ML18088B305

Attachment C to L-77-291 Proposed Technical Specification Changes

ML18088B305
Person / Time
Site:	Saint Lucie
Issue date:	09/16/1977
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML18088B305 (17)

Text

C.

~ f ATTACHlIJlENT C TO L-77-293.

PROPOSED. TECHNICAL SPECIFE CATION CHANGES

APP.LICABILITY SURVEILLANCE RKgUIRBlENTS (Continued):

a A total'aximum combined. interval time. for any 3 consecutive sumeil1ance intervals not. ta- exceed: 3 25 timm tha specified

'urveillance. interval 4.0.3 Performance of- a Survei1lance Requirement mthin the speci'i.i'ime interva1 shall- constitute compliance with OPERABILITY reqmrements for a Limiting Condition for Operation and associat d ACYXQH st~Gments unless otherwise required by the specification..

4.Q.4 Entry. into. an OPERATIONAL YiOGE or other specified'pplicabHity condition'shall not be made unless the Surveillance Requirement(s) as'ther's'tise:

associated with the Limiting Condition for Operation have been perTormed within the stated. survei11ance interval or specified 4.0.5 SurveiLlance Requirements for in-service inspection and, testing of Class 1, 2 and, 3 components shall be applicable as follows:.

ASME'ode ae Xn-service inspe'ction of ASME Code Class 1,, 2 and. 3 components and in-service testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in'ccordance with Section ZX of the ASME Boiler and Pressure. Vessel Code and: applicable-. Addenda as required'y. 10 CPR 50, Section 50.55a(g), except where specific written relief has been. granted.,

by the Commissioxr purSuant to 10 CPR 50, Section 50.55a(g) (6).(i) Xn cases where during the process. of inspection and testing, certain re-quirements, are- found to be impractical', due to unforeseen. circumstances relief may be"'requested: at, that: time- and, satisfaction of these be deferred'. pending: NRC'. action upon that request

.'require-'ents'ay.

b Surveillance intervals: specified: in Section XX of the- ASME Boiler and'-

,Pressure Vessel Code and applicable. Addenda. for the in-sezvice inspection and. testing; activities: required by. the ASME Boiler and: Pressure.Vessel Code and applicable Addenda shall be applicable as follows in these-TechnicaL Specifications:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology Required frequencies for perform-for. in-service- inspection and ing in-service inspection and testin criteria testin activities Test Period:

l.. Refueling Shutdown A scheduled shutdown (with reactor .,

head off) with reactor maintained in

• MODE 6 for at least 72,hours.

2. Cold Shutdown A scheduled shutdown with reactor main tained in*MODE 5 for at least 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />

3. Operation 3 Months or less to Code.

• Table 1.1, Operational .Modes ST. LUCIE - UNIT l 3(4 0-2 9/16/77

APPLICABILITY SURYEILLANCE REgUIRB'lEHTS (Continued)'SME Boiler and. Pressure Vessel Code; Required frequencies for perform-and applicable Addenda terminology. for ing in-service inspection and.

-service inspection and testing criteria testin activities Monthly At least once per 3X days 3 Months At least once pe'r: 92-days YearIy or -Annually

• At least once per 366 days-Performance of the above. in-service inspection and testing activities shall be

in addition to other specified Surveillance Requirements. The provisions of Specification 4.0.2 are applicable to surveillance intervals- associated with in-service inspection and testing activities required by Section ZZ of the above ASME Boiler and Pressure Vessel'Code and applicable Addenda.

L v

ST. LUCIS - UNIT 1 3/4 0-3 9/l6/77

REACTOR COOLANT'YSTEN.

SKEEVCViKVES - SHtJTQOMN

. LIMITING CONDITION FOR. OPERATION 3.4.2' minimum of one. pressurizer code safety valve shall be OPERABLE.

with a. lift setting of 2500 PSIA + lX.

APPLICABILITY: NOGES 4- and 5.

ACTION.

with no pressurizer code safety valve OPERABLE,. inanediataly suspend all operations. involving. positive reactivity changes and.'lace- an OPERABLE-.

shutdown cooling loop. into. operation; SURVEILLANCE REgtJIRPitENTS'-

~*

~ j t'A 2'o: additionaL Surveill'ance; Recpxirementa other than those- recpu.reef by Specification 4.0 5-ST. LUCIE - UNIT l 3(4 4-2 9/16/77

REACTOR COOLANT SYSTEM'.4'.10'TRUCTURAL INTEGRITY" .

ASME CODE CLASS le 2'ND 3'OMPONENTS LIMITING'ONOITIONFOR'PERATION:

3.4.10.1 The structural integrity of ASMS Code Class 1 .2 and-.3,components--

(except Steam generator Tubes) shall be maintained in accordance with Specidica- ';

tion 4.4.10.1.

APPI ICABILITY: IDES 1', 2, 3 g 4 ACTION a Mitk the structural'ntegrity of any ASME Code Class.l com-ponent(s) not. conforming, to the above requirements, restore.

',,

~

the structural integrity of the affected component(s) to within'ts,limit or isolate the affected component(s) prior the Reactor Coolant: System temperature mora to'ncreasing~

above the minimum temperature required. by NDT considerati'ons than'0.'F

b. With. the structural integrity, of any. ASHE Code. CTass 2'om- .

ponent(s) not: conforming, to the;-above requirements,. restore

"

.the structural: integrity of'he affected component's) toi within", its; Timit. or isoIate the affected .component[d)'ninm to R~reasing; the: Reactor. Coo Tant. System teepe~z~abuV c' Mftk the. structural, integrity of any ASME Code CVass 3',com-not conforming. to. the above requirements.restore

.'he structuraI1'.

-'onent(s).

integrity of the affected! component to within

'ilats limit: or- isolate. the affected:. component from: service d' The provisions'f Specification- 3'.0.4 are not.applicable.

'

SURYEILLANCE RE UIREMENTS 4- >>-1'o additional Surveillance Requirements other than those

'required by Specification 4.0.5.

ST LUCZE UNIT 1 3/4 4-26 9/16/77

1 P, t

r I',

E p ~ ~ C

~ 4

~ PAGES 3/4 4-27'O '3/4 4-55. lNTENTlONALLYLEFT BLANC.

hi ~

~

'l ~

'V

~r ~

9/16/77

BlERGBlCY CORF CQQUifG SYSTEM'.S, REQUBB~ 'tTS (Continued)

'UR'lEILLNCK a

e At Yeast one per 18 umnths:, Bunny shuts:~n by-J' W~ ~

'er i7ying the~ each Signai) I autoaiitic valve ia. the Ao~s path ac~<z-

~O

.

0 ates to its carrec< position oa a Qfebj Xnjectioa Actuation Verifying: that each of the foklosting pumps stazh aut~a<feaI- P..

)J upoa receipt of a Safe"y Enaction, Aciuaiion'ignal..

a Hig1r-Pressure 5'a< tg Tnjec ice puma.

b .. Lm-Pressure Sa7e~y. ZnjeM~Qn- gts~ip 0 k

. $i'18/7 >

Np additiona1. Surveillance Requirements, other, than ariose:

required: bj

,Specifica&on. 4.0;5 g C

• I

~ ~

h I

Oa ~

~

~ ~

r~

ST. LUCIi - Ui(IT Y 9/16/77

COh tAiflitBITSYSTB45 SUV.~L ~~C=- R~qUIRm=~@AS. (Can~inued)

P 4

Yerlfying 'tha~.upon; a recircuZa~fae actva~iom, sfgnaT'

.. the cantainaren~. sump, isolation va'ives opea ar4 4ha4 a.

' . l ecircuTa~ion mech fZaw path via- arl GPE<.BKZ she 8o~-

cooling hea exchanger is. esta&liah cf,.'mick.

0

~ .: 2.; Verifying that each va)ve (manual power opera~ed ov .-.'.;

in the vGow path is poli ioned to take ""'utomatic),

suction signckl s Tl'Gs

. ~

... - -:,"-

die RMT On'L Cantairmenh Pressur --Hiah-Bigs

. ~ .(

'

b., A~ Zeal once per 28'months;. during sk<dawrr, by='

~ ~ 0 ~ <<& & ~'

0 ~

~ ~ o. e oe mo eoeo 0 0 ~ ~

Verifgi'ng thaC even; aut~itic; viva $ n ~ie rD'aw perh, ."

actuates;ta: im carr.'ect: posi>>iaa aa a. Caa~~irm~~C Pressura-Hfgk-High sfgna7.

2* Verifying tIra>> each: spray puap s~artc. au.~~ Pcs Iy. om- .-

a Contairwez~ Prmsur =Rigk-Hzgk sxgrraT

)

,'.c, Vms>> onc pm. 8 @care by perRm~ng am afv. or +~.aR .CTow 3/l8/>

.

" A>>

test through each spray h~~dee anC vervryiag, e ch spray r0~7e...

ws unobs~~c+wcE d'. '. No a@Xi.tion'a1 Suxveil.lance" Recgxixements othe+ than those x'ecpiired-by

.. 'Speci%.cation 4.0.5."

0 ST. LUCRE - U)ll7 l, 3(4 6-lo 9/16/77

4 l r ~ ~

~ ~ ~ ~ ~ ~

~ I ~ ~ I

~ ~

~ ~

~ ~ ~ I I

~ l ~

I ~

l s

~ ~ ~

~ ~ ~ ~

~ ~ ~ I ~ ~

~ ~ ~ ~ ~

CONTAINNEHT SYSTEMS SURVEILLANCE RE UIREt'tEHTS Continued 4.6.3.1.2. Each iso1ation va1ve specified in Table 3.6-2shalj be demonstrated OPERABLE during the COLD SHUTOOMN'r Rc.FUECIliG tiODE at least once per 18 months. by:verifying that oa a containment isolation test signaT; each isolation vaTve actuates to its isolation position

,3/lS 4.6.3'.X 3 No additional surveillance re~irements other than those required'.

y Specification 4 0.5 ST. LUCIE - UNIT 1 3/4 6-19 9/16/77

PLANT SYSTB/S

\

SUR>IEILLAHCE RE UIRBt HTS (Continued 3/18/77 b No adcLLtional surveillance. requirements other than those required by Specie.cation. 4;.Q' I'

~

0 h

ST. LUCIE - UilIT -l 9/16/77

PLANT SYSTEi~lS SStV-"B:HHGE-RE U IREHENTS Continued f

P f b.. At 7'east once per. 18'months during; shutdownby:

each automati'c: va1:ve.servicing:

W ~

verifying." that '. ','

safety'elated." equipment actuates-to its, correct position'on a Safety Injection Actuation Signal'

. 3jl 4

C>> No: a'dditiona3'urveillance. requirements other than those: recgxired,'- by:

Specificatiom 4.0.$ f f f

~ '

~

e

~, f, e

e 1

~ t ~ I

'a h}

ST. LUCIE - UNIT 1

-9/16/77' f

~ ~ 4~ ~

PLANT SYSTEM/S.

I

. SUR>IEILLAHCE RE UIRBl NTS'ontinued) 1 h ~ w

~ - ~ .i r " r.

At least once- per, T8'months, during- shutdown',, by verifying-. that-. =---

each'utomatic vaTve servicing safety re%ated equipment-.actuates, to its. correct position; on a. Safety Injection- Actuation Signal'..:

h 4

h

-',;3/18/77

, '.

c. No additiona1'uareillance hy Specification, 4'.0.5.

recpxixements other than. those'equireC: "-

r

~ '

t-t

'

,

I!

'

F

, ~

~' I A

ST.,LUCIE - UNIT.1 3/4 7-17'/16/77

APPt; EBB ILLY' 0

ps BASES 4-0-5 This specification ensures that. i an~+~s and, valves and'n-service inspection: o

-se~ce test

',and. 3- Components wiLL'e performeck in accordance with a periodically updated

'version of Section ZX of the ASME'oiler and Pressure Vessel Code and Addenda.

Ias required by: LO 'CZR"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 ojtbe+rectuencies .for perforanng.tbe in-service testing activities required 'by. Section xz. of 'the ASME. Boiler.and Pressure VesseL Code and applicable Addenda. This clarifi;ca-,

'tion is provided. to ensure consistency in surveiLLance-intervals throughout

these technical specifications and to remove any- ambiguities relative to

-the frequencies- for performing, the required: in-.service testing ac;tivities

~ I I v

r c

r ~

I I

I I P

~ '

t IP ~

I I ~ ~

1 I

~ ~

3r ~

F Ia ~

I 1

I F

- 8 3l4'-3 9/L6/77 I

ST. LUCIE UNIT 1

REACTOR COOLANT SYSTEM:

BASES Ar piping pumps and, valves Bein> this. ~~eratire, the system'r essure =

mush be limited; to a, maximum of.'0~ of the: system'a hjdroataHc test pl'essure oF 3T25 ps'he number of reactor vessel irradiation surveillance specimens and.

the frequencies for removing and testing these specimens are provided.-.in,

'able 4.4-5 to assure comp1iance anth the requirements ~f Appendix H to 10 CFR. Part 50 The l,imitations imposed on the piessurizer heatup and coo1down rates and spray eater temperature differential are provided to assure that the pressurizer is, operated vtithin the design criteria. assumed for the fati-gue analysis perforn'od. in. accordance <vith the AQlE Code requirements.

I 3/4.4.10 STRUCTUPAL [iHTEGRIiY The inspection programs. for the ASME Code Class 1, 2 and 3 components'nsure that the structural integrity of these components will be maintained: at. an acceptable level. throughout. the. life of the plant To the extent. applicable the inspection; program for these.. is:

'in complxance with; Section ZL of'he ASME Boiler and'ressurecomponents.

,

Vesse1 Code ST. LUCIE - UNIT 1 8 3/4 4-12 9/16/77

1 I I

'E'ACTOR'OOLANT SYSTEM

) 3'/4A'T CORE. O'ARREL"'~(OVEHEii7 I

r.

This specMicition:Vs pravSdedl te ensure ea're detec ion: oi. excessive

<

core BarrH movement M ft

'tected by using;- four excare neutron shauT'c5 occur,. Care barreT: rmvement v~A7 b~

detectors. m abta=.n; A~pTitude.

. I'rababiTity. Gistributfan. (APOI ant SpeciaT Analyst $ SA) BaseTine

'.

core bar rel'averent ATert L'eveT's and.'ction. L'ereTs at nominaT <NERVAL 0!lER. level:s or 20 50,. 80" and'l.00f of RATED THEPJNL PO'rlER viiTl be

determined'uringi the reactor startup test prague

~ -'

A'odi Ticatian-an anaTysis of the tldata obtained, the:- required'onitoring: program; and'by an:

may. be:

ex~vination of the. affected justified'by, parts during;- the plant: shutdown at the end; of the furs~ ueT cycTe T. LUCRE - VNET 1' 3/4'-13 9/16/77