ML17219A491
| ML17219A491 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/01/1987 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17219A490 | List: |
| 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 vchaIl4 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 1 I '
%A p
a 4.7.10, Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.
'P
= ~
a.
Visual Ins ections
~l f
hb
~&I"bm Ht d-
-'efterfourmonths-bdwWhm 14-moths-.gX-commencing-POWB-OPERAS-NN-and-s~H mehtd aN-rubbers l-is-&d-i.n-Tebl.es-8-.7-2a-and&.7-2b- -I-f-h~~H
~
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-firat-ins pec tion..
Otherw~ ~sequent-Visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers er Ins ection Period Subsequent Visual 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
87000b0447 870401 PDR ADOCK 05000335 P
PDR 3/4 7-29 Amendment Ho. Rf, 44
~
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~
(IOX 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.
\\
E Snubber s identified m-Tables 3-.7-2a-and 3-.7-2b-as "Especially Oifficult to Remove" or in "High Exposure Zones Ouring Shutdown" shall also be d
4 i h
p
<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 d.
~
- 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.
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.
LUGIE - UNIT 1
3/4 7-31 Amendment No. g7, 44
TABLE 3.7-2a SAFETY RELATED HYDRAULIC SHUBBERS*
~ L LOCAT NO
~ 001 002 003 004 005 006 007 008 009 010 011 012 013 014 015 0! 6 017 018 019 020 MARK NO.
SS-1 SS-2 1A SS-3 1A S~-4 1A SS-5 1A SS-6 lA SS-7 1A SS-8 1A SS-1 1B SS-2 1B SS-3 1B SS-4 1B SS-5 1B SS-6 1B SS-7 1B SS-8 1B 1A1 1A2 1B1 1B2 1A, L'vel. 62',
lA, Evel.
62 1A, Evel.
62 1 A, Evel ~
62'A, Evel ~
62'Evel.62' h>>
Rv
~
62'h, Evel.
1B, Elev.
62 lB, El.ev.
62'B, Elev.
62 1B, Elev.
62'B, Elev.
62'B, Elev.
62'g, Elev.
62'B, Elev.
62'l, Elev.
57 Al, Elev.
57'l, Elev.
57'l, Elev.
57'S, Steam Gen.
Steam Gen.
MS, team Can.
HS, Ste Gan.
MS, Steam MS, Steam Gen.
MS, Steam Gen.
MS, Steam,Cen.
MS, Steam Gen.
MS, Steam Cen.
HS, Steam Gen.
HS, Steam Gen.
MS, Steam Gen.
Steam Gen.
MS, Steam Gen.
MLS, Steam Gen.
RC, RCP Motor 1
RC, RCP Motor 1
RC, RCP Motor 1
RC, RCP Motor 1 SYSTVA.SNUBBL'R INSTALLED ON LOCATION AND P3.1?VATION
~ i~ ACCESSIBLE"Olf.,llIGI1 RADIATIOH INACCESSIBLE ZONE*~
(A or I)
(Yes or No)
Ho, I~
ra I
~
Ho I
No I
Hp I
Nq I
No.
I
~
Ho, I
Ho I
No Ho, I
lP No-I No.
I ~
o.
I Ho.
I No I
Ho I
No I
Ho (Yes or Yes Yes
~
Yes
-Yes Yes Yes Yes Yea Yes.
Yes Yes LI Yes
<<Yes, Yes.
Yes Yes No No No Ho) 1 I ~
ESPECIALl Y DXFFICIJ(T TO REMOVE
O LOCAT ND.
033 034 035 036 037 030 039 040 04l 042 043 044 047 052 053 050 061 066 073 074 076 077 079 080 081 002
'83 MARK HO.
649-319 MS 5> -5 MS 1076-64 MS '649-314 MS. 649-314 Ms 649-310
. MS 649-304A MS 548-9 MS 548-9 BF 549-7 QP 549-7 BF 549-8 BF 549-17 BF 549-17 SI 968210 SI 969 1216 MS 549-11 MS 549-11 SI 972-6240 SI 973-240 SI 973-6224 SI 860 64 SI 868-163 Sl 860 410 SI 676-67 SI 676 67 SI 676-105 SYSTBI SHUBDElt IHSTALfED OH I.OCATION.. AND I:I.I?Vh'I'ON MS>
MS>>
- MS>
IIS >
MS,
~ MS>
MS, BP, BP BL',
SI, SI>
SI, SI>
SI, SI>
Reactor Bldg.
Reactor Bldg.
M.S. Trestle, Reactor Bldg.
Reactor Bldg.
eactor Bldg.
Re or Bldg.
Reacto Bldg.
Reactor B
Reactor Bldg.
Reactor Bldg.
Reactor BLdg.
Reactor BLdg.
Reactor Bldg.
Reactor Bldg.
Reactor Bldg.
Reactor Bldg.
Reactor Bldg.
Reactor Bldg.
Reactor Bldg.
Reactor Bldg.
RAB, Elev.
4'AB, El.ev.
4'AB>
Kiev.
4 RAB, L'lev.
4'lev.
82'lev.
82'lev.62 Elev.
55 Kiev. 82 Elev.
50'lev.
30'lev.50 Elev.
50 Lev. 40'
-'0 ELev.
0 L>Lev. 36 L'lev.
36lev.
16'lev.18 Elev.
18'lev.
20'lev.16 Elev.
18 ELev. 18 ACCESSIBI.E OR IHACCESSIBI.E (A or I)
A A
AIII AIII,II A
A A D@
A
-Tg II A
A
'A A
. A A
A
~
I HIGH RADIATION ZONE**
(Yes or No)
No No.,
No*
Ho No '.
Ho No.
Ho.
No.
Ho Ho,'o
'o No No Ho No Ho No 0
No No Ho Ho No No No I
~
1 SAFETY REI.ATED HYDRAUI.IC SNUBBERS+
1 C,!>1 v
~
'I ESPECIALLY DIPPICUI',T
- TO REMOVL'Yesor No)
- -.'o
!'Ho
.'i No
.. No 9: No
.jt No i' Yes
'~( Yes Yes No
'". Ho
!,I Yes
.~w Yes Ho Ho No No No No No Ho
. -No No No No N&o
TABLI? 3 ~ 7-2a CONTINUED SAFETY RI?I.ATED IIYDRAULIC SNUBBERS*
l LOCATI HO.
I rr
. 084 086 087 1 lU 1 ll 112
'14 091 090 092 093 MARK 0
SI 676-l, Sl 676 129
- I c 7t -"48l Sl bio 247 SI 676-2475A SI 676 4505 SI 972-6240 SPS-417 SPS>>27 SPS-467 SPS-777 SYSTI21 SNUBBI'R IHSTALI.I?0 OH LOCATION AHI) I!I.I?Vh'I'TOH SI, RAB, Elev.
4'AB, Kiev.
4'I, Elev.
24 Sf,,
4
, Pressurizer
- Spray, Reactor Bldg. Elev.
50'ressurizerSpray, Reactor Bldg. Elev.
50'.
Pressurizer Spray, Reactor Bldg. Elev.
80 Pressurizer
- Spray, Reactor Bldg-Elev. 80' ACCESSIBLE OR INACCESSIBLE (A or I)
A A
A A
A A
A Op~ ~rg llIGN RADIATIOH ZONE**
(Yes or No)
No No No Ho Ho Ho No Ho Ho ESPECIALLY DIFFICULT TO REMOVE (Yes or No)
No No No No Ho No Ho I
l No No No
l
~
~
I
'l o
I i
~
o TABLE 3. 7-2a CONTINUL'D SAFETY RELATL'D HYDRAULIC SNUBBERS*
'~e-i
~
~.
i ~
e~p LOCATIO NO'ARK
).
NO.
096 CC-1 865-9 08ll CC-I 899-48 089 CC-1852-6241 01 CC-1 7-1 102 MS-649-313 I 04 CC-21-1 103 BF-549-7 105 CC-23-2 106 CH-3-40
~
I,07 CII-3-75 108 MS-649-313 1 09 HS-649-313 097 MS-649-314 099 MS-649-314 SYSTEM'NUBBER INSTAf.f.ED ON LOCATION AND ELEVATIOH (A or I)
C, Reactor Bldg, Elev.
25 CC, ctor Bldg, L'lev. 25 CC, Reacto dg, Elev.
25'C, RAB, Elev.
2'0'C, RAB, Elev.
26'C, RAB, Elev.
20'C, RAB, Kiev.
26'C, RAB, Elev.
26'H, RAB, Elev.
34'H, RAB,'l.ev. 23 MS, Reactor Bldg, Elev.
80'S, Reactor Bldg, Elev.
80'S, Reactor Bldg, Elev.
80'S, Reactor Bldg, Elev.
80'CCESSIBLE OR INACCESSIBLE (uAu + pr IIIII)
'A I A
". A
.A
- A
.A
~ A
~7F A
AI
~.I I
IIIGH RADIATION ZONE**
(Yes lor No)
!No
~ No tNp
'No
'No
.'No
- No No
."No
.No
<Ho
.'No iNO
'No ql No:
No No No No Np No Ho Nb Ho No Ho No ESP I':CIALLY DIFF II:UI T TO REMOVE 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 Hon-areas-may-be-made-vt:thou t~orWce~mendment.
p rovtd~d-tlra~revIM>~T<b~7-2a-ts-I nc 1~dud~ lth-th~ex t-blcense-Amendment reques t.
TABLE 3.7-2b SAFETY RELATED MECI{ANICALSNUBBERS*
L LOCA'O.
021 022 023 025 026 024 028 027 029 030 031 032 045 046 048 049 050 051 054 055 056 057 059 060 062 063 064 065 MARK NO RC 005-3 RC 005-34B ftC 005-36 RC 005-128 RC 005-l.2B RC 005-1 2A RC 005-55C ltC 005-55B ftC 005-62A RC 005-89 RC 005-90 RC 005>>98 BF 549-11 BP 549-11 BP 661-407 BP 6610407 BP 661-416 BP 66l-416 SI 968-565 SI 989 1205 SI 968-1207 SI 969-1190 SI 969-6193 SI 969 6195 SI 969-6201 SI 696-6217 SI-696-6217 SI-970-1 21 0 (A
RC, RC, RC, RC, RC>
RC, RC, RC, RC, RC, RCo BP BP, BF, BP, BP BP)
SI, SI, SI, SI, SI, SI, SI, SI, SI ~
or I).
Reactor Reactor Reactor Reactor Reactor Reactor Re>a r
Reacto Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor lteactor Reactor Reactor Reactor 68 68'8'0 80'0'0 80'0'0'0'ldg,
- Bldg, Bldg,
- Bldg, Bldg,
- BWg, Bldg,
- ldg, Bldg
- Bldg, Bldg,
- Bldg, Bldg+
Bldg.
Bldg.
Bldg.
Bldg.
Bldg+
Bldg.
Bldg.
- Bldg, Bldg,
- Bldg, Bldg,
- Bldg, Bldg,
- Bldg, Bldg, Elev.
Elev.
Elev.
Elev.
Elev.
Elev.
Elev.
Elev.
~Eleve Elev.
E1%e~
Elev. 0 Elev.
Kiev.
Elev.
- Elev, F.lev.
Elev.
L'lev.
Elev.
Elev.
Elcv ~
Elev.
Elev.
L'lev.
Elev.
P.lev.
Elev.
50'0'0'Or 50'0'5'0'8'0'8'8 18'8'8 33'YST&f SNUBBER INSTAfLED OH LOCATION AND EI.L'VATlOH ACCESSIBLE OR INACCESSIBLE (Yes or No)
A A
A A
A A
A A
h A
A A'
II Q~
A
'A AI A
A A
h AI NIGH RADIATION ZONE**
(Yes or No)
NO NO NO NO NO HO NO NO HO HO NO NO HO HO NO HO NO HO HO NO 0
HO NO.
HO NO NO NO HO ESPECIALf Y DIFFICUf.T TO REMQVE HO HO
'HO NO
- HO HO HO HO NO
~ HO/
HO )
HO HO
'O
)
HO; NO )
HO NO NO
.NO HO HO HO NO HO NO HO
TAIILI! 3 ~ 7-2b
~CONTINUED SAFETY RRLATliU MECIIANICAL SNUBBERS*
I LOCATI0 HO 067 060 069 070
- 071, 072 075 078 095 113 094 085 098 100 HARK f0.
SI 970-125 SI 971-6 SI 971-1229 SI 971-6229 SI 971-6236 SI 972-1243 SI 973-621.9 Sj 868 111 SI 676-1 27 SI 971;6236 CS-832-118 CS-878 115 CC-1899-2208 CC-1865-2207 SYSThH SNUBBL'IL fNSTAf.LED ON I.OCATIOH hND I?f.EVh'I'ION SI, Reactor Bldg, Elev.
20'I, eac tor Bldg, Elev.
20'I, Rea t~r Bldg, Elev.
20'I, Reactor ff'hing Elev.
20'I, Reactor Bldg El~
20'I, Reactor Bldg, Kiev. 25 SI, Reactor Bldg, Elev.
36'I, RAB, L'lev.
4'I~
RAB, Elev.
4'I, RAB, Elev.
4'S, Reactor Bldg, Elev.
125'S, Reactor Bldg, Kiev.
1 8 CC, Reactor Bldg, Elev.
59'C, Reactor Bldg, Elev.
59'Yes or No)
NO NO HO HO NO NO NO NO NO 0
NO Ho NO HQ ACCESSIBLE OR ffIGH RADIATION INACCESSIBLE ZONE*~
(A or I)
AIIII AI Ogf A
A A
'A A
A ESPECIhf f Y DIFFICULT TO REHOVE (Yes or No)
NO HO NO NO HO NO HO NO NO
~
HO YES YES HO
LA In Pl GJ I
CO CL B
s IEI O
PL LOC OH
'O.
115 116 117 110 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 l37 130 139 140 141 142 143 144 145 146 147 NRK HO.
RC164-ll I
62-11 RC-21A RC-1-1 RC162-11 RC-1-192A RC-5-475 CH-129-99 RC-217-5 CH-65-54C CH-142-9 CH143-30C
.,RC-215-9A HSI-22-3A RC-1-124C HSI-20-3A HSI-16-3h CH-125-35O HSI-14-3A CH-129-339 RC-220-105 RC-217-5 CH 129-339 RC 114-129 RC 221-)62 CII-107-38A CH-143-26C CII-141-74 D-2-Hl RC 128-99 CII-143-34C RC-1-25C CH-141-36=C TAULE 3. 7-Zb
.JliTIHUkO SAFE l'Y IIkNLATLO HkCHAHICAL SNUOOERS*
ACCfSSIDLE 'OR INACCESSIBLE I
I I
I I
I I
I I
I I
I I
I I
I I
I SYSTEH SNUBBER INSTALLED ON, LOCATION AND 1I.EYA'i'ION Yes or No N~o I
Yes or 36'5'1'9'5'9'7'3'5'1'0' 73'7'9'8'7'0'2'2'2 75l 32'8'8'4'7'4'I67'7'1'2'O HO NO HO HO HO HO HO NO NO NO NO HO HO NO NO NO HU NO.
NO HO NO HO NO NO HO NO HO NO NO HO HO NU HO NO HO HO HO HO NO NO HO HO HO HO HU tg NU RC RCG Elev.
'C RCB Elev.
RC RCD Elev.
RC RCO flev.
RC RCO Elev.
RC RCD flev.
R RCG Elev.
CH CO Elev.
RC RC
- Elev, CH RAD l.ev.
CH RCB Ele~'H RCO Elev.
1 RC RCO flev.
HS RCD Elev.
RC RCO Elev.
HS RCD Elev.
HS RCO Elev.
CH RCD Elev.
HS RCD flev, CH RCG Elev.
NU N0 NO HO RC RCB El ev.
RC RCO flev.
CH RCD Elev.
RC RCB Elev.
il
~I I
I I'I I
I I
I I
HO NO NO NO RC RCD Elev.
Cll RCD flev.
CH RCG Elev.
CH RCD Elev.
NO HO D RCB Elev.
3 RC RCO El ev.
Cll RCG Elev.
RC RCB Elev; CH RCB El ev.
NO NO 0
0 t
HIGH RADIATION ESPECIALLY DII.FICULT ZONE*~
TO RB10VE
In oM TABLE 3. 7-Z~bCOHT INUEOJ SAI'ETY RLLATEO HLCIIANlCAL'-SHUDDERS>>
s
~
O 148 149 150 151 lb2 153 154 l5b 156 l5/
158 lb9 160 1C)1 162 163 164 165 166 167 168 169 170 171 172 I/3 174 175 176 1/7 178 L
~ LOCA H
NO.
IMARI'.
NO.
C-1-124A t>250 Msll-7A HPR-201-1 6 HPR 200-20 8-2l.-311 8-21-3110 8-21-3240 CC>>1 899-2200 SYSTBf SNUBBER IHSTALLEI)
ON LOCATION AHD ELEVATI'ON RC RCB Elev 71'C RCG Elev.
74 RC RCB Elev.
73'+
RCS El.ev.
78'C R 8 Elev.
76'II RAB ev. 30' RCG Elev.
8'I RCB Elev.
5 RC RCB Elev, 50'I RCG Elev.
57'H RCG Elev.
32 CN RCG Elev. 32' RAG Elev.
36'll RAB Elev.
26'S Steam Trestle El.ev. 38 HP RCB Elev.
34'm Stream Trestle Elev.
38 HP RCG Elev.
35'P RCI3 L'lev.
35'-RAG Elev.
36'-RAB Elev.
35'-RAB Elev.
38'C-RCB Elev.
57'CCL'SSIBLE OR INACCESSIl3LE (A or I)
IIII g
IIIIIIII I
AI AII A
I (Yes or No)
NO HO NO
- NO NO HO NO HO NO HO NO HO NO NO NO HO NO 0
NO HO NO HO HO (Yes or NO NO HO NO HO NO HO HO HO HO NO HO HO
. NO HO NO HO HO NO NO NO 0
NO No)
HIGll RADIATIOH ESPECIALl Y DIFFICULT ZONE**
TO REHOVE
?
- 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.
p.
Meteorological data, summarized and reported in a format consistent with the recommendation of Regulatory Guides 1.21 and 1.23.
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 Ieted.
(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 not necessary provided the snubber Technical Specification specifies which snubbers are required to be OPERABLE.
The snubber LCO has been clarified to II~fl *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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