ML20237H547

Rev 2 to Function Restoration Guidelines FR-S.1, Response to Nuclear Power Generation/Atws

ML20237H547
Person / Time
Site:	Sequoyah
Issue date:	09/08/1986
From:	Deakins D, Strickland G TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20237H133	List: ML20237H131 ML20237H155 ML20237H173 ML20237H196 ML20237H257 ML20237H274 ML20237H281 ML20237H298 ML20237H348 ML20237H361 ML20237H365 ML20237H400 ML20237H412 ML20237H421 ML20237H430 ML20237H438 ML20237H452 ML20237H464 ML20237H480 ML20237H492 ML20237H501 ML20237H508 ML20237H517 ML20237H532 ML20237H547 ML20237H559 ML20237H593 ML20237H602 ML20237H616 ML20237H629 ML20237H641 ML20237H649 ML20237H654 ML20237H659 ML20237H671 ML20237H682 ML20237H689 ML20237H696 ML20237H699 ML20237H703 ML20237H714 ML20237H719 ML20237H726 ML20237H735 ML20237H739 ML20237H770 ML20237H796 ML20237H852 ML20237H899 ML20237H967 ... further results
References
FR-S.1, NUDOCS 8708170261
Download: ML20237H547 (7)

Text

_ _ - - _ - _ _ -

R-t.

4

~o a-TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT

• eh.

FUNCTION RESTORATION GUIDELINES FR-S.1

-RESPONSE TO NUCLEAR POWER GENERATION /ATWS P

Revision 2 r

PREPARED BY:

G.

Strickland RESPONSIBLE SECTION:

Operations REVISED BY:

Don Deakins f'

SUBMITTED BY:

Wirlsq<

w

(.>

'Respon'sible Section Supervisor e

PORC REVIEW DATE:

SEP 0 81986 APPROVED BY:

D' Plant Manager DATE APPROVED:

SEP 0 81986 L.

Reason for revision I

(include all Instruction Change Form Nos.):

L_

Revised to prevent overpressurizing BIT recirculation lines, prevent diverting BIT contents to BAT until recirculation is closed and prevent dilution of BIT.

The last page of this instruction is number:

f 5

m L.

L 8708170261 87g h PDR ADOCK 0 PDR P

~-

3 4

SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG FUNCTION RESTORATION GUIDELINES FR-S.1 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS) 0 10/04/85 All Revised to add reference to status tree; correct valve number; change to isolate 1

08/21/85 1,3 letdown prior to isolating charging.

Revised to prevent overpressurizing BIT recirculation lin.es, prevent diverting 2

SJ, P 0 81933 BIT contents to BAT until recirculation 3

is closed and prevent dilution of BIT.

f

% J l

L 0278L/v1f L.

sL_

l

SQNP I

FR-S.1 Unit 1 or 2 Page 1 of 5 Rev. 1 RESPdNSE TO NUCLEAR POWER GENERATION /ATWS A.

PURPOSE This guideline provides actions to add negative reactivity to the core.

B.

SYMPTOMS 1.

Power range greater than 5%

2.

Intermediate range positive startup rate C.

TRANSITION FROM OTHER INSTRUCTIONS 3

)(c 1.

E-0, Reactor Trip Or Safety Injection 1

p 2.

Status Tree

.f*

~

eS _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

SQNP FR-S.1 Unit 1 or 2 Page 2 of. 5

' Rev. 0

. y-RESPONSE TO NUCLEAR POWER GENERATION /ATWS STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED y.

• Note:

Steps 1 through 4 are IMMEDIATE ACTION STEPS t

1

' Open Reactor Trip Breakers IF trip breakers can NOT. be opened, a.

Pnl M-4 or M-6 THEN:

a.

Decrease turbine load

~b.

Verify auto rod insertion or manuahy insert control rods to ' maintain.T-avg at T-ref c.

Open reactor trip breakers at MG Set C-Room Aux Bldg 759 e

d.

Open breakers to control rod MG sets at 480V Unit Boards A and B AND notify inst to close P-4 contact 6

/

SQNP FR-S.1 Unit 1 or 2 J*

Page 3 of 5 Rev. 2 RESPONSE TO NUCLEAR POWER GENERATION /ATWS STEP ACTION / EXPECTED RESPONJ:

RESPO SE NOT OBTAINED 2

Borate RCS a.

Close BIT recire g

FCV-63-38, 41, and 42 b.

Open BIT outlet g

FCV-63-25 and 26 c.

Open BIT inlet p

FCV-63-39 and 40 d.

Close letdown orifice valves FCV-62-72, 73, and 74 r

e.

Close charging valves FCV-62-90 and 91

/

f.

Open RWST valves FCV-62-135 and 136 g.

Close VCT outlet valves FCV-62-132 and 133 h.

Open emergency borate g

valve FCV-62-138B i.

Place BA transfer pumps to fast speed L.

j.

Establish CCS to B CCP k.

Start second CCP if L

required 1.

Decrease turbine load' to maintain T-ref at T-avg T

I 1

u 1 L l

SQNP FR-S.1 Unit 1 or 2 Page 4 of 5 Rev. O I

I RESPONSE TO NUCLEAR POWER GENERATION /ATWS i

1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3

After Reactor Trip, Verify IF turbine can NOT be Turbine Trip tripped,

)

THEN:

a.

All turbine stop valves -

CLOSED Close MSIVs and bypasses i

Trip turbine from main turbine front standard Stop and PULL-TO-LOCK

{

both EHC pumps at EHC l

pump control station 4

Ensure All AFW Pumps - RUNNING

(

a.

Both motor driven AFW

,j(

< pumps b.

Turbine driven AFW pump 5

Check RCS Press < 2335 psig IF RCS press > 2335 psig, THEN:

a.

VerEy pzr PORV and block valve open b.

Verify entmt purge air exhaust isolated

,m,

..me..

u-e.

-4..

ew-**

-*M-=

l s 4

SQNP j

FR-S.1 Unit 1 or 2 Page 5 of 5 Rev. O RESPONSE TO NUCLEAR POWER GENERATION /ATWS STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6

Verify All Dilution Paths Isolated i

7 Check Intact S/G Levels a.

Narrow range S/G a.

Ver'ly AFW flow and IcVels > 25%

S/G levels returning to normal program b.

Control S/G levels between 25% and 50%

8 Check S/G Press IF the S/G with low or Ecreasing press has NOT a.

Press in all S/Gs within been isolated, 100 psi of each other THEN go to

• E-2,

(

FAULTED STEAM

. e {k GENERATOR ISOLATION b.

AU S/G press - STABLE OR INCREASING 9

Check If Reactor Subcritical Continue to borate and evaluate cause of reactor a.

Power range < 5%

criticality b.

Intermediate range -

NEGATIVE STARTUP RATE 10 Return To Instruction In Effect i

e

+-e

.m+*=wem-ev m.e g

5-

)