ML20215L824

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RCS Pressure Boundary Check Valves 4-874A & B Leak Test, for Unit 4
ML20215L824
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
4-OSP-041.19, 4-OSP-41.19, NUDOCS 8706260186
Download: ML20215L824 (11)
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. 1 FloridaPower & Light Company Turkey Point Nuclear Plant Unit 4  !

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j 4-OSP-041.19 l

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i Title _:  !

R.CS Pressure Boundary Check Valves j 4-874A and B Leak Test - 1 Safety Related Procedure Responsible Department: Technical Reviewed by PNSC: 86-248 Approved by Plant Manager-N: 9/23/86 i l

RTS 86-1503P

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T' i ff Procidur3 No.; Procedure

Title:

Pagt:

4 1 RCS Pressuro Boundary Check Valves . Approval Date:

4 OSP-041.19 4 874A and B Leak Test 9/23/88 i

LIST OF EFFECTIVE PAGES l i

Revision l Page Date i 1 09/23/86 2 09/23/86 l 3 09/23/86  :

4 09/23/86 l 5 09/23/86 6 09/23/86 l

7 09/23/86 8 09/23/86 9 09/23/86 10 09/23/86 11 -09/23/86 l

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Procedure No.: Procedure Titta: Paga:

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"' . RCS Pressure Boundary Check Valves Appro@ Oats; 4 874A and B LeakTest 4.OSP 041.19 9/23/86

~~1 TABLE OF CONTENTS l

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Section Page 1.0 : PURPOSE ....................................... 4 1

2.0 REFERENCES

/ RECORDS REQUIRED . . . . . . ,. . . . . . . . . . . . . . .

4 1 1

3.0 PREREQUISITES ................................... 5 1 4.0 PRECAUTIONS / LIMITATIONS ......................... 5 J 5.0 SPECIAL TOOLS / EQUIPMENT ........................ 6 6.0 ACC E PTA NC E C R ITE RI A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6  :

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7.0 PROCEDURE

7.1 Check Valves 4-874A and B Leak Test .................... 7 I

ATTACHMENT:

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_ ttachment1 4-874A and B Leak Test Data Sheet .................... 10 9

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. 1 RCS Pressuro Boundary Chsek Valve) Approval Date:

4 OSP 041.19 4 874A and B Leak Test 9/23/86 1.0 PURPOSE'

- This procedure provides instructions for performing leak testing of RCS pressure l boundary check valves 4-874A and B . This test shall be performed during Unit 4. l heatup as directed by OP-0202.1, Reactor Startup - Cold Conditions to Hot Standby i

. Conditions. This surveillance satisfies the requirements of reference 2.1.1 and  !

2.1.2, for the valves tested.

2.0 REFERENCES

/ RECORDS REQUIRED ]

1 2.1 References I 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 2.1.3 .OP-0202.1, Reactor Startup - Cold Conditions to Hot Standby Conditions 2.2 Records Reauired  !

2.2.1 The date, time and section started and the date, time and section  !

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, celays ,

due to changes in plant conditions, etc.).

2.2.2 Completed copies of the below listed section(s), enclosure (s) and/or 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
2. Attachment 1 2.2.3 Completed copies of the below-listed section(s), enclosure (s), 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
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A 1 Procedurs No.: Proc $ dure Titla: Pagt:

' RCS Prsssura Boundary Chsck Valves approm oat.- <

4.OSP.041.19 . 4-874A and B Leak Test 9/23/86

._ l 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 Attachment 1.

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 Stipervisor - Nuclear shall . be notified immediately if any acceptance criteria is not met or any malfunction or abnormal condition occurs.

4.3 If any' check valve is declared inoperable due to the test, Technical

. Specification Section 3.16 should be referred to for required actions.

l 4.4 All' RCS and test pressure gauges used during the performance of this 4 procedure shall have been cali 3 rated 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. 1 Insure that the lines are drained by use of a properly secured drain going to j the containment sump or the waste hold up tank. 1 1

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

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

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Procedure No.: Procedura Titl@: Pagg:

RCS Pressure Boundary Check ValvGs ApprovM oate: l l '4.OSP.041.19 ' 4 874A and B Leak Test 9/23/88 '

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5.0 SPECIALTOOLS/ EQUIPMENT 5.1 Plastic bag or container to collect leakage at system drain point.

5.2 A graduated container

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a 5.3 Stopwatch i 6.0 ACCEPTANCE CRITERIA 6.1 Check valve 4-874A and B leak rates are considered acceptable if when tested l with a minimum of150 psig differential pressure the:

6.1.1 Corrected leak rate is less than or equal to 1.0 gpm l

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 rneasured 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.

t*~'~ ~ ~ ~ ~'~'~'~'~'~ ~ ~ ~=~'~ ~'~ - - ~ ~

.- NOTE ~'s.

I 1 l Acceptance Criteria 6.1.2 can be calculated with the formula; l

l LP< S-L I I 2 i I where; L = latest correctedleakage and, I l P = Previous correctedleakage. l

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Procedure No.: Proc $durs Tit le: Page:

RCS Prcssurs Boundcry Ch:ck Valves Approval DatE 4-OSP 041,19 4 874A and B Leak Test 9/23/86

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7.0 PROCEDURE 7.1 Check Valves 4-874A and B Leak Test INIT. Date/I'ime 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 i performing this test. '

7.1.3 Place test gauge PI-4-6341 in service by opening the following:

1. PI-4-6341 Root Valve,4-941C
2. PI-4-6341 Isol Valve,4-868G 7.1.4 Read and record the followingdata:
1. RCS pressure esig
2. Pressure indicated on PI-4-6341 osig
3. RCS/PI-4-6341 AP _

osig 7.1.5 If AP is less than 150 psig reduce upstream pressure by venting at RHR Drain 4-941D until AP is 150 psig or greater. (N/A if ventingis not required.)

7.1.6 Record the following on Attachment 1,4-874A and B Leak Test Data Sheet:

1. Time test started
2. RCS Pressure
3. PI-4-6341 indicated pressure
4. RCS/PI-4-6341 AP
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Procedure No.: Procedurs Titi@: Paga:

RCS Pressurs Boundcry Ch:ck Valves approm o.te: )

4.OSP.041.19 4 874A and B Leak Test 9/23/86 j 1

INITI A LS il CK'D VERIF.

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Once test is started all fluid vented from system to maintain AP greater than ISO psig .

I shall be collected for measuring and determining leak rate. I

(.........._.........-....'...I 7.1.7 Monitor pressure indicated at PI-4-6341, venting to the collection container as necessary to maintain AP greater than 150 psig. )

7.1.8 After a leak rate is determined or a minimum of 10 minutes, if no leakage is noted, record the following on Attachment 1:

1. Time test stopped
2. RCS pressure
3. PI-4-6341 indicated pressure
4. RCS/PI-4-6341 AP
5. Volume ofleakage collected l

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NOTE .

I I l Totalleakage coIIected will be assigned to each valve tested.

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7.1.9 Determine and record the corrected leak rate by using the formula on Attachment 1.

7.1.10 Remove test gauge PI-4-6341 from service by closing the following:

1. PI-4-6341 Root Valve,4-941C
2. PI-4-6431 Isol Valve,4-868G 7.1.11 Notify the Plant Supervisor . Nuclear that the RCS check valve leak test is complete and inform the PS-N of any problems or abnormal conditions. Ensure these conditions are noted in the associated attachment.

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Procedure No.: Procedure Titla: Paga:

. . 9 RCS Pressurs Boundcry Check Valves ApprovalDate:

4 OSP 041.19 4 874A and B Leak Test 9/23/86 i

INIT. '

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

Date/ rime Completed:

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PERFORMED BY (Print) INITIALS i

REVIEWED BY: .

Plant Supervisor - Nuclear or SRO Designee i

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END OF TEXT

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4 1 Proc: dura No : Prociduro Titl@ Page:

RCS Prsssura Boundary Chcck Valves Approve oate:

4 OSP 041.19 4 874A and B Leak Test 9/23/86 ATTACHMENT 1 l (Page 1 of 2) l 4-874A AND B LEAK TEST DATA SHEET i i

Ref. Step No. Data Required 7.1.6 Time test started Stoowatch MTE No.

RCS pressure osig CalDate PI-4-6341 Cal Date PI-4-6341 pressure psig AP usig (Acceptance Criteria)

(150 psig minimum ) ,

7.1.8 Time test stopped RCS pressure osig PI-4-6341 pressure esig AP osig (Acceptance Criteria) l (150 psig minimum) ,

. Leakage collected ml '

Total test time mins 7.1.9 4-874A and B Leak Rate Calculation ml(collected) = cals (collected) 3785.43 ml/ gal gals (collected) = gpm at test pressure mins (total test time)

Leak rate corrected to 2235 psig:

2235 psin 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

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Procedura No : Proc' dure

Title:

Pag g; RCS Pressura Boundary Check Velves ^pp**' oat *:

4 OSP.041.19 4 874A and B Leak Test 9/23/86 ATTACHMENT l' t (Page 2 of 2) 4 874A AND B LEAKTEST DATA SHEET Remarks:

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l Test Performed by:

Date Date .

Test and Data Reviewed by: Date Plant Supervisor -Nuclear .

Evaluation Completed by: Date QC Surveillance Technician FINAL PAGE i

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