ML20248K385

Amends 109 & 99 to Licenses DPR-77 & DPR-79,respectively, Correcting Action Statement of Table 3.3-1, Reactor Trip Sys Instrumentation for Unit 2 Only & Instrumentation Listed in Table 3.3-11, Fire Detection Instruments

ML20248K385
Person / Time
Site:	Sequoyah
Issue date:	04/03/1989
From:	Black S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248K389	List: ML20248K385 ML20248K391
References
NUDOCS 8904170319
Download: ML20248K385 (20)

Text

__

l

+*sf "* %,C, UNITED STATES

'E,.

i NUCLEAR REGULATORY COMMISSION l

3e s

l wasmNoroN. o. c. rosss s

.a 1

/

l i

l' l

i l

i l

I TENNESSEE VAL.L.E.Y AU.T.H.O_RI.T..Y.

DOCKET NO. 50-327' 1

i l

SEQUOYAH NU,C,L, EAR PLANT, U,N E 1 i

AMENDMENT TO FACILITY OPERATING LICENSE I

i 1

Amendment No.109 i

License No. DPR-77 l

1.

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

)

A.

The application for amendment by Tennessee Valley Authority (the i

licensee).datedSeptember 14, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Ccmmission's rules and regulations set forth in 10 CFR Chapter I; P.

The facility will operate in ccrformity with the application, the provisions of the Act, and the rules and regulations of the Cormissicn; C.

There is reasonable assurance (1) that the activities authori:ed by this aner'dtrent can be conducted without endangering the health and i

safcty cf the public, and (ii) that such activities will be ccnducted in compliar.ce with the Comission's regulations; i

l C.

The issuance of this amendment will net be inimical to the comen I

l defense and security or to the health and safety of the public; and E.

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

l l

8904170319 990403 PDR ADOCK 05000327

-P PDC

.i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-77 is hereby I

amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.109, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION m m tA.-

C

/

Suzanne ack, Assistant Director j

for Projects l

TVA Projects Division i

Office of Nuclear Reactor Regulation

Attachment:

1 Changes to the Technical i

Specifications Cate of Issuance: April 3, 1989 l

l a

I l

l l

l

.. d 1

I l

t 1

A

l r

ATTACHMENT TO LICENSE AMENDMENT N0,.,,1p9 FACILITY OPERATING LICENSE N0. DPR-77 COCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified belcw and inserting the. enclosed pages.

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

Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-63 3/4 3-63 3/4 3-68 3/4 3-68 3/4 3-68a 3/4 3-68a 3/4 8-3 3/4 8-3 3/4 8-5 3/4 8-5 3/4 8-6 3/4 8-6*

3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14*

1 I

l

~

de rar fn I

e l

blaa rm er 55555555111169 9

9 9

2 pe Oh T

s tnc eimr S

ut T

rc N

t e E

sl M

ne U

I o R

t 1

T mo 1

S uh N

mP 3

I in 3

N i n O

Mo E

I i

L T

t B

C a

3 3

3 3

2 A

E z

T T

i E

n D

o I

E R

I F

22222222 222 2222222222222 7777777722777B B

A A

77 2

I 2

l B

B d

d.

d d

l l l l l ! l l

.. l l l m

m.

B B

B B

8 8

EEE m EEEEEEEEl n

2 2

l EE

,R R

R R

y y

y y

a a

a a

BBBBAAAA.. mmrt t

t t

l l

l l

m n

- - - - - - - - mmRR os s

s s

e e

e e

R R

o 8888AAAARR d u u

u u

R R

R R

i 221122lI rria a

a a

d d

t eseerh h

h h

B B

A A

r a

ggff rx x

x x

a c

smmmmmmmaassoE E

E E

8 B

A A

o o

RRRRRRRR rrnnC 2

1 2

1 B

B L

ooaa.&5&5&5&5.

5 tt rr t

nnnnnnnnSSTT ne0 e0. e0 e0 n2n2 n2 n2n0 n0 n

eeeeeeee ek4k4k4k4 e2 e2 e2 e2 e4 e4 e4 e4 e

GGGGGGGGl l l l Ga7 a7 a7 a7G7G7G7G7G7G7G7G7 m

i iii t

t t

t u

l l l l l l l l OOOOl n. n. n n

.l

. l

.l

.l

.i

.l r

eeeeeeee eI l I 1 Il Il el el el el el el el el t

sssssssseel i s E

E E

EsE sE sE sE sEsE sE sE s

eeeeeeeebb eeer r

r r

e e

e e

e n

iiiiiiii uuuuii i

i i

i i

i i

i i

I DDDDDDDDLLFFDA A

A A

D D

D D

D D

ee rn i o 12345678901234 5

6 7

8 9

0 1

2 3

FZ 11111 1

1 1

1 1

2 2

2 2

S3.

E C5- "

t' s

• 5d '

• Y8 7 @ (( @

• F j

2 r

E-t-

~

derar fn I

e l

blaa rm er 2

2 pe Oh T

s tnc eimr S

ut

)

T rc

'd N

t e e

E sl u

M ne n

U I o i

R t

t T

mo n

S uh o

N mP C

I i

(

n N

n i

O Mo 1

1 I

i T

t 4

4 4

4 4

4 2

2 2204 4

2 3

C a

2 2

1 1

1 1

1 1

1 E

z 3

T i

E n

E D

o L

I B

E A

R T

I F

3 5

A A

A A

1 1

1 1

6 1

1 1

1 7

7 A

A A

A C

C C

C C

C 1

2 2

l I

1 C

7 7

7 7

3 3

33E g g

C C

C C

C C

A B

55 d

d m.

m m.

m 66

,l l

l n

R R

R R

A B

rB B

o m.

m.

m m.

m.

m 1 - 1

.. o C

d d

d d

R R

R R

R R

l 1 dl l

i t

r r

r r

p p

EEi o o

a a

a a

a g

g g

g g

g m

m rr r

m c

o o

o o

n n

n n

n n

u u

rt t

R o

B B

B B

i i

i i

i i

P P

ABon n

5...... a a

a a

a a

y y A8 C

C p

5 5

5d d

d d

d d

- - C o o

L t

n0 n0 n0 n0 e e

e e

e e

a a

11 i

n e4 e4 e4 e4 r6 r6 r6 r6 r6 r6 r3 r3 g

,9

,9 u9 e

G7G7G7G7 p0 p0 p0 p0 p0 p0 p5 p5 p pd r 6 r6 q6 q6 m

S7S7S7S7S7S7S6S6 mml o6o6E6E6 u

uuBd d

l

. l

. l

.l e

r el el e1 e1 e e

e e

e

.PP i.i.....

t sE sE sE sEl 1 l l l 1 l 1 l 1 l 1 t1 t1

.r1 r1 h1 h1 s

e e

e e

bEbEbEbEbEbEnE nERR xrErEcE cE n

i i

i i

a a

a a

a a

o o

HH uo o

I D

D D

D C

C C

C C

C C

C RRAC C

M ee rno 6

7 8

9 0

1 2

3 4

5 9

0 3478 9

0 i

FZ 2

2 2

2 3

3 3

3 3

3 3

4 4444 4

5 meg $z ' Ch -

m g,* 8 N$@$" 5, U '

l'

3i; i

l g'

derar fn I

e l

b l

a a r m e r

- 1 1

p e O h T

s tn c e

i m r S

u t

)

T r c d

N t

e 1

I e

E s

l u

M n e n

U I

o i

R t

t T

m o n

S u h o

N m P C

I i

(

n n N

i O

M o 1

1 I

i T

t 32222

~6 1

6 1

22223 3

3 3

7 7

444 3

C a

E z

3 T

i E

n E

D o

L I

B E

A R

T I

F 66 6

00 W

W 444 0

77.

7 r

r m

m m

m 111 66

.. t t

R R

R R

U U

777 00l 1 1 1

6 A

A 1 77EEF F

0 I

l r

r r

r E

7 g

i i

i i

l l

11 1

.. aa.

d A

A A

A o

o EEE a11 eet t

m m

C C

l n

eEErre e

l R

B R

e e

e e

o r

AAt t

E g

g g

g mmm i

Aaa r

r k

k 4444 r r

r r

l l

RRR t

eeeeT T

n p

n 1111 u u

u u

l l

a grrgg g

a i

a 7777P P

P P

A A

c nAAaas s

d T

u T

ttt o

i rra a

l q

5 S

nnn L

gggooG G

B E

1l11 A

A eee anntt t

t EEEEn n

n n

VVV t

kiiSS n

l n

o o

o o

n cdd g4 g4 t o0a6o0

. i 4 i 4 i 4 i 4 g4 g4 & & &

d1d1 p C9n0C9smmst1t1t1t1d1d1 e

aaal l m

P ooeel 7l 7 q5 6o7 6RRRRa7a7a7a717l 7ggg u

LLuuB B

E

.e i

e l

l l

l

.B.B nnn 7 m

.t

.m SSSSi.i.i.i r

e FF

.iii t

tkk

.1

.l

.1 u1 il ulTTTTt1 tl tltl

.l

.1 ttt s

ssswwxE xEd7l EdEl EGGGGnEnE nEnExExEaaa n

aaaeeu u

d o

d o

BBBBe e

e e

u u

eee WCCNNA A

A V

A V

AAAAV V

V V

A A

HHH I

ee rn 567890 1

2 3

4 5

67890 1

2 3

4 5

678 i o 111112 2

2 2

2 2

22223 3

3 3

3 3

333 FZ 111111 1

1 1

1 1

11111 1

1 1

1 1

111 u, W 13? E 5d '

1E$

<2-

%* jw

! g g g 2o'

,d

[

i 2

(il l!)il\\

6 jl llll' L

l ll

il lil o~

~

l'

. n,

~

=

~:

dera

.r fn I

e l

b l

a a r m e r 9

4 9

8 2222222 p e O

h T

s tn c e

i m r S

u t

)

T r c d

N t

e e

E s

l u

M n e 3444 n

U I

o i

R t

t T

m o n

S u h o

N m P C

I i

(

n N

i n

1 O

Mo 1

I i

T t

3 C

a 11444444448 4

8 35 16 99 E

z 1

2 3

T i

E n

E D

o L

I B

E A

R T

I F

38 97 99 2

67 44 3

7799999999 7 ss 4444444155 55 uu1 l 7777777788 88 4,

lll EE 66 66r 0D Euu l l EE 55 o

74 nn,,

n l l11l1 ll 88.. d

.nnss o

VVEEEEEEEE1l 66l l i.

sAArr i

II EE EEra 18 d

ee t

B8AAAAB8 rt5E4

. B g gl l

a 11Il2222 oS.

nnoo~

.l1

..ee........RRssEEssC 0.L4sRiioo 3333333 c

RR o

RR g1 a 3dCddCC 9999999 L

ssmssmms

.n6t 7B ll 6666666

.si Ss nii RRRRRRRR

.es t

tt r r R R r r R p&

d

..i uutt n

tt........ tt tt m

pB1t a B B p pl1111 11 e

aaddddddddssrrssru0m EnM mmEEEEEEE m

BBBBBBBBBBnneenneP9uR o

rroo

~

u IIttIIt 6PC CnooCC r

VVVVVVVVVV uu u

B ott 2211334

.pkl W t

.pp

. 1 nmcc s

5500000000 xxmmxxmtECx1imaarrPPPPPPP n

2288888888 uuoouuon Ru a o e e w pC C C C C C C 1144444444 AACCAACI EA MCRRLURRRRRRR I

ee rn 567890123478901236 76 7801246701458 io 555556666666677777 79 9933555566666 FZ 222222222222222222 22 2233333333333 C( "

mg,4m

,gs[=" f $

,._8 meg l

j' ll' l'!

ll;llll ljlllI!

1 l

derar fn I

e l

blaa rm er 2

8 11 111111 pe 1

0h

' T s

tnc eimr S

ut

)

T rc d

N t e e

E sl 21 u

M ne 22 n

U o

I~t i

R t

T co n

S uh o

N mP C

I i

(

n N

in 1

O Mo 1

I i

T t

3 C

a 222 2

E z

3 T

i E

n E

D o

L I

B E

A R

T I

F 0

0 9

9 6

6 44 444444 33 333333 l

99l 77l 777777 l

44E E

a 77 ssW gl l gl l l l l l uu NEE nEEEEEE n

l l l l i i

o uug eel 22l 222222 i

nnd 8Ai888AAA i

t nnl VVe12 e111222 a

AAB C

C c

3 o

9...

mmmmmmsmmmmm L

6 ggt RR oRR oRRRRRR ddn o

o t

.l l o RddRdddddd n

l BBC6tt BB BBBBBB e

E 0tt g g

m

,rre7 aanddndddddd u

oon

.BBiSSiSSSSSS r

4tti t

t t

ccbl VVnVVnVVVVVV s

P aarE55 u00 u000000 n

C eeu 22 o88o888888 I

RRRT 11C44C444444 ee rn 9237 788235678901 i o 6778 225666666677 FZ 3333 444444444444 a:

E x S3. C2 ~5*

i ' 2 t* i8*

2&* n c

,ll'

7 j

l:

w L

{

f l'

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4

4.

• Verifying the diesel starts from ambient condition and l

accelerates to at least 900 rpm in less than or equal to l

10 seconds.. The generator. voltage and frequency shall be 6900 690 volts and 60 1 1.2 Hz within 10 seconds after the l-l start signal.

The diesel generator shall be started for this

.f

. test by using one of the following signals with startup on each i,

l l

signal verified at least once per 124 days:

1 l

a)

Manual.

i b)

Simulated loss of offsite power by itself.

i l-I i -

c)

An ESF actuation test signal by itself.

3 5.

• Verifying the generator is synchronized,' loa'ed to greater than d

or equal to 4400 kw in less than or equal to 60 seconds, and I

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

Verifying the diesel generator is aligned to provide-standby j

power to the associated shutdown boards.

b.

At least once per 31 days and after each operation of the diesel a

where the period of operation was greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by checking for and removing accumulated water from the engine-i mounted fuel tanks.

c.

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

j 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, j

2.

Verifying the generator capability to reject a load of greater f

than or equal to 600 kw while maintaining voltage within i 10 percent of the initial pretest voltage and frequency at 60 + 1.2 Hz.

At no time shall the transient voltage exceed 8276V.

3.

Verifying the generator capability to reject a load of 4400 ku j

without tripping.

The generator voltage shall not exceed l

114 percent of the initial pretest voltage or 8276V, whichever t

is less during and following the load rejection.

l

• The diesel 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-l veillance testing may be preceded by an engine idle start, followed by gradual acceleration to synchronous speed (900 rpm), synchronization, and gradual loading.

SEQUOYAH - UNIT 1 3/4 8-3 Amendment No. 52,64,9% 109

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

The generator voltage and frequency shall be 6900 i 690 volts and 60 1 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. Within 5 minutes after completing this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, perform Specification 4.8.1.1.2.d.4.

8.

Verifying that the auto-connected loads to each diesel generator

.do not exceed the continuous rating of 4400 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.

t

'. 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 1 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 e.

At least once per 10 years or after any modifications which could l

affect diesel generator interdependence by starting 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.

f.

At least once per 10 years

• by:

1.

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypoclorite solution, and i

l 2.

Performing a pressure test of those portions of the diesel l-fuel oil system design to Section III, subsection N0 of the l

ASME Code at a test pressure equal to 110 percent of the system design pressure.

• These requirements are waived for the initial surveillance.

SEQUOYAH - UNIT 1 3/4 8-5 Amendment No. 52,64, 109

_- _ - _ _ _ + _-

.i

-ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

4. 8.1.1. 3 The 125-volt D.C. distribution panel, 125-volt D.C. battery bank j

and associated charger for each diesel generator shall be demonstrated j

'0PERABLE:

I a.

At least once per 7 days by verifying:

1.

That the parameters in Table 4.8-la meet the Category A limits.

2.

That the total battery terminal voltage is greater than or equal to 124-volts on float charge, b.

At least once per 92 days by:

i 1.

Verifying that the parameters in' Table 4.8-la meet the l

Category B limits, i

2.

Verifying there is no visible corrosion at either terminals or connectors, or the cell to terminal connection resistance of these items is less than 150 x 10 8 ohms, and 3.

Verifying that the average electrolyte temperature of 6 connected cells is above 60 F.

c.

At least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal. deterioration.

2.

The battery to battery and terminal connections are clean, tight and coated with anti-corrosion material.

3.

The resistance of each cell to terminal connection is less than or equal to 150 x 10 6 ohms.

4.8.1.1.4 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.2.2.

SEQUOYAH - UNIT 1 3/4 8-6 Amendment No. 52

l i.

TABLE 4.11-2 (Continued)

TABLE NOTATION b.

Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of rated thermal power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the dose equiva-lent I-131 concentration in the primary coolant has not increased l

more than a factor of 3 and (2) the containment noble gas activity l

monitor (RE-90-106 or RE-90-11?) shows that the radioactivity has not increased by more than a factor of 3.

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

the refueling canal is flooded.

d.

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

Sampling shall also be performed at least on:e per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from 215% RATED THERMAL POWER, startup of 215% 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

g.

The principal gamma emitters for which the LLD specification applies 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, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Co-144 for particulate principal gamma emitters.

This list does not mean that only these nucli'ies are to be detected and reported.

Other gamma peaks which are mesureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semi-annual Radioactive Effluent Release Report pur m nt to Specification 6.9.1.9.

h.

During releases via this exhaust system.

i.

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 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 between 20 and 25 minutes following initiation of the incore instrument room purge.

SEQUOYAH - UNIT 1 3/4 11-13 Amendment No. 42,65. 109

e.

TABLE 4.11-2 (Continued)

TABLE NOTATION J.

Venting - Applicable in MODES 1, 2, 3, and 4; the containment will be

. vented to the containment annulus and then to.the auxiliary building via containment annulus fans.

The lower.' containment compartment shall

.be sampled daily when venting is'to occur to account for.the radio-activity being discharged'from the venting process.

~

9 l

l.

l 1

l SEQUOYAH - UNIT 1 3/4 11-14 Amendment No. 42,65 b___=-_____-'- - - - - - - - - - -. -. - - - - _ - - - - - - - - - - - - - - - - - -

l

e'

1. "g.-..%*%

UNITED STATES

,h NUCLEAR REGULATORY COMMISSION

[

,s>

l wAswiNoToN. o. c. 2osss

\\,,.

]

TENNESSE_E VALLEY AUTHORITY 00C K ET,,N,02 10-328 S_ERU,0,Y,AH huCLEAR PL,AN,T,, UNIT 2 AMENDMENT TO F.ACJ,LJ,T,Y,,0,P,E, RATING LJCE,NS,E Amendment No.99 License No. OPR-79' 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee)datedSeptember 14, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations. set forth in 10 CFR Chapter I; P.

The facility will operate in ccr.formity with the application, the provisions of the Act, and the rules and regulations of the Corraissicr:;

C.

There is reasonable assurance (i) that the activities authorized by this an,endrr.ert can be conducted without endangering the health and safety of the public, ard (ii) that such activities will be I

conoucted in compliarce with the Couission's regulations, j

D.

The issuance of this amendment will rict be inimical to the comon l

defense and security or to the health and safety of the public; and

]

E.

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

A l

l 2.

Accordingly..the license is amended by changes to the Technical

' Specifications as indicated in the attachment to this license amendment l

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

(2)- Technical Specifications.

The ' Technical Specifications contained in Appendices A and B, as revised through Amerdment No. 99, are hereby incorporated -in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

.A.

un L-Suzanne ack, Assistant Director for Projects TVA Projects Division i

Office of Nuclear Reactor Regulation

Attachment:

Changes to.the Technical Specifications Cate of Issuance: April 3, 1989 l

l 1

1 I

q q

i i

1 o

{

ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE N0. DPR-79 i

DOCKET NO. 50-328 l

Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3/4 3-7 3/4 3-7 3/4 8-3 3/4 8-3 3/4 11-11 3/4 11-11*

l 3/4 11-12 3/4 11-12 I

i l

l-1 l

_ _ _ _ _ ____i

e.

i 1

TABLE 3.3-1 (Continued) i ACTION 8 - With less than the Minimum Number of Channels OPERABLE, declare the interlock inoperable and verify that all affected channels i

of the functions listed below are OPERABLE or appiy the appro-priate ACTION statement (s)'for those functions.

Functions to be evaluated are:

a.

-Source Range Reactor Trip.

4 b.

Reactor Trip l Low Reactor Coolant Loop Flow (2 loops)

J Undervoltage Underfrequency l

c Pressurizer Low Pressure I

Pressurizer High Level c.

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

Reactor Trip Intermediate Range Low Power Range Source Range ACTION 9 - Deleted ACTION 10 - Deleted ACTION 11 - Deleted-ACTION 12 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT Si.tNDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

I SEQUOYAH - UNIT 2 3/4 3-7 Amendment No. 46* 99 i

l b

\\

I ELECTRICAL POWER SYSTEMS 4

SURVEILLANCE REQUIREMENTS (Continued) 4.

• Verifying the diesel starts from ambient condition and l

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

The generator voltage and frequency shall be 6900 690 volts and 60 i 1.2 Hz within 10 seconds after the l

start signal.

The diesel generator shall be started for this test by using one of the following signals with startup on each I

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.

5.

• Verifying the generator is synchronized, loaded to greater than or equal to 4400 kw in less than or equal to 60 seconds, and operates for greater than of 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 each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by' checking for and removing accumulated water from the engine-mounted fuel tanks.

j c.

At least once per 92 days and from new fuel oil prior to addition 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 er 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 par 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 within 10 percent of the initial pretest voltage and frequency at 60 + 1.2 Hz.

At no time sbsll the transient voltage exceed 8275V.

3.

Verifying the generator c y ability to reject a load of 4400 kw without tripping.

The generator voltage shall not exceed 114 percent-of the initial pretest voltage or 8276V, whichever is less during and following the load rejection.

• The diesel 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 j

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

j SEQUOYAH - UNIT 2 3/4 8-3 Amendment No. 44,55,88, 99 l

_.._--_._._._-._.-___.--.._.--._--_.-.___a_

4 TABLE 4.11-2 (Continued) t l

TABLE NOTATION t

The LLD is defined,.for the purposes of these specifications, as the smallest a.

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 fab ely concluding that a blank observation represents a "real" signal.

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

4.66 s E

V 2.22x10' Y

exp (-A.ot)

Where:

LLO is the "a priori" lower limit of detection as defined ebove in i

microcurie per unit mass or volume, is the standard deviation of the background counting rate or of s s the counting rate of a blank sample as appropriate (as counts per i

minute),

l E is the counting efficiency,as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclides, and at for. plant effluents is the elapsed time between midpoint of sample collection and time of counting (midpoint).

It should be noted that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b.

Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of rated thermal power within I hour unless (1) analysis shows that the dose equiva-lent I-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the containment noble gas activity monitor (RE-90-106 or RE-90-112) shows that the radioactivity has not increased by more than a factor of 3.

SEQUOYAH - UNIT 2 3/4 11-11 Amendment No. 34,57

-e TABLE 4.11-2 (Continued)

TABLE NOTATION l

c.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when l'.

the refueling canal is flooded.

l' d.

Samples shall be changed at least'once per 7 days 'and analyses shall l

be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from l

sampler).

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

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.dayr from e.

the ventilation exhaust from the spent fuel pool area, whenover 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.

g.

The principal gamma emitters for which the LLD specification applies 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 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 6.9.1.9.

h.

During releases via this exhaust system.

i.

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

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.

The incore instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument room purge.

J l

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.

I SEQUOYAH - UNIT 2 3/4 11-12 Amendment No. 34, 99 i

(Corrected page) i A=20-%

.