Text

Proposed Tech Spec Changes as Result of Mods to Satisfy Requirements of NUREG-0737,Items II.B.1,II.F.1.1,II.F.1.3, II.F.1.4 & II.F.2 & Diesel Generator Testing
	ML20079P978
Person / Time
Site:	Sequoyah
Issue date:	01/25/1984
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20079P958	List: ML20079P955; ML20079P978;
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.F.1, TASK-2.F.2, TASK-TM NUDOCS 8401310425
	Download: ML20079P978 (30)
	v • d • e

- - - - _

~

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATIONS SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 1

i

'a h

l l-I l

8401310425 840125 PDR ADOCK 05000327 P PDR

, TABLE 3.3-6 -

RADIATION MONITORING INSTRUMENTATION 5 MINIMUM e

CHANNELE) APPLICABLE ALARM / TRIP MEASUREMENT

, g IllSTRufiENT OPERABLE MODES SETPOINT RANGE ACTION

l. AREA MONITORS

a. Fuel Storage Pool Area 1 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 Ci/cc 10 -~'10 7

a. Containment Purge Air -3 1 1, 2, 3, 4 & 6 5 8.5 x 10 cpm 28

b. Containment

{ i. Gaseous Activity y a) Ventilation Isolation 1 ALL MODES

-3 5 8.5 x 10 Ci/cc 10 - 10 cpm 28 g b)RCS Leakage Detection 1 1, 2, 3 & 4 - N/A 10 - 10 7cpm 27 ii. Particulate Activity a) Ventilation Isolation 1 -5 b)RCS Leakage Detection 1 ALL MODES 5 1.5 x 10 pCi/cc 10-10fcpm 28 1, 2, 3 & 4 N/A 10 - 10 cpm 27

c. Control Room Isolation 7 1 ALL MODES 5 400 cpm ** 10 - 10 cpm 29

,' d. Noble Gas Effluent Monitors

i. Shield Building Exhaust 1 1,2,4, & 4 10~ - 10 pCi/cc 30 (Iligh Range) -7 5

11. Condenser Exhaust 1,2,3, & 4 10 - 10 pCi/cc 30 (iiigh Range)

Uith fuel in the ,stor-qg pool or building

- Equivalent to 1.0 x 10 pCi/cc e

f .

I k-.

If;STRUMENTATION TABLE 3.3-6 (Continued) -

L;.

TABLE NOTATION J

ACTION 26 - With the number of OPERABLt channels less than required by the i 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 number.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 r. umber 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 i system in the recirculation mode of operation. I ACTION 30 - With the number of OPERABLE Channel (s) less than required by the.

Minimum Channel (s) OPERABLE rquirements, initiate the preplanned alternate method of monitorfag the appropriate parameter (s), I g

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.

SE0VOYAH - UNIT 1 3/4 3-41 y .a. t := - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ __

un- 3: a: ~ :- ~~

v, TABLE 4.3-3 .

EB g RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 55 x

OSES IN WHICH CHANNEL ,

!! CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i ' -< INSTRUMENT CHECK CALIBRATION TEST REQUIRED e

q 1. AREA MONITORS

a. Fuel Storage Pool Area S R M *

b. Containment Area S R M 1, 2, 3 & 4

2. PROCESS MONITORS

a. Containment Purge Air Exhaust S R M 1, 2, 3, 4 & 6 j' b. Containment Gaseous Activity

1. -

i' a) Ventilation Isolation S . R M ALL MODES

$$ b) RCS Leakage Detection 5 R M 1, 2, 3, & 4 ii. Particulate Activity j

a) Ventilation Isolation S R ;M ALL MODES b) RCS Leakage Detection S R -

M 1, 2, 3, & 4

c. Control Room Isolation S R M ALL MODES

., d. Noble Gas Effluent Monitors

i. Shield Building Exhaust S R M 1, 2, 3, & 4

,, (iligh Range)

11. Condenser Exhaust S R M 1, 2, 3, & 4 i' (Iligh Range)

With fuel in the storage pool or building f .

~

m TABLE 3.3-10 .

E g ACCIDENT MONITORING INSTRUMENTATION ,

s HININUM REQUIRED NO CilANNELS .

e 3 INSTRUMENT OF CHANNELS OPERABLE w

~ 1. 2 1 Reactor Coolant THot (Wide Range)

2. Reactor Coolant TCold (Wide Range) 2 1

.. 3. Containment Pressure (Wide Range) 2 l l

4. Refueling Water Storage Tank Level 2 ., 1

5. Reactor Coolant Pressure (Wide Range) 2 ] {

w 6. Pressurizer Level (Wide Range) 2 1 s

[ 7. Steam Line Pressure 2/ steam line 1/ steam line

8. Steam Generator Level - Wide 1/ steam generator 1/ steam generator l

l

9. Steam Lendrator level - Narrow 1/ steam generator 1/stecm generator

10. Auxiliary Feedwater Flow Rate 1/p, ump 1/ pump 1

11. Reactor Coolant System 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 4/ core quadrant 2/ core quadrant

- - 1

17. Reactor Vessel Level Instrumentation System ._

2

Not applicable if the associ,ated block valve is in the closed position.

- Not 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 im-plemented until Sequoyah Specific Instructions are developed for the use of this '

system as committed to in our response to Supplement 1 of NUREG 0737. ;

utiLL 4. 3-/

r .

f.! '

ACCIDENT MONITORING INSTRUMENTATION SURVEILLAtlCE REQUIREMENTS S>

i CilANNEL CFIANNEL c- INSTRUMENT C11ECK CALIBRATION -

25 1.

] Reactor Coolant Tilot (Wide Range) H R

2. Reactor Coolant T Cold Wide Range) H '

R

3. Containment Pressure (Wide Range) H R

4. Refueling Water Storage Tank Level H R

5. Reactor Coolant Pressure (Wide Range) H R

6. Pressurizer Level H R w

2 7. Steam Line Pressure H R

8. Steam Generator Level - Wide H R

9. Steas Generator Level'- Narrow H R

10. Auxiliary Feedwater Flowrate H R

11. Reactor Coolant System Subcooling Margin Monitor H 'R

12. Pressurizer PORV Position Indicator M R

13. Pressurizer PORV Block Valve H R Position Indicator

14. Safety Valve Position Indicator M R

15. Containment Water Level (Wide Range) H R

16. In Core Thermocouples N R

17. Reactor 'Tessel Level Instrumentation System ** M R 2

- Note: This technical specification and surveillance requirement will not be

'j~ 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.

i

v3 TABLE 3.3-13 E -

i 8 RADI0 ACTIVE GASE0US EFFLUENT M0tJITORING INSTRUMENTATION Y gi r .

MINIMUM CHANNELS E INSTRUMENT OPERABLE APPLICABILITY ACTION A

, _., 1. WASTE GAS DISPOSAL SYSTEM

d. Noble Gas Activity Monitor 1 *

b. 40 Effluent System Flow Rate Measuring Device 1

41

2. WASTE GAS DISPOSAL SYSTEM EXPLOSIVE GAS j f10NITORIllG SYSTEM ,

4

a. Hydrogen and Oxygen Monitors **

i 2 43

' w 3. CONDENSER VACUUM EXilAUST SYSTEM u

i w a. Noble Gas Activity Monitor (Low Range) -

I

42 h b. Flow Rate Monitor 1

41

4. SilIELD BUILDING EXilAUST SYSTEM l .

a. Noble Gas Activity Monitor (Low Range) 1

b. Iodine Sampler 42 1 ***

c. Particulate Sampler 44 1 ***

d. Flow Rate Monitor 44 1 ***

e. Sampler Flow Rate Monitor 41 1 ***

!- ' 41 i

a

=

\

1 I

1,.

(' f

^

l TABLE 3.3-13 (Continued)

TABLE !!0TATION i

- i

~^

At all times.

During waste gas disposal system operation.

i

- - During shield building exhaust system operation. i i r ACTI0tl 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:

l

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 independently verify the release rate calculations I and discharge valve lineup; -

l Otherwise, suspend release'of radioactive effluents ria this '

pathway.

l ACTI0tl 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 .

i ACTI0tl 42 -

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 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 . ,

i ACTI0tl 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 for up to 7 days provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . With the hydrogen and oxygen monitors inoperable, be in at least HOT STA!1DBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I 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 collected with auxiliary sampling equipment as required in Table 4.11-2.

]

, I SEQUOYAH - UNIT 1 3/4 3-77

g TABLE 4.3-9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL MODES IN WHICH h

= CilANilEL SOURCE CilANNEL FUNCTIONAL SURVEILLANCE U IriSIRbllENT CilECK CllECK CALIBRATION TEST REQUIRED I. WASlE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor P P R(3) Q(1) ****

, b. Flow Rate Monitor D fl. A. R Q

2. WASIE GAS DISPOSAL SYSTEM EXPLOSIVE GAS MONIIORIllG SYSTEM

.i i a. Ilydrogen ilonitor D N.A. Q(4) M

! b. Oxygen Monitor D N.A. Q(S) M R

3. C0llDENSER VACUUM EXilAUST SYSTEM

[

! b a. Noble Gas Activity Monitor (Low D M R(3) Q(2)

b. Flow Rate Monitor Range) D N.A. R Q

4. SilIELD BUILDING EXilAUST SYSTEM .

I

a. Noble Gas Activity Monitor (Low D M R(3) Q(2) ***

b. Iodine Sampler Range)W N.A. N.A. N.A.

4

c. Particulate Sampler W H.A. N.A. N.A.

d. Flow Rate Monitor D N.A. R Q

e. Saiiiplei Flow Rate Monitor D N.A. R Q i

I -

t e -,

i

REACTOR COOLANT SYSTEM i /'~ REACTOR COOLANT SYSTEM VENTS

(

i ,

LIMITING CONDITION FOR OPERATION h 1

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

APPLICABILITY: MODES 1, 2, and 3. t 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With no RCSV path OPERABLE, restore at least one path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

fr

\

SURVEILLANCE REOUIREMENTS s.

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

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

b.

Operating each remotely controlled valve through at least one cycle '

from the control room, and c.

Verifying flow through the RCSV paths during venting.

Use of Power Operated Relief Valves (PORV's) with associated blocked valves is considered one system. Closure of one or both block valves does not make the vent path inoperable provided the valve (s) can be opened. S ,

. Note:

This technical specif,1 cation and surveillance requirement will not be

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

SEQUOYAll - UNIT 1 3/4 4-39 9 , Y > $A .-

__ny-,,v-w--wmr--eM*Y

REACTOR COOLANT SYSTEM BASES i

3/4.4.11 REACTOR C001. ANT SYSTEM VENTS- -

from The function of the RCS ventspressurizer.

is to remove noncondensable or steam i

the reactor vessel head and/or This system is designed to mitigate a possible condition of inadequate core cooling, inadequate natural i

. circulation, or inability to depressurize the RHR System initiated conditions resulting from the accumulation of noncondensable gases in the Reactor Coolant System.

with redundant The reactor safetyvessel grade head vent and the pressurizer vent are each designed vent paths. Having either system OPERABLE or having one path in each system from opposite trains OPERABLE is sufficient to meet the provisions of Specificatic i 3.4.11, 4

s i

i,

f. -

t t

P l

t i

t SEQUOYAH - UNIT 1 B 3/4 4-16

_ - _ - _ . . . ~

- -:==---~~'~ ~~ ~ ~ ~ - ~ ' ~'~

ELECTRICAL POWER SYSTEh5 SURVEILLANCE RECUIREMENTS (Continued) ,

4. Simulating a loss of offsite power by itself, and:

a) Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.

Verifying the diesel starts on the auto-start signal, b) energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady state voltage and frequency of the shutdown boards shall be maintained at 6900 690 volts and 60 t 1.2 Hz during this test. i

5. Verifying that on a ESF actuation test signal, without loss of offsite power, the diesel generator starts on the auto start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 6900 690 volts and 60 t 1.2 Hz within 10 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained within these limits during this test.

n I

i

6. Simulating a loss of offsite power in conjunction with an ESF i actuation test signal, and I a) Verifying de-energization of the shutdown boards and load shedding frcm the shutdown boards.

b) Verifying the diesel starts on the auto-start signal, erergizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 6900 690 volts and 60 1.2 Hz during this test.

c) Verifying that all automatic diesel generator trips, except engine overspeed and generator differential, are automatically bypassed upon loss of voltage on the shutdown board and/o" safety injection actuation signal.

SEQUOYAH - UNIT 2 3/4 8-4

)

i ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

. t

7. Verifying the diesel generator operates for at least 24 nours.-

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to greater than or equal to 4400 kw and duri'ng the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded to greater than or equal to 4000 kw. The generator voltage and fraquency shall be 6900 690 volts and 60 1.2 Hz within 10 seconds after the start signal; the steady state generatnr voltage and frequency shall be maintained within these limits auring this test. Within 5 minutes after completing this 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test, perform Specification 4.8.1.1.2.d.4.b

8. Verifying that the auto-connected loa'ds to each diesel generator do not exceed the 2000~ hour rating of 4000 kw.

9. Verifying the diesel . generator's 'cadability to:

a) Synchronize with the offsite power source while the

, generator is loaded with its emergency Ioads upon a simulated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Be restored to its shutdown status, i

10. Verifying that the automatic load sequence timers are OPERABLE with the setpoint for each sequence timer within + 5 percent of .

its design setpoint.

11. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) Engine overspeed b) 86 GA lockout relay s

e. At least once per 10 years or after any modifications which could affect diesel generator interdependence by startind the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds.

SEQUOYAH - UNIT 2 3/4 8-5 58 WMI5% __

sps~ J&#rW cw _

nde

.,,, 'l Allt i 3.3

.----.f3 m *

~@. ItAD1 AI10H 110ril10ltiilG 1fiSIIllMt ill AIION o

@ MINIHild ,

. CilAhfll l *> APPI lCAllt i Al Al:H/IitIP Hl:ASul:111Lill

, c- INSiltilMl NI OPll(Allil' (1001 S SI IPulfil RAllGl. ACI1011

e

,Q l. AltLA MONil0RS N a. luel Storage I....l Area i ^ s 15 mR/lir 10'I - 10 mR/lir 26 8

b. Cont aisunent h. . i 2- 1, 2, 3 & 4 N/A 1- 10 RAD /HR. 30

2. PROCLSS M0Hil0RS

a. Containment 1...se Air i 1, 2, 3, 4 & 6 < H.S x 10- pCi/cc 10 - 10 com 26 13 Con t a isuaent

i. Giscons i.. ivity I

_3 7 a)VenL i 1.it inn i30lat ion 1 Al! !!ODI S -

8. S x 10 pCi/cc 10 - 107 cpm 2 11 l l>)RCS leatage Detection i 1, 2, 3 & 4 ft/A 10 - 10 cpm 2/

.t> ii. Particulate Activity _g 7 4 a) Ventilation isolation 1 All H0DLS ( l.S x 10 pCi/cc 10 - 107 cpm 28 y l>)RCS t eatage Det ect. ion 1 1, ?, 3 & 4' N/A 10 - 10 cpm 2/

D c. Control R4a.m isolation 1 All 110DI S i 400 cpm ^^ 10 - 10 (pm 29

d. flotale Gas Lttinent 11onitors .

- 105Ci/cc

i. Shield Building Exhaust 1 1, 2, 3, & 4 -7 30 10 (iiigh Range)

11. Condenser Exhaust 1 1, 2, 3, & 4 10-7 _ 105 Ci/cc 30 (Iligh Range)

OWith fuel in the storage pool or building

-5 00 Equivalent to 1.0 x 10 Ci/cc f .

I r A

TABLE 3.3-6 (Continued).

ACTION STATEMENTS .

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

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

ACTION 27 - With tne 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 OPERACLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.'

ACTION 29 - With the number of OPERABLE channels less than required by the Minimum Channels GPERABLE 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 tr.e recirculation mode of operation.

ACTION 30 - With the number of OPERABLE' Channel (s) less than required by the M 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

A' '

16151E 4 3:2 N-HADI All0li 110N110Rilk; INSil:lllll NIA110N SilRVi lll ANCE I?LQUIRIMENIS ,

CllANNLL HOOLS FOR WillCil b FUNClIDNAL SilHVElliANCE IS 33 CilANilE1 CllAliflEL .

IN51Rilllf NI Clll CK CApllRA110N TEST ,

kl(lulRID

]

1. AREA HONilui:S

^

a. luel Storage Pool Area S R H H 1, 2, 3 & 4 12 . Containn.unt Area S 1:

2. PI(0CLSS ikilll10HS

a. Contaisonent Purge Air l xlianst S R M I, 2, 3, 4 & 6 l

12 Conta i nneent j

i. tiaseous Activity H All. Il0llLS '

a) Ventilation isolation S R H I, 2, 3, & 4 l>)l:CS leakage Detection S R ii. Part.iculate Activity

" R- M ALL th)DLS a) Ventilation isolation S H 1, 2, 3 & 4

't' l>)RCS teakage Detection S R .

h All 110 DES i Control Room isolation S R H c.

cl. Holsle t;as Effluent Monitors .

l l

1. Shield Building Exhaust S R ,

M 1, 2, 3, & 4 (Iligh Range)

11. Condenser Exhaust S R M 1, 2. 3, & 4 (Iligh Range)

~*Willa f uel in t he st orage pool or tsuiltfisi!;.

l I *

=_. -. . _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ - - __

i 1ABLE 3.3-10 -

EI .

{3 ACCIDENT MONITORING INSTRUMENTATION S?

zo -

x .

c- MINIMUM INSTRUMENT REQUIRED NO. CHANNELS gj OF CHANNELS OPERABLE-

^) 1.

Reactor Coolant Tifot (Wide Range) 2 1 -

2. Reactor Coolant TCold ( ide Range) 1 2 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 M

e 7. Steam Line Pressure 2/ steam line i' 1/ steam line u; 8. Steam Generator Level - (Wide Range) 1/ steam generator 1/ steam generator

9. Steam Generator Level - (Harrow Range) -

1/ steam generator 1/ steam generator

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

11. Reactor Coolant System 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 Instrurentation System *** 4/ core quadrant 2/ core quadrant 2

1

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

i **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 Laplemented until Sequoyah Specific Instructions are developed , ,

for the use of this system as committed to in our response to Supple-

j. ment 1 of NUREG 0737.

PL 5 ,

8

.< TAP.LE 4.3-7 .

a

. ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS -

E G CHANNEL CHANNEL y INSTRUMENT CllECK CAllBRATION

1. Reactor Coolant THot (Wide Range) M R ,

2. Reactor Coolant TCold (Wide Range) M R

3. Containment Pressure (Wide Range) M R

4. Refueling Water Storage Tank Level M R

5. Reactor Coolant Pressure (Wide Range) M R l

u, 6. Pressurizer Level M R 2

u, 7. Steam Line Pressure M R (n

o' 8. Steam Generator Level - (Wide) M R

9. Steam Generator Level - (Narrow) M R

10. Auxiliary Feedwater Flowrate M .R 1

11. Reactor Coolant System Subcooling M R

Margin Monitor

12. Pressurizer PORV Position Indicator M R

13. Pressurizer PORV Block Valve M R Position Indicator

14. Safety Valve Position Indicator M R

15. Containment Water Level (Wide Range) M R

16. In Core Thermocouples M R

17. Reactor Vessel Level Instrumentation system

M R

Note: This technical specification and surveillance requirement will not be bnplemented until Sequoyah Specific Instructions are developed *-

for the use of this system as committed to in our response to Supplement 1 of NUREG 0737. ,

l !

f f e o 3 21 2441 1 l 01 I 44 4 44 44444 C

A Y

l I

l i

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TABLE 3.3-13 (Continued)

TABLE NOTATION

At all times. ,

- During waste gas disposal system operation. k

- - During shield building exhaust system operation.

ACTION 40 - With the number of channels OPERABLE less than required by the tiinimum 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 independently verify the relea,se rate calculations and discharge valve lineup; Otherwise, suspend release 'o'f radioactive effluents via this pathway.

ACTION 41 - With the number of channels OPERABLE less than required by the 111nimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow l rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 42 - With the number of channels OPERABLE less than required by the Itinimum Channels OPERABLE requirement, effluent releases via 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 .

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 for up to 7 days provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . With the hydrogen and oxygen ironitors ir. operable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 collected with auxiliary sampling equipment as required in Table 4.11-2.

SEQUOYAH - UNIT 2 3/4 3-79 t

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REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS -

LIMITING CONDITION FOR OPERATION -

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~6 hours.

b. With no RCSV path OPERABLE, restore at le'ast one path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

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

b. Operating each remotely controlled valve through at least one cycle from the control room, and

c. Verifying flow through the RCSV paths during venting.

- *Use of Power Operated Relief Valves (PORV's) with associated blocked valves is considered one system. Closure of one or both block vales does not make the vent path inoperable provided the valve (s) can be opened.

Note: This technical specification and surveillance requirement will not be inplemented 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 - bMIT 2 3/4 4-39 r

REACTOR COOLANT SYSTEM BASES 3/4.4.11 REACTOR COOLANT SYSTEM VENTS The function of the RCS vents is to remove noncondensable or steam from the reactor vessel head and/or pressurizer. This system is designed to mitigate a possible condition of inadequate core cooling, inadequate natural circulation, or inability to depressurize the RHR System initiated conditions resulting from the accumulation of noncondensable gases in the Reactor Coolant System.

The reactor vessel head vent and the pressurizer vent are each designed with redundant safety grade vent paths. Having either system OPERABLE or having one path in each system from opposite trains OPERA 8LE is sufficient to meet the provisions of Specification 3.4.11.

~,

SEQUOYAII - UNIT 2 8 3/4 4-16 b

ELECTRICAL POWER SYSTEMS SURVEILLANCE RE0UIREMENTS (Continued) -

~

4. Simulating a loss of offsite power by itself, and:

a) Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.

b) Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady state voltage and frequency of the shutdown boards shall be maintained at 6900 690 velts and 60 1.2 Hz during this test. -

5. Verifying that on a ESF actuation test signal (without loss of offsite power) the diesel. generator starts on the auto-start '

signal ano operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 6900 1 690 volts and 60 i 1.2 Hz within 10 seconds after the auto-start signal; the steady state generator voltage and fre-quency shall be maintained within these limits during this test.

6. Simulating a loss of offsite power in conjunction with an ESF l actuation test signal, and a) Verifying de-energization of the shutdown boards and load shedding from the shutdown boards, b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the shutdown boards with permanently connected loads withir. 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loa. fed with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 6900 1 690 volts and 60 1.2 Hz during this test.

c) Verifying that all automatic diesel generator trips, except engine overspeed and generator differential, are automatically bypassed upon loss of voltage on the shutdown board and/or safety injection actuation signal.

7. Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to greater than or equal to 4400 kw and during the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded to greater than or equal to 4000 kw.

SEQUOYAH - UNIT 1 3/4 8-4 h .

ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

Within 5 minutes after completing this 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test, perform Specification 4.8.1.1.2.c.4. The generator voltage and fre-quency shall be 6900 690 volts and 60- 1.2 Hz within 10 seconds after the start signal; the steady state generator voltage and frequency shall be maintained within these limits during this test.

8.

Verifying that the auto connected loads to each diesel generator do not exceed the 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating of 4000 kw.

9.

Verifying the diesel generator's capability to:

a)

Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power.

b) Transfer its loads to the offtite power source, and c) Be restored to its snutdown status.

1 10.

Verifying that the automatic load sequence timers are OPERABLE with the setpoint its design for each sequence timer within : 5 percent of setpoint.

11.

Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) Engine overspeed b) 86 GA lockout relay e.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the dieseltogenerators equal 10 seconds.accelerate to at least 900 rpm in less than or f.

At least orfce per 10 years

by:

1.

Draining each fuel oil storage tank, removing the accumulatea

.secliment solution, andand cleaning the tank using a sodium hypoclorite 2.

Performing a pressure test of those portions of the diesel fuel oil system design to Section III, subsection ND of tne ASME Code at a test precsure equal to 110 percent of the system design pressure.

Mhese requirernents are waived for the initial surveillance.

SEQUOYAH - UNIT 1 3/4 8-5 r v:- _

5055Y*& - * "W

ENCLOSURE 2 JUSTIFICATION FOR THE PROPOSED TECHNICAL SPECIFICATION CH',NGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 The proposed technical specification changes are submitted to comply with the NUREG-0737 requirements and as a result of modifications to comply with operating license conditions. As noted in the November 1, 1983 letter (Generic Letter 83-27) from D. G. Eisenhut to "All Pressurized Water Reactor Licensees," the limiting conditions for operation (LCO) involved in the d1anges are consistent with the NRC Standard Review Plans (SRPs) and are similar to those recommended in Generic Letter 83-37. The proposed technical specification changes for the diesel generator, delete surveillance requirement (S/R) 4.8.1.1.2.d.6, -is being submitted as raquested by NRC in the July 25, 1983 letter (Generic Letter 83-30) from D. G. Eisenhut. As stated in Generic Letter 83-30, the requirements of S/R 4.8.1.1.2.d.6 were not consistent with General Design Criteria (GDC) No.

17, Regulatory Guide 1.108, or the NRC SRPs. The significant hazards consideration determination (SHCD) for the NUREG-0737 technical specifica-tions is provided in attachment 1. The SHCD for the diesel generator technical specification is provided in attachment 2. The SHCD revealed that no significant hazards considerations are involved.

L - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ . - _ _ _.

.' ATTACEMENT '

I SIGNIFICANT HAZARDS CONSIDERATIONS

1. Is the probability of at; occurrence or the consequences of an accident -

or malfunction of equipment important to safety previously evaluated in ..

- ~

the safety analysis report increased?

'i No. The consequences of an accident or malfunction may actually be reduced because of the installation of additional mitigation and diagnostic equipment. The probability of an occurrence has not been increased because the reactor coolant pressure boundary penetrations made for reactor coolant vent ar.d level systems were made in accordance with codes, standards, and quality assurance requirements consistent with the design and fabrication cf the rest of reactor coolant pressure boundary. Installation of the high-range radiation monitors does not increase the probability for accidents or malfunctions because they only connect to the release paths.

2. Is the possibility for an accident or maSfunction of a different type than evaluated previously in the safety analysis report created?

No. The installation of the reactor coolant pressure boundary penetrations will not create the possibility for an accident or malfunction of a different type than previously analyzed. The penetrations were made in accordance with codes, standards, and quality assurance requirements consistent with the design and fabrication of the rest of the reactor coolant pr. essure boundary. Installation of the high-range radiation monitors does not create the possibility for an accident or malfunction of a different type than p,r'riously analyzed.

The monitors only connest to the release paths.

3 Is the margin of safety an defined in the basis of any technical specification reduced?

No. The margin of safety provided by the technical specifications is actually increased because additional mitigation and diagnostic equipment is required to be operable, and out-of-service times for this equipment are limited by the action statements.

l

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ATTACHMENT 2 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION -g' The provisions of GDC 17, Regulatory Guide 1.108, and NRC Standard Review Plans 8.2, 8.3 1 ensure that the public safety and health will be P protected. The deletion of SR 14.8.1.1.2.d.6 is consistent uith these guides and Generic Letter 83-30. No new or previously analyzed accident or malfunction possibility is created or increased by deletion of this surveillance requirement. The margin of safety is not reduced.

e E g E d 8

d' '

F g

t e.

.., SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The provisions of GDC 17, Regulatory Guide 1.108, and NRC Standard Review 5

Plans 8.2, 8 3 1 ensure that the public safety and health will be protected. The deletion of SR 14.8.1.1.2.d.6 is consistent with ohese guides and Generic Letter 83-30. No new or previously analyzed accident or malfunction possibility is created or increased by deletion of this surveillance requirement. The margin of safety is not reduced.

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(

'. 1 SIGNIFICANT HAZAFDS CONSIDERATIONS

1. Is the probability of an occurrence or the consequences of an accident ~

or malfunction of equipment,important to safety previously evaluated in the safety analysis report increased? ,

s No. The consequences of an accident or malfunction may actually be reduced because of the installation of additional mitigation and diagnostic equipment. The probability of an occurrence has not been increased because the reactor coolant pressure boundary penetrations made for reactor coolant vent and level systems were made in accordance with codes, standards, and quality assurance requirements consistent with'the design and fabrication of the rest of reactor coolant pressure boundary. Installation of the high-range radiatien monitors does not increase the probability for accidents or malfunctions because they only connect to the release paths.

2. Is the possibility for an accident or makrunction of a different type than evaluated previously in the safety analysis report created?

No. The installation of the reactor coolant pressure boundary penetrations will not create the possibility for an accident or malfunction of a different type than previously analyzed. The penetrations were made in accordance with codes, standards, and quality assurance requirements consistent with the desian and fabrication of the rest of the reactor coolant pressure boundary. Installation of the high-range radiation monitors does not create the possibility for an accident or malfunction of a different type than previously analyzed.

The monitors only co.inect to the release paths.

3 Is the margin of safety as defined in the basis of any technical specification reduced?

No. The margin of safety provided by the technical specifications is ,

actually increased because additional mitigation and diagnostic equipment is required to be operable, and out-of-service times for this equipment are limited by the action statements.

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