ML20138K241

From kanterella
Jump to navigation Jump to search
Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1
ML20138K241
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/31/1997
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20138K159 List: ... further results
References
RTR-NUREG-0578, RTR-NUREG-578 IT-530, NUDOCS 9702180073
Download: ML20138K241 (29)
v • d • e


Text

p(m,,n

~ ~

7 f

d;

,( y y ,

mgBUSINESSUNIT ' . .

11T.530{ o ' '

C

$MINSERVICE: TESTS v

  • MAJORb M -

?? '

+ .

Revision 12i >

M [%5%

LEAKAGE * ' 'REDdCTI N'AND PREVENTIVE >

$ January 3I?19973

^ '

a 7~t 9 MAINTENANCE PROGRAM TEST OF THE . ' ~ , ,

aw LRESIDUAL HEAT REMOVAL ~ SYSTEM -

,a.

li e, \(REFUELING)?. M G MJ i;

< :V f L

UNIT 10 , ,

< > ~ ; h. -

y#g s .

w 3

REC,ORD;

m

c.

2 DSS >

rnocsouma vanFmo cunaswr Ano nsCKsD PCR 1BeoRARY CW0s3 F FmLD [ 7 o ,~ ', , ?a ~ '

, W corms asouman, uns rar.cau. Aw we u 4 AND 00 art 00t.eLaTs Tms BLOCK. -

, , ^

.BY;; ' DATE:

f 1 . , <

m;, .

- p; '

. y

- +

'(jy, PURPOSE- - '

, . ~ , ;y :c 4 74 y ., .i.. . _ <i ,

d y:m pg f. (l;1(j7To ~

detect and accordance'with

~

quantify ofNUREG-0578_and the requirements leakage from~Technical the components Specificationi comprisi y w.

/:

' Table 15.4.1-2(22). ,.

4

, OL .s i

',A * +-

. .. ,s. .

Lt.24 To hydrostatically test, inspect"and measure leakage from components of the RHR' system ;

4 ,

' including intersystem leakage as required .by Technical Speci6 cation _15.4.4.IV.A. I.(a) and 4 15:4.4.IV.A.2. ~

, , . . , , a

7  ; l.3T _ Refueling frequency, quanti 6ed sent leakage testing ofvalves 1SI-8'54A&B,-

c < 1RH-706A&B, and ISC-959 as required by ASME Boiler and Pressure Vessel Code, w i Section XI, " Rules for Inspection ofNuclear Power Plant C&= "

~

. 4 S '

- 1.4 : LSection.7,0 of this procedure may be usedlwith Attachment D to fulfill't hd 40-month .
functional pressure test of Class 2 RHR system piping in accordance with ASME
o. -
Section XI and the PBNP Pressure Test Program,

>,A

2.0 REFERENCES

s ,

j6 f 12.1 4 Technical Spacifications:

i

~

g 12.1.1 Table 15.4.1-2, Item 22- d.~-

n, +-

~

  • Q 2.1.2.-  ? 15.4.4.IV.A.I.(a)

., i e . nr- -. 2 et , djD + .."

ih' g ,

2

' 2.1.3 ? 1514.IV.12 -.

m> -

g ..-m- ,.

m f- -

, ' 12 2 L . OI-65,;" Post-Maintenance Pressure Testing"

- m -

M } e _ . ' (2.3 5 i P&ID l'10E'018, Shekl. Adx Coolant Systemi

-3

~

3. _- r ..

jf]

kl(; '

  • L2.4?

1 NUREG4578; Item 2.1.6.a, "Imkage Reduction and Preventive Maintenance Program" '

j 8,

f .+ 33y

.W

[y ,

W_y sm e

. >3 ;p m,

. z, .

}a Sh " 9702180073 970210 Page 1 of 29)

~ " CONTINUOUS USE

, O if . PDR ADOCK 05000301 '

~% %/ ,. :n .c

c. s , a M

i= p- P PDR 9=

, ...m._,,_ . . , .. _ _ _ __.2- rc -

u _4 ___

1

[' ' 5NUCLEARPOWER BUSINESS UNIT  ;IT 530; 1 sINSERVICE TESTS  : MAJOR'

- 1 Revision 12  ;

? LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 .

~

4 MAINTENANCE PROGRAM TEST OF THE ,

' RESIDUAL HEAT REMOVAL SYSTEM L (REFUELING)

UNIT 1 '

J 2.5 : : EDS Nuclear report, " Leakage Rsduction and Preventive Maintenance Program at Point'- f Beach Nuclear Plant," dated 7 24-80? R 2.6 ? IR 96-006, NRC Inspection Report! NRC Commitment for Operations procedures

)

L PMT/QC reviews. "

.i

[3 0L ' TPRECAUTIONS AND LIMITATIONS' '

L3.11 RHR system fluid is radioactive. Appropriate health physics practices should be observed.

J 3.2 ? : Components required for redundant decay heat removal shall be in accordance with ;

Technical Specification 15.3.1.A.3.

1 3.3 J When a hydro pump is connected to a radioactive liquid system, maintain the test point ' j valve shut until hydro pump pressure is established and shut the test point valve before securing the hydro pump on depressurizing to prevent contamination of the hydro hose (s): .,

and pump _ i INITIALS l

'4.0; SEAT LEAKAGE TEST OF IP-10A SUCTION VALVES -

s4.I' Initial Conditions

4. L 1. .

The RHR system is aligned per CL-7A or 7B.

-4.1.2 The RCS is:

a. In the process of cooldown per OP-3C with decay heat removal via the RC loops and steam generators and RCS -

r temperature is between 500*F and 350*F, or f

,~q

. b. ;In a refueling shutdown condition with the refueling cavity ^

+ "

I flooded and upper intemals removed, or ~~'

c.' In the process' ofheatup per OP-1 A .with decay heat removal via the.RC loops 'and steam generators and RCS

. t 1 emperature is between 350'F and 500*F.

I4.i'3 ' , ' A pressure test gauge for 350 psig is available.-

g, e

,[  ; Page 2 of 29'

~

CONTINUOUS USE g." #'

~ r

NUCLEAR' POWER BUSINESS UNIT IT.530 INSERVICE TESTS MAJOR '

Revision 12 _

. LE'AKAGE REDUCTION'AND PREVENTIVE January 31,1997  ;

p MAINTENANCE PROGRAM TEST OF THE -  :

h RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

. UNIT 1 1 l

Date RECORD  :

DSS PROCEDURE VEREED CURAWT AND CHECKED FOR TEMPORARY CHANGE! IF FIELD copies RswrRED.usE PBF410m 1AW NP l.24 AND DO NQI COMPLETE THIS BLOCK  !

BY: DATE:

1.0 PURPOSE 1.1 To detect and quantify leakage from the components comprising the RHR system in accordance with the requirements ofNUREG-0578 and Technical Specification Table 15.4.1-2(22).  :

L 1.2 To hydrostatically test, inspect and measure leakage from components of the RHR system including intersystem leakage as required by Technical Specification 15.4.4.IV.A.I.(a) and - d

15.4.4.IV.A.2.- ,

1 5

1.3 Refueling frequency, quanti 6ed seat leakage testing ofvalves ISI-854A&B, I O 1RH-706A&B, and ISC-959 as required by ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inspection ofNuclear Power Plant Components "

i 1.4 Section 7.0 of this procedure may be used with Attachment D to fulfill the 40-month functional pressure test of Class 2 RHR system piping in accordance with ASME

Section XI and the PBNP Pressure Test Program.

2.0 REFERENCES

2.1 Technical SpacWie=* ions:

2.1.1 Table 15.4.1-2, Item 22 4 2.1.2 IS.4.4.IV.A.I.(a) 2.1.3 15.4.4.IV.A.2

~

2.2 - 01-65, " Post-Maintenance Pressure Testing" i
2.3 P&ID 310E018, Sheet 1, Aux Coolant System

,& 2.4 NUREG-0578, Item 2.1.6.a, " Leakage Reduction and Preventive Maintenance Program"

.V i

9702180073 970210 Page1of29 CONTINUOUS USE I PDR ADOCK 05000301

+.. . , - - - - . .. ;

NUCLEAR POWER BUSINESS UNIT IT 530 l INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 ,

MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 2.5 EDS Nuclear report, " Leakage Reduction and Preventive Maintenance Program at Point Beach Nuclear Plant," dated 7-24-80.

l 2.6 IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures PMT/QC reviews.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 RHR system fluid is radioactive. Appropriate health physics practices should be observed.

3.2 Components required for redundant decay heat removal shall be in accordance with Technical Specification 15.3.1.A.3.

3.3 When a hydro pump is connected to a radioactive liquid system, maintain the test point valve shut until hydro pump pressure is established and shut the test point valve before securing the hydro pump on depressurizing to prevent contamination of the hydro hose (s) and pump.

i INITIALS 4.0 SEAT LEAKAGE TEST OF IP-10A SUCTION VALVES 4.1 Initial Conditions 4.1.1 The RHR system is aligned per CL-7A or 7B.

4.1.2 The RCS is:

a. In the process of cooldown per OP-3C with decay heat removal via the RC loops and steam generators and RCS -

temperature is between 500 F and 350'F, or

b. In a refueling shutdown condition with the refueling cavity flooded and upper internals removed, or -' ~ ~ ~
c. In the process of heatup per OP-1 A with decay heat terroval via the RC loops and steam generators and RCS temperature is between 350 F and 500*F.
4. l'.3 A pressure test gauge for 350 psig is available.

Page 2 of 29 CONTINUOUS USE

_ . ~ . . _ . _ . . _ _ __ _ _ . . ._ . _.. _ ._.. _.. _ _ __..__..__ ___ _ _ .

l

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS , MAJOR Revision 12  !

-LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 - j MAINTENANCE PROGRAM TEST OF THE 1

\ ' RESIDUAL HEAT REMOVAL SYSTEM j
.. (REFUELING) ..
UNIT 1  ;

INITIALS  ;

K

. 4.1.4 A Haskal hydro pump is available on the El. 8' of the PAB w'.th  ;

L '

hydro hose to connect to'IRH-V1, IP-10A suction gauge isolation, and a rule to measure reservoir water level. i j 4.1.5 A graduated cylinder in cc or ml for leak rate measurement is available. t

! l

4.1.6 An RWP is available.  ;

4.1.7 The "A" train ofRHR/Lo-head SI may be taken out of service. l e ,

j- 4.1.8 Permission to Perform Test I "

3 The conditions required by this test are consistent with required  ;

plant enadWas iadadia= equipment operability. Permission is '

{

granted to perform this test. .,

DSS Time Date NOTE: Prior to taking pump out ofservice, ensure IP-1M has runfor

~S min. toflush test volume isolation valves. i 4.2 Enter LCO for 1P-10A, if required.  ;

? .

4.3- Place the IP-10A RHR pump control switch in " Pull-out." _  !

,j; }

4.4 Isolase se test volume by shutting the following valves: j]

j ISI-851A 4 ;'

IP-10A sump "B" suction MOV -

'd 1SI-856A IP-10A RWST suction MOV (9 i

' 1RH-704A

~ ~ ~

IRH-733A-

^ ~ IP-10A loop suction manual isolation 'q IP-10A mini-recirc isolation -

IRH-823A ' IP-10A suction drain 1RH-709A . IP-10A discharge manualisolation 4.5 Shut IRH-VI, then disconnect the suction gauge tubing at 1RH-VI and p -

~ connect the hydro hose to the welded reducer at IRH-V1.

q> . -

Page 3 of29 , CONTINUOUS USE

' )

.--,.' , , ., ,.n'. . -.-L- - ,. , ., --

NUCLEARPOWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 INITIALS 4.6 With IRH-VI shut, operate the hydro pump per 01-65, Part 3 to raise discharge pressure to 100 psig.

4.7 Open IRH-VI and raise test volume pressure per 01-65 to 350

(+25, -0) psig as indicated by IPI-628.

4.8 Maintain a stable test pressure for 10 minutes, then quantify the following:

NOTE: To save time, thefollowing leakage measurements should be determined concurrently.

4.8.1 Total input pumping rate in scem by accurately measuring the pump reservoir draw down over a suitable period of time.

Minimum run time for measurement is 15 minutes unless a high pumping rate (>l"/ minute) is experienced. Measure the change in mehes (AH) in reservoir level over a corresponding time hiterval(AT)in minutes and record.

AH =

inches AT =

minutes IPI-628 =

psig 4.8.2 Quantify the leak rate at the seal of IP-10A and record.

IP-10A sealleak rate = seem 4.8.3 '

Calculate the leak rate attributable to ISI-856A and 1RH-823A using the data of Steps 4.8.1 and 4.8.2.

d d

j 946Ex = 946 x = total seem - - " = -

in AT total seem - IP-10A seal = valveleakage

- =

seem

~

O

- 4

,, Page 4 of 29 CONTINUOUS USE es

NUCLEAR POWERBUSINESS UNIT IT 530  ;

I 3

INSERVICE TESTS MAJOR Revision 12 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

MAINTENANCE PROGRAM TEST OF THE [

4 RESIDUAL HEAT REMOVAL SYSTEM  !

] (REFUELING)  !

UNIT 1  ;

INITIALS  !

i

NOTE
Although the target testpressure is 350psigfor seat leakage l

measurwment ofSI-854A, the minimum acceptablepressure is 100 psig as indicated by IPI-628. If1PI-628 pressure is <100psig, then record the maximum achievable hydropung dataper Step 4.9 and i i in addition, perform the special test ofAttachment A.

4.9 Electrically open ISI-856A, then operate the hydro pump to restore test

! volume pressure to 350 (+25, -0) psig and record as in Step 4.8.1. ,

l AH = inches i AT =

minutes r

IPI-628 = Psig h

l NOTE: Duringperformance ofthis test, a hydraulic lock may occur between 1RH-7NA and check mulve 1RH-718A. Prior to depressuridag test ,

volume, this may be avoided by slowly cracking open 1RH-7NA l prior to depressuridng test volume .

a 4.10 When the leak rate measurements are completed:

4.10.1 Shut IRH-VI, then secure, depressurize and disconnect the

, hydro pump.

I m 4.10.2

, Reconnect the suction gauge tubing at IRH-VI and leak check

by momentarily opening IRH-VI.

1 7

4.10.3 Open IRH-733 A to depressurize the test volume and leave -

open. J 4.10.4 Open IRH-709A.

4.10.5 Position ISI-856A and IRH-704A per the direction of the DSS.

I m 4.10.6 Test run 1P-10A to verify operability.

Lp V 4.11 End LCO for 1P-10A, if required. -

,- Page 5 of 29 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (R,EFUELING)

UNIT 1 INITIALS 4.12 Complete the test data sheet section for seat leakage rates of IP-10A suction valves.

5.0 SEAT LEAKAGE TEST OF 1P-10B SUCTION VALVES 5.1 Initial Conditions 5.1.1 The RHR system is aligned per CL-7A or 7B.

5.1.2 The RCS is:

a. In the process of cooldown per OP-3C with decay heat removal via the RC loops and steam generators and RCS temperature is between 500*F and 350 F, or
b. In a refueling shutdown condition with the refueling cavity flooded and upper internals removed, or I
c. In the process of heatup per OP-1 A with decay heat  !

removal via the RC loops and steam generators and RCS temperature is between 350 F and 500*F.

5.1.3 A pressure test gauge for 350 psig is available.

5.1.4 A Haskal hydro pump is available on the El. S' of the PAB with hydro hose to connect to IRH-V2, IP-10B suction gauge ,

isolation, and a rule to measure reservoir water level.

~.

5.1.5 A graduated cylinder in cc or ml for leak rate measurement is available.

5.1.6 An RWP is available.

5.1.7 The "B" train ofRHR/Lo-head SI may be taken out of service.

O Page 6 of 29 CONTINUOUS USE Y , #

~ _ __ . . - . . _ - . _ . _ _ _ _ _ . _ . , _ _ .._ _ __.._ _. __. _

i p -NUCLEAR POWER BUSINESS UNIT IT 530 l

' INSERVICE TESTS - MAJOR t Revision 12 i

' LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 pg  ;

MAINTENANCE PROGRAM TEST OF THE l Q RESIDUAL HEAT REMOVAL SYSTEM '

(REFUP. LING)  ;

UNIT 1 l

INITIALS i

~

.5.1.8 Permission to Perform Test The conditions required by this test are consistent with required  ;

plant conditions including equipment operability. Permission is i granted to perform this test.

DSS Time Date NOTE: Prior to takingpump out ofservice, ensure IP-10B has run ~5 min.

toflush test volume isolation valves. l i

5.2 Enter LCO for IP-10B, if required. i 5.3 ' Place the IP-10B RHR pump control switch in " Pull-out."

5.4 Isolate the test volume by shutting the'following valves: '

O' ISI-851B IP-10B sump "B" suction MOV "

ISI-856B IP-10B RWST suction MOV 1RH-704B IP-10B loop suction manual isolation IRH-733B IP-10B mini-recire isolation IRH-823B IP-10B suction drain 1RH-709B 1P-10B discharge manualisolation i 5.5 Shut IRH-V2, then disconnect the suction gauge tubing at IRH-V2 and ,

i connect the hydro hose to the welded reducer at IRH V2. Et l 5.6 Mi With IRH-V2 shut, operate the hydro pump per OI-65, Part 3 to raise i

discharge pressure to 100 psig.

T4 5.7 Open IRH-V2 and raise test volume pressure per 01-65 to " ~ ~

350 (+25, -0) psig per 01-65 as indicated by 1PI-629.

l.

1

, Page 7 of 29 CONTINUOUS USE  !

.+ , .. . .-

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997  :

MAINTENANCE PROGRAM TEST OF THE l RESIDUAL HEAT REMOVAL SYSTEM I (REFUELING) l UNIT 1

]

INITIALS 5.8 Maintain a stable test pressure for 10 minutes, then quantify the following:

NOTE: To save time, thefollowing leakage measurements should be l

determinedconcurrently.

5.8.1 Total input pumping rate in seem by accurately measuring the  ;

pump reservoir draw down over a suitable period of time.

Minimum run time for measurement is 15 minutes unless a high i pumping rate (>l"/ minute)is experienced. Measure the change I in inches (AH) in reservoir level over a corresponding time interval (AT)in minutes and record.

AH =

inches AT =

minutes IPI-629 =

psig 5.8.2 Quantify the leak rate at the seal of IP-10B and record. .

1P-10B seal leak rate = seem 5.8.3 Calculate the leak rate attributable to ISI-856B and IRH-823B using the data of Steps 5.8.1 and 5.8.2.

AH 946 cc -- x 946 x =

total seem m AT -

total seem - 1P-10B seal _ valve leakage

f. '

seem 3 Ql ii

' 's l Page 8 of 29 CONTINUO.US USE

NUCLEARPOWERBUSINESS UNIT IT 530 INSERVICE TESTS MAJOR-Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 i Og MAINTENANCE PROGRAM TEST OF THE Q RESIDUAL HEAT REMOVAL SYSTEM i

(REFUELING)
UNIT 1

- INITIALS ,

NOTE: Although the target testymsure is 350psigfor seat leakage measurement of1SI-854B, the minimum acceptablepressure is i

100psig as indicated by 1PI-629. If1PI-629 pressure is <100psig, then record the maximum achiemble hydropungp dataper Step 5.9

andin addition, perform the special test ofAttachment B.

5.9 Electrically open ISI-856B, then operate the hydro pump to restore test

volume pressure to 350 (+25, -0) psig and record as in Step 5.8.1.

AH = inches

! AT =

minutes IPI-629 = Psig .

NOTE: Duringperformance ofthis test, a hydraulic lock may occur between IRH-704B and check valve 1Rif-718B. Prior to depressuridag test mlume, this may be avoided by slowly emeking open 1Rif-704B

.O priorto depressuridng test volume 5.10 When the leak rate measurements are completed:

4 4

5.10.1 Shut IRH-V2, then secure, depressurize and disconnect the i hydro pump.

I fMI i 5.10.2 Reconnect the suction gauge tubing at IRH-V2 and leak check l- by momentarily opening 1RH-V2.

l

5.10.3 Open IRH-733B to depressurize the test volume and leau open.

5.10.4 Open IRH-709B. ~ ~~~-

5.10.5 Position ISI-856B and IRH-704B per the direction of the DSS. ,

I rmI 5.10.6 Test run IP-10B to verify operability.

5.11 Exit LCO for IP-10B, if required. -

1 4

Page 9 of 29 CONTINUOUS USE O I 4 '

NUCLEAR POWERBUSINESS UJGT IT530 INSERVICE TESTS MAJOR Revision 12 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l MAINTENANCE PROGRAM TEST OF THE '

RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 1 INITIALS 5.12 Complete the test data sheet section for seat leakage rates of IP-10B j suction valves.

1 6.0 SEAT LEAKAGE TEST OF 1 SF-818. 819.1SC-959.1RH-705. 706A. 706B.

l 712 AND 715C i l

aCAUTIONa TEST SECTION 6.0 MUST BE COMPLETED PRIOR TO ANY RCS CLEANING OPERATIONS WITH THE RHR ,

SYSTEM IN OPERATION, SUCH AS CAMP-110,IN l

ORDER TO MINIMIZE EXPOSURE TO TEST '

PERSONNEL NOTE: Ifperforming RHR Boundary Leak TestperSection 7.0in conjunction with this test, perform Steps starting at 6. 7 and 7.2 concurrently.

6.1 Initial Conditiom 9i 6.1.1 The RCS is solid and on RHR with RCS temperature <200 F.

6.1.2 The RCS is capable of being pressurized to 350 psig.

6.1.3 The RHR system is aligned per CL-7B.

6.1.4 Normalletdown system is available. I l

6.1.5 The SFP purification system may be secured.

"f 6.1.6 A graduated cylinder in cc or ml for leak rate measurement is -

available. '

6.1.7 An RWP is available.

6.1.8 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is granted to perform this test. ~

DSS Time Date Page 10 of 29

. CONTINUOUS USE

- - _ _ - _ . - - _ _ . - . _ - - - - _ _ - _ - ~

NUCLEAR POWER L'US' NESS UNIT IT 530 l 1 INSERVICE TESTS MAJOR -

Revision 12  ;

LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 i A - MAINTENANCE PROGRAM TEST OF THE ,

- RESIDUAL HEAT REMOVAL SYSTEM

. (REFUELING) - i

. UNIT 1 INITIALS NOTE: Steps 6.2 through 6.6 may beperformed concumntly.

6.2 - Alienment ofPrimary Samnlina System  !

6.2.1. Isolate the hot leg sampling system by shutting 1SC-955, 966C and 956C. .

6.2.2 Verify shut 1SC-951,953,966A and %6B, pressurizer sample l valves. If 1SC-951 and 966A were open for pressurizer degas, then notify Control that pressurizer degas is secured for this ,

procedure.  !

6.2.3 Verify shut ISC-959 and 990, RHR sample valves. l 6.2.4 Shut ISC-968, common sample return isolation. ]

.p  !

d 6.2.5 Verify open 1SC-958A, RHR root sample valve. I l

6.2.6 Open ISC-965C and 971 to provide a valve leak-off path to the sample sink. i 6.2.7 Notify Chemistry that the primary sample system is aligned for a leak test and must not be altered without the test directors

, l pernussion. i I

i 6.3. Alienmant ofRHR 1* dawn Sveram l e 7. ' )

6.3.1 Ifletdown is from the RHR system via IRH-715C and  !

ICV-369A, then shiA to any other letdown mode or H l

! combination and shut 1CV-369A.

6.3.2 . Verify shut ISF-821 A and IRH-715D, refueling cavity j puri6 cation system cross-connects.

6.3.3 - ' Attach a Tygon tube to IR..H-D13 and route the tube to an i elevation greater'than the highest point within the boundary of O 1RH-715C,715D and ICV-369A. Secure the Tygon in place to act as a system overflow vent.

Page11of29 CONTINUOUS USE -

~. ,

l l

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 I MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1  !

INITIALS 6.3.4 With IRH-715C open, crack open IRH-D13 to fill / prime the leak detection hose until it ovedlows into a container, then shut 1RH-715C firmly and shut IRH-D13 as a leak-off path.

6.4 Alienment of RHR Suction Makeuo Line 6.4.1 Verify shut ISF-819, makeup system isolation valve.

6.4.2 Attach a Tygon tube to ISF-819B and route the tube to an elevation greater than the highest point within the boundary of ISF-819 and 819A. Secure the Tygon in place to act as a i system overflow vent.

6.4.3 Align the SFP purification to supply the head required to fill / prime the Tygon tube, then open ISF-819A.

6.4.4 Crack open ISF-819B to fill / prime the leak detection hose until it overflows into a container, then shut ISF-819A and open fully ISF-819B.

6.4.5 Secure P-33, refueling water circ pump, if operating.

6.4.6 Isolate the SFP purification system by shutting:

SF-795 P-33 discharge to U6 SF-27 P-12A&B discharge to U6 SF-812A SFP purification return isolation g

6.5 Alinnment ofLocal RHR Samole System 6.5.1

~

Verify shut IRH-705 and 712, local sample valves.

6.5.2 Verify the sample tubing is open to the local sample sink to act .

as leak-off collection point for seat leakage of 1RH-705 and 712.

Page 12 of 29 CONTINUOUS USE 4 4

  • NUCLEARPOWERBUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE

-V(7 RESIDUAL HEAT REMOVAL SYSTEM i (REFUELING) t UNIT 1 INITIALS .

6.6 Alignment ofHigh Flow Test Line ,

6.6.1 Verify IRH-706A&B, test line isolation valves, are shut firmly.

6.6.2 Attach a Tygon tube to IRH V16 and route the tube to an ,

elevation greater than the highest point within the boundary of IRH-706A&B and 742. Secure the Tygon in place to act as a  ;

system overflow vent.

NOTE: This procedure assumes that the IFE-660 onfice is installed and the blank is removed Otherwise thefill and vent of the test line will need to be modified byfilling through  ;

1RH-706A orb. '

6.6.3 With all test line vents and drains shut, pasally open IRH-742 '

and 742B.

6.6.4 Crack open 1RH-V16 to fill / prime the test line and leak detection hose until it overflows into a container, then shut 1RH-742 and 742B firmly.

6.6.5 Measure and record a stabilized baseline leak rate, if any, at IRH-V16. Baseline leakage = scem i

  • CAUTION
  • AS RHR SYSTEM PRESSURE IS INCREASED TO TEST PRESSURE, THE LEAK-OFF POINTS AT 1RH-D13, ,

IRH-V16 AND ISF-819B MUST BE MONITORED TO ,l ~ I PREVENT LEAK-OFF CONTAINER OVERFILLING.~

NOTE: Steps 6. 7 and 6.8 of thisprocedure are common with Steps 7.2 ,

~~

and 7.3 ofSection 7.0. \

6.7 Raise RCS system pressure to >350 psig and maintain stable pressure for the duration of the test.

J l

Page 13 of29 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12

, LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RLSIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT I INITIALS '

6.8 After 10 minutes at test pressure, collect and record the seat leakage rate for the following valves:

NOTE: RHR system walkdown andleakage to atmosphere measurements per Section 7. 0 ofthis procedure should be performed concurrently.

6.8.1 Measure and record a baseline leak rate, if any, at I SC-971.

Baseline leakage = sccm 6.8.2 Open ISC-990, then measure the seat leak rate of ISC-959 at sample valve ISC-971.

1SC-959 leakage = secm 6.8.3 When leak rate measurement of ISC-959 is complete, then shut 1SC-990,965C and 971.

NOTE: Ifpressurizer degas is to be resumed, reference OP-5D, Section C and reopen 1SC-968, 951 and 966A. Throttle degasflow with ISC-965A for aflow rate of 0.5-1.0 GPMper IF1-903.

6.8.4 Open IRH-D13, allow leakage to stabilize, then collect and record leak rate of IRH-715C at IRH-D13 = seem 6.8.5 When leak rate measurement of IRH-715C is complete, then shut IRH-D13 and remove the leak-off Tygon tube. -

6.8.6 Record leak rate of 1RH-705 and 712 at the local sample

~

sink = seem 6.8.7 Open IRH-V16, allow leakage to stabilize, then collect and record seat leakage rate of 1RH-706A&B at IRH-V16 seem O

Page 14 of 29 CONTINUOUS USE

-- - . . . . . - - _- - - . - .- -. . . = . - . - . -

L NUCLEAR POWERBUSINESS UNIT IT 530 l INSERVICE TESTS MAJOR .{

Revision 12 -

.. LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l MAINTENANCE PROGRAM TEST OF THE i RESIDUAL HEAT REMOVAL SYSTEM  !

(REFUELING) ,

UNIT 1 +

INITIALS  :

6.8.8 When leak rate measurement of IRH-706A&B is complete, i then shut IRH-V16, remove the Tygon tube and cap 1RH-V16.

6.8.9 Verify open ISF-819B, then record leak rate of ISF-818 and

. 819 at 1SF-819B = scem 6.8.10 When leak rate measurement of ISF-818 and 819 is complete, I

then shut ISF-819B and remove the leak-offTygon tube.

i 6.9 . Alinn the Followina Valves for System to Atmosohere Leaknoe Measurement 6.9.1 Verify IRH-V14 shut, then open IRH-V14A to protect gauge  :

IPI-657 from overpressure. i i

6.9.2 Open IRH-715D.

O 6.9.3 Slowly open IRH-715C to pressurize the piping to ISF-821 A l

and ICV-369A.

6.9.4 Verify IRH-742, 742A and 742B shut, then partially open l

, IRH-706A to pressurize the piping to IRH-742B. l

l. l
6.9.5 Open ISC-959 to pressurize the piping to ISC-990. '

1- 6.10 Complete the test data sheet section for sest leakage rates ofvalves tested l in this section.

{.f i- J rw

.s.. - - t - _ . - kG ;tN %M l

i O -

- Page 15 of 29 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 530 i INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE Januar,.i 31,1997 i

- MAINTENANCE PROGRAM TEST OF THE R6SIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 1 INITIALS 7.0 RHR BOUNDARY LEAK TEST "CAUTIONa TEST SECTION 7.0 MUST BE COMPLETED PRIOR TO RCS CLEANING OPERATION WITH THE RHR SYSTEM IN OPERATION, SUCH AS CAMP-110,IN l ORDER TO MINIMIZE EXPOSURE TO TEST I PERSONNEL. I NOTE: This test and the vahw leakage test ofSection 6.0 should be performed concurrently.

7.1 Initial Conditions 7.1.1 The RCS is solid and on RHR with RCS temperature <200 F.

7.1.2 The RCS is capable of being pressurized to 350 psig. I 7.1.3 The RHR system is aligned per CL-7B.

7.1.4 Graduated cylinders in cc or ml for leak rate measurement are available.

7.1.5 An RWP is available.

7.1.6 If this test is being utilized to fulfill 40-month functional pressure test requirements, then:

.)

a. The QTS inspector is notified of the test.

[

b. The ANIIis notified of the test.
c. The pretest data of Attachment D is completed.

7.1.7 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is granted to perform this test.

.. Page 16 of 29 CONTINUOUS USE

i ' NUCLEAR POWER BUSINESS UNIT' IT 530 l

INSERVICE TESTJ MAJOR.

Revision 12

LEAKAGE REDUCTION'AND PREVENTIVE ~' January 31 1997 MAINTENANCE PROGRAM TEST OF THE
g. . RESIDUAL HEAT REMOVAL SYSTEM (REFUELING) 4 UNIT 1 ,

INITIALS' e

i  :

_ 7.2 < Raise RCS pressure to >350 psig and maintain Mable pressure for the duration of the test. For a 40-month test, record test pressure achieved data on Attachment D.

l

' 7.3 - After 10 minutes at test pressure, visually inspect the piping system and ~

components (heat exchanger tubesheet joints, pump seals, valve stems and

, body to bonnet joints, pipe flanges / orifices, vent and drain plugs / caps, instrument line fittings / gauges) listed in Attachment C. Collect and record  :

p all visible leakage to atmosphere in secm. For a 40-month test, record Attachment D data.

t

7.4 When the leak test data and Attachment C data are complete, including Attach >=* D if applicable:

j 7.4.1 Shut IRH-715D and IRH-V14A. -

i 7.4.2 Position IRH-715C and 1CV-369A per the direction of the DSS. .

I 7.4.3 Red lock shut 1RH-706A. Lock No.

7.4.4 Shut ISC-959.

7.5 ' Total the individual component leakages of Attachment C in seem and record on An=chr=* C. d

, 8,0 ACCEPTANCE CRITERIA ll W

}

8.1 Leakage criteria of the Leakage Reduction and Preventive Maintenance 4

Program are used to evaluate leakage from residual heat removal system ~ ~~~T

[ components to atmosphere. Total leakage from all post-accident system components located in a specific area of the plant is limited by Criterion 1

," or Criterion 2. The total post-accident system leakage from all areas of the plant is limited by Criterion 3. Thus, acceptance of these test results requires their evaluation together with the results of the other post-accident t system leakage tests.

Page 17 of29 CONTINUOUS USE 9 4 8 ,

e 8 #

, 9

, G r

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 INITIALS 8.2 Valve through-leakage should not exceed 30 cc/hr per inch of valve diameter. This is only to be used as a guideline, and may be changed to be consistent with the as-low-as-practicable" philosophy.

8.3 The maximum allowable leakage from the RHR system components (which includes valve stems, flanges and pump seals) shall not exceed two gallons per hour per Technical Specification 15.4.4.IV.B.  ;

1 9.0 ANALYSIS TO BE COMPLETED WITHIN 96 HOURS BY OPERATIONS MANAGER OR HIS REPRESENTATIVE.

9.1 Comparisons with allowable ranges of test values and analysis of deviations complete.

9.2 Any requirements for corrective action?

e Yes No (If yes, give details in the remarks section.)

9.3 Data analyzed by Time and date Remarks: 'I a

4 Page 18 of 29 CONTINUOUS USE e, *8 ,

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12.

LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 l

/ MAINTENANCE PROGRAM TEST OF THE

\, RESIDUAL HEAT REMOVAL SYSTEM '

(REFUELING)

UNIT l' INITIALS TEST DATA SHEET 1.0 Valve Seat Leakane NOTE: Allleak rates arein secm.

NOTE: Column A data is information only. Column B data is applicable to Technical Specifications andNUREG 0578.

Col. A Col. B '

l.1 ISI-856A and IRH-823A (Reference Step 4.8.3) 1.2 1SI-854A (Reference Step 4.9 and Attachment A) 946 "- x = 946 x = seem m DT minus 1P-10A sealleak (Step 4.8.2) =

or Attachment A = gpm 1.3 ISI-856B and IRH-823B (Reference Step 5.8.3) 4 1.4 ISI-854B (Reference Step 5.9 and Attachment B) 946 ""x = 946 x = seem m AT minus 1P-10B sealleak (Step 5.8.2) =

or Attachment B = gpm 1.5 ISC-959 (Reference Steps 6.8.1 and 6.8.2)

Corrected leak rate = Step 6.8.2 minus 6.8.1 =

1.6 1RH-7ISC (Reference Step 6.8.4) =

1.7 1RH-705 and 712 (Reference Step 6.8.6) =

1.8 0 1.9 1RH-706A&B (Reference Step 6.8.7) =

ISF-818 and 819 (Reference Step 6.8.9) =

. Page 19 of29 CONTINUOUS USE

,t , '

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE  ;

RESIDUAL HEAT REMOVAL SYSTEM '

(REFUELING)

UNIT 1

~

INITIALS .

ATTACHMENT A Seat Leakage Test of 1SI-854A Usine P-33 NOTE: This test cannot beperformedifRHR is operating in the DHR mode and 1RH-701 cannot be shut.

NOTE: This test is required when the seat leakage ofISI-854A exceeds thepumping rate of the ,

hydropump and test systempressureper JPI-628 is <100psigper Step 4.9.  !

1

. 1.0 Shut 1RH-V1, then secure the hydro pump. I 2.0 Secure SFP recirc or Unit 2 RWST recire, ifin operation. l 3.0 Align P-33 for Unit 1 RWST recire at 20 gpm per FI-636 by throttling with 1SF-811.

4.0 Verify 1RH-701 shut, then open ISF-819 and verify FI-636 flow remains at 20 gpm.

5.0 Open IRH-704 A to ~25% open and allow flow at FI-636 to stabilize.

6.0 Record the following data:

P-33 flow per FI-636 gpm P-33 pressure per PI-651 psig 4; <

Test volume pressure per IPI-628 psig '

j  !

7.0 Shut ISF-819 and IRH-704A.

8.0 When P-33 flow has stabilized, record the following data:

P-33 flow per FI-636 gpm P-33 pressure per PI-651 psig Test volume pressure per IPI-628 psig l 9.0 Return P-33 to previous status or as directed by the DSS '

Page 20 of 29 CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR . ,

Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 A MAINTENANCE PROGRAM TEST OF THE i h RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)  ;

UNIT 1 - ,

ATTACHMENT A INITIALS  :

10.0 Calculate ISI-854A seat leakage as P-33 flow in Step 8.0 minus P-33 flow in  !

Step 8.0 = gpm. Record this leakage on the test data sheet, Step 1.2 11.0 Return to procedure step in effect of Section 4.0. _

t

)

O l 9

i

? -:

l 1  ;; ;

]

~

l s

p-V .

I

. l Page'21 of29 C. ONTINUOUS USE  !

, }

1

NUCLEAR POWERBUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 INITIALS ATTACHMENT B Seat Leakane Test ofISI-854B Usine P-33 NOTE: This test cannot beperformed ofRHR is operating in the DHR mode and 1RH-701 cannot be shut.

NOTE: This test is required when the seat leakage of1SI-854B exceeds the pumping rate of the hydro pump and test system pressureper JPI-629 is

<100psigperStep 5.9.

1.0 Shut IRH-V2, then secure the hydro pump.

2.0 Secure SFP recire or Unit 2 RWST recire, ifin operation.

3.0 Align P-33 for Unit 1 RWST recire at 20 gpm per FI-636 by throttling with 1SF-811.

4.0 Verify IRH-701 shut, then open ISF-819 and verify FI-636 flow remains at 20 gpm.

5.0 Open IRH-704B to ~25% open and allow flow at FI-636 to stabilize.

l 6.0 Record the following data: 1 i

P-33 flow per FI-636 gpm P-33 pressure per PI-651 psig , .

Test volume pressure per IPI-629 psig g 7.0 Shut ISF-819 and 1RH-704B. k 8.0 When P-33 flow has stabilized, record the following data:

P-33 flow per FI-636 gpm P-33 pressure per PI-651 psig Test volume pressure per IPI-629 psig 9.0 Return P-33 to previous status or as directed by the DSS.

  • I l

Page 22 o.f 29, ,, , ,,

CONTINUOUS USE ..

NUCLEAR POWERBUSINESS UNIT 'IT 530  :

INSERVICE TESTS MAJOR  :

Revision 12 i LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

/ MMNTENANCE PROGRAM TEST OF THE

'\ - Rl:SIDUAL HEAT REMOVAL SYSTEM  :

(RiFUELING)

Uh IT 1 ATTACHMENT B INmALS l 10.0 Calculate ISI-854B seat leakage as P-33 flow in Step 6.0minus P-33 flow in i Step 8.0= gpm. Record this leakage on the test data sheet, Step 1.4.

11.0 Retum to procedure step in effect of Section 5.0.

i l

l O .

i j

l l

j

' i

(/ .

Page 23 of 29 CONTINUOUS USE 4 e

NUCLEAR POWER BUSINESS UNIT - IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 ATTACHMENT C Leakage Rate Component ID Comoonent Description (secm)

IP-10A RHR Pumo Cubicle 1RH-823 A IP-10A suction low point drain IRH-V10 1P-10A seal supply vent 1RH-VI I IP-10A seal heat exchanger inlet vent 1RH-71 ID IP-10A sealleak telltale Flange IP-10A seal RO flange IRH-711 A IPT-628 root valve IP-10A Pump seals PAB General Area South. E! -19'3" 1PT-629 IP-10B discharge pressure transmitter IPT-628 IP-10A discharge pressure transmitter IP-10B RHR Pumo Cubicle IRH-823B IP-10B suction low point drain 1RH-71 IF IP-10B sealleak telltale IRH-V12 IP-10B seal supply vent IRH-V13 IP-10B seal heat exchanger inlet vent Flange IP-10B seal RO flange IRH-71IB IPT-629 root valve ,

1P-10B Pump seals V p

Unit 1 RHR Pipeway S

~ ~

1RH-710A 1P-10A discharge check valve lRH-709A IP-10A discharge isolation IRH-713A IP-10A discharge cross-connect IRH-D1 IP-10A&B discharge cross-connect drain IRH-713B IP-10B discharge cross-connect IRil-709B ' IP-10B discharge isolation IRH-710B . IP-10B discharge check valve ISI-851 A IP-10A "B" sump suction MOV ISI-851C Pressure equalizer for ISI-851 A ISI-851B IP-10B "B" sump suction MOV Page 24 of 29 CONTINUOUS USE

. . - . . - - = . - . .

7

' NUCLEARPOWERBUSINESS UNIT IT 530 f INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 p MAINTENANCE PROGRAM TEST OF THE

d '(RESIDUAL HEAT REMOVAL SYSTEM

. REFUELING)

. UNIT 1 -

ATTACHMENT C Leakage Rate i Component ID Comoonent Descriotion (sccml ,

Unit 1 RHR Pineway (Cont.)

i i ISI-851D Pressure equalizer for ISI-851B .

IRH-715A IHX-11 A inlet isolation l

l 1RH-D2 1HX-11 A interpass drain  ;

j 1RH-D3 1HX-11 Ainterpass drain  ;

i 1RH-D4 1HX-11 A interpass drain  !

2 1RH-715B 1HX-1IB inlet isolation i i

1RH-D5 IHX-1IB interpass drain

[ ]RH-D6 ~ lHX-11B interpass drain  !

1RH-D7 IHX-1IB interpass drain  :

PAB Ganaral Area S=th El -5'3" l 1RH-624 IHX-11 A discharge TCV 1RH-625 IHX-1IB discharge TCV 1RH-716A IHX-11 A outlet isolation

1RH-716B lHX-1IB outlet isolation IRH-716C IHX-1IB outlet cross-connect I L

1RH-716D 1HX-II A outlet cross-connect I 4

1RH-D8 IHX-11 A outlet drain l PAB General Area S=th El. 8'0" I 1RH-705 RHRlocal sampleisolation IRH-711C IP-10A seal water supply vi 1RH-71IE IP-10B seal water supply IFT-626 Train "A" RHR flow transmitter ~ ~ " -

IFT-928 Train "B" RHR flow transmitter 2

- IRH-V4 - Train "B" RHR to SI and spray suction line vent (in overhead ofsealwater return filter cubicle)

Page 25 of5

- CONTINUOUS USE I O

e

i NUCLEAR POWER BUSINESS UNIT IT 530 )

l INSERVICE TESTS MAJOR Revision 12 j

- LEAKAGE REDUCTION AND PREVENTIVE January 31,1997 j MAINTENANCE PROGRAM TEST OF THE i RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 l ATTACHMENT C l Leakage Rate Comoonent ID Comoonent Descriotion {

(seem) l Lower Pineway #2 l

1RH-VIB IPI-653A root valve 1RH-VI A IPI-653 A bleed-off for seat leakage of IRH-VlB 1RH-VIC IPI-654A root valve 1RH-V2B 1PI-653B root valve 1RH-V2A 1PI-653B bleed-off for seat leakage of IRH-V2B  ;

1RH-V2C IPI-654B root valve '

IPI-654A IP-10A RHR suction pressure indication IPI-654B IP-10B RHR suction pressure indication ISI-856A IP-10A RWST suction MOV 1SI-856B IP-10B RWST suction MOV 1SI-854A IP-10A RWST suction check ISI-854B  !

IP-10B RWST suction check 1RH-712 RHR local sample isolation 1SC-958 RHR sample system isolation llui-714A RHR heat exchanger bypass isolation 1RH-714B RHR heat exchanger bypass isolation 1RH-626 RHR heat exchanger bypass FCV 1SC-958 A RHR pump discharge sample isolation IRH-V1 IPI-653A and 654A root valve 1RH-V2 IPI-653B and 654B root valve IRH-704A IP-10A RCS loop suction isolation 1RH-704B IP-10B RCS loop suction isolation 1RH-718A IP-10A RCS loop suction check 7

1RH-718B IP-10B RCS loop suction check 1RH-717A IFT-626 high pressure root valve 1RH 717B IFT-626 low pressure root valve -

IFE-626 Train "A" RHR flow orifice 1RH-848F IFT-928 high pressure root valve 1RH-848E 1FT-928 low pressure root valve -

IFE-928 Train "B" RHR flow orifice ISF-819 RHR loop suction makeup isolation 1RH-733A P-10A mini-recire isolation IRH-733B 1P-10B mini-recire isolation Page 26 of 29 CONTINUOUS 'USE 49

4

-NUCLEAR POWER BUSINESS UNIT IT 530 J INSERVICE TESTS MAJOR

' Revision 12 LEAKAGE REDUCTION AND PREVENTIVE - January 31,1997 A MAINTENANCE PROGRAM TEST OF THE l

l( '- ) RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)

UNIT 1 '

ATTACHMENT C Leakage Rate l Comoonent ID Component Descriotion (secm)

Lower Pineway #2 (Cont.) -

P7 Loop suction containment penetration P8 Train "A" RHR discharge containment penetration

P22 Train "B" low head SI containment penetration Containment Sorav and SI Pumo Area 4

l ISI-871 A Train "A" RHR/CS cross-connect MOV ,

ISI-871B Train "B" RHR/CS cross-connect MOV l 1SI-857A Train "A" RHR/SI cross-connect isolation l l 1SI-857B Train "B" RHR/SI cross-connect isolation Lower Pineway #2 '

  • 1RH-706A IP-10A high flow test line isolation
  • 1RH-706B IP-10B high flow test line isolation
  • lFE-660 High flow test line orifice flange
  • 1RH-662A FIT-660 high side root valve

'pf

  • 1RH-662B FIT-660 low side root valve N)
  • lFIT-660 High flow test line flowindicator

. *1RH-715C RHRletdown isolation "" -

  • 1CV 369A RHR letdown isolation
  • 1RH-715D Refueling cavity purification isolation ~
  • ISC-990 RHR sample sink isolation I
. Page 27 of 29

- CONTINUOUS USE

NUCLEAR POWER BUSINESS UNIT IT 530 INSERVICE TESTS MAJOR Revision 12 LEAKAGE REDUCTION AND PREVENTIVE January 31,1997

- MAINTENANCE PROGRAM TEST OF THE RESIDUAL HEAT REMOVAL SYSTEM

. (REFUELING)

UNIT 1 ATTACHMENT C Leakage Rate Comoonent ID Component Descriotion (secm)

PAB General Area South. El -5'3"

  • lSF-821 A P-33 cavity purification discharge isolation Other miscellaneous system components (specify in Remarks)

Total Leak Rate l

  • Inspect and record leakage after system is pressurized; Step 6.9 is completed.

O i

2. i

.,;;S i

.. Page 28 of,29 CONTINUOUS'USE

NUCLEAR POWER BUSINESS UNIT IT 530

_ INSERVICE TESTS MAJOR Revision 12

' LEAKAGE REDUCTION AND PREVENTIVE ' January 31,1997 g MAINTENANCE PROGRAM TEST OF THE  !

{Q RESIDUAL HEAT REMOVAL SYSTEM (REFUELING)'

UNIT 1 - ,

ATTACHMENT D 40-MONTH FUNCTIONAL PRESSURE TEST PRETEST DATA i

Record calibration dates for:

1PI-628 1PI-629 TEST DATA Test pressure achieved:

IPI-628 psig IPI-629 psig Tune (O

J 10-Minute hold / Inspection started:

1PI-628 psig 1PI-629 psig Time Inspection completed:

1PI-628 psig 1PI-629 psig Time ACCEPTANCE CRITERIA The functional pressure test is considered acceptable if the pressure retaining piping and components withstand the test pressure without loss of structural integrity.

I '

Additionally, the test is considered acceptable if there is no leakage from the system other than controlled - i leakage or leakage through boundary valves.

Test Director Date QTS Reference Report Number:

'l ' Remarks:

(G -

Page 29 of 29 CONTINUOUS USE 9

Retrieved from "https://kanterella.com/w/index.php?title=ML20138K241&oldid=2865993"