ML20065L215

Amends 148 & 134 to Licenses DPR-77 & DPR-79,respectively, Revising Listed Items Under Section 1, Definitions

ML20065L215
Person / Time
Site:	Sequoyah
Issue date:	11/16/1990
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065L219	List: ML20065L215 ML20065L220
References
NUDOCS 9012050321
Download: ML20065L215 (83)

Text

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UNITED STATES y

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NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D c. 20656

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPER& ING LICENSE Amendment No. i AB License No. OPR 77 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment ey Tennessee Valley Authority (the licensee). dated March 9, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;-

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the hetith and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

.E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9012050321 901116 PDR ADOCK 05000327 P

PDC

. 2.

Accordingly, the license is amended by changes to the Technical l

Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-77 is hereby amended to read as follows:

1 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.148, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION w ~'s Frederick J. HeWon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 16, 1990 T

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ATTACH!'.ENT TO LICEl:SE tt1ENDMEtiT t;C.148

{ACILITYCFEP.ATINGLICENSrNO,.OPR-77 DOCKET NO. f0-3?7 Ptvise the Apper. dix A Technical Specifications by reroving the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned aniendrent number and contain marginal lines indicating the area of change.

Overleaf pages* are provided to naintain document con;pleteness.

PU'0 VE INSERT V

V XI XI 1-3 1-3*

i 1-4 1-4 1-5 1-5 1-6 1-6 3/4 3 68a 3/4-3-69 3/4 3-69 3/4-3-70 3/4 3-70 1

t 3/4 3-70a 3/4 3-71 3/4 3-71a 3/4 3-72 3/4 3-72a i

3/4 3-73 3/4 3-74 3/4 3-71 3/4 3 75 3/4 3-72 3

3/4 3-76 3/4 3-77 3/4 3-73 3/4 3-78 3/4 3-74 3/4 3-79 3/4 3-80 3/4 3-75 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 l

3/4 11-6 3/4 11-7 3/4 11-8 3/4 11-2 3/4 11-9 3/4 11-3 3/4 11-10 3/4 11-11 3/4 11-12 l

3/4 11-13 3/4 11-14 3/4 11-15 l

3/4 11-16 3/4 11-17 3/4 11-10 3/4 11-4 3/4 11-19 3/4 11-5 3/4 11-20 3/4 11-6 l

o J

2 REMOVE INSERT 3/4 11-21 3/4 11-22 3/4 11-7 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 B 3/4 3-5 B 3/4 3-5 B 3/4 11-1 B 3/4 11-1

- B 3/411-2 B 3/4 11-2 B 3/4 11-3 B 3/4 11-4 B 3/4 11-5 l

B 3/4 12 1 B 3/4 12-1

-B 3/4 12-2 6-15 6-15 6-16 6-16*

6/17

.6-17 6-18 6-18 6-19 6-19 6-20 6-20 6-21 6-21' 6-2P.

6-22* 23 6-23 6-24

'6-24 6-25 6-25 6-26

,6-26*

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l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS i

i SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference.....................................

3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor..............................

3/4 2-5 3/4.2.3 Nuclear Enthalpy Hot Channs1 Factor.......................

3/4 2-10 3/4.2.4 Qua dra n t Powe r Ti l t Ra ti o.................................

3/4 2-12 3/4.2.5 DNB Parameters............................................

3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.......................

3/4 3-1 1/ ?.3. 2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.........................................

3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......................

3/4 3-39 Movable Incore Detectors..................................

3/4 3-43

. Seismic Instrumentation...................................

3/4 3-44 Meteorological Instrumentation............................

3/4 3-47 Remote Shutdown Instrumentation...........................

3/4 3-50 ChlorineDetectionSystems(Deleted) 3/4 3-54 Accident Monitoring Instrumentation.......................

3/4 3-55 Fire Detection Instrumentation............................

3/4 3-58 Deleted...................................................

3/4 3-70 Explosive Gas Monitoring Instrumentation..................

3/4 3-71

'SEQUOYAH - UNIT 1.

V Amendment No. 62, 138, 148

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INDEX I

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j

SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Deleted..................................................

3/4 11-1 Deleted............................................

3/4 11-1 i

Deleted..................................................

3/4 11-1 l

Liquid Holdup Tanks......................................

3/4 11-2

{

3/4.11.2 GASEOUS EFFLUENTS Deleted..................................................

3/4.11-3 l

Deleted..................................................

3/4.11-3

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Deleted..................................................

3/4.11-3 Deleted..................................................

3/4.11-3 Explosive Gas Mixture....................................

3/4.11-4 i

Gas Decay Tanks..........................................

3/4.11-5 i

3/4.11.3 Deleted..................................................

3/4.11-6 3/4.11.4.

Deleted................................'..................

3/4.11-7 J

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l

3/4.12.1 Deleted.................................................

3/4.12-1 3/4.12.2 Deleted.................................................

3/4.12-1 3/4.12.3 Deleted.................................................

3/4.12-1 1

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l SEQUOYAH - UNIT 1 XI Amendment No.148

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1 DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /

gram) 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 Power and Test Reactor Sites."

E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide 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, m6 king up at least 95% of the total non-iodine activity in the coolant.

1 ENGINEERED SAFETY FEATURE RESPONSE TIME 1.12. The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety 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.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correscond to the intervals defined in Table 1.2.

GASEOUS RADWASTE TREATMENT SYSTEM 1.14 A GASEOUS RA0 WASTE TREATMENT SYSTEM is any system 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.

IDENTIFIED LEAKAGE 1

i 1.15 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such

)

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

SEQUOYAH - UNIT 1 1-3 Amendment No. 12, 71

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b.

Leakage into the containment 6tmosphere from sou: ces that are both specifically located and known either net to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or 3

w Reactor coolant system leakage throuqt a steam generator to c.

the secondary system.

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MEMBER (S) 0F THE PUBLIC 1.16 MEMBERS OF THE PUBLIC shall include all individuals who are not C

occupationally associated with the plant.

This category shall includt non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant 1

functions.

This category does not include non employees such as vending machine servicemen or postmen who, as part of their formal je, function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure *o radiation and radioactive materials.

0FFSITE DOSE CALCULATION MANUAL (0DCM) 1.17 Ttc 9FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and paru.!

1rs used in the calculation of offsite doses resulting from radio-active gaseous ar,. liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiologitt' Environmental Monitoring Program.

The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Moaitoring Programs required by Section 6.8.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.'-

OPERABLE - OPERABILITY 1.18 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 J

electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its functien(s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE i

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

PHYSICS TESTS 1 ?0 PHYSICS TESiS 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 Commission.

2 SEQUOYAH - UNIT 1 14 Amendment No. 12, 71, 148

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PRESSURE BOUNDARY LEAKAGE l

1.21 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.

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual i

-or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; and other

. requirements noverning the disposal of solid radioactive wastes.

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 F0WER 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.

With one excore detector inoperable, the remaining three detectors shall be used for. computing the, average.

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.

i REACTOR-TRIP SYSTEM RESPONSE TIME M

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

.until 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.

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l SEQUOYAH - UNIT 1 1-5 Amendment No. 12, 71, 14 1 148

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e o SHIELO BUILDING INTEGRITY 1.28 SHIELD BUILDING INTEGRITY'shall exist when:-

a.

The door in each-access opening is closed except when the Laccess opening is being used for normal transit entry and exit.

b..The en,argency gas treatment system is OPERABLE.

c.

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

welds, bellows or 0-rings) is OPERABLE.

SHUT 00WN MARGIN

'1.29 SHUTDOWN: PAP. GIN'shall be the instantaneous amount.of reactivity by which

the reactor is subcritical or would be suberitical 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 whichLi.s assumed to be fully withdrawn.

SITE BOUNDARY 1,30- The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise'co'ntrolled by the licensee (see Figure 5.1-1).

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SOLIDIFICATION-l'. 3 11 Deleted SOURCE CHECK 1.32' Deleted 9

STAGGERED TEST-BASIS 1.33 L A' STAGGERED TEST BASIS shall consist of:'

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a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified' test interval.into n e

equal subintervals, b.

The testing of one syscem, subsystem, train or other designated component at_the beginning of each subinterval.

. THERMAL POWER' 1.34 THERMAL POWER shall be the total reactor core heat transfer rate to the

. reactor-coolant.

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SEQUOfAH - UNIT 1 1-6 Amendment No. 12, 71 148

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~ TABLE 3.3-11 (Continued) w

~ FIRE DETECTION INSTRUE NTS-E

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. Fire

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Minimum Instruments Operable j,

Zone Instrument Location Ionization: Photoelectric Thermal Infrared-

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'369 RCP 4, E1. 693 2

E 372 Reactor Bldgi Annulus 22' Z

373 Reactor Bldg. Annulus21-387 Turbine Cont.iBldg. Wall.

18 g

E1. 7062 427 125V Batt. Re. */ El. 749

- 2 428

'125V Batt. Rs. V E1. 749 2'

458 Counting Room Ceiling E1. 690 2

462 480V Sd Bd Rs.:IB2 E1._.734 1

463 480V Sd Bd Rs.' 2A2 E1. 734-1 465 Counting'R wn' Ceiling E1. 690 2

466--

480V Sd Bd Rs. 182 E1. 734 l'-

467 480V Sd Bd Re. 182 El..'734-1 R

468

_480V Sd Bd Rs. 182 E1. 734- ~

1 469 480V Sd Bd Rs. 2A2 El. 734 1

Y

~470

-480V Sd Bd Rm.:2A2 El. 734 1

.471 480V..Sd Bd Rs.'2A2 El. 734 1

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4-INSTRUMENTATION DELETED LlHITING CONDITION FOR OPERATION 3.3.3.9 This Specification is deleted.

The Tables 3.3-12 and 4.3-8 are also deleted.

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SEQUOYAH - UNIT 1 3/4 3-70 Amendment No. 13, 42, 57, 81, 114, 125,148

INSTRUMENTATION 4

EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION s

3.3.3.10 The. explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

. APPLICABILITY:

As shown in Table 3.3-13 ACTION:

With an explosive gas monitoring instrumentation channel alarm / trip l

a.

setpoint less conservative than required by the above Specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table

,3.3-13. ' Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, p epare and submit a Soecial Report to the Commission pursuant to Specification 6.9.2.1 to explain why this.inoperability was not corrected in a timely manner.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

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. SURVEILLANCE REQUIREMENTS

.c 4.3.3.10L EachLexplosive gas monitoring instrumentation channel shall be demonstrated OPERABLE-by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9.

f SEQUOYAH - UNIT 1 3/4 3-71 Amendment No. 81,143 L--

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- TABLE 3.3-13 :

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y 5XPLOSIVE GAS MONITORING ~ INSTRUMENTATION t

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-MINIMUM CHANNELS E

INSTRUMENT OPERABLE APPLICABILITY ACTION

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1.

Deleted

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2.

WASTE GAS DISPOSAL SYSTEM EXPLOSIVE GAS

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MONITORING SYSTEM 43 a.,

Hydrogen and 0xygen Monitors" 2

1 M

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Y M

9 E

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TABLE 3.3-13 (Continued)

TABLE NOTATION During waste gas compressor operation.

-i ACTION 40 Not Used.

ACTION 41 Not Used.

ACTION _42 - Not Used.

' ACTION 43 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste-gas disposal system may continue provided grab samples are taken:

and analyzed either (1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations of the' reactor coolant system, or (2) daily during other operations.

ACTION 44' - Not Used.

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4 L-SEQUOYAH - UNIT 1 3/4 3-73 Amendnent No. 42,148

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y, TABLE 4.3-9:

m g-EXPLOSIVE GAS' MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

- 5 1

CHANNEL MODES FOR WlICH '

c CHANNEL-CHANNEL FUNCTIONAL SURVEILLANCE IS h

INSTRUMENT

~ CHECK CALIBRATION TEST REQUIRED' 1.

Deleted i

i 2.

WASTE GAS DISPOSAL SYSTEM EXPLOSIVE.

GAS MONITORING SYSTEM a.

Hydrogen Monitor D

Q(4)

M b.

Oxygen Monitor ~

D Q(5)

M K

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TABLE NOTATION

-During waste gas compressor operation.

(1) Not Used.

(2) Not Uses.

(3) Not Used.

(4) The CHANNEL CALIBRATION shall' include the use of standard gas samples containing-a nominal:

1.

One volume percent hydrogen, balance nitrogen, and 2.

Four, volume percent hydrogen, balance nitrogen.

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l(5). The CHANNEL CALIBRATION shall' include the use of standard gas samples containing a nominal:

o 1.

- One. volume percent oxygen, balance nitrogen, and 2.

Four volume percent oxygen, balance nitrogen, e

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SEQUOYAH

. UNIT 1 3/4 3-75 Amendment No. 25, 122, 148

.h 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS LIMITING CONDITION FOR OPERATION 3.11.1.1 This specification is deleted.

3.11.1.2 This specification is deleted.

3.11.1.3 This specification is deleted.

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SEQUOYAH - UNIT 1 3/4 11-1 Amendment. No. 42,148

RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the fol-lowing tanks shall be limited by the following expression:

concentration of isotope i y

,700

<6

$ maximum permissible concentration of isotope i excluding tritium and dissolved or entrained noble gases.

I a.

Condensate Storage Tank b.

Steam Generator Layup Tank c.

Outside temporary tanks for radioactive liquid APPLICABILITY:

At all times.

ACTION:

With the quantity of radioactive material in any of the above listed a.

i tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

-The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

ll SURVEILLANCE REQUIREMENTS 4.11.1.4.The quantity of radioactive material contained in each of the above i

listed-tanks-shall be. determined to be within the above limit by analyzing _a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

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SEQUOYAH UNIT 1 3/4 11-2 Amendment No. 42,148 l

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.RADI0 ACTIVE EFFLUENTS' 3/4.11.2 2ASE005 EFFLUENTS LIMITING CONDITION FOR OPERATION 13,11.2.1 This specification is deleted.

3.11'.~ 2. 2 - ThisLspecification is deleted.

3.11.2.3 This specification is deleted.

l3.11.2.4 This_ specification is deleted.

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SEQUOYAH - UNIT 1 3/4 11-3 Amendment No. 42, 65, 109, 114, 148

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY:

At all times.

ACTION:

With the concentration of oxygen in a waste gas holdup tank greater a.

than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

With the concentration of oxygen in a waste gas holdup tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, without delay suspend all additions of waste gases to the affected waste gas holdup tank and reduce the concentration of oxygen to less than or equal to 2% by volume without delay,

_The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE' REQUIREMENTS 4.11.2.5 The concentration of hydrogen and_ oxygen in the waste gas holdup system shall be determined'to be within the above limits by monitoring the waste gas additions to the waste gas holdup system with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

l SEQUOYAH - UNIT 1 3/4 11-4 Amendment No. 42,148 l

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RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 50,000 curies of noble gases (considered as Xe-133).

APPLICABILITY:

At all times.

L-ACTION:

With the quantity of radioactive material in any gas decay tank a.

P exceeding the above limit, without delay suspend all additions of

[

radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLAf4CE REQUIREMENTS 4.11.2.6 The quantity of-radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materiai= are being added to the tank.

SEQUOYAH - UNIT 1 3/4 11-5 Amendment No. 42,148

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RADIOACTIVE EFFLUENTS 4

3/4.11.3 DELETED LIMITING-CONDITION FOR OPERATION

'3.11'. 3 This specification is deleted.

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SEQUOYAH - UNIT 1 3/4 11-6 Amendment No. 42,148

1 RADI0 ACTIVE EFFLUENTS 3/4.11.4 DELETED LIMITING CONDITION FOR OPERATION 3.-11.4 This specifiestion is deleted.

SEQUOYAH - UNIT 1 3/4 11-7 Amendment No. 42,148

. 3/ '+.12 RADIOLOGICAL ENVIRONMENTAL MONITORING-LIMITING CONDITION FOR OPERATION 3.12.1 This Specification is deleted.

3.12.2 This Specification is deleted.

3.12.3 This Specification is deleted.

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~SEQUOYAH - UNIT 1 3/4 12-1 Amendment No. 42, 114, 148

INSTRUMENTATION BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages.. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.3.3.9 This Specification is deleted.

'3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system.

The OPER-ABILITY and use of this instrumentation is consistent with the requirements for monitoring potentially explosive gas mixtures.

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SEQUOYAH - UNIT 1 B 3/4 3-5 5k8nE@dN0th[.148 u

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f 3/4.11 RADIOACTIVE EFFLUENTS BNSES 3/4.11-1 LIQUID EFFLUENTS 3/4.11.1.1 This specification is deleted.

3/4.11.1.2

.This specification is deleted.

3/4.11.1.3 This specificationLis deleted.

1-3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the f tanks' contents, the resulting concentrations would be less than the' limits of 10 CFR Part,0,< Appendix B, Table II, Column 2, at the nearest potable water 2

supply and the nearest surface water. supply in an unrestricted area.

3/4.11.2 : GASEOUS EFFLUENTS 3/4.11.2.1 This. specification is deleted.

3/4.11.2.2-This1 specification is deleted.

L3/4:11.2.3 This specification is deleted.

3/4.11.2.4 This specification is deleted.

1 SEQUOYAH - UNIT 1 B 3/4 11-1 Amendment No. 42,148

t RADI0 ACTIVE EFFLUENTS BASES

'l 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the waste gas holdup system is main-tained below the flammability limits of hydrogen and oxygen.

Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in con-formance with-the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.6 GAS DECAY TANKS Restricting the quantity of radioactivity contained in each gas decay tank provides absur.snce that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".

3/4.11.3 This specification is deleted.

-3/4.11.4 This specification is deleted.

SEQUOYAH - UNIT 1 8 3/4 11-2 Amendment No. 42,148

'3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 This Specification is deleted.

1 3/4.12.2

-This Specification is deleted, 3/4.12.3 1

This Spehification.is deleted.

g.

\\

StQUOYAH - UNIT 1 B 3/4 12-1 Amendment No. 42,148

1..

4 ADMINISTRATIVE CONTROLS b.'

Refueling operations.

Surveillance and test activities of safety-related equipment.

c.

d.

Plant Physical Security Plan implementation.

e.

Site Radiological Envergency Plan implementation.

f.

. Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

Quality Assurance Program-for effluent monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977, or Regulatory Guide 1.21, Rev. 1, 1974 and Regulatory Guide 4.1, Rev. 1, 1975.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in Specification 6.5.1A above.

u 6.8.3 Temporary' changes to procedures of 6.8.1 above may be made provided:

a.

The. intent of the original procedure is not altered.

L

b..

The change isl approved by two members of the plant management staff,

'at least one of whom holds a Senior Reactor Operator's License on the unit'affected..

c.

The change is approved in accordance with Specification 6.5.1A above within 14~ days of; implementation.

6.8.4 Written procedures shall be established, implemented and maintained by

-t

' Radiological Control covering the activities ~below:

g a.

OFFSITE DOSE CALCULATIONAL MANUAL implementetion.

o y b.

Quality Assurance Program for environmental monitoring.:using the 3

guidance; contained in Regulatory Guide 4.15, December'1977.

6.8.5 The following programs shall be: established, implemented, maintained, and changes-thereto made in accordance with Section 6.5.1A:

a.

Primary Coolant Sources Outside Containvent p

1 A program to reduce leakage from those. portions of systems.outside-

'l containment that could contain highly radioactive fluids during a-x serious transient or accident to as' low as practical levels. ;The o

I L

l l

SEQUOYAH - UNIT 1 6-15 Amendment No. 42, 58, 74, 148 t

\\

p.;;

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l 1

ADMINISTRATIVE CONTROLS' systems include the safety injection system, residual heat removal system, chemical and volume control system, containment spray system, and RCS sampling system.

The program shall-include the following:

i.

L1, (i) Preventive maintenance and periodic visual inspection requirements, l

and (11)l Integrated leak test requirements for each system at refueling cycle intervals or less.

b b.

In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine H

the airborne iodine concentrations in vital areas under accident conditions.- This program shall include the following:

(i) ~ Training of personnel, 1

1 L

(ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling end analysis equipment..

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to-inhibit steam

. generator tube degradation.

This program shall include:

3

,(i) Identift:ation of a sampling schedule for the critical variables and control points for these variables, (ii)

Identification of the procedures used to measure the values of the critical variables,

~(iii) Identification of process sampling' points.

-(iv) Procedures for the recording and management of data, (v)> Procedures defining corrective actions for off-control point chemistry conditions, 1

-(vi). Procedures identifying-(a) the authority responsible for the n

interpretation of the data; and (b)'the sequence and: timing of administrative events required:to initiate corrective action, and (vii) Monitoring of the condensate at the discharge of the condensate pumps for evidence of condenser in-leakage.

When condenser in-leakage is confirmed, the leak-shall be repaired, plugged, or isolated within 96 hoars.

SEQUOYAH - UNIT 1 6-16 Amendment No. 58, 74

. n.

• ~

ADMINISTRATIVE CONTROLS d.

Backup Method for Determining Subcooling Margin i

A program which will ensure the capability to accurately monitor the:

Reactor Coolant System Subcooling Margin.

This program shall include the following:

(i) Training of personnel, and I

(ii) Procedures for monitoring, e.

Postaccident Sampling A program which will ensure the capability to-obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous' effluents, and containment atmosphere samples under accident conditions. ~The program shall include the following:

(W Training'of-personnel, (ii, Procedures for sampling and analysis,

'(iii) Provisions for maintenance of sampling and analysis equipment.

i f.:

. Radioactive Effluent Controls Program li

-A program shall be provided conforming with 10 CFR 50.36a for the L,

control of radioactive effluents and for maintaining the doses to

-l

_i MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the 00CM,-(2) shall belimplemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall; include the following elements i

L-1)i Limitations on the' operability of radioactive liquid and gaseous

,\\

i l

D!l monitoring. instrumentation including surveillance tests and set-1 point-determination in accordance with the methodology in the~

00CM, 2)

Limitations on the concentrations of radioactive material L

released in liquid effluents to UNRESTRICTED AREAS conforming L

to 10 CFR Part 20, Appendix B' Table-II, Column 2,

,3)-

Monitoring.. sampling, and analysis of radioactive liquidtand gaseous effluents in accordance with 10 CFR 20.106 and with the' J

' methodology and parameters'in the 00CM, 4)

Limitations on.the annual and quarterly doses or dose commitment to a MEMPER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix Ioto 10 CFR Part 50,'

s 5)-

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with'the methodology and parameters

'in the ODCM at least every 31 days, SEQUOYAH - UNIT 1 6-17 Amendment Nos. 12, 32, 58, 74, 148

.[

..l ADMINISTRATIVE CONTROLS 6).

Limitations'on the operability and use of the liquid and gaseous.

effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when

-the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I-to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations.on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)-

Limitations on the annual and-quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to. Appendix'I to 10 CFR Part 50, and 10)

Limitations on the annual dosn or dose commitment to any MEMBER

OF THE PUBLIC due to releases-of radioactivity and to radiation v

from uranium fuel cycle sources conforming to 40 CFR Part 190.

g.

Radiological Environmental Monitorino Procram A program shall be provided to monitor'the radiation and radionuclides in the environs of the plant.

The program shall provide (1) repre-sentative measurements of radioactivity:in the highest potential expo-1 surel pathways, and (2) verif Dation of the accuracy of the effluent monitoring program and modeling.of environmental exposure pathways.

The program shall (1) be contained in the ODCM,'(2) conform to the guidance:of Appendix I to 10'CFR Part 50, and (3) include the~

following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with:the-methodology.and parameters in the ODCM, E

2)

A Land Use Census to ensure that changes in the use of areas at _

j and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required'by the results of this. census, and 3)

Participation _in a Interlaboratory Comparison Program to ensure E

that' independent checks on the precision and accuracy _of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

SEQUOYAH -' UNIT 1 6-18 Amendment Nos. 12, 32, 58, 74, 148

,m

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ADMINISTRATIVE CONTROLS i

~

i 6.9': REPORTING REQUIREMENTS

' ROUTINE REPORTS' 1

(

J 6.9.1.'In addition to the applicable reporting requirements of Title 10, Code l"

of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall 4

u be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has beeri manufactured by a different fuel supplier, and (4) modifications'that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

K 6.9.1.2 The startup. report shall address each of the tests identified in the FSAR and shall include a description of-the measured values of the operating L

conditions'or characteristics obtained during the test program and a comparison of these values'with design predictions'and specifications.

Any' corrective L

actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions n

based on other commitments-shall be included in this report.-

l l

6.9.1 3 Startupireports shall be. submitted within (A) 90 days following completion of~the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or'(3) 9 months following initial p

criticality, whichever is earliest.- If the-Startup Report does not cover all

.three events (i.e..,Einitial criticality, completion of startup test program, one resumption or commencement of commercial power operation), supplementary repor d shall be eubmitted at least every three months until all-three events

'have been completed.

J ANNUAL. REPORTS [

-6.9.1.4 Annual reports covering the activities' of the unit. as described ~.below p

.for the previous calendar' year.shall be submitted prior to March 1 of each year. -The initial' report shall be submitted prior to March 1 of the year following initial criticality.

16.9.1.5 Reports required on an annual basis shall include a tabulation on an annual. basis for the number of station, utility'and other personnel (including contractors)receivingexposuresgreaterthan100mregyrandltheirassociated s"

man rem exposure according to' work'and job functionsi-e.g., reactor. operations Land surveillance, inservice inspection, routine maintenance, special maintenance 1/ - A single submittal may be made for a multiple unit station.

The submittal

~

should combine those. sections that are common to all units at the station.

2/ This tabulation supplements the requirements of 6 20.407 of 10 CFR Part 20.

SEQUOYAH - UNIT 1 6-19 Amendment Nos. 12, 32, 58, 72, 74, 148

a, '.

ADMINISTRATIVE CONTROLS (describe maintenancM, waste processing, and refueling.

The dose assignment to various duty funt.*. ions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

If the results of specific activity analysis in which the primary coolant exceeded the limits of specification 3.4.8.a. then the following information shall be included along with the results of specific activity analysis results in which the primary coolant exceeded the limits of the specifications:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the-limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while the' limit was exceeded and results of one analysis after the radioiodine activity was reduced to less then the limit.

Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1/

6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May l'of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the 00CM and.(2) Sections IV.B.2, IV.8.3, and IV.C7f Appendix ! to 10 CFR Part 50.

6.91.7_ (Relocated to the 00CM.)

SEMI ANNI y'JI0ACTIVEEFFLUENTRELEASEREPORT1/

6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the

operation of the. unit during the previous 6 months of operution shall be sub-mitted_ within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR'Part 50.

L 6.9.1.9 (Relocated to the ODCM or PCP.)

1/ A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from etch unit.

SEQUOYAH - UNIT 1 6-20 Amendment Nos. 42, 58, 74, 117, 148

ADMINISTRATIVE CONTROLS MONTHLY REAIT0F OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis no later '.han the 15th of each month following the calendar month covered by the report.

Any ena mes to tne OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Dperating Report within 90 days in which the change (s) was made effective.

In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.

i RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(2) function for normal operation shall be provided at least 60 days prior to cycle initial criticality.

In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.

Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.

SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified for each report, in accordance with 10 CFR 50.4 6.9.2.2 Diesel Generator Reliability Improvement Program As a minimum the Reliability Improveinent Program report for NRC audit, required by LCO 3.8.1.1. Table 4.8-1, shall include:

(a) a sumary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed (b) analysis of failures and determination of root causes of failures (c) evaluation of each of the recomendations of NUREG/CR-0660, " Enhancement of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"

with respect to their application to the Plant I-(d) identification of all actions taken or to be taken to 1) correct-the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability (e) the schedule for implementation of each action from d) above l

(f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment SEQUOYAH - UNIT 1 6-21 Amendment No. 42,58,72,74,117 i

L l

o ADMINISTRATIVE CONTROLS A supplemental repurt shall be prepared within 30 days af ter each subsequent failure during a valid demand for so long/20 or 6/100) for the reliability as the affected diesel generator unit continues to violt' criteria (a improvement program

&/

oction.

The supplemental report need only update the failure / demand M.s for the affected diesel generator unit since the last report for that diese..enerator.

The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the diesel generator improvement program and the schedule for implementation of those changes.

In addition to the above, submit a yearly oata report on the diesel generator reliability.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10. Code of Federal Regulations, the following records snall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a.

Records and logs of unit operation covering time interval at each power level, b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Comission, d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

Records of changes made to the procedures required by Specification e.

6.8.1 and 6.8.4 f.

Records of radioactive shipments.

g.

Records of sealed source and fission dete. tor leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

SEQUOYAH - UNIT 1 6-22 Amendment Nos. 52, 58, 74, 117

i ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating 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, i

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

contr'ai areas, d.

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

e.

Records of transient or operational cycles for those un!6 components identified in Table 5.7-1.

f.

Records of reactor tests and experiment'.

g.

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

h.

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

1.

Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Manual.

J.

Records of reviews nerformed for changes made to procedures or equipment or reviews of tests-and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PORC, SQN RARC, and the NSRB.

1.

' Records of analyses required by the radiological environmental monitoring program, m.

Records of secondary water sampling and water quality.

n.

Records of the service life monitoring of all safety-related hydraulic and mechanical snubbers, required by T/S 3.7.9, including the main-tenance performed to renew the service life, o.

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

_ Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the P,30 CESS CONTROL PROGRAM.

4 SEQUOYAH - UNIT 1 6-23 Amendment No. 42, 58, 74, 148

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered 1

to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radidtion area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance 1

thereto shall be controlled by requiring issuance of a Special (Radiation)

Work Pormit*.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one-or more of the following:

A radiation monitoring device which continuously indicates the a.

radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, An individual qualified in radiation protection procedures who is c.

equipped with a radiation dose rate monitoring device. This individual J

shall be responsible for providing positive control over the activities within the area and shall parform control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Site Radiological Control Superintendent in the Special (Radiation) Work Pennit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shif t Supervisor on duty and/or the Site Radiological Control Superintendent.

i

• Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with approved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

• 1 SEQUOYAH - UNIT 1 6-24 Amendment No. 42, 58, 74, 148

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGPAM (PCP) 6.13.1 Changes to the PCP:

1.

Shall be documented and records of reviews performed.shall be retaineo as requirec oy Specification C.10.2.p.

This documentation shall contain:

a.

sufficient information to support the change 'ogether with the appropriate analyses or evaluations justifying the change (s) and b.

a determiriation that the change will maintain the overall con-formance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2.

Shall become effective after review and approval in accordance with Section 6.5.1A.

1 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

1.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p.

This documentation shall contain:

a.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or. reliability of effluent, dose, or setpoint calculations..

2.

Shall become effective after review and acceptance by the SQN RARC.

3.-

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall l'

be identified by markings in the margin of the affected pages, clearly E

indicating the area of the the date (e.g., month / year)page that was changed, and shall indicate the change was implemented.

l I

SEQUOYAH - UNIT 1 6-25 Amendment No. 42, 58,. 74, 148

'a

ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid,gaseousandsolid):*

1.

Shall be reported to the Conrnission in the Semi-Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed in accordance with Section 6.5.1A. The discussion of each change shall contain:

A summary of the evaluation that led to the determination that a.

the change could be made in accordance with 10 CFR 50.59; b.

sufficient Jetailed information to totally support the reason for the change without benefit of additional or supplemental information; i

a detailed description of the equipment, components and proces-c.

ses involved and the interfaces with other plant systems; d.

an evaluation for the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto, j

an evaluation of the change which shows the expected maximum e.

exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f.

a comparison of the predicted releases of radioactive materials, l

in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

an estimate of the exposure to plant operating personnel as a result of the change; and h.

documentation of the fact that the change was reviewed and found acceptable in accordance with Section 6.5.1A.

2.

Shall become effective upon review and acceptance in accordance with Section 6.5.1A.

• Submittal of information required by this section may be made as part of the annual FSAR update.

SEQUOYAH - UNIT 1 6-26 Amendment No. 58, 74

I

(

o, UNITED STATES y

g NUCLEAR REGULATORY COMMISSION a f g.

W AsHINo To N, D. C. 20555

'44.....,6 TENNESSEE VALLEY AUTHORITY l

DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 1.

l-AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No.134 License No. DPR-79 1.

The Nuclear Regulatory Commission (the Commission) has found that:

i_

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated March 9,1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR i

Chapter'I; j

B..

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the L

Commission; C.

There is reasonable assurance (i) that the activities authorized by

.this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i

conducted in compliance with the Commission's regulations; 0.

The' issuance'of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and-I E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have l'

been satisfied.

1 l'

l' I

i' I

I 2

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amenoment l

and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.134, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION

/

Frederick J. He on, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachment' i

Changes to the Technical Specifications Date of Issuance: November 16, 1990 I

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ATTA C W E NT _ T,0,,L),0 E!@J,,A!a;pfJ!,T, !40,.,.,,,. FRILITY Of EF:AT1hG. LICENSE NO. DPR-79 DOCKET ifi,.,,50,,3,?,8 ptvise the Apgr. dix A Technical Specific 6tions by removing the pages 16titified Lt. low end institilig it.e enclosed past s. The revised pages are identified by tre ceptioned enendeent nur.ber and ccntain e.orgiral lines indicating the area of change. Overleef pages* are provided to raint61n (c.cutent conpletter.ess. FEVCVE INSERT V V XI XI XII XII* 1-3 1-3* 1-4 14 1-5 1-5 1-7 1-7 3/4 3-68 3/4 3-68 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75 3/4 3-76 3/4 3-69 3/4 3-77 3/4 3-70 3/4 3-78 3/4 3-79 .3/4 3-71 3/4 3-80 3/4 3-72 3/4 3-81 3/4 3-82 3/4 3-73 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-6 3/4 11-7 3/4 11-2 3/4 11-8 3/4 11-3 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-16 3/4 11-4 3/4 11-17 3/4 11-5 3/4 11-18 3/4 11-6 3/4 11-19 3/4 11-7

i -2 REMOVE INSERT 3/A 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 B 3/4 3-4 8 3/4 f-4 1 B 3/4 3-5 B 3/4 11-1 B 3/411-1 B 3/4 11-2 B 3/4 11-2 B 3/4 11-3 t B 3/411-4 B 3/4 11-5 B 3/412-1 B 3/4 12-1 B 3/4 12-2 6-15 6-15 6-16 6-16* 6-17 6-17 6-18 6-1B 6-19 6-19 6-20 6-20 6-21 6-21 6-22 6-22 6 6-23 o 6-24 6-24 L 6-25 6-25 t l 6-26 6-26 L 6 27 l r i 1' 1 1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.. 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACT 0R....................... 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATI0................................. 3/4 2-10 3/4.2.5 DNB PARAMETERS............................................ 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.........................................- 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...................... 3/4 3-40 Movable Incore Detectors.................................. 3/4 3-44 Seismic Instrumentation................................... 3/4 3-45 Meteorological Instrumentation............................ 3/4 3-48 Remote Shutdown Instrumentation........................... 3/4 3-51 Chlorine Detection Systems'(Deleted) 3/4 3-55 Accident Monitoring Instrumentation....................... 3/4 3-56 Fire Detection Instrumentation............................ 3/4 3-59 (Deleted)................................................. 3/4 3-68 Explosive Gas Monitoring Instrumentation.................. 3/4 3-69 l' i l SEQUOYAH - UNIT 2 V Amendment No. 54, 130, 134 1

.c. INDEX LIM! RING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10.4 REACTOR COOLANT L00PS..................................... 3/4 10-4 3/4.10.S POSITION INDICATION SYSTEM - SHUT 00WN..................... 3/4 10-5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Deleted.................................................. 3/4 11-1 Deleted.................................................. 3/4 11-1 Deleted.................................................. 3/4 11-1 Liquid Holdup Tanks...................................... 3/4 11-2 3/4 11.2 GASEOUS EFFLUENTS Deleted.................................................. 3/4 11-3 0eleted.................................................. 3/4 11-3 Deleted.................................................. 3/4 11-3 Deleted.................................................. 3/4 11-3 Explosive Gas Mixture.................................... 3/4 11-4 Gas Decay Tanks.......................................... 3/4 11-5 3/4 11.3 Deleted.................................................. 3/4 11-6 3/4 11.4 Deleted 3/4 11-7 i!4.1' RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.'1 Deleted................................................. 3/4 12-1 3/4.12.2 0eleted................................................. 3/4 12-1 3/4.12.3 Deleted................................................. 3/4 12-1 SEQUOYAH - UNIT 2 XI Amendment No.134

i INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY.......................s.. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 1 3/4.1.1 BORATION CONTR0L........................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS........................................... B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................. B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL-FLUX DIFFERENCE...................................... B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACT 0RS............................... B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATI0.................................. B 3/4 2-5 l 3/4.2.5 DNB PARAMETERS............................................. B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 L and 3/4.3.2 REACTOR TtIP SYSTEM and ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION................... B 3/4 3-1 3/4.3.2 E4GINEEREO SAFETY FEATURE INSTRUME.1TATION.................. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................. B 3/4 3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1' REACTOR COOLANT LOOFS AND COOLANT CIRCULATION..............B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY AND RELIEF VALVES....................... B 3/4 4-2 3/4.4.4 PRESSURIZER................................................ B 3/4 4-2 3/4.4.5 STEAM GENERATORS........................................... B 3/4 4-3 l SEQUOYAH - UNIT 2 XII i i 1

l DEFINITIONS DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and iso-topic mixture of I-131, I-132, 1-133, 1-134, 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 Power and Test Reactor Sites." l - AVERAGE DISINTEGRATION ENERGY 1.11 I shall be the average (weighted in proportion to the concentration of l each radionuclide 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 non-iodine activity in the coolant. ENGINEERED SAFETY FEATURE RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge ressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2. GASEOUS RADWASTE TREATMENT SYSTEM 2.14 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed l to reduce radioactiva gaseous effluents by collecting primary coolant system of fgases f rom the primary sys'.em and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. l SEQUOYAH - UNIT 2 1-3 Amendment No. 63 nm

DEFINITIONS IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be: i l a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as i pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or i c. Reactor coolant system leakage through a steam generator to the i secondary system. MEMBERS O' THE PUBLIC r 1.16 MEMBERS OF THE PUBLIC shall include all individuals who are not occupa-tionally asso' lated with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category does not include non-employees such a vending machine servicemen or i l postmen who, as part of their formal job function, occasionally enter an cea that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. OFFSITE DOSE CALCULATION MANUAL-i 1.17 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology J and parameters used in the calculation of offsite doses resulting from radio-3 active gaseous and liquid effluents, 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 Radio-active Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and i 6.9.1.8. 1 OPERABLE - OPERABILITY 1.18 A system, sebsystem, train, or component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), l l l-and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other 'l auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s). i l SEQUOYAH - UNIT 2 1-4 Amendment % 63, 134 u l

DEFINITIONS OPERATIONAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1. PHYSICS TESTS 1.20 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 Commission. PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE 801)NDARY LEAKAGE shall be leakage (exce t steam generator tube leakage) through a non-isolable fault in a Reactor Coo ant System component body, pipe wall or vessel wall. J PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid westes will be accomplished in stich a way as to assure compliance with 10 CFR Parts 20, 61 and 71; State regulations; and other requirementsgoverningthedisposalofso1Idradioactivewastes. PURGE - PURGING 1.23 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humioity, 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 -QU/DRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-l .brated outputs, or the ratio of the maximum lower excore detector calibrated ( output to the average of the lower excore detector calibrated outputs, which-ever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average. l l l SEQUOYAH - UNIT 2 1-5 Amendment No. 63 134

DEFINITIONS SOLIDIFICATION 1.31 Deleted. SOURCE CHECK 1.32 Deleted. STAGGERED TEST BASIS 1.33 A STAGGERED TEST BASIS shall consist of: A test schedule for n systems, subsystems, trains or other designated a. 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 1.34 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. UNIDENTIFIED LEAKAGE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE t or CONTROLLED LEAKAGE. 4 UNRESTRICTED AREA 4 1.36 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 radicactive materials or any area within the site boundary used for residential quarters or industrial, commer-cial, institutional, and/or recreational purposes. SEQUOYAH - UNIT 2 1-7 Amendment No. 63,134

INSTRUMENTATION DELETED LIMITING CONDITION FOR OPERATION 3.3.3.9 This Specification is deleted. The Tables 3.3-12 and 4.3-8 are also deleted. 3 l l l i l l l l SEQUOYAH - UNIT 2 3/4 3-68 Amendment No. 4, 34, 49, ~2, 114, 134 l

INSTRUMENTATION j EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATI0h ) 3.3.3.10 The explosive gas monitoring instrumentation channels shown in 1 Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure l that the limits of Specification 3.11.2.5 are not exceeded. APPLICABILITY: As shown in Table 3.3-13 ACTION: a. With an explosive gas monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13. b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2.1 to explain why this inoperability was not corrected in a timely manner. c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9. l l l SEQUOYAH - UNIT 2 3/4 3-69 Amendment No. 34, 72, 134 l

i E P O W Ca d -5 C 5 i i a lw .A ~ w A E g$" e, W i g s t Ig e g ,m b E 3 a w r a e-2 S 3 g 5 m [ a k a$5 - gu E t g 5 } s m e3 m s

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WC 5 $$ 4 r1 cJ SEQUOYAH - UNIT 2 3/4 3-70 Amendment No.134

4 TABLE 3.3-13 (Continued) TABLE NOTATION During waste gas compressor operation. ACTION 40 - Not used. ACTION 41 - Not used. ACTION 42 - Not used. ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas disposal system may continue provided grab samples are taken and analyzed either (1) every 4 hours durir igassing operations of the reactor coolant system or (2) daily 'ing other operations. ACTION 44 - Not used. SEQD0YAH'- UNIT 2 3/4'3-71 Amendment No. 34. 134

~ M TABLE 4.3-9 o g EXPLOSIVE GAS MDNITORING INSTRWIENTATION SURVEILLANCE REQUIREMENTS-t E 4 CHANNEL MODES FOR WHICH c CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS 3 INSTRUMENT CHECK-CALIBRATION TEST REQUIRED 1. DELETED 2. WASTE GAS DISPOSAL SYSTEM EXPLOSIVE GAS MONITORING SYSTEM t i a. Hydrogen Monitor D Q(4) M i i b. Oxygen Monitor D Q(5) M i s" k Y l M I r E: .r+ W I l l t i 4 w e

IABLE 4.3-9 (Continued) TABLE NOTATION During waste gas compressor operation. (1) Not Used. (2) hot Used. (3) Not Used. (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydrogen, balance nitrogen. (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:- l 1. One volume percent oxygen,- balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen. \\ l F 1 i 1 I I L 1 ) i Correction Letter: 10/18/89 SEQUOYAH - UNIT 2 3/4 3-73 Amendment No. 13, 111, 134 ~

i e 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS LIMITING CONDITION FOR OPERATION 3.11.1.1 This Specification is dele.ed. 3.11.1.2 This Specification is deleted. 3.11.1.3 This Specification is deleted. l l 'l l l :' (: SEQUOYAH - UNIT 2 3/4 11-1 Amendment No. 34,134 b

F RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the fol-lowing tanks shall be limited by the following expression: concentration of isotope i y <6,700 maximum permissible g concentration of isotope i excluding tritium and dissolved or entrained noble gases. a. Condensate Storage Tank b. Steam Generator Layup Tank c. Outside temporary tanks for radioactive liquid } APPLICABILITY: At all times. ACTION: ) With the quantity of radioactive material in any of the above listed a. tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit, b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. 4 SEQUOYAH - UNIT 2 3/4 11-2 Amendment No.134

l j RADIOACTIVE EFFLUENTS t 3/4.11.2 GASEOUS EFFLUENTS LIMITING CONDITION FOR OPERATION l. L 3.11.2.1 '.his Specification is deleted. 1 3.11.2.2 This Specification is deleted. l 3.11.2.3 This Specification is deleted. 3.11.2.4 This Specification is deleted. l l 1 l. ? l l l i l l l l SEQUOYAH - UNIT 2 3/4 11-3 Amendment No. 34, 57, 99, 104, 134

~ RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whencver the hydrogen concen-tration exceeds 4% by volume. APPLICABILITY: At all times. ACTION: With the concentration of oxygen in a waste gas holdup tank greater a. than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above litits within 48 hours. ( With the concentration of oxygen in a waste gas holdup tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, without delay suspend all additions of waste gases to the affected waste gas holdup tank and reduce the concentration of oxygen to less than or equal to 2% by volume without delay. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. t c. 1 SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by monitoring the l-waste gas additions to the waste gas holdup system with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10. l j l 1 i SEQUOYAH - UNIT 2 3/4 11-4 Amendment No. 34,134

RADIOACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 50,000 curies of noble gases (considered as Xe-133). APPLICABILITY: At all times. ACTION: l With the quantity of radioactive material in any gas decay tank a. exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ) SURVEILLANCE REQUIREMENTS j 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 1 hours when radioactive materials are being added to the tank. l \\ l l l SEQUO AH - UNIT 2 3/4 11-5 Amendment No. 34, 134

.i o RADIOACTIVE EFFLUENTS 3/4.11.3 DELFTED LIMITING CONDITION FOR'0PERATION j -l 3.11.3 This' Specification is deleted, h 1 l-o s ll tf ru $I' -l /; i y 7 .l (0 c) le yn g .o j l? "i l p I;- SEQUOYAH - UNIT 2: 3/4 11-6 Amendment No. 34' 134 i,, ,3 i ,i -1

RADIOACTIVE EFFLUENTS 3/4.11.4 DELETED LIMITING CONDITION FOR OPERATION 3.11.4 This Specification is deleted. l ) 8 -l i SEQUOYAH - UNIT 2 3/4 11-7 Amenoment.No. 34 .134 o

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3.,

I LIMITING CONDITION FOR OPERATION - 3.12.1. This-Specification is deleted.- ~ 3.12.2. This Specification is deleted. b - 1 3.12.3' This Specification is deleted, m. s-rr >. L' ' i t .\\<1.. t I e t t of, l =1 \\ d .I \\ L. s J)' I .I 4 .i l-: ,i-j 1. t' I I l 4 v;; ly g - i m-., 4

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'i.. S U;: > 's y n t; sw 1;jv ' ij' i t- _N/, j a: J l SEQUOYAH UNIT 2, 3/4 12-1 Amendment No. 34, 104, 134 ../ I r, t' I.(* ,'r'(_

.. ~. 1 INSTRUMENTATION BASES 3/4.3.3.-7 ACCIDENT MONITORING INSTRUMENTATION (continued) b. Temperature sensors downstream of each safety valve (one per valve). Tem-perature indication and alarm are provided in the main control room, c. Pressurizer relief tank temperature, pressure and level indication, and alarm in main control room. Pressurizer pressure indication and alarm in the main contre, room. d. 'Although all the above position indicators for the pressurizer safety valves and the PORVs are acceptable as one of the channels, the acoustic monitors must be onez of the two required operable channels. In addition to the four methods described above, the PORVs use an' electromagnetic " reed"-switch to determine valve position. The stem mounted switches are no longer in use since the PORVs were changed. 3/4.3.3.8 FIRE DETECTION INSTRUMENTATIO.T l: E OPERABILITY of the fire detection instrumentation ensures that adequate l warning capability is available for.the prompt detection of fires. This capability is required in order to detect _ and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to g safety related equipment and is an integral element in the overall facility b fire protection program, o* In the event that a portion of the fire detection instrumentation is .. inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation y' L is-restored to OPERABILITY. "3/4.3.3.9 ll This Specification is deleted. 3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION 'This instrumentation includes provisions for monitoring the concentrations of j Epotentially explosive gas mixtures in the waste gas holdup system. The OPERA-BILITY and use of.this instrumentation-is consistent with the requirements for monitoring potentially explosive gas mixtures. r s LSEQUOYAH - UNIT 2 B 3/4 3-4 Amendment No. 35, 46, 134 .a,

,<m, 5. .3/4.11 RADI0 ACTIVE-EFFLUENTS i BASES-3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 This' specification is deleted. 13/4.11.1.2- .This specification is deleted. -3/4.11.1.3 ix-- This, specification ^is-deleted. 3/4.'11.' *~ LIQUID HOLOUP TANKS , Restricting the quantity of radioacti d material contained in the specified -tanks provides assurance that in the eve. of an uncontrolled release of the tanks' contents, the resulting concentrations would be-lest than the limits of- -10 CFR Part 20,: Appendix B. Table 11, Column 2, at the nearest potable water supply -and -the nearest surface water.. supply in an unrestricted area. 3/4.11.2 ~ GASEOUS EFFLUENTS 3/4.11.2.1: This ~ specification is-deleted. 3/4.11.2.2! 'This specification-is deleted. 3/4.11.2;3 m

• This., specification.is deleted.

'3/4.1I.2.4 Thisj specification is deleted. t W ESEQUOYAH -; UNIT 2 B 3/4'11-1 Amendment No. 34,134-u

o. RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 EXPLOSIVE GAS MIXTURE . e This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen-and oxygen below their flammability limits pro-vides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. t 3/4.11.2.6 GAS DECAY TANKS j Restricting the quantity of radiosctivity contained in each gas decay tank provides assurance that in the event of an uncontrolled release of the tcnk's contents, the resulting total body exposure'to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is. consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure". 3/4.11.3 This' specification is deleted. m 3/4.11.4 This specification.is deleted._ SEQUOYAH - UNIT _2 B 3/4 11-2 Amendment No. 34,134

^^ 1 J 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING q BASES 3/4.12.1 ' This specification is. deleted. I 3/4.12.2 This' specification is deleted. ji 3/4.12.3 This specification is deleted. = 5 - 7, '?t, kl : 5 I 's = dd q-i '3D b ~4, 4 2,. i1 e t e Vik, :> ! SEQUOYAH - UNIT 2-B 3/4 12-1 Amendment No. 34,134 1;-

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3 ' ADMINISTRATIVE CONTROLS u h. Quality Assurance Program for effluent monitoring, using the guidance + contained in Regulatory Guide 4.15, December 1977 or Regulatory ~ Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev.1,1975. ~ 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in Specification 6.5.1A above. 6.8.3 Temporary changes to procedures of 6.8.1, above may be made provided: a. The intent of the original procedure is not altered. i b', The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. The' change Is approved in accordance with Specification 6.5.1A above c. within 14 days-of implementation. 6.8.4 Written procedures shall be established, implemented and maintained tar Radiological Control covering the activities below: a. OFFSITE DOSE CALCULATIONAL MANUAL implementation. -b. Quality Assurance Program and environmental monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977. q 6.8.5: The following programs shall be established, implemented, maintained, and' changes thereto made in accordance with Section 6.5.1A: a.. Primary Coolant Sources Outside' Containment A program to reduce leakage'from those portions of systems ou. side containment that could contain highly' radioactive fluids _ during a serious transient or accident to as low as practical levels. The systems include the safety injection system, residual heat renoval system,' chemical and volume control; system,' containment spray system, and RCS sampling system.' The program.shall include the following: J(1) ' Preventive maintenance.and periodic visual inspection requirements,- and 1 (ii) Integrated leak test requirements for each system =.; sfueling ~ cycle intervals or less. m , d.. - .SEQUOYAH - UNIT 2 6-15 gendmentNo. 34, 50, 66 I

ii av s i ADMINISTRATIVE CONTROLS 4 b.- In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine j, the airberne iodine concentrations in vital areas under accident conditions. This program shall include the following: (i) Training of personnel. (ii) Procedures for monitoring, and (iii) Provisions for maintenance of skmpling ano analysis equipment. c. Secondary Water Chemistry A program for monitoring of secondary water chemiatry to inhibit steam generator tube degradation. This program st all. include: 4 -(i). Identification of-a samp1.ing schedule for the critical variables and control points for these variables, 4 (ii) Identification of the procedures used to measure the values of ,, g the critical variables, m -_ iii) Identification of process sampling points,. ( g (iv) Procedures for the recording and management of data, (v) l Procedures defining corrective actions for off-control point chemistry conditions,- (vi) Procedures identifying'(a) the authority responsible for the interpretation.of the data; and (b) the~ sequence and timing of administrative = events required to, initiate corrective action,

and g

(vii) Monitoring.of the condensate at the discharge of the. condensate pumps.for evidence of conderser in-leakage. When condenser I .in-leakage.is confirmed, the leak shall.be-repaired, plugged,- ( .or isolated. ~ - d. - Backup Method for Determining Subcooling Marcin g A program which will ensure the-capability to accurately monitor the l Reactor Coolant System"Subcooling Margin. This program shall. include the following: (i) Training of personnel, and .(ii)' Procedures for monitoring. ,4 l SEQUOYAH - UNIT 2. 6-16 Amendment No.-50,-66 k 'd'

.c z.. 1 ADMINISTRATIVE CONTROLS e. Postaccident Samplina -A program which will ensure the capability to obtain and analyze reactor _. coolant, radioactive iodines and particulates in plant >l0 ; gaseous effluents,_and containment atmosphere. samples under -accident conditions. The program shall include the following: a-- (1) Training of personnel, (ii) Procedures for sampling and analysi.. (iii). Provisions.for maintenance of sampling and analysis equipment. ~ '. f. Radioactive Effluent Controls Program . -Y A program shall be provided conforming with 10 CFR 50.36a for the j ti control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive' effluents as=1ow as reasonably achievable. -The program (1) shall be contained in the ODCM, (2) shall

be' implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program: limits are exceeded.

The program shall include the following. elements: 1). Limitations on the operability of radioactive liquid and gaseous i monitoring instrumentation ~ including surveillance tests and set-point determination in accordance with the methodology:in the-ODCM,_ 2) ~ imitations on the concentrations of radioactive material L m - released in liquid effluents.to UNRESTRICTED AREAS; conforming 1 to 10 CFR Part'20, Appendix B.' Table II', Column 2, 3) Monitoring, sampling, and analysis of radioactive liquid and . gaseous effluents.in accordance with 10-CFR 20.106 and with the methodology and parameters in the ODCM, 4) Limitations on the annual and quarterly l doses or dose commitment J to a' MEMBER OF THE PUBLIC from radioactive materialsLin. liquid - effluents release from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,= ~ , - 5)' Determination of cumulative'and projected doseLeontributions l from-radioactive effluents' for the' current' caleadar quarter and . current calendar year i_n accordance with the methodology and f parameters:in the ODCM at least every 31 days, 6)z Limitati'ns.-on-the operability and use'of the-liquid and .( .. gaseous. effluent treatment systems to ensure _ that the: appro-priate portions of these systems are.used to reduce releases 7 '/ m 'L l.. 1 SEQUOYAH - UNIT 2' 6-17 ' Amendment'Nos. 28, 50, 66 s 134 [ sh /, _ i .ih! ,e

E o /, ADMINISTRATIVE CONTROLS 6.8.5 f. Radioactive' Effluent Controls Program (Cont.) 1 i .of radioactivity when the projected doses in a 31-day period - would exrted 2 percent of the guidelines for the annual dose or dose conmitment conforming to Appendix I to 10 CFR Part 50,. 7) Limitations on the dose rate resulting from radioactive etaterial released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit 4 h 'to areas beyond the SITE B0UNDARY conforming to Appendix I to 1 n,j 10 CFR Part 50, 1 9) Limitations on the annual and quarterly doses to a MEMBER OF-THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-i nuclides in particulate. form with half-lives greater than 8 days;in._ gaseous effluents released from each unit to areas beyond the' SITE. BOUNDARY conformine to Appendix.I to 10 CFR' .Part 50,1 and H 1 o

10) : Limitations on-the annual dose or dose commitment to any MEMBER:

i ? 10F THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources: conforming to 40 CFR Part 190.- { g. .RadiologicaliEnvironmental Monitorina Proaram t g 1 A program shall be-provided to+ monitor'the radiation and radionuclides M in;the' environs of the plant. The program shall provide (1) represen - ' l R, .tative= measurements of radioactivity in the-highest potential exposure ! pathways,,and (2). verification of the accuracy of the effluent' moni-s toring. program ~and'modeling of environmental: exposure pathways..The-program'shall.(1).be. contained in:the'ODCM,-(2) conform to the guid - ance-of' Appendix I'to 10 CFR Part'50, and:(3) incl ue the.following: r ir N '1). lM sitoring., sampling, analysis, and reporting of radiation and radionuclides in the environment in'accordance with the meth'odology;andparameters-inthe'00CM, if 2)- A. Land UsetCensus to' ensure that changes in the use of areas at-

and'beyond the. SITE BOUNDARY are identified and:that modifica-tions to.the monitoring-program'are made'if required by the 3,

'results2of this-census, and. 7 1g eV + j w SEQUOYAHr,- UNIT 2 6-18 Amendment Nos. 28,-50, 66 t 134 + ,Qpi1 I

.3 9 ADMINISTRATIVE CONTROLS 3) Participation in a Interlaboratory Comparison Program to -ensure -that independent checks on the precision and accuracy of.the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. '6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporticq requirements of Title 10, Code of Federal Regulations, the following report: shall be submitted in accordan.e with 10 CFR 50.4. 'STARTUP REPORT p< 6.9.1.1 : A summary report of plant startup and power escalation testing shall E

be submitted following. (1). receipt of an operating license, (2) amend.nent to the license _ involving a planned increase in power level, (3) insta11atien of

_ fuel that has a'different design or has been manufactured by a different fuel supplier, and. (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of'the plant. 6.9.1.2-The startup raport sha11' address each of the tests identified in the + -FSAR and.shall inr 'de a description of the measured values of the operating conditions.or charucteristics obtained during the test program and a comparison 'y cof these value. with design predictions and specifications. Any corrective [' ' actions that were required to obtain satisfactory operation shall also be cde,cribed. Any additional specifici etails' required in license conditions ) d % sed on.other commitments shall be' included in this report. 6.9.1.-3: Startup reports shall be submitted within (1) 90-days following f[ completion of the ctartup test program, (2) 90 days following resumption or l commencement of commercial power operation, or' (3) 9 months following initial. criticality, whichever is earliest. If the-Startup Report does not cover all

three e'ents (i.e., initial criticality, completion'of startup; test program, v

N, and; resumption or commencoment of commercial power operatico),- supplementary reports shall.be submitted at least every three months until'all three events. f .have been completed. \\ i' 4 d/ i SEQUOYAH;- UNIT'2 6-19 A. went Nos. 28, 50, 64, -. L

'.s ADMINISTRATIVE CONTROLS ANNUAL REPORTS 1! 7 6.9.1.4 Annual reports ccvsring the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6. 9.1. 5 Reports required on an annual basis shall include a tabulation on an y

annual basis for the number of station, utility and other personnel ~(including L contractors) receiving exposures greater than 100 mrem /yr and their associated 2 man rem exposure according to work and job functions, / e.g., reactor operations and_ surveillance, inse:'vice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on-pocket dosimeter, TLD, or film' badge measurements. Small exposures totalling less than 20% of the L individual total dose.need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions. If the results of-specific activity analysis in which the primary coolant exceeded the limits of specification 3.4.8.a, then the following information shall be included along with the results of specific activity analysis results in which the primary coolant exceeded the limits of the specifications: (1) Reactor power history starting 48 hours prior to the irst samt; l' which- . the limit was exceeded; (2) Results of the last isotopic analysis fc-radio-ciodine performed prior to exceeding the limit, results of analysis while the limit was excaeded and-results of one analysis after the radiciodine activity was reduced to less than the-limit. Each result should include date and time of ' sampling and the radioiodine concentrations; (3) Clean-up system flow history starting I.8 hours prior to the first sample in which the limit was exceeded; (4)-Graph of the I-131 concentration and one other radioiodine isotope concen-tration_in microcuries-per gram as a function of' time for;the duration of the specific activity above the steady-state level; and (5) The time' duration when the specific activity of the primary coolant' exceeded the radioiodine limit. Y 1/ A single submittal may be made for a multiple unit station. The submittel should combine those sections-that are common to all units at the station. 2/- This tabulation supplements the requirements of S 20.407 of 10 CFR Part 20. I SEQUOYAH_.- UNIT 2 6-20 A.wrdinent No. 34, 50, 66, 107 =. 134 I ui

4 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT /

6. 9.1. 6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The report shall include summaries, interpreta-tions,'and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with-the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. 6.9.1.7 (Relocated to the ODCM.) SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1/ 6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted wi_ thin 60 days af ter January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the 00CM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

6. 9.1. 9 (Relocated to the ODCM or PCP.)

n 1/ A single submittal may 'se made for a multN1e unit station. The submittal ~ should combine those sections that are cc m an to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. SEQUOYAH - UNIT 2 6-21 Amendment No. 34, 50, 66, 107 134

ADMINISTRATIVE CON 1, 'S MONTHLY REACTOR OPb.ATING PEPORT 6.9.1.10. Routine reports of operating statistics and shutdown experience, including documentation of all challentes to the PORVs or Safety Valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report. Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the pe*iod in which the-evaluation was reviewed and accepted by the PORC. RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided at least 60 days prior to cycle initial criticality. In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission. Any information needed to suport W(z) will be by request from the NRC and need. not be included in this report. SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified for each report, in accordance with 10 CFR 50.4. 6.9.2.2 Diesel Generator Reliability Improvement Program As a minimum the Reliability Improvement Program report for NRC audit, required by LCO 3.8.1.1, Table 4.8-1, shall include: (a) a summary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed (b) a' $ lysis of failures and determination of root causes of failures (c) evaluation of each of the recommendations of NUREG/CR-0660, " Enhancement of Onsite Emergency Diesel Generator Reliability in. Operating Reactors," with respect to their applicatP'. to the Plant (d) identification of all actions taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability (e) the schedule for implementation of each action from d) above (f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment SEQUOYAH - UNIT 2 6-22 Amendment Nos. 44, 50, 64, 66, 107, 134 u =

ADMINISTRATIVF CONTROLS Diesel Generator Reliability Improvement Program (Continued) A supplemental report shall be prepared within 30 days after each subsequent failure during a valid demand for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improvement program remedial action. The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator. The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the diesel generator improvement program and the schedule for implementation of those changes. In addition to the above, submit a yearly data report on the diesel generator l reliability. 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code l of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.1 The.following records shall be retained for at least five years: a. Records and logs of unit operation covering time interval at ech power level. l-b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to l-nuclear safety. 1 l c. All REPORTABLE EVENTS submitted to the Commission. l l d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications, Records of changes made to the procedures required by Specification e. 6.8.1 and 6.8.4. f. Records of radioactive shipments, g. Records of sealed source and fission detector leak tests-and results. L h. Records of annual physical inventory of all sealed source material of record. SEQUOYAH - UNIT 2 6-23 Amendment Nos. 44, 50, 66, 107, 134

~ ADMINISTRATIVE CONTROLS t 6;10.2 -The following records shall be retained for the duration of the Unit g . Operating License: Records and drawing changes reflecting unit design modifications made to a. systems and equipment described in the Final Safety Analysis Report, b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. Records of ~ radiation exposure for all individuals entering radiation e c. control areas. 7 L d. Records of gaseous and liquid radioactive material released to the environs. Records of transient or operational cycles for those unit components e. identified in Table 5.7-1. In f. Records of reactor tests and experiments. p p g. Records'of training and qualification for current members of the Em~ facility staff. 'h. -Records of in-service inspections performed pursuant to these Technical . Specifications. ) f l.

1..

Records of Quality Assurance activities required for lifetime reten-L, tion by the Nuclear-Quality Assurance Manual. j. Records of reviews' performed for changes made to procedures or = equipment or. reviews 'of. tests and experiments pursuant 'to 10 CFR 50.59. .l 4> k. Records of_ meetings of the PORC, SQN RARC, and the NSRB.' i '1. Records of. analyses required by the radiological environmental 1 monitoring program. o -1 -Records of~-secondary water. sampling and water quality. m. - n '. - Records of the service life monitoring of all safety-related hy-L drauliciand mechanical snubbers, required by T/S.3.7.9,iincluding Q the: maintenance performed'to renew the service'11fe~.- 1 u -o. . Records for. environmental qualification ~which are covered under the.

1 provisions of. paragraph'2.C.(10)(b) of license No. OPR-79.

~ n p. Records of reviews performed for changes made to the OFFSITE DOSE ]' CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. o i l

.l SEQUOYAH:- UNIT-2 6-24 Amendment No. 28, 50, 66,-134 j

g' 96 ajf '

[

o t... ,J .g 1 ADMINISTRATIVE CONTROLS z 6.11 RADIATION PROTECTION-PROGRAM . Procedures for personnel radiation protection shall be prepared consistent. K with.the requirements of 10 CFR Part 20 and shall be approved, maintained and . adhered to for all operations involving personnel radiation exposure. 6 4 1 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of L -radiction is greater than 100 mrem /hr but less than 1000 mrem /hr shall be L

barricaded and conspicuously posted as a high radiation area and entrance L

thereto shall be controlled by requiring issuance of a Special (Radiation) ? Work Permit *. Any individual or group of individuals permitted to enter.such areas shall be provided with or' accompanied by one or more of the following: A radiation monitoring device which continuously indicates the 3 a.- l L radiation dose rate in the area. l b.. A radiation monitoring device which continuously 1.,tegrates'the-radiation dose rate in the area and alarms when a preset integrated dose is received.- Entry into such areas with this monitoring device j: may be made after the dose rate level in the area has been estab-11shed and personnel have been made knowledgeable of them. c. An individual qualified in radiation protection procedures who is i

equipped with a. radiation dose. rate monitoring device.

This indi-L vidual shall be responsible for providing positive control over the' activities within.the area and shall-perform control'over the activ- -ities within the area and=shall perform periodic rediation surveil-lance at the frequency specified by the facility Site Radiological ~ Control: Superir.tendent in the Special (Radiation) Work Permit. 6.12.2. The requirements of 6.12.1, above, shallt also apply to each high L - radiation area in which the intensity of. radiation is' greater than ~1000 mrem / hr. Iniaddition,-locked doors shall be provided to prevent unauthorized entry into such~ areas and the keys shall be maintained under the-administrative control =of the Shift Supervisor on duty and/or.the Site l Radiological Control' l Superintendent. ~ q l ,l k Ik j

• Radiological' Control personnel or personnel escorted by Radiclogical. Control personnel in accordance with approved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties,' provided they comply with approved radiation 1

protection procedures for entry into high radiation areas. g SEQUOYAH-- UNIT 2 6-25 Amendment No. 34, 50, 66, 134 l,' j [ T,4 i ) l lf,\\ 1 4

f ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 16.13.1 Changes to the PCP: 1.- Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2p. This documentation shall contain: b: a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b. A determination that the change will maintain the overall conformance of the solidified waste product to existing require-ments of Federal, State, or other applicable regulations. 2.- Shall become effective after review and approval in accordance with Section 6.5.1A. 6.14 0FFSITEDOSECALCULATIONMANUAL(0DCM) J .6.14.1 Changes to the ODCM: 1 ' 1. Shall be documented and records of reviews performed shall b'e _ retained as required 'oy Specification'6.10:2p.- This documentation shall contain: .a. Sufficient information.to. support the change tcgether with the appropriate analyses or evaluations justifying the change (s) and 4 b. A determination that the change will maintain the level of radioactive' effluent control; required by 10 CFR 20.106, 40 CFR Part:190,L10 CFR.50.36a,,and Appendix I. to 10 CFR Part 50 and-not adversely impact the! accuracy or reliability of effluent. . dose, or setpoint calculations. M 2. Shall becomeleffective after review and acceptance by the SQN RARC. ,oX . 3.: 'Shallbe:subbittedtothe.Commissionin'theformofacomplete, legibleicopy/of the er, tire.0DCM as a part.of or concurrent with the Semiannu'al Radioactive: Effluent Release Report'for the period oftthe- . 1 reportrin which any change to the 0DCM was made'. Each change shall: y lbe identified by markings.in the margin of the affected pages,. clearly indicating ('the' area of the page that was changed,' and shall indicate.the date e.g., ~~ month / year).the change was implemented. 1

• d'

'y L 1 in 4 E' SEQUOYAH - UNIT /2 6-26 Amendment No. 34, 50,'66 ' ~ '134 w .,?

{i,-

g 5

a-5' r ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):* 1. Shall be reported to the Commission in the Semi-Annual Radioactive Effluent Report for the period in which the evaluation was reviewed in accordance with Section 6.5,1A. The discussion of each change shall contain: a. A summary of the evaluation tiit led to the determination that the change could be made in ac:ordance with 10 CFR 50.59; b. sufficient detailed informatici to totally support the reason for the change without benefit of additional or supplemental information; a detailed description of tne equipment, components and proces-c. ses involved and the inte.cfaces with other plant systems, d. 'an evaluation for the change which shows the predicted releases of radioactive me.terials in liquid and gaseous effluents and/or quantity of sciid waste that differ from those previously oredicted fii the-license application and amendments thereto; e, an evaluation of the change which shows the expected maxiins.n exposures to individual in the' unrestricted area and to.the general population that differ from those previously estimated 'inithe license application t.nd amendments thereto; f. a comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and.in solid waste, to the L actual releases for the period prior to when the changes are ) be made;- 'g. an estimate of the exposure to plant operating personnel as a result of the change; and t, documentation of the fact that the change was reviewed and found acceptable in accordance with Section 6.5.1A. -2. Shall become effective upon review and acceptance in accordance with i Section 6.6.1A. o h

• Submittal--of information required by this section may be made as part of the-i m

annual FSAR update. 1.( ' L 'SEQUOYAH_- UNIT 2 6-27 Amendment No. 34, 50, 66, 134 ] c { -}}