Text

Technical Requirements Manual
	ML20202J765
Person / Time
Site:	Sequoyah
Issue date:	02/13/1998
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
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ML20202J745	List: ML20202J742; ML20202J760; ML20202J765;
References
	PROC-980213, NUDOCS 9802230215
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TENNESSEE VALLEY ALTHORITY SEQUOYAH NUCLEAR PLANT i

! CKITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL lBR'288!!8388)l27

SEQUOYAH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL PURPOSE The purpose of the Technical Requirements Manual (TRM) is to provide a location for selected safety related system requirements that do not meet the criteria foHnclusion in the Technical 3 Specifications (TSs) in accordance with 10 CFR 50.36. The requirernents contained in the TRM may contain actions that requi e declaring TS systems inoperable or may require a unit shutdown. These requirements augment the TS requircrr.:nts but do not supersede any provisions in the TSs. The TRM contains the same definitions and usage requirements ( as delineated in Sections 1.0, TR 3.0, and TR 4.0) in addition to those found in the TSs and do not affect the application of the associat.:d TS requirements. Deviations from the TRM are considered to be a non-compliance condition subject to the corrective action program. However, as the TRM is not a part of the TSs, the deviations are not considered to be an operation prohibited by TSs.

Changes to the TRM can be processed without prior NRC review and approval as opposed to TS requirements that require the processing of a License Amendment Request. Changes to the TRM will be made in accordance with the program controls found in Section 6.0 of the TRM.

Changes to the TRM that involve an unreviewed safety question or require a TS change will require prior NRC approval in accordance with 10 CFR 50.59.

l INDEX DEFINITIONS SECTION PAGE

-1.0 DEFINITIONS 1.1 ACTION............................................................... 1-1 1.2 AX I AL FLUX D I FFE RENCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 1 I 1.3 B Y PAS S L EAKAG E P AT H . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 1 l 1.4 C HAN N EL C ALI B RAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 1 1.5 CHANNEL CHECK ................................., .................... 1-1 1.6 CCANNEL FUNCTIONAL TEST... ..

....................................... 1-1 1,7 CONTAINMENT INTEGRITY................................................ 1-2 1.8 CONTROLLED LEAKAGE............................................... ... 1-2 1.9' CORE ALTERATION,.............. ...................................... 1-2 1.10 CORE OPERATING LIMITS REPORT.................................... .... 1-2 1.11 DOSE EQUIVALENT I-131................................................ 1-2 1.12 E - AVE RAGE DI S I NT EG RAT IO N ENERGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1,13 ENGINEERED S AFETY FEATURE RES PONSE TIME . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.14 FREQUENCY NOTATION,.................................................. 1-3 1,15 GASEOUS RADWASTE TREATMENT SYSTEM..... ............ ................. 1-3 1.16 I D ENT I FI E D L EA KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 3 1.17 MEMBER (S) 0F THE PUBLIC............ ................................. 1-3 1.18 OFFSITE DOSE CALCULATION MANUAL (ODCM)............................... 1-4 1.19 OPERABLE - OPERABILITY........................... ................... 1-4 1.20 OPERATIONAL MODE - MODE.............................................. 1-4 1.21 PHYSICS TESTS........................................................ 1-4 1.22 PRESSURE BOUNDARY LEAKAGE.......... ................................. 1-4 SEQUOYAH - UNITS 1 AND 2 I TECHNICAL REQUIREMENTS xm.a -

INDEX DEFINITIONS SECTION PAGE 1.0- DEFINITIONS (Continued) 1.23 PURGE - IURGING., ................................................... 1-4 -

1.24 (UADRANT POWER TILT RATIO............................................ 1-4 1.25 RATED THERMAL POWER (RTP)............................................ 1-4 1.26- REACTOR TRIP SYSTEL. RESPONSE TIME.................................... 1-5 1.27 REPORTABLE EVENT..................................................... 1-5 1.28 SHIELD BUILDING INTEGRITY........,................................... 1-5 1.29 S H UT DOWN MARG I N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 5 1.30 UITE BOUNDARY.,........ ............................................. 1-5 1.31 STAGGERED TEST BASIS.................. .............................. 1-5 1.32 THERMAL POWER......................................... .............. 1-5 1.33 UNIDENTIFIED LEAKAGE................................................. 1-5 1.34 UNRESTRICTED AREA........................................... ........ 1-6 1.35 VENTILATION EXRAUST TREATMr.NT SYSTEM................................. 1-6 1.36 VENTING.............................................................. 1-6 OPERATIONAL MODES (TABLE 1.1).............................................. 1-7 FREQUENCY NOTATION (TABLE 1.2)......................... ................... 1-8 SEQUOYAH - UNITS 1 AND 2 II TECHNICAL REQUIREMENTS

l.

INDEX TECHNICAL REQUIREMENTS SECTION PAGE TR 3/4.0 APPLICABILITY .............................. ............... 3/4 U-1 2R 3/4.1 REACTIVITY CONTROL SYSTEMS No current requirements TR 3/4.2 POWER DISTRIBUTION LIMITS 1

No current requirements l

1 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)

No current requirements TR 3/4.6 CONTAINMENT SYSTEMS No current requirements TR 3/4.7 PLANT SYSTEMS TR 3/4.7.1 SNUP7ERS................................................ 3/4 7-1 TR 3/4.8 ELECTRICAL POWER SYSTEMS l'a 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 - UNITS 1 AND 2 III TT.CHNICAL REQUIREMENTS

INDEX TECHNICAL REQOIREMENTS BASES

'SECTION PAGE TRB 3/4.0 APPLICABILITY....................................... ......B 3/4 0-1 TRB 3/4.1 REACTIVITY CONTROL SYSTEMS No current discussions

TRL 3/4.2 POWER DISTRIBUTION LIMITS No current discussicns TRB 3/4.3 INSTRUMENTATION No current discussions TRB 3/4.4 REACTOR COOLANT SYSTEM No current discussions TPB,3/4.5 EMERGENCY CORE COOLING SYSTEMS Nc: utrent discussions TRB 3/4.6 CONTAINMENT S'JSTEMS No current discussions TRB 3/4.7 PLANT SYSTEMS TRB 3/4.7.1 SNUBBERS..............................................B 3/4 7-1

-TRB 3/4.8 ELECTRICAL POWER SYSTEMS No current discussions TRB 3/4.9 REFUELING OPERATIONS No current discussions TRB 3/4.10 CPECIAL TEST EXCEPTIONS No current discussions TRB 3/4.11 RADIOACTI'IC EFFLUENTS No current discussions SEQUOYAH - UNITS 1 AND 2 IV TECHNICAL REQUIREMENTS

INDEX DESIGN FEATURES SECTION PAGE 5.0 DESIGN FEATURE 3 No current requirements SEQUOYAh - UNITS 1 AND 2 V TECHNICAL REQUIREMENTS

\

INDEX ADMINISTRATIVE CONTROLS SECTION .PAGE 6.0 ADMINISTRATIVE CONTROLS

-6.1 TECHNICAL REQUIREMENTS (TR) CONTROL PROGRAM............................ 6 I i

SEQUOYAH - UNITS 1 AND 2 VI TECHNICAL REQUIREMENTS 1

1.0 DEFINITIONS DEFINED TERMS The defined terms of this section appear in capitalized type and are dppl1 Cable throughout these Technical Requirements.

ACTIOt; 1.1 ACTION shall be that part of a Requirement which prescribes remedial measures required under designated conditions.

AXIAL FLUX DIFFERENCE 1.2 AXIAL FLUX DIFFERENCE shall be the difference in normalized-flux signals between the top and bottom halves of a two-section excore neutron detector.

BYPASS LEAKAGE PATH 1.3 A BYPASS LEAKAGE PATH is a potential path for leakage to escape from both the primary containment and annulus pressure boundary. Only one type of BYPASS LEAKAGE PATH is recognized:

1 l a. BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING are those paths that would potentially allow leakage from the primary containment to circumvent the annulus secondary containment enclosure and escape directly to the Auxiliary Building secondary containment enclosure.

CHANNEL CALIBRATION 1.4 A cMANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNCL FUNCTIONAL TEST. The

. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behav!or during operation by observation. This determination shalt include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

' CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. 31 stable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

c. Digital channels - the injection of a simulated signal int. +he channel as close to the sensor input to the process racks .:t practicable to verify OPERABILITY including alarm and/or tt >

functions.

SEQUOYAH - UNITS 1 AND 2 1-1 TECHNICAL REQUIREMENTS l

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CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed during accident conditions are eitner:

1) Capable of being closed by an OPERABLE containment automatic isolation valve system, or

2) Closed by manual valves, blino flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as-permitted by Technical Specification 3.6.3.

b. All equipment hatches are closed and sealed,

c. Each air lock is in compliance with the requirements of' Technical Specification 3.6.1.3, '

d. The containment leakage rates are within the limits of Technical Specification 4.6.1.1.c,

e. The sealing mechanism associated with each penetration (e. g. ,

welds, bellows, or 0-rings) is OPERABLE, and

f. Secondary containment bypass leakage is within the limies of Technical Specification 3.6.1.2.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that. seal water ficw supplied to the reactor coolant pump seals.

CORE ALTERATION 1.9 CORE ALTERATION shall be the'mo'vement of any fuel, sources, reactivity control components, or other components affecting reactivity _within the reactor vessel with the head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLP) is the unit-specific document

.that provides core operating limits for the current operating reload cycle.

These cycle-specific core operating limits shall be determined for ea-* reload cycle in accordance with Technical Specification 6.9.1.14. Unit operation within these operating limits is addressed in individual specificatie.1s.

DOSE EQUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /

grami which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for rewer ,

and Test Reactor Sites."

i

'SEQUOYAH - UNITS 1 AND 2 1-2 TECHNICAL REQUIREMENTS

E - AVERAGE DISINTEGRATION ENEAGY 1.12 E shall Le the average (weighted in proportion to the concentration of each radionucliot in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total ncn-iodine activity in the coolant.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be tr.. .ime interval

-from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF aquipment is capable of performing its s=#ety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FREQUENrY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

GASEOUS RADWASTE TREATMENT SYSTEM 1.15 A GASEOC3 RADWASTE TREATMENT SYSTEM is any cystem designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment, i IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be: I

a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as

, pump seal or valve packing leaks thct are captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere frem sources that are both specifically located and known either not to interfere- with the operation of leakage detection systems or not to be PEESSURE BOUNDARY LEAKAGE, or

c. Reactor coolant system leakage through a steam generator to the secondary system.

MEMBER (S) OF THE PUBLIC 1.17 MEMBERS OF THE PUBLIC means an individual in a controlled or unrestricted arua. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.

SEQUOYAH - UNITS 1 AND 2 1 -3 TECHNICAL REQUIREMENTS

OFFSITE DOSE CALCULATION MANUAL (ODCJM 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid offluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls required by Technical Specification 6.8.4 and the Radiological Environmental Monitoring Programs and (2) descriptions of the information that should be included in the Annual Radiological Environmental Opera *ing and Annual Racteactive Effluent Release Reports required by Technical Specifications 6.9.1.6 and 6.9.1.8.

OPERABLE - OPERABILITY 1.19 A system, subsystem, train, or component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are recuired for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall corresponu to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1.

PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Cormission.

PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PURGE - PURGING 1.23 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the confinement.

QUADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER (RTP) 1.25 RATED THERMAL POWER (RTP) shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

SEQUOYAH - UNITS 1 AND 2 1-d TECHNICAL REQUIREMENTS

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor untti loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.27 A. REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHIELD BUILDING ZNTEGRITY-1.28 SHIELD BUILDING INTEGRITY shall exist when:

a. The door in each access opening is closed except when the access

. opening is being used for normal transit entry and exit.

! b. The emergency gas treatment system is OPERABLE.

c. The sealing mechanism associated with each penetration (e.g.,.

welds, bellows, or 0-rings) is OPERABLE.

SHUTDOWN MARGIN 1,29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition

. assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 11,30' The SITE BOUNDARY shall be that line beyond which the land is not owned,

' leased, or otherwise controlled by the licensee (see Technical Specification

- Figure 5.1-1).

STAGGERED TEST BASIS-l 1.31 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified- test interval into n equal subintervals,

b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.32 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIDENTIFIED LEAKAGE 1.33 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

SEQUOYAH - UNITS 1 AND 2 1-5 TECHNICAL REQUIREMENTS r .

UNRESTRICTED AREA i 1.34 An UNRESTRICTED AREA shall be any area, at or beyond the site boundary, to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.35 A VENTILATION EXHAUST TREATMENT SYSTEM is any systen designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from rhe gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems are .

g not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.36 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required during VENTING. Vent, usec in system names, does not imply a VENTING process.

s SEQUOYAH -' UNITS 1 AND 2 1-6 TECHNICAL REQUIREMENTS

TABLE 1.1 GPERATIONAL MODES REACTIVITY % RATED AVERAGE COOLANT MODE CONDITION, K,er THERMAL POWER

TEMPERATURE

1. POWER OPERATION 20.99 >5% 2350'F

-2. STARTUP 20.99 55% 2350'F

3. HOT STANDBY <0.99 0 2350*F

4. HOT SHUTDOWN <0.99 0 350*F > T.,,

>200*F

5. COLD SHUTDOWN <0.99 0 s200*F-

6. REFUELING ** s0.95 0 sl40*F

Excluding decay heat.

- Fuel in the reactor vessel with-the vessel head closure bolts less than fully e tensioned or with the head removed.

SEQUOYAH - UNITS 1 AND 2 1-7 TECi;NICAL REQUIREMENTS

. TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY' S At least once per 12-hours.

D At least once per 24 hoars.

W At least once per 7 days.

M At least once per 31 days.

)

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed prior to each release.

N.A. Not applicable.

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i SEQUOYAH - UNITS 1 AND 2 1-8 TECHNICAL REQUIREMENTS

, . . . . . . J

TR 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS TR 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION TR 3.0.1 Compliance witn the Limiting Conditions for Operation contained in the succeeding Requirements is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet th? Limiting Conditions for Operation, the associated ACTION requirements shall be met.

TR 3.0.2 Noncompliance with a Requirement shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are #

not met within the specified time intervals. If the Limiting Conditions for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

TR 3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the Requirement does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirement 3, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. -Exceptions to these requirements are stated in the individual Requirements.

TR 3.0.4 Entry into an OPERATIOMAL MODE or other specified condition shall not be made unless the conditions for the Limiting Condition for. Operation are met without reliance-on provisions contained in the ACTION requirements. This provision shall not prevent passags through OPERATIONAL MODES as required to

-comply vith ACTION requirements. Exceptions to these requirements are stated in the individual Requirements.

TR 3.0.5 When a system, subsystem, train, component, or device is determined to be inope -bl.e solely because its emeraency power source is inoperable, or solely bet its normal power source is inoperable, it may ba consicered-OPERABLE L rhe purpose of satisfying the requirements of its applicable Limiting c ndition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all af its redundant system (s),

subsystem (s), train (s), component (s), and device (s) are OPERABLE, or likewise

satisfy the requirements of this Requirement. Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This Requirement is not applicable in MODES 5 or 6.

TR-3.0.6 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to sarvice under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.1 and 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

SEQUOYAH - UNITS 1 AND 2 3/4 0-1 TECHNICAL REQUIREMENTS l

I

APPLICABILITY SURVEILLANCE REQUIREMENTS TR 4.0.1- Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation ;

unless otherwise stated in an individual Surveillance Requirement. i TR 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

TR 4.0,3 Failure to perform a Surveillance Requirement within the allowed surveillance 'nterval, defined by Technical Requirement 4.0.2, shall .

constit ^ 'ompliance with the OPERABILITY requirements for a Limiting Condit

ration. The tima limits of the ACTION requirements are applicom ; time it is identified that a Surveillance Requirement has not been , rmed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit tne completion of the surveillance when the allowable outage time

, limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

, TR 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall j not be made unless the Surveillance Requirement (s) associated with the Limiting. Condition for Operation have been performed within the specified surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

TR 4.0.5_ Surveillance Requirements for inservice inspection and-testing of ASME Code Class 1, 2, and 3 components shall be as follows:

Inservice Inspection Program This program provides controls for inservice inspection of ASME Code Class 1, 2,.and 3 components, including applicable supports. The program shall include the following:

a. Provisicas.that inservice testing of ASME Code Class 1, 2, and 3 components shall-be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a;

b. The provisions of Technical Requirement'4.0.2 are applicable to the frequencies for. performing inservice inspection activities;

c. Inspection of each reactor coolant pump flywheel per the recommendation of Regulation Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirement of any Technical Requirement.

odQUOYAH - UNITS 1 AND 2 3/4 0-2 TECHNICAL REQUIREMENTS

__ __________________d

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

TR 4.0.5 (Continued)

Inservice Testing Program This program provides controls for inservice testing Of ACME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:

a. Provisions that inservice testing of ASME Code Class 1, 2, and 3 j pumps and'velves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a;

b. Testing Frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice testing activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 davs Yearly or an aa'ly. .

At least once per 366 e.,s l Biennially or every 2 years At least once per 73; ;s

c. The provisions of Technical Requirement 4.0.2 are applicaule to the-above required Frequencies for performing inservice testing activities;

d. The provisions of Technical Requirement 4.0.3 are applicable to inservice testing and activ!*ies; and

e. Nothing in the ASME Boiler and Pressure V'ssel Code shall be construed to supersede the requirements of any Technical Requirement.

SEQUOYAH - UNITS 1 AND 2 3/4 0-3 TECHNICAL REQUIREMENTS

TR 3/4.7 PLANT SYSTEMS TR 3/4.7.1 SNUBBERS LIMITING CONDITION FOR OPERATION TR 3.7.1. All safety-related snubbers shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

(MODES 5 and 6 for snubbers located on s systems or partial systems required OPERABLE in those MODES.)

ACTION:

With one or mors snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 W44444444444444444444444444444444444444444444444444444444444444444444444444444 TR 4.7.1. Each safety-related snubber shall be demonstrated OPERABLE :

performance of the following augmented inservice inspect'.on program anc he requirements of Technical Requirement 4.0.5.

a. Inspection Groups The sr bbers may be categorized into two major groups based on whether the st 5ers are accessible or inaccessible during reactor operation.

- These n jor 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 test independently in accordance with TR 4.7.1.d through TR 4.7.1.h.

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 L considered separately for visual inspections.

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

The visual inspection interval for the population or each category shall be determined based upon the criteria provided in Table 4.7.1-1., and the g first inspection interval determined using this criteria shall be basec' F upon the previous inspection interval as established by the requirements F in effect before the amendment which incorporated this change was issued

[

by the NRC.

L SEQUOYAH - UNITS 1 AND 2 3/4 7-1 TECHNICAL REQUIREMENTS

Table 4.7.1-1 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNbBBERS 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 ir.terval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. 3 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 an described by interpolation.

Note 3: If the number of unacceptacle snubbers is equal to or less than the nwmber 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 next 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 i terval 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 Requirement 4.0.2 are applicable for all inspection intervals up to and including 48 months.

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

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 4.7.1.e. Hydraulic snubbers with inoperable single or 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 1R 4.7.1.g and TR 4.7.1.h have been met and any other appropriate corrective action implemented, shall not be counted in determining the next visual inspection interval.

d. Functional Test Schedule, Lot Size, and Composition During each refueling outage, a representative sample of 10% of the total I 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 4.7.1.f indicates otherwise, the sample shall 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 4 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.

SEQUOYAH - UNITS 1 AND 2 3/4 7-3 TECHhICAL REQUIREMENTS

_.____J

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 j travel. i

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

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 specificallf requircd 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 arameters indirectly or parameters other than those specified li 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 origi: 11 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 snubbars 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 us*d to select other suspect snubbers for verifying the attachment f a e '. ene rs , as applicable.

Snubbers shall net be subjected to prior maintenance specifically for the purpose of meeting functional test requirements.

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

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 i

1 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 installarion 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.

1. 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, rable 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 snubbe , 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 c mpletion of their fabrication or at a subsequent date.

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

TRB 3/4.0 APPLICABILITY BASES The requirements of this section provide the general requirements applicable to each of the Limiting Conditions for Opera

on and Surveillance Requirements within Technical Requirements 3/4.

TRB 3.0.1 This Requirement defines the applicability of each requirement in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate specifically when each requirement is applicable.

TRB 3.0.2 This Requirement defines those conditions necessary to constitute compliance witn the terms of an individual Limiting Condition for Operation '

and associated ACTION requirement.

TRB 3.0.3 This Requirement delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of the requirement. For example, Technical Specification 3.5.3 requires two independent ECCS subsystems to be i

OPERABLE and provides explicit ACTION requirements if one ECCS subsystem is j inoperable. Under the requirements of Technical Specification 1.0.3, if.both

of the required ECCS subsystems are inoperable, within one ht.. measures'must be initiated to place.the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further example, Technical Specification 3.6.2.1 requires two containment spray subsystems to be OPERABLE and provides explicit ACTION requirements if one spray system is inoperable. Under the requirements of Technical Specification 3.0.3, if both of the required containment spray subsystems are inoperable, within one hour measures must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

TRB 3.0.4 This Requirement provides that entry into an OPERATIONAL MODE or other specified applicability condition must be made with (a) the full complement of required systems, equipment, or components OPERABLE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard for allowable deviations and out-of-service provisions contained in the ACTION statements.

The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

Exceptions to this provision have been provided for a limited number of requirements when startup with inoperable equipment would not affect plant safety. These exceptions are stated in the ACTION statements of the appropriate requirements.

TRB 3.0.5 This Requirement delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not O?ERABLE. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

SEQUOYAH UNITS 1 AND 1 B 3/4 0-1 TECHNICAL REQUIREMENTS

APPLICABIIITY BASES The provisions of this Requirement permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source. It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoperable solely because of the inoperability of its normal or emergency power source.

For example, Technical Specification 3.8.1.1 requires in part that four emergency diesel generators be OPERABLE. The ACTION statement provides for a 72-hour out-of-service time when one emergency diesel generator is not OPE RABLE. If the definition of OPERABLE was applied without consideration of Technical Specification 3.0.5, all systems, subsystems, trains, components, and devices supplied by the inoperable emergency power source would also be inoperable. This would dictate invoking the applicable ACTION statements for eich of the applicable Limiting Conditions for Operation. However, the provisions of Technical Specification 3.0.5 permit the time limits for continued ;peration to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy Technical Specification 3.0.5 (i.e., be capable of performing their i

design function and have at least one normal or one emergency power source l' OPERABLE). If they are not satisfied, action is required in accordance with this specification.

a further example, Technical Specification 3.8.1.1 requires in part that two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE. The ACTION statement provides a 24-hour out-of-service time when both required offsite circuits are not OPERABLE. If the definition of OPERABLE was applied without consideration of Technical Specification 3.0.5, all systems, subsystems, trains, components, ard' devices supplied by the inoperable normal power sources, both of the offsite circuits would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable LCOs. However, the provisions of Technical Specification 3.0.5 permit the time. limit for continued operation to be consistent with the ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied. In this case, this would mean that for one division the emergency power source must be OPERABLE (as must be the components

-supplied by the emergency power source), and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE. If these conditions are not satisfied, action is required in accordance with this specification.

In MOD"S 5 or 6, TR 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.

SEQUOYAH UNITS 1 AND 2 B 3/4 0-2 TECHNICAL REQUIREMENTS

l c

APPLICABILITY-1 BASES !

TRB 3.0.6 LCO TR 3.0.6 established the allowance for restoring equipmeat to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Requirement is to provide an exception to LCOs TR 3.0.1 and TR 3.0.2 (e.g., to not comply with the applicable Required Actionts]) to allow the performance of SRs to demonstrate:

a. The OPERABILITY of the equipment being returned to services or i

b. The OPERABILITY of other equipment. ^

The administrative controls ensure the time the equipment is returned to 4

service in conflict with the requizements of the ACTIONS is limited to the time absolutely necessary to perform the allowed SRs. This Requirement does not provide time to perform any other pre" ntive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to

- service is reopening a containmeat isolation valve that has been closed to comply with Required Actions and must be reopened to perform the SRs.

a An- example c:' demonstrating the OPERABILITY of other equipment is taking an

. incperable enannel or trip system out of the tripped condition to prevent the trip function from occurring during the perfor..ance of an SR on anothcr channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of an SR on another chanrel in the same tilp system.

4 TRB 4.0.1 This Requirement pro > ides that survejllance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for V.ich the Limiting Condi~ ions for Operation are applicable. Provisions for additional 4

surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements. Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being

utilized as an exception to an individual requirement.

TRB 4.0.2 Requirement TR 4.0.2 established the limit for which the specified

' time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be - table for conducting the surveillance; e.g., transient ,

conditic o or other ongoing surveillance or maintenance activities. It als,

! provides flexibility to accommodate the length of a fuel cycle for l'

surveillances that are performed at each refueling outage and are specifieu with an 18-month surveillance interval. It is no' intended that this i - provision be used repeatedly as a convenience to' extend surveillance intervals

! beyond that specified for surveillances that are not performed during

_ refueling outages. The . limitation of TR 4.0.2 is based on engineering l

judgment and the recognition that the rest probable result of any particular *

- surveillance being performed is the verification of conformance with the O Surveillance Requirements This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

<f.QUOYAH UNITS 1 SD 2 B 3/4 0-3 "t THNICAL REQUIREMENTS 4_

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l_ APPLICABILITY BASES TRB 4.0.3 This Requirement establishes the failure to perform a Surveillance ,

Requirement within the allowed surveillance interval, defined by the i provisions of TR 4.0.2,-as a condition that constitutes a failure to meet the

OPERABILITY requirements for a Limiting Condition for Operation. Under tho provisions of this Requirement, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed j . within the specified time interval. However, nothing in this provision is to 3 be construed as implying that systems or components are OPERABLE when they are

found or known to be inorsrable although still meeting the Surveillance Requirements. This Requirement also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance i has not been performed and not at the time that the allowed aurveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance

! with the requirements of TR 4.0.3. However, this does not negate the fact that.the failure to have performed the surveillanca within the allowed a

surveillance interval, def:ned by the provisions of TR 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation.

) If the allowable outage time limits of the ACTION requirement are less than ,

, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (the allowable outaae time limits are dcfined as the first timeframe encountered in the ACTION requirement) or a shutdown is required to comply with ACTION requirements; e.g., TR 3.0.3, a 24-hour allowance is provided to l permit a delay in implementing the ACTION requirements. This provides an

adequate time limit to complete Surveillan: e Requirements that have not been 4

performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACL JN requirements i

or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes r consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, .. nd the safety ;

. significance of the delay in completing the required surveillance. This prov!sion also provides a time limit for.the completion of Surveillance Requi emonts that become applicable as a consequence of MODE changes imposed by AC 10N requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of TR 4.0.4 is allow 3d. If a surveillance is not completed within the 24-hour allowance, the time limits of .

the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are -

not met, the time limits of the ACTION requirements are applicable at the time !

that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requireanents define the remedial measures that apply.

However, the Surveillance Requiraments have to be met to demonstrate that ;

inoperable equipment has been restored to OPERABLE status. '

t SEQUOYAH UNITS 1 AND 2 B 3/4 0-4 TECHNICAL REQUIREMENTS l

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i APPLICABILITY DASES TRB 4.0.4 This Requirement establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement. The purpose of this Requirement is to ensure that system and component OPERA 3ILITY requirements or parameter limits are met before entry into a MODE or condition

. for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other spec 4fied conditions associated with plant shutdown as well as startup.

Under the provisions of this Requirement, the arplicable Surveillance Pequirements must be performed within the spectfied surveillance interval to ensure that the Limiting Conditions for Operations are met during initial plant startup or follv'ing a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of TR 4.0.4 do not apply because this would delay placing the facility in a lower MODE o" operation.

TRB 4.0.5 This Requirement ensures that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Clasr 1, 2, and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and

, Addenda as required by 10 CFR 50.55a.

L This Requirement includes a clarification of the frcquencies for performing the inaervice inspection and testing activities required by Section XI of +.he ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Requirements and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this Requirement, the more restrictive requiremencs of the Technical Requirements take precedence over the ASMr Boiler and Pressure Vessel Code and applicable Addenda. For example, tne requirements of TR 4 a.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE sr other specified applicability condition takes precedence over the ASME Boiler and Presrure Vessel Code provision which allowr pumps to be tested up to one week af ter return to normal operation. For example, the Technical Requirement definicion of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

SEQUOYAH UNITS 1 ANO 2 9 3/4 0-5 TECHNICAL REQUIREMENTS e hm - - - -

-TRB 3/4.7 PLANT SYSTEMS BASES TRB 3/4.7.1 SNUBBEPS Snubbers are designed to prevent unrestrained pipe or component motion under dynamic loads as might occur during an esrthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The con-sequence of an inoperable snubber la . screase in the probability of structural damage to piping or compone.J 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 operatio...

Because the snubber protection is required only daring relatively low probability events, a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 whether the mode of failure of the snubber has adversely affected any safety-related component or system.

Safety ~ elated snubbers are visually inspected for overall integrity and operability. Tne inspection will include verification of proper orientation, 3 adequate fluid level if applicable, and attachment of the snubber to its anchorage. The removal of insulation or the verification of torque values for threaued fasteners is net 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 t'. observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next required ir.spection. 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 tha original required time interval has elapsed (nominal time less 25 percent) may not be f 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 in a visual in.pection is clearly established and remedial for that snubber and for any other snubbers that may be generically susceptible and operability verified by inservice functional testing, if applicable, that snubber may be exempted from being caunted 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, 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 expe.cted 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 B 3/4 7-1 TECHNICAL REQUIREMENTS

PLANT SYSTEMS BASES SNUBBERS (Continued!

To further increase the assurance of snubber reliability, functional tests shall be performed during each refueling outage. These tcsts will .,

include stroking of the snubbers to verify proper movement, activation, and bleed or release. The performance of hydraulic snubbers 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 informati(n regarding the change during

(

the service of the snubber of the acceleration / :esistance 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 movement 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 testjng 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 al; required functional tests.

A list of individual snubbers with detailed information of snubber location and si:e shall be available at the plant in accorcance 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 operatiens (e.g.,

temperature, atmosphere, locr*. ion, etc.), and the recommendations of Regalatory Guide 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical snubber shall be mace in accordance with Section 50.59 of 10 CFR Part 50.

SEQUOYAH - UNITS 1 AND 2 B 3/4 7-2 TECHNICAL REQUIREMENTS j

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

6.1.1 Changes or additions to the Technical Requirements M nual 1,TRM) shall be made under appropriate administrative controls and reviews.

l 6.1.2 Changes or additions to the Technical Requirtments Manual (TRM) shall include an evaluation in accordance with 10 CFR 50.59.

l 6.1.3 Licensees may make additions to the TRM without prior NRC approval provided the changes have been determined not to be candidates for inclusion I

in the Technical Specifications (TS). The determination thet the changes do I

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

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 additions to the TRM implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR Sv.71(e).

SEQUOYAH - UNITS 1 AND 2 6-1 TECHNICAL REQUIREMENTS P

Table 4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column tl Column C or Category Extended Interval Repeat Interval Reduce Inter al (Notes 1 and 2) (hotes 3 and 6) (Notes 4 and 6) (Notes and 6) 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 R157 200 2 5 13 300 5 2 25 400 8 g 18 36 500 12 < 24 48 750 20 V 40 78 1000 or greater 29 56 109 Note 1: The next visual inspec on interval for a snubber population or category size shall b determined based upon the previous inspection interval and the nu er of unacceptabl- snubbers found during that interval. Snubber may be categorized, based upon their accessi-bility during po r operation, as accessible or inaccessible. These-categories may e examined separately or jointly. However, the licensee must ake and document-that decision before any inspection and shall us that decision as the basis upon which to determine the next inspe ion interval for that category.

Note 2: Interpo tion between population or category size and the number of unacce able snubbers is permissible. Use next lower integer for the lue of the limit for Co cmns A, B, or C if that integer in udes a fractional value of unacceptable snubbers as described by i erpolation.

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.

September 10, 1991 SEQUOYAH - UNIT 1 3/4 7-21a Amendment No.153 SEP 101991

Table 4.7.9-1 (continued)

, SNUBBER VISUAL INSPECTION INTERVAL Note 4: If the number of unacceptable snubbers is equal to or less than t l number in Column B but greater than the number in Column A, the xt inspection interval shall be the same as the previous interval R157 Note 5: If the number of unacceptable snubbers is equal to or great than i the number in Column C, the next inspection interval shall e two-thirds of the previous intarval. However, if the number f unaccep-table snubbers is less than the number in Coluno C but enter than the number in Column B, the next interval shall be re ced )ropor-tionally by interpolation, that is, the previaus int val s1all be reduced by a factor that is one third of the ratio f the difference between the number of unacceptable snubbers found uring the previous interval and the number in Column B to the diff ence in the numbers in Column B and C.

Note 6: The provisions of Specification 4.0.2 are a licable for all inspection intervals up to and including montins.

1 4,

4 v

ON

{

l October 4, 1995 SEQUOYAH - UNIT 1 3/4 7-21b Amendment No. 153, 213

PLAWT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) !

c. Visual Insoec. tion Performance and Evaluation Visual inspections shall verify (1) that there are no visible indic ions R16 of damage or impaired OPERABILTY, (2) bolts attaching the snubber the foundation or supporting structure are secure, and (3) snubbers tached to sactions of safety-related systems that have experienced une ected potentially damaging transients since the last inspection per d shall be evaluated for the possibility of concealed damage and functi ally _ tested, if applicable, to confirm operability.

Snubbers which appear inoperable as a result of visual spections may be determined OPERABLE for the purpose of establishing th next visual

! inspection interval, providing that (1) the cause of 1e rejection is clearly established and remedied for that particula snubber and for other snubbers that may be generically susceptib1 and (2) the affected snubber is functionally tested in the as-found c dition and determined [

OPERABLE per Specification 4.7.9.e. Hydraulic nubbers with inoperable R183 single or common fluid reservoirs which have covered fluid ports shall be declared inoperable.

Rid 3 Also, snubbers which have been made inop /able as the result of unexpccted transients, isolated damage or other su random events, when the provisions of 4.7.9.g and 4.7.9.h have been met d any other appropriate corrective action implemented, shall not be cou ed in determining the next visual inspection interval. R16

d. Functional Test Schedule. Lot Si e. and Comoosition During each refueling outage, representative 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 be ch test.

h9 Q/

SEQUOYAH - UNIT 1 3/4 7-22 Amendment No. 12, 153, 179 April 18, 1994

, i

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. Functional Test Schedule, Lot Size, and Comtosition (Continued)

The representative sample selected for functional testing shall in ude the various configurations operating environments, and the range f size and capacity of snubbers wIthin the groups or subgroups. The r resentative sample should be weighted to include more snubbers from severe service areas such as near heavy equipment. Unless a failure analys as required by 4.7.9.f indicates otherwise, the sample shall be a comp ite based on the ratio of each group to the total number of snubbers i talled in the plant. Snubbers placed in the same location as snubber which failed the R16 previous functional test shall be included in the nex est lot if the i

failure analysis shows that failure was due to locat n.

The security of fasteners for attachment of the s bbers *:.o the component and to the snubber anchorage shall be verifieg snubbers selected for functional tests. t

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

1. Activation (restraining action) s achieved within the specified range in both tension and tom ession, except that inertia dependent, acceleration limiting mechan al snubbers, may be tested to verify only that activation takes lace in both directions of travel.

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

3. The force required o initiate or maintain motion of the snubber is within the specif ed range in both directions of travel.

ht157 -

4. For snubbers ecifically required not to displace wder continuous load, the ab' ity of the snubber to withstand load without displace-ment shall e verified.

5. Testin ethods may be used to measure parameters indirectly or param ers other than those specified if those results can be R16 corr ated to the specified parameters through established methods.

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

September 10, 1991 SEQUOYAH - UNIT 1 3/4 7-23 Amendment No. 12 153 SEP 101E91

PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) _ /

f. Functional Test Failure Analysis and Additional Test lots (Continued)

If more than two snubbers do not meet the functional test acceptant criteria, an additional lot equal to one-half the original lot si shall be functionally tested for each fails.d snubber in excess of the o R16 allowed failures. An engineering evaluation shall be made of ch failure to meet the functional test acceptance criteria to de rmine the cause of the failure. The result of this analysis shall be sed, if applicable, in selecting snubbers to be tested in the subs uent lot in an effort to determine the operability of other snubbers ich may be subject to the same failure mode. (Selection of snubber for future testing may also be based on the failure analysis.) T sting shall continue until not more than one additional inoperab snubber is found within a subsequent required lot or all snubbers of he original inspec-tion group have been tested, or all suspect snubb s identified by the failure analysis have been tested, as applicable The discovery of loose or missing attachment steners will be evaluated to determine whether the cause may be locali ed or generic. The result of the evaluation will be used to select or er suspect snubbers for verifying the attachment fasteners, as ap l icabl e.

9 Snubbers shall not be subjected to - maintenance specifically for the purpose of meeting functional test uirements. ,

g. Functional Test Failure - Attac Comoonent Analv d1 M

For snubber (s) found inoperabl an er.gineering avaluation shall be performed on the components w ch are restrained by the snubber (s). The purpose of this engineering valuation shall be to determine if the I components restrained by t snubber (s) were adversely affected by the inoperability of the snub er(s), and in order to ensu.: that the restrained . pone,c re ins capable of meeting the designed service,

h. Functional Testina o Repaired and Snare Snubbers Snubbers which fa the visual inspection or the functional test acceptance criteria shall b repaired or replaced. Replacement snubbers and snubbers which have repe rs which might affect the functional test results shall be tested to et the functional test criteria before installation in the unit. Thes snubbers shall have met the acceptance criteria subsequent to their m t recent service, and the functional test must have been performe' within 12 months before being installed in the unit.

1. Snubbe Service Life Proaram The service life of hydraulic and mechanical snubbers shall be monitored t ensure that the service life is not exceeded between surveillance nspections. The maximum expected service life for various seals, springs, and other critical parts shall be determined and established kl8)

April 18, 1994 SEQUOYAH - UNIT 1 3/4 7-24 Amendment No. 12, 179

- )

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

1. Snubber Service life Proaram (Continued) based on engineering information and shall be extended or shorten d based on monitored test results and failure history. Critical parts all be replaced so that the maximum service -life will not be exceeded uring a period when the snubber is required to be OPERABLE. The part replacements shall be documented and the documentation shall be retained n accordance with Specification 6.10.2.n.

j .. Exemotion From Visual Insoection or Functional Tests Permanent or other exemptions from the surveillance ogram for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and if applicable snubber fe destructive testing was performed to qualify snubber operability for he applicable design conditions at either the completion of their f rication or at a subsequent date.

l R43 l

h Qi G

9 April 18, 1994 SEQUOYAH - UNIT 1 3/4 7-25 Amendment No. 39,179 m

_ - - _ . .- . _ _ _ . . _ _ - . - . - - . ~ - . - - - . - - ~ - _ - - . . - - - - - - _ . _ - _ - . .

3 PLANT SYSTEMS BASES

'!4.7.8 AUXILIARY BUILDING GAS TREATMENT SYST!

The OPERABILITY of the auxi 'ary building gas treatment system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are filtered prior to reaching the environment. The eperation of this system and the resultant effect on offr!.te dosage calculations was assumed in the accident analyses. ANSI N510-1975 will be used as a procedural guide for surveillance testing. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The minimum vacuum relief flow requirement in TS Surveillance Raquirement BR-6 4.7.8.d.3 is for test purposes only. It is intended to demonstrate an acceptable IcVel of ABGTS performance margin by simulating an ABSCE boundary breach. The inability to meet the specified minimum test condition under other circumstances does not challenge the operability of the ADGTS.

3/4.7.9 SNUBBERS Dus SPett F1t ATioN T.s DELETEb caut;-- E : ____,___ __ ,______ -reetrained pipe er re paa-at -ette- >

under dynamic loads as might occur during an earthquake or severe transie , !

while allowing normal thermal motion during startup and shutdown. The n-sequence of an inoperable snubber is an increase ir the probability o structural damage to piping or components as a resu.t of a seismic other event initiating dynamic loads. It is therefore required that a snubbers required to protect the primary coolant system or any other sa ty system or component be operable during reactor operation.

Because the snubber protection is required only d ing relatively low probability events, a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is allowed replace or restore the inoperable snubber (s) to operable status and perfo an engineering evaluat!on on the supported component or declare the suppor d system inoperable and follow the appropriate limiting conditi or eration statement for that 'R16 system. The engineering evaluation i ed to determine whether the mode of failure of the snubber has adverse ected any safety-related component or system. V Safety-related snubbers are sually inspected for overall integrity and operability. The inspection wi include verification of proper orientation, adequate fluid level if appli le, and attachment of the snubber to its anchorage. The removal of sulation or the verification of torque values for threaded fasteners is no required for visual inspections.

The inspectio requency is based upon maintaining a constant level of snubber prc*ectio . Thus, the required inspection interval varies inversely with the observ enubbrx failures. The number of inoperable snubbers found during a re ed inspection determines the time interval for the next required inspection Inspections performed before that interval has elapsed may be used as a new eference point to determine the next inspection. However, the resu, of such early inspections performed before the original required time int al has elapsed (nominal time less 25 percent) may not be used to lengthen t required inspection interval. 7ay inspection whose results require a hertcr inspc; tion- interval vill oveeridc the previou: : h:dule.

August 11, 1995 SEQUOYAH - UNIT 1 B 3/4 7-5 Amendment No. 12

-PLANT SYSTEMS BASES y

, r r v r y ,

-3 U000n3-fcontinu:S THIS IAGE bMD

. A A. _

W en the cause of the rejection of a snubber in a visuni inspection is e arly established and remedial fnr that snubber and for any other saubbers th may be generically susceptible and op -ability verified by inservice fune onal testing, if applicable, that snubber may be exempted from being coun .d as inoperable. Generically susceptible snubbera are those which are o a specific make or model and have the same design-features directly related t rejection of the snubber, or are similarly located or-exposed to the same vironmental-conditions such as temperature, radiation, and vibration. Test coups mav be established based on design features and installed conditions ' ich may 11 R157 expJcted to be generic. Each of these groups are tested sep ately unleas an e gineering analysis indicates the group is improperly cons tuted. All l- r; . pect snubbers are subject to inspection and testing re rdless of test l froupings.

[

To further increase the assurance of snubber rel ability, functional tests shall be performed during each refueling outag These teste will include stroking of the onubbers to verify proper ement, activation, and bleed or release. The performance of hydraulic sn bers generally depends on a clean, deaerated fluid contained within variable ressure chambers, flowing at l closely controlled rates. Since these characte stics are subject to change l with expo-sure to the reactor environment, tim , and other factors, their performance within the specified range shoul e verified. Mechanical snubbers which depend upon overcoming the inertia of mass and the braking action of a capstan spring contained within the snubbe for limiting the acceleration of the attached component (within the load r ting of the snubber) are not cubject to changes in performance in the same er as hydraulic snubbers. Pen-ing the development of information regardi the change during the service of the snubber of the acceleration /resistane relationship and the optimum method for detecting this change, these me al snubbers may be tested to verify that when subjected to a large chan velocity the resistance to movement increases greatly. The perfo e change information was developed in order lR157 to establish test methods to Sed during and after the first refueling outage.

Ten percent of th Ot 1 population of snubbers is an adequate sample for lR157 functional tests. The inI al sample is to be proportioned among the groups in order to obtain a represe ative sample. Observed failures of more than two snubbers in the initial ot will require an engineering analysis and testing of additional snubbers se eted from snubbers likely to have the same defect. A thorough inspection o the snubber threaded attach-ments to the pipe or components and the a chorage will be made in conjunction with all required functionai tests.

A list of redividual snubbers with detailed information of snubber loca-

, tion and size all be available at the plant in accordance with R43 Section 50.71 ) of 10 CFR Part 50. The accessibility of each snubber shall be lR157 determined b/ sed upon the existing radiation levels and the expected time to perform a v sual inspection in each snubber location as well as other factors R43 associate with accessibility during plant operations (e.g., temperature, atmosphe e, September 10, 1991 SEQUOYAH - UNIT 1 B 3/4 7-6 Amendment No. 39. 153 r >

PLANT SYSTEMS BASES

- " '"s : " "". 0 'C:ntired}

1;;;'.ic , :tc.}, --' ,^

__n2m2__ __ 2_,_.4_ .s

w,a

- n ...,tirn:

'I 4- _

___".25ul:t cf t.:

ry Cuid: _uS.S, , and

_.,__..tt- t- 4.10

- 2.

. 4- Th R43 1552 1" l'.l55 5::$'-E 50$ 5? :fic 5""'r :t 505 3/4.7.10 SEALED SOURCE CONTAMINATIOff The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, BR-3 and special nuclear naterial sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurtte with che probability of damage to a source in that group. Those sources which are frequently bandled are required to be tested more often than those which are not. Sealed turces which are continuously enclosed within a shielded mechanism (i.e., aaled sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

3/4.7.11 FIRE SUPPRESSION SYSTEMS i

R231 This specification is deleted, l

l August 12,1997 SEQUOYAH - UNIT 1 B 3/4 7-7 Amendment do. 39, 227

ADMINISTRATIVE CONTROLS 6 10 The following records shall be retained for the duration of the Unit rating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

D b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation centrol areas.

d. Records of gaseous and liquid radioactive material released to the

% environs and the resulting calculated dose to an individual member of R178 q the public,

e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the D facility staff.

h. Records of in-service inspections performed pursuant to these R78 f

Technical Specifications.

Nl% 1. Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Plan, i ;37 s J. Records of reviews performed for changes made to procedures or equip-k ment cr reviews of tests and experiments pursuant to 10 CFR 50.59.

b k. Records of meetings of the PORC and the NSRB.

R182l k.N-p 1. Records of analyses required by the radiological environmental

% monitoring program.

y m. Records of secondary water sampling and water quality.

' n. Records of the service life monit n of etv-related l

hydraulic and mechanical snubber t m i nd by T/S g including the maintenance performed to ren e er e tire

o. Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12)(b) of License No. DPR-77. R62

p. Records of reviews performed'for changes made to t'e n0FFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. R152 March 31, 1994 SEQUOYAH - LHIT 1 6-23 Amendment Nos. 42, 58, 74, 148, 163, 174, 178

e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM . . . . . . . . . . . 3/4 7-13 3/4.7.5 ULTIMATE HEAT SINK . . . . . . . . . . . . . . . . . . . 3/4 7 14 3/4.7.6 FLOOD PROTECTION PLAN . . . . . . . . . . . . . . . . . . 1/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . . . . . . . 3/4 7-17 3/4.7.8 AUXILIARY BUILDING GM TREATMh.NT w SYSTEM ~ . . . . . . . . . 3/4 7-19 l

3/4.7.9 SNUBBERS E.L N . . . . . . . . . . . . . . . . . . . 3/4 7 '!1

~ - -

, , A + #

3/4.7.10 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . . 3/4 7-41 3/4.7.11 FIRE SUPFRESSION SYSTEMS (DELETED) . . . . . . . . . . . 3/4 7-43 R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) . . . . . . . . . . . 3/4 7-52 3/4.8 ELECTRICAL POWER SYSTEMS J

3/4.8.1 A.C. SOURCES Operating . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 Shutdown .

. . . . . . . . . . . . . . . . . . . . . . . 3/4 8-9 3/4.8.2 ONSITE POWFR DISTRIBUTION SYSTEMS A.C. Distribution - Operating . . . . . . . . . . . . . . 3/4 8-10 A.C. Distrioution - Shutdown . . . . . . . . . . . . . . 3/4 8-11 D.C. Distribution - Operating . . . . . . . . . . . . . . 3/4 8-12 D.C. Distribution - Shutdown . . . . . . . . . . . . . . 3/4 8-15 August 12, 1997 5,EQUOYAH - UNIT 2 IX Amendment No. 218

-- - - . _. . . _ _ _ - _ _ - _ . - - ._~ ..-_ - - -

1 IFDEX 1 l

BASES I

-~=

SECTION P.h91 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM . . . . . . . . . . . B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK . ....... . . . . . . . . . . . B 3/4 7-4 3/4.7.6 FLOOD PROTECTION . . ....... . . . . . . . . . . . B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . . . . . . . B 3/4 7-4 3/4.7.8 ILIARY BUILDING GAS S.IJ . . B 3/4 7-5 3/4.7.9 SNUBBERS (D E \ mE.M . . . . .s . . . . . . . . . . +. . . . B 3s / 4 7-5 A x +-

3/4.7.10 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . B 3/4 7-6a 3/4.7.11 FIRE SUPPRESSION SYSTEM 3 (DELETED) . . . . . . . . . . . B 3/4 7-7 R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) . . . . . . . . . . . B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS . . . . . . . ...... . . . . . . . . . . . . B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES . . . . . . . . . B 3/4 8-2

{

3/4.9 REFUELING OPERATIONS r

3/4.9.1 BORON CONCENTRATION . ....... . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRUMENTATION , . . ...... . . . . . . . . . . . . B 3/4 9-1 3/4.9.3 DECAY TIME . . . . . .......... . . . . . . . . B '/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . . . . . . . . . B 3/4 9-1 3/4.9.5 COMMUNICATIONS . . . .......... . . . . . . . . B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE . . .... . . . . . . . . . . . . . . .B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA (DELETED) . . . . . . B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCU'.ATION . . . . . . B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM . . . . . . . . . . . . B 3/4 9-3 August 12, 1997 SEQUOYAH - UNIT 2 XIV Amendment Nc. 194, 218 i

PLANT SYSTEMS 3/4.7.9 ' SNUBBERS LIMITING CONDITION FOR OPERATION

' v THis seccitic. ATioro Is bettTsb.

3.7.9 ^" ::fety-rchted rdb:r: :h: b; Or:RACLE. - g31

-_ , s - -

ArrLICAOILIT'/. " eda 1, 2, 2 :.d i. '"00:0 5 and C for :nubbers located -

systems or partial systems required OPERABLE in those MODES.)

ACTION: g y@

With one or more snubbers 75 e, w; thin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubbrz o OPERABLE status and perform an engineering evaluation o

p;approprictttc

m. hed component ACTIOM ; tat =;ntor fordeclare the attached system inoperable and follow that system.

g v N v PACES 3/4 7-2 l THuuc H 3/4 b 2E Au DELETED.

~ > %. ,

WE-KLANCE REQUIR0iENTS l

4.7.9 Each safety-related snubber shall be demonstrated OPERABLE by '

performance of the following augmented inservice inspection program a the requirements of Specification 4.0.5. R31 a, , Inspection Groups The snubbers may be categorized into two major oups based on whether the snubbers are accessible or inacc 1ble during reactor operation. These major groups may be furt r subdivided into subgroups based on design, environment, other features which may be expected to affect the OPERABILITY the snubbers within the subgroup. Each subgroup may be tes d independently in accordance with 4.7.9.d through 4.7.9.h. R143

b. Visual Inspection Schedula All of the safety-rela snubbers shall be included in one population or they shall be cat nrized as accessible or inaccessible for visual inspection. If u , the accessible or inaccessible categories shall be considered s rately for visual inspections. R143:

When reco i g cate ories into one population, the shorter interval of the gories sha 1 be used.

Th isual inspection interval for the population or each category all be determined based upon the criteria provided in Table 4.7.9-1, and the 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 incorp;rcted thi; change W:: is:ued by th: NRC.

SEQUOYArt - UNIT 2 3/4 7-21 Amendment No. 31,143 SEP 10 Ei ______J

Table 4.7.9-1

, SNUBBER VISUAL INSPECTION INTERVAL f

NUMBER OF UNACCEPTABLE SNUBBERS Population column A column B Column C or Category Extendad Interval Repeat Interval Reduce Inter 1 (Notes 1 and 2) (Notes 3 and 6) (Notes 4 and 6) (Notes and 6) 1 0 0 1 80 0 0 2 100 0 -

1 4 150 0 3 8 200 2 5 13 300 5 25 400 8 18 36 500 12 <) 24 48 750 20 g- 40 78 gi4 1000 or greater 29 56 109 Note 1: The next visual inspecti interval for a snubber population or category size shall bg/ determined based upon the previous inspection interval and the numpbr of unacceptable snubbers found during that interval. Snubber may_be categorized, based upon their accessi-bility during po operation, as accessible or inaccessible. These categories may examined separately or jointly. However, the licensee must jfake and document that decision before any inspection and shall usvthat decision as the basis upon which to determine the next inspe fion interval for that category.

Note 2: Interpol ion between population or category size and the number of unacce abic snubbers is permissible. Use next lower integer for the v ue of the limit for Columns A, B, or C if that integer inc des a fr:ctional value of unacceptable snubbers as described by i erpolation.

Note 3: f 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.

SEQUOYAH - UNIT 2 3/4 7-21a Amendment No.143 SEP 101931

Table 4.7.9-1 (continued)

SNUBEER VISUAL INSPECTION INTERVAL Note 4- If the number of unacceptab.2 snubbers is equal to or less than e number in Column B but greater than the number in Column A, the ext inspection interval shall be the same as the previous interva .

R143 Note :: If the number of unacceptable snubbers is equal to or grea r than the number in Column C, the next inspection interval shai" be two-thirds of the previous interval. However, if the number of unaccep-table snubbers is less than the number in Column C but reater than the number in Column B, the next interval shall be re uced propor-tionally by interpelation, that is, the previous in rval shall be reduced by a factor that is one third of the ratio of the difference between the number of unacceptable snubbers foun during the previous interval and the number in Column B to the diff ence in the numbers in Column B and C.

Note 6: The provisions of Specification 4.0.2 are a plicable for all inspectior, intervals up to and including months.

i 9

d' l

s t

September 10, 1991 SEQUOYAH - UNIT 2 3/4 7-21b Amendment No.143 SEP 101001

PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS ,

c. Visual Insoection Performance and Evaluation Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) bolts at ching the snubber to the foundation or supporting structure are cure, and (3) snubbers attached to sections of safety-related syst s that have experienced unexpected aotentially damaging transi ts since the last inspection period s1all be evaluated for the ossibility of concealed damage and functionally tested, if applica e, to confirm operability.

Snubbers which appear inoperable as a result of isual - inspections may be determined OPERABLE for tha purpose of stablishing the next visual inspection interval, providing that ( the cause of the rejection is clearly established and remedi d for that particular snubber and for other snubbers that may b generically susceptible; and (2) the affected snubber is function ly tested in the as-found gily t l condition and determined OPERABLE per ecification 4.7.9.e.

' Hydraulic snubbers with inoperable si gle or common fluid reservoirs which have uncovered fluid ports sh 1 be declared inoperable, gi71 4

April 18, 1994 SEQVOYAH - UNIT 2 3/4 7-22 Amendment No. 2, 143, 171 m

PLANT SYSTEMS Sl!RVEILLANCE REQUIREMENTS (Continued) / c

c. Visual Inspection Performance and Evaluation (Cont'd)

Also, snubbers which have been made inoperable as the resul of unexpected transients, isolated damage or other such rando events, when the provisions of 4.7,9.g and 4.7.9.h have been met nd any other appropriate corrective action implement 0d, shall t be counted in determining the next visual inspection interval.

d. Functional Test Schedule, Lot Size, and Compositio During each refueling outage, a representative mple of 10% of the total of the safety related snubbers in use i he plant shall be functionally tested either in place or in a nch test. u The representative sample selected for fu tional testing shall include the various configurations, oper ing environments, and the range of size and capacity of snubbers - itha the groups or subgroups.

The representative umple should be ighte *o include more snubbers from severe service areas such as ny r heavy equipment. Unless a failure analysis a3 required by 4.7.9.f indicJtes otherwise, the sample shall be a composite base on the ratio of each group to the total number of snubbers insta ed in the plant. Snubbers placed in the same location as snubbers hich failed the previous functional test shall be included in t next test lot if the f ailure analysis shows that failure was e o location.

The security of fast for attachment of the snubbers to the component and to th ubber anchorage shall be verified on snubbers selected for fun 1 tests,

e. Functional Test ceptance Criteria The snubber f ctional test she verify that:

1. Activ ion (restraining act. ton) is achieved within the specified rang in both tension and compres: ion, except that inertia de ndent, acceleration limiting mechanical snubbers, may be t ted to verify only that activation takes place in both irections 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 "nitiate or maintain motion of the snubber is within the specified range in both directions of travel.

R143 SEQUOYAH - UNIT 2 3/4 7-23 Amendment No. 2, 143 SEP 10 01

PLANT SYSTEMS 4

SURVEILLANCE REQUIREMENTS (Continued) /

e. Functional Test Acceptance Criteria (Cont'd) lR143

4. For snubbers specifically required not to displace und r contiauous load, the ability of the snubber to withs nd load without displacement shall be verified.

5. Testing methods may be used to measure parameter indirectly or parameters other than those specified if those esults can be .

correlated to the specified parameters throu established

l methods.

f. Functional Test Failure Analysis and Additions Test Lots If any snubber selected for functional ! either fails.to lock i up or fails to move due to manufacture e gn deficiency, all l

snubbers of the same design subject e same defect shall be functionally tested, g If more than two snubbers do not m t the functional test acceptance criteria, an additional lot equal o one-half the original lot size shall be functionally tested for each failed snubber in excess of the two allowed failures. An gineering evaluation shall be made of each failure to meet the nctional test acceptance criteria to determine the cause of the allure. The result of this analysis shall be used, if applica e, in selecting snubbers to be tested in the subsequent lot in an effort to determine the operability of other snubbers which mp be subject to the same failure mode.

(Selection of snubber for futuri ' nting may also be based on the failure analysis.) esting shall s .nue until not more than one additional inoper e snubber is founs 'hin a subsequent required lot, or all snub rs of the original inspection group have been tested, or all uspect snubbers identified by the failure analysis have been tes d, as applicable.

The discovp y of loosa or missing attachment fasteners will be evaluatecVto determine whether the cause may be localized or generic.

The result of the evaluation will be used to select other suspect lR143 snubb (s for verifying the attachment fasteners, as applicable.

Snybbers shall not be subjected to prior maintenance specifically f r the purpose of meeting functional test requirements.

SEQUOYAH - UNIT 2 3/4 7-24 Amendment No. 2 143

. SEP 10 Oi

PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) ,

g. Functional Test Failure - Attached Component Analysis For snubbers (s) found inoperable, an engineering evaluation sh 1 be performed on the components which are restrained by the snub r(s).

The purpose of this engineering evaluation shall be to det ine if the components restrained by the snubber (s) were adversel affected by the inoperability of the snubbers (s), and in order to e ure that the restrained component remains capable of meeting the de gnod service.

h. Functional Testino of Repaired and Soare Snubbers Snubbers which fail the visual inspection or the unctional test acceptance criteria shall be repaired or repla d. Replacement snubbers and snubbers which have repairs whic might affect the functional test results shall be tested to et the funtional test l

criteria before installation in the unit. hese snubbers shall have met the acceptance criteria subsequent t their most recent service, and the functions 1 test must have been erformed within 12 months l

' before being installed in the unit.b A

l i. Snubber Service life Procram V

R171 The service life of hydraulic mechanical snubbers shall be moni-tored to ensure that the servi e life is not exceeded between surveil-lance inspections. The maxi 'm expected service life for varicus seals, springs, and other c itical parts shall be determined and established based on engi ering information and shall be extended or shortened based on monit red test results and failure history.

Critical parts shall b replaced so that the maximum service life will not be exceeded duri a period when the snubber is required to be OPERABLE. The part replacements shall be documented and the documen-tation shall be r ained in accordance with Specification 6.10.2.n.

J. Exemotion From isual Insoection or Functional Tests Permanent or other exemptions form 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 destruc ve testing was performed to qualify snubber operability for the a licable design conditions at either the completion of their R31 fabr)ationoratasubsequentdate.

SEQUOYAH - UNIT 2 3/4 7-25 Amendment No. 31, 104, 171 April 18, 1994 9

PLANT SYSTEM 1 BASES 3 /4 . 7. 8 AUXILIARY BUILDING GAS TREA'IHENT SYSTEM The OPERABILITY of the auxiliary building gas treatment system ensures that radioactive materials leaking from the.ECCS equipment following a LOCA are filtered prior to reaching the en**ironment. The' operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses. ANSI N510-1975 will be used as a procedural guide for surveillance testing. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The minimum vacuum relief flow requirement in TS. Surveillance Requirement 4.7.8.d.3 is for test purposes only. It is intended to demonstrate an ER-8 acceptable level of ABGTS performance margin by simulating an ABSCE boundary breach. The inability to meet the specified minimum *.est condicion under other circumstaneen does not challenge the operability of tue ABGTS.

~

3/4.7.9 SNUBBERS mts SPEuFIc ATI T

-Gauwt. :: ::= : %.. 1 -T, . . .:.~5 ==M ==rGh: s bE1.Q r .w. ,

-r-...... - -. . .s& '

dynamic loads as might occur during an earthquake or severe transient, while allowing normal themal motion during startup and shutdown. The consequene of an inoperable snubber is an increase in the probability of structu. al dam e-to piping or components as a result of a seismic or other event initiatin ynamic loads. It is there M e required that all snubbers required to prote the primary coolant system or any other safety sysum or component be erable during reactor operation.

Because the. snubber protection is required only during rela ely low probability events, a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is allowed to re ace or restore the inoperable snubber (s) to operable status and perform a ngineering evaluation on the supported component or declare the supported stem inoperable and follow the appropriate limiting condition for oper ion statement for that system. The engineering evaluation is performe o detemine whether the mode of failure of the snubber has adversely af d any safety-related component or system.

R2 Safety-related snubbers are visuall h pected for overall integrity and operability. The inspection will i lude verification of proper orientation, adequate fluid level if applicabl and attachment of the snubber to its anchorage. The removal of insu ion or the verification of torque values for threaded fasteners is not re red for visual inspections.

The inspe.: tion frequency a based upon maintaining a constant level of snubber protection. Thits , the equired inspection interval varies inversely with the observed snubber fa res. The number of inoperable snubbers found during a required inspecti determines the time interval for the next required inspection. In ections performed before that interval has elapsed may be used as a new ref nce point to determine the next inspection. However, the results of uch early inspections performed before the original required time interval as elapsed (nominal time less 25 percent) may not be used to lengthen the r ired inspection interval. Any inspection whose results require a

/_ _ .

August 11, 1995 SEQUOYAH - UNIT 2 B 3/4 7-5 Amendment 2

_a

PLANT SYSTEMS BASES

- - - - - ~_ _

iH,5 Puc Is terreFo 3/4.7.0 SNUBSERS (cont'd) i

^ N ~: t2 When the cause of the rejection of a snubber in a visual inspection is early established and remedied for that snubber and for any other snubbers at may be generically susceptible and operability verified by inservice fu tional testing, if applicable, that snubber may be exempted from being c nted as inoperable. Generically susceptible snubbers are those which ar of a specific make or model and have the same design features directly relat to rejection of the snubber, or are similarly located or exposed to the s .e environmental conditions such as temperature, radiation, and vibration. st groups may be established based on design features and installed condit ns which may be expected to be generic. Each of these groups are teste separately unless an R143 engineering analysis indicates the group 1s improp onstituted. All suspect snubbers are subject to inspection and te T regardless of test groupings.

v To further increase the assurance of snubber $ ability, functional tests shall be performed during each refueling outa . These tests will include stroking of tne snubbers to verify proper mo ment, activation, and bleed or release. The performance of hydraulic snu ers generally depends on a clean, deaerated fluid contained within variabl pressure chambers, flowing at closely controlled rates. Since these characte stics are subject to change with exposure to the reactor environment, me, and other factors, their performance R2 within the specified range should b verified. Mechanical snubbers which depend upon avercoming the inertia f a mass and the braking action of a capstan spring contained within e snubber for limiting the acceleration of the attached component (within e load rating of the snubber) are not subject to changes in performance in e same manner as hydraulic snubbers. Pending the development of informat' n regarding the change during the service of the snubber of the acceleratio / resistance relationship and the optimum method for detecting this change, t se mechanical snubbers may be tested to verify that when subjected to a lar e change in velocity the resistance to movement i increases greatly. T e performance change information was developed in iR143 order to establish st methods to be used during and after the first refueling R2 outage.

Ten percent of he total population of snubbers is an adequate sample for l R143 functional t ts. The initial sample is to be proportioned among the groups in order to ob ain a representative sample. Observed failures of more than two snubbers the initial lot will require an engineering analysis and testing of R2 additio 1 cnubbers selected from snubbers likely to have the same defect. A thoro inspection of the snubber threaded attachments to the pipe or comp ients and the anchorage will be made in conjunction with all required fu tional tests.

September 10, 1991 SEQUOYAH - UNIT 2 B 3/4 7-6 Amendment No. 2 143

~

SEP 10 Q

BASES

-3/?.7.0 SNUSSERS (:O r.t ' d)

A l'st of Individual snubbers with detailed information er location and size shall be available at the plant ccordanc ection 50.71(c) of 10 CFR Part 50. The accessibili er shall be determined based upon the existing radiati the expected time to perform a R14:

visual inspection in each snub ~

o cation as well as other factors associated with accessibility dur ant operations (e.g. , temperature, atmosphere, R31 ;

location etc. the recommendations of Regulatory Guide 8.8 and 8.10. The '

addit deletion of any hydraulic or mechanical snubber shall be made in m;rtr:: eith S;; tier. 50.50 of 10 CTP, Part 50. '

3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requi ing leak testing, including alpha emitters, based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required i to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

SE000YAH - UNIT 2 B 3/4 7-6a Amendment No. 31, 143 Septem , L99L c.tj,,10 b J

l ADMINISTRATIVE CONTROLS

[6.10.2]ThefollowingrecordsshallberetainedforthedurationoftheUnit Operating License: R28

a. Records and drawing changes reflecting unit design modifications made l to systems and equipment described in the Final Safety Analysis Report

b. Records of new and irradiated fuel inventory, fuel tr,.'sfers and assembly burnur histories.

A') c. Records of radiation exposure for all individuals entering raajation control areas.

d. Records of gaseous and liquid radioactive material rel' .

k environs and the resulting calculated dose to an indi s of R165 4 the public.

\% e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.

h f, Records of reactor tests and experimeats.

Av

g. Records of training and qualification for current members of the facility staff.

9 h. Rccords of in-service inspections performed pursuant to these k Technical Specifications 4

Qj i. Records of Quality Assurance activities required for lifetime reten- R50 q tion by the Nuclear Quality Assurance Plan. R153 eM j. Records of reviews performed for changes made to procedures or equip-N ment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k f k. Records of retings of the PORC and the NSRB.

g169l

1. Records of analyses required tj i.he radiological environmental N monitoring program.

I k m. Records of secondary water sampling and water quality.

n. Records of the service life p -

.-related hydrau-lic and mechanical snubber u= b 7'S ,.7.0 neluding the maintenance performed to re -ybie I serv {

D i

y o. Records for anvironmental qualification which are covered under the provisions of paragraph 2.C.(10)(b) of license No. DPR-79.

g30 S, j

p. Records of reviews perfor ed for changes made to the OFFSITE DOSE CALCULATION MANUA! and u.a PROCES L'NTROL PROGRAM. R134 March 31, 1994 SEQUOYAH - UNIT 2 6-24 Amendment No. 28, 50, 66, 134, 153, 165,169 m s ,

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-97-04 REVISED PAGES I. AFFECTED PAGE LIST Unit 1 Index Page IX Index Page XIV Operating License Page 8 3/4 7-21 B 3/4 't-5 B 3/4 '-6 B 3/4 7-7 6-23 Unit 2 Index Page IX Index Page XIV 3/4 7-21 B'3/4 7-5 B 3/4 7-6 B 3/4 7-6a 6-24 II. REVISED PAGES See attached.

4 E3-1 w :.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS EFCTION PAGE i

3/4.7.5 ULTIMCE HEAT SINK . . . . . . . . . . . . . . . . 3/4 7-14 I 3/4.7.6 FLOOD PROTECTION . . . . . . . . . . . . . . . . . . . . 3/4 7-15 Rf,5 3/4.7.7 CONTROL ROOM EME2GENCY VENTILATAON SYSTEM . . . . . . . . 3/4 7-17 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM . . . . . . . . . 3/4 7-19 3 / 4 . ~3 . 9 SNUBBERS (DELETED) . . . . . . . . . . . . . . . . . 3/4 7-21 l ,

3/4.7.10 SEALED SOURCE CONTAMINATION 3/4 7-29 f

3/4.7.11 FIRE SUPPRESSION SYSTEN'S (DELETED) . . . . . . . . . . . 3/4 7-31 R231 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) . . . . . . . . . 3/4 7-41 3/4.8 ELECTRICAL POWER SYSTEMS

{ R65 3/4.8.1 A.C. SOURCES OPERATING , . . . . . . . . . . . . . . . . . . . . 3/4 8-1 SHUTDOWN . . . . . . . . . . . . . . . . . . . . 3/4 8-8 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBJ. ION - OPERATING , . . . . . . . . . . . . . 3/4 8-9 A.C. DISTRIBU'1 ION - SEUTDOWN . . . . . . . . . . . . 3/4 8-10 D.C. DISTRIBUTION - OPERATING . . . . . . . . . . . 3/4 S.11 D.C. DISTRIBUTION - SHUTDOWN . . . . . . . . . . . . 3/4 8-14 3/4.8.3 ELECTRICA EQUIPMENT PROTECTIVE DEVICES CONTAINMENT DEhETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES . . . . . . . . . . . . . 3/4 8-15

=

W b_

k ut s SEQUOYAH - UNIT 1 IX Amendment No. 61, 227, I

L' \

m g- .

J

JNDEX BASES SECTION PAGE {,

3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM , . . . . . . . . . . B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK (UHS) . . . . . . . . . . . . . . . . B 3/4 7-4 I 3/4.7.6 FLOOD PROTECTION . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . . . . . . . B 3/4 7-4 3/4.7.8 AUXILIARY BUILDING JAS TREATMENT SYSTEM . . . . . . . . . B 3/4 7-5 3/4.7.9 SNUBBERS (DELETED) . . . .

. . . . . . . . . . . B 3/4 7-5 l 3/4.7.10 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . B 3/4 7-7 3/4.7.11 FIRE SUP'RESSION SYSTEMS (DELETED) . . . . . . . . . . B 3/4 7-7 R231 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) . . . . . . . . . . B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4. 8.1 std 3/4. 0. 2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS . . . . . . . . . . . . . . B 3/4 0-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES . . . . . . . . . B 3/4 8-2 l

3 /.* . 9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.3 DECAY TIME , . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 CONTAINME*IT BUILDING PENETRATIONS . . . . . . . . . B 3/4 9-1 3/4.9.5 COMMUNICATIONS . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4 9.6 MANIPULATOR CRANE . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SFENT FUEL PIT AREA (DELETED) . . . . . . B 3/4 9-2 lR208 3/4.9.8 RESIDUAL HFAT REMOVAL AND COOLANI CIRCULATION . . . . . . B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM . . . . . . . . B 3/4 9-3 SEQUOYAH - UNIT 1 XIV Amendment No. 157, 204, 227, i

.g.

(19) Mecchanical Snubbers This condition is deleted.

l (20) 1.ow Temoerature Overoressure Protection (Section 5.2.2)

At the firs' outage of sufficent duration but no later than startup following the second refueling outage, TVA shall install an overpressure mitigation system l )

which meets NRC require. .ents.

[R27 i I

(21) Q.o.trirni Rod Guide Thimble (Seuion 4.2) l l l

Prior to startup after first refueling, TVA shSil submit the details of the inspection program for ccontrol rod guide thimble tube wall wear for NRC approval.

(22) TMI Action Plan Full Power Conditions Each of the fo!!owing conditions shall be completed to the satisfaction of the NRC by the times indicated:

A. Safety Enaineerina G oun (Section 22.2.l.B.1.2)

Prior to exceeding fu ,3ercent power, TVA is required to have an onsite Safety Engineering Group. NRC will verify the adequacy of the Safety Engineering G,oup and its independence.

B. Short-Term Accident Analysis and Procedure Revision (Section 22.2.1.C.11 Within thirty effective fullcov er days, TVA shall revise Emergency Operating Procedures and brief the opere . ors on the revision.

C. Control Room Desiap (Section 22.2.l.D.11 TVA shall considor the benefits of installing cata recording and logging l equipment in the control room to correct the deficiencies associated with l the trending of important parameters on strip chart recorders used in the l control room as part of the Detailed Control Room Dasign Review. l Implementation shall be carried out in occordance with SECY 82-1118. lR27 l

I i

l Amendment 23

.. .. --- =

. PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9. This cpecification i.s deleted.

l t

t I

(Pages 3/4 7-21 thrcugh 3/4 -25 are deleted) l s'

SEQUOYAH - UNIT 1 3/4 7-21 Amendment No. 39, 153, 213 1

-_ , ___s

1 1

\ ..

1 ELANT SYSTEMS BASES 3/4.7.O AUXILIARY BUTLDING GAS TREATMEN SYSTEM The OPERABILTTY of the auxiliary building gas treatment system ensures that radioactive ma*.erials 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. ANSI N510-1975 will be used as a procedural guide for surveillance testing. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The minimum vacuum relief flow requirement in TS Surveillance Requirement BR-6 4.7.8.d.3 is tor test purposes only. It is intended to demonstrate an acceptable level of ABGTS performance margin by simulating an ABSCE boundary breach. The inability to meet the specified minimum test condition under other circumstances does not chal?2rge the operability of the ABGIS.

3/4.7.9 SNUBBERS This specification is deleted. .

SEQUOYAH - UNIT 1 B 3/4 7-5 Amendment No. 12,

1 l

1 PLANT SYSTEMS RASES I

.)

I This page is deleted l

SEQUOYAH - UNIT 1 B 3/4 7-6 Amendment No. 39, 153,

i PLANT SYSTEMS BASES 3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, BR-3 and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unlcss they are removed from the shielded mechanism.

3/4.7.11 FIRE SUPPRESSION SYSTEnd R231 This Specification is deleted.

t SEQUOYAH - UNIT 1 E 3/4 7~7 Amendment NO. 39, 227, a b

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM . . . . . . . . . . . 3/4 7-13 3/4.7.5 ULTIMATE HET.T SINK . . . . . . . . . . . . . . . . . . . 3/4 7-14 3/4.7.6 FLOOD PROTECTION PLAN . . . . . . . . . . . . . . . . . . 3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . . . . . . 3/4 7-17 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM . . . . . . . . . 3/4 7-19

- 3 /-4 . 7. 9 SNUBBERS (DELETED) . . . . . . . . . . . . . . . . . . . 3/4 7-21 l 3/4.7.10 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . . 3/4 7-41 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DCLETED) . . . . . . . . 3/4 7-43 R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) . . . . . . . . . . 3/4 7-52

),,/.idJsLECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 Shutdown . . . . . . . . . . . . . . . . . . . . . 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating . . . . . . . . . . . . . . 3/4 8-10 A.C. Distribution - Shutdown . . . . . . . . . . . . . . 3/4 8-11 D.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-12 D.C. Distribution - Shutdown . . . . . . . . . . . . 3/4 8-15 r

SEQUOYAH - UNIT 2 IX Amendment No. 218,

ADMINISTRATIVE CONTROLf'

=

[6.10 The following records shall be retained for the duration of the Unit Operating Licer.ae:

a. Records and drawing changes reflecting unit design modifications made to systems and equip.nent described in the Final Safety Analysis Report,

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

}A c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs and the resulting calculated dose to an indir!. dual member of the public. R178 l g.

'l

e. Records of transient or operational cycles for those unit components l identified in Table 5.7-1.

f. Recore of reactor tests and experiments.

g. Records of training and qualification for current members of the facility staff.

R78 -

h. Records of in-service inspediens performed pursuant to these Technical Specificat'.cns.

D 1. Records of Quality Assurance activities required for lifetime reten-h tion by the Nuclear Quality Assurance Plan. '

q R167

j. Records of reviews performed fcr changes made to procedures or lw equipment or reviews of tests and experiments oursuant to 1] 10 CFR 50.59.

'( k. Records of meetings of the PORC and the NSRB.

lR182

( l. Records of analyses required by the rediological environmental monitoring program.

$O,

m. Records of secondary water sampling and water quality.

, n. Pecords of the service life monitocing of all safety-related hydraulic and mechanical snubbers including the maintenance performed to renew the serrice life.

b

o. Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c. (12) (b) of License M. DPR-77. R62 ]

p. Records of reviews performed for changes made to the OFFSITE DOSE h CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

R152 SEQUOYAH - UNIT 1 6-23 Amendment Nos. 42, 58, 74, 140, 163, 174, 176, b-

1 E{ ANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR CPERATION

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3.7.9 This specification is deleted.

(Pages 3/4 7-21 through 3/4 7-25 are deleted) l 1

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SEQUOYAH - UNIT 2 3/4 7-21 Amendmeit Nos. 31, 143, l l

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( *l i I #

'g) "

th '---

PLANT SYSTEMS BASES 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTJM The OPERABILITY of the auxiliary building gas treatment system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are .

j 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. ANSI N510-1975 will be used as a procedural guide for surveillance testing. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters- i The minimum vacuum relief flow requirement in TS Surveillance Requirement 4.7.8.d.3 is for test purposes only. It is intended to demonstrate an BR-8 acceptable level of ABGTS performance margin by simulating an ABSCE boundary breach. The inabi.ity to meet the specified minimum test condition under other circumstances does not challenge the operability of the ABGTS.

2/4.7.9 SNUBBERS l

This specification is deleted.

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SEQUOYAH - UNIT 2 B 3/4 7-5 Amendment 2,

(

E-PLANT SYSTEMS BASES l

m

,u, k This page is deleted s

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1-dr.

i SEQUOYAH - UNIT 2 B 3/4 7-5 Amendment Nos. 2, 143, r

BASES 3/4.7.10 SEALisD SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commyneurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanium (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

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SEQUO'IAH - UNIT 2 B 3/4 7-6a Amendmeat Nos. 31, 143, o

ADMINISTRATIVE CONTROLS 6.10 M The following records shall be ret Aned for the duration of the Unit R28 fperating License:

a. Records and drawing changes reflecting unit 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 radiation exposure for all individuals entering radiation control areas.

%g

d. Records of gaseous and liquid radioactive material released to the R165 environs and the resulting calculated dose to an individual member of the public. '

e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the facility staff,

h. Records of in-service inspections performed pursuant to these g Technical Specifications.

1. lR50 Records of Quality Assurance activities required for lifetime reten- R153l tion by the Nuclear Quality Assurance Plan.

(9 j. Records of reviews performed for changes made to procedures or N equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PORC and the NSRB. lR169 k 1. Records of analyses required by the radiological environmental monitoring program.

m. Records of secondary water sampling and water quality.

N

\J n. Records of the service life monitoring of all safety-related hy-draulic and mechanical snubbers including the maintenance performed to renew the service life.

, 4

o. Records for environmentaA qualification which are' covered under the R50 9 ;

provisions of paragraph 2.C. (10) (b) of license No. DPR-79.

p. Recordt of reviews parformed for changes made to the OFFSITE DOSE R134 CALCULATION MANUAL and the PROCESS CONTF4L PROGRAM.

SEQUOYAH - UNIT 2 6-24 Amendment Nos. 28, 50, 66, 134, ,

, 153, 165, 9. l s

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1

ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-97-04 TECHNICAL REQUIREMENTS MANUAL See attached E4-1

IFDEX BASES MLQH PAGE 3/4.7.4 ESSFNTIAL RAW COOLING WATER SYSTEM . . . . . . . . . . B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.6 FLOOD PROTECTION . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENL'Y VENTILATION SYSTEM . . . . . . . . B 3/4 7-4 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM . . . . . . . . B 3/4 7-5 s 3/4.".9 SNUBBERS (DELETED) . . . . . . . . . . . . . . . . B 3/4 7-5 l 3/4.7.10 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . B 3/4 7 6a 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED) . . . . . . . . . . B 3/4 7-7 R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) . . . . . . . . . . B 3/4 7-7 3/4.8 ELEC'.IICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES . . . . . . B 3/4 8-2 3/4.9 REFUELING OPFfMLOJS, 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRU'4ENIATION . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.3 DECAY TLYS . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . . . . . . . B 3/4 9-1 3/4.9.5 COMMUTICATIONS . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA (DELETED) . . . . D 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIR"ULATION . . . . . B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM . . . . . . . . . . B 3/4 9-3 SEQUOYAH - UNIT 2 XIV Amendment No. 194, 218, v ._

ML20202J765

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