Text

Proposed License Amendments Re Minor Changes/Corrections to Technical Specifications
	ML063040607
Person / Time
Site:	Saint Lucie
Issue date:	10/19/2006
From:	Johnston G; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2006-221
	Download: ML063040607 (58)
	v • d • e

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 0 October 19, 2006 FPL L-2006-221 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Minor Changes/Corrections Pursuant to 10 CFR 50.90, Florida Power and Light Company (FPL) requests to amend Facility Operating Licenses DPR-67 for St. Lucie Unit I and NPF-16 for St. Lucie Unit 2 by incorporating the attached Technical Specifications (TS) revisions. The proposed amendments are required to correct various minor errors within the existing Technical Specifications.

Attachment 1 is an evaluation of the proposed changes. Attachment 2 is the "Determination of No Significant Hazards Consideration." Attachment 3 provides the proposed changes to the TSs, and Attachment 4 provides the word-processed TS changes.

The St. Lucie Facility Review Group and the FPL Company Nuclear Review Board have reviewed the proposed amendments. In accordance with 10 CFR 50.91 (b) (1), copies of the proposed amendments are being forwarded to the State Designee for the State of Florida.

There is no particular requested need date for this licensing action request. Please issue the amendments to be effective on the date of issuance and to be implemented within 60 days of receipt by FPL. Please contact Ken Frehafer at (772) 467-7748 if there are any questions about this submittal.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on the day of _ _ _, 2006.

Ve13 mty yours, Gor--d'-n L. Johnston Site Vice President St. Lucie Plant GLJ/KWF Attachments cc: Mr. W. A. Passetti, Florida Department of Health and Rehabilitative Services Auci an FPL Group company

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 1 of 10 Minor Changes/Corrections EVALUATION OF PROPOSED TS CHANGES

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 2 of 10 Minor Changes/Corrections Introduction Florida Power and Light Company (FPL) requests to amend Facility Operating Licenses DPR-67 for St. Lucie Unit 1 and NPF-16 for St. Lucie Unit 2 by incorporating the attached Technical Specifications (TS) revisions. The proposed amendments are required to correct various discrepancies within the existing Technical Specifications.

Background/Discussion/Justification for Change The background and justification for the changes are discussed below. TS page mark ups for the proposed changes are in Attachment 3.

Corrections Associated With the Relocation of TS Administrative Requirements to Licensee Controlled Programs TS Changes On November 21, 2003, FPL docketed FPL letter L-2003-246 for a proposed change to the St.

Lucie Unit 1 and 2 TSs to relocate certain provisions of TS Section 6.0, Administrative Controls, to license controlled documents such as the FPL Topical Quality Assurance Report (TQAR) and the St. Lucie Unit 1 and Unit 2 Updated Final Safety Analysis Reports (UFSAR). The submittal justified relocating the administrative TS controls for the Facility Review Group (FRG), the Company Nuclear Review Board (CNRB), and record retention requirements to the FPL TQAR.

The NRC approved the relocation for these administrative TS controls to the FPL TQAR in the NRC SER dated March 11, 2004 for St. Lucie Units 1 and 2 TS amendments 189/133.

FPL subsequently identified several TS changes that should have been within the scope of the original submittal and NRC SER.

1. Both units have TS requirements associated with FRG responsibilities. The FRG and its responsibilities have been relocated to the TQAR. Therefore, FPL proposes to revise the following TS to delete references to FRG and FRG responsibilities that now reside in the FPL TQAR

" Unit 2 TS Table 3.3-1 ACTION 2a will be revised to delete the requirement to review the desirability of maintaining inoperable RPS channels in the bypass condition in accordance with TS 6.5.6.m. TS 6.5.6.m was a review function of the FRG that was relocated to the TQAR.

TS Table 3.3-3 ACTION 14a (Unit 1) and ACTION 13 (Unit 2) and ACTION 20a (Unit 2) will be revised to delete the requirement to review the desirability of maintaining inoperable ESFAS channels in the bypass condition in accordance with TS 6.5.6.m. TS 6.5.6.m was a review function of the FRG that was relocated to the TQAR.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 3 of 10 Minor Changes/Corrections

TS 6.13.2 for both units will be revised to delete the relocated FRG review and acceptance functions associated with changes to the Process Control Program.

TS 6.14.2 for both units will be revised to delete the relocated FRG review and acceptance functions associated with changes to the Offsite Dose Calculation Manual (ODCM).

2. Both units have requirements associated with CNRB audit functions for the programs listed in TS 6.8.4. TS 6.8.4 for both units will be revised to delete the reference to program audit requirements.

3. Both Units have FRG, CNRB, and corporate officer review functions for REPORTABLE EVENTS that have been relocated to the TQAR. TS 6.6.1 .b for both units will be revised to delete these relocated review functions.

4. Both units have requirements associated with TS record retention. TS record retention requirements were relocated to the TQAR. Therefore, FPL proposes to revise the TS listed below to delete the record retention requirements.

Unit 1 TS Surveillance Requirement (SR) 4.7. 10.g will be revised to delete the requirement for record retention associated with Snubber Service Life Monitoring.

Unit 2 TS SR 4.7.9.h will be revised to delete the requirement for record retention associated with the Snubber Seal Replacement Program.

" TS 6.13.1 for both units will be revised to delete the requirements for record retention associated with the Process Control Program.

TS 6.14.1 for both units will be revised to delete the requirements for record retention associated with the Offsite Dose Calculation Manual (ODCM).

With the exceptions noted below, the above changes are justified by the original submittal and NRC SER for the relocation of TS administrative requirements to licensee controlled documents. These changes are within the scope of the NRC guidance on the relocation of Technical Specifications provisions that are not specifically required by 10 CFR 50.36(c)(5) and not otherwise necessary in TS for the safe operation of the plant from the plant license to licensee controlled documents. This NRC position was provided in amendments to 10 CFR 50.36, Final Rule, Technical Specifications, 60 FR 36593 (July 19, 1995), Standard Technical Specifications (STS) for Combustion Engineering Plants (NUREG-1432), dated April 1995, and Administrative Letter (AL) 95-06, Relocation of Technical Specification Administrative ControlsRelated to Quality Assurance, issued on December 12, 1995. AL 95-06 provides specific guidance for relocating TS provisions of reviews and audits, procedure review processes, and records and records retention to the Quality Assurance (QA) Plan.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 4 of 10 Minor Changes/Corrections The deletion of the TS required FRG review functions associated with extended bypass conditions and changes to the Process Control Program and ODCM is further justified by the NRC approved TSTF-76, Revision 1, Remove References to the Onsite Review Function. The TSTF states that the ISTS have no requirements for onsite review of bypassed protective channels and changes to the ODCM, and that the onsite review committee review and audit functions have been relocated to licensee controlled documents. The onsite review function for changes to the Process Control Program is not specifically mentioned in the TSTF, but the elimination of that TS review function meets the intent of reviews relocated to and governed by licensee controlled documents. As stated earlier, St. Lucie's onsite review functions were relocated to the TQAR, and these changes should have been within the scope of the original FPL submittal on Administrative TS changes.

The deletion of the program audit requirements associated with the programs listed in TS 6.8.4 is justified for the following reasons:

The audit frequency for programs audited by the QA Department is governed by FPL Quality Instruction 18 QAD 3, Scheduling of Quality Assurance DepartmentAudit Activities.

The audit scope and CNRB interface for programs audited by the QA Department are defined in St. Lucie Quality Department Administrative Letter SLQD AL- 13, Surveillance Program Scoping and Scheduling.

The majority of the programs listed in TS 6.8.4 had their associated CNRB audit functions relocated to the TQAR as part of license amendments 189/133.

" The CNRB audit functions associated with TS programs 6.8.4.a, PrimaryCoolant Sources Outside Containment,and 6.8.4.b, In-PlantRadioiodineMonitoring, had no corresponding CNRB audit functions that were previously relocated to the TQAR. However, as described earlier, these program audits are also governed by licensee controlled procedures that control St.

Lucie Plant QA audit scope and scheduling.

" Additionally, similar to the justification for removal of onsite review requirements in TSTF-76 above, the ISTS have no program audit requirements in the administrative TSs.

The audit requirements for the programs listed in TS 6.8.4 have been relocated to licensee controlled documents such as the TQAR and/or other QA procedures. Consistent with the ISTS, the audit requirement for TS required programs and can be removed from the TSs. These changes should have been within the scope of the original FPL submittal on administrative TS changes.

Corrections Associated With the Recently Irradiated Fuel TS Changes On May 23, 2002, FPL docketed FPL letter L-2002-089 for a proposed change to the St. Lucie Unit 1 and 2 TSs to incorporate line item improvements associated with the handling of recently

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 5 of 10 Minor Changes/Corrections irradiated fuel assemblies in accordance with Revision 2 of NUREG-1432, Standard Technical Specifications Combustion EngineeringPlants (STS), and a portion of Nuclear Energy Institute (NEI) TS Task Force (TSTF) change traveler TSTF-5 1, Revision 2. TSTF-51 removed the TS applicability regarding operability of certain systems (containment penetrations, spent fuel pool and shield building ventilation, and containment isolation) when handling fuel that has decayed a sufficient period of time such that dose consequences for the postulated FHA remain below the limits of the SRP when these systems are not available. The NRC approved the TS changes in the SER for St. Lucie Units 1 and 2 amendments 184/127 dated August 30, 2002.

FPL subsequently identified TS changes that should have been within the scope of the original submittal and NRC SER.

1. TSTF-5 1, Revision 2 included an ACTION for the refueling containment penetration TS to immediately suspend all operations involving movement of recently irradiated fuel in the containment. However, the St. Lucie refueling TS 3.9.9 for containment isolation does not have a NUREG-1432 counterpart and changes to the St. Lucie TS was not specifically addressed as part of the TSTF. Although the change to the LCO applicability for TS 3.9.9 met the intent of TSTF-5 1, the action to immediately suspend all operations involving movement of recently irradiated fuel in the containment was not incorporated as part of the proposed change.

FPL proposes to revise TS 3.9.9 for both units such that the action with the containment isolation system inoperable will allow either the immediate suspension of all operations involving movement of recently irradiated fuel in the containment or closure of each of the containment penetrations providing direct access from the containment atmosphere to the outside atmosphere.

This change is justified because the proposed action is consistent with the actions proposed for inoperable containment penetrations during refueling operations. This action meets the intent of TSTF-5 1, Revision 2, and is within the scope of the original FPL submittal and NRC SER.

2. On September 18, 2003 FPL docketed FPL letter L-2003-199 that included a proposed change to the St. Lucie Unit 1 and 2 TSs to resolve inconsistencies in the radiation monitoring TS related to previously approved amendments 184/127. The TS amendments changed the LCO applicability for the containment isolation system (CIS) radiation monitors from Mode 6 to "During movement of recently irradiated fuel assemblies within containment" in TS Tables 3.3-6 for both units. The NRC approved the change in the LCO applicability for the CIS radiation monitors in the SER for the St. Lucie Units 1 and 2 amendments 197/139 dated September 27, 2005. However, the modes for the CIS radiation monitor surveillance applicability were not changed as part of the TS amendments.

FPL proposes to revise TS Table 4.3-3 for both units to change the modes for which the surveillance is applicable from Mode 6 to "During movement of recently irradiated fuel assemblies within containment."

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 6 of 10 Minor Changes/Corrections This change is justified because the TS changes associated with Units 1 and 2 TS amendments 184/127 changed the LCO action statements associated with the CIS radiation monitors to comply with the LCO of TS 3.9.9 (Containment Isolation System). TS amendments 184/127 changed the applicability of the LCO for TS 3.9.9 to "During the movement of recently irradiated fuel assemblies within containment," however, those amendments did not change the LCO applicability for the CIS radiation monitors. St. Lucie Units 1 and 2 amendments 197/139 changed the LCO applicability for the CIS radiation monitors to match the applicability of TS 3.9.9. The proposed change in the surveillance mode applicability for the CIS radiation monitor is consistent with the current TS requirement for containment isolation system operability.

Corrections Associated With the AFAS Trip/Bypass Requirements TS Changes On October 18, 2001, FPL docketed FPL letter L-2001-216 for a proposed change to the St. Lucie Unit 1 and 2 TSs to limit the period of time that inoperable auxiliary feedwater actuation signal (AFAS) input channels could be in the bypass and/or tripped condition in order to enhance the functional capability and performance levels of equipment. As discussed in the submittal, placing an AFAS channel in indefinite trip is not appropriate because an additional single failure would result in the feeding of a faulted steam generator. The TS change involved placing a limit for the amount of time an AFAS channel could be in trip, at which time the affected channel would be placed in bypass. The NRC approved the TS change in the SER for St. Lucie Units 1 and 2 TS amendments 188/132 dated September 30, 2003.

FPL subsequently identified TS changes that remove internal inconsistencies with the approved TS wording and are within the scope of the original submittal and NRC SER. Therefore, FPL proposes the following changes.

1. Action Statement 2 of St. Lucie Unit 1 TS Table 3.3-1 for RPS requires that an inoperable steam generator level channel, and all related functional units, be placed in the tripped condition after 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . However, Action Statement 14 of Table 3.3-3 for AFAS would require that an inoperable steam generator level channel, and all related functional units, be placed in the bypassed condition after 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

FPL proposes to resolve this discrepancy by modifying Action Statement 2.b to simply state "Within one hour, all functional units receiving an input from the inoperable channel are also bypassed or tripped". The portion of the Action Statement concerning "placed in the same condition ... as that required by a. above for the inoperable channel" will be deleted.

2. Action Statements 9.b & 14.b for St. Lucie Unit 1 TS Table 3.3-3 for ESFAS have the identical wording of RPS Action Statement 2.b. The "same condition" requirement contained in the existing action statement wording creates the same discrepancy for inoperable steam generator level and pressure channels as that described above.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 7 of 10 Minor Changes/Corrections FPL proposes to resolve this discrepancy by modifying Action Statements 9.b and 14.b to simply state "Within one hour, all functional units receiving an input from the inoperable channel are also bypassed or tripped". The portion of the action statement concerning "placed in the same condition ... as that required by a. above for the inoperable channel" will be deleted.

3. Action Statement 10.b for St. Lucie Unit I TS Table 3.3-3 for ESFAS has the identical wording of RPS Action Statement 2.b. Action Statement 10.b is only applicable to an inoperable CSAS containment pressure channel. Although containment pressure is used in multiple functional units, the "same condition" requirement contained in the existing action statement wording does not create any discrepancy between equally applicable action statements. However, this action statement will be revised to be consistent with Action Statements 2.b (RPS), 9.b (ESFAS) and 14.b (ESFAS).

The changes for items 1, 2, and 3 above are justified for the following reasons:

Certain measurement channel parameters are utilized by multiple protection system functions. For example, steam generator level is used by the RPS low water level trip function and by the AFAS actuation function. The purpose of the action statement is limited to providing redundant assurance that required mitigating actions are implemented for all affected protection system functions in the event of a measurement channel failure. In the event of a measurement channel failure, each RPS and ESFAS action statement applicable to that parameter will be independently entered into and complied with.

It is inappropriate for the action statement to dictate the required condition (bypassed or tripped) of other affected functional unit(s) since the required condition is controlled by the action statements applicable for affected functional unit(s).

" It is contradictory that the "same condition" be mandated for all applicable functional units.

This "same condition" requirement implies that the "safe" condition for all functional units associated with a given measurement parameter is the tripped condition (which was correct prior to TS amendments 188/132). However, the July 18, 2002 submittal demonstrated that bypass, rather than trip, is the most conservative condition for AFAS functional units in the event of an inoperable channel. Consequently, inclusion of the words "same condition" create a conflict between the requirements of AFAS functional unit end states (i.e., bypass) and the requirements of RPS functional unit end states (i.e., tripped) for an inoperable steam generator level or steam generator pressure channel.

" Equivalent St. Lucie Unit 2 action statements do not include this "same condition" requirement. In addition, the proposed wording of the revised action statements closely resembles the existing wording of equivalent St. Lucie Unit 2 action statements.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 8 of 10 Minor Changes/Corrections

4. Action Statement 14.a (Unit 1) and 20.a (Unit 2) to TS Table 3.3-3 for ESFAS is applicable to the following auxiliary feedwater instrument channels:

steam generator level channels used for AFAS actuation

steam generator differential pressure channels used for AFAS isolation

feedwater header differential pressure channels used for AFAS isolation As currently written these action statements require that "If the inoperable channel can not be restored to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then both AFAS-1 and AFAS-2 in the inoperable channel shall be placed in the bypassed condition." This requirement is appropriate for the differential pressure measurement channels used for AFAS isolation. However, the requirement to bypass both AFAS- 1 and AFAS-2 for an inoperable steam generator level channel is not appropriate, and is also not consistent with existing definitions of which functional units are associated with which process measurement channels.

FPL proposes to resolve this discrepancy by adding an additional sentence to these action statements to differentiate between the functional unit bypass requirements for inoperable steam generator level and differential pressure channels. The new sentence specifically added for steam generator level will read as follows: "If an inoperable SG Level channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then AFAS-1 or AFAS-2 as applicable in the inoperable channel shall be placed in the bypassed condition." The existing sentence will be annotated with a measurement channel applicability qualifier as follows: "If an inoperable SG DP or FW Header DP channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then both AFAS-1 and AFAS-2 in the inoperable channel shall be placed in the bypassed condition."

These changes are justified as follows:

The action statements applicable to inoperable AFAS measurement channels were extensively revised in response to two separate postulated failure scenarios that could compromise the AFAS rupture detection/isolation logic. The first scenario was identified as the indefinite trip scenario, and the remedy imposed by amendments 188/132 was to limit the amount of time that an AFAS channel could remain in the tripped condition. There is no residual discrepancy associated with this portion of the TSs. The second scenario was identified as the indefinite bypass scenario, where in response to a differential pressure measurement channel failure only one of the two AFAS functional units (i.e., either AFAS- 1 or AFAS-2) was bypassed. This precondition, in conjunction with a single failure of a second differential pressure channel and a feedwater header rupture event, could result in feeding a ruptured steam generator. The remedy imposed by amendments 188/132 was to specify that both AFAS-1 and AFAS-2 must be bypassed in the inoperable channel. Review of these scenarios, and the related justification for amendments 188/132, clearly shows that the rational for ensuring that both AFAS- 1 and AFAS-2 are bypassed is limited to failures

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 9 of 10 Minor Changes/Corrections involving the steam generator differential pressure or feedwater header differential pressure channels, and not steam generator level channels.

Review of the AFAS actuation and rupture detection logic circuits clearly shows that the low level channels of steam generator A are dedicated to the AFAS- 1 logic circuits, and the low level channels of steam generator B are dedicated to the AFAS-2 logic circuits. In contrast, the steam generator A pressure signals are compared with the steam generator B pressure signals to determine if the differential pressure rupture detection setpoints are exceeded. Likewise, the feedwater header A pressure signals are compared with the feedwater header B pressure signals to determine if those differential pressure rupture detection setpoints are exceeded. Based on the way in which these measurement channel signals are used in the AFAS logic, it is clear that an inoperable SG or FW header pressure channel would affect the rupture logic of both AFAS-1 and AFAS-2.

" St. Lucie Unit 2 RPS TS Table 3.3-1 Action Statement 2, and ESFAS TS Table 3.3-3 Action Statements 13 and 14, identify the functional unit requirements for inoperable AFAS related measurement channels. These AFAS related functional unit requirements were clarified several years ago by Amendment 73, and are correct as currently written. The functional unit requirements for Steam Generator Level - Low are defined as follows:

"If SG-2A, then AFAS-1 (AFAS)", and "If SG-2B, then AFAS-2 (AFAS)".

The functional unit requirements for Steam Generator Pressure - Low are defined as follows:

"AFAS-1 and AFAS-2 (AFAS)",

The proposed change will make the action statements consistent with the functional unit definitions currently contained in the Unit 2 Technical Specifications.

Miscellaneous Typographical Corrections

1. The St. Lucie Unit 1 License Condition 3.E for Fire Protection reflects an incorrect date for a listed NRC letter. The date for the letter listed as "dated July 17, 1984" should be July 11, 1984.

FPL proposes to correct the date as an administrative change.

2. The St. Lucie Unit 2 TS Table 5.7-1 incorrectly sets the upper bound for RCS heatup and cooldown transients at 545 'F. The St. Lucie Unit 2 UFSAR Table 3.9-2, "Transients Used In Design And Fatigue Analysis," states that upper bound for the 500 heatup and cooldown cycles during the design life of the plant is 532 'F. The existing lifetime heatup and cooldown count is not affected by this TS inaccuracy because plant procedures use the UFSAR designated 532 'F

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 1 Proposed License Amendments Page 10 of 10 Minor Changes/Corrections upper bound for the design heatup and cooldown count. FPL proposes to correct TS Table 5.7-1 as an administrative change. Additionally, the table has several other typographical errors that are being corrected as administrative changes:

The table uses the word "heat" instead of"heatup" in the design 500 pressurizer heatup and cooldown cycles discussion.

The table uses the word "critically" instead of "criticality" in the design 200 leak testing cycles discussion.

There is an extraneous period in the design 40 turbine trip cycles discussion.

Conclusion As discussed above, these proposed changes to the TS are needed to correct errors that are either administrative in nature or changes that should have been included in previously approved licensing actions.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 2 Proposed License Amendments Page 1 of 3 Minor Changes/Corrections DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 2 Proposed License Amendments Page 2 of 3 Minor Changes/Corrections DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Descriptionof amendment request: The proposed license amendments (PLAs) to Facility Operating Licenses DPR-67 for St. Lucie Unit 1 and NPF-16 for St. Lucie Unit 2 are necessary to correct existing minor errors within the Technical Specifications.

Pursuant to 10 CFR 50.92, a determination may be made that a proposed license amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Each standard is discussed as follows.

(1) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

These proposed license amendments require no plant hardware or operational modifications. The proposed changes either correct various administrative errors or incorporate changes that have been justified by previously approved license amendments and should have been made as part of those submittals. Therefore, operation of the facility in accordance with the proposed amendments would not involve a significant increase in the probability or consequences of an accident previously evaluated.

(2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.

No modifications to either plant hardware or operational procedures are required to support these proposed license amendments; hence, no new failure modes are created. The proposed changes either correct various administrative errors or incorporate changes that have been justified by previously approved license amendments and should have been made as part of those submittals.

Therefore, operation of the facility in accordance with the proposed amendments would not create the possibility of a new or different kind of accident from any accident previously evaluated.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-3 89 Attachment 2 Proposed License Amendments Page 3 of 3 Minor Changes/Corrections (3) Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

The TS corrections proposed by these license amendments are administrative in nature in that they either correct typographical errors (e.g., letter dates and transient limits) or are justified by previous license amendments (i.e., relocation of administrative programs to the TQAR, the implementation of TSTF-51 for recently irradiated fuel, and correct inconsistencies introduced by AFAS trip and bypass requirements). Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

Based on the above discussion and the supporting evaluation of Technical Specification changes, FPL has determined that the proposed license amendments involve no significant hazards consideration.

Environmental Consideration The proposed license amendments do not change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The proposed amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite, and no significant increase in individual or cumulative occupational radiation exposure. FPL has concluded that the proposed amendments involve no significant hazards consideration and meet the criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and that, pursuant to 10 CFR 51.22(b), an environmental impact statement or environmental assessment need not be prepared in connection with issuance of the amendments.

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 1 of 22 Minor Changes/Corrections ST. LUCIE PLANT MARKED-UP TECHNICAL SPECIFICATION PAGES Unit 1 License Condition Page 4 3/4 3-5 3/43-12 3/4 3-13 3/4 3-13a 3/4 3-24 3/4 7-31 3/4 9-9 6-12 6-14 6-23 Unit 2 3/4 3-4 3/4 3-15 3/4 3-16b 3/4 3-28 3/4 7-24 3/4 9-10 5-5 6-13 6-14a 6-23

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 2 of 22 Minor Changes/Corrections

. . "-4-:

E. Fire Protection FPL shall implement and maintain in effect all provisions of the a oved pp fire protection program as described in the Updated Final Safety Anal sis Report for the facility (The fire protection program and features were origina y described in FPL submittals L-83-514 dated October 7,1983, L-83-227 dated pril 12,1983, L-83-261 dated April 25,1983, L-83-453 dated August 24,1983, 488 dated September 16,1983, L-83-588 dated December 14, 1983, L-84-46 dated November 28,1984, L-84-390 dated December 31, 1984, and L- -71 dated February 21, 1985) and as approved by NRC letter dated July ,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. 5 4 (p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: 'Florida Power and Light &

FPL Energy Seabrook Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan," submitted by letter dated September 23, 2004, and supplemented on October 15, October 22, and October 29, 2004.

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 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 Revised by letter dated October 29, 2004

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 3 of 22 Minor Changes/Corrections TABLE 3.3-1 (Continued)

ACTION STATEMENTS*

b. Within one hour, all functional units receiving an input from the inoperable channel are also paIe4d-.".

thc zama condition (litherbypassed or tripped, ee,

.pc c tht e a. abov f the haznnl.

erz~l

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to I hour for surveillance testing per Specification 4.3.1.1.1.

ST. LUCIE - UNIT I 3/4 3-5 Amendment No. 45, 27

St. Lucie Units I and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 4 of 22 Minor Changes/Corrections 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.

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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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-plaeed the siw dine-*

"i- ",bypassed or tripped.es aptliczb* ) ca that . ,qir by ........ ,-the

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ST. LUCIE - UNIT I 3/4 3-12 Amendment No. 4-5, 45

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 5 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If the inoperable channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then place the inoperable channel in the tripped condition.

b. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , all functional units receiving an input from the inoperable channel are also pleced in tho cthe eame rdite* (the, bypassed or tripped. as appieble) ras ui;id by a .b...f.. z .. ......... nnol.

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ST. LUCIE - UNIT I 3/43-13 Amendment No. 45, 3U, 58, 72, 188

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 6 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If OPERABILITY can not be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. The Minimum Channels OPERABLE requirement is met; however,* one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 pro d rovid i i e satisfied: S. eta- GvJ bir

a. The inopre channel is aced in eithe the bypassed or tripped Sionwithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If. inoperable hannel can not be restored to 7OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then both AFAS-1 and AFAS-2 in the inoperable channel shall be placed in the bypassed condition. -if-the ip/rable ehar,,el is byp'assd, the simbilite-.*. ,,-ita,; ,u ,;

chanal n to b znitim dazc sh,,ll berveve in seerd, e vth Spesitifietn 9869.11.96... The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

b. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , all functional units receiving an input from the inoperable channel are also pl.cod in th3 csmecendition (eith.. bypassed or tripped,.C st ansp r-gu.... byh bont for the rthle

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ST. LUCIE - UNIT 1 314 3-13a Amendment No. 188

" C) 0 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES INWHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED c 00

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 RCS Leakage Detection S R M 1,2,3&4 ii. Particulate Activity S RCS Leakage Detection R M 1,2,3&4 With fuel in the storage pool or building.

ST. LUCIE - UNIT 1 3/4 3-24 Amendment No. 59 0 CD

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 8 of 22 Minor Changes/Corrections 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 to the next scheduled snubber service 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 in the records.

ST. LUCIE - UNIT 1 3/4 7-31 Amendment No. 24, 44, 83, 110

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 9 of 22 Minor Changes/Corrections 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, close each of the penetrations providing direct access from the containment atmosphere to~he outside atmosphere.

SURVEILLANCE REQUIREMENTS 4.9.9 The containment isolation system *all be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of and least once per 7 days during movement of recently irradiated fuel assembli' _by verifying that containment isolation occurs on0 manual initiation and on a high adiation signal from two of the containmentradiation monitoring instrumentation ch nnels..

"I ST. LUCIE - UNIT 1 3/4 9-9 Amendment No. 40,403,448. 184

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 10 of 22 Minor Changes/Corrections ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following action/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 50oemd,

b. EsJ ePOTBE V Of the .. O....

.h... 66 u. Mit.

.. ~4e4~e

~ielear~

6.7 DELETED ST. LUCIE - UNIT 1 6-12 Amendment No. 4R, 03, 402,4Z, 478, 484, 199

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 11 of 22 Minor Changes/Corrections 6.0 ADMINISTRATIVE CONTROLS 6.8.3 DELETED 6.8.4 The following programs shall be established, implemented rnaintained. a,.-el..h4_-_

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 Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration invital 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 I 6-14 Amendment No. 69, 42-6, 440, 4-4, 47-7, 489,199

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 12 of 22 Minor Changes/Corrections ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

I. Shall be documented and .... fd; .f FeyqeA.t

. Prfar..d cha.. be

atain.. d a. F rc..- d by ....... I .. - ..is 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 overal conformance of the solidified waste product to existing re-quirements of Federal, State, or other applicable regula-tions.

2. Shall become effective after rc" r" -ad acptane -by.tho Fe.eit Rflyi.w rcuFp and the approval of the plant manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

1. Shall be documented and fee.rds e;r.;,vie ýPFc,-,.Ad qhall be otelinod as ,quied by Cpeifi,*et.on 6.1-.2. J6is 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 rtaiow end aczonc. by th-c F*Cil'ty R-eview Ctifp athe 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., monthlyear) the change was implemented.

ST. LUCIE - UNIT 1 6-23 Amendment No. 69, 69, 86, 423, 42-5,4-7, 199

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 13 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . if the

nePcable ch~nnol Isbypassed, tha.sdýiltyý 1b4riOUwed inAccorda.-.th Spzoificctcn 6.6.1 .6m.

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 Pressure - 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 2 314 3-4 Amendment No. 48, 73

St. Lucie Units 1 and 2 L-2006-22 1 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 14 of 22 Minor Changes/Corrections 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at-least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Ift4haino-.a.a.lo chnz bypassed, the desirabilty of 1.16.c i i, bypass-' Gonditicn salb r~~owt Spesitleati s 6* 5"1Or The channel shall be returned to 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)

3. Steam Generator Level - Steam Generator Level - Low (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 3143-15 Amendment No. 2-, 73

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 15 of 22 Minor Changes/Corrections TABLE 3.3-3 (Continued)

TABLE NOTATION ACTION 20 - With the number of channels OPERABLE one less than the Total Number of Channels, operatioj procee ditions are satisfied: C>) ( vJ4Aýeat* w

a. The inoperable cljannel is pla in either the bypassed or tripped condition ith our If- inoperable hannel can not be restored to OPERABLE.

status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then both AFAS-1 and AFAS-2 in the inoperable channel shall be placed in the bypassed condition. ei*n*,operable rhaonnl is bypassed, 1he desiribilit; -f.m-i-t~irin IN. eI-l ineHRhe bypassed eendtifn shall b acco, dn v Specifkeft;er-.

65A* 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT

, ~6STANDBY hours.

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following ST. LUCIE - UNIT 2 3/4 3-16b Amendment No. 132

CD TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w 00 CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED

1. AREA MONITORS '00

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

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.

'_ ST. LUCl E- _UNý2 IT CDN 0 CD t' N)

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 17 of 22 Minor Changes/Corrections PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (continued)

h. Snubber Seal Replacement Projram "rn &%*.trAJ The seal service life of hydraulic snubbers shall be monitored to ensure that the seals do not fail between surveillance inspe ons.

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. The ,... rGploazmc zh*,l ,-

'-4:th Spz*c*if..tlen 6.10.2.

L Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a 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. 22, 51

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments page 18 of 22 Minor Changes/Corrections REFUELING OPERATIONS 314.9.9 CONTAINMENT ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The containment isolation system shall be OPERABLE.

APPUCABILITY: During movement of recently irradiated fuel within containment.

ACTION:

With the containment isolation system inoperable, close each of the containment penetrations providing direct access from the containment atmo)phere to the outside atmosphere.

SURVEILLANCE REQUIREMENTS :

4;9.9 The containment isolation system shall Ie demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of and at leas 'once per 7 days during movement of recently irradiated fuel by verifying that ontainment isolation occurs on manual initiation and on a high radiation test s nal from each of the containment radiation monitoring instrumentation channels.Is_

ST. LUCIE - UNIT 2 3/4 9-10 Amendment No. 87, 127

-~0 0

TABLE 5.7-1 0 C COMPONENT CYCLIC OR TRANSIENT LIMITS CD CYCLIC OR DESIGN CYCLE COMPONENT TRANSIENT LIMIT OR TRANSIENT 10 Reactor Coolant System 500 system heatup and cooldown Heatup ýT- from < 200 0 F S3-z5 F cycles at rates < 100°F/hr. to > 5 cooldown cycle -.

fyTavag from~ to <200*F 500 pressurizer heatup and "Heacycle - Pressurizer temperature cooldown cycles at rates from < 2001F to > 653°F; cooldown

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

200 leak testing cycles. RCS pressured to 2250 psia with RCS temperature greater than minimum for hydrostatic testing, but less than minimum RCS temperature for 400 reactor trip cycles. Trip from 100% of RATED THERMAL POWER.

40 1turbine trip cycles with Turbine trip (total load rejection) delayed reactor trip. from 100% of RATED THERMAL POWERA followed by resulting reactor trip.

ST. LUCIE - UNIT 2 5-5 0Q t7 0D 0 0

0 IQ

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 20 of 22 Minor Changes/Corrections ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENTS ACTION 6.6.1 The following action9 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.-aal-

b. Ea h RePO-A- EV" .,NTTi-,h ol; aau-lto , by u,,&ER,,N,

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. 4-3, 9, 47, 462.4, 146

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 21 of 22 Minor Changes/Corrections 6.0 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4 The following programs shall be established, implemented, maintainedap4-shae -beý

-.-dted undz. the ccnenqzanee ef the C*NRD-

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 Monitoring 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. 97, 146

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 3 Proposed License Amendments Page 22 of 22 Minor Changes/Corrections ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

.1. Shall be documented and.r,*.d f r.'vc-;c ,,nd 0 ,l-

d-...as ftlreteiid b etaine * &**c-.c. his 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 changewill 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 -W-iv-. . .d. --by._: "i'i RevAcw Cr'-p c-d the approval of the plant manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

1. Shall be documented and -eee-de-ef-feviowc porfzr,'zd-Thdl-be

.. tai. d a...

....... .. byvSp .2at-e . his

'*e h.. 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 _"........ t..... ythe -acility ReviewC. tipsdthe 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 pedod 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 2 6-23 Amendment No. 43, 2-, 45, 60, 653,146

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 1 of 22 Minor Changes/Corrections ST. LUCIE WORD-PROCESSED TECHNICAL SPECIFICATION PAGES Unit 1 License Condition Page 4 3/4 3-5 3/4 3-12 3/4 3-13 3/4 3-13a 3/4 3-24 3/4 7-31 3/4 9-9 6-12 6-14 6-23 Unit 2 3/4 3-4 3/4 3-15 3/4 3-16b 3/4 3-28 3/4 7-24 3/4 9-10 5-5 6-13 6-14a 6-23

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 2 of 22 Minor Changes/Corrections 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 datedDecember 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 CFR 73.21, is entitled: "Florida Power and Light &

FPL Energy Seabrook Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan," submitted by letter dated September 23, 2004, and supplemented on October 15, October 22, and October 29, 2004.

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 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 Revised by letter dated October 29, 2004

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 3 of 22 Minor Changes/Corrections 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on than channel provided the other inoperable channel is placed inthe 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing per Specification 4.3.1A.1.1.

ST. LUCIE - UNIT 1 3/4 3-5 Amendment No. 45, 27-,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 4 of 22 Minor Changes/Corrections 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 inthis MODE below 685 psig;.bypass shall be automatically removed at or above 685 psig.

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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and inCOLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 ineither the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . For the purposes of testing and maintenance, the inoperable channel maybe bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed inthe 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed inthe tripped condition.

ST. LUCIE - UNIT 1 3/4 3-12 Amendment No. 4-5, 45,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 5 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Ifthe inoperable channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then place the inoperable channel in the tripped condition.

b. Within hour, 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ST. LUCIE - UNIT 1 3/4 3-13 Amendment No. -1*5,3 57-,2, 488,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 6 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . IfOPERABILITY can not be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If an inoperable SG level channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then AFAS-1 or AFAS-2 as applicable in the inoperable channel shall be placed in the bypassed condition. Ifan inoperable SG DP or FW Header DP channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ST. LUCIE - UNIT 1 3/4 3-13a Amendment No. 498,

0 0

0 CD 0 0 z0 I=1 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

.CHANNEL MODES INWHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 0 INSTRUMENT CHECK CALIBRATION TEST REQUIRED 00

1. AREA MONITORS 100

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 S

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

b. Containment

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

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 1 3/4 3-24 Amendment No. 50, 0 0CD

=0 t' N

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 8 of 22 Minor Changes/Corrections 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. Actvation (restraining action) is achieved in both tension and compression.

g. Snubber Service Life Monitoringq 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. Ifthe indicated service life will be exceeded by more than 10% prior to the next scheduled snubber service 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 in the records.

ST. LUCIE - UNIT 1 3/4 7-31 Amendment No. 24, 44, 83, 4-1-0,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 9 of 22 Minor Changes/Corrections 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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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. 49, 403, 448, 4-4,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 10 of 22 Minor Changes/Corrections ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following action 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.

b. Deleted 6.7 DELETED ST. LUCIE - UNIT I 6-12 Amendment No. 69, 93, 02-,

4 4.-,

7.

489,499,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 11 of 22 Minor Changes/Corrections 60 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 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 Monitoring 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. 6r. 426, 440, 448, 4-7, 48*9,49,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 12 of 22 Minor Changes/Corrections 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. I 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. , 6, -,-423, 42-5,4-7-7,49,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 13 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The channel shall I 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 Pressure - 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)

IfSG-2A, then AFAS-1 (AFAS)

IfSG-2B, then AFAS-2 (AFAS)

ST. LUCIE - UNIT 2 3/4 3-4 Amendment No. 48, 4,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 14 of 22 Minor Changes/Corrections 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 I hour. The channel shall be returned to 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)

3. Steam Generator Level - Steam Generator Level - Low (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 3-15 Amendment No. 28, 73,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 15 of 22 Minor Changes/Corrections 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Ifan inoperable SG level channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then AFAS-1 or AFAS-2 as applicable in the inoperable channel shall be placed inthe bypassed condition.

Ifan inoperable SG DP or FW Header DP channel can not be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then both AFAS-1 and AFAS-2 inthe 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 intest, 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 inthe tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ST. LUCIE - UNIT 2 3/4 3-16b Amendment No. 432,

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TABLE 4.3-3 C.-

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CD CD~

CHANNEL MODES FOR WHICH -.-- c CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED

1. AREA MONITORS 00 00o

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

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

b. Containment

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

With fuel in the storage pool or building.

- With irradiated fuel in the storage pool.

During movement of recently irradiated fuel within containment.

0I ST. LUCIE - UNIT 2 3/4 3-28 Amendment No.

CD CD

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 17 of 22 Minor Changes/Corrections PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

h. Snubber Seal Replacement Program 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.

i. Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a 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, 6-4-,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 18 of 22 Minor Changes/Corrections REFUELING OPERATIONS 314.9.9 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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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. 87-, 42-7,

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0 TABLE 5.7-1 P7" COMPONENT CYCLIC OR TRANSIENT LIMITS aq O0 CYCLIC OR DESIGN CYCLE COMPONENT TRANSIENT LIMIT OR TRANSIENT Reactor Coolant System 500 system heatup and cooldown Heatup cycle - Tavg from < 200°F cycles at rates < 100°F/hr. to > 532 0F; cooldown cycle -

Tavg from > 532°F to < 2000 F.

500 pressurizer heatup and Heatup cycle - Pressurizer temperature cooldown cycles at rates from < 200OF to > 6530F; cooldown

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

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

17' ST. LUCIE - UNIT 2 5-5 Amendment No.

a F' 0h 0

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 20 of 22 Minor Changes/Corrections ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENTS ACTION 6.6.1 The following action 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.

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. 43, 2-9, 47, 6, 424, 446,

£ St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 21 of 22 Minor Changes/Corrections 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. Q7, 446,

St. Lucie Units 1 and 2 L-2006-221 Docket Nos. 50-335 and 50-389 Attachment 4 Proposed License Amendments Page 22 of 22 Minor Changes/Corrections 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 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 2 6-23 Amendment No. 43, 25,45, 64, 64,163,446,

L-2006-221, Proposed License Amendments Re Minor Changes/Corrections to Technical Specifications

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