ML20205B510

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Rev 2 to Emergency Operating Procedure EOP 35 ES-3.1, Post-Steam Generator Tube Rupture Cooldown Using Backfill
ML20205B510
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-3.1, NUDOCS 8810260257
Download: ML20205B510 (8)
v • d • e


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Stephen E.

Mace' 3-31-87 87-12 Form Approved by Stat..n Superintendent Effective One 50RC Mtg. No.

4 1 STATION PROCEDURE' COVER SHEET

.Q nr A.

IDENTIFICATION Number: E0P 35 ES-3.1 Rev.

2

Title:

POST-SGTR C00LOOWN USING BACKFILL Prepared By: R. F. Martin B.

REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE.

OEPARTMENT H'EAD

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C.

SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents.

YES [ ]

NO [ T (17 yes, perform written USQ detarmination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED

_(Adverse environmental in. pact)

YES [ ]

NO ((

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 systelr.s which may indirectly affect safety system response.

YES ( )

NO [ [

(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 (g

(%

c.

PROCEDUREREQUIRESR0_Rd/50RCREVIEW (in addition to revi'ew, ite with a YES response must be documented in the R /50RC meeting minutes.)

YES ( g NO ( )

h SORC APPROVAL SORC Heeting Number J-9 7.Lo 7 G.

H.

APPROVAL AND IMPLEMENTATION

$ W,re is " reby approved, and effective on the da The attache nr^'"

s. n ff Ftation/ Service / Unit Superintendent Effective Date O

SF 301 Rev. 9 h![2gg0 {

3 Page 1 of 1 P

4 E0P 35 ES-3.1 Page 1 Rev. 2 i

I POST SGTR C00LDOWN USING BACKFILL h

Page.No.

Eff. Rev.

1-7 2

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POST-SGTR C00LDOWN USING BACKFILL E0P 35 ES-3.1 Page 2 Re'i. 2

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%s 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 through the ruptured SG tube into the RCS.

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 from a.

E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 39, if Director of Station Emergency Organization (DSEO) selects backfill method.

b.

E0P 35 ES-3.2, POST-SGTR C00LDOWN USING BLOWDOWN, Step 9, when blowdown is not available and Director of Station

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Emergency Organization (DSEO) selects backfill method.

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C'P5064 2 3 44

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L FUbi-db1M COULUUWN UblNU BACKilLL EOP 35 ES-3.1 Page J Rev. 2 I

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.m STEP ACTK)N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Foldout page should be open.

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 35 ECA-3.1, on core exit TCs > 30'F SGTR WITil LOSS OF j

(90*F FOR ADVERSE REACTOR COOLANT -

CONTAINMENT)

SLBC00 LED RECOVERY DESIRED, Step 1 PZR level > 7% (50% FOR ADVERSE CONTAINMENT)

/_s; b.

Restore power to isolation m-valves (32-2R-R5F, 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 RCS.

3 Verify Adequate Shutdown Margin a.

Sample RCS

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b.

Shutdown margin - ADEQUATE b.

Borate as necessary.

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1

POST-SGTR C00LDOWN USING BACKFILL E0P 35 ES-3.1 Page 4 Rev. 2

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STEP ACTION / EXPECTED MESPONSE PESPONSE 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 wide range SG 1evel 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 Check Intact SG Levels a.

Narrow range level a.

Maintain total feed

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

> 4% (34% FOR ADVERSE s

(/)

CONTAINMENT) in at least one SG.

b.

Coatrol feed flow to b.

IF narrow range level maintain narrow range in any ir. tact SG 1evel between 4%

continues to increase (34% FOR ADVERSE in an uncontrolled CONTAINMENT) and 50%

manner, THEN go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

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POST-SGTR C00LDOWN USING BACKFILL EOP 35 ES 3.1 Page 5 Rev. 2 l

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STEP ACTION / EXPECTED RESPONSE RESPONSF NT OBTAINED NOTE 1.

Since ruptured SG(s) may contir e to depressurize to less than the mi'nimum RCS pressure r.t assary for continued RCP operation, cooldown to cold shutot<n shoul/ be completed as quickly as possible, not to exceed '00*F/hr.

2.

The Main Steam Isolation Valves' cooldown mode should be actuated for intact SG(s) when RCS temperature indicates approximately 400*F to preclude foadvertent closure of these valves.

5 Initiate RCS Cooldown to Cold Shutdown a.

Maintain cooldown rate in RCS cold legs < 100 F/HR b.

Use RHR System if in service c.

Dump steam to condenser c.

Manually OR locally from intact SG(s) dump steam to atmosphere.

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)

IF no intact SG available

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and RHR NOT in service,

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THEN use a faulted SG OR--

l go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1.

NOTE In 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 rather than continuously feeding the ruptured SG to control level.

__ __6 Check Ruptured SG(s) Narrow Refill ruptured SG to 82%

Range Level > 4% (34% FOR (61% FOR ADVERSE CONTAINMENT) l ADVERSE CONTAINMENT) using feed flow.

IF ruptured SG pressure decreases in an uncontrolled manner OR ruptured SG pressure increases to 1100 psig, THEN stop feed flow to ruptured SG, Imv) 0%Mei in

POST-SGTR C00LDOWN USING BACKFILL E0P 35 ES-3.1 Page 6 Rev. 2 l

RESPONSE NOT OBTAINED STEP ACTION / EXPECTED RESPONSE 7

Control RCS Makeup Flow And Letdown To Maintain PZR Level a.

PZR )- -I > 17% (50%

a.

Increase RCS makeup l

FOR AuvERSE CONTAINMENT) f13w as necessary.

Go to Step 8.

b.

PZR level < 73% (50%

b.

Decrease RCS makeup j

FOR ADVERSE CONTAINMENT) flow as necessary.

Go to Step 9.

NOTE The upper head region may void during RCS depressurization if RCPs are not running.

This may result in a rapidly in reasing PZR level.

8 Depressurize RCS To Backfill From Ruptured SG(s) a.

Use normal PZR spray a.

IF letdown is in

(

i service, TifEN use auxiliary spray.

IF NOT, THEN use one PZR PORV b.

Turn ON PZR heaters as necessary c.

Maintain RCS subcooling based on core exit TCs

> 30'F (90 F FOR l

ADVERSE CONTAINMENT) 9 Check If RHR System Can Be Placed in Service a.

Check RCS, temperature a.

Go to Step 10.

< 250 F AND RCS pressure < 390 psit b.

Place RHR system in service using OP 3208 PLANT C00LD0b'N

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OPWAt 3 64

POST-SGTR C00LDOWN USING BACKFILL E0P 35 ES-3.1 Page 7 Rev. 2 t

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STEP ACTION /EXPCCTED RESPONSE RESPONSE NOT OBTAINED

___10 Check If RCPs Must Be Stopped a.

Check the following a.

Go to Step 11.

1) Number 1 seal differential pressure

'< 210 psid

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2) Number 1 seal return flow <.2 gpm b.

STOP affected RCP(s)

___11 Check RCS Temperatures AND Return to Step 3.

RVLMS Head T/C's < 200 F

___12 Maintain cold shutdown conditions

- FINAL -

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O P'K68 - 1 3 44

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