ML17209B061

Proposed Tech Specs Re Surveillance Requirements & Listing of Mechanical Snubbers

ML17209B061
Person / Time
Site:	Saint Lucie
Issue date:	05/11/1981
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17209B060	List: ML17209B059 ML17209B061
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 Subsequent Visual er Ins ection Period Ins ection Period*8 0 18 months + 25X 1 12 months + 25X 2 6 months + 25%

3,4 123 days + 25%

576,7 62 days + 25%

8 or more 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

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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

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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 MARK SISTER SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIPPICULT NO NO. ON LOCATION AND.SENSATION. t INACCESSIBLE ZONE** TO REMOVE (A or I) (Yes or No) (Yes or No) 001 SS-1 1A MS, Steam Gen. 1A, Evel. 62 I No Yes 002 SS-2 1A MS, Steam Gen. 1A, Evel. 62 I No Yes 003 SS-3 1A MS, Steam Gen. 1A, Evel. 62 I No Yes 004 SS4 1A MS, Steam Gen. 1A, Evel. 62 I No Yes 005 SS-5 1A MS, Steam Gen. 1A, Evel. 62'2 I No Yes 006 SS-6 1A MS, Steam Gen. 1A, Evel- I No Yes 007 SS-7 1A MS, Steam Gen- 1A, Evel. 62'2 I No Yes 008 SS-8 1A MS, Steam Gen. 1A, Evel. I No Yes 009 SS-1 1B MS, Steam Gen. 1B, Elev. 62 I No Yes 010 SS-2 1B MS, Steam Gen. 1B, Elev. 62'2 I No Yes 011 SS-3 1B MS, Steam Gen. 1B, Elev. I No Yes 012 SS-4 1B MS, Steam Gen. 1B, Elev. 62 I No Yes

. 013 SS-5 1B MS, Steam Gen. 1B, Elev. 62 I No Yes 014 SS-6 1B MS, Steam Gen. 1B, Elev o 62 I No Yes 015 SS-7 1B MS, Steam Gen. 1B, Elev. 62 I No Yes 016 SS-8 1B MS, Steam Gen. 1B, Elev. 62 I No Yes 017 1A1 RC, RCP Motor lA1, Elev. 57 I No No 018 lA2 RC, RCP Motor lA1, Elev. 57 I No No 019 1B1 RC, RCP Motor lA1, Elev. 57 I No No 020 1B2 RC, RCP Motor lAl, Elev- 57 I No No

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TABLE 3.7-2a CONTINUED SAFETY RELATED HYDRAULIC SNUBBERS*

PPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO ON LOCATION ANDi ELEVATION',: INACCESSIBLE ZONE** TO REMOVE or I) (Yes or No) (Yes or No) 033 MS 649-319 MS> Reactor Bldg. 82'2 A No No 034 MS 548-5 MS, Reactor Bldg. Elev. A No No 035 MS 1076-3164 MS> M-S. Trestle, Elev. 62 A No No 036 MS 649-314 MS, Reactor Bldg. Elev. I No No 037 MS 649-314 MS> Reactor Bldg. Elev. I No No 038 MS 649-310 MS, Reactor Bldg. Elev. 55'2'0'0'0'0 I No No 039 MS 649-304A MS> Reactor Bldg. Elev. A No Yes 040 MS 548-9 MS, Reactor Bldg. Elev- I No Yes 041 MS 548-9 MS> Reactor Bldg.

4'lev.Elev. I No Yes 042 BP 549-7 BP, Reactor Bldg. Elev. 40 I No No 043 BF 549-7 BF, Reactor Bldg. Elev. I No No 044 BP 549-8 BP, Reactor Bldg. Eleve 40'0'6'6 I No Yes 047 BP 549-17 BP, Reactor Bldg. Elev. A No Yes 052 BF 549-17 BP, Reactor Bldg. Elev. A No No 053 SI 968210 SI> Reactor Bldg. Elev. I No No 058 SI 969 1216 SI, Reactor Bldg. Elev. 16'8'8'0'6'8'8'A A No No 061 MS 549-11 SI> Reactor Bldg. Elev. A No No 066 MS 549-11 SI, Reactor Bldg. Elev. I No No 073 SI 972-6240 SI> Reactor Bldg. Elev. I No No 074 SI 973-240 SI, Reactor Bldg. Elev. A No No 076 SI 973-6224 SI> Reactor Bldg. Elev. A No No 077 SI 868 64 SI> RAB, Elev. A No No 079 SI 868-163 SI> Elev- 4'AB, A No No 080 SI 868-410 SI, Elev. 4'AB, A No No 081 SI 676-67 SI, Elev- 4'AB, A No No 082 SI 676-67 SI> Elev. 4'AB, A No No 083 SI 676-105 SI, Elev. 4'AB, A No No

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TABLE 3.7-2a CONTINUED SAFETY RELATED HYDRAULIC SNUBBERS*

FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO ON LOCATION AND ELEVATION- INACCESSIBLE ZONE** TO REMOVE or I) (Yes or No) (Yes or No) 084 SI 676-105 SI, RAB, Elev. A No No SI Elev. 4 4'I, 086 676 129 RAB, A No No 087 SI 676-2481 SI, RAB, Elev. A No No Elev.

24'I, 110 SI 676 247 RAB, A No No Elev.

30'I, 111 SI 676-2475A RAB, A No No Elev.

30'I, 112 SI 676 4505 RAB, A No No 114 SI 972-6240 Elev. 4 7'I, RAB, A No No Pressurizer Spray, Reactor 80'A 091 SPS-417 Bldg. Elev- No No 090 SPS-27 Spray, Reactor 50'ressurizer Bldg. Elev. No No 092 SPS-467 Spray, Reactor 50'ressurizer Bldg. Elev. 80 No No 093 SPS-777 Pressurizer Spray, Reactor Bldg. Elev. No No

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TABLE 3.7-2a CONTINUED SAFETY RELATED HYDRAULIC SNUBBERS*

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) (1lAu or llllt) (Yes or No) 096 CC-1865-9 CC, Reactor Bldg, Elev. 25 A No No 088 CC-1 899-48 CC, Reactor Bldg, Elev. 25 A No No 089 CC-1852-6241 CC, Reactor Bldg, Elev. A No No RAB, Elev. 20 25'C, 1 01 CC-1 7-1 A No No 102 MS-649-313 CC, RAB, Elev. A No No RAB, Elev.

26'C, 104 CC-21-1 A No No RAB, Elev 20'C, 103 BF-549-7 A No No RAB, Elev- 26 26'C, 105 CC-23-2 A No No 106 CH-3-40 CH, RAB, Elev. 34 A No No 1 07 CH-3-75 CH, RAB, Elev- 23 A No No 1 08 MS-649-313 MS, Reactor Bldg, Elev- I No No 1 09 MS-649-313 Reactor Bldg, Kiev- 80 80'S, I No No 097 MS-649-314 MS, Reactor Bldg, Elev- 80 I No No 099 MS-649-314 MS, Reactor Bldg, Elev- 80 I 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-

• ~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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TABLE 3 7-2b SAPETY RELATED MECHANICAL SNUBBERS*

C FPL LOCATION MA.RK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT g NO. NO. ON LOCATION AND'EL'EVATION!. INACCESSIBLE ZONE** TO REMOVE ft (A or I) (Yes or No) (Yes or No) 021 RC 005-34A RC, Reactor Bldg, Elev. A NO NO 022 RC 005-34B RC, Reactor Bldg, Elev- A NO NO 023 RC 005-36 RC> Reactor Bldg, Elev. A NO NO 025 RC 005-12B RC> Reactor Bldg, Elev. A NO NO 026 RC 005-12B RC> Reactor Bldg, Elev. 68'8'8'0'0'0'0'0'0'0 A NO NO 024 RC 005-12A RC> Reactor Bldg, Elev. A NO NO 028 RC 005-55C RC> Reactor Bldg, Elev. A NO NO 027 RC 005-55B RC> Reactor Bldg, Elev. A NO NO 029 RC 005-62A RC, Reactor Bldg, Elev. A NO NO 030 RC 005-89 RC> Reactor Bldg, Elev. A NO NO 031 RC 005-90 RC> Reactor Bldg, Elev. 80 A NO NO 032 RC 005-98 RC> Reactor Bldg, Elev. 80'0 A NO NO 045 BP 549-11 BF, Reactor Bldg- Elev. I NO NO 046 BF 549-11 BP, Reactor Bldg. Elev. I NO NO 048 BP 661-407 BF> Reactor Bldg. Elev. I NO NO 049 BF 6610407 BP, Reactor Bldg. Elev.

50'0'0'0'0 I NO NO 050 BP 661-416 BF, Reactor Bldg. Kiev. I NO NO 051 BP 661-416 BP, Reactor Bldg. Elev. I NO NO 054 SI 968-565 SI, Reactor Bldg- Elev. 25'0'8 A NO NO 055 SI 989 1205 SI, Reactor Bldg. Eleve A NO NO 056 SI 968-1207 SI> Reactor Bldg, Elev. A NO NO 057 SI 969-1190 SI, Reactor Bldg, Elev. I NO NO 059 SI 969-6193 SI> Reactor Bldg, Elev. A NO NO 060 SI 969 6195 SI, Reactor Bldg, Elev o 20'8'8'8'8'8'3 A NO NO 062 SI 969-6201 SI, Reactor Bldg, Elev. A NO NO 063 SI 696-6217 SI, Reactor Bldg, Elev. A NO NO 064 SI-696-6217 SI> Reactor Bldg, Elev. A NO NO 065 SI-970-1 210 SI, Reactor Bldg, Elev. . I NO NO

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TABLE 3. 7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*

FPL LOCATION MARK SNUBBER INSTALLED OR HIGH RADIATION ESPECIALLY DIFFICULT

.ELEVATION'CCESSIBLE INACCESSIBLE ZONE** TO REMOVE NO+ NO. ON LOCATION AND (A or I) (Yes or No) (Yes or No) 067 SI 970-1251 SI, Reactor Bldg, Elev. 20 A NO NO 068 SI 971-6 SI, Reactor Bldg, Elev. 20 I NO NO 069 SI 971-1229 SI, Reactor Bldg, Elev. I NO NO

.P 070 SI 971-6229 SI, Reactor Bldg, 20'lev.

I NO NO I

59'YSTEM SI 971-6236 SI, Reactor Bldg, 20'lev.

071 NO NO SI 972-1243 SI, Reactor Bldg, A 20'lev.

072 NO NO 075 SI 973-6219 SI, Reactor Bldg, 25'lev.

I NO NO 078 SI 868 111 SI, RAB, Elev. A NO NO RAB, Elev-4'I, 095 SI 676-127 36'lev.

A NO NO SI 971-6236 RAB, Elev. A 4'I, 113 NO NO CS-832-118 Reactor Bldg, 4'S, 094 A NO YES Reactor Bldg, 125'lev.

085 CS-878 115 CS, A No YES CC-1899-2208 Reactor Bldg, A 18'lev.

098 CC, NO NO 100 CC-1 865-2207 CC, Reactor Bldg, 59'lev.

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TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*

j 1 FPL LOCATION NARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON, LOCATION AND <ELEVATjON,'NACCESSIBLE ZONE** TO REMOVE Aor I Yes or No Yes or No 115 RC164-11 RC RCB I NO NO 116 RC162-11 RC RCB Elev. I NO NO 117 RC-1-221A RC RCB Elev. I NO NO 118 RC-1-124B RC RCB Elev. I NO NO CA 119 RC162-11 RC RCB Elev. I NO NO 120 RC-1-192A RC RCB Elev. I NO NO 121 RC-5-475 RC RCB Elev. I NO NO 122 CH-129-99 CH RCB Elev. I NO NO Pl 123 RC-217-5 RC RCB Elev. I NO NO 124 CH-65-54C CH RAB Elev. I NO NO I

36'5'1'9'5'9'7'3'5'1'0'7'3'7'9'8'7'0'2'2'2 125 CH-142-9 CH RCB Elev. NO NO 126 CH143-30C CH RCB Elev. I NO NO 127 RC-215-9A RC RCB Elev. I NO NO 128 NSI-22-3A NS RCB Elev. I NO NO 129 RC-1-124C RC RCB Elev. I NO NO 130 NSI-20-3A HS RCB Elev. I NO NO 131 NSI-16-3A NS RCB Elev. I NO NO 132 CH-125-35B CH RCB Elev. I NO NO I

133 MSI-14-3A NS RCB Elev. I NO NO CO 134 CH-129-339 CH RCB Elev. 75'2'8'8'4'7'4'lev.

I NO NO 135 RC-220-105 RC RCB Elev. I NO NO 136 RC-217-5 RC RCB Elev. I NO NO 137 CH 129-339 CH RCB Elev. I NO NO 138 RC 114-129 RC RCB Elev. I NO NO 139 RC 221-162 RC RCB Elev. I NO NO 140 CH-187-38A CH RCB Elev. I NO NO 141 CH-143-26C CH RCB Elev. I NO NO 142 CH-141-74 CH RCB Elev. I NO NO 143 B-2-Hl B RCB E lev. I NO NO 144 RC 128-99 RC RCB ev. I NO NO 145 CH-143-34C CH RCB Elev. 38'7'7'1'2'l I NO NO 146 RC-1-25C RC RCB Elev. I NO NO 147 CH-141-36=C CH RCB Elev. I NO NO

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TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*

g FPL LOCATION MARK SYSTEM SNUBBER INSTALLED OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON, LOCATION AND

~zz,pypvyp,'CCESSIBLE INACCESSIBLE ZONE** TO REMOVE I Yes or No Yes or No 148 RC-1-124A RC RCB Elev. I NO NO 149 MSI-10-3A MS RCB Elev. I NO NO 150 MSI-8-3A MS RCB Elev. I NO NO 151 CH 142-17 CH RCB Elev. I NO NO 152 RC-163-11 RC RCB Elev. I NO NO 153 RC 165-11 RC RCB Elev. I NO NO 154 MSI-18-3A MS RCB Elev. I NO NO 155 RC 128-99 RC RCB Elev. I NO NO 156 MS I-12-3A MS RCB Elev. I NO NO 157 RC 219-6B RC RCB Elev. I NO NO 158 CH 142-18 CH RCB Elev. I NO NO 159 RC 163-11 RC RCB Elev. I NO NO 160 CH 142-18 CH RCB Elev. I NO NO 161 RC 165-11 RC RCB Elev. I NO NO 162 RC-217-5 RC RCB 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'orI NO NO GO 163 SI-69-58 SI RCB Elev. I NO NO 164 SI-39-6 SI RAB Elev. I NO NO 165 RC 221-148 RC RCB Elev. I NO NO I 166 RC 164-11 RC RCB Elev. I NO NO 167 CH-67-81 CH RAB Elev. I NO NO 168 RC 114-129 RC RCB Elev. I NO NO 169 RC-44-26 RC RCB Elev. I NO NO 170 RC 220-112 RC RCB Elev. I NO NO 171 RC 218-26 RC RCB Elev. I NO NO 172 RC 44-11 RC RCB Elev. I NO NO 173 CH 67-81 CH RAB Elev. I NO NO 174 CH-65-54A CH RAB Elev. I NO NO 175 RC 220-112 RC RCB Elev. I NO NO 176 MS I-2-HI MS RCB Elev. I NO NO 177 RC 222-43 RC RCB Elev. I NO NO 178 MS I-4-HI MS RCB Elev. I NO NO

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TABLE 3.7-2b CONTINUED SAFETY RELATED MECHANICAL SNUBBERS*

FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR- HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEVATION.-'NACCESSIBLE ZONE** TO REMOVE (A or I) (Yes or No) (Yes or No) 180 RC 220-114 RC RCB Elev. I NO NO I

71'C 181 RC 215-9B RCB Elev. 74 NO NO 182 RC 219-6A RC RCB Elev. I NO NO I

73'S 182 MSI-3-Hl RCB Elev. NO NO I

78'C 184 RC 218-26 RCB Elev. NO NO I

76'H 185 CH-64-45A RAB Elev. 30' NO NO 186 B-1-H3A RCB Elev. 38 I NO NO 187 SI-69 -60B SI RCB Elev. I NO NO I

57'C 188 RC 150-H7 RCB Elev. NO NO I

50'I 189 SI-69-60 RCB Elev. 57 NO NO 190 CH-1 41-44A CH RCB Elev. I NO NO I

32'H 191 CH-1 41-44A RCB Elev. 32' NO NO 192 B-3-795 RAB Elev. I NO NO I

36'H 193 CH 130-66 RAB Elev. 26 NO NO 194 MSH-7B MS Steam Trestle Elev. A NO NO I

38'P 195 MPR-200-250 RCB Elev. 34'm NO NO 196 MSH-7A Stream Trestle Elev. A NO NO I

38'P 197 MPR-201-1 6 RCB Elev. NO NO I

35'P 198 MPR 200-20 RCB Elev. NO NO 199 B-21-311 Elev. 36 35'-RAB A NO NO 200 B-21-3110 B-RAB Elev. A NO NO 201 B-21-3240 Elev. 35'-RAB A NO NO 202 CC-1899-2200 Elev. 57 38'C-RCB I 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.

• 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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~,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

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,, ~, 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

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, 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

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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 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.

b. 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

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O'ZATE OF FLORXDA )

) ss COUNTY OF DADE )

Robert E. Uhrig, being firs 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

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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 l1y commission expires: QONOXO THRU NAYNARO 8 ONOtNG AGENCY

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