ML17345B225
| ML17345B225 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/19/1983 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17345B224 | List: |
| References | |
| NUDOCS 8308230372 | |
| Download: ML17345B225 (42) | |
Text
Section TABLE OF CONTENTS (Continued)
Title
~Pa e
3.0 3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.10 3.15 0.0 0.1 0.2 0.3 0.5 0.6
'.7 0.8.
0.9 Engineering Safety Features Safety Injection and RHR Systems Emergency Containment Cooling Systems Emergency Containment Filtering System Component Cooling System Intake Cooling Water System Post Accident Containment Vent System Control.Room Ventilation
~ Instrumentation Chemical.and Volume Control System Electrical Systems Steam Power Conversion Systems Radioactive Materials Release Liquid Wastes Gaseous Wastes Containerized Wastes Refueling Miscellaneous Radioactive Materials Sources Cask Handling Snubbers Fire Protection Systems Overpressure Mitigating System SURVEILLANCEREQUIREMENTS Operational Safety Review Reactor Coolant System In Service Inspection Reactor Coolant System Integrity Containment Tests Integrated Leakage Rate Test - Post Operational Local Penetration Tests Report of Test Results Isolation Valves Residual Heat Removal System Tendon Surveillance End Anchorage Concrete Surveillance Liner Surveillance Safety Injection Emergency Containment Cooling Systems Emergency Containment Filtering and Post Accident Containment Vent Systems Emergency Power System Periodic Tests Main Steam Isolation Valves 3.0-1 3.0-1 3.0-3 3.0-0 3.0-0a 3.0-5 3.4-6 3.0-6 3.5-1 3.6-1 3.7-1 3.8-1 3.9-1 3.9-1 3.9-3 3.9-5
.3.10-1 3.11-'1 3.12-1 3.13-1 3.14-1 3.15-1 O. 1-1 0.1-1 0.2-1 0.3-1 0.0-1 0A-2 0.0-2 0.0-3 0.0-3 4.0-6 0A-7
-0.5-1 0.6-1 0.7-1 0.8-1 0.9-1 8308230372 830819 PDR ADOCK 05000250 PDR ll
0 I
t'
Section 0.10 0.11 0.12 0.13 0.10 0.15 0.16
, 5.0 5.1 5.2 5.3 5.0 6.0 6.1 6.2 6.3 6.0 6.5 6.6
.6.7 6.3 6.9 6.10 6.11 6.12 6.13 B2.1 B2.2
.B2.3 B3.1 B3.2 B3.3 B3.0 TABLE OF CONTENTS (Continued)
Title Auxiliary Feedwater System Reactivity Anomalies Environmental Radiation Survey Radioactive Materials Sources Surveillance Snubbers Fire Protection Systems Overpressure Mitigating System DESIGN FEATURES Site'eactor Containment Fuel Storage ADMINISTRATIVECONTROLS Responsibility Organization Facility Staff Qualifications Training Review and Audit Reportabie Occurrence. Action Safety Limit Violation Procedures Reporting Requirements Record Retention Radiation Protection Program High Radiation Area Environmental Qualification Bases for Safety Limit, Reactor Core Bases for Safety Limit, Reactor Coolant System Pressure Bases for Limiting Safety System Settings, Protective Instrumentation Bases for Limiting Conditions for Operation, Reactor Coolant System Bases for Limiting Conditions for Operation, Control and Power Distribution Limits Bases for Limiting Conditions for Operation, Containment Bases for Limiting Conditions for Operation, Engineered Safety Features
~Pa e
0.10-1 0.11-1 0.12-1 0.13-1 0.10-1 0.15-1 0.16-1 5.1-1 5.1-1 5.2-.1 5.3-1 5.0-1, 6-1 6-1 6-1 6-5 6-5 6-6 6-10 6-10 6-10 6-16 6-27 6-29 6-29 6-30 B2.1-1 B2.2-1 B2.3-1 B3.1-1 B3.2-1 B3.3-1 B3.0-1
0
Section 0
TABLE OF CONTENTS (Continued)
Title
~Pa e
B3.5 B3.6 B3.7 B3.8 B3.9 B3.10 B3.11 B3.12 B3.13, B3.10 B3.15 B0.1 B0.2 B0.3 BQ.O B0.5
~B0.6 B0.7 B0.8
.B0.9 B0.10 B0.11 B0.12 B0.13 B0.10 B0.15 Bases for Limiting Conditions for Operation, Instrumentation Bases for Limiting Conditions for Operation, Chemical and Volume Control System Bases for Limiting Conditions for Operation, Electrical Systems Bases for Lirqiting Conditions for Operation, Steam and:Power Conversion Systems
- Bases for'Limiting Conditions for Operation, Radi'oactive Materials Release Bases for Limiting Conditions'for Operation, Refueling Bases for Limiting Conditions for Operation, Miscellaneous Radioactive Material Sources Bases for Limiting Conditions for Operation, Cask Handling Bases for Limiting Conditions for Operation, Snubbers Bases for Fire Protection System Bases for Limiting Conditions of Operation, Overpressure Mitigating System Bases for Operational Safety Review Bases for Reactor Coolant System In-Service Inspection Bases for Reactor Coolant System Integrity Bases for Containment Tests Bases for Safety Injection Tests Bases for Emergency Containment Cooling System Tests Bases for Emergency Containment Filtering andi Post Accident Containment Venting Systems Tests Bases for Emergency Power System Periodic Tests Bases for Main Steam Isolation Valve Tests Bases for Auxiliary Feedwater System Tests Bases for Reactivity Anomalies Bases for Environmental Radiation Survey Bases for Fire Protection Systems Bases for Snubbers Bases for Surveillance Requirements, Overpressure Mitigating System B3.5-1 B3.6-1 B3.7-1 B3.8-1 B3.9-1 B3.10-1 B3.11-1 B3.12'-1 B3.13-1 B3.10-1 B3.15-1 B0.1-1 B4.2-1 B0.3-1 B0.0-1 B0.5-1 B0.6-1 B0.7-1 B0.8-1 B0.9-1 B0.10-1 B0.11-1 B0.12-1 B0.13-1 B0.10-1 B0.15-1
0 0
3.13 SNUBBERS
~Ob ective:
To define the LIMITINGCONDITIONS FOR OPERATION applied to the
-. OPERABILITYof safety-related snubbers.
I 4
REFUELING SHUTDOWN, all safety-related snubbers listed in Table 3.13-1 shall be OPERABLE except as noted in 3.13.2 and 3.13.3.
2.
During COLD SHUTDOWN and REFUELING SHUTDOWN, all safety-related snubbers listed in Table 3.13-1 located on systems required to be OPERABLE, shall be OPERABLE except as noted in 3.13.3.
3.
With one or more safety-related snubber(s) 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 and perform an evaluation per T.S., 0.10.3 on the supported component(s) or declare the supported system inoperable and follow
, the appropriate specifications for that system.
0.
Snubbers may be added to or removed from SAFETY RELATED SYSTEMS without prior License Amendment to Table 3.13-1 provided that a revision to Table 3.13-1 is included with the next License Amendment request.
.3.13-1
0 0
TABLE 3.13-1 SHEET 1
SAFETY RELATED SNUBBERS - UNIT 3 FPL TAG NO.
SYSTEM APPROXIMATE ELEVATION (FEET)
SNUBBERS SNUBBERS IN HIGH ESPECIALLY RADIATIONAREAS DIFFICULTTO URING SHUTDOWN" REMOVE SNUBBERS INACCESSIBLE URING NORMAL OPERATION SNUBBERS ACCESSIBLE DURING NORMAL OPERATION 1
2 3
5 6'
8 9
10 ll 12 13 Charging Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer
,Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Spray Spray Spray Spray Spray Spray Spray Spray Spray Spray Spray Spray Relief
~
~
10 10 10 10 10 10 10 10 10 70b X
X X
X X
X X
X X
X 15 16 17 Pressurizer Relief Pressurizer Relief Pressurizer Relief 70Yi 70b 73 X
X X
X X
19 20 21 22 23 20 Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Spray Spray Spray Spray Spray Spray Relief 73 73 73 73 73 73 73 X
X X
X X
X X
FPL TAG NO.
SYSTEM TABLE3.13-1 SHEET 2 SAFETY RELATED SNUBBERS - UNIT 3 SNUBBERS APPROXIMATE SNUBBERS IN HIGH ESPECIALLY ELEVATION RADIATIONAREAS DIFFICULT TO (FEET)
DURING SHUTDOWN+
REMOVE SNUBBERS INACCESSIBLE DURING NORMAL OPERATION SNUBBERS ACCESSIBLE DURING NORMAL OPERATION 25 26 27 28 29 30 31 32 33 30 35 36 37 38 39 00 07 08 Pressurizer Relief Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Relief Pressurizer Relief 3A S/G Blowdown in Cubicle 3A S/G Blowdown in Cubicle 3A S/G Blowdown in Cubicle 3C S/G Blowdown in'Cubicle 3C S/G Blowdown in Cubicle 3C S/G Blowdown in Cubicle
.I, Residual Heat Removal Residual Heat Removal Residual Heat Removal Residual Heat Removal Safety Injection l
Residual Heat Removal Safety Injection Safety Injection Steam to Aux. Feedwater Steam to Aux. Feedwater Steam to Aux. Feedwater 73 73 73 73 73 73 73 32 32 32 33 33 21 2
12 12 12 12 26 26 26 X
X X
X X
X X
X X
X x ~
~ X
0
FPL TAG NO.
50 51 60 61 76 76 77 78 SYSTEM Steam to Aux. Feedwater Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam TABLE 3.13-1 SHEET 3 SAFETY RELATED SNUBBERS - UNIT 3 SNUBBERS APPROXIMATE SNUBBERS IN HIGH ESPECIALLY ELEVATION RADIATIONAREAS DIFFICULTTO (FEET)
'URING SHUTDOWN" REMOVE 305 32 32 32 32 32 32 32 32 SNUBBERS INACCESSIBLE URING NORMAL OPERATION SNUBBERS ACCESSIBLE DURING NORMAL OPERATION X
X X
x X
.X X
X X
79 80 81 82 83 85 86 87 88 89 90 91 92
93 90 Feed water Feed water Feed water Feed water Feedwater Feedwater Feed water Feed water Feed water Feedwater Feed water Feed water Feedwater A RTD Loop Cold Leg A RTD Loop Hot Leg 3C Mainsteam Line 58 56 52 52 58 55 55 58 56
'58 55 25 27 59 X
X X
X X
X X
X X
X X
0 0
1
TABLE3.13-1 SHEET 0 SAFETY RELATED SNUBBERS UNIT 0 FPL TAG NO.
Feedwater Feedwater SYSTEM APPROXIMATE ELEVATION (FEET) 30 30 SNUBBERS IN HIGH RADIATIONAREAS DURING SHUTDOWN+
SNUBBERS SNUBBERS SNUBBERS ESPECIALLY INACCESSIBLE ACCESSIBLE DIFFICULT TO DURING NORMAL DURING NORMAL REMOVE OPERATION OPERATION X
X 10 12 13 10 15 16 17 18 19 20 21 22 23 25 26 27 28'9 Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Charging Feed water Feedwater Feed water Feedwater Feed water Feed water Pressurizer Relief Pressurizer Relief Pressurizer Relief Pressurizer Relief Pressurizer Relief Pressurizer Spray 10 10 10 10 58 58 58 58 58 58 73 73 73 73 73 73 X
X X
X X
X X
X X
X X
X X
X X
X X
X X
X
TABLE 3.13-1 SHEET 5 SAFETY RELATED SNUBBERS - UNIT 0 FPL TAG NO.
30 31 32 30 35 36 37 38 39 00 01 02 03 00 05 06 07 08 09 50 51 52 53'0 SYSTEM Pressurizer Spray Pressurizer Relief Pressurizer Relief Pressurizer Pressurizer
'ressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Pressurizer Spray Spray Spray Spray Spray Spray Spray Spray Relief Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray Pressurizer Spray 4
Residual Heat Removal Residual Heat Removal Residual Heat Removal Residual Heat Removal Residual Heat Removal Safety Injection APPROXIMATE ELEVATION (FEET) 73 73 73 73 73 73 73 73 73 73 73 73 10 10 10 10 10 2
2 12 SNUBBERS IN HIGH RADIATIONAREAS DURING SHVTDO)VN+
X SNUBBERS ESPECIALLY DIFFICULTTO REMOVE SNUBBERS INACCESSIBLE URING NORMAL OPERATION X
X X
X X
X X
SNUBBERS ACCESSIBLE DURING NORMAL OPERATION X
X X
X
0
FPL TAG NO.
55 57 58 59 60 80 81 86 89 SYSTEM Safety Injection Main Steam Main Steam Main Steam Main Steam Feed water Feed water Feedwater Main Steam Main Steam Main Steam Main Steam "A"RTD Loop "A"RTD Loop "A"RTD Loop TABLE 3.13-1 SHEET 6
,SAFETY RELATED SNUBBERS UNIT 0 SNUBBERS APPROXIMATE SNUBBERS IN I-IIGH ESPECIALLY ELEVATION RADIATIONAREAS DIFFICULT TO (FEET)
DURING SHUTDOWN+
REMOVE 12 32 32 32 32 56 56 56 32 32 32 32 25 23 26 SNUBBERS INACCESSIBLE URING NORMAL OPERATION X
X X
SNUBBERS ACCESSIBLE DURING NORMAL OPERATION X
X X
x
~
X X
90 91 92 93 96 97
'98 "C" RTD Loop "C" RTD Loop "B" RTD Loop "B" RTD Loop "B" RTD Loop IIBII RTD I oop "B" RCP Seal Injection "A"RCP Seal Injection MSRV M.S. Platform 27 29 21 27 27 27 20 28 62 X
X X
X X
41
FPL TAG NO.
SYSTEM TABLE 3.13-1 SHEET 7 SAFETY RELATED SNUBBERS UNIT ii SNUBBERS APPROXIMATE SNUBBERS IN HIGH ESPECIALLY ELEVATION RADIATIONAREAS DIFFICULTTO (FEET)
'URING SHUTDOWN>>
REMOVE SNUBBERS INACCESSIBLE DURING NORMAL OPERATION SNUBBERS ACCESSIBLE DURING NORMAL OPERATION 99 100 101 102 103 400 105 106 107 108 109 110 ill 112 113 110 115 117 Aux Bldg: SIS Pump Room Aux Bldg: SIS Pump Room Aux Bldg: HCV 0-758 Aux Bldg: FE 0-605 Aux Bldg: FE 0-605 "A'-'CS Loop Near S.G.
A<<S G Blowdown Line "B" S.G. Blowdown Line "B" S.G. Blowdown Line "C" S.G. Blowdown Line "C" S.G. Blowdown Line "C" S.G. Blowdown Line I
"C" S.G. Blowdown Line l,
"C" S.G. Blowdown Line FW Recirc.
Cond Storage Tank AFW Suppl Cond Storage Tank 'AFW Suppl "C" S.G. Blowdown Lirie'7 27 19 16 30 33 21.5 23 33 00 00 33 28 28 33 X
X X
X X
X x ~
+ Modifications to this column due to changes in high radiation areas may be without prior License Amendment provided that a revision to Table 3.13-1 is included with the next License Amendment request.
0.10 SNUBBERS
~Did'eCtiVe:
To verify OPERABILITYof safety-related snubbers listed in Table 3.13-1
= by performance of the'following augmented inservice inspection program.
tI For each unit, the first inservice visual inspection of snubbers after approval of this amendment shall be performed during the next refueling and shall include all snubbers listed in Table 3.13-1.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection for each unit, the second inservice visual inspection shall be performed 12 months
+25% from, the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
Number Inoperable Snubbers er Ins ection Period er Unit Subsequent Yisual Ins ection Period+/i'
',0 5, 6, 7 3 or more 18 months + 25%
12 months + 25%
6 months + 25%
120 days + 25%
62 days + 25%
31 days+ 25%
Those 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 lenthened more than one step at a time.
P/ The provisions of T.S. 0.0.1 are not applicable.
0.10-1
2.
Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of 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 OPER'ABLE 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 (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 0.10.0.
3.
Functional Tests For each unit, at least once per 18 months during SHUTDOWN, a representative sample (1096 of the snubbers for the respective unit listed in Table 3-13-1) 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 0.10.0, an additional 1096 of that type of snubber shall be functionally tested until no
'more failures are found or until all these snubbers on that unit have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.
At least 2596 of the snubbers in the representative sample shall include snubbers from the following three categories:
A. The first snubber supporting main RCS piping downstream of reactor vessel nozzles.
B.
Snubbers within 5 feet of heavy equipment (ex. valves,
- pumps, turbines, motors, etc.)-
C. Snubbers within 10 feet of the discharge from a safety relief valve.
4.10-2
Ol
Snubbers identified in Table 3.13-1 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included'in the representative sample.+
In addition to the regular sample, snubbers which failed the previous
. functional test, shall be retested during the next test period.
If a 1
"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 may not be included for the re-sampling.
If any snubber selected for functional testing either fails to activate or fails to move, i.e., frozen in place, the cause will be evaluated under the provisions of 10 CFR Part 21.
Should the results of the evaluation indicate that the failure was caused by either manufacturer or design deficiency, further action shall be taken, if needed, based on manufacturer or engineering recommendations.
For the snubber(s) found inoperable, an evaluation shall be performed on the components which are supported by the snubber(s).
The purpose of this evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains capable of meeting the designed service.
Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber lifp destructive testing was performed to qualify snubber OPERABILITY for all design conditions at either the completion of their fabrication or at a subsequent date.
0.10-3
0 l
0.
Mechanical Snubbers Functional Test Acce tance Criteria The mechanical snubber functional test shall verify that:
A. The force that initiates free movement of the snubber rod in either tension. or compression is less than the specified maximum drag force.
Drag force shall not have increased more than 5096 since the )ast surveillance test.
B. Activation (restraining action) is achieved within the specified range of veldcity or acceleration in both tension and compression.
C. Snubber release rate, where required, is within the specified range in compression or tension.
5.
Snubber Service Life Monitorin 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 designated service life is based shall be maintained as required by Specification 6.10.2.m.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.13-1 shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life willbe exceeded 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.
This reevaluation, replacement or reconditioning shall be indicated in the records.
i.
Records of annual physical inventory verifying accountability of sources on record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
- a. - Records and drawing changes reflecting facility design
. modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for members of the plant staff for the duration of their employment.
h.
Records of in-service inspections performed pursuant to these Technical Specif ications.
i.
Records of Quality Assurance activities as required by Corporate Quality Assurance Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
6-30
- k. 'Records of meetings of'the PNSC and the CNRB.
l.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
m,.Records. of the service lives of all snubbers listed in Table "3.1'3-1 including the date at which the service life commences
~ and associated installation and maintenance records.
RADIATIONPROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be
- approved, maintained and adhered to for all operations involving personnel radiation exposure.
HIGH RADIATIONAREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20:
a.
Each 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 provided with a
radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
Each High Radiation Area in which the intensity of radiation is greater than 100 mRem/hr shall be subject to the provisions of 6.13.1(a) above, and in addition locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under administrative control.
6-35
B3.13 BASES FOR LIMITINGCONDITIONS FOR OPERATION SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other SAFETY RELATED SYSTEMS is 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 SYSTEMS.
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~ext inspection.
However, the results of early inspections performed before the original required-time interval has elapsed (nominal time less 2596) may not be used to lengthen the required inspection interval.
Any inspection whose results require a
shorter inspection interval will'verride the previous schedule.
'When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, 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.
V/hen a snubber is found inoperable, an evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any SAFETY-RELATED SYSTEM or COMPONENT has been adversely affected by the inoperability of the snubber.
The evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
B3.13-1
0
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers willbe functionally tested during plant SHUTDOV/NS at 18 month intervals.
Observed failure of these sample snubbers shall require functional testing of additional units.
In,.cases-where the cause of failure has been identified, additional testing shall be based on manufacturer's or engineering recommendations.
As applicable, this additional testing increases the probability of locating possible inoperable snubbers without testing 1009o of,the safety-related snubbers.
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 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 maintenance of records and the snubber service life review are-not intended to affect plant operation.
B3.13-2
~ ~
B0.10 BASES FOR SNUBBERS The bases for Specification 0.10 are the same as for Specification 3.13.
Refer to T.S.
B3.13.
Oi
~
f
STATE OF FLORIDA
)
)
ss.
COUNTY OF PALM BEACH )
Robert E. Uhri being first duly sworn, deposes and says:
That he is Vice President of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this 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 sworn to before me this day of AUGUsT I 983 NOTARY PUBLIC, in and for the County of Palm Beach, State of Florida.
Way p bric Stato of Rodda ~ L'mo My Commission Expires April 20, 1S86 My commission expires:
Bonded thru Mayn thru Ma ard Bonding Aiicncy
0