ML17229A744

Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures

ML17229A744
Person / Time
Site:	Saint Lucie
Issue date:	05/27/1998
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A743	List: ML17229A742 ML17229A744
References
NUDOCS 9806020317
Download: ML17229A744 (20)

Text

St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments: Onsite Facility Review Group TAC Nos. M97209/M97210 Chan es to Ori inal Re uest ATTACHMENT2 to L-98-072 ST. LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 6-7 Page 6-8 Page 6-13 INSERT - A, B Page 6-14 980b0203ii 980M705000335 PDR ADQCK P PDR

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6.. 0 ADMINISTRATIVE CONTROLS ALTERNATES 6.5.i.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: y/I procedure.

Review of 1) all procedures required by Specification 6.8 and chan es er , (2) all programs required by Specification 6.8 and c anges thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant General Hanager to affect nuclear et ui'ce a ~<<w e~ M'Peky ava 4O+~~

b. Rev>ew of a 1 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. Performance 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 d I II

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

I. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATlONMANUALand RADWASTE TREATMENTSYSTEMS.

m. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, anchor 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 shall: @rang

a. Recommend in writing to the Plant General Manager, approval or disapproval of items considered under Specifications 6.5.1,6.a through d above.

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

c. Provide written notication 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 Division and the Company Nuclear Review Board of disagreement between the FRG and the Plant General Manager, however, the Plant General'Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

BKt'QBDS 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 resident-Nuclear Division and the Chairman of the Company Nuclear Review Board.

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ST. LUCIE - UNIT 1 Amendment No. 69, W, 88,

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.

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

e.

f. Fire Protection Program implementation,

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSlTE DOSE CALCULATiONMANUALimplementation.

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

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

6.8.2 Each pr ur~LSpecification 6.8.1a through i. above, and c e e o, shall bereviewedbythe FRGancVShall4 romd-b ant GeneralManagerprior to implementation and ewed peri i ~-se h in administrative r ur 6.8.3 rary changes to proc ures o peci Ication 6.8.1a roug i. a ove m made pro de gpIL+ '$

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The intent of the original pr du 's n lt

b. The change is y two members of the plan a ement staff, at least om holds a Senior Reactor Operator's License on 't ected.

ST. LUCIE - UNIT 1 6-13 Amendment No., 59, 69.

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St. Lucie Unit 1 and Unit 2 L-98-072 Bocket. Nos. 50-335 and 50-389 Attachment 2 Proposed License Amendments: Onsite Facility Review Group TAC Nos. M97209/M97210 Chan es to Ori inal Re uest-INSERT - TS 6.8.2 6.8.2 Review and A royal of Procedures: Each new procedure of Specification 6.8.1.a through i. above shall be independently reviewed by an individual or group from the appropriate discipline(s), and shall be reviewed by the FRG. New procedures shall be approved by the Plant General Manager or individuals designated in writing by the Plant General Manager prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.

INSERT- B TS 6.8.3 6.8.3 Chan es to Procedures Each revision to the procedures of Specification 6.8.1.a through i. above shall be independently reviewed by an individual or group from the appropriate discipline(s), and revisions that require a written safety evaluation pursuant to 10 CFR 50.59 shall be reviewed by the FRG.

Procedure revisions shall be approved by the Plant General Manager or individuals designated in writing by the Plant General Manager prior to implementation.

b. Temporary changes to procedures of Specification 6.8.1a through i. above may be made provided:

1. The intent of the original procedure is not altered.

2. 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.

3. The change is documented and, if appropriate, incorporated in the next revision of the affected procedure pursuant to Specification 6.8.3.a.

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gl~&.ll g g g g g g 6.8.4 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'ransient 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:

g (i) Preventive maintenance and periodic visual inspection require-ments, and g

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

b. -Plant Radi iodin Honk 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) Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

'ST. LUCIE UNIT I 6-]4 Amendment No. 69.~,

St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments: Onsite Facility Review Group TAG Nos. M97209/M97210 Chan es to Ori inal Re uest ATTACHMENT3 to L-98-072 ST. LUCIE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 6-8 Page 6-9 Page 6-14 INSERT-A, B

6.5.1A 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 SpecIcations shall consist of the Chairman or his designated alternate and four members including alternates.

a.t( pr~c~ur e 6.5.1.6 The Facility Review Group shall be responsible for:

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a. Re of 1 al yrocedures required by Specmcation 6.8 and Ghanges4m

~e+ ~ (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 safe

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b. Review of ally)roposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix A Technical SpecNcations.

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 re ports covering evaluation and recommendations to prevent recurrence to the President-Nuclear Division and to ttte Chairman of the Company Nuclear Review Board.

f. Review of all REPORTABLE EVENTS.

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

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

ST. LUCIE- UNIT2 Amendment No. +3, 49, 4P, 65, pQ

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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.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE 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.

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

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a. Recoaeend in writing to the Plant General Manager approval or disap-proval 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, b, d and e above constitutes an unreviewed safety question.

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

6.5.2 COMPANY NUCLEAR REVIEW BOARD CNRB) e(~+ a <~~ ~ 8~~er>

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 I EE.~P

DMINISTRATIVE CONTROLS ~

PROCEDURES AND PROGRAMS (Continued)

f. Fire Protection Program implementation.

g. 'PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL 'impl ementati on.

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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 guid-ance in Regulatory Guide 4.1, Revision 1, April

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, shall be revsewe y-t4 d shal ppro e Plant Gene Nanager in

.8.3 may e made prior to e

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'+i -'tk r 'ed-pe cally as set forth gl

a. The intent of iginal procedure is not alt

b. The change is approved by the plant management staff, at least one of whom hol enior tor Operator's License on the unit affected.

c. Th ge is documented, reviewed by the FRG and appro the ant Genera1 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- I a0 Primar Coo1ant Sources Outside Containment e

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.

Amendment No. =".,

ST. LUCIE UNIT 2 6-14

St. Lucie Unit 1 and Unit 2 L-98-072 Bocket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments: Onsite Facility Review Group TAC Nos. M97209/M97210 Chan es to Ori inal Re uest INSERT -A TS 6.8.2 6.8.2 Review and A royal of Procedures: Each new procedure of Specification 6.8.1.a through i. above shall be independently reviewed by an individual or group from the appropriate discipline(s), and shall be reviewed by the FRG. New procedures shall be approved by the Plant General Manager or individuals designated in writing by the Plant General Manager prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.

INSERT - B TS 6.8.3 6.8.3 Chan es to Procedures Each revision to the procedures of Specification 6.8.1.a through i. above shall be independently reviewed by an individual or group from the appropriate discipline(s), and revisions that require a written safety evaluation pursuant to 10 CFR 50.59 shall be reviewed by the FRG.

Procedure revisions shall be approved by the Plant General Manager or individuals designated in writing by the Plant General Manager prior to implementation.

'. Temporary changes to procedures of Specification 6.8.1a through i. above may be made provided:

1. The intent of the original procedure is not altered.

2. 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.

3. The change is documented and, if appropriate, incorporated in the next revision of the affected procedure pursuant to Specification 6.8.3.a.

4 St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments: Onsite Facility Review Group TAC Nos. M97209/M97210 Chan es to Ori inal Re uest ATTACHMENT4 to L-98-072 PROPOSED CHANGE TO PSL1 AND PSL2 UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR)

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St. Lucie Unit1 and Unit2 L-98-072 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments: Onsite Facility Review Group AC Nos. M97209/M97210 Chan es to Ori inal Re uest ADD NEW SECTION 17.2.1 to the PSL1 and PSL2 UFSAR ro osed:

17.2.1 Plant Procedures The FPL Quality Assurance Manual contains the Topical Quality Assurance Report which complies with the criteria of 10 CFR 50, Appendix B. Generic requirements for Instructions, Procedures and Drawings are provided in section TQR 5.0 of the FPLTQAR, which, in part, requires that instructions and procedures for activities affecting quality shall be prepared, reviewed, and approved in accordance with written Quality Instructions. The Quality Assurance Department reviews and comments on Quality Instructions written by other departments. Comments concerning compliance with corporate Quality Assurance commitments and regulatory requirements are resolved prior to issuance. In addition to the guidance provided in section TQR 5.0 of the FPLTQAR, the following requirements apply to the review process for on-site instructions and plant procedures except Emergency Operating Procedures (EOPs) for which other specific administrative controls have been established.

New procedures and procedure revisions are independently reviewed for technical and functional

,accuracy by individuals or groups other than the author(s). Quality Instruction(s) and/or Administrative Procedure(s) provide guidance for the conduct of the independent review process.

Individuals performing these reviews are knowledgeable in the functional area(s) addressed by each new or revised procedure. Interdisciplinary review(s) is performed when a procedure or procedure revision affects more than one department/functional area. Comments resulting from the independent review process are documented in plant records and are resolved prior to implementation of each new or revised procedure.

New procedures and procedure revisions are reviewed to determine if a 10 CFR 50.59 written safety evaluation or license amendment is required prior to implementation. Quality Instruction(s) and/or Administrative Procedure(s) provide guidance for the conduct of the screening process including criteria the reviewer should consider to determine if a safety evaluation is required. If a safety evaluation or license amendment is not required, the basis for that determination is documented and retained in plant records. Individuals authorized to perform these screening reviews have demonstrated acceptable knowledge of the screening process and are designated in writing as qualified reviewers. Additional review of each procedure revision that requires a written safety evaluation and all new procedures is required pursuant to facility Technical Specification 6.8.

Reference:

St. Lucie Unit,1 [2] Pacttity Operating License Amendment No. ~Note Note: The appropriate license amendment number to be inserted.

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