ML20215L703

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RCS Pressure Boundary Valves MOV-3-750 &/Or MOV-3-751 Leak Test, for Unit 3
ML20215L703
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 09/23/1986
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20215L688 List:
References
3-OST-041.17, 3-OST-41.17, NUDOCS 8706260151
Download: ML20215L703 (16)


Text

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f Florida Power & Light Company i

Turkey Point Nuclear Plant '

Unit 3 l

o i

3-OSP-041.17 '

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k

Title:

l RCS Pressure Boundary Valves MOV-3-750 and/or MOV-3-751 Leak Test Safety Related Procedure Responsible Department: Technicai l Reviewed by PNSC: 86-248 Approved by Plant Manager N: 9/23/86 RTS 86-1503P I'JAC dt em p AD 0 0 L

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%l[ Procedura No.: Procedurs

Title:

Page:

2

. RCS Pr:ssure Boundary Valves MOV-3-750 Approm Om:

3 OSP.041.17 and/or MOV-3-751 Leak Test 9/23/86 LIST OF EFFECTIVE PAGES Revision Page Date 1 09/23/86 2 09/23/86 3 09/23rJ6 4 09/23/86 5 09/23/86  ;

6 09/23/86 1 7 09/23/86 8 09/23/86 9 09/23/86 10 09/23/86 11 09/23/86 {

12 09/23/86 13 09/23/86 -

4 14 09/23/86 i 15 09/23/86 16 09/23/86 I

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Procidure No.: Procedure

Title:

Pagt:

. . 3-

.. RCS Pressuro Boundary Valves MOV 3 750 - Appro@ Data: l 3.OSP-041.17 . and/or MOV 3 751 Leak Test 9/23/86

- 1

- j TABLE OF CONTENTS l 1

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1 Section Page 1 1.0 PURPOSE ....................................... 4 f

2.0 REFERENCES

/ REFERENCES REQUIRED ................. 4 1

h' 3.0 PREREQUISITES ................................... 5 l 4.0 PRECAUTIONS / LIMITATIONS ......................... 5 5.0 SP ECI AL TOOLS /EQUIPM ENT . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6.0 ACCEPTANCE CRITERIA ............................. 6

( 7.0 PROCEDURE )

I' l l

7.1 MOV-3-751 Leak Test .............................. 7 l l

7.2 MOV-3-750 Leak Test .............................. 9 l 1

1 7.3 MOV-3-750 and/or MOV-3-751 Leak Test Restoration .......... 11  ?

l ATTACHMENTS:

Attachment 1 MOV-3-751 Leak Test Data Sheet ....... ............... 12 l l

L Attachment 2 l MOV-3-750 Leak Test Data Sheet .....................14 l Attachment 3 1

MOV-3-750 and/or MOV-3-751 Leak Test Restoration Verification . . . 16 I l

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M Proc dure No.: Procedure

Title:

P1g3:

. 4 RCS Pressurs Boundery Valves MOV 3 750 Approval Date:  ;

3 OSP-04L17 and/or MOV-3-751 Leak Test 9/23/88 j i

1.0l PURPOSE i This procedure provides instructions for performing leak tests on the RHR Loop 30 Suction Stop Valves, MOV-3-750 and MOV-3-751. These test shall be performed during Unit 3 heatup as directed by OP-0202.1, Reactor Startup - Cold Conditions to Hot Standby Conditions. This surveillance satisfies the requirements of reference 2.1.2 and 2.1.3, for the valves tested.

2.0 - REFERENCES / RECORDS REQUIRED 2.1 References l

2.1.1 Technical Specification -

- 1. Section 3.16 Reactor Coolant System Pressure Isolation Valves.

2. Section 4.17 Reactor Coolant System Pressure Isolation Valves. <

2.1.2 Technical Specification (Interim) Section 4.4.6.2.2, RCS Operational Leakage. t 2.1.3 Letter L-85 350, Revision to the Inservice Test Program for Pumps and Valves.

2.1.4 3-OP-050, Residual Heat Removal System.

2.1.5 OP-0202.1, Reactor Startup - Cold Conditions to Hot Str.ndby .

Conditions. ,

i' 2.2 Records Reauired 2.2.1 The date, time and section started and the date, time and section i completed shall be logged in the Reactor Control Operator (RCO) logbook. Also, any problems encountered while performing the ,

procedure should be logged (i.e., malfunctioning equipment, delays due to changes in plant conditions, etc.).  ;

2.2.2 Completed copies of the below listed section(s), enclosure (s) and/or i attachment (s) document the compliance with Technical Specification surveillance requirements and shall be transmitted to the Quality Control Department for review prior to being sent to Document Control for retention for the lifetime of the plant in accordance with Quality Assurance records requirements:  :

1. Section 7.0 l
2. Attachments 1,2 and 3 I'J AC/dt em

j'i Proctdur3 No.; Procsdure Titis: Pcg3; RCS Prsssurs Boundary Valves MOV-3 750 Approval Date:

3 OSP 041.17. and/or MOV 3-751 Leak Test -9/23/86:

2.2.3 Completed copies of the below listed section(s), enclosure (s)l and/or attachment (s) shall be retained in the Plant Supervisor - Nuclear's file until the next performance of that section, enclosure, or '

attachment.

1. None 3.0 PREREQUISITES 3.1 Performance of this procedure has been directed by OP-0202.1, Reactor Startup - Cold Conditions to Hot Standby Conditions.  !

3.2 Personnel who will perform this procedure have reviewed it and understand their responsibilities.

3.3 Technical Department personnel have calculated the maximum allowable leak rate from previous test data, and recorded it on Attachments 1 and 2.

3.4 The Plant Supervisor - Nuclear has authorized performance of this test.

4.0 PRECAUTIONS / LIMITATIONS 4.1 -All work performed in Radiation Controlled Areas shall be performed in accordance with the requirements of the Radiation Work Permit and the ALARA program.

4.2 The Plant Supervisor - Nuclear' shall be notified immediately. if any acceptance criteria is not met or any malfunction or abnormal conditions occur.

4.3 - If either MOV is declared inoperable due to this test Technical Specification Section 3.16 should be referred to for required actions.

4.4 All RCS and RHR ressure gauges used during the performance of this .

procedure shall have een calibrated within 18 months of the test date.

4.5 During the performance of this procedure it may be required to drain aressurized pipe lines containing high temperature radioactive water.

Insure that the lines are drained by use of a properly secured drain going to the containment sump or the waste hold up tank.

4.6 The differential pressure across each valve being tested shall be at least 150 psig throughout the test.

4.7 The observed leak rate shall be corrected to normal system pressure to obtain actualleak rate.

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1. J -

Procedur3 No.; Procedurs

Title:

pag 3;

. 6

... RCS Pressuro Boundcry Valves MOV.3 750 Approvsl Dat3:

3.OSP.041.17 and/or MOV.3 751 Leak Test 9/23/86 5.0 SPECIALTOOLS/ EQUIPMENT

. 5.1. Ty,gon tubing of sufficient length to reach floor drain from system attachment i point.

5.2 A graduated container 5.3 Stopwatch 6.0 ACCEPTANCE CRITERIA 6.1 MOV.3 750 and MOV.3 751 leak rates are considered acceptable if when tested with a minimum of150 psig differential pressure the:

6.1.1 Corrected leak rate is less than or equal to 1.0 GPM OR 6.1.2 Corrected leak rate is greater than 1.0 gpm but less than or equal to 5.0 gpm and the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

NOTE .

I l l Acceptance Criteria 6.1.2 can be calculated with the formula; l I L-P< Ef l 1 2 I I where; L = latest correctedleakage and, I l P = Previous correctedleakage. l_

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y .t Proc 9dur# NO.: Pr0Cedurg

Title:

Page:

. 7

.: RCS Pr ssuro Boundary Valves MOV-3 750 ApproM Osts:

3 OSP.041.17 and/or MOV.3 751 Leak Test 9/23/86 7.0 PROCEDUR'E 7.1 MOV-3-751 Leak Test INIT. Date/ Time Started:

7.1.1 Obtain permission from the Plant Supervisor - Nuclear to perform this test .

7.1.2 If an on shift Quality Control Inspector is available, notify prior to performing this test.

,._._._._._._._._._._._.,_.,_._._._._._._._._._._.)

I 1 RCS pressure shaII be maintained less than 515 psig during the performance of this l test to prevent auto closure of RHR Loop 3CSuction Stop, MOV-3-750. l t._._._._._._._._._._._._._._._._._._._._._._._.J 7.1.3 Verify that the RHR System has been removed from cooldown operation as per 3-OP-050, Residual Heat Removal System. l 7.1.4 Have Operations personnel unlock and close the following breakers:

1. 30615 MOV-3-750
2. 30720 MOV-3-862A j 7.1.5 Have Operations personnel place both RHR pump control switches in Pull to Lock, j J
1. RHR Pump A I
2. RHR Pump B 7.1.6 Have Operations personnel close the RHR Pump RWST Suction Stop, MOV-3 862A 7.1.7 Connect a piece of Tygon tubing at the RHR Recire Line Vent, .

3-7410, and route the tubing to a f oor drain. l l

7.1.8 Slowly open the RHR Recire Line Vent,3-741C to depressurize the l t line. I 7.1.9 When the line is depressurized, elevate the end of the tubing above the RHR Recire Line Vent,3-7410.

7.1.10 Place the end of the tubing in a graduated container to allow measuring ofleak rate.

7.1.11 Have Operations personnel open the RHR Loop 3C Suction Stop, MOV-3-750.

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[. , j '1 Procedur2 No : Procedure Titl2: Page:

8

.. . RCS Prsssure Boundcry Val res MOV 3 750 Approval Data:

3 OSP-041.17 '

and/or MOV 3 751 Leak Test- 9/23/86 INIT.

7.1.12 Record the following on Attachment 1, MOV-3-751 Leak Test Data Sheet: ,

1. Time test started '
2. RCS pressure
3. RCS temperature
4. RHR pressure
5. RCS/RHR AP i

(

7.1.13 After a leak rate is determined, or a minimum of 10 minutes, if no leakage.is noted, record the volume of leakage collected and time '

. collecting is stopped on Attachment 1.

7.1.14 Have Operations personnel close the RHR Loop 30 Suction Stop, MOV-3-750.

7.1.15 Return the loose tubing end to the floor drain. /

7.1.16 Determine and record the corrected leak rate for the RHR Loop 30 Suction Stop, MOV-3-751 by using the formula on Attachment 1.

7.1.17 If the RHR Loop 30 Suction Stop, MOV-3-750 requires leak testing perform Section 7.2. (N/A if MO V-3-750 is not to be tested) 7.1.18 If the RHR loop 30 Suction Stc.p, MOV-3-750 does not require leak testing at this time perform Section 7.3, to restore system alignment.

'!(/A if MOV-3-750 is to be tested) l i

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.1 Proc" dure No : Proc 3durs Titl@: page;

. 9

- RCS Prsssure Boundary Valves MOV-3 750 A@ rod Date: I 3 OSP 041.17_ and/or MOV 3-751 Leak Test 9/23/86 7.2. MOV-3-750 Leak Test  !

INIT.

7.2.1 Obtain permission from the Plant Supervisor - Nuclear to perform this test. i 7.2.2 If an on-shift Quality Control Inspector is available, notify prior to performing this test.

._._._._._._._._._._._.g3_._._._._._._._._._._.

I I RCS pressure shall be maintained less than 515 psig during the performance of this .

I test to prevent auto closure of RHR loop 3C Suction Stop. MOV-3 7S t. I l._._._._._._._._._._._._._._._.._._._._._._._.J 7.2.3 Verify that the RHR System has been removed from cooldown  ;

operation as per 3-OP-050, Residual Heat Removal System.  ;

7.2.4 Have Operations personnel unlock and close the following breakers:

1. 30731 MOV-3-751 1
2. 30616 MOV-3-862B 7.2.5 Have Operations personnel place or verify both RHR pump control switches in Pull to Lock.
1. RHR Pump A
2. RHR Pump B 7.2.6 Have Operations personnel close the RHR Pump RWST Suction Stop, MOV-3 862B

._._._._._._._._._._._.g3_._._._._._._._._._._.

I i Steps 7.2.6 and 7.2.7 may be marked N/A if their required action has already been l completed by performance of Section 7.1, I 1._._._._._._._._.._._._._._._._._._._._._._._.J l 7.2.7 Connect a piece of Tygon tubing at the RHR Recire Line Vent,3-7410, and route the tubing to a floor drain.

7.2.8 Slowly open the RHR Recire Line Vent,3 741C to depressurize the  !

line.

7.2.9 When the line is depressurized, elevate the end of the tubing above the RHR Recire Line Vent,3-7410.

7.2.10 Place the end of the tubing in a graduated container to allow measuring ofleak rate.

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Procidurs No : Procidure htle: Pag 3:

,. RCS Prsssura Bounde.ry Valves MOV 3-750 Approdosta:

3 OSP 041.17. and/orMOV 3 751 Leak Test 9/23/88

-enL INIT.

7.2.11 Open the RHR Loop 3C Suction Stop, MOV 3-751.

7.2.12 Record the following on Attachment 2, MOV-3-750 Leak Test Data Sheet:

1. Time test started
2. RCS pressure
3. RCS temperature-
4. RHR pressure
5. RCS/RHR AP 7.2.13 After a leak rate is determined, or a minimum of 10 minutes, if ao leak rate is noted, record the volume of leakage collected and time collecting is stopped on Attachment 2.

7.2.14 Close the RHR Loop 3C Suction Stop, MOV-3-751.

7.2.15 Return the loose tubing end to the floor drain.

.7.2.16 Determine and record the corrected leak rate for MOV-3-750 by using the formula on Attachment 2. 1 7.2.17 Restore system alignment by completing Section 7.3.

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Procedurs No : Procedure

Title:

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11 RCS Pressura Boundary Valves MOV-3-750 Appro@ Dau: l 3 OSP 041.17 and/or MOV 3 751 Leak Test 9/23/86 h J

7.3 MOV-3-750 and/or MO'V-3-751 Leak Test Restoration INIT.

7.3.1 Close the RHR Recire Line Vent,3 7410. ,

7.3.2 Remove the tubing and replace the cap on the RHR Recire Line Vent, 3 741C 7.3.3 Open or verify open the following valves.

1. RHR Pump RWST Suction Stop, MOV 3-862A  !
2. RHR Pump RWST Suction Stop, MOV-3 862B 7.3.4 Place both RHR pump control switches in AUTO.
1. RHRPump A
2. RHR Pump B 7.3.5 - Open and lock or verify open and locked the following breakers:
1. 30731 MOV-3-751
2. 30615 MOV-3-750
3. 30720 MOV-3-862A ,
4. 30616 MOV-3-862B {

l 7.3.6 Perform independent verification of system restoration by (

completing Attachment 3, MOV-3-750 and/or MOV-3-751 Leak Test Restoration Verification.

7.3.7 Notify the Plant Supervisor - Nuclear that the Leak test of i MOV-3-750 and/or MOV 3 751 is com any problems or abnormal conditions.plete and inform Ensure these conditions the are PS-N o noted on the associated attachment.

7.3.8 Verify all log entries specified in Section 2.2 have been recorded.

Date/ Time Completed: l PERFORMED BY (Print) INITIALS  !

i REVIEWED BY-Plant Supervisor - Nuclear or SRO Designee END OF TEXT I ') A C d'sem 1

Procedure No : Procedure

Title:

Pege; 12 n RCS Pressuro Boundary Valves MOV-3 750 Approw oate:

3 OSP 041.17 and/or MOV 3 751 Leak Test 9/23/86

._ l ATTACHMENT 1 (Page 1 of 2)

MOV-3-751 LEAK TEST DATA SHEET Ref Step No. Data Required 7.1.12 Time test started .

RCS pressure esig RCS temperature 'F RHR pressure psig RCS/RHR AP osig (Acceptance Criteria)

(150 psig minimum )

7.1.13 Leakage collected ml Stopwatch MTE No.

Time test stopped Cal Date Total test time mins d 1

7.1.15 MOV-3-751 Leak Rate Calculation ml(collected) = gals (collected) l 3785.43 ml/ gal I

cals (collected) = epm at test pressure i mins (total test time)

Leak rate corrected to 2235 psig:

2235 osig x Leak Rate at = GPM osig(Test AP) test pressure Corrected Leak Rate Acceptance Criteria:

GPM Maximum as determined Calculation Independent Verification by Tech Dept.

Performed By: Date OJ AC.4% em

Procedure No.: Proc @ dure Trtl@: Pig 3:

13

.' RCS Pressurs Boundary Valves MOV.3 750 Approvai osta: 1 3 OSP 041.17 and/or MOV 3-751 Leak Test '

9/23/86 l l

ATTACHMENT 1 l (Page 2 of 2)

MOV-3 751 LEAK TEST DATA SHEET I l Remarks:

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l Test Performed by: Date l l

Date

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Test and Data Reviewed by: Date Plant Supervisor Nuclear 1

4 Evaluation Completed by: Date QC Reviewed by: Date  !

QC Surveillance Technician l l

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-. j ProcIdure No,: Procedure

Title:

Pcge:

14 1 RCS Prsssura Boundary Valves MOV 3 750 Approvai osta:

l l 3 OSP 041.17 and/or MOV 3-751 Leak Test 9/23/86 l

l l

ATTACHMENT 2 l l (Page 1 of 2) i MOV 3 750 LEAKTEST DATA SHEET 1

l Ref Step No. Data Required 7.2.12 Time test started )

l RCS pressure osig RCS temperature F i I

l RHR pressure asig RCS/RHR AP usig (Acceptance Criteria)

(150 psig minimum )

ml 7.2.13 Leakage collected gwgh S

Time test stopped Cal Date Total test time mins .j i

7.2.16 MOV-3-750 Leak Rate Calculation i ml(collected) = cals(collected) 3785.43 ml/ gal {

l gals (collected) = Epm at test pressure i mins (total test time)

Leak rate corrected to 2235 psig:

2235 psig x Leak Rate at = GPM psig(Test AP) test pressure Corrected Leak Rate l Acceptance Criteria: )

GPM Maximum as determined Calculation Independent Verification by Tech Dept.

Performed By: Date 1

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Procedure No.: Procedure Titt3: Page:

- - RCS Pressurs Boundary Valvss MOV 3 750 Approvu osta:

3 OSP 041.17 and/or MOV 3 751 LeakTest 9/23/86 ATTACH 5fENT 2 (Page 2 of 2) -

MOV 3-750 LEAK TEST DATA SHEET Remarks:

Test Performed by: Date l Date Test and Data Reviewed by: Date Plant Supervisor -Nuclear Evaluation Completed by: Date QC Reviewed by: Date QC Surveillance Technician i

1 4')AC hem t

Proctdure No : Proc durs

Title:

Page:

16

, RCS Pressuro Boundary Valves MOV 3 750 Approw oce:

3 OSP 041.17 and/or MOV-3 751 Leak Test 9/23/86 ATTACHMENT 3 (Page 1 of1)

MOV 3 750 and/or MOV-3-751 LEAKTEST RESTORATION VERIFICATION l

Component Required Ind. Ver.

No. Component Description Position (Initials)

RHR Pump A Control Switch AUTO RHR Pump B Control Switch AUTO VALVES CLOSED 3 741C RHR Recire Line Vent and CAPPED MOV-3-750 RHR Loop 3C Suction Stop CLOSED MOV-3-751 RHR Loop 3C Suction Stop CLOSED MOV-3-862A RHR Pump RWST Suction Stop OPEN MOV-3 862B RHR Pump RWST Section Stop OPEN BREAKERS 30731 MOV-3 751 LO OF 30615 MOV-3-750 LO D 30720 MOV-3-862A LO OF 30616 MOV-3-862B LOC D Op Remarks: I l

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Independent Verification i f Performed by: Date f l

l Reviewed by:

! Plant Supervisor - Nuclear or Designee Date FINAL PAGE O

JACat 94i l