ML20205C773

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Rev 2 to Emergency Operating Procedure EOP 35 FR-I.3, Response to Voids in Reactor Vessel
ML20205C773
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-FR-I.3, NUDOCS 8810260571
Download: ML20205C773 (13)
v • d • e


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Stephen E. v e9 3-31-87 87-12 Form Appr;v:d by Stat'..n Sup;rint:ndent Effective 0. ] 50RC Mtg. No.

STATION PROCEDURE COVER SHEET

/h A. IDENTIFICATION U

Number: E0P 35 FR-I._3 Rev. 2 i

Title:

ESPONSE TO VOIDS IN REACTOR VESSEL Prepared By: H. K. COVIN B. _ REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD G//

C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO [ 4 (If yes, perform written USQ determination and Safety l Evaluation, and contact Manager, Safety Analysis Branch to

  • determine need for Integrated Salety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO [ 7

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 which may indirectly affect safety system response. YES [ ] NO [-]

(If yes, perform written Safety Evaluation snd i contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO[Y F. PROCE9UPE REQUIRES ORC REVIEW (In addition to review, it with a YES response /

must be documented in th PO /SORC meeting minutes.) YES [d NO [ ]

G. hSORCAPPROVAL SQRC Meeting Number L y 7- ///7 H. APPROVAL AND IMPLEMENTATIC'N The attached to ei reby approved, and effective on the date below:

_ _- dlll' - # - / [ '

Station / Service / Unit Superintendent Effective Date

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SF 301 Rev. 9 Page 1 of 1 8810260571 00100723 i PDR ADOCK 050 P

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E0P 35 FR-I.3 Page 1 )

. Rev. 2 I

RESPONSE TO VOIDS IN REACTOR VESSEL l

Page No. Ef f. Rev. l 1 1-10 2 Attachment A 2 l t

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ntsrvNsE TO VOIDS IN REAGTOR VESSEL E0P 35 FR-I.3 Pags 2 Rev. 2

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A. PURPOSE This procedure provides actions to respond to voids in the reactor  !

vessel head.

6 B. ENTRY CONDITIONS This procedure was written for Modes 1, 2, 3, and 4 assuming SI has been terminated. Using this procedure when not in these modes 1

requires a step by step evaluation to determine if the required action is still 9plicable to current plant conditions.

This procedure is entered from E0P 35 F-0.6, INVENTORY Critical Safety Function Status Tree on a YELLOW condition. l 4

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OP9004 7 3H a

O RESPONSE TO VOIDS IN REACTOR VESSEL EOP 35 FR-1.3 Pags 3 Rev. 2

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STEP ACTION /EMPECTED RESPONSE RESPONSE NOT OSTAINED ,

CAUTION 6

If a controlled natural circulation cooldown is in progress and a void in the reactor v-ssel upper head is expected, this procedure should not be performed.

~ r 1 Check If SI Has Been Return to procedure and step in .

Te rminated effect.

SI pumps - ALL STOPPED

a. Charging Pump to ,

Cold Les Injection , i Valves - CLOSED  ;

2 Check If Charging Flow Has Been Established I

a. Verify Recire a. Establish Recirc Flowpath i Flowpath - ESTABLISHEb

! O b. Charging pump -

AT LEAST ONE RUNNING

b. Perform the following i
1) IF RPCCW flow to RCP thermal barriers is 4

lost, THEN isolate ,

seal injection to affected RCP before starting charging pump. *

2) Start one charging  !

4 Pump, t 3) IF seal injection was ,

, isolated THEN

)

I resture seal .

j injection to RCP's '

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, c. Instrument Air to c. Establish instrument air i Containment - ESTABLISKED to containment. (

1) One instrument air r compressor running j
2) OPEN instrument air ,

i containment isolation  !

valves l

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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Paga 4 Rev. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO

d. Charging flow - d. Establish Normal ES TABLISHED charging flow IF charging can NOT be established, THEN establish excess letdown as per OP 3304A, CHARGING AND LETDOWN Go to Step 4.

3 Check Letdown - IN Ests;blish letdown SERVICE Ir, letdown can NOT be established, THEN establish excess letdown as per OP 3304A, CHARGING AND LETDOWN, ,

4 Establish Stable RCS Conditions

a. PZR level - STABLE a. Control charging and AND BETWEEN 40% AND letdown as necessary.

60%

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() b. RCS pressure - STABLE b. Turn on PZR heaters and use normal PZR spray as necessary. IF normal

]

spray NOT available and letdown in service, THEN use auxiliary spray.

1 i c. RCS hot leg c. Dump steam as necessary.

temperatures - ST/BLE f, 5 Check RCPs - ALL STOPPED Go to Step 12.

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OP$0641 344

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i KE5rvNst TO VOIDS IN REAGTOR VESSEL EOP 35 FR-I.3 Pogs 5 l Rev. 2 fi STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OOTAINED 6 Check If RCS Pressure Should Be Increased l

a. Pressure - AT LEAST s. Go to Step 9,  ;

100 psi < TECH SPEC f LIMIT on Figure 3.4-3 l

b. Pressure < 1850 psia b. Go to Ster 4. l (2120 psia FOR  !

ADVERSE CONTAINMENT)

c. Turn on PZR heaters to increase RCS pressure 50 psi  ;

7 Control Charging And Letdown As Necessary To ,

Maintain PZR Level .

>17% (50% FOR  ;

ADVERSE CONTAINMENT)

NOTE i Several increases of pressure may be necessary before RVLMS will ,

I i actually indicate level is increasing in the head.

1  !

% 8 Check RVLMS head AND plenum ,

level indication l

a. Indication - INCREASING a. Go to Step 9. i l
b. Head AND plenum - 100% b. Return to Step 6.

i l c. Turn off PZR heaters 6 i as necessary to stabilize RCS pressure l

d. Return t; procedure and

, step in effect l

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w RESPONSE TO VOIDS IN REACTOR VESSFL E0P 35 FR-1.3 Psge 6 Rev. 2 r

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STEP ACTION /EXPECTIO RESPONSE RESPCNSE NOT 09TAINGO CAUTION If seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation.

NOTE l,

RCPs should be run in order of priority (2, 1, then 3 or 4) to provide normal PZR spray.

9 Try To Start One kCP e

a. Establish the following a. IF conditions can NOT conditions prior to RCP be established, THEN start go to Step 12.
1) PZR level >90%

(90% FOR ADVERSE

[

CONTAINMENT)

2) RCS subcooling based O- on core exit TCs

>70*F (125'F FOR ADVERSE CONTAINMENT)

3) Prepare RCP for operation as per OP 3301D, REACTOR COOLANT PUMP OPERATION,
b. Start one RCP 10 Check RVLMS head AND Go to Step 12.

plenum level - 100%

  • 11 Go To Step 21 12 Determine containment hydrogen Obtain a containment hydrogen concentration per OP 3313A, concentration measurement ilYDROGEN RECOMBINERS, with the Post Accident HYDROGEN MONITORS AND Sampling System RECOMBINER BLDG VENTILATION O

OPD004-1 S-84

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nzsrunss To volus IN REALTUR VE5YET. E0P 35 FR*I.3 Pags 7 l Rev.'2 '

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STsP ACTION /EXPECTIO RESPONSE RESPONSE NOT OSTAINED CAUTION Following block of automatic SI actuation, manual SI act.uation may be required if .

conditions degrade.

13 Check If Low P2R Pressure SI Can Be Blocked

a. P7R pressure <1950 psia a. Decrease P~' 'jres su re to <1950 r 6 using normal P2
  • pray. IF normal ar-ay NOT l

avai}ableandletdown in service, THEN use  !

auxiliary spray. IF l NOT, THEN use one PZR l PORV.

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b. Block Low PZR Pressure SI 14 Record RCS Pressure psia  !

15 Establish Following RCS Conditions

a. PZR level - STABLE a. Control charging and AND BETWEEN 40% AND letdown as necessary.

60%

b. RCS pressure - STABLE b. Turn on PZR heaters and ,

use normal PZR spray as [

nece s s a ry. IF normal l spray NOT available and (

letdown in service, THEN i use auxiliary spray. [

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c. RCS subcooling based c. Dump steam as necessary.

l on core exit TCs  !

>80*F (140*F FOR j j ADVERSE CONTAINMENT)

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d. RCS hot leg tempera- d. Dump 2 35- as necessary. [

j tures - STABLE [

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RESPONSE TO VOIDS IN REACTOR VESSEL EOP 35 FR-1,3 Peg 2 8 Rev. 2 i

(D STEP ACTION /tKPECTED RESPONSg MESPONSE NOT OSTAIN80

__16 Prepare for Reactor Vessel l Venting

a. OPEN both Rx Vessel a. IF either valve in one Head Vent Isolation train fails to open valves (one Train THEN close both valves only) and open both valves in other train.
b. IF PRT not available, '

THEN consult with Director of Station Emergency Organization t (DSEO) l NOTE The following step is completed in case.a PRT rupture disc fails while venting the Rx vessel to the PRT.

17 Determine Maximum Allowable Venting Time

a. Containment hydrogen a. Decrease hydrogen O- concentration <3% concentration by operating H l

2  !

recombiners per OP 3313A, NYDROGEN  !

RECOMBINERS AND  ;

RECOMBINER BUILDING

b. Refer to ATTACHMENT  !

A to determine [

maximum venting time .

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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Page 9 Rev. 2 s -

STEP ACTIOM/tXPECTRO RESPONSE RESPONSE NOT 08TAINE0 18 Review Reactor Vessel Venting Termination Criteria

a. RCS su'> cooling based on core exit  !

TCs <30*F (90'F FOR l  !

ADVERSE CONTAINMENT) l 1

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b. PZR level <17% (50%  !

FOR ADVERSE CONTAINMENT) l.

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c. RCS pressure - DECREASES ,

, B)' 200 psi .

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d. Venting time - GREATER t i

THAN MAXIMUM TIME l CALCULATED IN STEP 17 i (IF a PRT rupture disc

, has failed)

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e. RVLMS head and plenum I level - 100% [

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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Paga 10 Rev. 2

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RESPONSE NOT OSTAIN80

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STEP ACTION /EXPEi:TSO RESPONSE '

CAUTION Venting should be stopped if any venting termination criterion in Step 18 is exceeded.

19 Vent Rx Vessel

a. Throttle OPEN one a. IF one valve fails to Rx Vessel Head Vent open THEN throttle OPEN Controller other valve.

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b. Any vaating termin- b. Cont}nue venting. WHEN" ation criterion - any venting termination EXCEEDED criterion is exceeded.

THEN go to Step 19c.

c. CLOSE all Vent Valves O _ 20 Check RVLMS head AND plenue level - 100%

'ncrease RCS pressure to value

.acorded in Step 14.

to Step 12, Return 21 Check PZR Level - STABLE Control charging and letdown as necessary.

22 Return To Procedure And Step In Effect

-FINAL-O OPK6M 344

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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Pega 1 of 1 Rev. 2

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O ATTACHMENT A INSTRUCTIONS FOR DETERMINING VENTING TIME

1. Determine Containment Volume at STP = A P 492*R 6 3 A = (2.26 x 10 gg ) x 14.7 psia x T where: P (psia) = Containment pressure (psia)

T (degrees R) = Containment temperature (degrees F) + 460

2. Determine Mtximum Hydrogen volume that can be vented = B (3.0% - Containment Hydrogen Concentration) x A B= 100%
3. Determine Hydrogen flow rate as a function of RCS pressure = C
a. Check RCS pressure,
b. Using OPS FORM E0P 35 FR-I.3-1, read hydrogen flow rate. l
4. Calculate maximum venting time:

Maximum venting time = B C

O OP9004 2 344

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FORM APPROVED BY LTNI'T 3 SUPERINTENDENT

&/a/a EFFECTIVE DATE 3-871vr PORC MTG NO 1

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