ML20205B557

From kanterella
Revision as of 07:12, 30 December 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Rev 2 to Emergency Operating Procedure EOP 35 ES-3.2, Post-Steam Generator Tube Rupture Cooldown Using Blowdown
ML20205B557
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/15/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-35-ES-3.2, NUDOCS 8810260272
Download: ML20205B557 (10)


Text

.. .

Stephen E. ace 3-31-87 ,

87-12 Form Approved by Station Superintendant Ef fective Disce 50RC Mtg. No.

STATION PROCEDURE COVER SHEET .!

A. IDENTIFICATI'ON -

Number: E0P 35 ES-3.2 Rev. 2

Title:

P_OST-SGTR C00LDOWN USING BLOWDOWN i

Prepared By: R. F. Martin B. REVIEW I have reviewed the above procedure and have round it to be satisfactory.

. lITLE SIGNATURE DATE DEPARTMENT HEAD M_b 7 J G // P8-C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO[I (If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO [ T D. SPECIFIC SAFETY EVALUATION REQUIRED l Affects response of safety systems, performance of systems which may have been credited in the, safety analysis o non-credited systems which may indirectly afiect safet) system response. YES [ ] NO [(

i (If yes, perform written Safety Evaluation and

contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] N0 [ (

! rT p E. PROCEDURE REQUIRES ( RORQ/SORC REVIEW (In adoition to re+4ew, items gith a YES response must be documented in the C)SORC meeting minutes.) YES [ [ NO [ ]

G. 50RC APPROVAL SORC Meeting Number }.-87-207 H. APPROVAL AND IMPLEMENTATION The attache r re y approved, and effective on the date below:

^

j _f / w d di~- (Y Station / Service / Unit Superintendent Efrective Date SF 301 l Rev. 9 4

8810260272 001007 Page 1 of 1 PDR A30CK 05000213 P PDR

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

E0P 35 ES-3.2 Page 1 Rev. 2 0 1 POST-SGTR C00LD0kH USING BLOk'D0kW 4 Page No. Eff. Rev.

1-9 2 l

i l

l

[

5 4

i i

I i

i t P

l i

I r

i f

i f

i i

1 I

< i I

i I

l l

6 i

r f

n i I

P051-5Gls! CVOLDOnN U51NG BLOWDOWN E0P 35.ES-J.2 Page 2 Rev. 2 7- __ __- ,

N.]

A. PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a steam generator tube rupture. This recovery method depressurizes the ruptured SG(s) by draining it using SG blowdown.

B. ENTRY CONDITIONS This procedure was written for Modes 1, 2 and 3 assuming RHR system not in service. Using this procedure when not in these modes requires a step by step evaluation to determine if the required.

action is still applicable to current plant conditions.

1. This procedure is entered f rom E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 39, if'Direc,or of Station Emergency Organization (DSEO) selects the blowdown method.

A

\

OP5M.8-2 3 84

POSI-5 bin COOLLOWN USING BLOWDOWN E0P 35 ES-3.2 Page 3 Rev. 2

/ 4

-] ,

STEP ACTION / EXPECTED RESF ONSE RESPONSE NOT OBTAINED NOTE Foldout page should be cpen.

1 Turn ON PZR Heaters As Necessary To Saturate PZR Water At Ruptured SG(s) Pressure 2 Check if SI Accumulators Should Be Isolated

a. Check RCS subcooling based a. Go to E0P s5 ECA-3.1, on core exit TCs > 30*F SGTR WITH LOSS OF

[90'F FOR ADVERSE REACTOR COOLANT -

CONTAINMENT] SUDC00 LED RECOVERY AND DESIRED, Step 1.

PZR level > 7% [50% FOR l ADVERSE CONTAINMENT]

b. Restore power to isolation valves (32-2R-RSF, f3 32-2W-R3J, 32-2R-F4M,

( ) 32-2W-F4M)

c. CLOSE all SI accumulator c. Vent any unisolated isolation valves accumulators.
d. Remove power from isolation valves CAUTION Dilution of RCS boron concentration may occur on transfer of secondary water into the PCS.

3 Verify Adequate Shutdown Margin

a. Sam}4e RCS
b. Shutdown m.irgin - ADEQUATE b. Borate as necessary.

,O '

'% j OPM641 3 . *4

. POST-SGTR C00LDOWN USING BLOWDOWN E0P 35 ES-3.2 Page 4 Rev. 2

/~' s N,]

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION CST water source for AFW pumps will be necessary if DWST level decreases to < 80,000 gal. l NOTE If the SG 1evels are out of the narrow range, the vide range SG 1evel indication should be used to anticipate approach tc the narrow range and also as an early aid in identifying previously undetected steam generator tube failures.

4 Check Intact SG Levels

a. Narrow range level a. Maintain total feed flow

> 4% (34% FOR ADVERSE > 525 gpm until narrow CONTAlhMENT) range level > 4% (34%

FOR ADVERSE CONTAIhMENT) in at least one SG.

[~'s- -} b. Control feed fl'ow to b. IF narrow range level in any intact SG centinues maintain narrow range level between 4% to increase in an (34% FOR ADVERSE uncontrolled manner, THEN CONTAINMENT) and 50% go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

l l 6 l

l /~'

1 \~,)T OPSX4 1 3 $4 l

l

. POST-SGTR C00LDOWN USING BLOWDOWN E0P 33 ES-3.2 Page 5 Rev. 2 l \

\ /

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINtJ NOTE

1. Since ruptured 'SG(s) may continue to depressurize to less than the minimum,RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should be completed as quickly as possible, not to exceed 100 F/hr.
2. The Main Steam Isolation Valven cooldown mode should ba actuated for intact SG(s) when RCS temperature indicates ipproximately 400'F to preclude inadvertent closure of these valves.

5 Initiate RCS Cooldown To 350*F

a. Maintain cooldown rate in RCS cold legs

< 100*F/IIR

b. Dump steam to condenser b. Manually 03 locally dump from i.1 tact SG(s) steam to atmosphere.

IF no intact SG

(h

( ,)

available, THEN use a faulted SG OR go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -

SUBC00 LED RECOVERY DESIRED, Step 1.

O P*>C48 1 3-se

PUSf-SGIR COOLDOWN LSING BLOWDOWN EOP 35 ES-3.2 Page 6 Rev. 2 7 s ,

i i L .J' STEP ACTION /EXFECTED RESPONSE - RESPONSE NOT OBTAINED CAUTION RCS and rupture SG(s) pressures must be maintained less than the ruptured SG(s) atmospheric dump setpoint.

6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage

a. Perform appropriate action (s) from table RUPTURED SG(s) INCREASING DECREASING OFESCALE

. VEL HIGli PZR LEVEL

':17% (50% FOR ADVERSE Increase RCS Increase RCS Increase RCS

0NTAINMENT) Makeup Flow Makeup Flow Makeup Flow f}

V AND AND Depressurize Maintain RCS RCS Using Arad Ruptured Step 6b SG(s) Pressures Equal

!!ETkEEN Depressurize Turn On Maintain RCS 17% (50% RCS Using PZR And Ruptured FOR ADVERSE Step 6b Heaters SG(s) P essures

0NTAINMENT) and 50% Equal BETWEEN 50% AND Depressurize Turn On  !!aintain RCS 13% (50% RCS Using PZR And Ruptured FOR ADVERSE Step 6b lleaters SG(s) Pressures
0NTAINMENT) Equal

^ND Decrease RCS Makeup Flow _

73% (50% Decrease RCS Turn on Maintain MCS FOR ADVERSE Makeup Flow PZR And Ruptured

0NTAISMENT) Heaters SG(s) Pressin i s Equal
b. Use nornal PZR spray b. IF letdown is in service, per Step 6a. THEN u :e auxiliary spray.

IF NOT. TilEN use one PZR p PORV.

o 00%%4 ' 3 84 t

POST-SGTR COOLDOWN USING BLOWDOWN E0P 35 ES-3.2 Page 7 Rev. 2

\ ,/

STEP ' CTION/ EXPECTED NSPONSE RESPONSE NOT OBTAINLD 7 Check if RCS Cooldown should be stopped

a. RCS Temperatures a. Return to Step 3.

< 350'F l

b. Stop RCS cooldown NOTE la the following step, it is intended that the operator allow the ruptured SG to drain to a low narrow range level and then refill it to a high narrow range level ratner than continuously feeding the ruptured SG to cortrol level.

8 Check Ruptured SG(s) Refill ruptured SG to 82%

Narrow Range Leve). (61% FOR ADVERSE CONTAINMENT)

> 4% (34% FOR ADVERSE using teed flow. IF ru.'.ured CONTAINMENT) SG pressure decreases in uncontrolled manner Oh ruptured SG pressure increases to 1100 psig, THEN stop feed flow to ruptured SG.

(_)

V NOTE Blowdown from ruptured SG(s) may be stopped when RHR System is in service.

9 Establish Blowdown From Go to alternate post-SGTR Ruptured SG(s) cooldown procedure, E0P 35

a. Establish minimum "S-3.1, POST-SGTR COOLDOWN condenser vacuum USING BACKFILL, Step 1, OR E0P 35 ES-3.3, POST-SGTR C00LDOWN USING STEAM DUMP, Step 1.
b. Establish blowdown from ruptured SG to condenser 10 Control RCS Makeup And Letdown To Maintain PZR Level
a. PZR level > 17% (50% a. increase RCS ma'<eup FOR ADVERSE CONTAINMENT) flow as necessary. Go to Step 11.
b. PZR level < 73% (50% FOR b. Decrease RCS makeup AD'/ERSE CONTAINMENT) flow as necessary, f}

LJ Go to Step 12.

C#~,M-3. t 3 84

~

. POST-SGTR COOLDOWN USING BLOWDOWN E0P 35 ES-3.2 Page 8 Rev. 2 N.

I

~_ Y STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PZR level.

11 Depressurize RCS To Minimize

  • RCS-To-Seconoary Leakage
a. Use normal PZR spray a. IF letdown is in service, THEN use auxiliary spray.

IF NOT, THEN use one P2R PORV.

b. Turn ON PZR heaters as necessary
c. Maintain RCS pressure at ruptured SG(s) pressure
d. Maintain RCS subcooling based on core exit TJs

, _ , , > 30'l (90*F FOR ADVERSE CONTAINMENT)

(V')

12 Check 1( RCPs Must Be Stopped

a. Check the following a. Go to Step 13.
1) Number 1 seal differential pressure

< 210 psid OR

2) Number 1 seal return flow < .2 gpm
b. STOP affected RCP(s) l i

i V

ON64 1 3 d4

1 I

POST-SGTR C00LDOW USING BLOWDOWN E0P 35 ES-3.2 Page 9 i

Rev. 2

_ _13 Check If RHR System Can Be l

l' Placed in Cooldown Mode

a. Check RCS temperature a. Return to Step 8.
< 350'T (350 F FOR ,

ADVERSE CONTAINMENT) AND l RCS pressure < 390 PSTA t (390 PSIA FOR ADVERSE r

~,

CONTAINMENT)

b. Place RitR system in cooldown -

l node using OP 3208 PLANT l

! COOLDOW l

c. Stop blowdown from ruptured *l SG(s)

{

f 14 Continue RCS Cooldown To  !

Cold Shutdown l

a. Maintain cooldown rate (

in RCS cold legs r

< 10')'F/HR l l
b. Use RHR System I c. Du:np steam f rom intact c. Manually OR locally f SG(s) to condenser dump stea a to a tmc,aphere .  ;

IF no intact SG available [

! and RHR system NOT in #

! service, TyEN use a p

' faulted SG OR go to EOP l SS EhtECORC NT -

i SUBC00 LED RECOVERY -

l DESIRED, Step 1.  !

l I l 15 Check RCS Temperatures AJ Return to Step 8. I j RVLMS Head T/C's < 200"F l

16 Maintain cold shutdown [

) conditions l

I

! -FINAL- j I-i l

l

,.