ML20196G807

Revs to Technical Requirements Manual

ML20196G807
Person / Time
Site:	Sequoyah
Issue date:	06/22/1999
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20196G793	List: ML20196G788 ML20196G796 ML20196G807
References
PROC-990622, NUDOCS 9907010271
Download: ML20196G807 (25)

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. TECHNICAL REQUIREMENTS i-PAGE l-

' SECTION TR 3/4 0 -'APPLICABI1JTY ............................................. 3/4 0-1 TR 3/4.1' REACTIVITY CONTROL SYSTEMS No current requirements

.TR 3/4.2 POWER DISTRIBUTION LIMITS No current' requirements ,

"TR' 3/4.3 INSTRUMENTATION No current requirements TR 3/4.4 REACTOR COOLANT SYSTEM No current requirements TR 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 1No current requirements TR 3/4.6 CONTAINMENT SYSTEMS No current requirements TR 3/4.7 PLANT SYSTEMS TR 3/4.7.1 Through 3/4 7.8 (No current requirements)...... ........... 3/4 7-1 TR 3/4.7.9 S N UB B ERS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

TR 3/4.8 ELECTRICAL POWER SYSTEMS No current requirements TR 3/4.9 REFUELING OPERATIONS ,

No current requirements TR 3/4.10 SPECIAL TEST EXCEPTIONS No current requirements TR 3/4.11 RADIOACTIVE EFFLUENTS No' current requirements 9907010271 990622 PDR ADOCK 05000327 P PDR October 1, 1998 III SEQUOYAH - UNITS 1 AND-2 TECHNICAL REQUIREMENTS.

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i I l INDEX TECHNICAL REQUIREMENTS BASES SECTION PAGE TRB 3/4.0 APPLICABILITY............................................. B 3/4 0-1 l

TRB 3/4.1 REACTIVITY CONTROL SYSTEMS No current discussions l TRB 3/4.2 POWER DISTRIBUTION LIMITS No current discussions TRB 3/4.3 INSTRUMENTATION No current discussions TRB 3/4.4 REACTOR COOLANT SYSTEM

~No current discussions l

l TRB 3/4.5 EMERGENCY CORE COOLING SYSTEMS No current discussions TRB 3/4.6 CONTAINMENT SYSTEMS No current discussions TRB 3/4.7 PLANT SYSTEMS TRB 3/4.7.1 Through 3/4 7.8 (No current discussions)................. B 3/4 7-1 TRB 3/4.7.9 SNUBBERS................................................ B 3/4 7-2 TRB 3/4.8 ELECTRICAL POWER SYSTEMS No current discussions l TRB 3/4.9 REFUELING OPERATIONS

• l l No current discussions TRB 3/4.10 SPECIAL TEST EXCEPTIONS l

No current discussions TRB 3/4.11 RADIOACTIVE EFFLUENTS No current discussions i

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'TR 3/4.7 PLANT SYSTEMS

! TR 3/4 7.1 No current requirements l l

TR 3/4 7.2 No current requirements l TR 3/4 7.3 No current requirements

! TR 3/4 7.4 No current requirements TR 3/4 7.5 No current requirements l

TR 3/4 7.6 No current requirements TR 3/4 7.7 No current requirements TR 3/4 7.8- No current requirements l

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TR 3/4.7 PLANT SYSTEMS TR 3/4.7.9 SNUBBERS l LIMITING CONDITION FOR OPERATION l

TR 3.7.9. All safety-related snubbers shall be OPERABLE. l APPLICABILITY: MODES 1, 2, 3, and 4. (MODES S and 6 for snubbers located on systems or partial 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 and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate Technical Specification ACTION statement for that system.

SURVEILLANCE REQUIREMENTS TR 4.7.9. Each safety-related snubber shall be demonstrated OPERABLE by l

. performance of the following augmented inservice inspection program and the requirements of Technical Requirement 4.0.5.

a. Inspection Groups j The snubbers may be categorized into two major groups based on whether the snubbers are accessible or inaccessible during reactor operation.

'These major groups may be further subdivided into subgroups based on design, environment, or other features which may be expected to affect the OPERABILITY of the snubbers within the subgroup.. Each subgroup may be tested independently in accordance with TR 4.7.9.d through TR 4.7.9.h.l

b. Visual Inspection Schedule and Lot Size a All of the safety-related snubbers shall be included in one population, or they shall be categorized as accessible or inaccessible for visual inspection. If used, the accessible or inaccessible categories shall be considered separately for visual inspections.

When recombining categories into one population, the shorter interval of the categories shall be used.

The visual inspection interval for the population or each category shall j be determined based upon the criteria provided in Table 4.7.9-1., and thel 4 first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before the amendment which incorporated this change was issued by the NRC. .

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3/4 7-2 October 1, 1998 SEQUOYAH - UNITS 1 AND 2 TECHNICAL REQUIREMENTS

Table 4.7.9-1 l SNUBBER VISUAL INSPECTION INTERVAL i NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extenced Interval Repeat Interval Reduce Interval (Notes 1 and 2) (Notes 3 and 6) (Notes 4 and 6) (Notes 5 and 6) 1 0 0 1 80 0 0 2 0 1 4 100 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1000 or greater' 29 56 -

109 Note 1: The next visual inspection interval for a snubber population or category size shall be' determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.

These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2: Interpolation between population or category size and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as described by interpolation.

Note 3: If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the l

previous interval but not greater than 48 months.

Note 4: If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next l

inspection interval shall be the same as the previous interval.

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! Note 5: If the number of unacceptable snubbers is equal to or greater than the nunber in Column C, the next inspection interval shall be two-I thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation; that is, the previous I

! interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers fornd during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

Note 6: The provisions of Technical Requirement 4.0.2 are applicable for all inspection intervals up to and including 48 months.

3/4 7-3 October 1, 1998 SEQUOYAH - UNITS 1 AND 2 TECHNICAL REQUIREMENTS

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. Visual Inspection Performance and Evaluation Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) bolts attaching the snubber to the foundation or supporting structure are secure, and (3) snubbers attached to sections of safety-related systems that have experienced unexpected potentially damaging transients since the last inspection period shall be evaluated for the possibility of concealed damage and functionally tested, if applicable, to confirm operability.

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) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per TR 4.7.9.e. Hydraulic snubbers with inoperable single or l common fluid reservoirs which have uncovered fluid ports shall be declared inoperable, ,

Also, snubbers which have been made inoperable as the result of unexpected transients, isolated damage, or other such random events, when the provisions of TR 4.7.9.g and TR 4.7.9.h have been met and any other l appropriate corrective action implemented, shall not be counted in determining the next visual inspection interval.

d. Functional Test Schedule, Lot Size, and Composition At an interval commensurate with each refueling outage, a representative l sample of 10% of the total of the safety-related snubbers in use in the plant shall be functionally tested either in place or in a bench test.

The representative sample selected for functional testing shall include the various configurations, operating environments, and the range of size and capacity of snubbers within the groups or subgroups. The representative sample should be weighted to include more snubbers from severe service areas such as near heavy equipment. Unless a failure analysis as required by TR 4.7.9.f indicates otherwise, the sample shall l be a composite based on the ratio of each group to the total number of snubbers installed in the plant. Snubbers placed in the same location as snubbers which failed the previous functional test shall be incladed in the next test lot if the failure analysis shows that failure was due to location.

The security of fasteners for attachment of the. snubbers to the component and to the snubber anchorage shall be verified on snubbers selected for functional tests. ,

The provisions of Technical Requirement 4.0.2 are applicable to the interval for performing functional tests. During plant operating MODES 1 through 4 (and MODES 5 and 6 for snubbers located on systems or partial systems recuired OPERABLE in those MODES), administrative controls are required for performing snubber functional surveillance testing for the purpose of satisfying the functional test interval requirement.

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3/4 7-4 October 1, 1998 SEQUOYAH - UNITS 1 AND 2 TECHNICAL REQUIREMENTS l

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

e. Functional Test Acceptance Criteria The snubber functional test.shall verify that:

1. Activation (restraining action) is achieved within the specified range in both tension and compression, except that inertia dependent, acceleration limiting mechanical snubbers, may be tested i to verify only that activation takes place in both directions of travel.

2. Snubber bleed, or release where required, is present in both tension l

and compression within the specified range.

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3. The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel.

4. For snubbers.specifically required not to displace under continuous load, the ability of the snubber to withstand load'Without displace-ment shall be verified.

5. Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

f. Functional Test Failure Analysis and Additional Test Lots )

l If any snubber selected for' functional testing either fails to lock up or I fails to move due to manufacture or design deficiency, Ela snubbers of the same design subject to the same defect shall be functionally tested.

If more than two snubbers do not meet the functional test acceptance criteria, an additional lot equal to one-half the original lot size shall be functionally tested for each failed snubber in excess of the two allcwed failures. An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The result of this analysis shall be used, if applicable, in selecting snubbers to be tested in the subsequent lot in an effort to determine the operability of other snubbers which may be subject to the same failure mode. (Selection of snubbers for future testing may also be based on the failure analysis.) Testing shall continue until not more than one additional inoperable snubber is found within a subsequent required lot or all snubbers of the original inspection group have been tested, or all suspect snubbers identified by i

the failure analysis have been tested, as applicable.

The discovery of loose or missing attachment fasteners will beThe evaluated result to determine whether the cause may be localized or generic..

of the evaluation will be used to select other suspect snubbers for

. verifying the attachment fasteners, as applicable.

Snubbers shall not be subjected to prior maintenance specifically for the purpose of meeting functional test requirements.

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3/4 7-5 October 1, 1998 {

SEQUOYAH - UNITS 1 AND 2. j

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5 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

g. Functional Test Failure - Attached Component Analysis For snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are restrained by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber (s) were adversely affected by the incperability of the snubber (s) and in order to ensure that the restrained component remains capable of meeting the designed service.

h. Functional Testing of Repaired and Spare Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which'have repairs which might affect the functional test results shall be tested to meet the functional test criteria before installation in the unit. These snubbers shall have met the acceptance criteria subsequent to their most recent service, and the functional test must have been performed within 12 months before being installed in the

. unit.

l. Snubber Service _ Life Program The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The maximum expected service life for the various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when-the snubber is required to be OPERABLE. The parts replacements shall be documented, and the documentation shall be retained in accordance with Appendix B, Table 2, of the Nuclear Quality Assurance Plan.

j. Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and if applicable snubber life destructive testing was performed to qualify snubber operability for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

SEQUOYAH - UNITS 1 AND 2 3/4 7-6 October 1, 1998 TECHNICAL REQUIREMENTS

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I TRB'3/4.7 PLANT SYSTEMS BASES TRB 3/4.7.1 No current discussions TRB 3/4.7.2 No current riiscussions TRB 3/4.7.3 No current discussions TRB 3/4.7.4 No current discussions TRB 3/4.7.5 No current discussions TRB 3/4.7.6 No current discussions TRB 3/4.7.7 No current discussions TRB 3/4.7.6 No current discussions i

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l TRB 3/4.7 PLANT SYSTEMS i l

BASES TRB 3/4.7.9 SNUBBERS l Snubbers are designed to prevent unrestrained pipe or component motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The con-sequence of an inoperable snubber is an increase in the probability of structural damage to piping or components 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 system or any other safety system or component be operable during reactor operation.

Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed to replace or restore the inoperable snubber (s) to operable status and perform an engineering evaluation on the supported component or declare the supported system inoperable and follow the appropriate limiting condition for operation statement for that system. The engineering evaluation is performed to determine wnether the mode of failure of the snubber has adversely affected any safety-related component i

,or system. Individual snubbers may be removed from service for functional I testing during plant operating MODES 1 through 4 (and MODES 5 and 6 for I snubbers located on systems or partial syst. ens required OPERABLE in those

' MODES) provided administrative controls established herein are met.

Safety-related snubbers are visually inspected fot overall integrity and operability. The inspection will include verification of proper orientation, adequate. fluid level if applicable, and attachment of the snubber to its anchorage. The removal of insulation or the verification of torque values for threaded fasteners is not required for visual inspections.

The inspection frequency is based upon maintaining a constant level of snubber protection. Thus, the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed ,

may be used as a new reference point to determine the next inspection.

However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25 percent) may not be used to lengthen the required inspection interval. Any inspection whose ,

results require a shorter inspection interval will override the previous l schedule, j When the cause of the rejection of a snubber in a visual inspection is clearly established and remedied for that snubber and for any other snubbers that may l be genericelly susceptible and operability verified by inservice functional testing, if applicable, 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 l rejection of the snubber, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. Test groups may be established based on design features and installed conditions  !

which may be expected to be generic. Each of these groups are tested separately unless an engineering analysis indicates the group is improperly constituted. All suspect snubbers are subject to inspection and testing regardless of test groupings.

SEQUOYAH - UNITS 1 AND 2 P 3/4 7-2 October 1, 1996 TECHNICAL REQUIREMENTS

PLANT SYSTEMS-BASES SNUBBERS (Continued)

To further increase the assurance of snubber reliability, functional tests shall be performed at an interval commensurate with each refueling outage. These tests will include stroking of the snubbers to verify proper movement, activation, and bleed or release. The performance of hydraulic anubbers generally depends on a clean, deaerated fluid contained within variable pressure chambers, _ flowing at closely controlled rates. Since these characteristics are subject to change with exposure to the reactor environment, time, and other factors, their performance within the specified range should be verified. Mechanical snubbers which depend upon overcoming the inertia of a mass and the braking action of a capstan spring contained within the snubber for limiting the acceleration of the attached component (within the load rating of the snubber) are not subject to changes in performance in the same manner as hydraulic snubbers. Pending the development of information regarding the change during the service of the snubber of the acceleration / resistance relationship and the optimum method for detecting this change, these mechanical snubbers may be tested to verify that when subjected to a large change in velocity the resistance to n.ovement increases greatly.

• The performance change information was developed in order to establish test methods to be used during and after the first refueling outage.

Ten percent of the total population of snubbers is an adequate sample for functional tests. The initial sample is to be proportioned among the groups in order to obtain a representative sample. Observed failures of more than two snubbers in the initial lot will require an engineering analysis and testing of additional snubbers selected from snubbers likely to have the same defect. A thorough inspection of the snubber threaded attachments to the pipe or components and the anchorage will be made in conjunction with all required functional tests.

Snubbers may be removed from service for functional surveillance testing in MODES 1 through 4 (and MODES 5 and 6 for enubbers located on systems or partial systems required OPERABLE in those MODES) to satisfy the required testing interval, provided the following administrative controls are implemented:

'l. TR 3.7.9 ACTION statement shall be met

2. Snubbers on trained systems or portions of trained systems may be removed only on the scheduled train work week. Snubbers on non-trained systems or portions on non-trained systems may only be removed following a documented risk assessment. Snubbers may not be removed from service for testing on one train of a system while the other train has been declared inoperable for any reason.

3. No more than one snubber may be removed from service at a time on any line and attached piping which is analyzed as a seismic subsystem.

Multiple snubbers may be removed for testing simultaneously only if separated by a seismic anchor.

A list' cf individual snubbers with detailed information of snubber location and size shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., 1 t?mperature, atmosphere, location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

B 3/4 7-3 October 1, 1998 SEQUOYAH - UNITS 1 AND 2 TECHNICAL REQUIREMENTS

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'6.0f ADMINISTRATIVE. CONTROLS 6.1 TECHNICAL REQUIREMENTS (TR) CONTROL' PROGRAM This Program provides a means for controlling changes or additions to the Technical Requirements and their Bases.

6.1.1 Changes or additions to the Technical Requirements Manual (TRM) shall be made under appropriate' administrative controls and reviews.

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!' 6.1.2 Changes or additions to the Technical Requirements Manual (TRM) shall l; include an evaluation in accordance with'10 CFR 50.59, 6.1.3 Licensees-may make additions to-the TRM without prior NRC approval f provided the changes have been determined not to be candidates for inclusion in the Technical Specifications (TSs). The determination that the changes'do ,

not need to be included in TS shall include screening the change against the criteria contained in 10 CFR 50.36(c) (2) (ii) . 'An exception to this

' requirement is allowed if a temporary addition is needed pending a subsequent l TS change where conservative (safe direction) administrative controls are i-implemented in accordance with NRC Administrative Letter 98-10, R2 "Dispositioning Of Technical Specifications That Are Insufficient To Assure

• Plant Safety." These additions must not be in conflict with existing TS requirements, and should be removed upon NRC approval of the TS. Removal of the temporary addition is acceptable based upon the NRC TS change Safety i Evaluation Report authorizing the change and further 10 CFR 50.59 evaluation l is'not required due to NRC approval to place in TSs.

6.1.4 Changes or' additions to the TRM will be evaluated to ensure that they are accurately reflected in the FSAR as appropriate.

6.1.5 Proposed changes or additions that do not meet the criteria of 6.1.2 shall be reviewed and approved by the NRC prior to implementation. Changes or l

additions to the TRM implemented without prior NRC approval shall be provided to the NRC on a ' frequency consistent with 10 CFR 50.71(e) .

SEQUOYAH - UNITS 1 AND 2 6-1 February 12, 1999 TECHNICAL REQUIREMENTS' t.

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' TECHNICAL LREQUIREMENTS l'

'SECTION PAGE

'TR 3/4.0 APPLICABILITY ..........'................................... 3/4-0-1 TR 3/4.1 REACTIVITY CONTROL SYSTEMS No current requirements TR 3/4.2 POWER DISTRIBUTION' LIMITS-No-current requirements TR 3/4.3 INSTRUMENTATION-TR 3/4.3.1 Through TR-3/4.3.2 (No-current requirements)............... 3/4 3-1 TR 3/4.3.3 MONITORING INSTRUMENTATION

' TR 3/4. 3.3.1 RADIATION MONITORING ' INSTRUMENTATION . . . . . . . . . . . . . . . 3 /4 3-2 LTR 3/4.4 ' REACTOR COOLANT SYSTEM

> 'No current requirements

'O TR3/4f5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

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No current ~ requirements TR 3/4. 6 - CONTAINMENT SYSTEMS .

No current: requirements t TR 3/4.7' PLANT SYSTEMS TR 3/4.7.1^Through.TR 3/4 7.6 (No current. requirements)............... 3/4 7-1

'TR 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.................. 3/4 7-2 TR 3/4.7.8 (No current requirements).................................. 3/4 7-3 TR.3/4.7.9 SNUBBERS.................................................. 3/4 7-4 TR 3/4.8 ELECTRICAL POWER SYSTEMS No current requirements TR 3/4.9 REFUELING OPERATIONS No current requirements

.TR 3/4.10 SPECIAL TEST EXCEPTIONS No current requirements TR 3/4.11 RADIOACTIVE EFFLUENTS No current requirements SEQUOYAH sUNITS l'AND 2 III March 18, 1999 TECHNICAL' REQUIREMENTS-

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INSTRUMENTATION TR 3/4.3.1 No current requirements TR 3/4.3.'2 No current requirements I

i March 18, 1999 SEQUOYAH - UNITS 1 AND 2 3/4 3-1 TECHNICAL REQUIREMENTS

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BOLD TEXT REPRESENTS CONSERVATIVE ADDITIONS TO CURRENT TS REQUIREMENTS

. INSTRUMENTATION TR 3/4.3.3' MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION TR 3.3.3.1 The radiation monitoring-instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the

.specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable. .

b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c. The provisions of Technical Specifications and Technical Requirements 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS TR 4.3.3.1 Each radiation monitoring instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MCDES and at the frequencies shown in Table 4.3-3.

March 18, 1999 SEQUOYAH - UNITS 1 AND 2 3/4 3-2 TECHNICAL REQUIREMENTS l

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TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 26 - With the number of OPERABLE crannels less than required j by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 27 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Technical Specification 3.4.6.1.

ACTION 28 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Technical Specification 3.9.9 (MODE 6) and Technical Specification 3.3.2.1 (MODES 1, 2, 3, and 4). l ACTION 29 - a 'With one channel inoperable, place one CREVS train in recirculation mode of operation within 7 Days or be in at  ;

• least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and In COLD  !

SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> l b With two channels inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation If the completion time of Action 29b can not be met in MODES 1, 2, 3, and 4, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

If the completion time of Action 29b can not be met during the movement of irradiated fuel assemblies, suspend core alterations and suspend movement of irradiated fuel assemblies.

If the completion time of Action 29b can not be met in MODES 5 or 6, initiate action to restore one CREVS train.

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• TR 3/4.7 PLANT SYSTEMS TR 3/4 7.1 No current requirements TR 3/4 7.2 No current requirements TR 3/4'7.3 No current requirements TR 3/4 7.4 No current requirements TR 3/4 7.5 No current requirements TR 3/4 7.6 No current requirements l

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BOLD TEXT REPRESENTS CONSERVATIVE ADDITIONS TO CURRENT TS I REQUIREMENTS -l i

PLANT SYSTEMS TR 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION

-TR 3.7.7 Two independent control room emergency ventilation systems (CREVS) shall be OPERABLE. +

APPLICABILITY: ALL MODES and During Movement of Irradiated Fuel Assemblies ACTION:

MODES 1, 2, 3 and 4

a. With one CREVS inoperable, restore the inoperable system to OPERABLE status within 7 days or'be'in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

bl With both CREVS inoperable due to actions taken as a result of a tornado warning, restore at least one train'to operable status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in a least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within'the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

MODES 5, 6, and During Movement of Irradiated ruel Assemblies

a. With one CREVS inoperable, restore the inoperable system to OPERABLE status withinL7 days or initiate and maintain operation of the control room emergency ventilation system in the recirculation mode

b. With both CREVS inoperable, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS TR 4.7.7 Each CREVS shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room ,

air temperature is less than or equal to 104*F. i

b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.

c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone  ;

communicating with the system by:

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SEQUOYAH - UNITS 1 AND 2 3/4 7-2 March 18, 1999 TECHNICAL REQUIREMNENTS

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, i TR 3/4.7 PLANT SYSTEMS l TR 3/4 7.8 No current requirements l

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. e TR'3/4.7 PLANT SYSTEMS I

TR 3/4.7.9 SNUBBERS l J l

LIMITING CONDITION FOR OPERATION- )

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i TR 3.7.9. .All. safety-related snubbers shall be, OPERABLE. l 4

k' APPLICABILITY: MODES 1, 2, 3, and 4. (MODES 5 and 6 for snubbers located on systems or partial systems' required OPERABLE in those MODES.)

ACTION: i 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 j

' inoperable' snubber (s) to OPERALLE status and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate Technical-Specification ACTION statement for that system.

SURVEILLANCE REQUIREMENTS TR 4.7.9. Each safety-related snubber shall be demonstrated OPERABLE by l

. performance of the following augmented inservice inspection program and the requirements of Technical Requirement 4.0.5.

a. Inspection Groups The' snubbers may be categorized into two major groups based on whether the snubbers are accessible or inaccessible during reactor operation.

.These major groups may be further subdivided into subgroups based on design, environment, or other features which may be expected to affect the OPERABILITY of the snubbers within the subgroup. Each subgroup may be-tested independently in accordance with TR 4.7.9.d through TR 4.7.9.h.l

b. Visual Inspection Schedule and Lot Size All of the safety-related snubbers shall be included in one population,

'or they shall be categorized as accessible or inaccessible for visual inspection. If used, the accessible or inaccessible categories shall be considered separately for visual inspections.

When recombining categories into one population, the shorter interval of the categories shall be used.

The visual inspection interval for the population or each category shall f be determined based upon the criteria provided in Table 4.7.9-1., and thel

-first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before the amendment which incorporated this change was issued by the NRC. .

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Table 4.7.9-1 l SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extended Interval Repeat Interval Reduce Interval (Notes 1 and 2) (Notes 3 and 6) (Notes 4 and 6) (Notes 5 and 6) 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.

These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2: Interpolation between population or category size and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as described by interpolation.

Note 3: If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.

Note 4: If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.

Note 5: If the number of unacceptable snubbers is equal to or greater than the number in Column C, the pext inspection interval shall be two-thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater'than the number in Column B, the next interval shall be reduced proportionally by interpolation; that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found

-' during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

Note 6: The provisions of Technical Requi.ement 4.0.2 are applicable for all inspection irtervals up to and including 48 months.

SEQUOYAH - UNITS 1 AND 2 3/4 7-5 October 1, 1998 TECHNICAL REQUIREMENTS

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p PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. Visual Inspection Performanc_e and Evaluation Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) bolts attaching the snubber to the foundation or supporting structure are secure, and (3) snubbers attached to sections of safety-related systems that have experienced unexpected .

potentially damaging transients since the last inspection period shall be 1 evaluated for the possibility of concealed damage and functionally tested, if applicable, to confirm operability.

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 particu.lar snubber and for i other snubbers that may be generically ausceptible and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per TR 4.7.9.e. Hydraulic snubbers with inoperable single or l common fluid reservoirs which have uncovered fluid ports shall be declared inoperable. -

Also, snubbers which have been made inoperable as the result of unexpected transients, isolated damage, or other such random events, when the provisions of TR 4.7.9.g and TR 4.7.9.h have been met and any other l appropriate corrective action implemented, shall not be counted in determining the next visual inspection interval.

d. Functional Test Schedule, Lot Size, and Composition At an interval commensurate with each refueling outage, a representative l sample of 10% of the total of the safety-related snubbers in use in the plant shall be functionally tested either in place or in a bench test.

The representative sample selected for functional testing shall include the various configurations, operating environments, and the range of size and capacity of snubbers within the groups or subgroups. The representative sample should be weighted to include more snubbers from severe service areas such as near heavy equipment. Unless a failure analysis as required by TR 4.7.9.f indicates otherwise, the sample shall l be a composite based on the ratio of each group to the total number of snubbers installed in the plant. Snubbers placed in the same location as snubbers which failed the previous functional test shall be included in the next test lot if the failure analysis shows that failure was due to location.

The security of fasteners for attachment of the-snubbers to the component and to the snubber anchorage shall be verified on snubbers selected for functional tests. ,

The provisions of Technical Requirement 4.0.2 are applicable to the interval for performing functional tests. During plant operating MODES 1 through 4 (and MODES 5 and 6 for snubbers located on systems or partial systems required OPERABLE in those MODES), administrative controls are required for performing snubber functional surveillance testing for the purpose of satisfying the functional test interval requirement.

3/4 7-6 October 1, 1998 SEQUOYAH - UNITS 1 AND 2 TECHNICAL REQUIREMENTS

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PLANT SYSTEMS

! SURVEILLANCE REQUIREMENTS (Continued)

e. Functional Test Acceptance Criteria The snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range in both tension and compression, except that inertia dependent, acceleration limiting mechanical snubbers, may be tested to verify only that activation takes place in both directions of travel.

2. Snubber bleed, or release where required, is present in both tension and compression within the specified range.

3. The force required to initiate er maintain motion of the snubber is within the specified range in both directions of travel.

4. For snubbers.specifically required not to displace,under continuous load, the ability of the snubber to withstand load without displace-ment shall be verified.

5. . Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

f. Functional Test Failure Analysis and Additional Test Lots If any snubber selected for functional testing either fails to lock up or fails to move due to manufacture or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested.

If more than two snubbers do not meet the functional test acceptance criteria, an additional lot equal to one-half the original lot size shall be functionally tested for each failed snubber in excess of the two allowed failures. An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.. The result of this analysis shall be used, if applicable, in selecting snubbers to be tested in the subsequent lot in an effort to determine the operability of other snubbers which may be subject to the same failure mode. (Selection of snubbers for future testing may'also be based on the failure analysis.) Testing shall continue until not more than one additional inoperable snubber is found within a subsequent required lot or all snubbers of the original inspection group have been tested, or all suspect snubbers identified by the failure analysis have been tested, as applicable.

The discovery of loose or missing attachment fasteners will be evaluated to_ determine whether the cause may be localized or generic. The result of the evaluation will be used to select other suspect snubbers for verifying the attachment fasteners, as applicable.

Snubbers shall not be subjected to prior maintenance specifically for the purpose of meeting functional test requirements.

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SEQUOYAH - UNITS'l AND 2 3/4 7-7 October 1, 1998 TECHNICAL REQUIREMENTS

7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

g. Functional Test Failure - Attached Component Analysis For snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are restrained by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber (s) were adversely affected by the inoperability of the snubber (s) and in order to ensure that the restrained component remains capable of meeting the designed service.

h. Functional Testing of Repaired and Spare Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the functional test criteria before installation in the unit. These snubbers shall have met the acceptance criteria subsequent to their most recent service, and the functional test must have been performed within 12 months before being installed in the

, unit.

i. Snubber Service Life Program The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The maximum expected service life for the various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extenden or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented, and the documentation shall be retained in accordance with Appendix B, Table 2, of the Nuclear Quality Assurance Plan.

j. Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for ,

individual snubbers may be granted by the Commission if a justifiable i basis for exemption is presented and if applicable snubber life .

destructive testing was performed to qualify snubber operability for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

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