ML17228B300
| ML17228B300 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/25/1995 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17228B301 | List: |
| References | |
| NUDOCS 9510310207 | |
| Download: ML17228B300 (13) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER 5 LIGHT COMPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 140 License No.
DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E, The application for amendment by Florida Power
& Light Company, et al. (the licensee),
dated February 28, 1994 and modified by letter dated September 25,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions OIf'he Act, and the rules and regulations of the CommlssiGKI" There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
95i03i0207 95i025 PDR ADQCK 05000335 P
0
2.
3.
Accordingly, Facility Operating License No.
DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 140, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance,and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 25, 1995
ATTACHMENT TO LICENSE AMENDMENT NO.
40 TO FACILITY OPERATING LICENSE NO.
DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pa es 6-11 6-14 Insert Pa es 6-11 6-14
g.
All REPORTABLE EVENTS.
h, All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
i.
Reports and meeting minutes of the Facility Review Group.
6.5.2.8 Audits of unit activities shall be performed under the cognizance of the CNRB.
These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions.
b.
The performance, training and qualifications of the entire unit staff.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety.
d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50.
e.
Any other area of unit operation considered appropriate by the CNRB or the President - Nuclear Division.
f.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA 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.
i.
The OFFSITE DOSE CALCULATIONMANUALand implementing procedures.
J.
The PROCESS CONTROL PROGRAM and implementing procedures for dewatering of radioactive bead resin.
ST. LUCIE-UNIT1 6-11 Amendment No. B5, 59, 69, 140
ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The CNRB shall report to and.advise the President - Nuclear Division on those areas of responsibility specified 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 ~
b.
C.
Minutes of each CNRB meeting shall be prepared, approved and forwarded to the President '- Nuclear Division within 14 days following each meeting.
Reports of reviews encompassed by Specification 6.5.2.7 above, shall be preoared, approved and 'forwarded to the President-Nuclear Division within 14 days following'ompletion of the review.
Audit reports encompassed by Specification 6.5.2.8 above, shall be forwarded to the President - Nuclear Division and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the FRG, and the results of the review shall be submitted to the CNRB, and the 'President'-
Nuclear Division.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1
hour.
'The President-Nuclear Division and the CNRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the FRG.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
ST.
LUCIE - UNIT 1
6-12 Amendment No. H~ $)
6.0 ADM N ST T V CONTROLS c.
The change is documented, reviewed by the FRG and approved by the Plant General 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:
a 0 m r lan r
u ainm 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.
-Pl nt Radi i in M
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.
nda Na 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 6-14 Amendment No. 69~~,
140
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555<001 FLORIDA POWER 5 LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF E CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No.
NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Florida Power 8 Light Company, et al. (the licensee),
dated February 28, 1994 and modified by letter dated September 25,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:
2.
Techni cal S eci fications 3.
The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 80
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 25, 1995
TT CHMENT TO LICENSE AMENDMENT NO.
8 TO FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pa es 6-11 6-12 6-14 Insert Pa es 6-11 6-12 6-14
,ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The CNRB shall review:
a.
b.
C.
d.
The safety evaluations for (1) changes to procedures, equipment, or systems and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
Proposed tests or experiments which'nvolve an unreviewed safety question as defined in Section 50.59, 10 CFR.
Proposed changes to Technical Specifications or this Operating License.
e.
Violations of codes, regulations,
- orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
Significant operatinc abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,
- systems, or components that could affect nuclear safety.
Reports and meetings minutes of the Facility Review Group.
AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the CNRB.
These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions.
b.
The performance, training and qualifications of the entire unit staff.
c.
The results of actions taken to correct deficiencies occurring'n unit equipment, structures,
- systems, or method of operation that affect nuclear safety.
ST.
LUCIE - UNIT 2 6"11 Amendment No. +3; 80
hlKHIS (continued) d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 60.
e.
Any other area of unit operation considered appropriate by the CNRB or the President - Nuclear Division.
f.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel.
g.
The fire protection equipment and program implementation at least once per 42 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.
Ihe radiological environmental monitoring program and the results thereof.
i.
The OFFS)TE DOSE CALCULATIONMANUALand implementing procedures.
j.
The PROCESS CONTROL PROGRAM and implementing procedures for dewatering of radioactive bead resin.
6.S.2.9 The technical reyiev responsibilities under the cognizance of the CNRB eha11 encompass:
a.
Plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources that may indicate areas for improving plant safety:
b.
Ce d.
Plant operations, modifications, maintenance, and surveillance to verify independently that these activities are performed safely and correctly and that human errors are reduced as much as practical; Internal and external operational experience information that, may indicate areas for improving plant safetyg and Making detailed recommendations through the Chairman-CNRS for revising procedures, equipment modifications or other means of improving nuclear safety and plant re?iability.
TIMID 6.5.2.10 The CMB shall report to and advise the president - Nuclear Division on those areas of responsibility specified in Specifications 6.5.2.7, 6.5.2.8, and 6.5.2.9.
ST. LUCIE - UNIT 2 6-12
. Amendment No.~ 49; 80
ADMINISTRATIVE CONTR S
ROCEDURES AND PROGRAMS (Continued) f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
guality Control Program for effluent monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974.
guality Control Program for environmental monitoring using the guid-ance in Regulatory Guide 4.1, Revision 1, April 1975.
6.8.2 Each procedure of Specification 6.8. la. through i. above, and changes
- thereto, shall be reviewed by the FRG and shall be approved by the Plant General Nanager prior to implementation and shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8. Ia. through i. above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the FRG and approved by the Plant General 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-a \\
b.
Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the Shutdown Cooling System, High Pressure Safety Injection System, Containment Spray System, and RCS Sampling.
The program shall include the following:
(i)
Preventive maintenance and periodic visual inspection require-
- ments, and (ii)
Integrated leak test requirements for each system at refueling cycle intervals or less.
In-Plant Radioiodine Mo itor 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. ~.
80