ML17221A324

Proposed Changes to Tech Spec 3.4.10 Re RCS - Structural Integrity ASME Code Class 1,2 & 3 Components & Section 4.0 Re Surveillance Requirements

ML17221A324
Person / Time
Site:	Saint Lucie
Issue date:	08/17/1987
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17221A325	List: ML17221A324 ML17308A425
References
NUDOCS 8708240048
Download: ML17221A324 (58)

Text

ATTACHMENT I Marked-up TechnicaI Specification Pages 3/4 0-2 B3/4 0-2 3/4 4-26 8 27 3/4 4-28 to 36 3/4 4-37&38 3/4 4-39 to 52 3/4 4-53 8 54 3/4 4-55 B3/4 4-I2 B3/4 4-l3 8P08240048 8708017>>>

I OR ADOCH, 0500>0>R~I P MSD I/009/3 l'-'Ir Ir<<X~1 i~<<i APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with: '.A maximum allowable extension not to exceed 25K of the test interval, and b.A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

4.0.4 Entry

into an OPERATIONAL MOOE or other specified applicability condi-tion'shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

The provisions of Specification 4.0.4 are not applicable to the performance of surveillance activities associated with fire protection technical specifica-tions 4.3.3.7.1.

4.3.3.7.2, 4.7.11.1, 4.7.11.2 and 4.7.12 until the completion of the initial surveillance interva?associated with each specification.

R.Q 5 Surveillance Requirements for inservice inspectlonTand testing]of ASME Code Class 1, 2 and 3 components shall be applicable as follows: ae b.Inservice inspection of ASME Code Class 1, 2 and 3 componentsPand, inservice testing ASME Code Class 1, 2 and 3 pumps and valvesgshall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection pand testincgactivities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ST.LUCIE-UNIT 1~3/4 0-2 Amendment No.gl, 40 h I APPLICABILITY SURVEILLANCE RE UIREMENTS Continued 4.0e5 (Continued)

ASME Boiler and Pressure Vessel'Code and applicable Addenda terminology for inservice inspectionCand testin activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually Required frequencies for performing inservice inspection Pand testing5 activities At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days c.The provisions of Specification 4.0s2 are applicable to the above required frequencies for par farming inservice inspection[and testing/activities.

d.Performance of the above inservice inspection/and testing)activities shall be in addition to other specified Surveillance Requirements.

e.Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

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APPLI CAB ILITY BASES.4.0.1 This'specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MOOES or other condition's for which the Limiting Conditions for Operation are applicable.

Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL HOOES or other conditions are provided.in the individual Surveillance Requirements.

~Mt 4.0.2 The provisions of this specification provide allowable tolerances for performing s<:rveillance activities beyond those specified in the nominal surveillance interval.These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.

The tolerance values, taken either individually or consecutively over 3.test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not signifi-cantly degraded beyond that obtained from the nominal specified interval..Under the terms of this specification, for example, during initial plant startup or following extended plant outages, the applicable surveillance activities must be performed within the stated surveillance interval prior to pl'acing or returning the system or equipment into OPERABLE status.4.0.5 (S~e Wa4ad)ST.LUCIE-UNIT 1 B 3/4 0-2 4.0.3 The provisions of this specification set forth the crit ria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.

Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.Nothing in this provision is to be cons.rued as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveil-lance Requirements.

4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL HOOE or other applicable condition.

The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirement of the Limiting Condition for Operation.

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This specification ensures that inservice inspection of ASME Code Class 1,,2'nd;;3.componentsf.and inservice testing of ASME Code Class 1, 2 and 3 pumps and valvesjwill be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the fgequencies for performing the inservice inspection Pand testing activitiesgrequired by Section XI of theASME Boiler and Pressure Vessel Code and applicable Addenda.This clarification is provided to ensure consistency in surveillance intervals thoughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection Pand testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.'/For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other spe'cified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to normal operation.

And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

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1 4 h C.t'P$j REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL INTEGRITY MME ccoK cL RSB 2.,2and 8 QQNPciNKHi5 LIMITING CONDITION fOR OPERATION ARK cede CL~i,2.0.od3 3.4.10.1 The structural integrity of components (except steam generator tubes)~noa4s shall be maintained In GCCOrhaat.g Z ig~ii<<ff it i.i.ii.i.Rl.l ii iiiiiiiiii:

iiiii~ACTION: Cr ee aN-e i<<i Ioaer4 each Iriee r Pope.J SURVEILLANCE RE UIREMENTS Ha o<<M iona 5<<r<<69orae Remi reoiedla o@ei ieoa+osereoe<<.eO

+'IT<<<<if'iea ioo<<0eo.4.4.10.1P g sAutdown: ST.LUCIE-UNIT 1 3/4 4-26 Amendment No.69 o'~1'l 1 I4 4 w I b.C>>Mith the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural

~integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NOT considerations.

Mith the structural integrity of any ASMf Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 2004F.Nth the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from servic'e.d.The provisions of Specification 3.0.4 are not applicable.

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~~~i'i'REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS Continued ,~I I f ST.LUCIE-UNIT 1 3/4 4-27 DE,LF YP TABLE 4.4-6 INSERVICE INSPECTION PROGRAN-SAFETY CLASS 1 COHPONENTS SECTION 1.REACTOR VESSEL AND CLOSURE HEAD C Ho.1.2 E4 EQ Categoar r~b Examination Area(b)Longitudinal and Cir-cumferential shell welds in core region.Longitudinal a ir-cumferential welds shell (other than those of Category A and C).Examination

~Hethad b Volumetric Volumetric Tentative Inspection During 10-year Inter val See Note (a)and Remarks See Note (a)and Remarks Rsna~ks The required examinations will be performed at or near the end of the 10-year inspection interval or when the internals are removed for other reasons.Hechanized Ultrasonic ex-amination will be used.(1)The required amount of weld lengths will'c examined at or near the end of the 10-year inspection interval or when the internals are removed for other reasons.(2)Closure head meridional welds and dome (circumferential) welds which are not accessible inside the head cooling shroud assembly will be excluded from the examination.

(3)A partial examination of the RPV lower head we]ds can be done from the ID with mechanized techniques.

Approximately 25K of meridional welds.b roximately 75K of circumferential wol wer head to shell).c)lOOX of dome welds (circumferen-tial).(4)IDOL manual examination o lower head welds will be performed externa during baseline.

E Pl Ho.C lo3~Cate or (h)Exaotaattoo Area(h)Vessel-to-flange and head-to-'flange cir-cumferential welds.Examination

~kethod h Volumetric Tentative Inspection Ouring 10-year Interval See Note (a)and Remarks TABLE 4.4-6{Cont'd)SECTION 1.REACTOR VESSEL AND CLOSURE HEAO Reaarka Both of these welds are available for ex-amination during normal refueling operations.

D>>I~aR IO 1.4 ary nozzle-to-vessel welds d nozzle-to-vessel inside ra sed sections.Vol'umetr ic See Note (a)and Remarks The required examinations will be performed by mechanized techniques as follows: Whenever the internals are removed, one (1)outlet and one (1)inlet nozzle during the first two thirds of this interval (not to exceed 2 each).Balance per remark (2)below.(2)In case the internals are not removed, two (2)outlet nozzles for the first two thirds of the interval and four (4)inlet nozzles near or at the end of the interval.Vessel penetrations, in-cluding control rod drive penetrations and control rod housing pressure boundary welds.Volumetric See Rema (3)The CRlN tubes and in-core instrumentation tubes are welded to the upper head with a partial penetration weld.The assemblies.corttain an integrally welded thermal sleeve Volumetric examination is not feasible by currently available techniques.

These enetrations are included in Category E-2.llousi ressure boundary welds are in-accessible e to head cooling shroud as so())bly.'Heets exclusion crit a of paragraph IS-121(a)ref: FSAR 15..le6 E-2 Vessel penetrations, in-Visual eluding control rod drive penetrations and control, rod housing pressure See Note (a) r~At~0>L L'f v-TABLE 4.4-6 (Cont'd)SECTION 1.REACTOR VESSEL AND CLOSURE HEAD A (el em Ho.-I 1.7~Cate or (b)Examioattoo Area(b)F Primary nozzles to safe end welds.Examination

~metbod b Visual.surface and volumetric.

Tentative Inspection During 10-year Inter val See Remarks Remarks There are no welds in this category.1.8 1.9 G-1 G-1 osure studs and nuts.Ligaments be en threaded stud ho Visual.surface and volumetric Volumetric See Note (a)and Remarks See Note (a)and Remarks Surface exam1nation does not apply to nuts.The ligaments w111 be examined whenever the Reactor Vessel Flange Meld of Itea 1.3 is examined.~e I 1.10 G-1 Closure washers, bushings.Visua See Note (a)There are no bushings.Rab 1.12 G-2 Pressure retaining bolting.'Integrally t(elded vessel supports.Visual Volumetric See Remarks See R s There is no bolting less than 2-inches in diameter accessible for examination.

Nozzle-type pad supports are installed and are examined under Item 1.4, Category D.1.13 Closure head cladding Visual and surface or volumetric See Note (a)and R s At least six (6)patches (each 36 sq.in.)of the RPV Closure Head will be examined-sual and surface.1.14 Vessel cladd1ng.Visual See Note (a)and Remarks At leas x patches (each 36 sq.in.)of the vessel will examined by remote techniques, 1.15 Interior surfaces and Visual 1nternals and integrally welded internal supports.See Note (a)and Remarks (1)The examination 11 be done by remote visual techniques.

(2)Mhenever refueling occurs an ernals are removed, a remote visual exam ion will be performed'on tl)e vessel inter

~~~e'Q<i~I'i I n R No.b te or 2.1 B 2.2 b Examination Area b ongitudinal and C r rential Melds Nozzle-to-Vesse and nozzle-to-vessel inside radius section Examination

~Method h Visual and Volumetric Volumetric Tentative Inspection Ouring lO-year Inter val See Note (a)See Note (a)TABLE 4.4-6 (Cont'd)SECTION 2.PRESSURIZER Reeeeke 2e3 2.4 a 2e5 2e6 E-1 E-2 G-1 G-2 Neater Connections lleater Connections Pressure Retaining Bolting Pressure retaining Bolting Visual and Surface Visual Visual and Volumetric Visual remarks See Note (a)See Ranarks See Note fa)and Renarks (1)Hect the exclusion criteria of IS-121 (c)and are examined under category K-2.Bolting 2-inch in diameter and greater exist.The bolting less t-nches in diameter wi1l be visually inspected, ei-place under tension or when they are disasse I Pl Ho.Examination

~he\had h Tentative Inspection During 10-year Interval TABLE 4.4-6 (Cont'd)SECTION 2.PRESSURIZER Remarks 2.7 2.8 I-2 Integrally welded vessel supports.Ves cladding.Visual and Volumetric Visual See Note (a)See Note (a)and Remarks At least one (1)patch (36 sp.in.)below the primary manway will be examined.SECTION 3.STEAN GEHEAATORS Ll Iaa 3.1 Longitudinal and c1'r-cumferential welds, including tube sheet-to-head welds on the primary side.V s and volumet See Note (a)and Remarks Hechanized examination, no visual, will be performed on three (3)each staywell circum-ferential welds due to limited access and undue radiat1on exposure to personnel.

3.2 3.3 3.4 3m5 3.6 G-1 G-2 Primary nozzle-to-huad wolds and nozzle-to-head inside radi-used sections.Primary nozzle-to-safe end welds.Pressure reta1ning bolt1ng.'ressure retaining bolting.-Integrally welded vessel supports.Volume tr ic Visual, surface and volumetric.

Visual and volumetric Visual Visual and volumetric See Hot a See Remarks plicable.See Remar ks Hot Applicable.

See Note (a)and Remarks The bolting less that 2-1nches iameter will be visually examined in place tension.or whenever the bolting connect is disassembled.

See Note (a)

~~ea'a I~I QEiP Tp TABLE 4.4-6,(Cont'd)

SECTION 3.STEAM GEttERATORS Ho.3.7 Cate or b-2 Examination Area(b)Vessel cladding Examination

~Method h Visual Tentative Inspection During 10-year Interval See Hote (a)and Remarks Remarks Radiation levels permitting, the examinations will be conducted.

4.1 Vessel..and valve Safe ends-t imary pipe welds and safe e in branch piping welds.SECTION 4.PIPIttG PRESSURE BOUNDARY Visual.sur-See Hote (a)and Remarks face and volumetric The pressurizer and pump nozzle-to-safe end welds are.included in this item.4.2 4.3 G-1 G-2 Pressure retaining bolting.Pressure retaining bolting.ual and vol ric Visual See Remarks There is no bolting 2-inches and larger in the piping system.See Hote (a)and Remat ks All bolting below 2-inches in diameter will be visually examined, either in-place or whenever the bolted connection is disassembled.

4.4 Circumferential

and longitudinal pipe welds.Visual and volumetric See Hote An augmented inspection of the following welds shall be performed:

(1)During first inspection interval-100'S of the longitudinal welds from the reactor vessel to approximately the outboard surfaces of the reactor cavity shall be amined at approximately 3 I/3'year in als in each of the two hot legs of the un (2)During subse nt inspection intervals-provided no defe are found during the first inspection int 1 exceeding the allowable limits provide Section XI of tlute ASttE Code, IDOL of the longitudin-al welds in either one of the two legs shall be examined during each inspect interval following the first.

~a'sa t~QELlsTfTABLE 4.4-6 (Cont'd)SECTION 4.PIPING PRESSURE BOUNOARY I g~mo.~tate or (k)4.5'-1 Examination Area(b)Branch pipe connection welds, exceeding 4-fn.nominal p1pe s1ze.Examination

~teethed b Visual and volumetric Tenta tf ve Inspect f on Ouring 10-year Interval See Note (a)Remarks 4.6 4.7 4.8 Da e J-1 J-2 cket Melds.Branch pfp nnection welds,.4-1n.

n al pipe size and sma Circumferential and longitudinal pipe welds and branch pipe connection welds.Visual and surface Visual and surface Visual See Note (a)See Hote (a)See Note (a)4.9 4.10 Integrally welded supports.K-2 Piping supports and hangers.Visual and volumetr1c Visual See Notes (a)and (d)See No a)SECTION 5.PUMP PRESSURE BOUNDARY AND PUMP EELS 5.1 Pump casing welds.Visual and volumetric

.See Note (a)and Remarks The only feasible method known to date to lumetrfcally examine these pump casing welds fs fography.If radfography is possible, or an ernate exam1nation method is developed, the examin on vill be performed at the fre-quency 1ndfca See Note (c).5.2 5.3 L-2 Pump casings.'isual Hozzle-to-safe end welds;Visual and volumetric See Note (a)and Renarks See Note (a)and Remarks Radiation levels perm 1ng, the exam1natfon will be performed wheneve e puntps are disassembled.

This item fs considered under Section Iten 4.1.

rr~,~~~'L:)Qadi=-YF TABLE 4.4-6 (Cont'd)SECTION 5.PUHP PRESSURE DOUHOARY AND PUMP FLYMNEELS No.~Cate er (b)Exaeteattea Area(b)Examination

~bathed b Tentative Inspection Ouring 10-year Interval keearke 5.4 5.5 5.6 5.7 5.8 G-2 K-2 Pressure retain1ng bolting.Pressure'retaining bolting.Integrally welded supports.Supports and hangers.Flywheel V1sual and volumetric Vis Visual and volumetric Visual Volumetric (1)(2)Surface (2).Sec Note (a)and Remarks See Remarks See Note (a)See No a)See Remarks (1)Bolting 2-inches and larger in diameter will be examined either in-place under tension, or when the bolt1ng.is removed or when the bolting connection is disassembled.

(2)There is no feasible method of examining the flange ligaments of the pumps volumetrically at the present t1me.See note (c).'here is no bolting below 2-inches in diameter.(1)An in-place ultrasonic volumetric ex-.amination of the areas of higher stress concentration at the bore and key way at approximately 3 year intervals, during the refueling or ma1ntenance shutdown incid1ng with the inservice inspection sch e, 4 (2)A surface nlnation of all exposed sur-faces and comp ultrasonic volumetric examination at app mately 10 year intervals, during the p t shutdown coinciding with the inserv nspection schedule.Removal of the flywhe is not required to perform these examinatio Qr ig T P, TABLE 4.4-6 (Cont'd)SECTION 6.VALVE PRESSURE DOUNOARY Ho.~Cate or b feamtoatioo Area(bj Examination

~tietbod b Tentative Inspection During 10-year Interval Reearta 6.1 6.2 H-2 Valve body welds Valve bodies Visual and volumetric Visual Remarks Not Applicable.

See Note (a)and Remarks Examinations will be conducted provided valves can be disassembed without undue radiation exposure to personnel.

6e3 6o4 6e5 6.6 G-1 G-2 Valve-to fe end welds.Pressure retaining bolting.Pressure retaining bolting.Integrally welded supports Visual and volumetric Visual and volwaetrlc sual Visual and volumetric See Remarks See Remarks See Note (a)and Remarks e Remarks Not Applicable.

There are no valves with bolting 2-inches and larger in diameter.All bolting below'2-inches in diameter will be visually examined, either in-place if the bolting connection is not disassembled during the inspection interval, or whenever the bolting connection is disassembled.

There are no valves with integrally welded supports.6.7 K-2 Support and hangers Visual See Note Note a: (b): (c): (d): e extent an frequency of t e examinations will be at least as much as the gui nes'.of Table IS-251 of Section XI 1971 Edition through Minter 1972 Addenda.The item number, category, examination area and examination method are listed in Table IS-of Section XI of the ASHE Boiler and Pressure Vessel Code.a Present ultrasonic techniques may not.be aiaenable to examination of pump/valve castings.Mhere accossibility to welds prohibits their examination, each weld shall be examined on a case by case bas

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a'0I II)f.SCa ,g 1 I"h'g,f, 4'L ACTQR CQQLANT SYSTEM SURVEI NCE RE UIREMENTS Continued The service Inspection Program shall be reviewed every 5 years assure that the techniques.

and procedures being uti-lized a urrent and applicable.

The results of these reviews shall be re rted in Special Reports to the Coamission pursuant to Specificat n 6.9.2 within 90 days of completion.

b.Ins ections Foll Re airs or Re lacements The structural ntegr ty o a ety ass components s a be demonstrated after completion of al repairs and/or replacements by veri-fying the repairs and/or placements meet the requirements of Section XI of the ASIDE Boi and Pressure Vessel Code, 1971 Edition.and Addenda through nter 1972.Nhen repairs and/or replacements are made which inv ve new strength welds on com-ponents greater than 2 inch diame , the new welds shall receive a surface and 100 percent v umetric examination and meet applicable code requirements.

Mh repairs and/or replace-.ments are made which involve new strengt'ds on components 2 inch diameter or smaller, the new welds s 11 receive a surface examination and meet applicable code quirements.

c.S stem Pressure Tests The structural integrity o afety ass components s all be demonstrated by perform system pressure tests per the requirements of Section XI of ASME Boiler and Pressure Vessel Code, 1971 Editioh, and Adden through Minter 1972.ST.LUCIE-UNIT 1 3/4 4-38 TABLE 4.4-7 INSERVICE INSPECTION PROGRAN-SAFETY CLASS 2 COHPOHEHTS SECTION Cl.PRESSURE VESSELS No.or.Examination Area Examination Hethod Tentative Inspection Ourirg 10-year Interval Remarks Cl.l C-A cumferential she d head welds Volumetric

'he comoonents in this category are included in the overall total of required examinations for ISC-261(a) and ISC-261(b}

components.

A cumulative 25K of the overall total of re-quired examinations will be completed during.the interval.See Note (a).(1)The areas of examination include shell and head circumferential welds~hich are gross structural discontinuities (see Subparagraph NE-3213.2 of Section Ill-Huclear Power Plant Components Code)in vessels exceeding 4-inch nominal pipe size.(2)See Note (f)(3)See Note (b).(4)The steam generator stakmell d welds will not be examined due to their configuration, limited access and radiation exposure to personnel.

Clm2 C-B Hozzle-to-vessel welds Volumetric The components in this category are included in the overall total of required examinations for ISC-261(a) and ISC-261(b) components.

A cumulative 25K of the overall total hf re-quired examinations will be completed during the interval.See Note (a).(1 e Note (b).(2)See Note I 1

.I I~~e u~I d Item C1.3 e or C-C Examination Area Integrally-welded upports Examination Hethod Surface@~LET~SECTION Cl.PRESSURE VESSELS Tentative Inspection During 10-year Interval The components in this category are 1ncluded in the overall total of requ1red examinations for ISC-261(a) and ISC-261(b) components.

A cumulative 25K of the overall total of re-quired examinations w1ll be completed during the interval.See Note (a).Remarks (l)See Note (b).~(2)See Note (f).d Ch Cl.4 C-0 Pressure-retain1ng bolting isual and e r surface or vo etric The components in th1s category are included 1n the overall total of required examinations-for ISC-26l(a) and ISC-261(b) components.

A cumulative 25K of tne overall total of required examinations will Le completed during the terval;See Note'(a).(1)Bolting exceeding 1-inch in diameter will be examined 1n-place in the bolted-up cond1tion or whenever the bolted connection 1s disasseiabled.

Flange ligaments between threaded stud holes will be included whenever the connection is disasseaible, and feasible methods of examination have been developed.

(2)A required examieatioo toesists of the following: (a)Visual examinat1ons will include 100K of the bolts, studs, and nuts in the bolted joint.(b)Surface examinat1ons w111 be performed on 10K of the bolting 1n each joint, but not less than 2 bolts or studs per joint whenever the connection is disassembled.

(3)See ote (b).(4)See Note I I Ho.Cate or C1.5 Examination Area ISC-261(c) components Examination Hethod Visual TABLE 4.4-7 Cont'd SECTION Cl.PRESSURE VESSELS Tentative Inspection Ouring 10-year Interval Cumulative lOOX of the required examinations (see Note (c)).Remarks (1)Examinations will be conducted in accordance with the procedures of IS-211 for evidence of component leakage or structural distress with the system under pressure as specified in ISC-520(b), when'the system is undergoing either a periodic system performance test or a system pressure test.Ral 4h C1.6 ISC-261(d)

Components Visual C lative 100$of the required eexam ions (see Note.(c)).

SECT I C2.P IP IHG (2)For insulated components, the examinations will be conducted without the removal of the insulation.

(3)Components in letdown portion of CVCS system{from pressure control valves to volume control tank, which normally operates at less than 275 psig 200 F)will be visually examined in accordance with ISC-261(c).

(1)See Hate (g).C2.1 C-F C2.1.1 Circumferehtial Volumetric butt welds The'components in is category are included in the o all total of required examinations r ISC-261{a) components.

A cumulative 25K of the overal total of required"examinations wi~be completed during the interval.See Note (a).(1)The areas of examination include circumferential butt welds at structural discontinuities in piping exceeding 4-inch nominal pipe size and circumferential butt welds in piping exceeding 4-inch nominal pipe sjze within 3 pipe-diameters of the centerline of rigid pipe anchors, or anchors at the penetration of the primary con-ainment, or at rigidly anchored components.

(2).See e{b).(3)See Note (h er~Ho.ate or C2.1 C-G C2.1.2 Examination Area Circumferential t welds Examination Hethod Volumetric TABLE 4.4-7 Cont'd SECTIOH C2.PIP IHG Tentative Inspection Ouring 10-year Interval One-half of the components in this category will be selected and included in the overall total of required ex-aminations for ISC-261(b) components.

A cumulative 25K of the overall total of required examinations will be completed during the interval.See Hoto (a).Remarks The areas of examination include circumferential butt welds at structural discontinuities in piping exceeding 4-inch nominal pipe size and circumferential butt welds in piping exceeding 4-inch nominal pipe size within 3 pipe-diameters of the centerline of rigid pipe anchors, or anchors at the penetration of the primary con-tainment, or at rigidly anchored components.

(2)A representative sampling among the total number of welds will be selected for examination.

C2.2 C-F C2.2.1 Longitudinal weld)oints in fittings Volumetric (3)(4)The components in this categor e in-(1)eluded in the overall total of requ examinations for ISC-261(a) components.

A cumulative 25K of the overall required examinations will be'completed during (2)the interval.See Hote (a).(3)'See Hote (b).See Hote (i).The areas of examination include the longitudinal weld Joints in pipe fittings exceeding 4-inch nominal pipe size.Se ote (b).See Hote (>.

I n Pl C2.2 C2.2.2 C-G itudinal weld Joint ittings e or Examination Area Examination Hethod Volumetric TABLE 4.4-7 Cont'd SECTIOH C2.PIP IHG Tentative Inspection Ouring 10-year Interval See Remarks.QFLv"-TP Rsnarks Hot applicable for Hote (i)systems.C0.3 C2.3.1 C-F Branch pipe-to-pip weld joints lumetric See Remarks.Hot applicable for Xote (h)systems.4b I Crk C2.3.2 C-G Branch pipe-to-pipe Volumetric weld joints e-half of the components in this cate will be selected and included in the ove total of required ex-aminations for l(b)components.

A cumulative 25lof the all total of required examinations wil completed during the interval.See Note (a).(1)The areas of examination include branch con-nection weld joints exceeding 4-inch nominal pipe size.(2)A representative sampling among the total number of welds will be selected for examination.

e Hote (b).(4)See Hote n Ho.Cate or C2e4 C-Examination Area Integrally-welded support-to-pipe ds Examinat1on Hethod Suface SECTION C2-PIP IHG Tentative Inspection During 10-year Interval The components in th1s category are in-(1)eluded in the overall total of required examina'tions for ISC-261(a) and ISC-261(b)

(2)components.

A cumulat1ve 25K of the over-all total of required examinations will be completed during the interval.See Note (a).Remarks See Note (b).See Notes (h)and (1).C2.5 C-D Pressure-retaining V 1 and bolt1ng.eithe r-face or volumetric The components 1n this category are 1n-(1)eluded in the overall total of required examinations for ISC-26l(a) and ISC-261(b) omponotns.

A cumulative 25K of the over-a otal of required exam1nations will be comple during the interval.See Note (a).Bolting exceed1ng 1-inch in diameter will be examined in-place 1n the bolted-up condition or whenever the bolted connection is dis-assembled.

Flange ligaments between threaded stud holes will be included whenever the con-nection is disassembled, and feasible exam tion methods have been developed.

(2)A required examinat1on consists of the following: (a)Visual examinations will include 100K of the bolts, studs, and nuts in the.bolted point.(b)Surface examinations will be performed on of the bolting 1n each]oint.but not less than 2 bolts or studs per joint whenever I connection is disassembled.

6)t4)See Hote (b.See Notes (h)and (

~~F n m Ho.or C2.6 C-E Exam4ation Examination Area Hethod or ts and'isual hange SECTION C2.P I PING Tentative Inspection Ouring 10-year Interval The components in this category are included (1)in the overall total of required examinations for ISC-261(a) and ISC-261(b) components.

A-cumulative 25K of the overall total of required examinatfons will be comploted during the inter-val.See Notes (a)and (e).Reearks See Note (b).C2.7--ISC-261 (c)System Visual Cumua 1MX of the required examinations.

(1)See Note (c.(2)Examinations will be conducted in accord-ance with the procedure of IS-211 for evfdence of component leakage or structural distress with the system under pressure as specified in ISC-520(b), when the system is undergoing either a periodic system per-,formance test or a system pressure test.insulated components, the examinatio will ducted wfthout the removal of the insulat QFLl.VF n m No.or Examination Area Examination Method TABLE 4.4-7 Cont'd SECTION C2.PIPING Tentative Inspection Ouring 10-year Interval Remarks (3)Components in letdown portion of CVCS system (from pressure control valves to volume control tank.which normally operates at less than 275 psig 200 F)will be visually examined in accordance with ISC-261(c).

C2.8 fSC-261(d) systems Visdal Cumulat X of the required examinations se e (c)).(1)See Hot (g).Ral~mam a C3 I C-F A'.3.1.1 C.3.1.2 C-G SECTION C3.PUMPS Pump casing welds Volumetric See Remarks.Pump casing welds Volumetric

-See Reamrks.Hot app for Note ())pumps.Hot applicable for Note ())p C3.3 C-9 C n Pl Ho.Cate or C3.2 C-TABLE 4.4-7 Cont'd SECTIOH C3.PUMPS Examination Area Examination Method Tentative Inspection Ouring 10-year Interval Visual Pump Casing-The components in this category are in-cluded 1n the overall total of required examinations for ISC-261(a) and ISC-261(b) components.

A cumulativo 25K of the over-all total of required exam1nations will be completed during th'nterval.Sae Note (a).Pressure-retaining-1sual and The components in this category are in-bolting e r surface eluded in tha overall total of required or vo atric examinations for ISC-261(a) and ISC-26l(b) components.

A cumulativa 25K of tha over-all total of required examinations will be i lated during the interval.Sae Hote (a).Renarks (1)See Note (b).(2)See Note (j).(1)Bolting exceeding 1-inch in diameter will be examined in-place in the bolted-up condition or whenever the bolted connection is dis-, assembled.

Flange.ligaments between threaded stud holes will be included whenever the con-nect1on is disassembled, and feasible examina-tion methods have been developed.

(2)A required examination consists of the following: (a)Visual examinations will 1nclude 100K of the bolts, studs.and nuts 1n the bolted joint.(b)Surface examinations w111 be performed on 10">>of the bolting in each joint, but not less than 2 bolts or studs per joint whenever the connection is disassembled.

('3)See ta (b).(4)See Note (

'a s ,~a r I Fl Ho.Cate or Examination Area Examination Method TABLE 4.4-7 Cont'd SECTION C3.PUMPS Tentative Inspection During 10-year Interval 0>h6 l~=Remarks C3.4 C-E Supports and gers Visual The components in this category are in-(l)See Note-(b).eluded 1n tho overall total of required examinat1ons for ISC-261(a) and ISC-261(b)

(2)See Note ()).components.

A cumulative 25%of the over-all total of required examinat1ons will be completed during the interval.See Notes (a)and (e).C3.5 C3.6 Q~ISC-261(c) components Visual Integrally

~elded Surface supports See Renarks Hot applicable for Note 0)pumps.Cumulativ X of the required exam1nations (l)Exam1nations will be conducted in accordance See Note (c).with the procedures of IS-2ll for evidence of component leakage or structural distress with the system under pressure as specified in ISC-520(b).

when the system is undergo1ng either a periodic system performance test or a system pressure test.(2)insulated components, the examinations will be ucted without the retrroval of the insulat o r hr't n C No.r Examination Area Examination Method TABLE 4.4-7 Cont'd SECTION C3.PUMPS Tentative Inspection Ouring 10-year Interval Qi,L'E YP Remarks (3)Components in letdown portion of CVCS system (from pressure control valves to volume control tank, which normally operates at less than 275 psig 200 F)will be visually examined in accordance with ISC-261(c).

1 C3.7 ISC-261(d)'omponents Vis u'al Cumulative 50K o (see Note (c)).equired examinations (1)See Note (g).4h k~C4.1 C-F C4.1.1 SECTION C4.VALVES Valve body welds Volumetric See Remarks Hot applicable tes{h)and (i)systems.C4.1.2 C-G Valve body welds Volumetric See Reamrks Hot applicable for Hotes (h)and (i)syst~

C P4 No.te o C4.2 C-H Examination Area Valve Bodies Examination Method Visual SECTION C4.VALVES Tentative Inspection During 10-year Interval The components in this category are included in the overall total of required examinations for ISC-261(a) and ISC-261(b).components.

A cumulative 25%of the overall total of required examinations will be completed during Qe interval.Sec Note (a).Remarks (1)See Hote (b).(2)See Hotes (h)and (i).C4.3 C-D Pressure-retain-ing bolting Vis and either face or volumetric The components in this category aro included in the overall total of required examinations for ISC-261(a) and ISC-261(b) components.

A c ative 25%of the overall total of re-quire aminations will be completed during the interv See Note (a).(1)Bolting exceeding 1-inch in diameter will be examined in-place in the bolted-up con-dition or whenever the bolted connection is disassembled.

Flange ligaments between threaded stud holes will be included when-ever the connection is disassembled.

See Hote (d).(2)A required examination consists of the following: (a)Visual examinations will include 1004 of the bolts, studs, and nuts in the bolted)oint.)Surface examinations will be performed n le of the bolting in each)oint, b ot less than 2 bolts or studs per joint ever the connection is disassembl (3)See Note (b).(4)See Hotes (h)and (i).

M SECTION C4.VALVES ate or C-E Examination Examination Area Hethod Supports and-Visual ers Integrally-welded Surface supports Tentative Inspection Ouring 10-year Interval The components in this category are included in the overall total of required examinations for ISC-261(a) and ISC-261(b) components.

A cumulative 251, of the overall total of required examinations will be completed during the interval.See Notes (a)and (e).See Remarks Remarks (1)See Hote (b).Hot applicable for Hotes (h)and (i)systems.ISC-261(c) components Visual Cumulativ'f of the required examinations.

See Note (c).(1)Examinations will be conducted in accordance with the procedures of IS-211 for evidence of component leakage or structural distress with the system under pressure as specified in ISC-520(b), when the system is undergoin either a periodic system performance test or a system pressure test.For insulated components, the examinations 1 be conducted without the removal of the insu on.(3)Components in own portion of CVCS system (from pressure contr valves to volume con-trol tank, which normally rates at less than 2?5 psig 200 F)will be lly ex-amined in accordance with ISC-261 c

~~p f TABLE 4.4-7 Cont'd SECTION C4.VALVES Or 1>=(>No.ate or Examination Area C4.7--ISC>>261(d) onents Examination Hethod Visual Tentative Inspection During 10-year Interval Remarks Cumulative 50K of the required examinations (1)See Note (g).(see note (c)).ote a: (b): (c): d e f 9 h 3)t east part o t e overa to a of required exam ions will be performed by the expiration of 1/3, 2/3, and the end of the 10-year interval.The total number of required examinations is dependent upon her or not a system consists of multiple streams which perform the same (or redundant) functions as stated in ISC-242(a);

the distr on of individual components to be examined will be determined in accordance with ISC-242(b).(c).and (d).At least 25K of the required examinations will be completed by the expirat of 1/3 of the 10-year inspection interval.with not more than 66-2/3X of the required examinations completed by the expiration of f the 10-'year inspection interval.Present ultrasonic techniques and procedures may not be amenable to examination of castings.)there accessibility to welds prohibits their examination, each weld will be evaluated on ase by case basis.The regenerative, letdown, and shutdown heat exchangers, and the steam generators (secondary e)are to be examined.Components and systems'n which the contained fluid will be verified by periodic sampling and tes Portions of the shutdown c'ooling systems are to be examined.Portions of the main steam and feedwater systems are to be examined.Low pressure safety injection pmxps are to be examined.

ACTOR COOLANT SYSTEM SAFE CLASS.3 COMPONENTS QRi6<<LIMITING C ITION FOR OPERATION 3.4.10.3 The stru ural integrity of components identified in Section 3.2.2 of the FSAR as afety Class 3 components shall be maintained at a level consistent wit the acceptance criteria in Specification 4.4.10.3.APPLICABILITY:

ALL MODES.ACTION: Mith the structural integrity of a of the above components not con-forming to the above requirements.

re ore the structural integrity of the component to within its limit or is ate the affected components from service.The provisions of Specific ion 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.10.3 The following inspection program shall be per rmed: a.Inservice Ins ections The structural integrity o the Safety ass components s all be demonstrated at least o e per 40 months during periods of normal reactor operation or ring system performance testing by verifying via visual insp tions, as outlined by the inspection program shown in Table 4.'4-that there is no evidence of unanticipated component leakag structural distress.or corrosion.

1 ST.LUCIE-UNIT 1 3/4 4-53 Amendment No.6g

~g P yp" V*A 4 ACTOR COOLANT SYSTEM 0eg.7r SVRVEILL CE RE VIREMENTS Continued b.S stem essure Tests The structural integrity of the Safety ass co onents shall be demonstrated at least once per 10 years by per ing system pressure tests at the following test pressures:

1.For closed syst , at least 110 percent of the design pressure, 2.For open storage tanks, least the nominal hydrostatic pressure developed with the nks filled to design capa--city.and c~3.Open-ended portions of systems may exempted from pres-sure testing.Pi Han er Ins ections The structural integrit of the Safety C ass 3 components sha 1 be demonstrated at least e per 40 months by verifying via visual inspections that the s orts and hangers for piping and components over 4 inches in ter show no evidence of inadequate support, unintended restrain or structural distress.ST.LUCIE-UNIT 1 3/4 4-54

'.~~Tr TABLE 4.4-8 INSERVICE INSPECTION PROGRAM-SAFETY CLASS 3 COMPONENTS Class 3 piping greater than 4 inches and components with pipe connections greater than 4 inches w ssure tested and visually examined near or at the end of the 10-year inspection interval.In components will be visually examined during periods of normal operations or during system performanc once during each 1/3 of the year 10-year inspection interval.2.Open-ended portions of systems will not be pressure V~~I,'t J/f REACTOR COOLANT SYSTEM BASES for piping, pumps and valves.Below this temperature, the system pressure must be limited to a maximum of 20" of the system's hydrostatic test pressure of 3125 psia.The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4-5 to assure compliance with the requirements ef Appendix H to 10 CFR Part 50.The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fati-gue analysis performed in accordance with the ASME Code requirements.

3/4.4.10 STRUCTURAL INTEGRITY~s~ŽS SWATS i~O~pq+&AC 6>)~6-lb'equired inspection program)for the Reactor Coolant System componen ensure that the structural integrity of these components will be maintain at an acceptable level throughout the life of the plant.To the extent licable, the inspection program for the Reactor Coolant System components

's in compliance with Section XI of the ASME Boiler and Pressure Vessel Cod"Inservice Inspection of Nuclear Reactor Coolant Systems", 1971 Edition, nd Addenda through Minter 1972.All areas scheduled for lumetric examination have been pre-service mapped using equipment, techniq and procedur es anticipated for use during post-operation examinations.

To assure that consideration is given to the use of new or improved i ection equipment, techniques and procedures, the Inservice Inspection rogram will be periodically reviewed on a 5 year basis.The use of conventional nondestructive, dir t visual and remote visual test techniques can be applied to the inspec on of most reactor coolant loop components except the reactor.vessel.Th reactor vessel requires special consideration because of the radiation els and the requirement for remote underwater accessibility.

The techniques anticipated for inservice inspection include'al inspections, ultrasonic, radiographic, magnetic particle and dye pen trant testing of selected parts.ST.LUCIE-UNIT 1 B 3/4 4-12 REACTOR COOLANT SYSTEM BASES nondestructive testing for repairs on components greater than 2 inches di eter gives a high degree of confidence in the integrity of the system, d will detect any significant defects in and near the new welds.Repairs components 2 inches in diameter or smaller receive a surface examinatio hich assures a similar standard of integrity.

In each case, the leak t t will ensure leak tightness during normal operation.

For normal opening and re sing,'the structural integrity of the Reactor Coolant System is unchang Therefore, satisfactory performance of a system leak test at 2235 psia f owing each opening and subsequent reclosing is acceptable demonstration o he system's structural inte-rity.These leak tests will be conducted'in the.pressure-temperature limitations for Inservice Leak and Hydrostatic esting and Figure 3.4-2.The Safety Class 2 and 3 components will be pre ure tested at least once toward the end of each inspection interval years).The Safety Class 2 components having a design temperature abov 400'.F will be pressure tested at not less than 125 percent of the system sign pressure while those components having a design temperature of 4'F and below will be pt essure tested at 110 percent of design pressure.T Safety Class 3 components will be pressure tested at the levels indica in Specificatinn 4.4.10.3b.

1 T.LUCIE-UNIT 1 I B 3/4 4-13 Amendment No.80 LCE-srs br<sos for Dj<<.<.<Q-st<<vcTu<<o<.

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porsoon5 yo I gpR 9'>SC.S"s<.)3<'.<.I(i)(o<nycoencs opW ceno@<aoo4<<h sqs3e<a ooo<e des<<<net Yo pro<(de access 4 pe<<nA<<<sere<co<n<pehlo'os

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~<~4 (Ee4Ob Xl Of%he.4~~SC<leC CA6 9(eSSuCt 385Sdl~q W1 I Sd,k o,~awd@deeda A<net<<)<nhe<lyp ATTACHMENT 2 EVALUATION As required by 10 CFR 50.55a(g), FPL updated the lnservice Inspection (ISI)and Inservice Testing (IST)programs, together with proposed Technical Specification amendments for St.Lucie Unit I, to the requirements of the 1974 Edition through Summer 1975 Addenda of the ASME Boiler and Pressure Code.The ISI program was submitted to the NRC in July and September of 1977.On December 20, 1977, the NRC granted relief, on an interim basis, pending completion of a detailed review of the programs.Final NRC approval is still pending and, since 1977, FPL has had to comply with both the existing Technical Specifications and the proposed ISI and IST programs, whichever, is more restrictive.

The proposed amendments which were submitted in 1977, removed reference to a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Code for inservice inspections and, instead, proposed a new Specification

4.0.5 addressing

surveillance requirements for inservice inspection and testing.The subject revised amendment proposes to maintain a similar format as was originally submitted.

This format is consistent with both the Combustion Engineering

-Standard Technical Specifications (CE-STS)and the St.Lucie Unit 2 Technical Specifications.

A change is proposed to add a new specification in Secton 4.0 (Surveillance Requirements) of the Technical Specifications.

The change will include Surveillance Requirements for inservice inspection of ASME Code Class I, 2 and 3 components.

Specification 4.0.5 has been added to include this requirement.

This addition reflects wording provided in the CE-STS and provides consistency between the Unit I and Unit 2 Technical Specifications.

The purpose of the change to Technical Specification 3 4.,10, Structural lntegrity-ASME Code Class I, 2 and 3 Components, is to incorporate three (3)separate Limiting Conditions for Operation (LCO)into one (I)LCO.That is, the change incorporates the Structural Integrity-ASME Code Class I, 2 and 3 Component individual LCOs into one (I)LCO.The format reflects the format/wording contained in both the CE-STS and the St.Lucie Unit 2 Technical Specifications.

The changes are as follows: Limitin Condition for 0 ration (LCO)-The LCO has been written to encompass ME Code Class I, 2 and 3 Components and is written consistent with the CE-STS and the St.Lucie Unit 2 Technical Specifications.

A licabilit-The applicability has been changed to reflect ALL MODES since ME ode Class I, 2 and 3 Components have been incorporated into one Specification.

This is consistent with the CE-STS and St.Lucie Unit 2 Technical Specifications.

MSD I/009/4 W'W'~~I~W Wt~~I W W~'W a It W I~w W ll~W W I~I Action-The Action Statement has been changed to reflect three (3)separate statements for Structural Integrity of ASME Code Class I, 2 and 3 Components.

This is consistent with the CE-STS and St.Lucie Unit 2 Technical Specifications.

Surveillance Re uirernents

-With the addition of Specification 4.0.5, as discussed above, the Surveillance Requirements have been changed to reflect the ISI requirements as outlined in Specification 4.0.5.Reference to the Surveillance Requirements, as outlined in Section XI of the ASME Boiler and Pressure Vessel Code, l97l Edition and Addenda through Winter 72, have been deleted.Inservice Inspection requirements are already outlined in the appropriate Edition and Addenda of'Section XI, as referenced in the new Specification 4.0.5.Therefore, restatement of these requirements in the Technical Specifications is not necessary.

The Inservice Inspection Program Tables for ASME Code Class I, 2 and 3 Components have been deleted since they are maintained in the St.Lucie Unit I ISI Program.These changes to Technical Specification 3.4.IO reflect the format in the CE-STS and the St.Lucie Unit 2 Technical Specifications.

MSD I/009/5

~e<r r I H e~II e e

~~ATTACHMENT 3 NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission's regulations, IO CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (I)involve a significant increase in the probability or consequences of an accident previously evaluated; or (2)create the possibility of a new or different kind of accident from any accident previously evaluated or (3)involve a significant reduction in a margin of safety.Each standard is discussed as follows: (I)Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

The change to Technical Specification Section 4.0, Surveillance Requirements, is a change to achieve consistency between the St.Lucie Unit I Technical Specifications and the St.Lucie Unit 2 Technical Specifications.

The intent of the Specifications has not been changed.The change incorporates the format/wording of the Combustion Engineering

-Standard Technical Specifications and the St.Lucie Unit 2 Technical Specifications.

The change to Technical Specification 3.4.IO--Structural Integrity-ASME Code Class I, 2 and 3 Components is proposed to achieve consistency between the St.Lucie Unit I Technical Specifications and St.Lucie Unit 2 Technical Specifications.

Three (3)separate Limiting Conditions for Operation have been incorporated into one (I)LCO.Reference to lnservice Inspection Tables and Surveillance Requirements of a specific Edition and Addenda of Section Xl of the ASME Boiler and Pressure Vessel Code have been deleted.Reference to Specification 4.0.5 has been added to provide Surveillance Requirements for lnservice Inspection of ASME Code Class I, 2 and 3 Components in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by IO CFR 50.55a(g).

Also, the St.Lucie Unit I ISI Program contains the requirements as provided in the appropriate Edition and Addenda of Section Xl of the Code.Therefore, these changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

(2)Use of the modified specification would not create the possibility'of a new or different kind of accident from any accident previously evaluated.

The change to Technical Specification Section 4.0, Surveillance Requirements, is a change to achieve consistency between the St.Lucie Unit I Technical Specifications and the St.Lucie Unit 2 Technical Specifications.

The intent of the Specifications has not been changed.The change, incorporates the format/wording of the Combustion Engineering

-Standard Technical Specifications and the St.Lucie Unit 2 Technical Specifications.

MSD I/009/6 h P II>pl bI n 0

~~0 The change to Technical Specification 3.4.IO-Structural Integrity-ASME Code Class I, 2 and 3 Components is proposed to achieve consistency between the St.Lucie Unit I Technical Specifications and St.Lucie Unit 2 Technical Specifications.

Three (3)separate Limiting Conditions for Operation have been incorporated into one (I)LCO.Reference to Inservice Inspection Tables and Surveillance Requirements of a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Code have been deleted.Reference to Specification 4.0.5 has been added to provide Surveillance Requirements for Inservice Inspection of ASME Code Class I, 2 and 3 Components in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by IO CFR 50.55a(g).

Also, the St.Lucie Unit I ISI Program contains the requirements as provided in the appropriate Edition and Addenda of Section XI of the Code.Therefore, th'e possibility of a new or different kind of accident from any accident previously evaluated is not created.(3)Use of the modified specification would not involve a significant reduction in a margin of safety.The change to Technical Specification Section 4.0, Surveillance Requirements, is a change to achieve consistency between the St.Lucie Unit I Technical Specifications and the St.Lucie Unit 2 Technical Specifications.

The intent of the Specifications has not been changed.The change incorporates the format/wording of the Combustion Engineering

-Standard Technical Specifications and the St.Lucie Unit 2 Technical Specifications.

The change to Technical Specification 3.4.IO-Structural Integrity-ASME Code Class I, 2 and 3 Components is proposed to achieve consistency between the St.Lucie Unit I Technical Specifications and St.Lucie Unit 2 Technical Specifications.

Three (3)separate Limiting Conditions for Operation have been incorporated into one (I)LCO.Reference to Inservice Inspection Tables and Surveillance Requirements of a specific Edition and Addenda of Section XI of the ASME Boiler and Pressure Vessel Co'de have been deleted.Reference to Specification 4.0.5 has been added to provide Surveillance Requirements for Inservice Inspection of ASME Code Class I, 2 and 3 Components in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by IO CFR 50.55a(g).

Also, the St.Lucie Unit I ISI Program contains the requirements as provided in the appropriate Edition and Addenda of Section Xl of the Code.Therefore, use of the modified specification would not involve a significant reduction in the margin of safety.Based on the above, we have determined that the amendment request does not (I)involve a significant increase in the probability or consequences of an accident previously evaluated, (2)create the possibility of a new or different kind of accident from any accident previously evaluated, or (3)involve a significant reduction in a margin of safety;and therefore does not involve a significant hazards consideration.

MSD I/009/7 A'h O t J A 4 0 0 ll V l'