ML20062H129
| ML20062H129 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/13/1979 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| Shared Package | |
| ML20062H133 | List: |
| References | |
| NUDOCS 7905150223 | |
| Download: ML20062H129 (1) | |
Text
,
1LANT SYSTEMS 3/4 7.10 SNUBBERS _
LIMITING CONDITION FOR OPERATION 3.7.10 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.
APPLICABILITY:
MODES 1, 2,
3 and 4.
(MODES 5 and 6 f or snubbers located on systems required OPERABLE in those MODES).
1 ACTION:
With one or more snubbers inop e rable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or resto re the inop erable snubber (s) to OPERABLE status or declare the supported system inoperable and f ollow the approp riate ACTIOC s tatemenc for that system.
SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by perf ormance of the f ollowing augmented inservice inspection program.
- a. Visual Inspections The f irs t inservice visual inspection of snubbers shall be perf ormed af ter f our months but within 10 months of commencing F0WER OPERATION and shall include all s nubbers listed in Tables 3.7-4a and 3.7-4b.
If less then two (2) snubbers are found inoperable during the first inservice visual insp ection, the second inservice visual inspection shall be perf ormed 12 months 125% f rom the date of the f irst inspection.
Otherwise, subsequent visual insp etons shall be perf ormed in accordance with the f ollowing schedule:
No. Inoperable Snubbers Subsequent Visual i
par Inspection Period Iqspection Period *5 0
18 months 125%
1 12 months 1257.
{
\\
2 6 months i 25%
' ~ ~
3,4 123 days i 25%
5,6,7 62 days i 257.
8 or more 31 days i 25%
The snubbers may be categorized into two group s:
Those accessible and those inaccessible during reactor op e ration.
Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more tnan one step at a time unless a generic problem has been identified and corrected; in that event the inspection may be lenghtened one step the f irst time and two steps thereaf ter if no inoperable snubbers are f ound.
- The provisions of Specification 4.0.2 are not applicable.
l ST. LUCIE - UNIT 1 3/4 7-29 333 a:*
rt-
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a
- b. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are ho Uisible indicationa of the damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure.
Snubbers which appear inoperable as a r esult of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of ti e rej ection is clearly established and remedied for that particular snubber and.for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.10.d or 4.7.10.e, as applicable.
I
- c. Functional Tests At least once per 18 months during shutdown, a representative sasple* (10% of the i
snubbers listed in Tables 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 107.
of that type of snubber shall be functionally tested. ' Functional testing shall continue until no additional snubbers are found inoperable or all snubbers listed in Tables 3.7-2a and 3.7-2b have been tested.0 The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.
1 Snubbers identified in Tables 3.7-2a and 3.7-2b as "Especially Difficult to Remove" or in "High Exposure Zones During Shutdown" shall also be included in the representative sample.**
Tables 3.7-2a and 3.7-2b may be used jointly or separately as the basis for the sampling plan.
/
In addition to the regular sample, snubbers which failed the previous functional s
test shall be retested during the next test period.
If a' spare snubber has been Ins talled in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and. the spare snubber' shall be retested.
Test results of these snubbers shall not result in additional functional testing due to failure.
1 l
- The requirements of this section for functionally testing mechanical snubbers may be waived until startup following the fifth refueling outage for Unit 1
- *Pe rmanent or other exemptions from the functional testing for individual snubbers in i
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 operabililty for all design conditions at either the completion of their fabrication or at a subsequent date.
l 1
9 St. Lucie Unit 1 3/4 7-30
, -.,, - ~
y,,.-._,4_
PLANT SYSTalS SURVEILLANCE REQUUtE'4ENTS (Continued)
If any snubber selected f or f unct ional testing either f alls to lockup or falls to move, i.e.,
f rocen in place, the cause will be evaluated for f urther action or testing.
- d. Ilydraulic Snubbers Functional Test Accep tance Criteria The hydraulic snubber f unctional test shall verif y that:
1.
Activation,(restraining action) is achieved within the specified range of velocity or acceleration in both t ens ion and comp ress ion.
2.
Snubber bleed, or release rate, where required, is within the specif ied range in comp ression or tension.
- c. Mechanical Snubbers Functional Test Accep tance Criterta The mechanical snubber f unctional test shall verif y that:
s 1.
The force that initates f ree movement of the snubber rod in either tension or compression is less than the specif led maximum drag f orce.
2.
Activation (restraining action) is achieved in both tension and comp ression.
f. Snubber Se rvice Lif e Monttoring-A record of the se rvice life of each snubber, the date at which the designated service lif e commences and the installation and maintenance records on which the designed service lif e is based shall be maintained as required by Specif ication 6.10.2.m.
Concurrent with the f irst inservice visual inspection and at least once per 18 months thereaf ter, the installation and maintenance records f or each snubber listed in Tables 3.7-2a and 3.7-2b shall be reviewed to verif y that ' the indicated service lif e has not been exceeded or will not be exceeded by more than 10% prior to the next scheduled snubber se rvice lif e review.
If the indicated service lif e will be exceeded by Edre than 107, prior to the next scheduled snubber service life review, the snubber service lHe shall be reevaluated or the snubber shall be replaced or recondit Loned so as to extend its service life beyond the,date of the next scheduled service lite review. The results of the reevaluation may be used to justif y a change to the service, lif e oE/ the snubber. This reevaluation, replacement or reconditioning shall be indicated in the records.
St. Lucie Unit 1 3 /4 7-31
f I
',,~ i
',I" TABLE 3.7-2a
/
ETY RELATED HYDRAULIC SNUBBL 4
~
FPL LOCATION MARK SYSTFA SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT f
NO.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) g 3
0 01 SS-1 1A MS, Steam Gen. lA, Evel. 62' I
No
-Yes 002 SS-2 1A MS, Steam Gen. lA, Evel. 62' I
No Yes 003 SS-3 1A MS, Steam Gen. lA, Evel. 62' I
No Yes 004 SS-4 1A MS, Steam Gen. lA, Evel. 62' I
No Yes 005 SS-5 1A MS, Steam Gen. lA, Evel. 62' I
No Yes 006 SS-6 1A MS, Steam Gen. l A, Evel. 62' I
No Yes 007 SS-7 1A MS, Steam Gen. lA, Evel. 62' I
No Yes 008 SS-8 1A MS, Steam Gen. lA, Evel. 62' I
No Yes 009 SS-1 IB MS, Steam Gen. IB, Elev. 62' I
No Yes 01 0 SS-2 IB FG, Steam Gen.1 B, Elev. 62' I
No-Yes 011 SS-3 IB MS, Steam Gen. IB, Elev. 62' I
No Yes 012 SS-4 IB MS, Steam Gen. IB, Elev. 62' I
No Yes
+
013 SS-5 IB MS, Steam Gen. IB, Elev. 62' I
No Yes 014 SS-6 IB MS, Steam Gen. IB, Elev. 62' I
No Yes
~
015 SS-7 IB MS, Steam Gen. IB, Elev. 62' I
No,
Yes 01 6 SS-8 IB MS, Steam Cen. 1B, Elev. 62' I
No Yes e
017
- l Al -
RC, MCP Motor 1 Al, Elev. 57',
1 No No 018 1A2 RC, IECP Motor 1 A1, Elev. 57' I
No No
~
I Bl RC, RCP Motor IAL, Elev. 57
I
~
No No 019/
020 IB2 RC, RCP Motor I Al, Elev. 57' I
No No l
1 j
l TABLE 3.7-2a (CONTINUED)
SAFETY RELATED HYDRAULIC SNUBBERS
- N FPL
'E LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGil RADIATION ESPECIALLY DIFFICULT 0.
NO.
NO.
l*
'ON, LOCATION AND ELEVATION INACCESSIBLE ZONEw*
TO REMOVE (A or I)
(Yes or No)
(Yes or No)
E 033 MS 649-319 MS, Reactor Bldg. Elev. 82' A
No No
'E 034 MS 548-5 FG, Reactor Bldg. Elev. 82' A
No No 035 MS 1076-3164 MS, M.S. Trestic, Elev. 62' A
No No 036 FG 649-314' MS, Reactor Bldg. Elev. 55' I
No No 037 MS 649-314 MS, Reactor Bldg. Elev. 82' I
No No 038 FG 649-310 FS, Reactor Bldg. Elev. 50' I
No No 039 MS 649-304A MS, Reactor Bldg. Eley. 30' A
No Yes 040 MS 548-9 FS, Reactor Bldg. Elev. 50' I
No Yes 041 MS 548-9 MS, Reactor Bldg. Elev. 50' I
No Yes 042 BF 549-7 BF, Reactor Bldg. Elev. 40' I
No No 043 BF 549-7 BF, Reactor Bldg. Elev. 40' I
No No-i 044 BF 549-8 BF, Reactor Bldg. Elev. 40' I
No,. ),
Yes 047 BF 549-17 BF, Reactor Bldg. Elev. 36' A
No Yes u,
j ;;
052 BF 549-17 BF, Reactor Bldg. Elev. 36' A
No No 053 SI 968210 SI, Reactor Bldg. Elev.16' I
No No y
il 058 SI 9691216 SI, Reactor Bldg. Elev.18' A
No No i
0 61 MS 549-11 SI, Reactor Bldg. Elev.18' A
No No 066 MS 549-11 SI, Reactor Bldg. Elev. 20' I
No No 073 SI 972-6240 SI, Reactor Bldg. Elev.16' I
No No 074 SI 973-240 SI, Reactor Bldg. Elev.18' A
No No 076 SI 973-6224 SI, Reactor Bldg. Elev. 18 '
A No No I
077 SI 868 64 SI, RAB, Elev. 4' A
No No 079 SI 868-163 SI, RAB, Elev. 4' A
No No 080 SI 868 410 SI, RAB., Elev. 4' A
No No 0 81 SI 676-67 SI, RAB, Elev. 4' A
No No 082 SI 676 67 SI, RAB, Elev. 4' A
No No l
083 SI 676-105 SI, RAB, Elev. 4' A
No No i
a l
I
_m TABLE 3.7-2a (CONTIMUED).
../ETY RELATED HYDRAULIC SNUBBE.w*
l E'
'O.
LCCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE CR HIGH RADIATION ESPECIALLY DIFFICULT NO.
NO.
ON, LOCATION AND ELEVATION E
~~
INACCESSIBLE ZONE **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 4 j EE 084 SI 676-105 SI, RAB, Elev. 4' A
No No s
086 SI 676129 SI, RAB, Elev. 4' A
No No 087 SI 676-2481 SI, RAB, Elev. 24' A
No No 110
.SI 676 247 SI, RAB, Elev. 30' A
No No
[
111 SI 676-2475A SI, RAB, Elev. 30' A
No No 112 SI 676 4505 SI, RAB, Elev. 7' A
No No j
114 SI 972-6240 SI, RAB, Elev. 4' A
No No 0 91 SPS-417 Pressurizer Spray, Reactor i
Bldg. Elev. 50' I
Nc No
}
090 SPS-27 Pressurizer Spray, Reactor l
Bldg. Elev. 50' I
No No 092 SPS-467 Pressurizer Spray, Reactor Bldg. Elev. 80' A
No No y
']
093 SPS-777 Pressurizer Spray, Reactor jy Bldg. Elev. 80' A
No No i
I f
1 I
I t
l i
l
+
I i
I i
.N
. [
- g.
TABLE 3.7-2a (CONTINUED) n SAFETY RELATED HYDRAULIC SNUBBERS
NO.
ON, LOCATION AND ELEVATION, INACCESSIBLE ZONE **
TO REMOVE (A or I)
("A" or "I")
(Yes or No) 096 CC-1865-9 CC, Reactor Bldg, Elev. 25' A
No No 088 CC-1899-48 CC, Reactor Bldg, Elev. 25' A
No No 089 CC-1852-6241 CC, Reactor Bldg. Elev. 25' A
No No 1 01 CC-17-1 CC, RAB, Elev. 20' A
No No 102 MS-649-313 CC, RAB, Elev. 26' A
No No 104 CC-21-1 CC, RAB, Elev. 20' A'
No No-103 BF-549-7 CC, RAB, Elev. 26' A
No No u
3:
105 CC-23-?
No No 106 CH-3-40 Cil, RAB, Elev. 34' A
No No y
6 107 CH-3-75 CH, RAB, Elev. 23' A
No No l
108 MS-649-313 MS, Ro sctor Bldg, Elev. 80' I
No No i
109 MS-649-313 FS, Reactor Bldg, Elev. 80' I
No No 097 MS-649-314 MS, Reactor Bldg, Elev. 80' I
No No l
099 MS-649-314 MS, Reactor Blds, Elev. 80' I
No No l
l
- Snubi ers may be added to or removed f rom saf ety related systems without prior License Amendment to Table 3.7-2a provided a revision to Table 3 7-2a ts incluaed with the next License Amendment request.
l
- Modif ications to this column due to changes in high radiation areas may be made without prior License Amendment l
provided that a revision to Table 3.7-2a is included with the next License Amendment request.
L-
V '
m TABLE 3.7-2b SAFETY RELATED MECHANICAL SNUBBERS *
.E
[
FPL S
LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGIl RADIATION ESPECIALLY DIFFICULT E
_NO.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE p
(A or I)
(Yes or No)
(Yes or No) 021 RC 005-34A RC, Reactor Bldg, Elev. 68' A
NO NO
~
022 RC 005-34B RC, Reactor Bldg, Elev. 68' A
NO NO 023 RC 005-36 RC, Reactor Bldg, Elev. 68' A
NO NO 025 RC 005-12B RC, Reactor Bldg, Elev. 80' A
NO N0 026 RC 005-12B RC, Reactor Bldg, Elev. 80' A
NO NO 024 RC 005-12A RC, Reacte r Bldg, Elev. 80' A
NO NO 028 RC 005-55C RC, Reactor Bldg, Eley. 80' A
NO NO 027 RC 005-55B RC, Reactor Bldg, Elev. 80' A
NO NO 029 RC 005-62A RC, Reactor Bldg, Elev. 80' A
NO NO 030 RC 005-89 RC, Reactor Bldg, Elev. 80' A
NO N0 031 RC 005-90 RC, Reactor Bldg, Elev. 80' A
NO NO 032 RC 005-98 RC, Reactor Bldg, Elev. 80' A
NO NO 045 BF 549-11 BF, Reactor Bldg. Elev. 50' I
NO NO 046 BF 549-11 BF, Reactor Bldg. Elev. 50' I
NO NO
{h 048 BF 661-!.07 BF, Reactor Bldg. Elev. 40' I
NO NO 049 BF 6610407 BF, Reactor Bldg. Elev. 40' I
NO NO y
050 BF 661-416 BF, Reactor Bldg. Elev. 50' I
NO NO m
051 BF 661-416 BF, Reactor Bldg. Elev. 50' I
NO NO 054 SI 968-565 SI, Reactor Bldg. Elev. 25' A
NO NO 055 SI 9891205 SI, Reactor Bldg. Elev. 30' A
NO NO 056 SI 968-1207 SI, Reactor Bldg, Elev.18' A
NO NO 057 SI 969-1190 SI, Reactor Bldg, Elev. 20' I
NO NO 059 SI 969-6193 SI, Reactor Bldg, Elev.18' A
NO NO 060 SI 969 6195 SI, Reactor Bldg, Elev.18' A
NO NO I
062 SI 969-6201 SI, Reactor Blig, Elev.18' A
NO NO 063 SI 696-6217 SI, Reactor Bldg, Elev.18' A
NO N0 1
1 064 SI-696-6217 SI, Reactor Bldg, Elev.18' A
NO NO 065 SI-970-1210 S1, Reactor Bldg, Elev. 33' I
NO NO
s..
+
TABLE 3.7-2b (CONTINUED)
SAFETY RELATED MECHANICAL SNUBBERS
NO.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE r.
(A or I)
(Yes or No)
(Yes or No) 8 067 31 970-1251 SI, Reactor Bldg, Elev. 20' A
NO NO EF 068 SI 971-6 SI, Reactor Bldg, Elev. 20' I
NO NO c:
069 SI 971-1229 SI, Reactor Bldg, Elev. 20' I
NO NO
?
070 SI 971-6229 SI, Reactor Bldg, Elev. 20' I
NO NO 0 71 SI 971-6236 SI, Reactor Bldg, Elev. 20' I
NO NO 072 SI 972-1243 SI, Reactor Bldg, Elev. 25' A
NO NO 075 SI 973-6219 SI, Reactor Bldg, Elev. 36' I
NO NO 078 SI 868111 SI, AAB, Elev. 4' A
NO NO 095 SI 676-127 SI, RAB, Elev. 4' A
NO NO 113 SI 971-6236 SI, RAB, Elev. 4' A
NO NO 094 CS-832-118 CS, Reactor Bldg, Elev. 125' A
NO YES 085 CS-878 115 CS, Reactor Bldg, Elev.18' A
No YES 098 CC-1899-2208 CC, Reactor Bldg, Elev. 59' A
NO NO 100 CC-1865-2207 CC, Reactor Bldg, Elev. 59' A
NO NO
1 r. TABLE 3.7-29 (CONTINUED) 1 FPL
~S Y RELATED MECHANICAL SNUBBf
~
i LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE (A or II (Yes or No)
(Yes or No)
I i
115 RC164-11 RC RCB Elev. 36' I
NO NO 116 RC162-11 RC RCB Elev. 35' I
NO N0
[
117 RC-1-221A RC RCB Elev. 31' -
I NO NO 118 RC-1-1248 RC RCB Elev. 19' I
NO NO El 119 RC162-11 RC RCB Elev. 35' I
NO NO j
120 RC-1-192A RC RCB Elev.19' I
NO NO l
E?
121 RC-5-475 RC RCB Elev. 77' I
NO NO i E3 122 CH-129-99 CH RCB C. lev. 33' I
NO N0 123 RC-217-5 RC RC6 Elev. 75' I
NO NO Ei 124 CH-65-54C CH RAB Elev. 21' I
NO NU
NO NO 126 CH143-30C CH RCB Elev. 17' I
NO NO
=
127 RC-215-9A RC RCB Elev. 73' I
NO NO l
128 MSI-22-3A MS RCB Elev. 57' I
NO NO i
129 RC-1-124C RC RCB Elev. 19' I
NO NO 130 MSI-20-3A MS RCB Elev. 58' I
NO NO
! u2 131 MSI-16-3A MS RCB Elev. 57' I
NO NO l ls 132 CH-125-35B Cd RCB Elev. 30' I
NO NO
-a 133 MSI-14-3A MS RCB Elev. 52' I
N')
NO do 134 CH-129-339 CH RCB Elev. 32' I
NO NO 4
135 RC-220-105 RC RCB Elev. 72 I
NO NO 136 RC-217-5 RC RCB Elev. 75' I
NO NO 137-CH 129-339 CH RCB Elev. 32' I
NO NO 138 RC 114-129 RC RCB Elev. 68' I
NO N0 t
139 RC 221-162 RC RCB Elev. 68' I
NO NO l
140 CH-187-38A CH RCB Elev. 24' I
NO NO 141 CH-143-26C CH RCB Elev. 17' I
NO NO j
142 CH-141-74 CH RCB Elev. 24' I
NO NO 143 B-2-H1 B RCB Elev. 38' I
NO NO 144 RC 128-99 RC RCB Elev. 67' I
NO NO 145 CH-143-34C CH RCB Elev. 17' I
NO NO 146 RC-1-25C RC RCB Elev. 31' I
NO NO j
147 CH-141-36=C CH RCB Elev. 32' I
NO NO I
L
m TABLE 3.7-2b__{ CONTINUED)
,g SAFETY RELATED MECHANICAL SNUBBERS
- o R
Ej FPL q LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 148 RC-1-124A RC RCB Elev. 17' I
NO NO 149 MSI-10-3A MS RCB Elev 57' I
NO NO 150 MSI-8-3A MS RCB Elev. 57' I
NO NO 151 CH 142-17 CH RCB Elev. 21' I
NO NO 152 RC-163-11 RC RCB Elev. 35' I
NO NO 153 RC 165-11 RC RCB Elev. 35' I
NO NO 154 MSI-18-5A MS RCB Elev. 57' I
NO NO 155 RC 128-99 RC RCB Elev. 68' I
NO NO 156 MSI-12-3A MS RCB Elev. 57' I
NO NO 167 RC 219-6B RC RCB Elev. 71' I
NO NO 158 Cil 142-18 CH RCB Elev. 21' I
NO NO 159 RC 163-11 RC RCB Elev. 35' I
NO NO 160 Cil 142-18 Cil RCB Elev. 21' I
NO NO lol RC 165-11 RC RCB Elev. 35' I
NO NO 162 RC-217-5 RC RCB Elev. 75' I
NO NO 163 SI-69-58 SI RCB Elev. 62' I
NO NO
- 4d 164 SI-39-6 SI RAB Elev.12' I
NO NO 165 RC 221-148 RC RCB Elev. 72' I
NO NO
^
Y 166 RC 164-11 RC RCB Elev. 36' I
NO NO E
167 Cil-67-81 CH RAB Elev. 21' I
NO NO 168 RC 114-129 RC RCB Elev. 68' I
NO NO 169 RC-44-26 RC RCB Elev. 40' I
NO NO 170 RC 220-112 RC RCB Elev. 71' I
NO NO 171 RC 218-26 RC RCB Elev. 76' I
NO NO 172 RC 44-11 RC RCB Elev. 35' I
NO NO 173 Cil 67-81 CH RAB Elev. 21' I
NO NO 174 Cil-65-54A Cil RAB Elev.12' I
NO NO 175 RC 220-112 RC RCB Elev. 72' I
NO NO 176 MSI-2-III MS RCB Elev. 78' I
NO NO 177 RC 222-43 RC RCB Elev. 70' I
NO NO 178 MSI-4-lil MS RCB Elev. 78' I
NO NO
.. -. - = -..
TABLE 3.7-2b (CONTINUED) rY RELATED MECHANICAL SWUBB 1
FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 180 RC 220-114 RC RCB Elev. 71' I
NO NO 1 81 RC 215-9B RC RCB Elev. 74' I
NO NO 182 RC 219-6A RC RCB Elev. 73' I
NO NO 182 MSI-3-H1 MS RCB Elev. 78' I
NO NO 184 RC 218-26 RC RCB Elev. 76' I
NO NO 185 CH-64-45A CH RAB Elev'. 30' I
NO NO 186 B-1-H3A B RCB Elev. 38' I
NO NO 187 SI-69 60B SI RCB Elev. 57' I
NO NO 188 RC 150-H7 RC RCB Elev. 50' I
NO NO 189 SI-69-60 SI RCB Elev. 57' I
NO NO 190 CH-141 -44A CH RCB Elev. 32' I
NO NO 1 91 Cil-141-4 4A CH RCB Elev. 32' I
NO NO 192 B-3-795 B RAB Elev. 36' I
NO NO L93 CH 130-66 CH RAB Elev. 26' I
NO N0 194 MSil-7B MS Steam Trestle Elev. 38' A
NO NO 195 MPR-200-250 MP RCB Elev. 34' I
NO NO 196 MSH-7A Sm Stream Trestle Elev. 38' A
NO NO 197 MPR-201-1G MP RCD Elev. 35' I
NO NO 198 MPR 200-20 MP RCB Elev. 35' I
NO NO 199 B-21-311 B-RAB Elev. 36' A
NO NO 200 B-21 -3110 B-RAB Elev. 35' A
NO NO 201 B-21-3240 B-RAB Elev. 38' A
NO NO 202 CC-1899-2200 CC-RCB Elev. 57' I
NO N0 i
1 j
CSnubbers may be added to or removed f rom saf ety related systems without prior License Amendaent to Table 3 7-2a provided a revision to Table 3.7-2a is included with the next License Amendment request.
- Modif ications to this column due.to changes in high radiation areas may be made without prior License Amendment provided that a revision to Tabic 3.7-2a is included with the next License Amendment ecquest.
i me n
re
PLANT SYSTEMS BASE 3 3/4.7.7 C NTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued) for operations personnel during and following all credible accident conditions.
The OPERABILITY of this sytem in conjuntion with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 ren or less whole body, or its equivalent and I
maintaining the chlorine concentration within acceptable limits during and following a chlorine accident This limitation is consistent with the requirements of General Design Criteria 10 of Appendix "A", 10 CFR 50.
3/4.7.8 ECCS AREA VENTILATION SYSTEM The OPERABILITY of the ECCS area ventilation system ersures that radioactive materials leaking from the ECCS equipment following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.
f 3/4.7.9 SEALED SOURCE CONTAMINATION The limitatios on sealed source removal contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the probable leakage from the source material.
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
Qualities of interest to this specification which are exempt f rca the leakage testing are consistent with the criteria of 10 CFR Parts 30.11-20 and 70.19.
Leakage from sources excluded from the requirements of this specification is not likely to represent nore than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.
l 3/4.7.10 SNUBBERS
\\
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 during and following a Geismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program 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 l
safety-related system.
The visual inspection frequency is based upon maintaining a constant l
level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed ' may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval i
i will override the previous schedule.
i St. Lucie Unit 1 B 3/4 7-5 l
_ PLANT SYSTEMS BASES 3/4.7.10 SNUBBERS (Continued)
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubber that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as ir. operable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or expased to the saae environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an evaluetion is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversly affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported couponent or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during pl tnt shutdowns at 18 month intervals.
Observed failures of these sample snubbers shall require functional testing of additional units.
In cases where the cause of failure has been identitiel, additional snubbers, having a high probability for the same type failure or that are being used in the same application that caused the failure, shall be teted.
Th!s requiroent increases the probability of locating inoperable snubbers without testing 100% of the snubbers.
Hydraulic snubbers and mechanical snub be rs may each be treated as a dif ferent entity for the above surveillance programs.
The se rvice life of a snubber is evaluated via manuf acturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, la high radiation area, in high temperature area, etc.
.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenmace of records and the snubber service life review are not intended to affect plant operation.
3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is St. Lucie Unit i B 3/4 7-6
PLCT SYSTFI!S BASES 3/4.7.11 FIR E SUPPRESSIO'4 SYSTCTS (Continued) loca ted.
The f tre suppression sys cem consists of the water system and f ice hose stations.
The collective capability of the f re suppression syste=a is adequate to minimize potential damage to saf ety related equipment and is a major element in the f acility fire protection program.
In the event that po rt ions of the ftre supp ress ion systems are inoperabic, alternate backup fire f ighting equipment is required to be made available in the af f ecced areas until th.e inoperable equipment is restored to service.
In the event the ftre s upp ress ion water system becomes inop e rable, immediate corrective measures must be takea since this system provides the major f tre supp ress ion capability of the plant.
The requirements for a twenty-f our hour report to the Commission provides f o r p ro::p t evaluation of the accep tability of the corrective measures to provide adequate ftre suppression capability f or the continued protection of the nuclear platt.
3/4.7.12 PENETRATION FIRE BARRIERS The f unctional integ rity of the penetration fire barreira enaures that fires will be co nf ined or adeauately retarded from spreading to adjancent portions of the Eacility.
This design f eature mininizes the possibility c: a sngle ftre rapidly involving several areas of the f aelity prior to detection and extinguishme nt.
The penetration fire barriers are a passive eleaent in the f acility f tre protection program and are subject to periodic inspections.
During periods of time when the barriers are not intact, routine f tre watch patrols in conjunction with OPERABLE fire detection ialtrumentation or a continuous ftre watch are required to be mainta ined in the vicinity of the af f ected barrier until the barrier is restored to intact status.
I I
St. Lucie Unit 1 B 3/4 7 -7
' ' ADMZNISTRATIVE CONTROLS e.
Records _ of gaseous and liquid radioact Lve material released to the environs.
f.
Records of translant or' operational cycles for those f acility components identified in Table 5.9-1.
g.
Records of training and qualification for current members of the plant staf f.
h.
Records of in-service iqpsections perf ormed pusuant to these Technical Specif ications.
1.
Records of Quality Assurance activities required by the QA Manual.
J.
Records of reviews perf ormed f or changes made to procedures or equipment or reviews of tests and experiments pursuant to 20 CFR-50.59 k
Records of meetings of the FRG and the CNRB.
1.
Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.
m.
Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-2a and 3.7-2b including the date at whch the service lif e commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures f or personnel radiation protection shall be prepared -consistent with the rquirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA t
6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10CFR 20:
a.
A High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shalt be barricaded and j
cotrpicuously posted as a High Radiarton Area and entrance thereto i
9 hall be controlled by issuance of a Radiacion Work Permit and any i
individual or group of individuals permitted to ' enter such areas shall be provided with a radiation monitoring device which i
continuously indicates the radiation dose rate in the area.
l b.
A High Radiation Area in which the intensity of tudiation is 3reater than 1000 mrem /hr shall be subject to the p rovisions of 6.12.1.a i
abo /e, and in addition locked daors sail be provtded to prevent unauthorized entry into such acess and the keys shall be maintained under the administrative control of the Shif t supervisar on duty.
i St. L'icie Unit 1 6-20
4 l
STATE OF FLORIDA
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COUNTY OF DADE
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Robert E. Uhrig, being first duly cuorn, deposes and says; l
Thal he is a Vice President of Florida Power & Light Co:apany,
the T,icencee herein; That-he has executed the foregoing docuir.cnt ; that the state-ments nade in this said document are true and correct to the bout of his knowledge, information, and belief, and that he is authorized to execute the docunan t on beha 1f of said I.icenneo.
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Rob rt. E.
Uhrig Subscribed and sworn to oefore n.c this
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MOTARY l' U D LIC, in and for the county of Dade, Sta te of I lori da ACTARY PUSUC $fA*! CF Ft.CF O A et LAEM MV CCM'MDCN L',F r:3 A s C+M T 24, 1 ?^.1 My commission ( xpires:
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