ML20215L779
| ML20215L779 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/23/1986 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20215L688 | List: |
| References | |
| 4-OSP-041.17, 4-OSP-41.17, NUDOCS 8706260171 | |
| Download: ML20215L779 (16) | |
Text
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Florida Power & Light Company Turkey Point Nuclear Plant Unit 4 ~
i 4 >
4-OSP-041.17 i
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Title:
1 L
RCS Pressure Boundary Valves MOV-4-750 and/or MOV-4-751 Leak Test Safety Related Procedure Responsible Department:
Technical Reviewed by PNSC:
86-248 i
Approved by Plant Manager-N:
9/23/86 RTS 86-1503P L-
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DOCK $5 50/
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Procedure No.:
Procedure Titla:
Pag 3:
RCS Pr:ssurs Boundary Valves MOV 4-750 Approval Date:
4 OSP 041.17 and/or MOV-4 751 Leak Test 9/23/86 LIST OF EFFECTIVE PAGES l
i Revision i
Page Date j
1 09/23/86 2
09/23/86 3
09/23/86 4
09/23/86 l
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 12 09/23/86 13
.09/23/86 14 09/23/86 15 09/23/86 16 09/23/86 I 'l AC,dtte
a Procedurs No,;
Procedure Tstl3:
page; 3
RCS Pressura Boundary Valves MOV-4 750 Appro@ Dat3:
4 OSP-041.17 and/or MOV-4 751 Leak Test 9/23/88 TABLE OF CONTENTS Section Page 1.0 PURPOSE 4
2.0 REFERENCES
/ REFERENCES REQUIRED 4
3.0 PREREQUISITES 5
L 4.0 PRECAUTIONS / LIMITATIONS 5
5.0 SPECIA L TOOLS / EQUIPMENT..........................
6 6.0 ACCEPTANCE CRITERIA............................'.
6 7.0 PROCEDURE 7.1 MOV-4-751 Leak Test 7
7.2 MOV-4-750 Leak Test 9
7.3 MOV-4-750 and/or MOV-4-751 Leak Test Restoration 11 ATTACHMENTS:
i MOV-4-751 Leak Test Data Sheet....................... 12 MOV-4-750 Leak Test Data Sheet 14 MOV-4-750 and/or MOV-4-751 Leak Test Restoration Verification... 16 i
l 1
1 Procedurs f4o.:
Procsdure htis; Pags:
RCS Pressuro Boundary Valves MOV 4 750 approm om:
4 OSP.041.17 and/or MOV-4 751 Leak Test 9/23/86 1.0 PURPOSE This procedure provides instructions for performing leak tests on the RHR Loop 4A Suction Stop Valves,-MOV-4-750 and MOV-4-751. These test shall be performed.
I during Unit 4 heatup as directed by OP-0202.1, Reactor Startup - Cold Conditions to Hot Standby Conditions.
This surveillance satisfles the requirements of reference 2.1.2 and 2.1.3, for the valves tested.
2.0 RE FERF,NCES/RECOR DS REQUIRED 2.1 References 2.1.1 Te4nical 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 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 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, c elays 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:
j 1.
Section 7.0 2.
Attachments 1,2 and 3
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Procedurs No.:
Procedure Ltis:
Pag 3:
)
5 4
RCS Prsssure Boundary Velves MOV 4-750 Appmve' oste; 4-OSP-041.17 and/or MOV-4-751 Leak Test 9/23/86 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 3.0 PREREQUISITES 0
3.1 Performance
- of this procedure has been directed by OP-0202.1, Reactor.
Startup - Cold Conditions to Hot Standby Conditfons.
3.2 - Personnel who will perform this procedure have reviewed it and understand
' their respcnsibilities.
3.3 Technical Department personnel have calculated the maximum allowable leak rate from previous test data, and recorded it on Attachments 1 and 2.
i 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.
i 4.3 If either MOV is declared inoperable due to this test Technical Specification Section 3.16 should be referred to for required actions.
auges used during the rformance of this l
All RCS and RHR 4.4 procedure shall have$ressureeen 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 containin high temperature radioactive water.
Insure that the lines are drained use of a pro the containment sump or the waste old up tank. perly secured drain go 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.
- oc e..
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i Procacurs No.:
Proc 3 dure Titl@:
Pag 3:
8 RCS Pressura Boundary Valves MOV.4 750 Approval oaE 4.OSP.041.17 and/or MOV.4 751 Leak Test 9/23/86 5.0 SPECIALTOOLS/ EQUIPMENT 5.1 Ty,gon tubing of sufficient length to reach floor' drain from system attachment pomt.
5.2 A graduated container 5.3 Stopwatch 6.0 ACCEPTANCE CRITERIA 6.1 MOV-4-750 and MOV-4-751 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 j
5.0 gpm and the latest measured rate has not exceeded the rate i
determined by the previous tant 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
I Acceptance Criteria 6.1.2 can be calculated with the formula; g'
I L-P < Ef I
l 2
l I
where; L = latest correctedleakage and.
l l
P = Previouscorrectedleakage.
g
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i
ProCedur3 No.:
Proctdurt htl3:
Pag}:
7 RCS Prsssuro Boundary Velves MOV-4 750 Approvai oate:
4 OSP-041.17 and/or MOV 4-751 Leak Test.
9/23/86 7.0 PROCEDURE 7.1 MOV-4-751 Leak Test INIT.
Date/ rime 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 I
RCS pressure shall be maintained less than SIS psig during the performance of this I
test to prevent auto clost e of RHR Loop 4A Suction Stop, MOV-4-750.
I t._._._._._._._._._._._._._._._._._._._._._._._.J 7.1.3 Verify that the RHR System has been removed from cooldown operation as per 4-OP-050, Residual Heat Removal System.
7.1.4 Have Operations personnel unlock and close the following breakers:
1.
40615 MOV-4-750 2.
40720 MOV-4-862A 7.1.5 Have Operations personnel place both RHR pump control switches in Pull to Lock.
1.
RHRPump A 2.
RHR Pump B 7.1.6 Have Operations personnel close the RHR Pump RWST Suction Stop, MOV-4-862A 7.1.7 Connect a piece of Tygon tubin.g at the RHR Recire Line Vent, 4-741C, and route the tubing to a f.oor drain.
7.1.8 Slowly open the RHR Recire Line Vent,4-741C to depressurize the line.
7.1.9 When the line is depressurized, elevate the end of the tubing above the RHR Recire Line Vent,4-7410.
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 4A Suction Stop, MOV-4-750.
- /JAC/dt/em e
m__
e Proc:durs No.:
Procedura
Title:
pagg 8
RCS Pressurs Boundcry Vcives MOV-4-750 Approm oats:
4 OSP-041.17_.
and/or MOV 4-751 Leak Test.
9/23/86 INIT.
7.1.12 Record the following on Attachment 1, MOV-4-751 Leak Test Data.
[
i Sheet:
.1.
Time test started 2.
RCS pressure.
I 3.
RCS temperature 4.
RHR pressure 5-RCS/RHR AP 7.1.13 After a leak rate is determined, or a minimum of 10 minutes, if no 4
leakage is noted, record the volume of leakage collected and time q
' collecting is stopped on Attachment 1.
-(
7.1.14 Have Operations personnel close the RHR Loop 4A Suction Stop, 4
MOV-4-750.
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 4A -
Suction Stop, MOV-4-751 by using the formula on Attachment 1.
7.1.17 If the RHR Loop 4A Suction Stop, MOV-4-750 requifes leak testing perform Section 7.2. (N/Aif MOV-4-750 is not to be tested) 7.1.18 If the RHR loop 4A Suction Stop, MOV-4-750 does not recuire leak testing at this time perform Section 7.3, to restore system a lignment.
(N/A if MOV-4-750 is to be tested) 4 I
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1 I
- mm..
Frocedura No.:
Proc 3dkre Trtle:
Page:
{
9-RCS Pressura Boundcry Valves MOV-4-750 Approval Dsts; 4-OSP 041.17 and/or MOV-4-751 Leak Test -
9/23/86-l
)
~7.2 MOV-4-750 Leak Test l
L i
INIT.
7.2.1 Obtain permission from the Plant Supervisor - Nuclear to perform this test.
l j
l l
7.2.2 If an on shift Quality Control Inspector is available, notify prior to l
performing this test.
l I.._....._._._.._..._..._._._...._.l L.
NOTE l
I' l
1 RCS pressure shall be maintained less than SIS psig during the performance of this j
=
l test to prevent auto closure of RHR Loop 4A Suction Stop. MOV-4-751.
.l l
l._._._._._._._._._._._._._._._.._._._._._._._.J I
7.2.3 Verify that the RHR System has been removed from cooldown operation as per 4-OP-050, Residual Heat Removal System.
7.2.4 -
Have Operations personnel unlock and close the following breakers:
I
- 1..40731 MOV-4-751 2.
40616 MOV-4-862B I
l 7.2.5 Have Operations personnel place or verify both RIIR pump control j
switches in Pull to Lock.
l 1.
RHR Pump A 1
2.
RHR Pump B 7.2.6 Have Operations personnel close the RHR Pump RWST Suction Stop, MOV-4-862B
._._._._._._._._._._._.g.,_._._._._._._._._._._.
I I
' Steps 7.2.6 and 7.2.7 may be marked N/A if their required action has already been l completedbyperformance of Section 7.1.
l 1._.._._._._._._._._._._.._._._._._._._._._._.J l
7.2.7 Connect a piece of Tygon tubin r at the RHR Recire Line Vent, l
4-741C, and route the tubing to a f oor drain.
1 7.2.8 -
Slowly open the RHR Recire Line Vent,4-741C to depressurize the line.
7.2.9 When the line is depressurized, elevate the end of the tubing above the RHR Recire Line Vent,4-7410.
7.2.10 Place the end of the tubing in a graduated container to allow measuring ofleak rate.
- nAccom b_______._-___--________.-_._-__---_-_----_---_-----------_-.--------------------------
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' c' RC'$ Pressurs Boundary Velves MOV 4 750; Appmm oate'
- W:X i
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-i and/or MOV-4-751 Leak Test 9/23/86 j
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. ; g*l %' l h2.11 d >L pga the RHR Loop 4A Suetion Stop, MOV4/151.
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, Re' cord the fcP.owin)g on Attachment 2, MOV 4-750 Leak Test D
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t ifr o
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1.
Time hat started '
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- 2..,RC, S pressure.
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3.
ECS temperature y_
4.
RHR pressure
' 5','
RCS/RHR AP L
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+
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7,,/ - ,.,:-
W" 7 2.13 After a leak rate is determined, or a minimum of 10 minutes, if no i
leak rate is noted, record the volume of leakage collected and time
/
collecting is stopped on Attachment 2.
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/ 7.".1h,%Close the RHR Loop 4A Suetion Stop, MOV-4-751.
- pj; 1
? 7 t;15 ' Return the loose tubing und to the floor drain.
- x r,
s 7.0;16' Determine and record the corrected leak rate for MOV-4-750'by -
^
ising the formula on Attachment 2.
)
/7.2.1?>, Restore system alignment by ecmpleting Section 7.3.
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,.n Procedure No :
Proc; dure
Title:
P:ge:
I1 RCS Pressurs Boundary Valves MOV 4-750 Apprmi oate:
4 OSP 041.17 and/or MOV-4 751 Lenk Test 9/23/86 n
Am
. 7.3 MOV-4' 750 and/or MOV-4-751 L'eak Test Restoratio'n INIT.
7.3.1 Close the RHR Recire Line Vent,4-7410.
7.3.2 Remove the tubing and replace the cap on the RHR Recire Line Vent, 4-741C 7.3.3 Open or verify open the following vglves:
1..
RHR Pump RWST Suction Stop, MOV-4-862A 2.-
RHR Pump RWST Suction Stop, MOV-4-862B 7.3.4 Place both RHR pump control switches in AUTO.
1.
RHR Pump A 2.
RHR Pump B 1
7.3.5 Open and lock or verify open and locked the following breakers:
1.
40731 MOV-4-751 2.
40615 MOV-4-750 3.
40720 MOV-4-862A 4.
40616 MOV-4-862B 7.3.6 Perform independent verification of system restoration by completing Attachment 3, MOV-4-750 and/or' MOV-4-751 Leak Test Restoration Verification.
7.3.7 Notify the Plant Supervisor - Nuclear that the Leak test of MOV-4-750 and/or MOV-4-751 is complete and inform the PS-N of any problems or abnormal conditions. Ensure these conditions are noted on the associated attachment.
7.3.8 Verify all log entries specified in Section 2.2 have been recorded.
]
Date/I'ime Completed:
PERFORMED BY(Print)
INITIALS REVIEWED BY:
Plant Supervisor - Nuclear or SRO Designee END OF TEXT
- *) AC dtem s
}.,
Proctdurs No.:
Procedura Titl3:
Pag 3:
12 RCS Pressura Boundsry Valves MOV 4-750 APProva'D$te:
4 OSP-041.17 and/or MOV 4 751 Leak Test 9/23/86 l
ATTACHMkNT 1 (Page 1 of 2)
MOV-4-751 LEAK TEST DATA SHEET l
1 Ref Step No.
Data Required 7.1.12 Time test started i
RCS pressure osig l
RCS temperature
(150 psig minimum )
l l
7.1.13 Leakage collected -
ml Stoowatch MTE No.
Time test stopped Cal Date l
l Total test time mins l
l l
7.1.15 MOV-4-751 Leak Rate Calculation 1
ml(collected) eals(collected)
]
=
3785.43 ml/ gal l
epm at test pressure l
cals (collected)
=
l mins (total test time) l l
l Leak rate corrected to 2235 psig:
l 2235 usie x
Leak Rate at =
GPM osig(Test AP) test pressure Corrected Leak Rate l
Acceptance Criteria:
1-1 GPM Maximum as determined Calculation Independent Verification by Tech Dept.
I Performed By:
Date O 'J A C dt efn a
[a l
Procedure No :
Procedure Titl@:
Pgg3; 13 l
RCS Pr ssuro Baundcry Velvss MOV-4 750 AppronI Dat3:
k 4-OSP 041.17 and/or MOV-4-751 Leak Test 9/23/86 l
1 i
l
.l ATTACHMENT 1
)
(Page 2 of 2) l l
L MOV 4 751 LEAK TEST DATA SHEET l
I l
Remarks:
1 1
\\
L I
l l
1 1
l l
l l
l Test Performed by:
Date Date i
Test and Data Reviewed by:
Date Plant Supervisor Nuclear l
Evaluation Completed by:
Date QC Reviewed by:
Date QC Surveillance Technician
{
l
- /J A C,dt em l
l
1 Procedure No :
Procsdura htt@:
Page:
14 RCS Prsssura Boundary Valves MOV-4 750 Approvai oats 4 OSP 041.17 and/or MOV-4 751 Lesk Test 9/23/86 i
ATTACHMENT 2 (Page l of 2)
MOV 4-750 LEAK TEST DATA SHEET Ref Step No.
Data Required 7.2.12 Time test started RCS pressure psig RCS temperature F
RHR pressure psig i
RCS/RHR AP osig (Acceptance Criteria)
(150 psig minimum )
1 l
7.2.13 Leakage collected ml Sgwgh Time test stopped Cal Date Total test time mins
'l 7.2.16 MOV-4-750 Leak Rate Calculation
)
)
ml(collected) gals (collected) l
=
3785.43 ml/ gal epm at test pressure gals (collected)
=
mins (total test time)
Leak rate corrected to 2235 psig:
2235 usir x
Leak Rate at =
GPM osig(Test AP) test pressure l
Corrected Leak Rate Acceptance Criteria 1
GPM Maximum as determined Calculation Independent Verification by Tech Dept.
Performed By:
Date
- JAC@em
I' g,oc.our. no; proc.our. w.:
a.92:
g RCS Prsssurs Boundary Valves MOV 4 750 Appro@ Dm:
4.OSP 041.17 and/or MOV-4 751 Lock Test 9/23/86' ATTACHMENT 2 l
(Page 2 of 2)
MOV-4 750 LEAK TEST DATA SHEET l
Remarks:
l f
l l
b l
l I
1 Test Performed by:
Date Date Test and Data Reviewed by:
Date Plant Supervisor -Nuclear l
Evaluation Completed by:
Date Tech Dept Representative QC Surveillance Technician 4
- !J AC,dt em
l Procedure No.:
Protsdure
Title:
Page:
18 RCS Pressure Boundary Vaivas MOV-4 750' Approvei oate:
'4 OSP 041.17 and/or MOV-4-751 Leak Test 9/23/86 ATTACHMENT 3 (Page l ofi)
MOV-4 750 and/or MOV 4-751 LEAK TEST RESTORATION VERIFICATION I
Component No.
Component Description -
Required Ind.Ver.
Position (Initiais) i RHR Pump A Control Switch AUTO RHR Pump B Control Switch AUTO VALVES CLOSED 4 741C RHR Recire Line Vent' and CAPPED MOV-4-750 RHR Loop 4A Suction Stop CLOSED MOV-4-751 RHR Loop 4A Suction Stop CLOSED MOV-4-862.A RHR Pump RWST Suction Stop OPEN MOV-4 862B RHR Pump RWST Section Stop OPEN BREAKERS LO D
40731-MOV-4-751
-40615 MOV-4-750 LOC D
Oy LO D
40616 MOV-4-862B Remarks:
Independent Verification Performed by:
Date
]
Reviewed by:
Date Plant Supervisor-Nuclear or Designee Date FINAL PAGE
)
4_
.