ML17209B061
| ML17209B061 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/11/1981 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17209B060 | List: |
| References | |
| NUDOCS 8105150223 | |
| Download: ML17209B061 (34) | |
Text
PLANT 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 for snubbers located on systems required OPERABLE in those MODES)~ACTION: 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 UIREMENTS 4.7 10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.a.Visual Ins ections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b~If less then two (2)snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months+25%from the date of the first inspection.
Otherwise, subsequent visual inspectons shall be performed in accordance with the following schedule: No.Inoperable Snubbers er Ins ection Period Subsequent Visual Ins ection Period*8 0 1 2 3,4 576,7 8 or more 18 months+25X 12 months+25X 6 months+25%123 days+25%62 days+25%31 days+25X The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor op eration.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 lenghtened one step the first time and two steps thereaf ter if no inoperable snubbers are f ound.8The provisions of Specif ication 4.0.2 are not applicable.
ST.LUCIE-UNIT 1 3/4 7-29 O'X9$3.$Q ckE I~I J k I PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.Visual Inspection Acceptance Criteria Visual inspections shall verify (1)that there are no visible indications of the damage or impaired OPERABILITY, (2)attachments to the foundation or supporting structure are secure.Snubbers which appear inoperable as a result of 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 generically susceptible; and/or (2)the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.F 10.d or 4.7.10.e, as applicable.
c.Functional Tests At least once per 18 months during shutdown, a representative sample*(10%of the 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 10%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.The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.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 test.shall be retested during the next test period.If a spare snubber has been installed 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.*The requirements of this section for functionally testing mechanical snubbers may be waived until startup following the fifth refueling outage for Unit 1**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 operabililty for all design conditions at either the completion of their fabrication or at a subsequent date.St.Lucie Unit 1 3/4 7-30 5 4I, I K Ks UKU J~ij l s)UK C l K'a Je Uy J II I J UK.Kll KK,s I Kj I'.UJ s K~I I~'I lt~Il i, K Kl 4 r~~, PLANT SYSTEMS SURVEILLANCE R UIREMENTS Continued If any snubber selected for functional testing either fails to lockup or f ails to move, i.e., f rozen in place, the cause will be evaluated f or further action or testing.d.H draulic Snubbers Functional Test Acc tance Criteria The hydraulic snubber functional test shall verify that: Activation (restraining action)is achieved within the specified range of velocity or acceleration in both tension and compression.
2~Snubber bleed, or release rate, where required, is within the specified range in compression or tension.e.Mechanical Snubbers Functional Test Acc tance Criteria The mechanical snubber functional test shall verify that: The force that initates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.2-Activation (restraining action)is achieved in both tension and compression.
f.Snubber Service Life Monitori A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designed service life is based shall be maintained as required by Sp ecif ication 6.1 0.2.,m.Concurrent with the first inservice visual inspection and at least once per 18 months thereaf ter, the installation and maintenance records for each snubber listed in Tables 3.7-2a and 3.7-2b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 10%prior to the next scheduled snubber service life review.If the indicated service life will be exceeded by more than 10%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 next 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, replacement or reconditioning shall be indicated in the records.St.Lucie Unit 1 3/4 7-31
TABLE 3.7-2a SAEETY RELATED HYDRAULIC SNUBBERS*FPL LOCATION NO MARK NO.SISTER SNUBBER INSTALLED ON LOCATION AND.SENSATION.
t ACCESSIBLE OR INACCESSIBLE HIGH RADIATION ZONE**ESPECIALLY DIPPICULT TO REMOVE 001 002 003 004 005 006 007 008 009 010 011 012.013 014 015 016 017 018 019 020 SS-1 1A SS-2 1A SS-3 1A SS4 1A SS-5 1A SS-6 1A 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 lA2 1B1 1B2 MS, Steam Gen.1A, MS, Steam Gen.1A, MS, Steam Gen.1A, MS, Steam Gen.1A, MS, Steam Gen.1A, MS, Steam Gen.1A, MS, Steam Gen-1A, MS, Steam Gen.1A, MS, Steam Gen.1B, MS, Steam Gen.1B, MS, Steam Gen.1B, MS, Steam Gen.1B, MS, Steam Gen.1B, MS, Steam Gen.1B, MS, Steam Gen.1B, MS, Steam Gen.1B, RC, RCP Motor lA1, RC, RCP Motor lA1, RC, RCP Motor lA1, RC, RCP Motor lAl, Evel.Evel.Evel.Evel.Evel.Evel-Evel.Evel.Elev.Elev.Elev.Elev.Elev.Elev o Elev.Elev.Elev.Elev.Elev.Elev-62 62 62 62 62'2 62'2 62 62'2 62 62 62 62 62 57 57 57 57 (A or I)I I I I I I I I I I I I I I I I I I I I (Yes or No)No No No No No No No No No No No No No No No No No No No No (Yes or No)Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes No No No No a~1 1, L Q~k'y-l>>/.l--y l.y., y y~y",'.'*.', yy y r C C C C/y y ,/*4 (
TABLE 3.7-2a CONTINUED SAFETY RELATED HYDRAULIC SNUBBERS*PPL LOCATION NO.MARK NO SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ON LOCATION ANDi ELEVATION',:
INACCESSIBLE HIGH RADIATION ZONE**ESPECIALLY DIFFICULT TO REMOVE 033 034 035 036 037 038 039 040 041 042 043 044 047 052 053 058 061 066 073 074 076 077 079 080 081 082 083 MS 649-319 MS 548-5 MS 1076-3164 MS 649-314 MS 649-314 MS 649-310 MS 649-304A MS 548-9 MS 548-9 BP 549-7 BF 549-7 BP 549-8 BP 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 868 64 SI 868-163 SI 868-410 SI 676-67 SI 676-67 SI 676-105 MS>MS, MS>MS, MS>MS, MS>MS, MS>BP, BF, BP, BP, BP, SI>SI, SI>SI, SI>SI, SI>SI>SI>SI, SI, SI>SI, Reactor Bldg.Reactor Bldg.M-S.Trestle, Reactor Bldg.Reactor Bldg.Reactor Bldg.Reactor Bldg.Reactor Bldg.Reactor Bldg.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, Elev-4'AB, Elev.4'AB, Elev-4'AB, Elev.4'AB, Elev.4'lev.Elev.Elev.Elev.Elev.Elev.Elev.Elev-Elev.Elev.Elev.Eleve Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.82'2 62 55'2'0'0'0'0 40 40'0'6'6 16'8'8'0'6'8'8'A or I)A A A I I I A I I I I I A A I A A I I A A A A A A A A (Yes or No)No No No No No No No No No No No No No No No No No No No No No No No No No No No (Yes or No)No No No No No No Yes Yes Yes No No Yes Yes No No No No No No No No No No No No No No I[k I fh C;k 1 (w F C r I F't I ll.+t'I t.I t k k II P r II'I C~r r F r-~I r t t r.II It l-F t F I I r t'I I f~~I k t h I 1 I Ir Il I F~-h F t F F'I' TABLE 3.7-2a CONTINUED SAFETY RELATED HYDRAULIC SNUBBERS*FPL LOCATION NO.MARK NO SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ON LOCATION AND ELEVATION-
-INACCESSIBLE HIGH RADIATION ZONE**ESPECIALLY DIFFICULT TO REMOVE 084 086 087 110 111 112 114 091 090 092 093 SI 676-105 SI 676 129 SI 676-2481 SI 676 247 SI 676-2475A SI 676 4505 SI 972-6240 SPS-417 SPS-27 SPS-467 SPS-777 SI, RAB, Elev.4'I, RAB, Elev.4 SI, RAB, Elev.24'I, RAB, Elev.30'I, RAB, Elev.30'I, RAB, Elev.7'I, RAB, Elev.4 Pressurizer Spray, Reactor Bldg.Elev-50'ressurizer Spray, Reactor Bldg.Elev.50'ressurizer Spray, Reactor Bldg.Elev.80 Pressurizer Spray, Reactor Bldg.Elev.80'A or I)A A A A A A A (Yes or No)No No No No No No No No No No No (Yes or No)No No No No No No No No No No No A s~P P II C E~l C<1 l v TABLE 3.7-2a CONTINUED SAFETY RELATED HYDRAULIC SNUBBERS*FPL LOCATION NO.MARK NO.SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION=-
ACCESSIBLE OR INACCESSIBLE HIGH RADIATION ZONE**ESPECIALLY DIFFICULT TO REMOVE 096 CC-1865-9 088 CC-1 899-48 089 CC-1852-6241 1 01 CC-1 7-1 102 MS-649-313 104 CC-21-1 103 BF-549-7 105 CC-23-2 106 CH-3-40 1 07 CH-3-75 1 08 MS-649-313 1 09 MS-649-313 097 MS-649-314 099 MS-649-314 (A or I)CC, Reactor Bldg, Elev.25 CC, Reactor Bldg, Elev.25 CC, Reactor Bldg, Elev.25'C, RAB, Elev.20 CC, RAB, Elev.26'C, RAB, Elev.20'C, RAB, Elev 26'C, RAB, Elev-26 CH, RAB, Elev.34 CH, RAB, Elev-23 MS, Reactor Bldg, Elev-80'S, Reactor Bldg, Kiev-80 MS, Reactor Bldg, Elev-80 MS, Reactor Bldg, Elev-80 (1lAu or llllt)A A A A A A A A A A I I I I (Yes or No)No No No No No No No No No No No No No No No No No No No No No No No No No No No No*Snubbers may be added to or removed from safety related systems without prior License Amendment 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 Table 3.7-2a is included with the next License Amendment request.
C C I (<RC>RC>RC>RC>RC>RC, RC>RC>RC>BF, BP, BF>BP, BF, BP, SI, SI, SI>SI, SI>SI, SI, SI, SI>SI, Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Bldg, Bldg, Bldg, Bldg, Bldg, Bldg, Bldg, Bldg, 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.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Kiev.Elev.Elev.Eleve Elev.Elev.Elev.Elev o Elev.Elev.Elev.Elev.68'8'8'0'0'0'0'0'0'0 80 80'0 50'0'0'0'0 25'0'8 20'8'8'8'8'8'3
.SYSTEM SNUBBER INSTALLED ON LOCATION AND'EL'EVATION!.(A or I)ACCESSIBLE OR INACCESSIBLE (Yes or No)A A A A A A A A A A A A I I I I I I A A A I A A A A A I (Yes or No)NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO HIGH RADIATION ZONE**ESPECIALLY DIFFICULT TO REMOVE NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO
)~n I'5'n~I E<<Il, e t"<e'" c n, n~~SA~y E t n t R n, II I n E's s"'I h~r~h ICE jym Ij I t I-I I e A~L n I t n, S tt E h in E II t E1 E C s~s n TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*FPL LOCATION NO+067 068 069.P 070 071 072 075 078 095 113 094 085 098 100 MARK NO.SI 970-1251 SI 971-6 SI 971-1229 SI 971-6229 SI 971-6236 SI 972-1243 SI 973-6219 SI 868 111 SI 676-127 SI 971-6236 CS-832-118 CS-878 115 CC-1899-2208 CC-1 865-2207 SI, Reactor Bldg, SI, Reactor Bldg, SI, Reactor Bldg, SI, Reactor Bldg, SI, Reactor Bldg, SI, Reactor Bldg, SI, Reactor Bldg, SI, RAB, Elev.4'I, RAB, Elev-4'I, RAB, Elev.4'S, Reactor Bldg, CS, Reactor Bldg, CC, Reactor Bldg, CC, Reactor Bldg, Elev.20 Elev.20 Elev.20'lev.20'lev.20'lev.25'lev.36'lev.125'lev.18'lev.59'lev.59'YSTEM SNUBBER INSTALLED ON LOCATION AND.ELEVATION'CCESSIBLE OR INACCESSIBLE (A or I)A I I I I A I A A A A A A A HIGH RADIATION ZONE**(Yes or No)NO NO NO NO NO NO NO NO NO NO NO No NO NO ESPECIALLY DIFFICULT TO REMOVE (Yes or No)NO NO NO NO NO NO NO NO NO NO YES YES NO NO
~~It tI II t t 4 TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*CA Pl I CO 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 j 1 FPL LOCATION NO.NARK NO.RC164-11 RC162-11 RC-1-221A RC-1-124B 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 NSI-22-3A RC-1-124C NSI-20-3A NSI-16-3A CH-125-35B MSI-14-3A CH-129-339 RC-220-105 RC-217-5 CH 129-339 RC 114-129 RC 221-162 CH-187-38A CH-143-26C CH-141-74 B-2-Hl RC 128-99 CH-143-34C RC-1-25C CH-141-36=C 36'5'1'9'5'9'7'3'5'1'0'7'3'7'9'8'7'0'2'2'2 75'2'8'8'4'7'4'lev.
Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.RC RCB RC RCB RC RCB RC RCB RC RCB RC RCB RC RCB CH RCB RC RCB CH RAB CH RCB CH RCB RC RCB NS RCB RC RCB HS RCB NS RCB CH RCB NS RCB CH RCB RC RCB RC RCB CH RCB RC RCB RC RCB CH RCB CH RCB CH RCB B RCB E RC RCB CH RCB RC RCB CH RCB lev.38'7'7'1'2'l ev.Elev.Elev.Elev.Aor I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ON, LOCATION AND<ELEVATjON,'NACCESSIBLE Yes or No NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO Yes or No NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO HIGH RADIATION ESPECIALLY DIFFICULT ZONE**TO REMOVE C'a.t.I~',.e<<>>e-.5~e~-~I-" 5,-e I~I-I I t I Ir r r F I'*t(5 tt ler 5~
TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*g FPL LOCATION NO.MARK NO.SYSTEM SNUBBER INSTALLED ON, LOCATION AND~zz,pypvyp,'CCESSIBLE OR INACCESSIBLE HIGH RADIATION ESPECIALLY DIFFICULT ZONE**TO REMOVE GO I 148 149 150 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 RC-1-124A MSI-10-3A MSI-8-3A CH 142-17 RC-163-11 RC 165-11 MSI-18-3A RC 128-99 MS I-12-3A RC 219-6B CH 142-18 RC 163-11 CH 142-18 RC 165-11 RC-217-5 SI-69-58 SI-39-6 RC 221-148 RC 164-11 CH-67-81 RC 114-129 RC-44-26 RC 220-112 RC 218-26 RC 44-11 CH 67-81 CH-65-54A RC 220-112 MS I-2-HI RC 222-43 MS I-4-HI RC RCB MS RCB MS RCB CH RCB RC RCB RC RCB MS RCB RC RCB MS RCB RC RCB CH RCB RC RCB CH RCB RC RCB RC RCB SI RCB SI RAB RC RCB RC RCB CH RAB RC RCB RC RCB RC RCB RC RCB RC RCB CH RAB CH RAB RC RCB MS RCB RC RCB MS RCB Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.Elev.17'7'7'1'5'5'7'8'7'1'1'5'1'5'5'2'2'2'6'1'8'0'1'6'5'1'2'2'8'0'8'or I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Yes or No NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO Yes or No NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO I'~5'4 I'J II 4'I TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*FPL LOCATION NO.180 181 182 182 184 185 186 187 188 189 190 191 192 193 194 195 196 197 198 199 200 201 202 MARK NO.RC 220-114 RC 215-9B RC 219-6A MSI-3-Hl RC 218-26 CH-64-45A B-1-H3A SI-69-60B RC 150-H7 SI-69-60 CH-1 41-44A CH-1 41-44A B-3-795 CH 130-66 MSH-7B MPR-200-250 MSH-7A MPR-201-1 6 MPR 200-20 B-21-311 B-21-3110 B-21-3240 CC-1899-2200 RC RCB Elev.71'C RCB Elev.74 RC RCB Elev.73'S RCB Elev.78'C RCB Elev.76'H RAB Elev.30'RCB Elev.38 SI RCB Elev.57'C RCB Elev.50'I RCB Elev.57 CH RCB Elev.32'H RCB Elev.32'RAB Elev.36'H RAB Elev.26 MS Steam Trestle Elev.38'P RCB Elev.34'm Stream Trestle Elev.38'P RCB Elev.35'P RCB Elev.35'-RAB Elev.36 B-RAB Elev.35'-RAB Elev.38'C-RCB Elev.57 SYSTEM SNUBBER INSTALLED ACCESSIBLE OR-ON LOCATION AND ELEVATION.-'NACCESSIBLE (A or I)I I I I I I I I I I I I I I A I A I I A A A I (Yes or No)NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO (Yes or No)NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO HIGH RADIATION ESPECIALLY DIFFICULT ZONE**TO REMOVE*Snubbers may be added to or provided a revision to Table removed from safety related systems without prior License Amendment to Table 3-7-2a 3.7-2a is included with the next License Amendment request.*Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-2a is included with the next License Amendment request.
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'lr~,i)PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Cont1nued) 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 rem or less whole body, or its equivalent and maintaining the chlorine concentration within acceptable limits during and following a chlorine accident This limitat1on 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 ensures 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.3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on sealed source removal contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of 1ngestion or inhalat1on of the probable leakage from the source material.The limitations on removable contaminat1on for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c)11mits for plutonium.
Qualities of interest to this specification which are exempt from 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 more than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.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 1s maintained during and following a seismic 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 safety-related system.The visual inspection frequency is based upon maintaining a constant 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 1nterval has elapsed (nominal time less 25%)may not be used to lengthen the required inspection 1nterval.Any inspection whose results require a shorter inspection 1nterval will override the previous schedule.St.Lucie Unit 1 B 3/4 7-5 4 4 W,r)Wr rp A lt Wr'WI W 4 4 4 hl II 4 W Ih J, AI I AIJ a ,,~, PLANT SYSTEMS BASES 3/4.7'0 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 funct1onal test1ng, that snubber may be exempted from being counted as inoperable.
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 exposed to the same environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an evaluation is performed, in addition to the determinat1on 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 component or system.To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant 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 identified, additional snubbers, having a high probability for the same type failure or that are being used in the same applicat1on that caused the failure, shall be teted.This requirement increases the probability of locating inoperable snubbers without testing 100%of the snubbers.Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).The requirement to monitor the snubber service life is 1ncluded to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records w111 provide statistical bases for future consideration of snubber service life.The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7'1 PIRE 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 1 B 3/4 7-6 tl 4 I<<4 I l 4 IH, II v'l>4'lit>e, 4 Il I 4 I>~I>I<<'I<<>r>~H 4 I,'be,l>e.~I'lr 4 4 JI v e 4 4 4
, PLANT SYSTEMS BASES 3 4.7.11 PIRE SUPPRESSION SYSTEHS Continued located.The fire suppression system consists of the water system and fire hose stations.The collective capability of the fre suppression systems is adequate to minimize potential damage to saf ety related equipment and is a ma)or element in the facility fire protection program.In the event that portions of the f ire suppression sys tems are inoperable, alternate backup f ire f ighting equ1pment is required to be made available in the affecred areas until the inoperable equipment is restored to service.In the event the fire suppression water system becomes inoperable, 1mmediate corrective measures must be taken since th1s system provides the major fire suppression capability of the plant.The requirements for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.~34~7.12 PENETRATION PIRE BARRIERS The f unctional integrity of the penetration f ire barreirs ensures that f ires will be conf ined or adeauately retarded f rom spreading to adjancent portions of the facility.This design feature minimizes the possibility of a sngle fire rapidly involving several areas of the faclity prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are sub5ect to periodic inspections.
During periods of time when the barriers are not intact, routine fire watch patrols in conjunction with OPERABLE fire detection instrumentation or a continuous fire watch are required to be maintained in the vicinity of the affected barrier until the barrier is restored to 1ntact status.St-Lucie Unit 1 B 3/4 7-7 l)II f I g ll II lb lb Ot~i4'ADMINISTRATIVE CONTROLS e.Records of gaseous and liquid radioactive material released to the environs.f~Records of transient or operational cycles for those facility components identified in Table 5.9-1~g.Records of training and qualification for current members of the plant staff.h.Records of in-service inpsections performed pusuant to these Technical Specifications.
Records of Quality Assurance activities required by the QA Manual.Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 20 CFR 50.59.k Records of meetings of the PRG and the CNRB.l.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 life commences and associated installation and maintenance records.6+11'ADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the rquirements of 10 CPR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.6.12 HIGH RADIATION AREA 6.12.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c)(2)of 10CPR 20: aO b.A High Radiation Area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provid'ed with a radiation monitoring device which continuously indicates the radiation dose rate in the area.A High Radiation Area in which the intensity of radiation is greater than 1000 mrem/hr shall be subject to the provisions of 6.12.1.a above, and in addition locked doors sall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift supervisor on duty.St.Lucie Unit 1 6-20
'f4, II O'ZATE OF FLORXDA))COUNTY OF DADE)ss Robert E.Uhrig, being f irs t duly sworn, deposes and says: That he is a Vice President.
of Florida Power a Light Company, the Licensee herein;That: he has executed the foregoing document;that the state-ments made in this said document are true, and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.Robert E.Uhrig Subscribed and ssvorn to before me this'l~Bay of NOTARY PUBLXC, in and for the county of Dade, State of Florida NOTARY PUBUC STATE 0 FhOR<OA st tAIKj-MY COMMISSION EXPIRES AUGUST 24'%1 QONOXO THRU NAYNARO 8 ONOtNG AGENCY l1y commission expires:
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