ML20203N743
| ML20203N743 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/08/1986 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20203N741 | List: |
| References | |
| GL-84-13, NUDOCS 8610200004 | |
| Download: ML20203N743 (10) | |
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- RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST Oc TABLES.
Table Page 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDINT MOHITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES .3-40 3.7-1 V0LTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 151>< 3.12-1 This table has been deleted.
3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-I RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 151>< 4.14-1 This table has been deleted.
4.17-1 MINIMUM NUMBER OF STEAM. GENERATORS TO BE 4-56 INSPECTED DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STENi GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEADER SURVEILLANCE 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No. 151 ix B610200004 e61oos DR ADOCK 05000 2
RANCHO SECO UNIT 1 l TECHNICAL SPECIFICATIONS Limiting Conditions for Operation j 3.12 SNUBBERS 151>- All snubbers shall be OPERARLE. The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are
< installed, would have no adverse effect on any safety-related system.
Applicability When the reactor system is at HOT SHUTDOWH, HOT STANDBY, STARTUP or POWER OPERATION. During COLD. SHUTDOWN and REFUELING, only snubbers located on systems required to be OPERABLE for nuclear safety.
Action J
161> 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 /> either:
- 1. replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.14c on
! the supported component, or declare the supported system inoperable and follow the
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2.
appropriate specification statement for that system, or
. 3. modify suppcrts such that the supported component and the ,
supports will be OPERABLE and within tie design basis of the
- pl ant. All such changes will be subject to the provisions of
- 10CFR50.59 and will be reflected in the records required by Specification 4.14f. Also perform an engineering evaluation of
< the as-found condition per Specification 4.14c.
i Bases Snubbers are designed to prevent unrestrained pipe motion under dynamic _ loads as might occur during an earthquake or severe
- transient, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore required that all snubbers required to protect the primary coolant 151>< system or any other safety system or component be operable.
l Proposed Amendment No.151 3-51
3 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS 151k< Table 3.12-1 has been deleted, and pages 3-51b through e completely removed.
Proposed Amendment No.151 3-51a
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.14 SNUBBERS Each snubber shall be demonstrated OPERABLE by performance of the following:
- a. Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing 151>< POWER OPERATION and shall include all snubbers. If less than 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 inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period
- 0 18 months
- 25%
1 .12 months
- 25 %
2 6 months
- 25%
3, 4 124 days
- 25 %
5,6,7 62 days
- 25%
8 or more 31 days
- 25 %
The snubbers may be categorized into two groups: Those
, accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
- b. Visual Inspection Acceptance Criteria i
Visual inspections shall- verify (1) that there cre no visible indications of damage or impaired OPERABILITY, (2) attachments
( to the foundation or supporting structure are secure, and (3) in j those locations where snubber movement can be manually induced l
without disconnecting the snubber, that the snubber has freedom
- of ravement and is not frozen up. 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 (2) tne affected snubber is
- The inspection interval shall not be lengthened more than one step at a time and Definition section 1.9 does not apply.
Proposed Amendment No. 151 4-47 l
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 2 Surveillance Standards
, functionally tested in the as found condition and determined 151>< OPERABLE per Specification 4.14d or '4.14e. However, when the
' fluid reservoir of a hydraulic snubber is found to have the
. reservoir port uncovered, the snubber shall be determined
. inoperable and may be determined OPERABLE via functional testing
- if the test is started with the piston in the as-found setting, I extending the piston rod in the tension mode direction.
. c. Functional-Tests At least once per REFUELING INTERVAL, a representative sample
' 151> (10% of the total of each type of snubber (mechanical or
- . <- hydraulic) in use in the plant) shall be functionally tested either-in place or in a bench test. For each snubber that does l 151> not meet the functional test acceptance criteria of Specification 4.14d or 4.14e, an additional 10% of that type of snubber (mechanical or hydraulic) shall be functionally tested.
The representative sample selected for functional test sample plans shall be randomly selected from the snubbers of each type 151> and' reviewed before beginning the testing. Review shall ensure as far as practicable that the selected snubbers are representative of the various configurations, operating
< environments, and the . range of size and capacity of . snubbers of j
< -each type (mechanical or hydraulic).
In addition to the regular sample, snubbers which failed the previous functional test and were reinstalled 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. These snubbers shall
- not be included in the random sample and the results of these 4
tests shall not be used to determine additional testing l ' requirements, i
, If any snubber selected for functional testing either fails to t
lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency l
all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be
!' independent of the requirements stated'above for snubbers not meeting the functional test acceptance criteria.
l.
Proposed Amendment No. 151 4-47a i
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RANCHO SEC0 UNIT 1 l TECHNICAL SPECIFICATIONS Surveillance Standards j For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering 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.
- d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
- 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
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- 2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
, 151> 'e. Mechanical Snubber Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
- 1. 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 50% since the last functional test.
- 2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- 3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability _ of the snubber to withstand load without displacement shall be verified.
- f. Snubber Service Life Monitoring 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.n.
Proposed Amendment No.151 4-47b i
- - - - , - - - - , - . - - .,...- - , - ,- --, . . . - - - , . , - - . -----n, ,
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 151> Concurrent with the first inservice visual inspection and at least once per. refueling interval thereafter, the installation and naintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to th? next scheduled snubber service life review. If the indicated service life review, the snubber service life shall be re-evaluated 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 re-evaluation, replacement or reconditioning shall be indicated
< in the records.
Bases 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 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 i
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 perfcrmed 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 will override 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 ineperable. 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 i 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 engineering evaluation 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 adversely 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.
Proposed Amendment No. 151 4-47c
[* RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 151> To provide assurance of snubber functional . reliability, a 10% sample of the installed snubbers will be functionally . tested during plant shutdowns at refueling intervals. 0bserved failures of these sample snubbers shall require functional testing of additional units.
Hydraulic snubbers and mechanical snubber will 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 included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical basis 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.
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4 Proposed Amendment No. 151 4-47d i
R NCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Table 4.14-1 Limiting Conditions for Operation DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS
- t. FUNCTIONALLY TESTED ONLY A5 REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4
151>< Table 4.14-1 has been deleted, and this page has been renumbered 4-47e. The page numbered 4-47e, prior to this amendment has been completely removed.
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Proposed Amendment No. 151 4-47e
, 4 1**- -RANCHO SECO UNIT 1
- t; TECHNICAL SPECIFICATIONS
. Administrative Contr61s
- 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 current members of the plant operating staff.
- h. Records of in-service inspections performed pursuant to these.
-Technical Specifications,
- i. Records of Quality Assurance activities required by the QA Manual.
, J. Records of reviews performed for changes made to procedures or
- j. equipment or reviews of tests and experiments pursuant to
- k. Records of meetings of the PRC and the MSRC,
- 1. Records for Environmental Qualification which are covered under i the provisions of paragraph 6.14.
- m. Records for Environmental Monitoring Program. "
i 151> n. Records of the service lives of all' hydraulic and mechanical
- snubbers including the date at which the service life commences
< and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM I
I Procedures for personnel radiation protection shall be prepared
!~ consistent with the requirements of 10 CFR Part 20 and shall be i approved, maintained and adhered to for all operations involving personnel radiation exposure.
I 6.12 - Deleted 1
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- Proposed Amendment No. 151 1 6-14 i
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