in writing with regard to e r or not ea em considered under Specifications 6.5.1.6.a, b, d, and e above constitutes an unreviewed safety question.

c. Provide written notificatio within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the President-Nuclear Qivision and the Company Nuclear Review Board of disagreement between the FRG and the Plant General Manager, however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

6.5.1.8 The Facility Review Group shall maintain written minutes of each FRG meeting that, at a minimum, document the results of all FRG activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the~President-Nuclear Division and the Chairman of the Company Nuclear R New Board.

ST. LUCIE - UNIT 1 Amendment No. 69, i%, 98,

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

d. Critical operation of the unit shall not be resumed until authorized by the Commission, 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

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

b. Refueling operations.

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

e. 5gLusgd

f. Fire Protection Program implementation.

g, PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATIONMANUALimplementation.

RGPLAt:E Quality Control Program for effluent monitoring, using the guidance in

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~iamb RegQIatoly Guide 1.21, Revision 1, June 1974.

XH@.aT-A Quality Control Program for environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.

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-be-reviewed'-the-FRG-anM hall-be-approved'-the-PIanMeneraWAanager-prior g~ heal 4Hmplementatio~d-shal&e-review~ nodiMIy-asset-fort¹iaadministrative ecedufes; 6.8.3 b. Temporary changes to procedures of Specification 6.8.1a through i. above may be made provided:

<eh+ +t)The intent oi the original proosdure is not aitersd.

Q4) 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. LUCIE- UNlT1 6-13 Amendmerrt No. 25, 59, 69, ss, tee, ss~s

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St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments 6.8.2 Each new procedure of Specification 6.8.1.a through i.

above, except 6.8.1.f, shall be reviewed and approved by the FRG prior to implementation. Fire Protection Program implementation procedures and changes thereto shall be reviewed by the FRG and approved by the Plant General Manager. Each procedure of Specification 6.8.1 shall be, reviewed periodically as set forth in administrative procedures.

6.8.3 a ~ Each revision to the procedures required by Specification 6.8.1.a through i. above shall be independently reviewed by an individual or group from the appropriate discipline(s), and except as required by Specifications 6.5.1.7 and 6.8.2, each revision shall be approved by the Plant General Manager or individual(s) designated in writing by the Plant General Manager prior to implementation. Personnel authorized to approve procedure changes pursuant to this Specification shall be at a management level appropriate for the activities affected by the procedure being revised.

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6. 0 AOMINISTRATIYE CONTROLS lc-dAlo& Q g; 3 ~

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re-lGd i he change is documented Pka~enmQWanager 6.S.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the CNRB:

a. P imar olan S rc s u id n ainm n

. 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. Tfie systems include the Shutdown Cooling System, High 'Pressure Safety Injection System, Containment Spray System, and RCS Sampling. The program shall include the following:

(i) Preventive maintenance and periodic visual inspection require-ments, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. -Plant Radi iodin Moni rin A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii:) Provisions for maintenance of sampling and analysis equipment.

c. S ndar Ma hemi A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule For the critical vari-ables and control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) monitoring Identification the of process sampling points, which shall include discharge of the condensate pumps for evidence of condenser in-leakage, ST. LUC IE - VNIT 14 Amendment No. 69.~

St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments ST ~ LUCIE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 6-8 Page 6-9 Page 6-14 INSERT A, B

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.

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.

6.5.1.6 The Facility Review Grou hall be responsible for. ~{) o~~e.

a. Review oi (t } alLprocedures required by Specificatio 6.8 an/changes ther (2) all programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant General Manager to affect nuclear safety.

b, Review of allyroposed 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.

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

f. Review of all REPORTABl E EVENTS.

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

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

i. Hashed.

-nstt'rrruic~c- tent t cn snP) sert'~o~~ ST. LUCIE - UNIT 2 Amendment No. +3, R9, 4V.

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ADMINISTRATIVE CONTROL ~EEPPPPI I ITIES Et tl

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

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

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

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

AUTHOR ITY Pp~qtrl~ 6.5.1.7 The Facility Review Group shall: P PP I Pl P. proval of items nsid ed u er S eci ic tions 6.5.1.6a throu h d. and m. abov a,s ee~~Peh~~ sushi~ t t4 F~iv~orbis Ws ~ed alta~~iDe..

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

c~ Provide written notification within 24 hours to the President-Nuclear Division and the Company Nuclear Review Board of disagreement between the FRG and the Plant General Manager; however, the Plant General Manager shall have responsibility for resolut-ion 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 specifi-cations. Copies shall be provided to the President - Nuclear Division and the Chairman of the Company Nuclear Review Bo rd. 6.5.2 COMPANY NUCLEAR REVIN BOARD CNRB) V.4.~V &.~~J 5a-e Cr 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 ~ I S . ',dddddtdd

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r ~ p ADMINISTRATI VE CONTROLS PROCEDURES AND PROGRAMS (Continued) Fire Protection Program implementation. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

quality Control Program for effluent monitoring, using the guidance in qC$w

>'hHIE gdh cedures. may .8.3 Temporary changes e made provided: to procedures of Specification 6.8.1a. through i. above p:t,l) The intent of the original procedure is not altered. Q~ P.(<) The t I change is approved by two members t unit affected. 1 h h dt N a qvoqv'gcLP&z ~gt 'g of the plant management staff, ~t wcol"povcL+@~d (N W8 oc,xf I'8AQ<N ~g ~ce~v~ pr~~an+aoS ~g t~6.8,S,~ sr.'(5) The change is documen e , -r w n p =-e enid'-.ion. pg 6.8.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the CNRB-

a. Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the Shutdown Cooling System, High Pressure Safety Injection System, Containment Spray System, and RCS Sampling. The program shall include the following:

(i) Preventive maintenance and.periodic visual inspection require-ments, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

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

(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment. ST. LUCIE - UNIT 2 6-14 Amendment No. ~. Pff 2 ~ Cg 1 ~ J Jf I L h s St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments 6.8.2 Each new procedure of Specification 6.8.1.a through i. above, except 6.8.1.f, shall be reviewed and approved by the FRG prior to implementation. Fire Protection Program implementation procedures and changes thereto shall be reviewed by the FRG and approved by the Plant General Manager. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures. 6.8.3 Each revision to the procedures required by Specification 6.8.1.a through i. above shall be independently reviewed by an individual or group from the appropriate discipline(s), and except as required by Specifications 6.5.1.7 and 6.8.2, each revision shall be approved by the Plant General Manager or individual(s) designated in writing by the Plant General Manager prior to implementation. Personnel authorized to approve procedure changes pursuant to this Specification shall be at a management level appropriate for the activities affected by the procedure being revised. 1 I r I I "7 ' I 'h,,t Ct If <'yo h ~ v te}}