ML072980860

Tech Spec Pages for Amendments 202 and 149 Regarding Minor Changes and Corrections to the Technical Specifications

ML072980860
Person / Time
Site:	Saint Lucie
Issue date:	10/22/2007
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Mozafari B, NRR/ADRO/DORL, 415-2020
Shared Package
ML072850821	List: ML072841019 ML072980860
References
TAC MD3497, TAC MD3498
Download: ML072980860 (24)

Text

applicable provisions of the Act and of the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 2700 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 202 are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

Appendix B, the Environmental Protection Plan (Non-Radiological), contains.

environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.

C. Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than March 1, 2016, and shall notify the NRC'in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

D. Sustained Core Uncovery Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.

Renewed License No. DPR-67 Amendment No. 202

E. Fire Protection FPL shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility (The fire protection program and features were originally described in FPL submittals L-83-514 dated October 7,1983, L-83-227 dated April 12,1983, L-83-261 dated April 25,1983, L-83-453 dated August 24,1983, L-83-488 dated September 16, 1983, L-83-588 dated December 14, 1983, L-84-346 dated November 28,1984, L-84-390 dated December 31, 1984, and L-85-71 dated February 21, 1985) and as approved by NRC letter dated July 11,1984, and supplemented by NRC letters dated February 21, 1985, March 5,1987, and October 4, 1988, subject to the following provision:

FPL may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR73.21, is entitled: "Florida Power and Light &

FPL Energy Seabrook Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan - Revision 3," submitted by letter dated May 18, 2006.

G. Mitiqation Strateqy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders Renewed License No. DPR-67 Amendment No. 202

4. This renewed license is effective as of the date of issuance and shall expire at midnight on March 1, 2036.

FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A, Technical Specifications

2. Appendix B, Environmental Protection Plan Renewed License No. DPR-67 Amendment No. 202

TABLE 3.3-1 (Continued)

ACTION STATEMENTS

b. Within one hour, all functional units receiving an input from the inoperable channel are also bypassed or tripped.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> while performing tests and maintenance on than channel provided the other inoperable channel is placed in the tripped condition.

ACTION 3 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> thereafter.

ACTION 4 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />; however, one channel may be bypassed for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1.

ST. LUCIE - UNIT 1 3/4 3-5 SAmendment No. 4-5,_2-, 202

TABLE 3.3-3 (Continued)

TABLE NOTATION (a) Trip function may be bypassed in this MODE when pressurizer pressure is < 1725 psia; bypass shall be automatically removed when pressurizer pressure is > 1725 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Trip function may be bypassed in this MODE below 685 psig; bypass shall be automatically removed at or above 685 psig.

1. The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 8 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

ACTION 9 With the number of OPERABLE channels one less than the.

Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a. The-inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

b. Within one hour, all functional units receiving an input from the inoperable channel are also bypassed or tripped.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ST. LUCIE - UNIT 1 3/4 3-12 Amendment No. 4-, 45, 202

TABLE 3.3-3 (continued)

TABLE NOTATION ACTION 10 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the bypassed or tripped condition and the Minimum Channels OPERABLE requirement is demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel can not be restored to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />, then place the inoperable channel in the tripped condition.

b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also bypassed or tripped.

c. With the number of channels OPERABLE, one less than the Minimum Channels OPERABLE, operation may proceed provided one of the inoperable channels has been bypassed and the other inoperable channel has been placed in the~tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Restore one of the inoperable channels to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> or be in at least HOT STANDBY within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in HOT SHUTDOWN within the following 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

ACTION 11 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channels to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> or be in at least HOT STANDBY within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in HOT SHUTDOWN within the following 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

ACTION 12 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ST. LUCIE - UNIT I 3/4 3-13 Amendment No. -,3-7-,7-, 7-, 88,202

TABLE 3.3-3 (continued)

TABLE NOTATION ACTION 13 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If OPERABILITY can not be restored within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />, be in at least HOT STANDBY within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in HOT SHUTDOWN within the following 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ACTION 14 With the number of channels OPERABLE one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If an inoperable SG level channel can not be restored to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />, then AFAS-1 or AFAS-2 as applicable in the inoperable channel shall be placed in the bypassed condition. If an inoperable SG DP or FW Header DP channel can not be restored to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />, then both AFAS-1 and AFAS-2 in the inoperable channel shall be placed in the bypassed condition. The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also bypassed or tripped.

c. With the number of channels OPERABLE one less than the Minimum Channels OPERABLE, operation may proceed provided one of the inoperable channels has been bypassed and the other inoperable channel has been placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Restore one of the inoperable channels to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> or be in at least HOT STANDBY within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in HOT SHUTDOWN within the following 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

ST, LUCIE - UNIT 1 3/4 3-13a Amendment No. 4-8, 202

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED

1. AREA MONITORS

a. Fuel Storage Pool Area S R M *

b. Containment (CIS) S R M

c. Containment Area - High Range S R M 1, 2, 3 & 4

2. PROCESS MONITORS

a. Fuel Storage Pool Area -

Ventilation System

i. Gaseous Activity S R M **

ii. Particulate Activity S R M **

b. Containment

i. Gaseous Activity S R M 1, 2, 3 4 RCS Leakage Detection ii. Particulate Activity S R M 1, 2, 3 & 4 RCS Leakage Detection

• With fuel in the storage pool or building.

• • With irradiated fuel in the storage pool.

During movement of recently irradiated fuel within containment.

ST. LUCIE - UNIT I 3/4 3-24 Amendment No. 59, 202

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

e. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

f. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1. The force that initiates free movement of, the snubber rod in either tension or compression is less than the specified maximum drag force.

2. Activation (restraining action) is achieved in both tension and compression.

g. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designed service life is based shall be maintained.

Concurrent with the first inservice visual inspection and at least once.

per 18 months thereafter, the installation and maintenance records for each safety related snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 10% prior to the next scheduled snubber service life review. If the indicated service life' will be exceeded by more than-10% prior tothe-next scheduJled-Subberser-vice-life- review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. The results of the reevaluation may be used to justify a change to the service life of the snubber. This reevaluation, replacement or reconditioning shall be-indicated irnthe-records.

ST. LUCIE - UNIT 1 3/4 7-31 Amendment No. 24, 44, 8*3, 140, 202

REFUELING OPERATIONS CONTAINMENT ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The containment isolation system shall be OPERABLE.

APPLICABILITY: During movement of recently irradiated fuel assemblies within containment.

ACTION:

With the containment isolation system inoperable, either suspend all operations involving movement of recently irradiated fuel assemblies within containment or close each of the penetrations providing direct access from the containment atmosphere to the outside atmosphere.

SURVEILLANCE REQUIREMENTS 4.9.9 The containment isolation system shall be demonstrated OPERABLE within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> prior to the start of and at least once per 7 days during movement of recently irradiated fuel assemblies by verifying that containment isolation occurs on manual initiation and on a high radiation signal from two of the containment radiation monitoring instrumentation channels.

ST. LUCIE - UNIT 1 3/4 9-9 Amendment No. 4 -403, 44, 484,4202

ADMINISTRATIVE CONTROLS 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. deleted 6.7 DELETED ST. LUCIE - UNIT 1 6-12 Amendment No. 6", 93, 1-92, 47, 41-7-8, 4-9. _--, 202

6.0 ADMINISTRATIVE CONTROLS 6.8.3 DELETED 6.8.4 The following programs shall be established, implemented, and maintained.

a. Primary 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 visualinspection requirements, and (ii) Integrated leak test requirements for each system at least once per 18 months.

The provisions of Specification 4.0.2 are applicable.

b. In-Plant Radioiodine Monitorincq 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.

ST. LUCIE - UNIT 1 6-14 Amendment No. 6;,4-24, 44G, 4

7R,

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

1. Shall be documented and this documentation shall contain:

a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

b. A determination that the change will maintain-the overall conformance of the solidified waste product to existing re-quirements of Federal, State, or other applicable regula-tions.

2. Shall become effective after the approval of the plant manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

1. Shall be documented and this documentation shall contain:

a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after the approval of the plant manager.

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

ST. LUCIE - UNIT 1 .6-23 Amendment No. 59, 69, 86, 4*,

4-24,:-7-,4-99, 202 .

- 3a -

B. Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 149 are hereby incorporated in the renewed license. FPL shall I operate the facility in accordance with the Technical Specifications.

Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commisson with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.

C. Updated Final Safety Analysis Reoort FPL's Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than April 6, 2023, and shall notify Renewed License No. NPF-16 Amendment No. 149

TABLE 3.3-1 (Continued)

ACTION STATEMENTS ACTION 2 - a. With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

b. With the number of channels OPERABLE one less than the Minimum Channels OPERABLE, STARTUP and/or POWER OPERATION may continue provided the following conditions are satisfied:

1. Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2. All functional units affected by the bypassed/tripped channel shall also be placed in the bypassed/tripped condition.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below:

Process Measurement Circuit Functional Unit Bypassed

1. Safety Channel - Nuclear Instrumentation Wide Range Rate of Change of Power - High (RPS)

Linear Range Variable Power Level - Hgh (RPS)

Local Power Density - High (RPS)

Thermal Margin/Low Pressure (RPS)

2. Pressurizer Pressure - Pressurizer Pressu're - High (RPS)

Thermal Margin/Low Pressure (RPS)

Pressurizer Pressure - Low (ESF)

3. Containment Pressure - Containment Pressure - High (RPS)

Containment Pressure - High (ESF)

4. Steam Generator Pressure - Steam Generator Pressure - Low (RPS)

Thermal Margin/Low Pressure (RPS)

AFAS-1-and-AFAS-2-(AFAS)- .-.-..

Steam Generator Pressure - Low (ESF)

5. Steam Generator Level - Steam Generator Level - Low (RPS)

If SG-2A, then AFAS-1 (AFAS)

If SG-2B, then AFAS-2 (AFAS)

ST, LUCIE - UNIT 2 3/4 3-4 Amendment No. -14g,-7, 149

TABLE 3.3-3 (Continued)

TABLE NOTATION (a) Trip function may be bypassed in this MODE when pressurizer pressure is less than 1836 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 1836 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Trip function may be bypassed in this MODE below 700 psia; bypass shall be automatically removed at or above 700 psia.

• The provisions of Specification 3.0.4 are not applicable.

ACTION OF STATEMENTS ACTION 12 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

ACTION 13 - With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The channel shall be returned to I OPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit Functional Unit Bypassed

1. Containment Pressure - Containment Pressure - High (SIAS, CIAS, CSAS)

Containment Pressure - High (RPS)

2. Steam Generator Pressure - Steam Generator Pressure - Low (MSIS)

AFAS-1 and AFAS-2 (AFAS)

Thermal Margin/Low Pressure (RPS)

Steam Generator Pressure - Low (RPS)

4. Pressurize PLevel r r- Steam Generator Level - I ow (RPS)

If SG-2A, then AFAS-1 (AFAS)

If SG-2B, then AFAS-2 (AFAS)

4. Pressurizer Pressure - Pressurizr Pressure - High (RPS)

Pressurizer Pressure - Low (SIAS)

Thermal Margin/Low Pressure (RPS)

ST. LUCIE - UNIT 2 3/4 3-115 Amendment No. 29, 7-, 149

TABLE 3.3-3 (Continued)

TABLE NOTATION ACTION 20 - With the number of channels OPERABLE one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If an inoperable SG level channel can not be restored to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />, then AFAS-1 or AFAS-2 as applicable in the inoperable channel shall be placed in the bypassed condition.

If an inoperable SG DP or FW Header DP channel can not be restored to*

OPERABLE status within 48 hoers, then both AFAS-1 and AFAS-2 in the inoperable channel shall be placed in the bypassed condition. The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

b With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed in ACTION 13.

c. With the number of channels OPERABLE one less than the Minimum Channels OPERABLE, operation may proceed provided one of the inoperable channels has been bypassed and the other inoperable channel placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Restore one of the inoperable channels to OPERABLE status within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> or be in at least HOT STANDBY within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in HOT SHUTDOWN within the following 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

ST. LUCIE - UNIT 2 3/4 3-16b Amendment No. 4-32, 149

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL (;HANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CA LIBRATION TEST IS REQUIRED

1. AREA MONITORS

a. Fuel Storage Pool Area S R M

i. Criticality and Ventilation System Isolation Monitor

b. Containment - Isolation S R M

c. Control Room Isolation S R M ALL MODES

d. Containment Area - High Range S R M 1,2,3, &4

2. PROCESS MONITORS

a. Fuel Storage Pool Area - Ven-tilation System

• • r

i. Gaseous Activity S R M ii. Particulate Activity S R M

b. Containment

i. Gaseous Activity S R M 1,2, 3, &4 a) RCS Leakage Detection ii. Particulate Activity S R M 1,2,3, &4 a) RCS Leakage Detection

• With fuel in the storage pool or building.

• • With irradiated fuel in the storage pool.

During movement of recently irradiated fuel within containment.

ST. LUCIE - UNIT 2 3/4 3-28 Amendment No: 149

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

h. Snubber Seal Replacement ProQram The seal service life of hydraulic snubbers shall be monitored and documented to ensure that the seals do not fail between surveillance inspections.

The maximum expected service life for the various seals, seal materials, and applications shall be estimated based on engineering information and the seals shall be replaced so that the maximum expected service life does not expire during a period when the snubber is required to be OPERABLE.

Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission ifa justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

ST. LUCIE - UNIT 2 3/4 7-24 Amendment No. 2-2, 5-1,149

REFUELING OPERATIONS 3/4.9.9 CONTAINMENT ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The containment isolation system shall be OPERABLE.

APPLICABILITY: During movement of recently irradiated fuel within containment.

ACTION:

With the containment isolation system inoperable, either suspend all operations involving movement of recently irradiated fuel assemblies within containment or close each of the containment penetrations providing direct access from the containment atmosphere to the outside atmosphere.

SURVEILLANCE REQUIREMENTS 4.9.9 The containment isolation system shall be demonstrated OPERABLE within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> prior to the start of and at least once per 7 days during movement of recently irradiated fuel by verifying that containment isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels.

.ST. LUCIE - UNIT 2 3/4 9-10 Amendment No. 8-7, 4-27, 14 9

TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS CYCLIC OR DESIGN CYC-LE COMPONENT TRANSIENT LIMIT OR TRANSIENT Reactor Coolant System 500 system heatup and cooldown Heatup cycle - Tavg from < 200OF cycles at rates < 100°F/hr. to > 532 0F; cooldown cycle -;

Tavg from > 5320 F to < 2000 FJ 500 pressurizer heatup and Heatup cycle - Pressurizer temperature cooldown cycles at rates from < 200OF to > 653 0F; cooldown

< 200°F/hr. > 653 0 F to < 200OF 10 hydrostatic testing cycles. RCS pressurized to 3110 psig with RCS temperature > 60°F above the most limiting componernts' NDTT value.

200 leak testing cycles. RCS pressured to 2250 psia with RCS temperature greater than minimum for hydrostatic testing, but ýess than minimum RCS temperature for criticality.

400 reactor trip cycles. Trip from 100% of RATED THERMAL POWER.

40 turbine trip cycles with Turbine trip (total load rejection) delayed reactor trip. from 100% of RATED THERMAL POWER followed by resulting reactor trip.

ST. LUCIE - UNIT 2 5-5 Amendment No. 14 9

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENTS 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. deleted 6.7 DELETED 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 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. Not Used.

e. Not Used.

ST. LUCIE - UNIT 2 6-13 Amendment No. 1-3, 2-9, 4-7, 86, 4-24,

--4-, 149

6.0 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4 The following programs shall be established, implemented, and maintained.

a. Primary 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 requirements, and (ii) Integrated leak test requirements for each system at least once per 18 months.

The provisions of Specification 4.0.2 are applicable.

b. In-Plant Radioiodine Monitorinq 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.

ST. LUCIE - UNIT 2 6-14a Amendment No. 9-1, 446, 149

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

1. Shall be documented and this documentation shall contain:

a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing re-quirements of Federal, State, or other applicable regulations.

2. Shall become effective after the approval of the plant manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

1. Shall be documented and this documentation shall contain:

a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and b) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after the approval of the plant manager.

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicatinq the area of the paqe that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

ST ICIE - UJNIT 2 6-23 Amendment No. 4-3 2-5 4-5 60.

'54, 6, 4-46, 414+9