ML17213A321

Forwards Amend 11 to FSAR

ML17213A321
Person / Time
Site:	Saint Lucie
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: ML17213A321
References
L-82-308, NUDOCS 8208120019
Download: ML17213A321 (11)

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

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SUBJECT:

Forw rds Amend 11 to FSAR,

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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 )

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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.

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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.