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{{#Wiki_filter:DOCKET 05000389 NOTES: REGULATORY Of%ÃTION DISTRIBUTION SY.M~IOS)ACCESSION NBR:8208120019 DOC~OATEN'2/08/02 NOTARIZED:
{{#Wiki_filter:REGULATORY               Of%ÃTION DISTRIBUTION SY           .M ~IOS)
YES FACIL:50-389 St.Lucie PlantP Unit 2<Florida Power L Light Co.AUTH, NAME AUTHOR AFFILIATION UHRIGPRSEB Florida Power 8 l.ight Co, ROC IP~NAME RECIPIENT AFFILIATION EISENHUTPD,G, Division of Licensing  
ACCESSION NBR:8208120019                   DOC ~ OATEN'2/08/02       NOTARIZED: YES             DOCKET FACIL:50-389 St. Lucie PlantP Unit                   2< Florida   Power L   Light   Co. 05000389 AUTH, NAME             AUTHOR         AFFILIATION UHRIGPRSEB             Florida Power 8 l.ight Co, ROC IP ~ NAME         RECIPIENT AFFILIATION EISENHUTPD,G,         Division of Licensing
                                                                              /g/ ~I E:


==SUBJECT:==
==SUBJECT:==
Forw rds Amend 11 to FSAR,+/0 tE Us(/5~M~A l/ol W.~/g/~DISTRIBUTION CODE: BOO IS COPIES RE EIVED:LTR EN L$I E: 1 Q.0 TITLE: PSAR/FSAR AMOTS and Related Correspondence RECIPIENT ID CODE/NAME A/D LICENSNG LIC BR P3 LA'TERNAL0 ELD/HDS2 IE/DEP EPOS 35 NRR/DE/CEB li NRR/DE/GB 28 NRR/OE/MEB 18 NRf4/DE/QAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRf</OHF S/PTRB20 NRR/DSI/ASB 27 NRR/DS I/CS8 09 NRR/DSI/ICSB ie NRR/DS I/RAB 22 NRR/OST/LGB 33 RGN2 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 0 1 0 1 0 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 10 10 1 1 1 1 1 1 RECIPIENT ID CODE/NAME LIC BR 43 BC NERSESPV, 01 IE FILE IE/OEP/EPLB 36 NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 20 NRR/DHFS/HFEBPO
Forw rds Amend 11 to FSAR,
" NRR/DHFS/OLB 34 NRR/DSI/AEB
      +/0 tE Us( /5 ~ M~A l/ol W                                         ~
?6 NRR/DSI/CPB 10 NRR/DS I/ETSB 12 NRR/DS I/PSB 19 NRR RSB 23 0g RM/DDAMI/MIB BNL (AMDTS ONlY)FEMA-REP DIV 39 NRC PDR 0?NTIS COPIES LTTR ENCL 1 0 1 1 1 1 3 3 3 3 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 T)TAL NUMBER Of COPIES REQUIRED: LTTR 58 ENCL 53 0~0~I~T~4'1~h J ,-'!k)q't t 1 I<'a) e 0 P.OX 1 JUNO BEACH, FL 3340B FLORIDA POWER&LIGHT COMPANY August 2, 1982 L-82-308 Office of Nuclear Reactor Regulation Attention:
Q. 0
Nr.Darrell G.Eisenhut, Director Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555
                                                      .
DISTRIBUTION CODE:
TITLE: PSAR/FSAR BOO AMOTS IS COPIES RE EIVED:LTR and Related Correspondence EN L
                                                                                $             1 NOTES:
RECIPIENT                  COPIES              RECIPIENT              COPIES ID CODE/NAME                LTTR ENCL        ID CODE/NAME           LTTR ENCL A/D LICENSNG                           0      LIC BR 43 BC              1    0 LIC BR P3 LA                 1      0      NERSESPV,        01        1    1 ELD/HDS2       'TERNAL0 1      0      IE FILE                    1    1 IE/DEP   EPOS     35                         IE/OEP/EPLB      36        3    3 NRR/DE/CEB NRR/DE/GB li 28 1
1 2
1 1
2 NRR/DE/EQB NRR/DE/HGEB 30 13        3 2
3 2
NRR/OE/MEB          18          1      1      NRR/DE/MTEB 17             1    1 NRf4/DE/QAB        21          1      1      NRR/DE/SAB       20       1    1 NRR/DE/SEB        25          1      1      NRR/DHFS/HFEBPO     "     1    1 NRR/DHFS/LQB 32                1      1      NRR/DHFS/OLB 34           1    1 NRf</OHF S/PTRB20              1              NRR/DSI/AEB ?6             1    1 NRR/DSI/ASB 27                        1      NRR/DSI/CPB     10       1    1 NRR/DS I/CS8        09                1      NRR/DS I/ETSB   12       1    1 NRR/DSI/ICSB ie                1              NRR/DS I/PSB 19           1    1 NRR/DS I/RAB 22                        1      NRR      RSB   23       1    1 NRR/OST/LGB        33          1      1                        0g       1    1 RGN2                            2      2      RM/DDAMI/MIB               1    0 EXTERNAL: ACRS                  41          10    10      BNL (AMDTS ONlY)
DMB/DSS (AMDTS)                1      1      FEMA-REP DIV 39 LPDR                03          1      1      NRC PDR         0?
NSIC                05          1     1       NTIS T)TAL NUMBER Of COPIES             REQUIRED: LTTR       58   ENCL     53


==Dear ter.Eisenhut:==
0 ~      0 ~        T ~
Re: St.Lucie Unit 2 Docket No.50-389'mendment 11 to The Final Sf A i1 ill In accordance with the requirements of 10 CFR 50.30, Florida Power 8 Light Company (FPL)is submitting sixty (60)copies of Amendment 11 to the Final Safety Analysis Report, St.Lucie Plant Unit 2.The changes to the amendment are contained in the attachment.
I ~
Very truly yours, Robert E.Uhrig Vice President Advanced Systems and Technology REU/RAK/cab Attachments cc: J.P.O'Reilly, Director, Region II (w/o attachments)
4
Harold F.Reis, Esquire (w/o attachments)
                                  '1
PEOPLE...SERVING PEOPLE STATE OF FLOREDA))COUNTY OF DADE)ss~being first.duly sworn, deposes and says: That he is Vice President Light Company, the herein;of Florida Power&That he has executed the foregoing document;that the state-ments made in this said document are true and correct, to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Robert E.Uhrig Subscribed and sworn to before me this~day of 19$~r'I NOTARY PUBLIC"-~Stai.e of Flo'y t ommission in and for the County of Dade, da N to~pUbtlc, Stete of Ronde ttt Lttrgo Cornrneszn Expire".October 30, ISG3 expires: My r~~:;~
                              ~ h J
0 0 I G I sr Iq I ATTACHMENT TO L-82-308 dated Au ust 2, 1982 Changes in the St Lucie Plant Unit 2 FSAR as a result of Amend-ment 11.Chapter 1-The changes basically contain revisions to reflect the changes in plant design as a result of NRC re-view and various commitments made to the NRC.This makes Chapter 1 consistent with the rest of the FSAR.In Section 1.1 value of net electrical output for rated power is corrected to correspond to the License Application and ER.In Section 1.3 slight changes are made to plant parameters to reflect final design values.In Section 1.7 update of the instrument arrangement and CWD list is provided.In Section 1.9A updates of information related to CE owners group effort on TMI related items are provided.Chapter 2 Clarified information found in text, revised ref-erences to figures, corrected typographical errors in equations, added references and revised a draw-ing.Chapter 3 Changes are made for consistency with other chapters of the FSAR, provided additional information on J<<impingement analysis and recently completed IEALA study (Section 3.9).In Section 3.10, seismic qualification data for electrical equipment and instrumentation are updated to reflect additional information available from vendor.Section 3.11 writeup for environment quali-fication has been basically deleted and supplemented with references to the Environmental Qualification Report 6 Guidebook previously submitted to the NRC under seperate cover.Chapter 4 Chapter 5 Revised to reflect the fact that part length CEAs will not be used in St Lucie Unit 2.Also updated are core parameters to reflect the final design.Minor clarification, cross-references to other FSAR sections and changes for consistency with other FSAR sections are made.
          , -'!k
Chapter 5 cont'd In Section 5.2 missing design information on Reactor Coolant Leak Detection Sensitivity is provided.In Appendix 5.2B additional information as to the amount of condensate water required to bring St Lucie Unit 2 thru four hours of hotstandby followed by natural circulation cooldown without upper head.voiding is provided.In Section 5.4 Condensate Storage tank water volume is revised to be consistent with already existing Chapter 10 values.The Failure Mode and Effects Analysis for Shutdown Cooling System is reformatted to include additional information on"Inherent Compensating Provisions" and"Remarks and other Efforts".Section 6.1 Indicated that insignificant amounts of PVC is used inside the containment and other minor changes to reflect the plant, design.Section 6.2 Section 6.3 Section 6.5 Modified design parameters slightly to reflect as-built conditions'.
                    ) q't t
Revised location of Hydro-gen analyvzers, tables in 6.2 to correct typos and other changes for consistency with the informa-tion provided to the NRC before.Inserted new revision of figures.Added new information on small break analysis per-formed with-0.15 and-0.25.ASIU.Safety Injection System FMEA was reformatted.
1 I
Included new power operated valves to listing.Increased number of TSP baskets present in the vicinity of the SL2 sump.Section 7.1 Section 7.2 Section 7.3 Minor changes for clarification and consistency with information already provided to the NRC.The asymmetric Steam Generator Transient Protective Trip Function is incorporated in the writeup.Reactor Protective System input values are updated to reflect final design.Battery fail bypass is added to the description of AFAS bypasses.Other changes made for clarifica-tion and consistency.
  < 'a)
Section 7.4 Post Accident Monitoring Instrumentation listing j.s updated and"instrument loop accuracys" values are provided.Additions are made to the safety related annunciator windows listing.
 
Appendix 7.5A-The Safety Assessment System writeup is updated to reflect current design.Section 7.6 Added information on Pressurizer Level Alarm and Heater Cutout.Section 8.2 Revised subsection on Grid availability to reflect current information, corrected titles on the load flow diagrams.Section 8.3 Cha ter 9 Cha ter 10 Section 10.4 Various changes made to writeup to primarily incorporate changes resulted from NRC review items like QSPDS and SAS.Inserted new Diesel Generator Loading Table and Battery Load Group table showing new loading sequence as a result of NRC concerns and questions.
e 0                                    P. OX 1    JUNO BEACH, FL 3340B FLORIDA POWER & LIGHT COMPANY August 2, 1982 L-82-308 Office of Nuclear Reactor Regulation Attention: Nr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Changes are made to the design information to reflect as built design, for consistency with other FSAR Sections, to incorporate information provided to the NRC previously and for completeness.
 
P Inserted latest revision of Drawings where applicable.
==Dear ter. Eisenhut:==
Provided clarification on the volume of'ondensate Storage Tank water available at St Lucie 2.Also, included information on CST water required to hold the plant at hot standby for 23 hours and subseQuent cooldown for four hours.Cha ter 11 Section 11.2 has minor changes made for consistency, clarification and proper cross-references to the other sections of the FSAR and to incorporate infor-mation already provided to the NRC.Designated the Liquid Water Concentrator Bottoms Tank as a future installation.
 
Section 11.3 Designated
Re:   St. Lucie Unit    2 Docket No. 50-389 Sf    A  i1 11  to  The ill
'the second oxygen analyzers of the GWMS as a future installation.
                            'mendment In accordance with the requirements Final of 10 CFR 50.30, Florida Power 8 Light  Company (FPL)     is submitting sixty (60) copies of Amendment              11 to the Final Safety Analysis Report, St. Lucie Plant Unit 2.
Section 11.5 Updated information on rad monitors per revised vendor's specifications.
The changes  to the  amendment          are contained in the attachment.
Cha ter 12 Cha ter 13 Upadated radiation monitor data to agiee with revise'd vendor's specifications.
Very  truly yours, Robert E. Uhrig Vice President Advanced Systems    and Technology REU/RAK/cab Attachments cc:   J. P. O'Reilly, Director, Region              II (w/o attachments)
Updated to reflect the current personnel changes and restructuring of the organization as a result of NRC review.Plant training schedule is also slightly modified.
Harold F. Reis, Esquire (w/o attachments)
45'4~CC 14~Ch 15.Discription of Auxiliary Feedwater System functional and endurance test and auto actuation system test are added.This chapter has been revised for consistency with changes made to the other chapters of the FSAR primarily generated as a result of the NRC review.'ection 15.0-Section 15.C.6 Section 15.C.7 The sequence of event diagrams are revised to correspond to the new Diesel Generator loading table in Chapter 8.Revised tables to indicate proper sequencing of events in terms of time and accident assumptions.
PEOPLE... SERVING PEOPLE
Added new information on the Atmospheric Dump Valve, Automatic Controls and a statement on the effects of PLCEA on accident analysis.The decision not to use PLCEA's in St Lucie 2 design, does not affect the accident analysis results.Added new subsection on Inadvertent opening of a pressurizer relief valve.Added a new subsection on one'ump resistance to forced flow.Section 1S.C.8 Added new subsection on opening one Atmospheric Dump Valve.NRC uestions 210A NRC uestions Revised response to indicate'that the list of snubbers would be provided in the Technical Specifications.
 
220 Clarified responses to indicate that the pressure described was that of the soil.NRC uestions 240 Added a clarifying statement to the response to describe the PNH groundwater level used in plant design.280 Revi'sed responses to reflect the most recent commitments made to the NRC.  
STATE OF FLOREDA          )
'0~
                                )      ss  ~
NRC ues tions 410 NRC uestions Inserted new response on Light Loads.Information has been previously transmitted to the NRC.Revised response due to the results of flooding of safety related equipment.
COUNTY OF DADE            )
420 NRC uestions Included additional information developed as a result of various NRC review requirements.
being    first. duly            sworn, deposes      and says:
Regulatory Guide 1.97 listing is updated to add new items.430A Inserted Question/Responses on PSB, R.G.1.63 conformance and total loss of A.C.Power.This information has been previously transmitted to'he NRC.NRC uestions 440 Clarifications added and changes made to incorporate requirements resulting from NRC review.}}
That he      is          Vice President                                of Florida Power &
Light Company, the                      herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct, to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Robert E. Uhrig Subscribed and sworn to before                me    this
        ~day            of                                           19    $  ~
r          'I NOTARY PUBLIC        in and for the       County        of    Dade,
  "-~ Stai.e    of Flo    da
    'y    t    ommission expires:
N My to~
                                              ~~:;
pUbtlc, Stete of Ronde ttt Lttrgo Cornrneszn r          Expire". October 30, ISG3
                                                                            ~
 
0 0 I
G I
I sr Iq
 
ATTACHMENT TO L-82-308 dated Au ust 2, 1982 Changes  in the St Lucie Plant Unit      2  FSAR as a  result of Amend-ment 11.
Chapter 1 The  changes basically contain revisions to reflect the changes in plant design as a result of NRC re-view and various commitments made to the NRC. This makes Chapter 1 consistent with the rest of the FSAR.
In Section 1.1 value of net electrical output for rated power is corrected to correspond to the License Application and ER.
In Section 1.3 slight changes are made to plant parameters to reflect final design values.
In Section 1.7 update of the instrument arrangement and CWD list is provided.        In Section 1.9A updates of information related to CE owners group effort on TMI related items are provided.
Chapter 2  Clarified information found in text, revised ref-erences to figures, corrected typographical errors in equations, added references and revised a draw-ing.
Chapter  3  Changes are made for consistency with other chapters of the FSAR, provided additional information on J<<
impingement analysis and recently completed IEALA study (Section 3.9).
In Section 3.10, seismic qualification data for electrical equipment and instrumentation are updated to reflect additional information available from vendor. Section 3.11 writeup for environment quali-fication has been basically deleted and supplemented with references to the Environmental Qualification Report 6 Guidebook previously submitted to the NRC under seperate  cover.
Chapter  4  Revised to     reflect  the fact that part length CEAs will not    be used  in St Lucie Unit 2. Also updated are core parameters to reflect the final design.
Chapter  5  Minor  clarification, cross-references to other FSAR  sections and changes for consistency with other FSAR  sections are made.
 
Chapter  5  In Section 5.2 missing design information on Reactor cont'd    Coolant Leak Detection Sensitivity is provided.
In Appendix 5.2B additional information as to the amount of condensate water required to bring St Lucie Unit 2 thru four hours of hotstandby followed by  natural circulation cooldown without upper head .
voiding is provided.
In Section 5.4 Condensate Storage tank water volume existing is revised to be consistent with already Effects Chapter  10 values. The Failure  Mode and Analysis for Shutdown Cooling System is reformatted to include additional information on "Inherent Compensating Provisions" and "Remarks and other Efforts".
Section 6. 1 Indicated that insignificant amounts of PVC is used inside the containment and other minor changes to reflect the plant, design.
Section 6.2  Modified design parameters slightly to reflect as-built conditions'. Revised location of Hydro-gen analyvzers, tables in 6.2 to correct typos and other changes for consistency with the informa-tion provided to the NRC before. Inserted new revision of figures.
Section 6.3  Added new information on small break analysis per-formed with -0.15 and -0.25. ASIU. Safety Injection System FMEA was reformatted.      Included new power operated valves to listing.
Section 6.5  Increased number of TSP baskets present in the vicinity of the SL2 sump.
Section 7.1  Minor changes for clarification and consistency with information already provided to the NRC.
Section 7.2  The asymmetric Steam Generator Transient Protective Trip Function is incorporated in the writeup.
Reactor Protective System input values are updated to reflect final design.
Section 7.3 Battery fail bypass is added to the description of AFAS bypasses. Other changes made for clarifica-tion and consistency.
Section 7.4  Post Accident Monitoring Instrumentation listing j.s updated and "instrument loop accuracys" values are provided. Additions are made to the safety related annunciator windows listing.
 
Appendix 7.5A The Safety Assessment    System writeup is updated to reflect current design.
Section 7.6  Added information on Pressurizer Level Alarm and Heater  Cutout.
Section 8.2    Revised subsection on Grid    availability to reflect current information, corrected titles on the load flow diagrams.
Section 8.3    Various changes made to writeup to primarily incorporate changes resulted from NRC review items like QSPDS and SAS. Inserted new Diesel Generator Loading Table and Battery Load Group table showing new loading sequence as a result of NRC concerns and questions.
Cha  ter 9    Changes are made to the design information to reflect as built design, for consistency with other FSAR Sections, to incorporate information provided to the NRC previously and for completeness.
P Cha  ter 10    Inserted latest revision of Drawings where applicable.
Section 10.4  Provided clarification on the volume of'ondensate Storage Tank water available at St Lucie 2. Also, included information on CST water required to hold the plant at hot standby for 23 hours and subseQuent cooldown for four hours.
Cha  ter 11    Section 11.2 has minor changes made for consistency, clarification and proper cross-references to the other sections of the FSAR and to incorporate infor-mation already provided to the NRC.
Designated the Liquid Water Concentrator Bottoms Tank as a  future installation.
Section 11.3  Designated 'the second oxygen analyzers of the    GWMS as a  future installation.
Section 11.5  Updated information on rad monitors per revised vendor's specifications.
Cha  ter 12    Upadated radiation monitor data to agiee with revise'd vendor's specifications.
Cha  ter 13    Updated to reflect the current personnel changes and restructuring of the organization as a result of NRC review. Plant training schedule is also slightly modified.
 
45
'
4
      ~CC      14    Discription of Auxiliary Feedwater System functional and endurance test and auto actuation system test are added.
      ~Ch      15 . This chapter has been revised for consistency with changes made to the other chapters of the FSAR primarily generated as a result of the NRC The sequence              of event diagrams are revised to correspond to the new Diesel Generator loading table in Chapter 8.
review.'ection Revised tables to indicate proper sequencing of events in terms of time and accident assumptions.
15.0 Added new            information on the Atmospheric Dump Valve, Automatic Controls and a statement on the effects of PLCEA on accident analysis. The decision not to use PLCEA's in St Lucie 2 design, does not affect the accident analysis results.
Section 15.C.6 Added new subsection              on  Inadvertent opening of  a pressurizer              relief valve.
Section 15.C.7 Added a new subsection              on one'ump resistance to forced flow.
Section 1S.C.8 Added new subsection on opening one Atmospheric Dump Valve.
NRC   uestions 210A       Revised response to indicate'that the list of snubbers would be provided in the Technical Specifications.
NRC  uestions 220       Clarified             responses to indicate that the pressure described was that of the soil.
NRC   uestions 240       Added a             clarifying statement to the   response to describe the             PNH groundwater level used in plant design.
280       Revi'sed responses to reflect the most recent commitments made to the NRC.
 
'0 ~
NRC   ues tions 410         Inserted new response   on Light Loads. Information has been previously   transmitted to the NRC.       Revised response due to the   results of flooding of safety related equipment.
NRC   uestions 420        Included additional information developed as a result of various NRC review requirements. Regulatory Guide 1.97 listing is updated to add new items.
NRC  uestions 430A       Inserted Question/Responses on PSB, R.G. 1.63 conformance and total loss of A.C. Power. This information has been previously transmitted     to'he NRC.
NRC   uestions 440         Clarifications added and changes made to incorporate requirements resulting from NRC review.}}

Revision as of 00:28, 30 October 2019

Forwards Amend 11 to FSAR
ML17213A321
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/02/1982
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML17213A323 List:
References
L-82-308, NUDOCS 8208120019
Download: ML17213A321 (11)
v • d • e


Text

REGULATORY Of%ÃTION DISTRIBUTION SY .M ~IOS)

ACCESSION NBR:8208120019 DOC ~ OATEN'2/08/02 NOTARIZED: YES DOCKET FACIL:50-389 St. Lucie PlantP Unit 2< Florida Power L Light Co. 05000389 AUTH, NAME AUTHOR AFFILIATION UHRIGPRSEB Florida Power 8 l.ight Co, ROC IP ~ NAME RECIPIENT AFFILIATION EISENHUTPD,G, Division of Licensing

/g/ ~I E:

SUBJECT:

Forw rds Amend 11 to FSAR,

+/0 tE Us( /5 ~ M~A l/ol W ~

Q. 0

.

DISTRIBUTION CODE:

TITLE: PSAR/FSAR BOO AMOTS IS COPIES RE EIVED:LTR and Related Correspondence EN L

$ 1 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A/D LICENSNG 0 LIC BR 43 BC 1 0 LIC BR P3 LA 1 0 NERSESPV, 01 1 1 ELD/HDS2 'TERNAL0 1 0 IE FILE 1 1 IE/DEP EPOS 35 IE/OEP/EPLB 36 3 3 NRR/DE/CEB NRR/DE/GB li 28 1

1 2

1 1

2 NRR/DE/EQB NRR/DE/HGEB 30 13 3 2

3 2

NRR/OE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRf4/DE/QAB 21 1 1 NRR/DE/SAB 20 1 1 NRR/DE/SEB 25 1 1 NRR/DHFS/HFEBPO " 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/OLB 34 1 1 NRf</OHF S/PTRB20 1 NRR/DSI/AEB ?6 1 1 NRR/DSI/ASB 27 1 NRR/DSI/CPB 10 1 1 NRR/DS I/CS8 09 1 NRR/DS I/ETSB 12 1 1 NRR/DSI/ICSB ie 1 NRR/DS I/PSB 19 1 1 NRR/DS I/RAB 22 1 NRR RSB 23 1 1 NRR/OST/LGB 33 1 1 0g 1 1 RGN2 2 2 RM/DDAMI/MIB 1 0 EXTERNAL: ACRS 41 10 10 BNL (AMDTS ONlY)

DMB/DSS (AMDTS) 1 1 FEMA-REP DIV 39 LPDR 03 1 1 NRC PDR 0?

NSIC 05 1 1 NTIS T)TAL NUMBER Of COPIES REQUIRED: LTTR 58 ENCL 53

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e 0 P. OX 1 JUNO BEACH, FL 3340B FLORIDA POWER & LIGHT COMPANY August 2, 1982 L-82-308 Office of Nuclear Reactor Regulation Attention: Nr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear ter. Eisenhut:

Re: St. Lucie Unit 2 Docket No. 50-389 Sf A i1 11 to The ill

'mendment In accordance with the requirements Final of 10 CFR 50.30, Florida Power 8 Light Company (FPL) is submitting sixty (60) copies of Amendment 11 to the Final Safety Analysis Report, St. Lucie Plant Unit 2.

The changes to the amendment are contained in the attachment.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/RAK/cab Attachments cc: J. P. O'Reilly, Director, Region II (w/o attachments)

Harold F. Reis, Esquire (w/o attachments)

PEOPLE... SERVING PEOPLE

STATE OF FLOREDA )

) ss ~

COUNTY OF DADE )

being first. duly sworn, deposes and says:

That he is Vice President of Florida Power &

Light Company, the herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct, to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Robert E. Uhrig Subscribed and sworn to before me this

~day of 19 $ ~

r 'I NOTARY PUBLIC in and for the County of Dade,

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'y t ommission expires:

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pUbtlc, Stete of Ronde ttt Lttrgo Cornrneszn r Expire". October 30, ISG3

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ATTACHMENT TO L-82-308 dated Au ust 2, 1982 Changes in the St Lucie Plant Unit 2 FSAR as a result of Amend-ment 11.

Chapter 1 The changes basically contain revisions to reflect the changes in plant design as a result of NRC re-view and various commitments made to the NRC. This makes Chapter 1 consistent with the rest of the FSAR.

In Section 1.1 value of net electrical output for rated power is corrected to correspond to the License Application and ER.

In Section 1.3 slight changes are made to plant parameters to reflect final design values.

In Section 1.7 update of the instrument arrangement and CWD list is provided. In Section 1.9A updates of information related to CE owners group effort on TMI related items are provided.

Chapter 2 Clarified information found in text, revised ref-erences to figures, corrected typographical errors in equations, added references and revised a draw-ing.

Chapter 3 Changes are made for consistency with other chapters of the FSAR, provided additional information on J<<

impingement analysis and recently completed IEALA study (Section 3.9).

In Section 3.10, seismic qualification data for electrical equipment and instrumentation are updated to reflect additional information available from vendor. Section 3.11 writeup for environment quali-fication has been basically deleted and supplemented with references to the Environmental Qualification Report 6 Guidebook previously submitted to the NRC under seperate cover.

Chapter 4 Revised to reflect the fact that part length CEAs will not be used in St Lucie Unit 2. Also updated are core parameters to reflect the final design.

Chapter 5 Minor clarification, cross-references to other FSAR sections and changes for consistency with other FSAR sections are made.

Chapter 5 In Section 5.2 missing design information on Reactor cont'd Coolant Leak Detection Sensitivity is provided.

In Appendix 5.2B additional information as to the amount of condensate water required to bring St Lucie Unit 2 thru four hours of hotstandby followed by natural circulation cooldown without upper head .

voiding is provided.

In Section 5.4 Condensate Storage tank water volume existing is revised to be consistent with already Effects Chapter 10 values. The Failure Mode and Analysis for Shutdown Cooling System is reformatted to include additional information on "Inherent Compensating Provisions" and "Remarks and other Efforts".

Section 6. 1 Indicated that insignificant amounts of PVC is used inside the containment and other minor changes to reflect the plant, design.

Section 6.2 Modified design parameters slightly to reflect as-built conditions'. Revised location of Hydro-gen analyvzers, tables in 6.2 to correct typos and other changes for consistency with the informa-tion provided to the NRC before. Inserted new revision of figures.

Section 6.3 Added new information on small break analysis per-formed with -0.15 and -0.25. ASIU. Safety Injection System FMEA was reformatted. Included new power operated valves to listing.

Section 6.5 Increased number of TSP baskets present in the vicinity of the SL2 sump.

Section 7.1 Minor changes for clarification and consistency with information already provided to the NRC.

Section 7.2 The asymmetric Steam Generator Transient Protective Trip Function is incorporated in the writeup.

Reactor Protective System input values are updated to reflect final design.

Section 7.3 Battery fail bypass is added to the description of AFAS bypasses. Other changes made for clarifica-tion and consistency.

Section 7.4 Post Accident Monitoring Instrumentation listing j.s updated and "instrument loop accuracys" values are provided. Additions are made to the safety related annunciator windows listing.

Appendix 7.5A The Safety Assessment System writeup is updated to reflect current design.

Section 7.6 Added information on Pressurizer Level Alarm and Heater Cutout.

Section 8.2 Revised subsection on Grid availability to reflect current information, corrected titles on the load flow diagrams.

Section 8.3 Various changes made to writeup to primarily incorporate changes resulted from NRC review items like QSPDS and SAS. Inserted new Diesel Generator Loading Table and Battery Load Group table showing new loading sequence as a result of NRC concerns and questions.

Cha ter 9 Changes are made to the design information to reflect as built design, for consistency with other FSAR Sections, to incorporate information provided to the NRC previously and for completeness.

P Cha ter 10 Inserted latest revision of Drawings where applicable.

Section 10.4 Provided clarification on the volume of'ondensate Storage Tank water available at St Lucie 2. Also, included information on CST water required to hold the plant at hot standby for 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> and subseQuent cooldown for four hours.

Cha ter 11 Section 11.2 has minor changes made for consistency, clarification and proper cross-references to the other sections of the FSAR and to incorporate infor-mation already provided to the NRC.

Designated the Liquid Water Concentrator Bottoms Tank as a future installation.

Section 11.3 Designated 'the second oxygen analyzers of the GWMS as a future installation.

Section 11.5 Updated information on rad monitors per revised vendor's specifications.

Cha ter 12 Upadated radiation monitor data to agiee with revise'd vendor's specifications.

Cha ter 13 Updated to reflect the current personnel changes and restructuring of the organization as a result of NRC review. Plant training schedule is also slightly modified.

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~CC 14 Discription of Auxiliary Feedwater System functional and endurance test and auto actuation system test are added.

~Ch 15 . This chapter has been revised for consistency with changes made to the other chapters of the FSAR primarily generated as a result of the NRC The sequence of event diagrams are revised to correspond to the new Diesel Generator loading table in Chapter 8.

review.'ection Revised tables to indicate proper sequencing of events in terms of time and accident assumptions.

15.0 Added new information on the Atmospheric Dump Valve, Automatic Controls and a statement on the effects of PLCEA on accident analysis. The decision not to use PLCEA's in St Lucie 2 design, does not affect the accident analysis results.

Section 15.C.6 Added new subsection on Inadvertent opening of a pressurizer relief valve.

Section 15.C.7 Added a new subsection on one'ump resistance to forced flow.

Section 1S.C.8 Added new subsection on opening one Atmospheric Dump Valve.

NRC uestions 210A Revised response to indicate'that the list of snubbers would be provided in the Technical Specifications.

NRC uestions 220 Clarified responses to indicate that the pressure described was that of the soil.

NRC uestions 240 Added a clarifying statement to the response to describe the PNH groundwater level used in plant design.

280 Revi'sed responses to reflect the most recent commitments made to the NRC.

'0 ~

NRC ues tions 410 Inserted new response on Light Loads. Information has been previously transmitted to the NRC. Revised response due to the results of flooding of safety related equipment.

NRC uestions 420 Included additional information developed as a result of various NRC review requirements. Regulatory Guide 1.97 listing is updated to add new items.

NRC uestions 430A Inserted Question/Responses on PSB, R.G. 1.63 conformance and total loss of A.C. Power. This information has been previously transmitted to'he NRC.

NRC uestions 440 Clarifications added and changes made to incorporate requirements resulting from NRC review.

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