ML20205B621

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Rev 2 to Emergency Operating Procedure EOP 35 ES-3.3, Post-Steam Generator Tube Rupture Cooldown Using Steam Dump
ML20205B621
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-3.3, NUDOCS 8810260288
Download: ML20205B621 (10)
v • d • e


Text

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Stephen E.  : ace 3-31-87 87-l2 Form Approved by Stat wn Superintendent Effective Ooci 50RC Mtg. No.

STATION PROCEDURE COVER SHEET .

(,) A. IDENTIFICATION Number E0P 35 ES-3.3 Rev. 2 1 Title POST-SGTR C00LOOWN USING STEAM DUMP Prepared By R. F. MxRTIN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD (,[4&P

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C. SPECIFIC UNREVIEWED SAFE 1Y QUESTION EVALUATION REQUIRED:-

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

Q ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO [T

0. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems wh;ch may indirectly affect safety system response. YES [ ] N0 [ }

(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 [ ] NO [M F. PROCEDURE REQUIRES /SORC REVIEW (In addition to revi%, ite.ms with a YES response '

must be documented in the P /50RC meeting minutes.) YES f] NO [ ]

G. 50RC APPROVAL SORC Meeting Number 1-V~J-2d7 H. APPROVAL AND IMPLEMENTATION The attach' + dure ereby approved, and effective on the date below:

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~5tation/ service / Unit SuperTntendent cffective Date SF 301 Rev. 9 Page 1 of 1 0010260?O0 001007 PDR ADOCK 0500021J P ppg

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. POST-SGTR C00LD0kW USING STEAM DUMP ECP 35 ES-3.3 Page 2 l Rev. 2 ,i l'

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A. PURPOSE This procedus'e provides actions to cool down and depressurize the plant to cold shutdown conditiens following a steam generator tube rupture. This recovery method depressurizes the ruptured SG(s) by dumping steam.

B. ENTRY CONDITIONS ,

This procedure was written for Modes 1, 2 and 3 assuming RHR System is 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 plattt conditions.  ;

1. This procedure is entered from
a. E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 39, if
Director of Station Emergency Organization (DSE0) selects steam dump method.
b. E0P 35 ES-3.2, POST-SGTR C00LD0kW USING BLOWD0kN, Step 9,
  • 1 when blowd.own is not available and Director of Station Emergency Organization (DSEO) selects steam dump method. ,

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POSI-5GIR COOLDOWN USING SIEAM DUMP EUP 35 ES 3.3 Page 3 Rev. 2 i )

Q ,i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION

1. Steam should not be released from any ruptured SG if water may exist in its steamline.
2. An offsite dose evaluation should be completed prior to using this procedure.

N0YE Foldout page should be open.

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

,_s a. Check RCS subcooling a. Go to E0P 35 ECA-3.1,

( ') based on core exit TCs SGTR WITH LOSS OF

\s / > 30 F (90 F FOR REACTOR COOLANT -

ADVERSE CONTAIN' MENT) SUBC00 LED RECOVERY AND DESIRED, Step 1.

PZR level > 7.0% (50% FOR ADVERSE CONTAINMENT)

b. Restore power to isolation valvas - AVAILABLE (32-2R-RSF, 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 O

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POST-SGTC COOLDOWN USING STE AM DUMP EUP 35 ES-3.3 Page 4 Rev. 2

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Dilution of RCS boron concentration may occur on transfer of secondary water into the RCS.

3 Verify Adequate Shutdown Margin

a. Sample RCS
b. Shutdown margin - ADEQUATE b. Borate as necessary.

CAUTION CST water source for AFW pumps will be necessary if DWST level decreases to < 80,000 gal.

NOTE (g) If the SG 1evels are out of the narrow range, N- ' the wide range SG level indication should be used to anticipate approach to the narrow range and also as an early aid in identifying previously undetected steam generator tube failures.

4 Checa Intact SG Levels

a. Narrow range level a. Maintain total feed flow

> 4.0% (34% FOR ADVERSE > 525 gpm until narrow CONTAINMENT) range level > 4.0% (34%

FOR ADVERSE CONTAINMENT) in at least one SG.

b. Control feed flow to b. IF narrow range level in maintain narrow range any intact SG continues level between 4.0% to increase in an (34% FOR ADVERSE uncontrolled manrier , THEN CONTAINMENT) and 50% go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

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rubi-dVIK LUULUUWS UbihU ditAM DUMP EOF 35 ES-3.3 Page 5 Rev. 2  ;

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STEP ACTION / EXPECTED RESPONSE RESPONSC NOT OBTAINED l l

NOTE

1. Since ruptured SG(s) may continue to depressurize to less than the minimum RCS pressare necessary for '

continued RCP operation, cooldown to cold shutdown should be completed as quickly as possible, not to e~ceed 100 F/hr.

2. The Main S_ nam Isolation Valves Cooldown mode should be actuated for intact SG(s) when RCS temperature indicates approximately 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/HR

b. Dump steam to conuenser b. Manually OR locally dump

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from intact SG(s) steam to a mosphere.

's_,,/ IF no intact SG available, THEN use a faulted SG OR go to E0P 35 ECA-3.1, SGTR WITil LOSS OR REACTOR COOLANT -

SUBC00 LED RECOVERY DESIRED, Step 1.

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q t >- i 2( - POST-SGTR COOLDOWN USING STEAM DUMP E0P 35 ES-3.3 Page 6 }

Rev. 2 3

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CAUTICN {

j RCS and rupture SG(s) preasures srust be maintained less than the ruptured SG(s) ataospheric dump setpoint.

,6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Lealage

a. Perform appropriate action (s) from table RUPTURED SG(s) INCREASING DECREASING OFFSCALE VEL HIGH PZR LEVZL

<!7% -

Increase RCS Increase RCS Increase RCS j, (50% FOR ADVERSE Makeup Flow Makeup Flow Makeup Flow

CONTAINMENT)

AND AND i

i Depressurize Maintain RCS RCS Using And Ruptured Step 6b SG(s) Pressures Equal BETWEEN Depressurize Turn On Maintain RCS 17% (50% RCS Using PZR And Ruptured FOR ADVERSE Step 6b Heaters SG(s) Pressures CONTAINMENT) and 50% Equal BETWEEN 50% AND Depressurize Turn On Maintain RCS 73% (50% FOR ADVERSE RCS Using PZR And Ruptured l CONTAINMENT) Step 6b Heaters SG(s) Pressurew Equal f A_N,_D,,

i Decrease RCS Makeup Flow '

l 473% (50% FOR ADVERSE Decrease RCS Turn on Maintain RCS l CONTAINMENT) Makeup Flow PZR And Ruptured i Heaters SG(s) Pressures

Equal 1

l b. Use normal PZR spray b. IF letdown is in service,

per Step 6a. TITEN use auxiliary spray.

IF NOT, THEN use one PZR PORV.

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -

7 Check if RCS Cooldown should be stopped ,

a. RCS Temperatures a. Return to Step 3.

< 350'F (350*F FOR * '

ADVERSE CONTAINMENT)

b. Stop RCS cooldown NOTE If the following step, it is intended that the operator allow the ruptured SG to drain to a low narrow level and then refill it to a high narrow range level rather than continueusly feeding the ruptured SG to control level.

8  ; beck Ruptured SG(s) Refill ruptured SG to 82%

Narrow Range Level (60% FOR ADVERSE

> 4.0% (34% FOR ADVERSE CONTAINMENT) using feed flow.

CONTAINMENT) IF ruptured SG pressure d-creases in an uncontrolled ma T.n 0_R ruptured SG pressure ince asas to 1100 psig, THEN stop feed flow to ruptured SG.

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CAUTION Ruptured SG(s) pressure may decrease rapidly when steam is released. g NOTE Steam release from ruptured SG(s) may be stopped when RHR System is in service.

,9 Lump Steam From Ruptured Dump steam using ruptured SG(s) To Condenser SG(s) .Rmospheric dump.

10 Control RCS Makeup And Letdown To Maintain PZR Level

a. PZR level > 17% (50% a. Increase RCS makeup FOR ADVERSE CONTAINMENT) flow as necessary. Go to Step 11.
b. p2R level < 73% (50% b. Decrease RCS makeup

'~' flos as necessary.

FOR ADVERSE CONTAISMENT)

Go to Step 12.

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POSI-SGTR COOLDOWN USING STEAM DUMP E0P 35 ES-3.3 Page 8 Rev. 2

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STEP ACTION / EXPECTED RESPONSE PESPONSE NOT b5?AINED NOTE The' upper head region may void during RCS depressurization if RCPs are not rur.ning . This may result in a ranidly increasing PZR level.

11 Depressurize RCS To Minimize RCS-To-Secondary Leakage

a. Use normal PZR spray a. If letdown is in service, THEN use auxiliary spray.

IF NOT, THEN use one PZR PORV.

b. Turn ON PZR heaters as necessary
c. Maint 'n RCS pressure at ruptu. SG(s) pressure
d. Maintait ;S subcooling based on m ore exit TCs (s'--) > 30*F (90*F FOR ADVERGE CONTAINt1ENT) 12 Check If 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 23 q flow < .. y
b. STOP affected RCP(=)

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POSI-SGTR COOLDOWN USING STEN! DialP E0P 35 ES-3.3 Page 9 Rev. 2

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ACTIONiEXPECTED RESPONSE RESPONSE NOT OBTAINED

_ STt? l 13 Check If RHR System Can Be Placed In Cooldown Mode

a. Check RCS temperature a. Go to Step e.

< 350'F A_ND RCS preasure < 390 psia

b. Place Rl[R system in cooldown mode using CP 3208 PLANT C00LDOWN
c. Stop dumping steam from the l ruptured SG(s) 14 Continue RCS Cooldown To Col: Shutdown
a. Flaintain cooldswn rate in RCS cold legs

< 100 F/llR

b. Use RHR System

^' c. s'. cam to condenser

[ Dump c. Planually OR locally Q) f rom intaa SG(s) dump steam to atmosphere E no intact SG available and RHR NOT in service, TifEN use a faulted SG OR go to E0P 35 ECA-3.1, SGiR WITH LOSS OF REACTOR C00LAh T - SUBC00 LED RECOVERY DESIRED, Step 1.

15 Check RCS Temperatures Return to Step 8.

A@ RVLt!S llead TC's < 200*F 16 'laintain cold shutdown condttions '

-FINAL-(O) s

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FOLDOUT FOR E-3 SERIES PROCEDURE

1. SI REINITIATION CRITERIA Manually operate ECCS pumps as necessary and go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESliED, r Step 1, if EITHER condition listed below occurs
a. RCS subcooling based on core exit TCs < 30'F (90'F FOR ADVERSE  ;

CONTAlh?iENT) l

-OR- ,

b. PZR level - CANNOT BE MAINTAINED > 7.0% (50% FOR ADVERSE ,

CONTAIh?!ENT)

2. RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power > 5% .
b. CORE COOLING - Core exit TCs > 1200*F l
c. HEAT SINK - Narrow range level in all SGs < 4% (34% FOR ADVERSE l 4 CONTAINMENT) AND total feedwater flow < 525 gpm  !
d. INTEGRITY - Cold leg temperature decrease > 100*T in last 60 7 minutes AND RCS cold leg temperature < 252'F '
e. CONTAINMENT - Containment pressure > 60 psia ,
3. SECONDARY INTEGRITY CRITERIA Go to E0P 35 E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1 if any  ;

SG pressure is decreasing in an uncontrolled manner OR has O completely depre'ssurized, and has not been isolated, unless ne ded for RCS cooldown.  ;

4. COLD LEG RECIRCULATION SWITCHOVER CRITERION Go to E0P 35 ES-1.3, TRANSFER TO COLD LEG RECIRCULOTION, Step 1. if RWST level decreases to < 520,000 gallons.
5. AFV SUPPLY SWITC110VER CRITERION l Switch to alternate AFV water supply if DWST 1cvel decreases to .

. < 80,000 gallons. l

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