ML20215L819
| ML20215L819 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/23/1986 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20215L688 | List: |
| References | |
| 3-OSP-041.19, 3-OSP-41.19, NUDOCS 8706260184 | |
| Download: ML20215L819 (11) | |
Text
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Florida Power & Light Company J
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Turkey Point Nuclear Plant
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Unit 3 l
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J 3-OSP-041.19 i
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Title:
.RCS Pressure Boundary Check Valves 3-874A and B Leak Test Safety Related Procedure Responsible Department:
Technical Reviewed by PNSC:
86-248 Approved by Plant Manager-N:
9/23/86 RTS 86-1503P 6 JAC/dt/em 0-87062601B4 870623 PDR ADOCK 05000250 P
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Procedure No.:
ProcIdure Titl3:
Page:
s, -
RCS Pressure Boundery Check Approval Date:.
3.OSP 041.19 Valves 3 874A and B Leak Test 9/23/86 LIST OF EFFECTIVE PAGES '
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Revision Page Date I
1 09/23/86 2
09/23/86 3
09/23/86 4
09/23/86 I
5 09/23/86-6 09/23/86 7
09/23/86 8
09/23/86 9
09/23/86 10 09/23/86 11 09/23/86 i
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- p Procedure No.:
Procedura Titt3; Pige:
g.
RCS Pressura Boundary Check AppronWate:
3.OS P.041.19 Valves 3 874A and B Leak Test 9/23/86
. TABLE OF CONTENTS i
Section Page 1.0 PURPOSE 4
2.0 REFERENCES
/ RECORDS REQUIRED.....................
4 4
]
3.0 PREREQUISITES 5
q 4.0 '.
PRECAUTIONS / LIMITATIONS 5
5.0 SPECIALTOOLS/ EQUIPMENT
........................6 i
6.0 A C C E PTA NC E C R ITE R I A..............................
6 j
7.0 PROCEDURE
q 7.1 Check Valves 3-874A and B Leak Test 7
ATTACHMENT: ~
3-874A and B Leak Test Data Sheet 10 I
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ProCtdure No :
Procedure
Title:
Page:
RCS Prsssurs Boundcry Chack Appr0M Date:
' 3.OSP-041.19 Valves 3 874A and B Leak Test
.9/23/86 s
i 1.0 PURPOSE.
This procedure provides instructions for performing leak testing of RCS pressure boundary check valves 3-874A and B. This 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 2.1.1 and 2.1.2, for the valves tested.
2.0
_ REFERENCES / RECORDS REQUIRED j
2.1 References l
2.1.1 Technical Specification l
1.
Section 3.16, Reactor Coolant System Pressure Isolation Valves i
2.
Section 4.17, Reactor Coolant System Pressure Isolation Valves l
1 2.1.2 Technical Specification (Interim) Section 4.4.6.2.2, RCS Operational Leakage j
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) i logbook. Also, any problems encountered while performing the l
procedure should be logged (i.e., malfunctioning equipment, delays due to changes in plant conditions, etc.).
enclosure (s) and/or 2.2.2 Completed copies of the below listed section(s),hnicalSp attachment (s) document the compliance with Tec I
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 l
Quality Assurance records requirements-1.
Section 7.0
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- 2.
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 perfctmance of that section, enclosure, or attachment.
1.
None l
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Procedyr3 No.:
Proctdure Titt3:
Pagt:
RCS Pressurs Boundary Check Approni Dm:
j 3 OSP 041.19
-Valves 3 874A and B Leak Test 9/23/86 i
3.0 PREREQUISITES 3.1 Performance of. this procedure has been directed by OP-0202.1, Reactor
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Startup - Cold Conditions to Hot Standby Conditions.
3.2 Personnel who will perform this procedure have reviewed it and understand their responsibilities.
j 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 l
4.1.All work performed in Radiation Controlled. Areas shall be performed in accordance with the requirements of the Radiation Work Permit and the q
ALARA program.
4.2 The Plant Supervisor - Nuclear shall ba notified immediately if any acceptance criteria is not met or any malfunction or abnormal condition -
- occurs, t
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.
4.4 All RCS and test pressure gauges used during the performance of this -
procedure shall have been calibrated within 18 months of the test date.
4.5 During the performance of this procedure it may be reguired to drain
?ressurized pipe - lines containin high tempcrature, radioactive water.
2nsure that the lines are drained use of a pro the containment sump or the waste old up tank. perly secured drain goin 4.6 The differential pressure across each valve being tested shall be at least 150 -
i psig throughout the test.
4.7 The observed leak rate shall be corrected ^o normal system pressure to obtain actualleak rate.
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Procedur3 No :
Procedure
Title:
Page:
6 s
RCS Pressure Boundery Chrck Apprmi oste:
3.OSP.041.19 Valves 3 874A'and B Leak Test
- 9/23/86-
-1j 5.0 S_PEC! ALTOOLS/ EQUIPMENT i
5.1_ Plastic bag or container to collect leakage at system drain point.
5.2 A graduated container 5.3 Stopwatch j
6.0 ACCEPTANCE CRITERIA 6.1' Check valve 3-874A and B leak rates are considered acceptable if when tested with a minimum of150 psig differential pressure the:
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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 i
determined by the previous te.st by.an amount that reduces the margin between measured leakage rate and the maximum i
permissible rate of 5.0 gpm by 50% or greater, j
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NOTE 4
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l Acceptance Criteria 6.1.2 can be calculated with the formula; l
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L-P< H I
I I
2 g
\\
I where; L = latest correctedleakage and, I'
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P = Previous correctedleakage.
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proc.our no.:
eroc.our. T,tto:
p.g.
2 7
RCS Prsssurs Boundary Check Approval oste:
3.OSP.041.19 Valves 3 874A and B Leak Test 9/23/86
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.7.0 -
PROCEDURE i
7.1 Check Valves 3-874A and B Leak Test i
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INIT. Date/I'ime Starte'd:-
'7.1.1 Obtain permission from the Plant Supervisor - Nuclear to perform this test, i
7.1.2 If an on shift Quality Control Inspector is available, notify prior to performing this test.
7.1.3 Place test gauge PI-3-6341 in service by opening the following:
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1.
PI-3-6341 Root Valve,3 941C 2.
PI-3-6341IsolValve,3 868G
_7.1.4 Read and record the following data:
I 1.
RCS pressure esig 1
2.
Pressure indicated on PI-3-6341 osig j
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RCS/PI-3-6341 AP psig
-l 7.1.5 If AP is less than 100 psig reduce upstream pressure by venting at RHR Drain 3-941D until AP is 150 psig or greater. (N/A if venting is not required.)
7.1.6 Record the following on Attachment 1,3-874A and B Leak Test Data Sheet:
- 1. - Time test started l
2.
RCS Pressure l
3.
PI-3-6341 indicated pressure 4.
RCS/PI-3-6341 AP
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Procedure No.:
Procedure Titts:
Page:
RCS Pr:ssure Boundcry Chsek Approd Detr 3 OSP.041.19 Valves 3 874A and B Leak Test 9/23/86:
_l INITI A LS CK'D VERIF.
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I Once test is started all fluid vented from system to maintain AP greater than 1S0 psig I shall be collected for measuring and determining leak rate.
l._._._._._._._._._.-._._._._._._._._._._._._._.a 7.1.7 Monitor pressure indicated at PI-3-6341, 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-3-6341 indicated pressure 4.
RCS/PI-3-6341 AP 5.
Volume ofleakage collected NOTE I
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Totalleakage collected will be assigned to each valve tested.
l i._._._._._._._._._._._._._._._._._._._._._._._.a 7.1.9 Determine and record the corrected leak rate by using the formula on Attachment 1.
7.1.10 Remove test gauge PI-3-6341 from service by closing the i
following:
1.
PI-3-6341 Root Valve,3 941C 2.
PI-3-6431 Isol Valve,3-868G 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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FrOCedure NO.:
Proctdurs
Title:
Page:
RCS Prassurs Boundary Check.
9 ApproM Oate:
3 OSP-041.19 Valves 3 874A and B Leak Test 9/23/88-1 1
INIT.
7.1.12 Verify all log entries specified in Section 2.2 hnve been recorded.
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Date/ Time Completed:
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PERFORMED BY(Print)
INITIALS REVIEWED BY:
Plant Supervisor - Nuclear or SR O Designee I
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END OF TEXT
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Procedure ido :
Procedure htle:
Page:
RCS Prassuro Boundary Ch::ck Approval Date:
4 3 OSP 041.19 Valves 3 874A and B LeakTest 9/23/86 f
ATTACHMENT 1 (Page l of 2) 3 874A AND B LEAKTEST DATA SHEET Ref. Step No.
Data Required
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7.1.6 Time test started Stoowateh MTE No7 1
RCS pressure osig CalDate PI-3 6341 pressure psig
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1 AP osig (Acceptance Criteria)
(150 psigminimum) 1 7.1.8 Time test stopped RCS pressure psig PI-3-6341 pressure asig AP usig (Acceptance Criteria)
(150 psig minimum )
Leakage collected ml Total test time mins 7.1.9 3-874A and B Leak Rate Calculation ml(collected) cals(collected)
=
3785.43 ml/ gal epm at test pressure gals (collected)
=
mins (total test time)
Leak rate corrected to 2235 psig:
2235 usig 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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Proc; dure No.:
ProCIdure Titl3:
Pige:. 11
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RCS Pressuro Boundary Ch:ck Aporovai otte:
3 OSP 041.19 Valves 3 874A and B Leak Test -
9/23/86 i.
L ATTACHMENT 1 (Page 2 of 2) 3 874A AND B LE AK TEST DATA SHEET L
Remarks:
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Test Performed by:
Date l
l Date 1
1 Test and Data Reviewed by:
Date Plant Supervisor - Nuclear l
Evaluation Completed by:
Date Tech Dept Representative QC Reviewed by:
Date QC Surveillance Technician l
FINAL PAGE i
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