Text

Marked-up Proposed Tech Specs Re Radiation Monitoring Instrumentation,Accident Monitoring Instrumentation, Radiological Effluents,Secondary Containment Bypass Leakage Paths & Electrical Power Sys
	ML20138H883
Person / Time
Site:	Sequoyah
Issue date:	12/09/1985
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20138H860	List: ML20138H855; ML20138H883;
References
	RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8512170362
	Download: ML20138H883 (27)
	v • d • e

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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TVA SON TS 52)

NUREG-0737 TECHNICAL SPECIFICATIONS DESCRIPTION OF CHANGES

1. Unit 1 page 3/4 3-40, Table 3.3-6 item 2.d.1 - Applicability should be Modes 1, 2, 3, and 4

2. Unit 1 page 3/4 3-40 Table 3.3-6 item 2.d.11 - Minimum Channels Operable value should be 1.

3. Unit 1 page 3/4 3-77, ACTION 41 - Margin bar has been added to specify where footnote pointer was deleted.

4. Unit I page 3/4 4-39 Asterisked footnote should specify block valves vs.

" blocked" valves.

5. Unit 2 page 3/4 3-42, ACTION 30 - Extraneous "M" should be deleted

6. Unit 2 page 3/4 3-57, Item 17 - Clarify that footnote "***" is associated with the RVLIS.

7. ' Unit 2 page 3/4 4-39, Asterisked footnote should specify block valves vs.

" blocked" valves. Valves has been incorrectly typed as, " vales."

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PDR ADOCK 05000327 '

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, TA8tE 3.3-6

.< RADIATION MONITORING INSTRUMENTATION -

E. MINIMUM s '

CHANNEL $1 APPLICA8LE ALARM / TRIP g INSTRUMENT OPERA 8tE MODES SETPOINT MEASUREMENT RANGE ACTION

[ 1. AREA MONITORS

a. Fuel Storage Pool Area

1

$ 15 mR/hr 10'I - 10 4mR/hr 26

b. Containment Area 2 1, 2, 3 and 4 N/A 1 - 18 RAD /HR 30 -

2. PROCESS MONITORS

a. Containment Purge Air 1, 2, 3, 4 & 6 -3 1

$ 8.5 x 10 Ci/cc 10 107cpm 28

b. Containment

{ l. Gaseous Activity w

j a) Ventilation Isolation 1 ALL MODES < 8.5 x 10 -3 pCi/cc 10 - 10 7cpm 28 b)RCS Leakage Detection 1 1, 2, 3 & 4 -

N/A 10 - 10 cpm 27

11. Particulate Activity a) Ventilation Isolation 1 -5 b)RCS Leakage Detection 1 ALL M00ES $ 1.5 x 10 pct /cc TO - 10 7cpm 28 1, 2, 3 & 4 N/A 10 - 10 cpm 27

c. Control Room Isolation 1 ALL MODES 5 400 cpm ** 10 - 107cpm 29

-i d. Noble Gas Effluent Monitors 3

1. Shield Building Exhaust 1 1, ,&4 10- - 10 pCi/cc (High Range) 30

11. Condenser Exhaust _7 y

1,2,3, & 4 10 - 10 pC1/cc 30 (High Range)

Uith fuel in the storagg pool or building

- Equivalent to 1.0 x 10 p Ci/ce "

O u __ _ _ _ _ _ _ _ _ _ _ _ _ _

. i ."

TABLE 3.3-13 (Continued)

TABLE NOTATION At all times. ' '

- During waste gas disposal system operation.

- - During shield building exhaust system operation.

i ACTION 40 -.

With the number of channels OPERABLE less than required'by the Minimum Channels OPERABLE requirement, the contents of the

' tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the Facility Staff independent 1y' verify the release trate calculations. ,

and discharge valve lineup; - '

r Otherwis'e, suspend release'of radioactive affluents via this ',

pathw4y.

ACTION 41 .-

With the number of channels OPERABLE less than required by the Minimum' Channels OPERABLE requirement. effluent releases via this pathway may continue for.up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . . l l

. ACTION 42 -

With the number of channels OPERABLE less than req'uired by the 4 i

Minimum Channels OPERABLE requirement, effluent releases via x this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and thesE samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . {

4 ACTION 43 - ,

With the number of channels OPERABLE less that required by the Minimum Channels OPERABLE requirement, operation of this waste -

gas disposal system may continue for up to 7idays provided grab l

samples are collected at -least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and ana13 zed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . With the hydregen and oxygen ,.

monitors inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . '

1 ACTION 44 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided ;

.that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the channel has been declared inoperable samples are continuously collectec:with auxiliary sampling equipment as required in Table 4.11-2. ', ,

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{ 4 SEQUOYAH - UNIT 1 3/4 3-77

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REACTOR COOLANT SYSTEM

[ REACTOR COOLANT SYSTEM VENTS

( .

LIMITING CONDITION FOR OPERATION '

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t 3.4.11 sTwo Reactor Coolant System Vent (RCSV) paths shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

3 a.

k'ith only one RCSV path OPERABLE, STARTUP and/or POWER OPERATIO continue provided the inoperable path is maintained-closed with power removed from the valve actuators; restore the inoperable path to OPERABLE status within 30 days; orc,be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT MiUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3 b.

With no RCSV path OPERABLE, restore at least one path to OPERABLE

'). [ status within SHUTD0hH 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months within or be 6inhours.

the following HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT

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1-SURVEILLANCE REOUIREMENTS

,4.4.11 18 months by:Each RCSV path shall be demonstrated OPERABLE at least once per '

m,

< a.

Verifying opag; that the position upstream for the manual isolation valve is locked in the head vent.

'Jr b.

Operating from the control each remotely room, andcontrolled valve through at least one cycle

.c.

Verifying flow through the RCSV paths during venting.

i Use of Power oneOperated system. Relief Valves (PORV's) with associated bloc

' /\ considered valves is

~, Closure of one or both block valves does ot make the vent path inoperable provided the valve (s) can be opened.

S

. Note:

}8\ This technical'apaciffcation and surveillance requirement will not be

'- implemented until Sequoyah Specific Instructions are developed for the use of this system as, committed to in our response to Supplement 1 of NUREG 0737 .

4

,SEQUpYAH - UNIT 1 3/4 4-39 1

TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 26 - With the numoer of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, perform area surveys of -

the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

ACTION 28 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.'

ACTION 29 - With the numDer of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

^

ACTICN 30 -

With the number of OPERABL1' Channel (s) less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

(1) either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or

.(2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SEQUOYAH - UNIT 2 3/4 3-42

IAULE 3.3-10 h ACCIDENT HONITORING INSTRUMENTATION * '

O .

E HINIHUM e

2 REQUIRE 0 H0. CHANNELS

INSTRUMENT OF CHANNELS OPERABLE .

N .

1. Reactor Coolant Tilot ( i e ange) 2 1

2. Reactor Coolant TCold (Wide Range) 2

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1

3. Containment Pressure (Wide Range) 2 1 l

4. Refueling Water Storage Tank Level 2 1

5. Reactor Coolant Pressure (Wide Range) 2 1

6. Pressurizer Level (Wide Range) 2 1

^ 7. Steam Line Pressure 2/ steam !ine 1/ steam line

8. Steam Generator Level - (Wide Range) 1/ steam generator 1/ steam generator

9. Steam Generator Level - (Narrow Range) -

1/ steam generator 1/ steam generator

10. Auxiliary Feedwater Flow Rate 1/ pump 1/ pump

11. Reactor Coolant Systeh Subcooling Margin Monitor 1 , 0

12. Pressurizer PORV Position Indicator

2/ valve 1/ valve

13. Pressurizer PORV Block Valve Position Indicator ** 2/ valve 1/ valve

14. Safety Valve Position Indicator 2/ valve 1/ valve

15. Containment Water Level (Wide Range) 2 1

16. In Core Thermocouples

17. Reactor Vessel Level Instrumentation System [ *** 24/ core quadrant 2/ core quadrant

~

1

Not applicable if ttie associated block valve is in the closed position.

- llot applicable if the block valve is verified in the closed position with power to the valve operator removed.

- - NOTE: This technical specification and surveillance requirement will not be implemented until Sequoyah Specific Instructions are developed i for the use of this system as committed to in our response to Supple-ry:rnr2 it c.R F9ar/R (iW11% . -

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. REACTOR COOLANT SYSTEM l REACTOR COOLANT SYSTEM VENTS LkITINGCONDITIONFOROPERATION '

3.4.11 Two Reactor Coolant System Vent (RCSV) paths shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With only one RCSV path OPERABLE, STARTUP and/or POWER OPERATION may continue provided the inoperable path is maintained closed with power removed from the valve actuators; restore the inoperable path to OPERABLE status within 30 days; or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following E hours.

b. * ~

With no RCSV path OPERABLE, restore at'least one path to OPERA 8LE status within within SHUTDOWN 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be.in 6HOT the following STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT hours.

SURVEILLANCE REQUIREMENTS 4.4.11 18 months Each by: RCSV path shall be demonstrated OPERABLE at least once per a.

Verifying that the upstream manual isolation valve is locked in the open position for t.he head vent.

b.

Operating each remotely from the control room, andcontrolled valve through at least one cycle c.

Verifying flow through the RCSV paths during venting.

wives

Use of Power Operated Relief Valves (PORV's) with associate bloc valves is considered one system. Closure of one or both block val does not make the vent path inoperable provided the valve (s) can be opene .

Note: This technical specification and surveillance requirement will not be implemented until Sequoyah Specific Instructions are developed for the use of this system as committed to in our response to Supplement 1 of NUREG 0737.

SEQUOYAH - UNIT 2 3/4 4-39 i

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TVA SQN TS 60)

RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)

DESCRIPTION OF CHANGES

1. Unit I and Unit 2, Table 4.11-1, page 3/4 11-3, item C - The existing heading is correct and should read, " Periodic Continuous Releases." The proposed change added a superscript "h" to the existing superscript "e."

2. Units 1 and 2, Surveillance Requirement 4.12.1 - Detection capabilities are described in Table 4.11-1; therefore, Table 4.2.1 should be changed to Table 4.12-1.

3. Unit 2, BASES 3/4.11.2.4 - the last sentence of BASES section 3/4.11.2.4 should read, "The specified limits governing the use of appropriate portions of the systems were specifed as a suitable fraction of the dose design objectives set forth in Sections II.B. and II.C of Appendix I', 10 CFR Part 50, for gaseous effluents."

4. Unit I section 6.10.2 item n - The margin bar was the result of a previous change to this specification. No change to item n is proposed by TVA-SQN-TS-60.

5. Unit I section 6.10.2 item o - Environmental Qualification license condition for unit 1 is 2.C.(12)(b).

6. Unit 2 section 6.10.2 item o - Environmental Qualification license condition for unit 2 is 2.C.(10)(b).

. TABLE 4.11-l'(Centinusd)

. RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

. Minimum ~ Lower Limit of Liquid Release Sampling Analysis Type of Activity Detection (LLD)

-' Type Frequency Frequenev Analvsis (pCi/ml*)

C. Periodic W Principa 5x10 Continuous *' C'ontinuous8 Composite

Emitters} Gamma ktl84545-1.-Ilon-Reclain- I-131 1x10

-6 able Waste Tank M8 M Dissolved and 1x10

-5

2. High Crud- Grab Sample Entrained Gases Tank (2) (Gamma Emitters)

3. Neutralizer ' M H-3 1x10

-5

. ' Tank Continuous 8 Composite

Gross Alpha 1x10

-8 Q Sr-89, Sr-90 5x10 Continuous 8 Composite

Fe-55 1x10

-6

~

TABLE NOTATION

a. The LLD is defined for the purpose of these specifications n's the saimilest concentration.of radioactive material in a sample that.will '

yield a net count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical ' >

separation):

4.66 s b E . V . 2.22x10s . Y . exp (-A.At)

Where: . -

LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, * )

l ss is the standard deviation of the background counting rate or of the c5unting rate of a blank sample as appropriate (as countes per minute), '

E is the counting efficiency as counts per disintegration V is the sample size in units of mass or volume, SEQUOYAH - UNIT I 3/4 11-3 a

RADIOACTIVELIQUIDWASTESAMPLINGANDkNALYSISPROGRAM Minimum Lower Limit of Liquid Release Sampling Analysis Type of Activity Type Frequency Frequency Detection (LLD)

Analysis (pCi/ml")

C. Periodic W Principa 5x10"I

, C,ontinuous*' Continuous 8 Composite

Emitters} Gamma e Releases

1. Non~ Reclaim- I-131 1x10

~0 able Waste Tank

M8 M Dissolved and 1x10

-5 E 2. High Crud Grab Sample Entrained Gases Tank (2) (Gamma Emitters)

3. Neutralizer- M H-3 1x10

-5 ,

Tank Continuous 8 Composite *

~

Gross Alpha 1x10 Sr-89,.Sr-90 ~8 Q 5x10 Continuous 8 Composite" Fe-55 ~0 1x10 !

i ,

~

TABLE NOTATION

a. The LLD is defined for the purpose of these specifications as the

. sam 11est concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s b g,

E . V . 2.22x10s , y , ,,p (.x,3g)

F t

Where: , .

i LLD is the "a priori"' lower limit of detection as defined above in l- microcurie per unit mass or volume, ,

s 3 is the standard deviation of the background counting rate or of the c5unting rate of a blank sample as appropriate (as countes per minute),

E is the counting efficiency as counts per disintegration V is the sample size in units of mass or volume, !

SEQUOYAH - UNIT 2 l 3/4 11-3 4

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__ .,,..._e.__,. . . _ . . . , _ _ _ _ . . _ _ . _ _ _ _ _ _ . . _ , . _ . . _ . _ , _ _ , . , _ _ _ _ _ . , _ _ . , , _ , . - . _ . _ . . _ _ _ _ . . . , , , _ . , _ .

.e ENVIRONMENTAL RADIOLOGICAL MONITORING LIMITING CONDITION FOR OPERATION report (LER) and pursuant to Specification 6.9.2, identify the cause(s) of the unavailability of samples and identify the new locations for obtaining replacement samples in the Annual Radio-logical Environmental Operating Report. A revised figure (s) and table (s) for the ODCM reflectin'g the new location (s) shall be included in in the next annual radiological effluent release report pursuantto specification 6.9.1.9.

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

~

4.12.1 pursuant The radiologica1 environmental monitoring samples shall be collected to table 3.12-1 from the locations given in the table and figure in the ODC!! and shall be analyzed pursuant to the requi.rements of tables 3.12-1 and the detection capabilities required by tabid y,lg-l,

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SEQUOYAll -

UNIT 1 3/4 12-2 l

-[

ENVIRONMENTALRADIOLOGICALMONITONING

' l LIMITING CONDITION FOR OPERATION l, i

report (LER) and pursuant to Specification 6.9.2, identify the I cause(s) of the unavailability of samples and identify the new !

locations for obtaining replacement samples in the Annual Radio-logical Environmental Operating Report. A revised figure (s) and i table (s) for. tha ODCM reflecting the new location (s) shall be included in '

in the next annual radiological effluent release report pursuantto specification 6.9.1.9.

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d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 Theradiologh.calenvironmentalmonitoringsamplesshallbecollected pursuant to table 3.12-1 from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the re3uirements of tables 3.12-1 and the detection capabilities required by table '4*.%4,,

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UNIT 2 3/4 12-2 L

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RADIOACTIVE EFFLUENTS l

} BASES t

3/4.11.2.3 DOSE - IODINE-131. TRITIUM, AND RADIONUCLIDES (Continued) on the existing radionuclide pathways to man, in the unrestricted area. The

! pathways which were examined in the development of these calculations were:

(1) individual inhalation of airborne radionuclides, (2) deposition of radio-l .nuclides onto green leafy vegetation with subsequent consumption by man, i

I (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of themilk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

J

3/4.11.2.4 GASEOUS RADWASTE TREATMENT

}

The requirement that the appropriate portions of these systems be used, when*

specified, provides reasonable assurance that the releases of radioactive * '

materials in gaseous affluents will be kept "as low as is reasonably achievable".

i i

This specification' implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives

given in Section II.D of Appendix I to 10 CFR Part 50. The specified sa suitable fraction of the dose design objectives set forth in Sections II.B and l II.C of Appendix I, 10 CFR Part 50, for gaseous affluents.1 0 rren 3/4.11.2.5 EXPLOSIVE GAS MIXTURE deestof.

oppe rfians/f4t' sys ens w s spec #d

) This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained '

below the flammability limits of hydrogen and oxygen. Maintaining the con-l centration of hydrogen and oxygen below their flammability limits provides 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.

3/4.11.2.6 GAS DECAY TANKS Restricting the quantity of radioactivity contained in each gas decay tank provides assurance 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".

a 4

3/4.11.3 SOLID RADIOACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include,

, but are not limited to waste type, waste pH, waste / liquid / solidification

agent / catalyst ratios, waste oil content, waste principal chemical constitu-J ents, mixing and curing times.

{ SEQUOYAH - UNIT 2 B32411-4 ,

4

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.

h. Records of new and irradiated- fuel inventory, f uel transfers .ind dssembly burnup histories.

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

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

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

f. Records of reactor tests and experiments,

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

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

i. Records of Quality Assurance activities required by the Operational 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

k. Records of meetings of the PORC, RARC, and the NSS reporic or the reuuttu of review and uf cognizance of auditc.

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 hydraulic and mechanical '

snubbers listed on Tables 3.7-4a and 3.7-4b, including the maintenance performed to renew the service life,

o. Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12) of License No. DPR-77. l 6.11 RADIATION PROTECTION PROGRAM (b

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

SEQUOYAH - UNIT 1 6-23

a a.

~

ADMINISTRATIVE CONTROLS

, 6.10.2 (Continued)

m. Records of secondary water sampling and water quality,

n. Records of the service lif e monitoring of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the maintenance performed to renew the service life. ,

o. Records for environmenta1 qualification which are i overed imder Ihe provisions os paragraph 2.C. M (b) of license Nu. 1)PH-i9.

6.11 RADIATION PROTECTION PROGRAM (lh Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

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 radiation is greater'than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by 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. A radiation monitoring device which continuously indicates the 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.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Special (Radiation) Work Permit.

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 ce naintained under the administrative control of the Shif t Engineer on duty and/or the Health Physicist. ,

" Health Physics personnel or personnel escorted by Health Physics 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.

SEQUOYAH - UNIT 2 6-29

ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TVA SQN TS 61)

SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS DESCRIPTION OF CHANGES

1. Units 1 and 2 Table 3.6-1, Move penetrations X-23, X-91, X-101, X-103, X-106, X-116 to the proper locations in the table and add a more detailed description of the penetration contents (see TVA-47W625-15).

2. Units 1 and 2 Table 3.6-1, Correct typographical error to correctly identify X-400 as the hydrogen purge line penetration. Moves X-400 to the proper location in the table (see TVA-47W846-2).

3. Units 1 and 2 Table 3.6-1, Move penetration X-44 to the proper location in the table and add a description of penetration's contents (see TVA-47W809-1).

TVA drawings 47W809-1, 47W625-15, 47W600-178 and 47W846-2 have been enclosed to support the conclusion that these changes are editorial in nature.

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ENCLOSURE 4 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TVA SON TS 62)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 1
l DESCRIPTION OF CHANGES
1. Units 1 and 2, LCO 3.8.3.1 - Margin bars have been added to clearly l Identify changes.
2. Units I and 2. LCO 3.8.3.1 - The original submittal deleted the phrase, "shown in Table 3.8-1" from the limiting condition for operation. The '
phrase should also have been deleted from the Surveillance Requirements.
Upon further review we propose to replace these deleted phrases with, "specified in appropriate plant instructions." This clarlfles the intent of the change which was to remove the table from the specifications and rely on existing plant instructions. These instructions are specified in the surveillance requirements previously submitted by our November 7, 1984 letter.
These revised pages are not intended to alter any of the test requirements for containment penetration conductor overcurrent protection devices and are consistent with the November 7, 1984 submittal.
i l
t
\
ELECTRICAL POWER SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CON 0! TION FOR OPERATION sfetll din optWt f&tinSfreeh'IIS o 3.8.3.1 All containment penetration conductor overcurrent protective devicesa shall be OPERABLE. /\
APPLICA8!LITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the containment penetration conductor overcurrent protective devicesAi noperablet l
.NA i.,
<t.
teteekt,'e.*etve.v tore the protective device (s) to OPERA 8LE status or de-energize the circuit (s) by tripping the associated backup circuit breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the backup circuit breaker to be tripped at least once per 7 days thereafter; the provisions of Specification 3.0.4 are-not applicable to overcurrent' devices in circuits which have their backup circuit breakers tripped, or
b. 8e in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
SURVEILLANCE REQUIREMENTS 4.8.3.1 -Allecontainment penetration conductor overcurrent protective devices
' n M TD 2 '; 2.I8 sftb$Irba. ~ fI@ D N t N8trhefient" ' phall be demonstrated OPERABLE:l t.. east dnce per 18 months:
1. For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72' months, by performance of:
(a) A CHANNEL CALIBRATION of the associated protective relays, Surveillance Instruction SNP SI-256 and , l (b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed using Surveillance Instruction SNP SI-257Ji e
l l
SEQUOYAH - UNIT 1 3/4 8-15 . l l .
l __.
j' *
. ,o
\.
)
't (WCTRICAL POWBR SYSTEMS SURVEILLANCE REQUIRDENTS (Continued) '
(c) For.each cirou'it breaker fbund inoperable during these functional' '
- . tests, an-additional mpresentative sample of at least 1 of the oircuit bmakers of the inoperable type shall also be function tested until no more failums are found or all circuit bmakers of that type have been functionally tested per Surveillance
,, . __ _ Instruqtion SNP SI-257. -** -"
2. By selecting and functionally testing a repmsentative sample of at ;
l-least 105 of eaon type of lower voltage circuit breakers. Circuit breakers selected for functional testing shall be selected on a v l ,, rotating basis. The functionni test, Surveillance Instruction SNP SI- )
t
.258, shall consist of injoeting a current input at the specified setpoint to each selected circuit breaker and verifying that each (
oircuit breaker functions as designed. Circuit bmakers found .
inopemble during functionni testing shall be restored to OPERABLE l
status prior to mausing operation. For each circuit breaker fbund
inoperable.during these functional tests, an additional representative sample of at least 10$ of all the oirouit breakers of the inopemble
' type shall also be functionally tested until no more failums are found or all circuit breakers of that type have been functionally tested. i
3. By sele 5 ting and functionally testing a representative sample of each type of fuse on a rotating basis. Each representative sample of fuses shall include at least 10% of all fuses of that type. The functional test, Surveillanoe Instruction SNP SI-270, shall consist of a non- i i
destructive resistance measurweent test which demonstrates that the l!
j fuse asets its manufacturgr's design criteria. Fuses found inopemble ,
during these functional testa shall be mplaced with OPERABLE fuses . .
!. -~ ' prior to resuming operation. For each fuse found inoperable during i
'these functional tests 7'ah~ additional representative sample of at least '
10$ of all fuses of that type shall be functionally tested until no i more tested.e failures arv found or all fuses of that type have been functionally
b. At least onoe per 60 months by subjecting each circuit bmaker to an inspection and preventive maintenance in accordance with Surveillance Instruction SNP SI-266 in conjunction with its annufacturer's recommen-dations. l
' Surveillance requirwoont al.8.3.1.a.3 may be suspended until the completion !
of Cycle 2 provided that the following surveillance requirement is implemented i A fuse inspoetion and maintenance program will be maintained to ensure that:
1. The proper size and type of fuse is installed,
2. The fuse shows no sign of deterioration, and 3 The fuse connections are tight and clean. .
i I
SEQUOYAN - UNIT 1 3/4 3 16
._-m. - _ _ _ _ - , _ _ . _
_w,_- ,,___-.
r-l l
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t . . -..- -... .:. . . .._ . . . _ . . .
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1 I
l I
I i
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1
PAGES 3/4 6-17 THROUGH 3/4 8-33
, , FOR MBLE 3.8-1 ARE DELrfRD e
l ,
. , p .
. .=
l ..
i O
8 O
t ELECTRICAL POWER SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION spetihed in appropriate pht instrWCtions 3.8.3.1 All containment penetration conductor overcurrent protective devices 4 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the containment penetration conductor overcurrent protective devicesA i noperables specs [M'm aaff*Prefeplagt *nskacfiens
a. 'Hestore the protective device (s) to OPERABLE status or de-energize the circuit (s) by tripping the associated backup circuit breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the backup circuit breaker to be tripped at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, or
b. 8e in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD '
SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . '
SURVEILLANCE REQUIREMENTS 4.8.3.1)Stu?.M'hallbedemonstratedOPERA8LE:U
t.w . .. "a W ioment penetration conductor o
$1 on p 18 months:
1. For at least one 6.9 kV reactor coolant pump circuit, such that a11 reactor coolant pump circuits are demonstrated OPERA 8LE at least once per 72 months, by performance of:
(a) A CHANNEL CALIBRATION of the associated protective relays, surveillance Instruction SNP SI-256 (b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circults function as designed using Surveillance Instruction SI-257.
SEQUOYAH - UNIT 2 3/4 8-16 .
E E.BCTRICAL POWER 3137EM i
SUWEILLANCE R(qUIRRE NTS (Continued)
(e) For each cirouit breaker found inoperable during these functional tests, an additional representative sample of at least 1 of the circuit breakere of the inoperable type shall also be functionally tested until no ~more failums are found or all circuit breakers of that type have been functionally tested per Surve111anoe Instruction SNP SI-257.
~ ~~
2. By selecting and functionally , testing,atrepresentative sample of at 11' east 105 or each type of lower voltage otrouit breakers. circuit !
breakere selected for functional testing shall be selected on a rotating basis. The functional test, Surveillance Instruction SNP SI-258, shall consist of injecting a ourrent input at the specified setpoint to each selected circuit bmaker and verifying that each circuit breaker functions as designed. Cirouit breakers found
- inoperable kring functional testing shall be restored to CPERABLE r status prior to mauming operation. For eaoh circuit breaker found inopemble .during these functional tests, an additionni representative semple of at least 10$ of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures am found or all circuit breakers of that type have been functionally tested.
3. By selecting and functionally testing a repmaantative snaple of each type of fuse on a rotating basis. Each mpresentative sample of fuses shall include at least 10$ of all fuses of that type. The functional test, Surveillance Instruction SNP SI-270, shall consist of a non-destructive resistanoe asasurement test which demonstrates that the fuse asets its manufactumr's design criteria. Fuses found inopemble during these functional teste shall be replaced with OPERABLE fuses ,
prior to meuming operation. For each fuse found inopemble kring these functional tests, an additional representative sample of at least 105 of all fuses of that type shall be functionally tested until no more failures
..L.~;.:.:*6estd.* ' , are ,found,_or
-~~
all _ fuses ..of.that_ type
~~ '" *~~
.have been functionally
b. At least onoe per 60 months by subjecting each circuit bmaker to an inspection and preventive maintenance in aooordance with Surveillanoe l Instruction SNP SI-266 in conjunction with its manufactumr's moommen- I dations.
'Surveillanoe requirement 4.8.31.a.3 may be suspended until the completion of Cycle 2 provided that the following surveillance requimeent is implemented:
A fuse inspection and maintenance program will be maintained to ensure that:
1. The proper sine and type of fuse is installed,
2. The fuse shows no sign of deterioration, and
3. The fuse connections are tight and clean. ,
SRQUOYAN - UNIT 2 3/4 s-17
l t
l e I
1 l a I
i PAGES 3/4 8-18 THR000N 3/4 8-32 i
FOR M SLE 3.8-1 ARE DE1.ETED
99 4
0 &
9. y e5 3 g D 4 t
i 9
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ML20138H883

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