Text

Proposed Tech Spec Change 87-39,correcting Minor Discrepancies Identified During Tech Spec Reviews
	ML20234D243
Person / Time
Site:	Sequoyah
Issue date:	09/14/1987
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20234D241	List: ML20234D239; ML20234D243;
References
	TAC-R00207, TAC-R00208, TAC-R207, TAC-R208, NUDOCS 8709220021
	Download: ML20234D243 (15)
	v • d • e

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ENCLOSURE 1

. PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2

)

DOCKET NOS. 50-327'AND 50-328 1

(TVA-SQN-TS-87-39) l

)

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LIST OF AFFECTED PAGES Unit 1 3/4 3-62 3/4 3-66 3/4 3-67 3/4 8-3 3/4 8-5 i

l 3/4 11-13 i

Unit 2 j

r 3/4 3-7 3/4 8-3 3/4 11-12 l

l 1

i i

l f

D P

1 1

TABLE 3.3-11 (Continued) 1 FIRE DETECTION INSTRUMENTS Fire Minimum Instruments Ot>erable Zone Instrument Location Ionization Photoelectric Thermal Infrared l

220 Main CR E1. 732 25 221 Red. Stor. Vault El. 732 2

i 222 Rcd. Stor. Vault El. 732 2

223 PS0 Engr. Shop E1. 732 1

224 PS0 Engr. Shop El. 732 1

225 Relay Bd. Rm. El. 732 13 226 Electric Cont. Bds. El. 732 11 l

227 Oper. Living Area E1. 732 7

228 Oper. Living Area El. 732 8

l 229 Main Cont. Bds.

9 298 Common Main CR Bds. EL 732 9

230 Aux. CR Bds. L-4A, 4C, 11A & 10 l

El. 732 9

296 Aux. CR Bds. L-48, 40, & 11B El. 732 6

114 Waste Packaging Area E1. 706 3

l 115 Waste Packaging Area E1. 706 3

I 116 Cask Loading Area E1. 706 2

l 117 Cask Loading Area E1. 706 2

118 New Fuel Storage Area El. 706 2

119 New Fuel Storage Area Ei, 706 2

nd 120 Aux. Bldg. Gas Trtmt. F1tr. El. g 1

121 Aux. Bldg. Gas Trtmt. Fitt. E1. fe&-

1 1

124 Additional Ecuip. Bldg. E1. 706 6

i 132 Ventilation & Purge Air Rm. El. 714 3

~

133 Ventilation & Purge Air Rm. El. 714 3

134 Aux. Bldg. AS-All, Col. U-W, E1. 714 7

1 O

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SEQUOYAH - UNIT 1 3/4 3-62 l

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TABLE 3.3-11 (Continued) i FIRE DETECTION INSTRUMENTS-Fire Minimum Instruments Operable I

Zone Instrument Location Ionization Photoelectric Thermal-Infrared

.267 Aux. Instr. Rm. E1. 685 8

268 Aux. Instr. Rm. El. 685 9.

269 Computer Rm. El. 685 4

270 Computer Rm. E1. 685 4

276 Intk. Pu ping Sta. El. 690 & 670.5 15

--> A22 ERLW '

Jia,

4/, 709 354. Upr. Compt Coolers, El. 778

/

4 352 Lwr.. Compt. Coolers, El. 693 4

356 RCP 2, El. 693 2*

lR41 357 RCP 2, El. 693 2

360 RCP 1, El. 693 2*

l' 361 RCP 1, El. 693 2

364 RCP 3, El. 693 2*

l41 365 RCP 3, El. 693 2

368 RCP 4, E1. 693 2*

]R41 369 RCP 4, El. 693 2

372 Reactor Bldg. Annulus 18

' i'...

373 Reactor Bldg. Annulus 18 1 Diesel Gen. Rm. 28-B, E1. 722 5

2 Diesel Gen. Rm. 28-B, El. 722 5

3 Diesel Gen. Rm. 18-B, El. 722 5

4 Diesel Gen. Rm. 18-B, El. 722 5

5 Diesel Gen. Rm. 2A-A, El. 722 5

6 Diesel Gen. Rm. 2A-A, El. 722 5

7 Diesel Gen. Rm. IA-A, El. 722 5

8 Diesel Gen. Rm. 1A-A, El. 722 5

~

387 Lh.,e Co.,1.'

/3/f it's//, S/. M fg "This change is effective upon completion of the associated modification.

R41 O 8 O A# E w

SEQUOYAH - UNIT 1 3/4 3-66 fnut:I-I b Si I

___.__.___.m_

__:__m..

_.._____..__m-_______.___.._.____.__._-.m____

____.___1___a

. e.,:,

.v TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS

' ~ ~

Minimum Instruments Ooerable Fire Zone Instrument Location Ionization Photoelectric Thermal Infrared 9 Lube Oil Storage Rm. El. 722 1

10 Lube Oil Storage Rm. El. 722 1-11 Fuel Oil Transfer Rm. El. 722 1

12 Fuel Oil Transfer Rm. El. 722 1

13 Diesel Gen. Corridor, El. 722 6

14 Air Intake & Exhaust Rm. 2B, E1. 740.5 '

9 15 Air Intake & Exhaust Rm.1B, E1. 740.5 9

16 Air Intake & Exhaust Rm. 2A, El. 740.5 9

Air Intake & Exhaust Rm. k, E1. 740.5 17 9

18 Diesel Gen. 2B-B Relay Bd. El. 722 3

)

th 19 Diesel Gen.1B-B Relay Bd. E1. 722 3

j

~~

20 Diesel Gen. 2A-A Relay Bd. El. 722 3

21 Diesel Gen. lA-A Relay Bd. E1. 722 3

22 Diesel Gen. Board Rm. 2B-B, El. -722 7'/0,i 2

23 Diesel Gen. Board Rm. 2B-B, E1. 222-7mS 2

24 Diesel Gen. Board Rm.1B-B, E1. 422 7Yo,f 2

25 Diesel Gen. Board Rm.1B-B, El. 743-7vo,I 2

26 Diesel Gen. Board Rm. 2A-A, El. 7ee 7YoS 2 27 Diesel Gen. Board Rm. 2A-A, El. 7et 7Yo f 2 ~

~

2B Diesel Gen. Board Rm. l A-A, El. -7tr 740I 2 29 Diesel Gen. Board Rm. l A-A, El. 7Ee 7Yo#

2 30 Cable Spreading Rm. C7-C11, El. 706

-14 31 Cable Spreading Rs. C7-C11, El. 706 14 32 Caole Spreading Rm. C7-C11, E1. 706 14 33 Caole Screading Rm. C7-C11, El. 706 14 34 Cable Spreading Rm. C3-C7, E1. 706 14 35 Cable Spreading Rm. C3-C7, El. 706 14 b

i SEQUOYAH - UNIT 1 3/4 3-67

1

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ELECTRICAL POWER SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) 1 4, 5 Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in.less than or equal to 10 seconds. The generator voltage and fr.quency shall be

-6900 690 volts and 60 1 1.2 Hz within 10 seconds after the.

lR56:

start signal.

The diesel generator shall be started for this i

test by using one of.the following signals with startup on each signal verified at least once per 124 days:

a)

Manual, b)

Simulated loss of offsite power by itself.

c)

An ESF actuation test signal by itself.

RS6

5. # erifying the generator is synchronized, loaded to greater than V

or equal to 4000 kw'in less than or equal to 60 seconds \\, and lR56 operates for greater than or equal to 60 minutes, and 6.

Verifying the diesel generator is aligned to provide standby-power to the associated shutdown boards.

b.

At least once per 31 days and after eaih operation of the diesel where the period of operation was greater than or equal to 1 hour-by checking for and removing accumulated water from the engine-mounted fuel tanks.

At least once per 92 days and from new. fuel oil prior to addition c.

n%

to the 7-day tanks by verifying that a sample obtained in accordance

,l with ASTM-D270-1975 has a water and sediment content of less than or C'

equal to.05 volume percent and a kinematic viscosity @ 100*F of greater than or equal to 1.8 but less than or equal to 5.8 centi-stokes when tested in accordance with ASTM-0975-77,'and an impurity level of less than 2 mg. of insolubles per 100 ml. when tested in accordance with ASTM-D2274-70.

d.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in.accordance with procedures prepared in conjunction with its manufacturer.'s.

recommendations for this class of standby service, 2.

Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage at 6900 2 690 volts and frequency at 60 + 1.2 Hz.

3.

Verifying the generator capability to reject a load of 4000 kw without tripping. The generator voltage shall not exceed 7866 volts during and following the load rejection.

"The ciese). generator start (10 sec) and load (60 sec) from standby conditions shall be performed at least once per 184 days in these surveillance tests.

All RS6 t

other ciesel generator engine starts and loading for the purpose of this sur-veillance testing may be preceded by an engine idle start,' followed by gracual l

acceleration to synchronous speed (900 rpm), ~ synchronization, and gracual loading.

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SEQUOYAH - UNIT 1 3/4 8-3 fr.n::=t t. M m

ELECTRICAL POWER SYSTEMS

,/- D. /. /, 2 d.

M'[,,,I/AD2Y/pS~

SURVEILLANCE REQUIREMENTS (Continued)

/

Within 5 minutes after/completino this 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test. DeM edification G.8 L 1.2 d.43f The generator voltage and fre-lR56 quency shall be 6900 : 690 volts and 60 2 1.2 Hz within 10 seconds after the start signal;'the steady state. generator voltage and frequency shall.be maintained within these limits duringthistest.g 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 genera-tor is loaded with its emergency loads upon a simulated restoration of offsite power.

b)

Transfer its loads to the offsite power source, and c)

Be restored to its shutdown status.

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:

l a)

Engine overspeed b) 86 GA lockout relay At least once r:er 10 years or after any modifications which could e.

affect diesel generator interdependence by starting the diesel generators si wltaneously, during shutdown, and verifying that the diesel generators accelerate to at least 900 rpm in less than, or equal to 10 seconds.

f.

At least once per 10 years

by:

1.

Draining each fuel oil storage tank, removing the accumulated I

sediment and cleaning the tank using a sodium hypoclorite l

solution, and 2.

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

"These requirements are waived for the initial surveillance.

/

I C E. -.. j 2, 1727 SEQUOYAH - UNIT 1 3/4 8-5 t.u. e c t t.

.____--.-._-._____________.m.-.

TABLE 4.11-2 (Continued)

'e,'

TABLE NOTATION i

b.

Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of rated thermal l

power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the dose equiva-R46 l

lent I-131 concentration in the primary coolant has not increased j

more than a factor of 3 and (2) the noble gas activity monitor shows that the effluent activity has not increased by more than a factor j

of 3.

i c.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refuelir.g canal is flooded.

l d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

for at least 2 days following each shutdown from 215% RATED THERMAL l

POWER, startup of 215% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall l

be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected l

for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

l e.

Tritium grab samples shall be taken at least once per 7 days from

.]

the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1', 3.11.2.2 and 3.11.2.3.

i 1

I g.

The principal gamma emitters for which the LLD specification applies j

exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, a

Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59, I-131, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for -

particulate principal gamma emitters.

This list does not mean that R46]

only these nuclides are to be detected and reported.

Other gamma j

peaks which are measureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semi-annual Radioactive Effluent Release Report pursuant to Specification 0.0.1.12.

l G. 9. I, 9.

h.

During releases via this exhaust system.

)

1.

Purging - Applicable in MODES 1, 2, 3 and 4, the upper and lower com-

~

partments of the containment shall be sampled prior to PURGING.

Prior R'

to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled.

The incore instru-ment room purge sample shall be obtained at the shield building exhaust i

between 20 and 25 minutes following initiation of the incore instrument I

room purge.

= =; , m SEQUOYAH - UNIT 1 3/4 11-13

.t r,dra r,t ". '

pt j

l t

TABLE 3.3-1 (Continued)

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, declare i

the interlock inoperable and verify that all affected channels of the functions listed below are OPERABLE or apply the appro-priate ACTION statement (s) for those functions.

Functions to.

be evaluated are:

Source Range Reactor Trip.

a.

b.

Reactor Trip Low Reactor Coolant Loop Flow (2 loops)

Undervoltage Underfrequency

~

Turbiac Trip-Pressurizer Low Pressure Pressurizer High Level c.

Reactor Trip Low Reactor Coolant Loop Flow (1 loop) 1 d.

Reactor Trip Intermediate Range Low Power Range Source Range

,a 5

20:G ACTION 9 - Deleted M'

g, g J, X,p Ay,,/ i., TVA -J Q W-ACTION 10 - Deieted 7,,,, y,y 7.r-a?- n

% S/

ACTION 11 - Deleted 6/IV/' 7 ACTION 12 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT-STANDBY'within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for R4.

up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.l.1

- 'provided the other channel is OPERABLE.

.}

nor;+ is, lo c'-

SEQUOYAH - UNIT 2 3/4 3-7

^

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4 ELECTRICAL POWER SYSTEMS

'i

~~~

SURVEILLANCE REQUIREMENTS (Continued)

4. E erifying the diesel starts from ambient condition and l

V accelerates to at least 900 rpm in less than or equal to 10 seconds.

The generator' voltage and frequency shall be.

6900 2 690 volts and.60 t 1.2 Hz within 10h seconds after the lR44 start signal. The diesel generator shall be started for this test by using one of the following signals with startup on each signal verified at least once per 124 days:

a)

Manual.

b)

Simulated loss of offsite power by itself.

1 c)

An ESF actuation test signal by itself.

5.

Verifying the generator is synchronized, loaded to greater than or equal to 4000 kw in less than or equal to 60 seconds \\, and lR44 1

operates for greater than or equal to 60 minutes, and 6.

Verifying the diesel generator is aligned to provide standby power to the associated shutdown boards.

b.

At least once per 31 days and af ter each operation of the diesel where the period of operation was greater than or equal to 1 bour by checking for and removing accumulated water from the engine-mounted fuel tanks.

At least once per'92 days and from new fuel oil prior to addition c.

to the 7-day tanks by verifying that a sample obtained in accordance with ASTM-D270-1975 has a water and sediment content of less than or 7.]

equal to.05 volume percent and a kinematic viscosity @ 100 F of C

greater than or equal to 1.8 but less than or equal to 5.8 centi-stokes when tested in accordance with ASTM-D975-77, and an impurity level of less than 2 mg. of insolubles per 100 ml. when tested in accordance with ASTM-D2274-70.

d.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's i

recommendations for this class of standby service, 2.

Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage at 6900 1 690 volts and frequency at 60 + 1.2 Hz.

3.

Verifying the generator capability to reject a load of 4000 kw without tripping. The generator voltage shall not exceed 7866 volts curing and following the lead rejection.

"The ciesel generator start (10 sec) and load (60 sec) from standby' conditions shall be performed at least once per 184 days in these surveillance tests.

All other diesel generator engine starts and loading for the purpose of this sur-R44 veillance testing may be prececed by an engine idle start, followed by gracual acceleration to synchronous speed (900 rpm), synchronization, and. gradual loading.

+,

SEQUOYAH - UNIT 2 3/4 8-3

$$5 b.

o TABLE 4.11-2 (Continued)

TABLE' NOTATION-Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when c.

the refueling canal is flooded.

d.

Samples shall be changed at least once per 7 days and analyses sh611 be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal' from sampler).

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least'2 days following each shutdown from >15% RATED THERMAL POWER, startup to >15% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

Tritium grab samples shall be taken at least once per 7 days from e.

the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

.f..

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

The principal gamma emitters for which the. LLD specification applies b

g.

exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133,.

Xe-133m, Xe-135, and Xe-138 for noble gases.and Mn-54, Fe-59, I-131, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144'for particulate principal gamma emmitters.

This list does not mean that only these nuclides are to be detected and reported.

Other gamma R34 peaks which are measureable and identifiable, together with the. above nuclides, shall also be analyzed and reported in the Semiannual Radio-active Effluent Release Report pursuant to Specification G.S.I.12.

b 9. I, 9.

h.

During releases via this exhaust system.

i.

Purging - Applicable in MODES 1, 2, 3, and 4, the upper and lower l

^

compartments of the containment shall be sampled prior'to PURGING.

Prior to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled.

R34 The-incore instrument room purge s ample shall be obtained at the shield building exhaust between 20 arid 25 minutes following initiation of the incore instrument room purge.

j.

Venting - Applicable in MODES 1, 2, 3, and 4, the containment shall be vented to the containment annulus and then to the auxiliary build-ing via containment annulus fans.

The lower containment compartment shall be sampled daily when venting is to occur to account for the radioactivity being discharged from the venting process.

...= q ,

m SEQUOYAH - UNIT 2 3/4 11-12

^ =trt " "

lR34 k

1 ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-39)

DESCRIPTION AND JUSTIFICATION FOR CORRECTION OF MINOR DISCREPANCIES I

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c.

ENCLOSURE 2

Description of Change Changes That Affect' Unit 1 and Unit 2 Item Page Description 1.

3/4 8-3 Move asterisk to clarify intent and scope of page note.

2.

3/4 11-13 (U1)

Correctly identify i

3/4 11-12 (U2)

' radiological reporting requirements of specification 4.11.2.1.2.

3 il Changes That Affect Unit 1 Only

~3.

3/4 3 Correct elevations of fire zones.

4.

3/4 3-66 Add fire zones inadvertently omitted from table 3.3-11.

5.

3/4 3-67 Correct' elevations and notations of fire zones.

6.

3/4 8-5 Correct an inconsistency.

between surveillance requirement 4.8.1.1.2.d.7,

'and'the corresponding-specification inLthe unit 2 technical specifications j

-(TSs).

~

Changes That Affect Unit 2 Only 7.

3/4 3-7 Correct inconsistency i

between table 3.3-1, action-J 8b, and the corresponding action in the unit 1 TSs.

I i

l

., Reason for Change Change number one clarifles the intent and scope of the page not concerning diesel generator set cold-fast starts.

The change will reduce the chance of misunderstanding the scope of the note which could result in unnecessary cold-fast starts.

Change number two corrects the administrative section radiological reporting requirements referenced in surveillance requirements 4.11.2.1.2.

The change corrects the references to semiannual reports as described in section six of' the TSs. The proper reporting requirements have been followed to date.

Change numbers three and five correct the elevations and the location description for several fire zones of table 3.3-11.

The change will correctly identify the zones and make the descriptions and locations consistent with the corresponding zones as listed in the unit 2 TSs.

Change number four adds two common area fire zones to. table 3.3-11.

The change'will reflect that the fire zones are applicable to unit 1' operation and will make the common area zones listed consistent with the corresponding unit 2 specification.

Change number six corrects an inconsistency between the wording in the unit i specification and the corresponding specification in the unit 2 TSs.

The change makes the wording consistent with the unit 2 TSs and NRC Stancard Technical Specifications (STSs).

l I

Change number seven corrects an inconsistency between table 3.3-1, action 8b, and the corresponding action in the unit l'TSs.

The deletion of the turbine trip function is made because the P-7 and P-13 interlocks do not affect the turbine trip function.

The change will make the action consistent with plant design and the corresponding unit 1 action.

Justification for Change The proposed changes correct inconsistencies between the TSs for one unit and-the other, correct discrepancies between the TSs and the design of the plant, correct inconsistencies between requirements in the TSs, and provide clarification for the intent of various specifications.

Correction of these discrepancies will eliminate confusion over applicable requirements and eliminate the potential for error.

+

'er 4; gy' ENCLOSURE 3 PROPOSED' TECHNICAL-SPECIFICATION CHANGES

^

SEQUOYAH NUCLEAR PLANT' UNITS l'AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-39)

DETERMINATION OF N0 SIGNIFICANT HAZARDS CONSIDERATIONS i

I 1

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___________.____._._____-___________am___.__-__-__._m____._

l ENCLOSURE 3 Significant Hazards Evaluation TVA has evaluated the proposed TS change and determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the i

proposed amendment will not:

1.

Involve a significant increase in the probability or consequences of an accident previously evaluated.

These changes are to correct minor j

inconsistencies between requirements and discrepancies between plant design and requirements.

Correcting these problems will eliminate confusion over applicable requirements and eliminate the potential for error.

Eliminating the potential for error will reduce the probability of an occurrence.

[

2.

Create the possibility of a new or different kind of accident from any j

accident previously evaluated.

These changes are to correct minor inconsistencies between requirements and discrepancies between plant design and requirements.

No hardware changes were made to the plant.

Correcting the inconsistencies between certain action statements and other requirements in the TSs will eliminate confusion over applicable requirements and eliminate the potential for error.

In this case, the I

error would be to operate in a plant configuration not previously analyzed.

Correcting these inconsistencies should eliminate the l

l potential for this type of error.

l l

3.

Involve a significant reduction in a margin of safety.

These changes are to correct minor inconsistencies between requirements and discrepancies between plant design and requirements.

Correcting these problems will eliminate confusion over applicable requirements and eliminate the potential for error.

The margin of safety will be increased with the elimination of the potential for error.

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ML20234D243

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