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| issue date = 01/31/1987
| issue date = 01/31/1987
| title = Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept
| title = Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept
| author name = STOFFEL J W
| author name = Stoffel J
| author affiliation = EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
| author affiliation = EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:EGG-NTA-7477 TECHNICAL EVALUATION REPORTREVIEWOFTECHNICAL SPECIFICATION CHANGESSUPPORTING NUREG-0737 ACCIDENTINSTRUMENTATION, ST.LUCIEPLANT,UNITNOS.1AND2DocketNos.50-335and50-389J.W.StoffelPublished January1987EG&GIdaho,Inc.IdahoFalls,Idaho83415,PreparedfortheU.S.NuclearRegulatory Commission Washington, D.C.20555UnderDOEContractNo.DE-AC07-76I001570 FINNo.06023@~so30G9'5 ABSTRACTThisEG&GIdaho,Inc.,reportreviews,thelicenseesubmittal requesting anamendment toplanttechnical specifications regarding instrumentation thathasbeeninstalled tomeettherequirements ofNUREG-0737.
{{#Wiki_filter:EGG-NTA-7477 TECHNICAL EVALUATION REPORT REVIEW OF TECHNICAL SPECIFICATION CHANGES SUPPORTING NUREG-0737 ACCIDENT INSTRUMENTATION, ST. LUCIE PLANT, UNIT NOS. 1 AND 2 Docket Nos. 50-335 and 50-389 J. W. Stof f el Published January 1987 EG&G  Idaho, Inc.
DocketNos.50-335and50-389TACNos.59356and59357 FORENORDThisreportissuppliedaspartofaprogramforcaseworkreviewofvariousnuclearpowerplantsandissues.Thisworkisbeingconducted fortheU.S.NuclearRegulatory Commission, OfficeofNuclearReactorRegulation, DivisionofP~ARLicensing-B, byfG8GIdaho,Inc.,NRRandI&ESupportBranch.TheU.S.NuclearRegulatory Commission fundedthisworkunderFINNo.06023.DocketNos.50-335and50-389TACNos.59356and59357 CONTENTSABSTRACT..~~~~~~~~~~~~~~~~FOREMOROo~~~~~~~~~~~~~~~~~~~~~~
Idaho  Falls, Idaho 83415, Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76I001570 FIN No. 06023
                      @~so 30 G9'5


==1.0INTRODUCTION==
ABSTRACT This EG&G Idaho, Inc., report reviews, the licensee submittal requesting an amendment to plant technical specifications regarding instrumentation that has been installed to meet the requirements of NUREG-0737.
Docket Nos. 50-335 and 50-389 TAC Nos. 59356 and 59357


~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~12.0BACKGROUND
FORENORD This report is supplied as part of a program for case work review of various nuclear power plants and issues. This work is being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of P~AR Licensing-B, by fG8G Idaho, Inc., NRR and I&E Support Branch.
~~~23.0EVALUATION
The U.S. Nuclear Regulatory Commission funded this work under FIN No. 06023.
~~~~~~~~~~~~~~~~
Docket Nos. 50-335 and 50-389 TAC Nos. 59356 and 59357


==34.0CONCLUSION==
CONTENTS ABSTRACT  ..                                                                                        ~  ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
S
F OREMORO o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~   ~ ~
~~~~~~~~~~~~~~~


==45.0REFERENCES==
==1.0  INTRODUCTION==
                      ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~  1


..........................................;......
==2.0  BACKGROUND==
~....5
                                                                                                        ~    ~  ~   2
: 3. 0  EVALUATION                                                                                    ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~  3


REVIEWOFTECHNICAL SPECIFICATION CHANGESSUPPORTING NUREG-0737 ACCIDENTINSTRUMENTATION ST.LUCIEPLANTUNITNOS.1AND21~0INTRODUCTION NUREG-0737, includesrequirements forspecificaccidentmonitoring 1instrumentation.
==4.0  CONCLUSION==
ThelicenseefortheSt.LuciePlant,UnitNos.1and2,hasidentified thenecessary instrumentation installed inthesetwounits2tomeettherequirements.
S                                                                      ~ ~  ~ ~ ~ ~  ~  ~ ~ ~ ~      ~ ~  ~ ~  4 5 .0  REFERENCES        ..........................................;......                                                 ~ .... 5
Inasubmittal datedJuly19,1985,thelicenseerequested NRCapprovalofproposedlicenseeamendments totheunits'echnical Specifications reflecting theaddedinstrumentation andrequirements ofNUREG-0737.
Thisreportprovidesanevaluation oftheproposedchangestothetechnical specifications forthetwounits.Thelicensee's submittal identifies theaffectedsectionsofthetechnical specifications.
Theseare:Tables3.3-11and4.3-7forUnitNo.1andTables3.3-10and4.3-7forUnitNo.2.Also,additional appropriate operability andactionstatements areincluded.  


==2.0 BACKGROUND==
REVIEW OF TECHNICAL SPECIFICATION CHANGES SUPPORTING NUREG-0737 ACCIDENT INSTRUMENTATION ST. LUCIE PLANT    UNIT NOS. 1 AND 2 1 ~ 0 INTRODUCTION 1
Theaccidentmonitoring instrumentation, Table3.3-llandtheaccidentmonitoring instrumentation surveillanc'e requirements, Table4.3-7oftheSt.Lucie1Technical Specifications donotpresently coveralltheinstalled accidentmonitoring instrumentation.
NUREG-0737,    includes requirements for specific accident monitoring instrumentation. The licensee for the St. Lucie Plant, Unit Nos. 1 and 2, has identified the necessary instrumentation installed in these two units 2
Thelicenseehasaddedincorethermocouples, containment sumpwaterlevel(narrowandwideranges),containment pressureandreactorvessellevelmonitoring systeminstrumentation totheplant.Theaccidentmonitoring instrumentation, Table3.3-lOandtheaccidentmonitoring instrumentation surveillance requirements, Table4.3-7oftheSt.Lucie2Technical Specifications donotpresently coveralltheinstalled accidentmonitoring instrumentation.
to meet the requirements.      In a submittal dated July 19, 1985, the licensee requested NRC approval of proposed licensee amendments to the units'echnical Specifications reflecting the added instrumentation and requirements of NUREG-0737. This report provides an evaluation of the proposed changes to the technical specifications for the two units.
Thelicenseehadaddedreactorvessellevelmonitoring systeminstrumentation totheplant.  
The licensee's    submittal identifies the affected sections of the technical specifications. These are: Tables 3.3-11 and 4.3-7 for Unit No. 1 and Tables 3.3-10 and 4.3-7 for Unit No. 2. Also, additional appropriate operability and action statements are included.


==3.0 EVALUATION==
==2.0 BACKGROUND==
Hehavecomparedtheproposedchangesinthetechnical specifications withtherequirements ofNUREG-0737 andfindthatthelicensees requestforanamendment totheSt.LuciePlant,UnitNos.land2Technical Specification indicates thatthechangesarenecessary andappropriate.
Theadditionofthiscurrently installed andoperational instrumentation tothetechnical specifications willprovideahigherdegreeofcontrolandoperational readiness byrequiring operability andmonthlysurveillance ofaccuracy.


==4.0CONCLUSION==
The accident monitoring instrumentation, Table 3.3-ll and the accident monitoring instrumentation surveillanc'e requirements, Table 4.3-7 of the St. Lucie 1 Technical Specifications do not presently cover all the installed accident monitoring instrumentation. The licensee has added incore thermocouples, containment sump water level (narrow and wide ranges), containment pressure and reactor vessel level monitoring system instrumentation to the plant.
S Basedonourevaluation, weconcludethefollowing withregardtotheproposedchangestotheplanttechnical specifications forSt.LuciePlant,UnitNos.1and2.oTheinstrumentation proposedforadditiontothetechnical specification tablesisconsistent withtherequirements ofNUREG-0737.
The accident monitoring instrumentation, Table 3.3-lO and the accident monitoring instrumentation surveillance requirements, Table 4.3-7 of the St. Lucie 2 Technical Specifications do not presently cover all the installed accident monitoring instrumentation. The licensee had added reactor vessel level monitoring system instrumentation to the plant.
oThechangesproposedbythelicenseetotheactionstatements andthesurveillance requirements areadequate.
oTheamendment involvesnosignificant hazardconsiderations inthatitisachangethatconstitutes anadditional limitation, restriction orcontrolnotpresently inthetechnical specifications.  


==5.0REFERENCES==
3.0  EVALUATION He have compared  the proposed changes in the technical specifications with the requirements of NUREG-0737 and find that the licensees request for an amendment to the St. Lucie Plant, Unit Nos. l and 2 Technical Specification indicates that the changes are necessary and appropriate.
The addition of this currently installed and operational instrumentation to the technical specifications will provide a higher degree of control and operational readiness by requiring operability and monthly surveillance of accuracy.


1.NUREG-0737, Clarification ofTMIActionPlanRequirements, II.F.l,NRC,November1980.2.Letter,FloridaPowerandLightCo.(J.N.WilliamsJr.)toNRC(H.L.Thompson),
==4.0    CONCLUSION==
"GenericLetter83-37,NUREG-0737 Technical Specifications,"
S Based on our    evaluation, we conclude the following with regard to the proposed changes    to the plant technical specifications for St. Lucie Plant, Unit Nos. 1  and 2.
July19,1985,L-85-252.
o    The  instrumentation proposed for addition to the technical specification tables is consistent with the requirements of NUREG-0737.
NRCFORMSSS12811NAChl1102,2201,2202U.S.NUCLEARREGULATORY COMMISSION BIBLIOGRAPHIC DATASHEETI,AEPOATNUMBER/AttiPntd oyTIDC,tddVolHo,!ItnclEGG-NTA-7477 SEEINSTRUCTIONS ONTHEAFVEASE2TITLcANDSUSTIT'REVIEMOFTECHNICAL SPECIFICATION CHANGESSUPPORTING NUREG-0737 ACCIDENTINSTRUMENTATION, ST.LUGIEPLANT,UNITNOS.1AIID22.LEAVEBLANKMONTHYEAAtDATEAEPORTCOMPLETED 6AI'THQAISi January1987J.W.Stoffel6DATEAEPORTISSUEDMON'TIIJanuary19877PEAFGAMINGORGANIZATION NAMEANOMAILINGADDRESSllntlcdtC!oCodtlEGSGIdaho,Inc.IdahoFalls,ID83415B.PAOIECTITASKlhYOAK UNITNUMBER!lPINOAGRANTNUMSEAA648310,SPONSORING ORGANIZATION NAMEANOMAILINGAQOAESSIlnttcdt2dCOdtlDivisionofSystemsIntegration OfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission ttashington, DC20555'l1~,TYPEOFREPORTTechnical Evaluation Report0,PEAIGDcovBREDIlntlctrrt dtltcl12SI.PPIchIENTARY NOTESIS,ABSTRACTI2'Vnordtor!tarThisEG8GIdaho,Inc.reportreviewsthelicenseesubmittal requesting anamendment toplanttechnical specifications regarding instrumentation thathasbeeninstalled tomeettherequirements ofNUREG-0737.
o    The changes    proposed by the licensee to the action statements    and the surveillance requirements are adequate.
14DOCUMENTANAI.YSIS c.KEYWOAOSIOESCAIPTOAS
o    The amendment    involves  no  significant hazard considerations in that  it  is a change  that constitutes an additional limitation, restriction or control not presently in the technical specifications.
'IS.AVAILABILITY STATEMENT O.IDENTIFIEASIOPcN ENDEDTEAMSIS.SECUAITYCLASSIFICATION ITnddtttl(Tnitrtoorrl17NUMBEROPPAGESIB!PAICE}}
 
==5.0  REFERENCES==
: 1. NUREG-0737, Clarification of  TMI  Action Plan Requirements, II.F.l, NRC, November 1980.
: 2. Letter, Florida  Power and Light  Co. (J. N. Williams Jr.) to  NRC (H. L. Thompson), "Generic Letter 83-37, NUREG-0737 Technical Specifications," July 19, 1985, L-85-252.
 
NRC FORM SSS                                                      U.S. NUCLEAR REGULATORY COMMISSION I, AEPOAT NUMBER /AttiPntd oy TIDC, tdd Vol Ho,!I tncl 12 811 NAChl 1102, 2201, 2202                      BIBLIOGRAPHIC DATA SHEET                                                      EGG-NTA-7477 SEE INSTRUCTIONS ON THE AFVEASE 2  TITLc AND SUSTIT'                                                                                 2. LEAVE BLANK REVIEM OF TECHNICAL SPECIFICATION CHANGES SUPPORTING NUREG-0737 ACCIDENT INSTRUMENTATION, ST. LUG IE PLANT, t DATE AEPORT COMPLETED UNIT NOS.         1  AIID 2 MONTH                              YEAA 6  AI'THQAISi                                                                                             January                                    1987 J. W. Stoffel                                                                                                    6 DATE AEPORT ISSUED MON'TII January                                    1987 7  PEAF GAMING ORGANIZATIONNAME ANO MAILINGADDRESS llntlcdt C!o Codtl                                B. PAOIECTITASKlhYOAKUNIT NUMBER EGSG      Idaho, Inc.
Idaho      Falls,       ID    83415                                                              !l PIN OA GRANT NUMSEA A6483 10, SPONSORING ORGANIZATIONNAME ANO MAILINGAQOAESS  Ilnttcdt 2 d COdtl                              'l1 ~, TYPE OF REPORT Division of Systems Integration Office of Nuclear Reactor Regulation                                                                Technical Evaluation Report U.S. Nuclear Regulatory Commission                                                                 0, PEAIGD cov BRED    Ilntlctrrt dtltcl ttashington,           DC    20555 12 SI.PPI chIENTARY NOTES IS, ABSTRACT I2'V nordt or!tar This    EG8G      Idaho, Inc. report reviews the licensee submittal requesting an amendment        to plant technical specifications regarding instrumentation that has been installed to meet the requirements of NUREG-0737.
14 DOCUMENT ANAI.YSIS     c. KEYWOAOSIOESCAIPTOAS                                                                                       'IS. AVAILABILITY STATEMENT IS.SECUAITYCLASSIFICATION ITnd dtttl O. IDENTIFIEASIOPcN ENDED TEAMS (Tnit rtoorrl 17 NUMBER OP PAGES IB! PAICE}}

Latest revision as of 09:58, 29 October 2019

Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept
ML17308A289
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 01/31/1987
From: Stoffel J
EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:
NRC
Shared Package
ML17219A564 List:
References
CON-FIN-D-6023, RTR-NUREG-0737, RTR-NUREG-737 EGG-NTA-7477, GL-83-37, TAC-59356, TAC-59357, NUDOCS 8703030696
Download: ML17308A289 (11)
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Text

EGG-NTA-7477 TECHNICAL EVALUATION REPORT REVIEW OF TECHNICAL SPECIFICATION CHANGES SUPPORTING NUREG-0737 ACCIDENT INSTRUMENTATION, ST. LUCIE PLANT, UNIT NOS. 1 AND 2 Docket Nos. 50-335 and 50-389 J. W. Stof f el Published January 1987 EG&G Idaho, Inc.

Idaho Falls, Idaho 83415, Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76I001570 FIN No. 06023

@~so 30 G9'5

ABSTRACT This EG&G Idaho, Inc., report reviews, the licensee submittal requesting an amendment to plant technical specifications regarding instrumentation that has been installed to meet the requirements of NUREG-0737.

Docket Nos. 50-335 and 50-389 TAC Nos. 59356 and 59357

FORENORD This report is supplied as part of a program for case work review of various nuclear power plants and issues. This work is being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of P~AR Licensing-B, by fG8G Idaho, Inc., NRR and I&E Support Branch.

The U.S. Nuclear Regulatory Commission funded this work under FIN No. 06023.

Docket Nos. 50-335 and 50-389 TAC Nos. 59356 and 59357

CONTENTS ABSTRACT .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

F OREMORO o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1.0 INTRODUCTION

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1

2.0 BACKGROUND

~ ~ ~ 2

3. 0 EVALUATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3

4.0 CONCLUSION

S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 5 .0 REFERENCES ..........................................;...... ~ .... 5

REVIEW OF TECHNICAL SPECIFICATION CHANGES SUPPORTING NUREG-0737 ACCIDENT INSTRUMENTATION ST. LUCIE PLANT UNIT NOS. 1 AND 2 1 ~ 0 INTRODUCTION 1

NUREG-0737, includes requirements for specific accident monitoring instrumentation. The licensee for the St. Lucie Plant, Unit Nos. 1 and 2, has identified the necessary instrumentation installed in these two units 2

to meet the requirements. In a submittal dated July 19, 1985, the licensee requested NRC approval of proposed licensee amendments to the units'echnical Specifications reflecting the added instrumentation and requirements of NUREG-0737. This report provides an evaluation of the proposed changes to the technical specifications for the two units.

The licensee's submittal identifies the affected sections of the technical specifications. These are: Tables 3.3-11 and 4.3-7 for Unit No. 1 and Tables 3.3-10 and 4.3-7 for Unit No. 2. Also, additional appropriate operability and action statements are included.

2.0 BACKGROUND

The accident monitoring instrumentation, Table 3.3-ll and the accident monitoring instrumentation surveillanc'e requirements, Table 4.3-7 of the St. Lucie 1 Technical Specifications do not presently cover all the installed accident monitoring instrumentation. The licensee has added incore thermocouples, containment sump water level (narrow and wide ranges), containment pressure and reactor vessel level monitoring system instrumentation to the plant.

The accident monitoring instrumentation, Table 3.3-lO and the accident monitoring instrumentation surveillance requirements, Table 4.3-7 of the St. Lucie 2 Technical Specifications do not presently cover all the installed accident monitoring instrumentation. The licensee had added reactor vessel level monitoring system instrumentation to the plant.

3.0 EVALUATION He have compared the proposed changes in the technical specifications with the requirements of NUREG-0737 and find that the licensees request for an amendment to the St. Lucie Plant, Unit Nos. l and 2 Technical Specification indicates that the changes are necessary and appropriate.

The addition of this currently installed and operational instrumentation to the technical specifications will provide a higher degree of control and operational readiness by requiring operability and monthly surveillance of accuracy.

4.0 CONCLUSION

S Based on our evaluation, we conclude the following with regard to the proposed changes to the plant technical specifications for St. Lucie Plant, Unit Nos. 1 and 2.

o The instrumentation proposed for addition to the technical specification tables is consistent with the requirements of NUREG-0737.

o The changes proposed by the licensee to the action statements and the surveillance requirements are adequate.

o The amendment involves no significant hazard considerations in that it is a change that constitutes an additional limitation, restriction or control not presently in the technical specifications.

5.0 REFERENCES

1. NUREG-0737, Clarification of TMI Action Plan Requirements, II.F.l, NRC, November 1980.
2. Letter, Florida Power and Light Co. (J. N. Williams Jr.) to NRC (H. L. Thompson), "Generic Letter 83-37, NUREG-0737 Technical Specifications," July 19, 1985, L-85-252.

NRC FORM SSS U.S. NUCLEAR REGULATORY COMMISSION I, AEPOAT NUMBER /AttiPntd oy TIDC, tdd Vol Ho,!I tncl 12 811 NAChl 1102, 2201, 2202 BIBLIOGRAPHIC DATA SHEET EGG-NTA-7477 SEE INSTRUCTIONS ON THE AFVEASE 2 TITLc AND SUSTIT' 2. LEAVE BLANK REVIEM OF TECHNICAL SPECIFICATION CHANGES SUPPORTING NUREG-0737 ACCIDENT INSTRUMENTATION, ST. LUG IE PLANT, t DATE AEPORT COMPLETED UNIT NOS. 1 AIID 2 MONTH YEAA 6 AI'THQAISi January 1987 J. W. Stoffel 6 DATE AEPORT ISSUED MON'TII January 1987 7 PEAF GAMING ORGANIZATIONNAME ANO MAILINGADDRESS llntlcdt C!o Codtl B. PAOIECTITASKlhYOAKUNIT NUMBER EGSG Idaho, Inc.

Idaho Falls, ID 83415 !l PIN OA GRANT NUMSEA A6483 10, SPONSORING ORGANIZATIONNAME ANO MAILINGAQOAESS Ilnttcdt 2 d COdtl 'l1 ~, TYPE OF REPORT Division of Systems Integration Office of Nuclear Reactor Regulation Technical Evaluation Report U.S. Nuclear Regulatory Commission 0, PEAIGD cov BRED Ilntlctrrt dtltcl ttashington, DC 20555 12 SI.PPI chIENTARY NOTES IS, ABSTRACT I2'V nordt or!tar This EG8G Idaho, Inc. report reviews the licensee submittal requesting an amendment to plant technical specifications regarding instrumentation that has been installed to meet the requirements of NUREG-0737.

14 DOCUMENT ANAI.YSIS c. KEYWOAOSIOESCAIPTOAS 'IS. AVAILABILITY STATEMENT IS.SECUAITYCLASSIFICATION ITnd dtttl O. IDENTIFIEASIOPcN ENDED TEAMS (Tnit rtoorrl 17 NUMBER OP PAGES IB! PAICE

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