L-2016-212, License Amendment Request to Relocate the Component Cyclic and Transient Limits from the Technical Specifications to License-Control Documents

License Amendment Request to Relocate the Component Cyclic and Transient Limits from the Technical Specifications to License-Control Documents

ML17006A007
Person / Time
Site:	Saint Lucie
Issue date:	12/22/2016
From:	Costanzo C Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2016-212
Download: ML17006A007 (37)

Text

• FPL.

U.S. Nuclear Regulatory Commission DEC 2 2 2016 L-2016-212 10 CFR 50.90 Attn: Document Control Desk Washington D C 20555-0001 RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Renewed Facility Operating Licenses DPR-67 and NPF-16 License Amendment Request to Relocate the Component Cyclic and Transient Limits from the Technical Specifications to Licensee-Controlled Documents Pursuant to 10 CFR Part 50.90, Florida Power& Light Company (FPL) hereby requests amendments to Renewed Facility Operating Licenses DPR-67 for St. Lucie Nuclear Plant Unit 1 and NPF-16 for St. Lucie Nuclear Plant Unit 2, respectively. The proposed license amendments relocate the Component Cyclic and Transient Limits Program requirements to the Administrative Controls sections of the St. Lucie Unit 1 and St. Lucie Unit 2 Technical Specifications (TS) and relocate the Component Cyclic or Transient Limits tables detailing the allowable limits from the respective TS to licensee-controlled documents.

The enclosure to this letter provides FPL's evaluation of the proposed changes. Attachment 1 to the enclosure provides the existing St. Lucie Unit 1 TS pages marked up to show the proposed changes.

Attachment 2 to the enclosure provides the St. Lucie Unit 1 retyped (clean copy) TS pages with revision bars to identify the proposed changes. Attachment 3 to the enclosure provides the St. Lucie Unit 2 marked up TS pages. Attachment 4 to the enclosure provides the St. Lucie Unit 2 retyped TS pages with revision bars to identify the proposed changes.

FPL has determined that the proposed changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92(c), and there are no significant environmental impacts associated with the change. The St. Lucie Plant Onsite Review Group has reviewed the proposed license amendment. In accordance with 10 CFR 50.91 (b)(1 ), copies of the proposed license amendments are being forwarded to the State designee for the State of Florida.

FPL requests that the proposed changes are processed as a normal license amendment request, with approval within one year of the submittal date. Once approved, the amendment shall be implemented within 90 days.

This letter contains no new regulatory commitments.

Should you have any questions regarding this submittal, please contact Mr. Mike Snyder, St. Lucie Licensing Manager, at (772)467-7036.

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on DEC 2 2 2016 zz:~tc:7 Christopher R. Costanzo Site Vice President St. Lucie Nuclear Plant Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Ms. Cindy Becker, Florida Department of Health

St. Lucie Nuclear Plant L-2016-212 Docket- Nos. 50-335 and 50-389 Enclosure Page 1of35 Enclosure Evaluation of the Proposed Changes St. Lucie Nuclear Plant, Units 1 and 2 License Amendment Request to Relocate the Component Cyclic or Transient Limits to Licensee-Controlled Documents 1.0

SUMMARY

DESCRIPTION ........................................................................................................................ 2 2.0 DETAILED DESCRIPTION .......................................................................................................................... 2 2.1 St. Lucie Unit 1- Revision ofTS 5.9.1 and Deletion ofTable 5.9-1 ............................................................... 2 2.2 St. Lucie Unit 2- Revision ofTS 5.7.1 and Deletion ofTable 5.7-1 ............................................................... 3

3.0 TECHNICAL EVALUATION

......................................................................................................................... 5

4.0 REGULATORY EVALUATION

..................................................................................................................... 5 4.1 Applicable Regulatory Requirements/Criteria ...............................................................................................5 4.2 Precedents .....................................................................................................................................................6 4.3 No Significant Hazards Consideration ............................................................................................................ 6 4.4 Conclusion .....................................................................................................................................................8

5.0 ENVIRONMENTAL CONSIDERATION

........................................................................................................ 8

6.0 REFERENCES

........................................................................................................................................... 8 - Proposed Unit 1 Technical Specification Pages (markup) ...................................... 10 - Proposed Unit 1 Technical Specification Pages (clean copy) ................................... 15 - Proposed Unit 2 Technical Specification Pages (markup) ....................................... 20 - Proposed Unit 2 Technical Specification Pages (clean copy) ................................... 28

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 2 of 35 1.0

SUMMARY

DESCRIPTION Florida Power& Light Company (FPL) hereby requests amendments to Renewed Facility Operating Licenses DPR-67 and NPF-16 for St. Lucie Nuclear Plant, Units 1 and 2, respectively. The proposed license amendments modify and relocate the Component Cyclic or Transient Limits requirements of TS 5.9.1 and TS 5.7.1 from the Design Features to the Administrative Controls sections of the St. Lucie Unit 1 and St. Lucie Unit 2 TS, respectively. In addition, the proposed license amendments relocate the Component Cyclic or Transient Limits Table 5.9-1 and Table 5.7-1 from the St. Lucie Unit 1 TS and the St. Lucie Unit 2 TS to the St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR) and the St.

Lucie Unit 2 UFSAR, respectively. The proposed changes serve to align the St. Lucie Unit 1 and Unit 2 TS more closely with NUREG-1432, Standard Technical Specifications - Combustion Engineering Plants, Revision 4.0 (Reference 6.1).

2.0 DETAILED DESCRIPTION 2.1 St. Lucie Unit 1 - Revision of TS 5.9.1 and Deletion of Table 5.9-1 St. Lucie Unit 1, TS 5.9.1, states that the components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-1. The proposed change relocates Table 5.9-1 from the St. Lucie Unit 1 TS to the St. Lucie Unit 1 UFSAR. In addition, the proposed change deletes TS 5.9.1, and relocates the requirement to newly created TS 6.8.4.q, Component Cyclic or Transient Limit Program, within the Administrative Controls section of the St. Lucie Unit 1 TS. Consistent with Section 5.5.5 of NUREG-1432, Revision 4.0 (Reference 6.1), TS 6.8.4.q will state that the

[Component Cyclic or Transient Limit] Program provides controls to track the FSAR cyclic and transient occurrences to ensure that components are maintained within the design limits.

The italicized sections below reflect the proposed change:

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St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 3 of 35 P-r:BSStJFB > 123§ fJS*ig TS 6.8.4.q Component Cvclic or Transient Limit Program The Program provides controls to track the FSAR, Section 5.2, cyclic and transient occurrences to ensure that components are maintained within the design limits.

2.2 St. Lucie Unit 2 - Revision of TS 5.7.1 and Deletion of Table 5.7-1 St. Lucie Unit 2, TS 5.7.1, states that the components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1. The proposed change relocates Table 5.7-1 from the St. Lucie Unit 2 TS to the St. Lucie Unit 2 UFSAR In addition, the proposed change deletes TS 5.7.1, and relocates the requirement to newly created TS 6.8.4.r, Component Cyclic or Transient Limit Program, within the Administrative Controls section of the St. Lucie Unit 2 TS. Consistent with Section 5.5.5 of NUREG-1432, Revision 4.0 (Reference 6.1), TS 6.8.4.r will state that the

[Component Cyclic or Transient Limit] Program provides controls to track the FSAR cyclic and transient occurrences to ensure that components are maintained within the design limits.

The italicized sections below reflect the proposed change:

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TS 6.8.4.r Component Cyclic or Transient Limit Program

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 5 of 35 The Program provides controls to track the FSAR, Section 3.9, cyclic and transient occurrences to ensure that components are maintained within the design limits.

3.0 TECHNICAL EVALUATION

The proposed change relocates Component Cyclic or Transient Limits Table 5.9-1 and Table 5.7-1 from the St. Lucie Unit 1 and St. Lucie Unit 2 TS, to the respective St. Lucie Unit 1 and Unit 2 UFSARs. In addition, the proposed change deletes TS 5.9.1 and TS 5.7.1 from the St. Lucie Unit 1 and the St. Lucie Unit 2 TS, respectively, and relocates the requirements to the Component Cyclic or Transient Limit Program, within the Administrative Controls sections of the St. Lucie Units 1 and 2 TS.

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The Component Cyclic or Transient Limits are derived from design analyses but are not of controlling importance to operational safety. More specifically, the limits do not impose any limitations or conditions on Reactor operation which are necessary to obviate an abnormal situation or event that could pose an immediate threat to public safety. Mence, changes to the Component Cyclic or Transient Limits should not be subject to Commission approval; a rationale espoused in the NRC's Final Policy Statement on TS Improvements for Nuclear Power Reactors (Reference 6.2). The Component Cyclic or Transient Limits are tracked via plant Administrative Procedure (AP) 0010134, Component Cycles and Transients, and the tracKing methodology and periodicity will remain unchanged. The relocation of Table 5.9-1 and Table 5.7-1 to the respective St. Lucie Unit 1 and 2 UFSAR(s) requires that future changes to the cyclic and transient limits are first evaluated pursuant to 10 CFR 50.59. Furthermore, the relocation of the Component Cyclic or Transient Limit Program to the TS Administrative Controls sections is consistent with Section 5.5.5 of NUREG-1432, Revision 4.0 (Reference 6.1). As such, deleting TS 5.9.1 and TS 5.7.1, relocating the Component Cyclic or Transient Limit Program to the TS Administrative Controls sections of the St. Lucie Unit 1 and 2 TS and relocating Table 5.9-1 and Table 5.7-1 to the respective St. Lucie Unit 1 and 2 UFSARs is reasonable.

4.0 REGULATORY EVALUATION

4.1 Applicable Requlatorv Requirements/Criteria 10 CFR 50.36, paragraphs (c)(1 ), (c)(2) and (c)(3) specify that the TS shall include safety limits, limiting safety system settings, limiting control settings, limiting conditions for operation (LCO), and surveillance requirements (SRs).

10 CFR 50.36(c)(4) specifies that the Design Features to be included in the TS are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in 10 CFR 50.36 paragraphs (c) (1 ), (2), and (3).

The Component Cyclic or Transient Limits are not safety limits, limiting safety system settings, or limiting control settings. In addition, they are neither LCOs nor SRs. Hence, the Component Cyclic.or Transient Limits are not covered in the categories described in 10 CFR 50.36 paragraphs (c) (1), (2), and (3).

The Component Cyclic or Transient Limits are listed in the respective St. Lucie Unit 1 and 2 TS as Design Features. However, the Component Cyclic or Transient Limits were established to ensure that the associated components are maintained within their design limits over the lifetime of the plant(s). As such, the

St. Lucie N-uclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 6 of 35 Component Cyclic or Transient Limits are not facility features which would have a significant effect on safety if altered or modified.

Based upon the foregoing, the Component Cyclic or Transient Limits do not satisfy the 10 CFR 50.36(c) criteria for inclusion in the TS and hence relocation of Table 5.9-1 and Table 5.7-1 to the respective St. Lucie Unit 1 and 2 UFSARs is reasonable. Following NRG approval of this license amendment, changes to the component cyclic or transient limits will be controlled pursuant to 10 CFR 50.59.

4.2 Precedents The following precedents establish a basis for the proposed changes.

4.2.1 South Texas Project, Units 1 and 2, License Amendment Request, Proposed Amendment to South Texas Project Technical Specifications to Revise Administrative Control Requirements, dated November 5, 2001, (Reference 6.4)

In Reference 6.4, the licensee proposed changes to the South Texas Project Unit 1 and 2 TS that would relocate the details contained in TS 6.8.3.f, regarding the component cyclic or transient limits, to the UFSAR and change the verbiage to be consistent with NUREG 1431 (Reference 6.3). In justifying the change, the licensee stated that the program requirements were being maintained in the TS and that only the specific details of the design limits were being relocated to the UFSAR. _)_

In Reference 6.5, the staff granted the licensee's request to amend the South Texas Project Unit 1 and 2 TS, stating that the change is acceptable and noting that the licensee would retain the program requirements in the TS but would relocate the specific detailed design limits to the UFSAR and that subsequent USFAR changes would be controlled by the provisions of 10 CFR 50.59.

4.2.2 Sequoyah Nuclear Plant (SQN) - Units 1 and 2 - Technical Specifications (TS)

Change 05-02 "Cyclic and Transient Limits with Design Features Revision",

dated September 30, 2005 (Access!on No. ML052870040) (Reference 6.6)

In Reference 6.6, the licensee proposed changes to the Sequoyah Nuclear (SQN) Units 1 and 2 TS that would relocate the component cyclic or transient limits requirements from the Design Features section to the Administrative Controls section of the SQN TS and would relocate Table 5.7.1,"Component Cyclic or Transient Limits", to the USFAR.

In Reference 6.7, the staff granted the licensee's request to amend the SQN Units 1 and 2 TS, stating that the change is administrative in nature since the requirements to track and maintain the [component or cyclic] limits remain in the SQN TSs and that the change also conforms to NUREG-1431 (Reference 6.3).

The above precedents are relevant to this license amendment request (LAR) because the *staff acknowledged that the TS requirement to maintain the component and cyclic limits would be retained, that changes to the specific design limits would be subject to the provisions of 10 CFR 50.59, and that the changes conformed to the applicable Improved Standard Technical Specifications.

c

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 7 of 35 4.3 No Significant Hazards Consideration The proposed change relocates Component Cyclic or Transient Limits Table 5.9-1 and Table 5.7-1 from the St. Lucie Unit 1 and Unit 2 TS, to the St. Lucie Unit 1 and Unit 2 UFSARs, respectively. In addition, the proposed change deletes TS 5.9.1 and TS 5.7.1 from the St. Lucie Unit 1 and Unit 2 TS, and relocates the Component Cyclic or Transient Limit Program, to the Administrative Controls seCtion of the respective TS.

As required by 10 CFR 50.91 (a), FPL has evaluated the proposed changes using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration. An analysis of the issue of no significant hazards consideration is presented below:

(1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The relocation of Component Cyclic or Transient Limits Table 5.9-1 and Table 5.7-1 from the St. Lucie Unit 1 and Unit 2 TS, to the St. Lucie Unit 1 and Unit 2 UFSARs, and the relocation of the Component Cyclic or Transient Limits Program requirements within the St. Lucie Unit 1 and Unit 2 TS are administrative changes in nature. The TS changes do not represent any physical change to plant systems, structures, or components, or to procedures established for plant operation. As such, the initial conditions associated with accidents previously evaluated and plant systems credited for mitigating the consequences of accidents previously evaluated remain unchanged.

Therefore, facility operation in accordance with the proposed license amendments would not involve a significant increase in the probability or consequences of an accident previously evaluated.

(2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The relocation of Component Cyclic or Transient Limits tables from the St. Lucie Unit 1 and Unit 2 TS, to the St. Lucie Unit 1 and Unit 2 UFSARs, and the relocation of the Component Cyclic or Transient Limits Program requirements within the St. Lucie Unit 1 and Unit 2 TS are administrative changes in nature. No physical change to plant systems, structures, or components, or the manner in which they are operated and maintained will result from the proposed license amendments.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

(3) Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No The relocation of Component Cyclic or Transient Limits tables from the St. Lucie Unit 1 and Unit 2 TS, to the St. Lucie Unit 1 and Unit 2 UFSARs, and the

St. Lucie Nuclear Plant L-2016-212

-Docket Nos. 50-335 and 50-389 Enclosure Page 8 of 35 relocation of the Component Cyclic or Transient Limits Program requirements within the St. Lucie Unit 1 and Unit 2 TS are administrative changes in nature.

As such, the proposed changes do not involve changes to any safety analyses assumptions, safety limits, or limiting safety system settings nor do they adversely impact plant operating margins or the reliability of equipment credited in safety analyses.

Therefore, operation of the facility in accordance with the proposed amendment will not involve a significant reduction in the margin of safety.

Based upon the above analysis, FPL concludes that the proposed amendment does not involve a significant hazards consideration, under the standards set forth in 10 CFR 50.92, "Issuance of Amendment," and accordingly, a finding of "no significant hazards consideration" is justified.

4.4 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health ~nd safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment modifies a regulatory requirement with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or changes an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Therefore, pursuant to 10 CFR 51.22{b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

6.0 REFERENCES

6.1 NUREG-1432, Standard Technical Specifications - Combustion Engineering Plants, Revision 4.0 (Accession No. ML12102A169) 6.2 NRC Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors," dated July 22, 1993 (58 FR 39132) 6.3 NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0, Volume 1, Specifications (Accession No. ML 121 OOA222) 6.4 South Texas Project, Units 1 and 2, License Amendment Request, Proposed Amendment to South Texas Project Technical Specifications to Revise Administrative Control Requirements, dated Novembers, 2001, (Accession No. ML013510314) 6.5 South Texas Project, Units 1 and 2 - Issuance of Amendments to Revise Specific Requirements of Technical Specification 6.0, "Administrative Controls" (TAC Nos.

MB3589 And MB3593), dated April 24, 2003 (Accession No. MI031140670)

-St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 9 of 35 6.6 Sequoyah Nuclear Plant (SQN) - Units 1 and 2 - Technical Specifications (TS) Change 05-02 "Cyclic and Transient Limits with Design Features Revision", dated September 30, 2005 (Accession No. ML052870040) 6.7 Sequoyah Nuclear Plant, Units 1 and 2 - Issuance Of Amendments Regarding Technical Specification Changes to Cyclic and Transient Limits with Design Features Revision (TAC Nos. MC8532 and MC8533) (TS 05-02), dated August 2, 2006 (Accession No. ML061390231)

St. L:ucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 10 of 35 Attachment 1 ST. LUCIE UNIT 1 PROPOSED TECHNICAL SPECIFICATION PAGES (MARKUP)

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 11 of 35 Attachment 1 DESIGN FEATURES SECTION 5.1 SITE Exclusion Area ............................. ,................. ,........................................ , .................. 5-1.

Low Population Zone .................................................................................................. 5-1 5.2 CONTAINMENT

.Configuration .............................................................................................................. 5-1 Design Pressure and Temperature ............................................................................. 5-4 Penetrations ................................................................................................................5-4 5.3 REACTOR CORE Fuel Assemblies ............................................ ,...... ,..................................................... 5-4 Control Element Assemblies ....................................................................................... 5-5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature ............................................................................. 5.-5 Volume ..................................., ...................................., ................................................... 5-5.

5.5 EMERGENCY CORE COOLING SYSTEMS .............................................................. 5-5 5.6 FUEL STORAGE Criticality ..................................................................................................................... 5-5 Drainage ..................................................................................................................... 5-6 5.7 SEISMIC CLASSIFICATION ...................................................................................... 5-6 5.8 METEOROLOGICAL TOWER LOCATION ............................................................... 5-6a 5.9 COMPONENT CYCLE OR TRANSIENT l:IMfFS-::IDELETED  !............................... 5-6a ST. LUCIE - UNIT 1 XIII Amendment No.~. 1'+f

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-3-35 and 50-389 Enclosure Page 12 of 35 Attachment 1 DESIGN FEATURES DRAINAGE 5.6.2 The fuel pool is designed and shall be maintained to prevent t

inadvertent draining of the pool below elevation 56 feet CAPACITY 5.6.3 The spent fuel pool storage racks are designed and shall be maintained With a storage capacity limited to no more than *1705 fuel assemblies, and the eask pit storage rack is designed and shall be maintained with a storage capacity limited to no . .

more than 143 fuel assemblies. The total Unit 1 spent fuel pool and cask pit storage capacity is limited to no more than 1849 fuel assemblies.

• 5.7 SEISMIC CLASSIFICATION

5. 7 .1 Those structures, systems and components identified as seismic Class. I in Section 3.2: 1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3.7 of the FSAR with allowance for no*rmal degradation pursuant to the applicable Surveillance Requirement.

5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorologicaltower location shall be as shown on Figure 5.1~ 1.

5.9 COMPONENT C¥GLE OR TRANSIENT LIMITS !DELETED I s:9.1 Tl 1e colliponents identified i11 Table 5.9 1 are designed and shall be maintained *within the eyelie er transient limits of Table 5.9 ~.

ST. LUCIE - UNIT 1 5-6a Amendment No. ~. 'f9S

St. Lucie NuclearPlant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 13 of 35 Attachment 1 COMPONENT CYCLIC OR TRANS!EN+-ldMl+s DESIGN CYCLE OR TR/lf*lSIENT

-!RK<.e!!ia!6el!e>f-rbC"'1eeB1iaa1A'1-t-eSAAyss;tee1.A*i-----<4fU0-tGriy~eleess-oe1f-11loss-of-!ead-witheui-t-----'1110:1tOH%<rtEee-tOl'll%o-1R~~"rTH:E:+/-DrTtJl;;IE::tR'1f>AA!A1L

-immediate reactor'lri,,.p--------4P"l031',N'iEER-R 40 eyeles of loss o! offsite 100% te 0% RATED THERMAL A.G. elee!Fieal pev.er PO'NER

• ,,,_ _ _ _ _ _ _ _ ___.1.,00...0....... to>-<O..,%""'?.AT!OD Tl IERMAe 400reee!eMrips -f>eWER-16 iAaa.efletil auxili&r)' Sp1ay line 650"F to 12ti-F spf8y-Cycle'*S>------------ffiiRrl1~.~

LW*tea!Meststs-----------IP"1F'E>6SS!S~l;lftf.>-'>...;~ci!i;3~5-flp<!t!lSig

.1 O l'lydrastalis pFessu*e tests Pressure ;:, 311 O psig Gamf'llete lass ef seeO!KlafY' Seco11dar ~ System 5 steam li.ie b1 eaks f3feSSure-200 leak tests Press.,re ~ 985 psig 1o-hydroetalie-pr-esstff0-t.01es'*lss------+'P""re>SsS1sUolfre-e"".':-'>1'C-23&1e>-1pS<sH!l-ig ST. LUCIE -UNIT 1 !l-7

St. Lucie Nuclear Plant* L-2016-212

-Docket Nos. 50-335 and 50-389 Enclosure Page 14 of 35 Attachment 1 ADMINISTRATIVE CONTROLS lcontjnuedl

• o. Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of frequencies of those Surveillance Requirements for which the frequency is controlled by the program.

b. Changes to the frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 4;0.2 and 4.0.3 are applicable to the frequencies established in the Surveillance Frequency Control Program.

p. Snubber Testing Program This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a in service inspection (ISi) requirements for supports. The program shall be in accordance with the following:

1. This program shall meet 10 CFR 50.55a(g) ISi requirements for supports.

2. The program shall meet the requirements for ISi of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b) subject to the conditions listed in 10 CFR 50.55a(b) and subject to Commission approval.

3. The program shall, as required by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection !STD, "Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants".

4. The 120-month program updates shall be made in accordance with 10 CFR 50.55a(g)(4), 10 CFR 50.55a(g)(3)(v) and 10 CFR 50.55a(b) (including 10 CFR 50.55a(b)(3)(v)) subject to the conditions listed therein.

q. Component Cyclic or Transient Limit Program The Program provides controls to track the FSAR, Section 5.2, cyclic and transient occurrences to ensure that components are maintained within the design limits.

ST. LUCIE - UNIT 1 6-15h Amendment No.~. ~. 232--

- __ _J

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 15 of 35 Attachment 2 ST. LUCIE UNIT 1 PROPOSED TECHNICAL SPECIFICATION PAGES (CLEAN COPY)

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 16 of 35 Attachment 2

.QES!GN FEATURES SECTION 5.1 SITE Exclusion Area ..............................................................................................................5-1 Low Population Zone ....................................................................................................5-1 5.2 CONTAINMENT Configuration ................................................................................................................5-1 Design Pressure and Temperature ............................................................................... 5-4 Penetrations ..................................................................................................................5-4 5.3 REACTOR CORE Fuel Assemblies ........................................................................................................... 5-4 Control Element Assemblies .........................................................................................5-5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature ............................................................................... 5-5 Volume ..........................................................................................................................5-5 5.5 EMERGENCY CORE COOLING SYSTEMS ................................................................5-5 5.6 FUEL STORAGE Criticality .......................................................................................................................5-5 Drainage .......................................................................................................................5-6 5.7 SEISMIC CLASSIFICATION ............................. ~ ........................................................... 5-6 5.8 METEOROLOGICAL TOWER LOCATION ................................................................5-6a 5.9 DELETED ...................................................................................................................5-Sa ST. LUCIE - UNIT 1 XIII Amendment No. 4M, 442

St. Lucie Nuclear Plant L-2016-212 D0cket Nos. 50-335 and 50-389 Enclosure Page 17 of 35 Attachment 2 DESIGN FEATURES DRAINAGE 5.6.2 The fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.

CAPACITY 5.6.3 The spent fuel pool storage racks are designed and shall be maintained with a storage capacity limited to no more than 1706 fuel assemblies, and the cask pit storage rack is designed and shall be maintained with a storage capacity limited to no more than 143 fuel assemblies. The total Unit 1 spent fuel pool and cask pit storage capacity is limited to no more than 1849 fuel assemblies.

5.7 SEISMIC CLASSIFICATION

5. 7.1 Those structures, systems and components identified as seismic Class I in Section 3.2.1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3. 7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirement 5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tower location shall be as shown on Figure 5.1-1.

5.9 DELETED ST. LUCIE - UNIT 1 5-6a Amendment No. ~. 493

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335- and 50-389 Enclosure*

Page 18 of 35 Attachment 2 DELETED ST. LUCIE - UNIT 1 5-7 Amendment No.

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 19 of 35 Attachment 2 ADMINISTRATIVE CONTROLS (continued\

o. Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of frequencies of those Surveillance Requirements for which the frequency is controlled by the program.

b. Changes to the frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the frequencies established in the Surveillance Frequency Control Program.

p. Snubber Testing Program This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (ISi) requirements for supports. The program shall be in accordance with the following:

1. This program shall meet 10 CFR 50.55a(g) ISi requirements for supports.

2. The program shall meet the requirements for ISi of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b) subject to the conditions listed in 10 CFR 50.55a(b) and subject to Commission approval.

3. The program shall, as required by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants".

4. The 120-month program updates shall be made in accordance with 10 CFR 50.55a(g)(4), 10 CFR 50.55a(g)(3){v} and 10 CFR 50.55a(b) (including 10 CFR 50.55a(b}(3}(v)) subject to the conditions listed therein.

q. Component Cyclic or Transient Limit Program The program provides controls to track the FSAR, Section 5.2, cyclic and transient occurrences to ensure that components are maintained within the design limits.

ST. LUCIE* UNIT 1 6-15h Amendment No. ;w+:, ~. ~

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 20 of 35 Attachment 3 ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATION PAGES (MARKUP)

St. i:.ucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 21 of 35 Attachment 3 LIST OE TABLES !Continued\

TABLE PAGE 3.7-1 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS ...................................................... 3/4 7-2 3.7-2 STEAM LINE SAFETY VALVES PER LOOP .................................................... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM ..............."....................................................................... 3/4 7-8 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL ................................................ 3/4 7-22

3. 7-3a DELETED ........................................................................................................ 3/4 7-26 3.7-3b DELETED ................................................................*........................................ 3/4 7-27

3. 7-4 DELETED

3. 7-5 DELETED 4.8*1 DIESEL GENERATOR TEST SCHEDULE ........................................................ 3/4 8-8 4.8-2 BATTERY SURVEILLANCE REQUIREMENT ................................................ 3/4 8-12 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES .......................................................... :............................... 3/4 8-18 4.11-1 DELETED 4.11-2 DELETED 3.12-1 DELETED 3.12-2 DELETED 4.12-1 DELETED 5.6-1 MINIMUM.BURNUP COEFFJCIENTS ...........................................:....................... 5-40 L7 1 GGMPGNENT CYCt:IC OR TRANSIENT LIMITS JDELETED  !......................,...... 5~5.

ST. LUCIE - UNIT 2 xxv Amendment No. 8. M, &a, 68,

-73, '1.-1+, 462, 167

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 22 of 35 Attachment 3 DESIGN FEATURES fcontirn red\

CRITICALITY (continued) 5.6.1 c. (continued)

4. The 2x2 array of fuel assemblies that span the interface between Region 1 and Region 2 of the spent fuel pool storage racks shall comply with the storage pattern definitions of Figure 5.6-3 and the minimum burnup

• requirements as defined in Table 5.6-1. The allowed special arrangements in Region 2 as shown in Figure 5.6-2 shall not be placed adjacent to Region 1.

(See Specification 5.6.1.c. 7 for exceptions)

5. Fuel placed in the cask pit storage rack shall comply with the storage pattern definitions of Figure 5.6-4 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1.c.7 for exceptions)

6. The same directional orientation for Melamie inserts is required for contiguous groups of 2x2 arrays where Metamic ipserts are required.

7. Fresh or spent fuel in any allowed configuration may be replaced with non-fuel hardware, and fresh fuel in any allowed configuration may be replaced with a fuel rod storage basket containing fuel rod(s). Also, storage of Melamie inserts or control rods, without any fissile material, is acceptable in locations designated as completely water-filled cells.

d. The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a maximum planar average U-235 enrichment less than or equal to 4.6 weight percent, while maintaining a ken of less than or equal to 0.98 under the most reactive condition.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.

CAPACITY 5.6.3 The spent fuel pool storage racks are designed and shall be maintained \\iith a storage capacity limited to no more than 1491 fuel assemblies, and the cask pit -t-storage rack is designed and shall be maintained with a storage capacity limited to no more than 225 fuel assemblies. The total Unit 2 spent fuel pool and cask pit storage capacity is limited to no more than 1716 fuel assemblies. .-1--

5.7 OOMPBNENT CYCLIC OR TRANSIEN=F l::IMl=FS !DELETED j 5.7.i The compeneftts identified in Tal31e 5.7 1 f!IFC designed and shall be maintained wilhln.

the eye!ic or transient limits of Table 5. 7 1.'

ST. LUCIE* UNIT 2 5'4a Amendment No.+, 40'!-, ~. *162"

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 23 of 35 Attachment 3

.+A~ DELETED! I GGM~R:.+RANSI~

4'C'><Y'<'C""L""IC"-'.F!0"'R'------------GESIGN GYGbE eeMPONENT TRANSIEN.fidMIT GR 'FRANS!ENT 500 sy~tem heatup and coekiov"' lieatap cycle T~"" nom;:,2oe*F eyoloo*at.,,ak...,,~40tl"F/hr...,-*--****----ro*~S~M-eyele T"'~ f* om .::.. 532°r to :! 2eoor.

~uiizer heatup ime! Hoo.l.u1Ho.7cle--Pfeesu!'i2er bmperali:lle aaol_clS'Nfl eyeles at rates from.:'. 200"r le =. S53"F; oosklew1'1

!:;'~ll>lir.,..----------_>*.f!61'>53~.**r-te:::-£00*F 10 hydros\atie-lestittg<Cyele"'s"".-----lR'!iC5iS&...pr"'e"'s"'sU'*.fifi>izeed1'Hfle,..,a<-11i41fl3.,,p.&s1ieg-vw"'Rll.

=.

ROG temperature S0°F*abeve-!fie me3tllmiliR§ eeffipefl-ffis' NOTF-.sh:*"-

""2"'0""1"'!e~a"'k""re-s"'ar-,g-c~y~e"'le~s-.-----...JRl+C"'-0"'-presstJred-t:l 22.50 psis >>il:ft RCS temperat~Fe @realer ti'la" mifiim1:11'1l fer hjdrosla!ie t<.s!i"g~tian miAim~m RCS temperature fOi *' ;ucality.

<<4QA<Q;....,,,.-.,,et""o-.!""li"p~e"'yc!""eMS~.-------'T"-timp'4"flAA"f>~fl'!~1"'0"'0'°'--%m g 'l'HERMAb PO'.l'IER.

40.trnbhie t!fp.cycles wlil1 Turbilze trip (total :oad zeja.et:en)"

• dala~a roa6tGF-tr"'iJl'-.-------4W"'G"'ffl'-'1'l+Ol::Oll<>%"""e~fLIR~./'>.:;,TEi:::49+'Tl-+l-lilEi"IRl'l'!M.4AAl-l+Pi;:oru*p~JE:;i:iR felleWed-byfStl!ting reaetar trip.

• ST. LUCIE- UNIT2

\

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 24 of 35 Attachment 3

'fk~edj COMf!ONENT CYCLIC GR TRANSIENT l:IMFFS-QF.'¥(F.QrLl~e~o~Rt<-------------HD~ES""I'~

COMF!GNENT TRANSIENT LIMITS OR TRANSIENT Reaetor CoelaMt S; s!en 1 19 eem13lete less ef .easier Si1'11<1latar.ee1o1S less oHill-ReaG!Gf eoc!ani~/ele;ir.---*------!6oolant--PtlmpoM;Mil0".4roffl:ATED "fHERMAf; f"O'ili'eR:

5-eoo11li!""'~*'"<*"95>flBi3Pt'------t-s--0*}.r...ecoi;daiy-pressure 'rom press1n=e cyctes eith~aMara~

MeBE-+;-2--of~

100 pressurittr sp1 ~ eyelcs pe. Sprey-e!>"ffiliee. eensisting of year wit~ l"ressuffi!eFlspray water epening aREl elosing-either-lhe-main-AT* 2oe*r or as.otherwise Of-<iuxilisr/ sprny ""e(5) ealeula~he-followin!Ymetnod-.---sprey*water/preSSt:Jrizer*lff-->-200"F-.

ITT'. LUCIE* UNIT 2

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 25 of 35 Attachment 3

+ABLE s.7 1 1coritinood}

CYCLIC OR DESIGN CYCLE COMPONENT R""FRANSIEN'F-Reactor Coolant S;'S!em Method l'o1 CeleHlating T'ressurli!cr Sprav Noozle Cunwlati"& **sage F~

~9 13,099 aei 480 s.eoo 401 §09 a,eee 591 see 1,SGG AT - TeffipeFature eiffefenoe-be!ween pressyrizer water ans spray il'l 0 F:.

N,.. -Alie*\'abte num~~eles.

IJ - N~mber er eye!ee &f 6T l'fmge i11dieated.

ST. LUCIE - UNIT Z 5-7

St. Lucie Nuclear Plant- L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 26 of 35 Attachment 3 TABLE S.7 1 (Confutued}-

eeMPeNENT CYCLIC OR TRANS1Efl!T LIMITS CYCLIC OR DESIGN CYCLE eeMPONElff TRANSIENT LIMIT OR TRANSIENT Rea-tor Coe~

GaleulatioA-Metlla!E-

1. :!'rt 12-mor.~ 1 inte. vals tile comtilative'~-cles shall be tutaled,

-lf..the-le!al*i3-e1i!t:l1lJ-l<l rn less !rum 1000, fiO fort:her action is , -(luired.

~mulatiJe t<>!a! exe-eds 1990, tfle sp.sy Re=;;le usag_ 7aeter sha:i ee salsuiatect as fellaws:

3. If ti 1e calcufated~~tor exceeds e. 75,.eubscquer.t pressuri!:er sprey-eperalie~e-thaHh~ee-belweerH~-ilref water lempeft!llJFC Sfld.!he spray .. at~lw!H>e-!i~

tess-than-ereq\l~hoo-ep~~n engineeFif'@ e*..,,luaiion ek-~"'6-ehall-de!efmi~e \Aal the MWE

• -maiAs aeeeptasle fur aaaili<mal seFViee i>Fier te remevir;g 11'is reslrietioo.

ST. LUCIE - UNIT 2

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 27 of 35 Attachment 3 ADMINISTRATIVE CONTROLS

q. Surileillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of frequencies of those Surveillance Requirements for which the frequency is controlled by the program.

b. Changes to the frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Sur\teillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the frequencies established in the Surveillance Frequency Control Program.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements ofTitle.10, Code of Federal Regulations; the following reports shall be submitted to the NRG:

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license. (2) amendment to the license involving a planned increase in power level, (3) installation. of fuel that has a different design or has been manufactured by a different fuel supplier; and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation). supplementary reports shall be submitted at least every three months until all three events have been completed.

r. Component Cyclic or Transient Limit Program The Program provides controls to track the FSAR, Section 3.9, cyclic and transient occurrences to ensure that components are maintained within the design limits.

St. Lucie Nuclear Plant L-2016-212 Docket Nos.. 50-335 and 50-389 Enclosure Page 28 of 35 Attachment 4 ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATION PAGES (CLEAN COPY)

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 29 of 35 Attachment 4 LIST OF TABLES IContinuedl 3.7-1 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS ......................................... 3/4 7-2 3.7-2 STEAM LINE SAFETY VALVES PER LOOP .................................................... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM ...................................................................................... 3/4 7-8 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL ................................................ 3/4 7-22 3.7-3a DELETED ........................................................................................................ 3/4 7-26 3.7-3b DELETED ........................................................................................................ 3/4 7-27 3.7-4 DELETED 3.7-5 DELETED 4.8-1 DIESEL GENERATOR TEST SCHEDULE ........................................................ 314 8-8 4.8-2 BATTERY SURVEILLANCE REQUIREMENT ................................................ 3/4 8-12 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES .......................................................................................... 3/4 8-18 4.11-1 DELETED 4.11-2 DELETED 3.12-1 DELETED 3.12-2 DELETED 4.12-1 DELETED 5.6-1 MINIMUM BURNUP COEFFICIENTS ................................................................... 5-40 5.7-1 DELETED ................................................................................................................ 5-5 ST. LUCIE - UNIT 2 xxv Amendment No.&, a.1-, ea, >1l, 73, 44+, ~. -1§7

St. Lucie Nuclear Plant

• L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 30 of 35 Attachment 4 DESIGN FEATURES (continued\

CRITICALITY (continued) 5.6.1 c. (continued)

4. The 2x2 array of fuel assemblies that span the interface between Region 1 and Region 2 of the spent fuel pool storage racks shall comply with the storage pattern definitions of Figure 5.6-3 and the minimum burnup requirements as defined in Table 5.6-1. The allowed special arrangements in Region 2 as shown in Figure 5.6-2 shall not be placed adjacent to Region 1.

(See Specification 5.6.1.c.7 for !?Xceptions)

5. Fuel placed in the cask pit storage rack shall comply with the storage pattern definitions of Figure 5.6-4 and the minimum burnup requirements .as defined in Table 5.6-1. (See Specification 5.6.1.c.7 for exceptions)

6. The same directional orientation for Metamic inserts is required for contiguous groups of 2x2 arrays where Metamic inserts are required.

7. Fresh or spent fuel in any allowed configuration may be replaced with non-fuel hardware, and fresh fuel in any allowed configuration may be replaced with a fuel rod storage basket containing fuel rod(s). Also, storage of Metamic inserts or control rods, without any fissile material. is acceptable in locations designated as completely water-filled cells.

d. The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a maximum planar average U-235 enrichment less than or equal to 4.6 weight percent, while maintaining a kett of less than or equal to 0.98 under the most reactive condition.

DRAINAGE 5.6.2 The spent fuel storage pool is-designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.

CAPACITY 5.6.3 The spent fuel pool storage racks are designed and shall be maintained with a storage capacity limited to no more than 1491 fuel assemblies, and the cask pit storage rack is designed and shall be maintained with a storage capacity limited to no more than 225 fuel assemblies. The total Unit 2 spent fuel pool and cask pit storage capacity is limited to no more than 1716 fuel assemblies.

5.7 DELETED ST. LUCIE - UNIT 2 5-4a Amendment No. '7, 4-Gi, 4M;, 4@

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 31 of 35 Attachment 4 DELETED ST. LUCIE - UNIT 2 5-5 Amendment No. 449

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 32 of 35 Attachment 4 DELETED ST. LUCIE - UNIT 2 Amendment No.

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 33 of 35 Attachment 4 DELETED ST. LUCIE - UNIT 2 5.7 Amendment No.

St. Lucie Nuclear Plant l-2016-212 Docket Nos. 50-335 and 50-389 Enclosure Page 34 of 35 Attachment 4 DELETED ST. LUCIE* UNIT 2 5-8 Amendment No.

St. Lucie Nuclear Plant L-2016-212 Docket Nos. 50-335 and 50-389 *Enclosure Page 35 of 35 Attachment 4 ADMINISTRATIVE CONTROLS

q. Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a.. The Surveillance Frequency Control Program shall contain a list.of frequencies of those Surveillance Requirements for which the frequency is controlled by the program.

b. Changes to the frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the frequencies established in the Surveillance Frequency Control Program.

r. Component Cyclic or Transient Limit Program The Program provides controls to track t.he FSAR,.Section 3.9, cyclic and transient occurrences to ensure that components are mciintained within tt)e desi.gn limits.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements ofTitle 10, Code of Federal Regulations, the following reports shall be .submitted to the NRC.

STARTUP REPORT 6.9.1.1.A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier; and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be .described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program; (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

' ST. LUCIE - UNIT 2 6-16 Amendment No.~.  ;;a, G:l, 444,

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