ML17219A491

Proposed Tech Spec 3/4 7.10, Snubbers, Deleting Listings within Tech Specs

ML17219A491
Person / Time
Site:	Saint Lucie
Issue date:	04/01/1987
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17219A490	List: ML17219A489 ML17219A491
References
NUDOCS 8704060447
Download: ML17219A491 (22)

Text

PLANT SYSTEMS 3 4 7.10 SNUBBERS LIMITING CONDITION FOR OPERATION relde9 3.7.1:0 All snubbers .

b-shall be OPERABLE.

A APPLICABILITY: NOOES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems requir'ed OPERABLE in thole MODES).

ACTION:

~pQ vchaIl 4 With one or more<snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UIREtiENTS 4.7.10, Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.

1 I ' 'P

%A p =~

- a

a. Visual Ins ections

~l

-'efter f hb ~&I"bm Ht d-fourmonths-bdwWhm 14-moths-.gX-commencing-POWB-OPERAS-NN-h~~H and-s~H mehtd aN-rubbers

~ l-is-&d-i.n-Tebl.es-8-.7-2a-and& .7-2b- -I-f-d'w al~ 'yah~

inset me-visuaMinspecti on~the-second-inservi ce-visual inspection.

-s ha) 1-be-per formed-1-2-months-+-25K-from-the-da te-o f-'the-fi ra t-i ns pec ti on..

Otherw~ ~sequent-Visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual er Ins ection Period Ins ection Period*P.

0 18 months + 25K 1 12 months + 255

~

2 6 months + 255 3, 4 123 days + 255 5, 6, 7 62 days + 25K 8 or more 31 days + 25K The snubbers may be categorized into two groups: :Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.

• The inspection interval shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection may be lengthened one step the first time and two steps thereafter if no inoperable snubbers are found.

>The provisions of Specification 4.0.2 .are not applicable.

ST. LUCIE - UNIT 1 3/4 7-29 Amendment Ho. Rf, 44 87000b0447 870401 PDR ADOCK 05000335 P PDR

~ t PLANT SYSTEMS SURVEILLANCE RE UIRB!ENTS Continued

b. Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY and (2) .attachments to the foundation or supporting structure are secure. Snubbers which appear

'inoperable as a result oV visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval.

providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be gener'ically susceptible; and/or (2) the affected snubber is functionall'y tested in the as found condition and determined OPERABLE per Specifications 4.7.10.d or 4.7.10.e, as applicable.

c. Functional Tests At least once pq1<1$ months during shutdown, a representative 'sample~

(I OX of thIaasrhf6bers) l+etwd-in&elRes-3 .7-.2a-and-3-.7-2b)-shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.10.d or 4.7.10.e, an additional 10K of that type of snubber shall be functionally tested. Functional testiry~half@continue until no additional snubbers are found inoperable or all snbbhers ~ed d-3 ~b have been't&ted.

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. \

Snubber s identified m-Tables E

3-.7-2a-and 3-.7-2b-as "Especially Oifficult be used d 4 i h p jointly or separately rdt as the basi iMR ~l-3~@.

to Remove" or in "High Exposure Zones Ouring Shutdown" shall also be

<Munc&ana.l-l~~w~ecfrrniza.1~ub bars may-b -ar-tup-4eQ+Aog-the ffi -th-refueHcg-outre-for-Unit 1-.

5*Permanent or other exemptions. from the functional testing for individual snubbers in these categories may be granted by the Commission only if justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify 'snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

ST. LUCIE - UNIT 1 3/4 7-30 Amendment No. g'I, 44

/

9 w ~ ~ + ~ ~

PLANT SYSTEMS URVEILLANCE RE UIREMENTS Continued

~

• lr If any snubber selected for functional t'es'ting.'ither fails'to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect 'shall be functionally tested.

This testing requirement shall be independent of the requirements stated ,

above'for snubbers not oheting the functional test acceptance criteria.

d. H draulic Snubbers Functional Test Acce tance Criteria The hydraulic snubber functional test shall verify that:

l. Activation (restraizing,action). is.achievgd.within the specified range of velocity 'or acceleration fn 'both tension" and'compression.

2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

e. tlechanical Snubbers Functional Test Acce tance Criteria The mechanical snubber functid'nal test shall verify that:

1. The force that initiates free movement of the snubber rod in either tension or compression is ldss* than the specified ma2imum drag force.

2. Activation (restraining action) is achieved in. both tension and compression.

Snubberervice Life ' Nonitorin '

I ~

A record of the service life of each snubber, the date at which the designa'ted service life commences and the installation and maintenance records on which the designed servicp life is based shall be maintained as required by Specification 6.10.2+.

Concurrent-with the first inservice visual inspection and at least once per 18 qoII(hg thereafter,

' the, installation and maintenance records for each~fn4b er d-3~b shall be reviewed to verify that the indicated service .life 'has not been exceeded or will not be exceeded by more than 105 prior to the next scheduled snubber service life review. If the indicated service life will be exceeded by more than 105 prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the'ext scheduled service life review. The results of the reevaluation may be used to justify a change to the service life of the snubber. This reevaluation, replac'ement or reconditioning shall be i ndi ca ted i n the records.

ST. LUG IE - UNIT 1 3/4 7-31 Amendment No. g7, 44

TABLE 3.7-2a SAFETY RELATED HYDRAULIC SHUBBERS*

~

L LOCAT MARK SYSTVA .SNUBBL'R INSTALLED ~ i ACCESSIBLE"Olf .,llIGI1 RADIATIOH

~

ESPECIALl Y DXFFICIJ(T NO NO. ON LOCATION AND P3.1?VATION INACCESSIBLE ZONE*~ TO REMOVE (A or I) (Yes or No) (Yes or Ho)

~

001 SS-1 Steam Gen. 1A, L'vel. 62', Yes 002 SS-2 1A Steam Gen. lA, Evel. 62 Ho, Yes 1 I~ I team Can. 1A, Evel. 62

~

003 SS-3 1A MS, ra ~

Yes 004 S~-4 1A HS, Ste Gan. 1 A, Evel ~ I ~

Ho -Yes I

62'A, 005 SS-5 1A MS, Steam Evel ~ No Yes 006 SS-6 lA MS, Steam Gen. 62' 62'Evel.

I Hp Yes 007 SS-7 1A MS, Steam Gen. h>> Rv ~ I Nq Yes 008 SS-8 1A MS, Steam,Cen. Evel.

62'h, I No. Yea 009 SS-1 1B MS, Steam Gen. 1B, Elev. 62 I ~

Ho, Yes.

010 SS-2 1B MS, Steam Cen. lB, El.ev. I Ho Yes 011 SS-3 1B HS, Steam Gen. Elev. 62 62'B, I . No Yes LI 012 SS-4 1B HS, Steam Gen. 1B, Elev. Ho, Yes 013 SS-5 1B MS, Steam Gen. Elev.

57'S, 62'B, I lP No- <<Yes, 014 SS-6 1B Steam Gen. Elev.

62'B, I No. Yes.

015 SS-7 1B MS, Steam Gen. Elev.

62'g, I ~

o. Yes 0! 6 SS-8 1B MLS, Steam Gen. Elev.

62'B, I Ho. Yes 017 1A1 RC, RCP Motor 1 Elev. 57 62'l, I No No 018 1A2 RC, RCP Motor 1 Al, Elev. I Ho No 019 1B1 RC, RCP Motor 1 Elev.

57'l, I No No 020 1B2 RC, RCP Motor 1 Elev.

57'l, I Ho

I ~ 1 SAFETY REI.ATED HYDRAUI.IC SNUBBERS+ >>

1 C,!>1 v

~ > '

'I

~

I LOCAT MARK SYSTBI SHUBDElt IHSTALf ED ACCESSIBI.E OR HIGH RADIATION ESPECIALLY DIPPICUI',T ND. HO. OH I.OCATION .. AND I:I.I?Vh'I'ON IHACCESSIBI.E ZONE** ;TO or I) (Yes or No)

REMOVL'Yes (A or No) 033 649-319 MS> Reactor Bldg. A No  ;-.'o 034 MS 5> -5 Reactor Bldg. 82'lev.

A No.,  !'Ho 035 MS 1076- 64 MS>> M.S. Trestle, 82'lev.

62 A No* .'i No 036 MS '649-314  : MS> Reactor Bldg. Elev. 55 I Ho .. No 037 MS. 649-314 Reactor Bldg. Kiev. 82 I No '. 9: No 030 Ms 649-310 IIS > eactor Bldg. Elev. I Ho .jt No 039 .

MS 649-304A MS, Re or Bldg. 50'lev.

A No. i' Yes 040 MS 548-9 ~

MS> Reacto Bldg. 50 30'lev.

I Ho. '~( Yes 04l MS 548-9 MS, Reactor B 4'lev. Elev. 50 I No. Yes 042 BF 549-7 BP, Reactor Bldg. Lev.

-'0 40' I, Ho No 043 QP 549-7 BP Reactor Bldg. I Ho,'o

'". Ho 044 BF 549-8 BL', Reactor BLdg. ELev. 0 I  !,I Yes 047 BF 549-17 Reactor BLdg. L>Lev.

'o BF, 36 A .~w Yes 052 BF 549-17 BF, Reactor Bldg. L'lev. A No Ho 053 SI 968210 SI, Reactor Bldg. 36lev.

No  !! Ho 050 SI 969 1216 SI, Reactor Bldg. 18 16'lev.

A D@ Ho No 061 MS 549-11 Reactor Bldg. Elev. A -Tg No No 066 MS 549-11 SI> Reactor Bldg. 18'lev.

I Ho No 073 SI 972-6240 SI 973-240 SI, Reactor Bldg. 20'lev.

16 I No No 074 SI, Reactor Bldg. Elev. 18 A 0 No 076 SI 973-6224 SI> Reactor Bldg. ELev. 18 No Ho 077 SI 860 64 SI, RAB, Elev. A No -No 079 SI 868-163 SI> El.ev. 4'AB,

'A Ho No 080 Sl 860 410 SI, Kiev. 4'AB>

A Ho No 081 SI 676-67 SI> P.lev- 4'AB,

. A No No 002 SI 676 67 SI, Elev. 4'AB, 4 A No

'83 SI 676-105 SI> RAB, L'lev. A No N&o O

TABLI? 3 ~ 7-2a CONTINUED SAFETY RI?I.ATED IIYDRAULIC SNUBBERS*

l LOCATI MARK SYSTI21 SNUBBI'R IHSTALI.I?0 ACCESSIBLE OR llIGN RADIATIOH ESPECIALLY DIFFICULT HO. 0 OH LOCATION AHI) I!I.I?Vh'I'TOH INACCESSIBLE ZONE** TO REMOVE I (A or I) (Yes or No) (Yes or No) rr . 084 SI 676-l, SI, RAB, Elev. A No No 086 Sl 676 129 Kiev. 4'AB, A No No 087 :I c 7t -"48l Elev.

4'I, 24 A No No 1 lU Sl bio 247 Sf,, RAB, A Ho No 1 ll SI 676-2475A RAB, Elev.

30'I, A Ho Ho 112 SI 676 4505 SI, RAB, h,lev. 7 A Ho No

'14 SI 972-6240 SI, RAB, Elev. 4 A No Ho 091 SPS-417 , Pressurizer Spray, Reactor I Op~ l Bldg. Elev. ~rg No 090 SPS>>27 Spray, Reactor 50'ressurizer Bldg. Elev. 50'. Ho No 092 SPS-467 Pressurizer Spray, Reactor Bldg. Elev. 80 No 093 SPS-777 Pressurizer Spray, Reactor Bldg- Elev. 80' Ho

'l o l ~ ~ I I i ' ~ o

'~e- . i ~ ~ .

i ~

TABLE 3. 7-2a CONTINUL'D SAFETY RELATL'D HYDRAULIC SNUBBERS*

e~p NO'ARK LOCATIO NO.

)

. SYSTEM'NUBBER INSTAf.f.ED ON LOCATION AND ELEVATIOH INACCESSIBLE OR IIIGH RADIATION ZONE**

ESP I':CIALLY DIFF TO REMOVE II:UI T (A or I) (uAu + pr IIIII) (Yes lor No) 096 CC-1 865-9 C, Reactor Bldg, Elev. 25 'A !No No:

08ll CC-I 899-48 CC, ctor Bldg, L'lev. 80'CCESSIBLE25 I A ~

No No 089 CC-1852-6241 CC, Reacto dg, Elev. ".

A tNp No CC-1 7-1 Elev.

25'C, 01 RAB, .'

'No 2'0'C, No 102 MS-649-313 RAB, Elev. .A 'No No CC-21-1 26'C, I 04 RAB, Elev. :A .'No BF-549-7 Np RAB, Kiev.

20'C, 103 .A ;No No CC-23-2 RAB, Elev.

26'C, 105 ~ A ~7F No Ho CH-3-40 26'H, 106 ~

RAB, Elev. A ."No Nb CII-3-75 RAB,'l.ev. 23 34'H, I,07 A .No Ho 108 MS-649-313 MS, Reactor Bldg, Elev. I <Ho No 1 09 HS-649-313 MS-649-314 Reactor Bldg, Elev.

80'S, 80'S,

~ .I .'No Ho 097 Reactor Bldg, Elev. iNO No 099 MS-649-314 Reactor I 80'S, Bldg, Elev. 'No ql i~ I ~ a l ~c . 4)""L~g31 w ') +c lc peov6hM~rev+ekon-~aM~-,7-2e-Isaac-tude~tth-th~ext-htxens~mendmen~eques t;~

• ~ModMfno~nsIm-tl~c&umn-due-t~ltanges-1 n-high-rudra H on-areas-may-be-made-vt:thou t ~orWce~mendment.

p rov td~d-tlra~revIM>~T<b~7-2a-ts-I nc 1~dud~ lth-th~ex t-bl cense-Amendment reques t.

TABLE 3.7-2b SAFETY RELATED MECI{ANICAL SNUBBERS*

L LOCA'O. MARK SNUBBER INSTAf LED ACCESSIBLE OR NIGH RADIATION ESPECIALf Y DIFFICUf.T NO OH LOCATION AND EI.L'VATlOH INACCESSIBLE ZONE** TO REMQVE (A or I). (Yes or No) (Yes or No) 021 RC 005-3 RC, Reactor Elev. 68 A NO HO 022 RC 005-34B RC, Reactor Bldg, Elev. 68'8'0 A NO HO 023 ftC 005-36 RC, Reactor Bldg, Elev. A NO 'HO 025 RC 005-128 RC, Reactor Bldg, Elev. A NO NO 026 RC 005-l.2B Reactor Bldg, Elev. 80'0'0 A NO ;HO 024 RC 005-1 2A RC> Reactor BWg, Elev. A HO HO 028 RC 005-55C RC, Re>a r Bldg, Elev. 80'0'0'0'ldg, A NO HO 027 ltC 005-55B RC, Reacto ldg, Elev. A NO HO 029 ftC 005-62A RC, Reactor Bldg~Eleve 33'YST&f h HO NO 030 RC 005-89 RC, Reactor Bldg, Elev. A HO ~

HO/

031 RC 005-90 RC, Reactor Bldg, E1%e~ A NO HO )

032 RC 005>>98 RCo Reactor Bldg, Elev. 0 A' NO HO 045 BF 549-11 BP Reactor Bldg+ Elev. HO HO 046 BP 549-11 BP, Reactor Bldg. Kiev. 50'0'0'Or I HO

'O 048 BP 661-407 BF, Reactor Bldg. Elev. I NO HO;

)

049 BP 6610407 BP, Reactor Bldg. Elev, Q~ HO NO )

050 BP 661-416 BP Reactor Bldg. F.lev. NO HO 051 BP 66l-416 BP) Reactor Bldg+ Elev. HO NO 054 SI 968-565 SI, Reactor Bldg. L'lev. A HO NO 055 SI 989 1205 Reactor Bldg. Elev. 50'0'5'0'8'0'8'8 'A NO .NO 056 SI 968-1207 SI, Reactor Bldg, Elev. A 0 HO 057 SI 969-1190 SI, Reactor Bldg, Elcv ~ I HO HO 059 SI 969-6193 SI, Reactor Bldg, Elev. A NO. HO 060 SI 969 6195 SI, Reactor Bldg, Elev. A HO NO 062 SI 969-6201 SI, lteactor Bldg, L'lev. A NO HO 063 SI 696-6217 SI, Reactor Bldg, Elev. 18'8'8 h NO NO 064 SI-696-6217 SI, Reactor Bldg, P.lev. A NO HO 065 S I -970-1 21 0 SI ~ Reactor Bldg, Elev. I HO

TAIILI! 3 ~ 7-2b ~CONTINUED SAFETY RRLATliU MECIIANICAL SNUBBERS*

I LOCAT I0 HARK SYSThH SNUBBL'IL fNSTAf.LED ACCESSIBLE OR ffIGH RADIATION ESPECIhf f Y DIFFICULT HO f0. ON I.OCATIOH hND I? f.EVh'I'ION INACCESSIBLE ZONE*~ TO REHOVE (A or I) or No) (Yes or No) 067 SI 970-125 SI, Reactor Bldg, Elev. A NO NO 060 SI 971-6 eac to r Bldg, Elev.

20'I, I NO HO 069 SI 971-1229 Rea t~r Bldg, Elev.

20'I, I HO NO 070 SI 971-6229 Reactor ff'hing Elev.

20'I, I HO NO El~

59'Yes I 20'I, 071, SI 971-6236 Reactor Bldg 20'I, NO HO 072 SI 972-1243 Reactor Bldg, Kiev. 25 A NO NO 075 SI 973-621.9 SI, Reactor Bldg, Elev. I NO HO RAB, L'lev.

36'I, 078 Sj 868 111 Ogf NO NO SI 676-1 27 Elev.

4'I~

095 RAB, A NO NO 113 SI 971;6236 RAB, Elev.

4'I, A 0 ~ HO CS-832-118 Reactor Elev.

4'S, 094 Bldg, A NO YES

'A 125'S, 085 CS-878 115 Reactor Bldg, Kiev. 1 8 Ho YES 098 CC-1899-2208 CC, Reactor Bldg, Elev. 59'C, A NO HO 100 CC-1865-2207 Reactor Bldg, Elev. A HQ

TAULE 3. 7-Zb .JliTIHUkO SAFE l'Y IIkNLATLO HkCHAH ICAL SNUOOERS* t PL LOC OH NRK SYSTEH SNUBBER INSTALLED ACCf SSIDLE 'OR HIGH RADIATION ESPECIALLY DII.FICULT ON, LOCATION AND 1I.EYA'i'ION

'O.

HO. INACCESSIBLE ZONE*~ TO RB10VE Yes or No Yes or N~o 115 RC164-ll RC RCG Elev. 'C NU I 116 I 62-11 RCB Elev. I HO HO 117 RC- 21A RC RCD Elev. I NO NO LA 110 RC-1-1 RC RCO flev. I HO HO 119 RC162-11 RC RCO Elev. I HO HO I

120 RC-1-192A RC RCD flev. 36'5'1'9'5'9'7'3'5'1'0' I HO HO 121 RC-5-475 R RCG Elev.

n 122 CH-129-99 CH CO Elev. I HO HO Pl HO NO 123 RC-217-5 RC RC Elev, I NO NO 124 CH-65-54C CH RAD l.ev. I NO HO 125 CH-142-9 CH RCB Ele~'H I NO HO 126 CH143-30C RCO Elev. 1 I NO HO 127 .,RC-215-9A RC RCO flev. I HO HO 128 HSI-22-3A HS RCD Elev. I HO HU 129 RC-1-124C RC RCO Elev. I 130 HSI-20-3A NO tg HS RCD Elev. I NU GJ 131 HSI-16-3h HS RCO Elev.

73'7'9'8'7'0'2'2'2 I NO NU 132 CH-125-35O CH RCD Elev. I NO I

133 HSI-14-3A HS RCD flev, I HU CO 134 CH-129-339 CH RCG Elev. I NO. N0 135 RC-220-105 RC RCB El ev. NO 136 l37 RC-217-5 CH 129-339 RC RCO CH RCD flev.

Elev.

75l il HO NO HO 130 RC 114-129

~I NO HO RC RCB Elev. I HO NO 139 RC 221-)62 RC RCD Elev.

67'7'1'2'O NO NO 140 CII-107-38A Cll RCD flev. 32'8'8'4'7'4'I I NO NO 141 CH-143-26C CH RCG Elev. I HO CL NO B

IEI 142 CII-141-74 CH RCD Elev. 'I NO s

143 D-2-Hl D RCB Elev. 3 I HO HO 144 RC 128-99 RC RCO El ev. I NO NO O 145 CII-143-34C Cll RCG Elev. I NO NO 146 RC-1-25C RC RCB Elev; I HO 0 147 CH-141-36=C CH RCB El ev. I HO 0

I TABLE 3. 7-Z~bCOHT INUEOJ noM SAI'ETY RLLATEO HLCIIANlCAL'-SHUDDERS>> s

~

L f

~ LOCA NO.

H IMARI'.

NO.

SYSTEH SNUBBER IHSTALLEO ON~ LOCATION AHD pt,pJ/p'('T~Q ACCESSIBLE iNAccEssioLE rAor i)

OR ZONE*"

T TYes or No

'U IIIGH RADIATIOH SPECIALLY DIFflCUI'T ltft1UYE (Yes or No 148 C-1-124A RC ltCD Elev. 17'S I NU NO 149 t>250 HP RCB Elev. 34'm I HO NO 196 Msll-7A Stream Trestle Elev. 38 A NO HO 197 HPR-201-1 6 HP RCG Elev. I 0 HO I

35'P 198 HPR 200-20 RCI3 L'lev. NO NO 199 8-2l.-311 Elev. 35'-RAG A HO NO 200 8-21-3110 Elev. 36'-RAB NO NO 201 8-21-3240 Elev. 35'-RAB HO 0 202 CC>>1 899-2200 Elev. 38'C-RCB I HO NO

?

• Snulslmr~ny-~ddm}-to~mwmove~m-ss&ety-reed:-ed-sys terna-without-prior-I icense-Amendmen~oMah1~~b ptovblad~cWM~i~~<~~7-2P-is-included-wf th-the-next-I icense-Amendment-request lrrov+ded-elise-a-revia-ion-t~aMe-3i-7-2-b-is-included-wi;th-the-next-deeense-Amendment-request

PL."t!T SYSTEHS BASES 3/4.?.7 CONTROL ROOYi EHERGENCY V"NTI'ATION SYST=!~ (Continued for operations personnel during and following al 1 credible accident condi-tions. The OPERABILITY of this system in conjunction with con rol room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or i.s equivalent.

This limitation is consist nt with the requirements of General Oesign Criteria 10 of Appendix "A"., 10 CFR 50.

i 3/4.7.8 ECCS AREA YtNTILATION SYSTEH The OPERABILITY of th ECCS area ventilation system ensures that radio-active materials leaking from the FCCS equippaent following a LOCA are filtered prior to reach'.ng the environment. ~. = operation of this system and the resultant effect on offsite dosage calculations;.as assumed in the accident analyses.

3/4.7.9 SEALEO SO"RCE CCHTAllINATiOfl The 1 imitations on sealed source removabl=- contamination ensure that the total body or ind'.vidual or gan irradiation does not exceed allovable limi.s in the event oi'ngestion Gr inhalation of the probable leakage rom the source materiai. The limitations on emovable contamination for sources reo.iring

'ieak testing, includ! rg alpha emit~e: s, is based on 10 CFR 70.39(c) limits for plutonium. guantities o. interest -.o this specification which are exempt from the leakage tes.ing are cons's-ent with the criteria of 10 CFR Parts 30.11-20 and 70.19. Leakage =rom sources excluded from the requirements of this specification is not likely to represent more than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.

3!4.7.10 ShUBBE,.S

~ekg ~e)a. ed All<snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained Curing and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are ".hose installed on

.nonsarety-related systems and then only if their failure or failure of the i system oui'hich they are installed would have no adverse effect on any safety-rel a ted sys tern.

The visual inspec"ion frequency is based upon maintaining a constant level of snubber protec .ion 0 sys ems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined ' the number or inope: able snubbet s found during an inspection. Inspections performed

1 0

ADMINISTRATIVE CONTROLS

g. Records of training and qualification for current members of the unit staff.

h. Rec6rds of in-service inspections performed pursuant to these Technical Specifications.

i. Records of guality Assurance activities required by the gA Manual .

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the FRG and the CNRB.

sa~ehq relapse

1. Records of the service lives of all<snubbers -Rsted-in-'Fa~

M-.7 2a-an~-.7-2b-including the date at which the service life conmences and associated installation and maintenance records.

m. Records of secondary water sampling and water quality.

n. Annual Radiological Environmental Operating Reports and records af.

analyses transmitted to the licensee which are used to prepare the Annual Radiological Environmental Monitoring Report.

o. Meteorological data, summarized and reported in a format consistent with the recommendation of Regulatory Guides 1.21 and 1.23.

p. Records of audits performed under the requirements of Specifications 6.5.2.8 and 6.8.4.

1 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

ST. LUCIE - UNIT 1 6-21 Amendment No. gg,$ 9,

ATTACHMENT 2 EVALUATION/DETERMINATIONOF NO SIGNIFICANT HAZARDS CONSIDERATION Back round In May l984, the NRC issued Generic Letter 84-I3 (Technical Specification for Snubbers) which reassessed the inclusion of snubber listings within the Technical Specifications. It was concluded in the Generic Letter that such listings are not necessary provided the snubber Technical Specification is modified to specify which snubbers are required to be OPERABLE. The Limiting Condition for Operation (LCO), surveillance requirements, and recordkeeping requirements will be maintained within the Technical Specifications. The snubber listings, when deleted from the Technical Specifications, will be maintained per controlled documents. Changes in snubber quantities, type, or locations would be a change to the facility and would, therefore, be subject to the provisions of 10 CFR Part 50.59.

Discussion This proposed change to the Technical Specifications is being processed to delete snubber Tables 3.7-2a, "Safety Related Hydraulic Snubbers" and 3.7-2b, "Safety Related Mechanical Snubbers," from the Technical Specifications. This change closely follows NRC guidance (GL 84-I3) for implementation. However, we have tailored the recommended LCO wording as described in the following discussion.

Generic Letter 84-l3 recommended the following LCO wording:

All snubbers shall be OPERABLE, the only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.

Our proposed Technical Specification would simply state: "All safety related snubbers shall be OPERABLE." All snubbers currently listed in the Technical Specification tables are safety related. Additionally, St. Lucie Unit I and Unit 2 Technical Specifications already contain the statement as written in the second sentence of the NRC suggested LCO. This statement, concerning snubber failures which may impact safety related systems, is currently contained in both Unit I and 2 Technical Specification Bases.

In addition to deleting the snubber tables from the Technical Specifications, the following changes are also proposed:

(A) Tables 3.7-2a and 3.7-2b: All references to Tables 3.7-2a and 3.7-2b have been deleted since these tables have been removed.

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(B) First lnservice Visual lns ection: The first inservice visual inspection of snubbers at St. Lucie Unit I has been performed and reference to this inspection is not required since this one time Surveillance Requirement has been completed.

(C)~Sj RI d: T various locations (prior to the word "snubber") in order to maintain consistency with the LCO.

(D) Footnote: The footnote concerning the waiving of mechanical snubber functional test requirements until startup following the fifth refueling outage has been deleted since the fifth refueling outage has been comp I eted.

(E) Snubber Service Life Monitorin: Records of the service life of each snubber shall be maintained as required by Administrative Controls Section 6.I0.2.I (Amendment 69 to Facility Operating License DPR-67 changed the alphabetical location of this requirement from 6. I0.2.m to

6. I 0.2.I. This change reflects the correction of the alphabetical location of this requirement from 6. I 0.2.m to 6. I0.2.I).

Determination of No Si nificant Hazards Consideration The standards used to arrive at a determination that proposed changes do not involve a significant hazards consideration are included in IO CFR 50.92(c), which states that the Commission may make such a determination if 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.

With respect to criterion (I), the changes being proposed by FPL are administrative; they do not affect assumptions contained in plant safety analyses, nor do they affect Technical Specifications that do preserve safety analysis assumptions. Safety related snubbers will continue to be controlled and surveil led according to Technical Specifications. Changes in snubber quantities, types, or locations would be a change to the facility and would be adequately controlled per the provisions of IO CFR 50.59. Therefore, the proposed changes do not affect the probability or consequences of accidents previously analyzed.

With respect to criterion (2), the changes being proposed by FPL are administrative; they will not lead to physical modifications. These changes do not add to, or delete from, the total number of plant snubbers available to provide dynamic load support during and following a seismic event or other initiating dynamic loads. Therefore, the proposed changes do not create the possibility of a new or different kind of accident.

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With respect to criterion (3), the changes being proposed by FPL are administrative; they do not modify the safety margins defined in and maintained by the Technical Specifications. The NRC has concluded that snubber listings are II ~fl not necessary provided the snubber Technical Specification specifies which snubbers are required to be OPERABLE. The snubber LCO has been clarified to

• d b b 0 K%ABLE. T i d involve a significant reduction in a margin of safety since: I) the LCO clearly specifies which snubbers are required to be OPERABLE, and 2) the snubber listing will be maintained via controlled documents.

In addition, the Commission has provided, guidance (48 FR l4870) concerning the application of standards for determining whether a significant hazards consideration exists by presenting examples of amendments that are considered not likely to involve a significant hazards consideration. Example (i) relates to a purely administrative change to the Technical Specifications: for example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature. The changes being proposed by FPL are similar to example (i) in 48 FR l4870 in that they are administrative changes designed to:

o Remove snubber listings from Tables 3.7-2a and 3.7-2b as per Generic Letter 84-I3.

o Remove outdated material.

o Correction of an error.

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