ML20079G115

Rev 1,to Inservice Testing Program for Pumps & Valves. Relief Requests Encl

ML20079G115
Person / Time
Site:	Point Beach
Issue date:	01/06/1984
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20079G108	List: ML20079G106 ML20079G115
References
PROC-840106, NUDOCS 8401190422
Download: ML20079G115 (124)

Text

.

. .~

et -

,g.,

INSERVICE TESTING PROGRAM WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT UNITS 1 & 2

- Revision 1,' January 6, 1984 i.

t I

f 4

fI &

i. . '

.i k

_L 5

A.

t f

k I

J k

i T

I

)

' S401190422'940116 PDR ADOCK 03000266 P-

pg "t C ata *-"t' N'"

q y y -99m< g e we e rgi9q.Se ye,g-p .g yg.g.,9,gpg.,,,,7..g, , _. _ , , __ _ ,, _ . _ , _

.e TABLE OF CONTENTS Page INTRODUCTION 11 s

1.0 INSERVICE TESTING OF PUMPS 1.1 General Information . . . . . . . . . .. . . . . . 1

1. 2 .- Program Information . . . . . . . . . . . . . . . . l-1.- 3 .' Test Frequency . . . . . . . . . .. . . . . . . . 1 1.4 Request for Relief . . . . . . . . . . . . . . . . 2 2.0 INSERVICE TESTING OF VALVES .

2.1 General Information . . . . . . . . . . . . . . . . 1

2. 2 ' Program Information . . . . . . . . . . . . . . . . 1 2.3 Valve position Indicator Verification . . . . . . . 3 2.4 Piping and. Instrumentation Drawings . . . . . . . . '3 2.5 Request for. Relief. . . . . . . . . . . . . . . . . 5 2.6 Explanation of Abbreviations and Notes. . . . . . . 5 3.0 INSERVICE TESTING OF PROGRAM - PUMPS 3.1 Unit 1 r- 3.2 Unit 2 Appendix A - Relief Requests for Pumps 4.0 INSERVICE TESTING OF PROGRAM - VALVES 4.1 Unit 1

'4.2 Unit 2 Appendix B - Relief Requests for Valves

i. .

,r ,-

...a e

'l INTRODUCTION The Inservice Testing Programs for Point Beach Nuclear Plant, Units 1 and 2, were developed in compliance with the rules and -regulations of 10 CFR 50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1977 Edition through Summer 1979 Addenda. Where these rules were determined to be impractical, specific relief was written.

c Section 1.0 discusses the Inservice Testing Program of applicable ASME Class 1, 2, and 3 pumps. Section 2.0 discusses the Inservice Testing Program of applicable ASME Class 1, 2, and 3 valves.

Both of these programs were initially developed to the guidelines suggested in an NRC letter dated January, 1978. A subsequent resubnittal was made based on the results of a Novamber 1, 1983, meeting with the

< NRC.

11

c -, .

- gm , g%

- , 4 Section 1.0 Revision 1

. 01-06-84 Page 1 1.0 - INSERVICE TESTING OF PUMPS 1.1 General Information The Inservice Testing Program for applicable ASME Class 1, 2, and 3 pumps was developed in accordance with, and. meets the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, 1977 Edition through Summer 1979 Addenda.

.This Inservice Testing Program will remain in effect throughout the second 10 year inservice inspection interval.

Section 3.0 lists all Class 1, 2, and 3 pumps which are to be t.osted, ,

~i- along with the applicable parameters to be measured.

i- Pumps that serve a common safety.. function (i.e. , . fur ction to serve both units) , are included in the Unit 1 inservice testing program list.

h .

Program Information 1.2 The following information is included in the Inservice Testing Program for pumps:

1.2.1 Pump Number. lists the pump identification number as shown on

[.

-the PGID's.

i

• 1.2.2 Pump Name describes the pump's functional identification as

it is related to system operation.

I-i" 1.2.3 Class is the ASME classification of the pump.

1. 2. 4 - Test Parameters indicates the required test quantities measured I^- per. Table IWP-3100-1.

1.2.5 Relief Request references the relief request contained in Appendix A that applies to the particular pump. Also included j are generic relief requests that are not specifically referenced

- in this column of the table, but apply to the pump program in general.

l:

iL 1.3 Test Frequency-h

-An inservice test shall be run on each pump nominally every three months b during plant operation. If this frequency can reasonably be accomplished

j. during shutdown periods it will be, however, this is not mandatory.

Where'a pump is not tested on a three month frequency during plant shutdown, it will be tested within one week after the plant is returned to normal operation.

L. . _

...n

O a

Section 1.0 Page 2 1.4 Request for Relief Where ASME Section XI requirements were determined to be impractical, a request for relief was written. These requests were developed to the

. guidelines suggested in an NRC letter dated January 1978, end a November 1, 1983, meeting with the NRC.

Where relief from an ASME Code requirement is granted within the provisions of 10 CFR 50.55a(g) (6) (1), it will be incorporated into Point Beach Units 1 and 2 Inservice Testing Program.

Relief requests are shown in Appendix A.

1.5 Pump Notes 1 Pump discharge pressure is measured and compared with inlet pressure to determine differential pressure.

2. Pump inlet pressure is determined with level in refueling

. water storage tank.

3. Full-flow test is conducted during refueling periods.

4. Pump inlet pressure is determined with level in circulating water forebay.

5. This pu::ip is operated more frequently than every quarter and

, will not be stopped for a special test (IWP-3400 b).

O b

L

g>

, s' Section 2.0 Revision 1 01-06-84 Page 1

~

2.0 INSERVICE TESTING OF VALVES 2.1 General Information The Inservice Testing Program for applicable ASME Clasa 1, 2, and 3 valves was developed in accordance with, and meets the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWV, 1977 Edition through Summer 1979 Addenda.

The Inservice Testing Program for valves will remain in effect throughout the second 10 year inservice inspection interval.

The Inservice Testing Program lists all applicable ASME Class 1, 2, and 3 valves that have been assigned salve categories. Except for valves directly in the flow path (E passive) , valves exempted per IWV-1200 are not' listed. Valves that serve a common safety function (i.e. ,

function to serve both units) are included in the Unit 1 Inservice Testing Program list.

The tables are organized by system in order of the assigned P&ID number and are listed in Section 2.4.

2.2 Program Information The following information is included in .the Inservice Testing Program

,- for valves:

2.2.1 Valve Number lists the valve identification number as shown on the P&ID's.

2.2.2 P&ID and Coordinates references the P&ID on which the valve appears and its coordinates.

2.2.3 Class is the ASME classification of the valve.

2.2.4 Valve Category indicates the category assigned to the valve based on the definitions of IWV-2200.

2.2.5 Valve size lists the nominal pipe size of the valve in inches.

2.2.6 Valve Type lists the valve design.

2.2.7 Actuator Type lists the type of valve actuator.

2.2.8 Valve Position indicates the normal position of the valve during plant operation; either normally open (0) or normally closed (C).

L

Section 2.0 Page 2 2.2.9 Stroke Direction indicates the direction which an active valve must stroke to perform its safety function. Also, the direction in which the valve will be stroked to satisfy the exercising requirements of IWV-3410 or IWV-3520. This may be specified as open (O) , closed (C) , or both (0/C) .

2.2.10 Test lists the test or tests that will be performed for each valve to fulfi~.1 the requirements of Subsection IWV.

Seat Leak Test AT Valve will be seat leak tested at the appropriate functional differential pressure.

Full Stroke Exercise Test BT Valve will be full stroke exercised for operability in the direction necessary to fulfill its safety function.

Check Valve Exercise Test CVT Check valve will be exercised to the position required to ful-fill its function. This functional test will be verified by the operation of the required system. Thus, " full stroke exercising" a check valve may be accomplished by either providing sufficient flow to fully open the disc, or provide the flow necessary to fulfill its associated safety function.

Check Valve Partial Exercise Test CVP Check valve will be part stroke exercised, (i.e., disc moves away from seat) when full stroke exercising is impractical.

Fail-Safe Test FST All valves with fail-safe actuators vill be tested to verify proper fail-safe operation upon loss of actuator power.

Relief Valve Set Point Check RVT Relief and safety valve set points will be verified in accordance with IWV-3510.

2.2.11 Test Mode indicates the frequency at which the above mentioned tests will be performed. The following abbreviations are used:

Cold Shutdown CS Valve testing at cold shutdown is valve testing which commences not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown and continues until required testing is completed or plant startup, whichever occurs first. Completion of all required valve testing is not a requisite to plant startup. Valve testing which is not completed during a' cold shutdown will be performed during subsequent cold shutdowns to meet the code specified testing requirements. No valve need be tested more often than once every 90 days.

NOTE: IT IS EXPECTED THAT THE REQUIRED VAI.VE TESTING WILL NORMALLY BE COMPLETED IN 96 HOURS FOLIDWING COLD SHUTDOWN.

Section 2.0 Page 3

_ Specific Cold Shutdown E-CS Valve tests with this designation will be conducted at cold shutdown conditions that also require " Event V" reactor coolant-system primary isolation valve testing. " Event V" valve testing requirements may be found in plant Technical Specification 15.3.16.

Normal Operation OP Valve tests with this' designation will be performed once every three months.

Reactor Refueling RR valve tests with this designation will be conducted at reactor refueling outages only.

Specific Reactor Refueling *RR Valve tests with this des.4 gnation will be conducted at a reactor refueling once every 10 year inservice inspection interval. Any reactor refueling within this period will suffice as long as overall plant conditions, associated with the specific refueling outage, will allow the performance of the required testing (i.e., core off-load'if necessary, etc.).

2.2.12 Max Strcke Time lists the maximum allowed full stroke time in seconds for valves requiring test.

2.2.13 Relief Request references the relief. request contained in Appendix B that applies to the particular valve.

2.2.14 R_emarks lists clarification remarks.

2.3 Valve Position Indicator Verification Valves with remote position indicators will be observed at least once every two years to verify that remote valve indications accurately reflects valve operation.

2.4 Piping & Instrumentation Drawings The following P&ID's contain valves which are part of the Inservice Testing Program:

n Section 2.0 Page'4 TITLE UNIT 1 UNIT 2 Safety Injection System .110E017 110E035 Sheets 1,2,3 Sheets 1,2,3

- Auxiliary Coolant System- 110E018 110E029 Sheets 1,2,4 Sheets 1,2 110E018 Sheet 4 Reactor Coolant System 541F091 541F445 Sampling System 541F092 541F448 Chemical-& Volume Control 684J741 695J175 Waste Disposal System 684J971 684J971 Section 2 Section 2 Main and Reheat Steam M-201 M-2201 Sheet 1 Sheet 1 Service Water M-207 M-20's Sheets 1,2,3,4 Sheets 1,2,3,4 Service Air M-209 M-209-

- Instrtanent Air M-209 M-209-Sheet 5 Sheet 5 .

Auxiliary Steam, Heating Steam,

~ Chilled & Hot Water  !!-214 M-2214 Heating & Ventilation M-215 M-2215 Auxiliary Feedwater System M-217 M-217 Containment Venting-System M-224 M-224 Emergency Diesel Generator M-209 -

Air Start System Sheet 10

Deionized and Reactor Makeup Water PBM-231 PBM-231 F

i

~

I. 'l e . .

l l

l Section 2.0 i Page 5 2.5 Request for Relief l Where ASME Section XI requirements were determined to be impractical, ,

a request for relief was written. These requests were developed to the j guidelines suggested in an NRC letter dated January, 1978 (see Appendix B)  ;

and a subsequent meeting on November 1, 1983, with the NRC. l l

2.6 Explanation of Abbreviations and Notes 2.6.1 Abbreviations See attached charts. i

~ l 2.6.2 Notes 2.6.2.1 Valves

1. This valve is checked for locked closed or l I

locked open position.

2. This valve is a pressure relief valve and will Le tested at the frequency stated in IWV-3511.

3. This valve is a passive valve and does not require testing.

4. Exercising this valve during operation could result in overpressurization of a low prassure system if upstream pressure isolation check valves should leak

. through. There are no pressure monitors installed on the high pressure side of the subject valve to determine status of upstream pressure-isolation valves. l 4a. Exercising this valve during operation is not possible because the reactor coolant system

i. pressure is higher than the safety injection pump discharge pressure (1500 psig) and the accumulator pressure (700 psig).

l S. Exercising this valve during operation is not advisable as the valve alignment required to facilitate valve stroking would-prevent boric acid from reaching the safety injection pump suctions.

6. All motor operated valves fail-as-is and therefore do not require a fail safe test per IWV-3415.

( 7. This valve is exercised during normal operation l and therefore does not require a separate test.

l h

L_.

Section 2.0 Page 6

8. This valve is tested when the containment spray system is tested per Technical Specification.

9. This valve-is A passive and will only receive a seat leakage test.

10. The seat leakage test for this. valve will be performed in accordance with 10 CFR 50, Appendix J requirements.

11. This valve is within a nonsafety-related system, however, it is used for containment isolation and therefore will receive a seat leakage test in accordance with 10 CFR 50, Appendix J requirements.

. 12. The valve alignment required to facilitate valve

.- testing during power operation would isolate sodium hydroxide from the spray system.

12a. Full stroke exercising this valve during operation is not possible because the residual heat removal pump discharge pressure cannot overcome reactor coolant system pressure and the recirculation line is not capable of passing the required flow.

13. Exercising this valve during operation would cause a loss of cooling water to the reactor coolant pump, which could result in damage to the pump.

14. It is the NRC's position that the PORV's be exercised at cold shutdown.

15. The PORV block valve will normally be stroke exercised

! during operation. If a PORV is isolated per the Technical Specifications, the block valve will then

be exercised at cold shutdown, not operation.

l

16. Exercising this valve during power operation produces transients in the charging and letdown system.

l These transients affect seal injection flow to the reactor coolant pumps and could result in pump seal damage.

17. Exercising this valve during power operation will cause isolation of main steam flow resulting in a turbine-reactor trip.

p , - - . ,

l 6 .

's Section 2.0 Page'7

18. Exercising this valve results in securing service water to the turbine hall. The major components relying on service water cooling in the turbine hall includes the main turbine, main generator, steam generator feedwater pumps and condensate pumps. Thus, exercising this valve during operation could result in significant damage to secondary plant equipment.

19. Exercising this valve during operation would result in thermal shocking the auxiliary feedline to main feedline nozzle.

20. During operation, full stroke exercising of these valves would require injection of relatively cold auxiliary feedwater to the steam generators since

.the recirculation line cannot pass the required flow. This would result in thermal shocking the auxiliary feedline to main feedline nozzle.

21. Exercising this valve during power operation will cause an interruption of feedwater flow which would result in a reactor trip.

22. These valves are not accessible during power operation due to their location within the reactor containment building.

23. During normal operation, the subject valve is shut and the system / subsystem containing the valve is out-of-service. Thus, s roke testing the subject valve on~ a quarterly basis is not required during this period, per IWV-3416. Prior to returning the system to a operable status, the valve will be exercised and the code required schedule will be resumed.

24. This va'lve must be locked closed and may not be opened unless the reactor is in a cold shutdown or refueling shutdown condition, per the plant's Technical Specifications. As long as the subject valve is maintained locked closed, the system is considered to be out-of-service. Thus, quarterly stroke testing of the subject valve, during any plant condition in which it is locked .losed, is not required per IWV-3416. Prior to returning the system to 'anoperable status, the valve will be exercised, and the code required schedule will be resumed.

i

?

I~

N h- , ,

INSERVICE TESTING PROGRAM '

ASME CLASS 1, 2 & 3 VALVES Revision 1 WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil NUCLEAR PLANT Page UNIT System Explanation of Abbreviations lP&ID 0 a b*

%j k 8 8 a e v

. .% . .  % ~D 2R i  %;

Valve No e

O d 33 3a 3*

y0 yM yh 3*

M Et

$ 8, ja mj

1. 4 jR d&

$@ gM $$ Remarks GA GATE GL GIDBE .

CK Cl!ECK SCK STOP CIIECK SV SAFETY RV RELIEF BTF l BITITERFLY DIA DIAPHRAGM SO SOLENOID AO AIR OPERATOR SA SELF ACTUATED MO MOTOR OPERATOR M MANUAL AT SEAT LEAK TEST FULL STROKE BT EXERCISE TEST

1-

~

. e S',

h O 2>

z Ck

= =z Om e 2

h h b C

t ot ni O 't H

> ~ mm z m z o 2

• <  ; d me t aS 5 a m

y 3 94 E O E EMe E NHx 4 em em = e m m' 8 4 E se g$e *a Cm a 8s " m9 M

a O

E h$ > H H k knt ot nr >O dt

'82 98 d8 EW mm mm ~e H e gm5 Q R-= g W e

8* en sH ss s 8 92 M na 5 s

$Y$

m o e. tseuqeR feileR emit ekortS mumixaM edoM Q 5 tseT Q 7 g y @

4 m

tseT N g N m

U n 3" noitceriD C ekortS O

o, noitisoP lamroN epyT rotautcA epyT evlaV m

O eziS M

.[O evlaV 2 r

@ yrogetaC O

@ T evlav Bn rP E $ "z

• o ssalC

@$m@

m d* W x s:

o U* n$ E Q"j@ g setanidrooC N '$ $

m N dt E

t e ni m=n x m

m ne z v n>H jrt o H dt n( Dt z an8* i a z nr H O N m H > 5 O' AT <

r: -

& +r..m ,Q

" Section 3.0 i

' Revision 1 i

01- 06-8h INSERVICE TESTING PROGRAM - PUMPS 3.1 UNIT 1 l

I -

l l .

I e

4 INSERVICE TESTING PROGRAM ,3 ASME CLASS 1, 2 & 3 PUMPS Revision 1 WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 1 UNIT 1 TEST PARAMETERS Pump P&ID and Lube Inlet Diff Flow I Brg Numbar Pump Name Coordinates Level Speed Press Press Rate Vib Temp Relief Request 110E018 RR-1, 4 P10A Residual Heat Removal D-8 Yes NA Yes Yes No Yes Yes Notes- 1, 3 110E018 RR-1, 4 P10B Residual Heat Removal C-8 Yes NA Yes Yes No Yes Yes Notes- 1, 3 110E017 RR-1, 6 P14A Containment Spray I-7 Yes NA Yes Yes' No Yes Yes Notes- 1, 2 110E017 RR- 1, 6 P14B Containment Spray C-7 Yes NA Yes Yes No Yes Yes Notes- 1, 2 110E017 RR-1, 3 PISA Safety Injection I-8 Yes NA Yes Yes No Yes Yes Notes- 1, 2, 3 110E017 RR-1, 3 Pl5B Safety Injection H-8 Yes NA Yes Yes No Yes Yes Notes- 1, 2, 3 M-217 RR-1, S P29 Auxiliary Feed (Turbine) B-4 Yes Yes Yes Yes No Yes Yes Note- 1 M-207 RR-1, 7, 8 P32A Service Water D-1 No NA Yes Yes No Yes No Notes- 1, 4, 5 M-207 RR-1, 7, 8 P32B Service Water D-1 No NA Yes Yes No Yes No Notes- 1, 4, 5 M-207 RR-1, 7, 8 P32C Service Water D-1 No NA Yes Yes No Yes No Notes- 1, 4, 5 M-207 RR-1, 7, 8 P32D Service Water F-1 No NA Yes Yes No Yes No Notes- 1, 4, 5 M-207 RR-1, 7, 8 P32E Service Water F-1 No NA Yes Yes No Yes No Notes- 1, 4, 5

• ~

t 5 s

e ,

u q

4 8

1 e ,

R ,1 7 51 5 1 f -

T e , s , - ,

I i 1 e 1 e 1 e N l - t - t - t U e R o R o R o R RN RN PN p s s gm o e e re N Y Y 1 BT n4 o8 b s s s i 2 i e e e

- s6 V Y Y Y i0e

- vg

- e1 a R0P we ot o o l a o FR N N N S

R s E f s s s s T f e e e e E i r M DP Y Y Y A

R A

P t s es s s s T l e e e e S nr Y Y Y E I P T

d e

e p A A A S N N N l

ee b v s s ue o e e LL N Y Y s

e t

d a 7 7 7 nn 01 14 14 ai 2 - 2 - 2 -

- d - F - D - F Dr M M M I o

& o PC Y

N A

P ) )

M r r O o o C t t MS T o o J APRN M M RMEA ( (

- GUWL OPOP e d d e

R P m r e P3 R a e e e CA N t F F G&I E a y N RL p W r y

I 2TC m r T ,CU u e a a

_ S EN P c i i E1 L i l l vr T EH i i S C x x ESNA e u u CAI E S A A I LSB VCN R OT

_ EECN

_ SMSI r NSI O e F A B I AWP pb 2 8 8 mm 3 3 3 uu P P P PN

f^

• /

INSERVICE TESTING PROGRAM - PIJMPS 3.2 UNIT 2 i

p

-' -r-- - --, . . . __ ._ ,

• ' ' ' - v ----.-

INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 PUMPS 7evision 1 WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 1 UNIT 2 TEST PARAMETERS Pump P&ID and Lube Inlet Diff Flow" Brg Number Pump Name Coordinates Level Speed Press Press Rate Vib Temp Relief Request 110E029 RR-4 P10A Residual Heat Removal D-8 YES NA YES YES NO YES YES Notes 1, 3 110E029 RR-4 P10B Residual Heat Removal C-8 YES NA YES YES NO YES YES Notes 1, 3 110E035 RR-6 P14A Containment Spray I-7 YES NA YES YES NO YES YES Notes 1, 2 110E035 RR-6 P14B Containment Spray C-7 YES NA YES YES NO YES YES Notes 1, 2 110E035 RR- 3 PISA Safety Injection I-8 YES NA YES YES NO YES YES Notes 1, 2, 3 110E035 RR- 3 P15B Safety Injection H-8 YES NA YES YES NO YES YES Notes 1, 2 , 3 M-217 RR- 5 P29 Auxiliary Feed (Turbine) G-4 YES YES YES YES NO YES YES Note 1 9

t

- _ _ _ _ - - _ _ - - _ - - _ - - - - - - - _ - - L-- - - - - - - - - - - -- - - - -

1 - %.s

_,f' APPENDIX __A REQUEST FOR RELIEF FOR PUcIPS

PUMP RELIEF REQUEST NO. 1 System: Safety Related,. Unit'1 Component: - All' pumps-in the program--

Class: ' 2 and 3

- Function: .To provide flow to safety systems

- Test' Requirement: Comply with the requirements of Section XI of the ASME' Boiler and Pressure Vessel Code, Division 1, 1977 Edition and Addenda through Sumer,1978, per the requirements of 10 CFR 50.55a..

' Basis For Relief: To achieve identical inspection basis for both PBNP units

' for the Section XI pump and valve inservice testing program.'

Alternate

- Testing: Comply _with the requirements of Section XI of the ASME Boiler

- and Pressure Vessel Code, Division 1,'1977 Edition and Addenda through Summer, 1979.

i d

- , 4- 4,,- - , -,,,-...--,,------m , , , , , , .m,y,- e,-, - - - , ,p- - ,ry , - - - w,--j

PUMP RELIEF REQUEST NO.-2 System: Safety Belated, Units 1 and 2 Component: All pumps in the program

-Class: 2 and 3 Function: To provide flow to safety systems Test

' Requirement: To test the pump nominally each month (IWP-3400a)

Basis For Relief: Industry data indicates that monthly testing of pump operating parameters ik not necessary to_ assure the reliability of'a safety grade pump. In fact, the acceptability of assessing a pump's operational readiness through a testing program based

-on a three month interval is evidenced by the recommended

. program contained in the'1980 edition of Section XI of the ASME Boiler and Pressure Vessel Code.

' Alternate Testing: Test the pump nominally every three months during ncrmal plant operation.

a , .

a;. - ..

PUMP RELIEF REQUEST NO. 3 System: Safety Injection, Units 1 and 2 Component: P15-A&B' Class: 2 Function: To provide high pressure injection flow for cold leg and core deluge safety injection modes.

Test Requirement: The resistance of the system shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference va.'.ue.

Each inservice test shall include the measurement and obser-vation of all quantities in Table TWP- 3100-1 except bearing temperatures, which shall be measured during at least one inservice test each year.

Basis For Relief: The inservice testing is accomplished by operating the pumps in a recirculation mode through a flow-restricting orifice.

The flow-restricting orifice ensures a fixed-resistance, fixed-flow condition near the horizontal portion of the pump curve which is associated with shutoff head, therefore, flow measuring instrumentation is not indicative of pump performance and consequently does not provide meaningful information in this portion of the pump curve.

Alternate Testing: During each inservice test, establish the recirculation mode system resistance via the fixed flow-restricting orifice.

Measure or observe all required parameters, except flow, and analyze these values per IWP-3200. During reactor refueling outages, when design system flow testing can be achieved, vary the system resistance to obtain flow and develorjed

. pump head data at three points along the pump curve and

[ - analyze these values per IWP-3200 with respect to the applicable reference values.

i

~

l l

L

. , , . . . ~ -. .. , -. . .. - - ,

, s. _ .

s.

J PUMP RELIEF REQUEST NO. 4 System: Safety Injection, Units 1 and 2

, Compon'ent: P10-A & B

' Class: 2 Function: To provide low pressure injection flow for cold leg and core deluge safety injection modes.

r Test Requirement: The resistance of.the system'shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference value.

Each inservice test shall include.the measurement and obser-I vation of all quantities in Table'IWP-3100-1 except bearing temperatures, which shall be measured during.at least one

. inservice test each year.

I Basis For Relief: The inservice tasting is accomplished by operating the ptsaps i in ' a recirculation mode through a flow-restricting orifice.

I The flow-restricting orifice ensures a fixed-resistance, fixed-i flow condition near the horizontal portion of the pump curve which is associated with shutoff head, therefore, flow

{ ' measuring instrumentation is not indicative of pump performance and consequently does not provide meaningful information in

this portion of the pump. curve.

Alternate Testing: During each inservice test, establish the recirculation mode system resistance via the fixed flow restricting orifice.

Measure or observe all required parameters, except flow, and analyze these values per IWP-3200. During reactor refueling outages, when design system flow testing can be achieved,

[ vary the system resistance to obtain flow and developed pump head data at three points along the pump curve and analyze these values per IWP-3200 with respect to the applicable

,- reference values.

l' s

i.

i-t

PUMP RELIEF REQUEST NO. 5 System: Auxiliary Feedwater, Units 1 and 2 Component: P29, P38-A E B Class: 3 Function: To provide auxiliary feedwater flow to the steam generators for heat removal.

Test Requirement: The resistance of the system shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference value.

Each inservice test shall include the measurement and obser-vation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one inservice test each year.

Basis For-Relief: The inservice testing is accomplished by operating the pumps in a recirculation mode through a flow-restricting orifice.

The flow-restricting orifice ensures a fixed-resistance, fixed-flow condition near the horizontal portion of the pump curve

- which is associated with shutoff head, therefore, flow measuring instrumentation is not indicative of pump performance and consequently does not provide meaningful information in this portion of the pump curve.

Alternate Testing: During each inservice test, establish the recirculation mode system resistance via the fixed flow restricting orifice.

Measure or observe all required parameters, except ficw, and analyze these values per IWP-3200. During cold shutdown conditions, when design system flow testing can be achieved without thermal shocking the auxiliary feedwater line to feed-line nozzles, obtain flow and developed pump head data with system operation at or near design conditions. Analyze this data per IWP-3200 with respect to the applicable reference values.

-o -

PUMP RELIEF REQUEST NO. 6 System: Containment Spray, Units l'and 2

- Component: P14-A & B Class: 2 Function: To provide containment atmospheric heat-removal and, if needed,

- iodine removal.

- Test

. Requirement: The resistance of the system shall be varied until either the .

-measured differential pressure or the measured flowrate equals the corresponding reference value.

Each inservice test shall include the measurement and obser-vation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one

~

inservice test each year.

, Basis For Relief: The inservice testing is accomplished by operating the pumps in-a recirculation mode through a flow-restricting orifice.

The flow-restricting orifice ensures a fixed-resistance, fixed-flow condition near the horizontal portion of the pump curve which is associated with shutoff head, therefore, flow measuring instrumentation is not indicative of pump performance and consequently does not provide meaningful information in this portion of the pump curve.

Alternate Testing: During each inservice test, establish the recirculation mode system resistance via the fixed flow restricting orifice.

Measure or observe all required parameters, except flow, and analyze these values per IWP-3200.

e

-y--

PUMP RELIEF REQUEST NO. 7 System: ' Service Water, Units 1 and 2

. Component: P32- A , B , C , D , _ E , F Class: -3 Funct' ion: To provide _ vital cooling water to safet'y related equipment.

Test.

-Requirement: To vary system. resistance until a reference.flowrate is achieved ~then measure flowrate and AP.

Basis For

• Relief: Normal plant operation requires a minimum of two pumps to be in operation on-a fixed resistance system. With the system resistance the same for each test of paired pumps, a measured AP is' indicative of pump performance.

Alternate Testing: Operate a given. pair of pumps on a fixed resistance system, measure AP and compare the measured AP.to a reference value for the same flow condition. Perform periodic maintenance inspections (such that each pair of pumps is inspected once during every 10 year ISI interval) on paired pumps to determine ,

if mechanical andfor hydraulic degradation is occurring.

s PUMP RELIEF REQUEST NO. 8 System: Service Water, Units 1 and 2

Component: 32-A, B, C, D, E, &-F Class: 3 Function: To provide vital cooling water to safety related equipment.

Test

. Requirement: Measure bearing temperature and' lubricant level.

Basis For 1 - Relief: These pu ps are vertical water lubricated sump pumps located in the-circulating water forebay. The pump bearings are submerged in the forebay and are inaccessible for temperature measurements. Lubricant level 1.s also inaccessible and will not be observed.

Alternate Testing: None s

M w,

c -. . _

> l%,

Section h.0

' ?"

Revision 1 01-06-8h INSERVICE TESTING PROGRAM - VALVES 4.1 UNIT 1

D INSERVICE TESTING PROGRAM

> ASME CLASS 1, 2 & 3 VALVES Revision 1 (

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil NUCLEAR PLANT Page 1 UNIT 1 System SAFETY INJECTION SYSTEM P&ID 110E017 Sheet 1

. m o e e R $ B ~3 .Y  ? . m#

%  : #T 8. 8. j. lt te o u. Jt **

Valve No O o

M o

YN ya YM

>m Yb

>g ,o cgk c$

a p, MM ma g $3 gx 5M xm gg Remarks 834-A J-10 2 B 1" GL AO C C NA Note 3 834-B F-lO 2 B 1" GL AO C C NA Note 3 834-C J-6 2 B 1" GA M O O NA Note 3 I

835-A 11 - 1 0 2 B 1" GL AO C C NA Note 3 835-B E-10 2 B l?' GL AO C C NA Note 3 839-A F-8 2 B 3/4 " GL AO C C NA Note 3 839-B F-9 1 B 3/4" GL AO C C NA Note 3 839-C F-9 2 B 3/4" GL AO C C NA Note 3 839-D F-8 1 B 3/4" GL AO C C NA Note 3 841-A 11 - 1 1 2 B 10" GA MO O O NA Notes 3, 6 841-B E-ll 2 B 10" GA MO O O NA Notes 3, 6 AT OP VRR-842-A 11 - 1 2 1 A/C 10" CK SA C O CVp ECS y9 cvT *RR AT UP VRR-842-B E-12 1 A/C 10" CK SA C O @@ EQ[ 19 843-A I-10 2 B 3/4" GL M C C NA Note 3 843-B E-10 2 B 3/4" GL M C C NA Note 3 J

b INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VALVES Revision 1 p WISCONSIN ELECTRIC POWER COMPANY - 01-06-84 POINT BEACH NUCLEAR PLANT Page 2 UNIT 1 System SAFETY INJECTION SYSTEM P&ID 110E017 Sheet 1

= e

$ c M y b 8 8 3 ," e c = .& . . # t "U i '

8 33 38 3* 3* "$ 1 j* # t.8 -

8 4&

Valve No O $ y0 $M j M $$ mY $ $j $ $$ Remarks 844-A I-ll 2 B 1" GL AO C C NA Note 3 844-B E-ll 2 B 1" GL AO C C NA Note 3

^

845-A H-12 1 A/C 2" CK SA C O VRR-2 845-B D-12 1 A/C 2" CK SA C O RR VRR-2 845-C G-12 1 A/C 2" CK SA C O VRR-2 RR 845-D D-12 1 A/C 2" CK SA C O VRR-2 845-E E-12 1 A/C 2" CK SA C O VRR-2 845-F G-12 1 A/C 2" CK SA C O p VRR-2 a1 xx 846 J-5 2 A 1" GL AO O C BT OP 4.5 VRR-0 Note 11 FST OP 850-A B-8 2 B 10" GA MO C O BT OP 10 Note 6 850-B B-ll 2 B 10" GA MO C O BT OP 10 Note 6 851-A B-5 2 B 10" GA 10 C O BT OP 130 Note 6 851-B A-5 2 B 10" GA MO C O BT OP 133 Note 6 852-A C-12 2 B 6" GA MO C O BT CS 15 Notes 4, 6 852-B C-12 2 B 6" GA MO C O BT CS 15 Notes 4, 6 s

INSERVICE TESTING PROGRAM #

ASME CLASS 1, 2 & 3 VALVES Revision 1 WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 3 UNIT 1 System SAFETY INJECT 70N SYSTEM P&ID llOEOl7 Sheet 1

= .

j .e b 8 8 C

a s" o e . . .

An 3 "' 3* $1

1. ~t at t.8

j. 18 8 8 33 38 t jgM e d a.

Valve No j $ $$ $M jh jh jj us t $ $j $$ Remarks CVP E-CS 853-A C-12 1 A/C 6" CK SA C O VT RR VRR-3 c

853-B C-12 1 A/C 6" CK SA C O EFr AT ras E-CS VRR-3 CVP E-CS 853-C C-14 1 A/C 6" CK SA C O (( gRCS VRR-3 CVP E-CS 85 3--D C-14 1 A/C 6" CK SA C O [ kcq VRR-3 861-A C-8 2 C 3/4" RV SA C O RVT Note 2 866-A H-5 2 B 4" GA MO O O NA Note 3 866-B H-5 2 B 4" GA MO O O NA Note 3 CVP E-CS 867-A H-13 1 A/C 10" CK SA C O C VRR-4 867-B E-13 1 A/C 10" CK SA C 0 gy Note 4A 878-A D-12 2 B 2" GL MO C O BT CS 15 Notes 4, 6 878-B D-12 2 B 2" GL MO O O NA Note 3 878-C G-12 2 B 2" GL MO C O BT CS 15 Notes 4, 6 878-D G-12 2 B 2" GL MO O O NA Note 3 878-E E-12 2 B 2" GL M O O NA Notes 1, 3 878-F F-12 2 B 2" GL M O O NA Notes 1, 3

b INSERVICE TESTING PROGRAM Revision 1 '"

ASME CLASS 1, 2 & 3 VALVES WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page'4 UNIT 1 System SAFETY INJECTION SYSTEM P&ID 110E017 Sheet 1 N ~ . 8 e e

M o N HM e'N E e uN

? $ $$ 5e 5e fe fN be e oe b$ $*

Valve No O U *

• u o >0 > un > cc 2 p. un o a ex x u) mm Remarks 4

887 E-6 2 C 3/4" RV SA C O RVT Note 2 830-A J-10 2 C 1" RV SA C O RVT Note 2 830-B F-10 2 C 1" RV SA C O RVT Note 2 957 I-6 2 A 1" GL AO C C AT RR Note 10

l ._

0

INSERVICE TESTING PROGRAM ,

ASME CLASS 1,'2 & 3 VALVES Revision 1 'f WISCONSIN ELECTRIC POWER COMPANY 01-06-84

- POINT BEACl! NUCLEAR PLANT Page 5 UNIT 1 _

System lP&ID 110E017 Sheet 2 e .

? c b d

a t' 8 8

1. - ~t Et J! r"

• u .

. .? . . i t i.

8 la 33 A* A* 3* j' # #4

• 8 a Valve No 0 d jO yM jh Mh @E R m$ t $. $j M $$ Remarks 825-A H-5 2 B 10" GA MO .C O BT OP 20 Note 6

• L 825-B 11 - 5 2 B 10" GA MO C O BT OP 20 Note 6 6 825-C 11 - 5 2 B 2" GA TO O O NA Note 3 826-A J-6 3 B 8" GA MO O O NA Notes 3, 6 826-B J-7 3 B 8" GA MO C O BT CS 15 Notes 5, 6 826-C J-7 3 B 8" GA MO C O BT CS 15 Notes 5, 6 827-A J-8 3 B 8" GA M O O NA Note 3 827-B J-8 3 B 8" GA M O O NA Note 3 829-A 11-11 2 B 4" GA M C C NA Notes 1, 3 829-B 11 - 1 1 2 B 4" GA M C C NA Notes 1, 3 854-A E-4 2 C 10" CK SA C O CVT RR VRR-6 854-B E-4 2 C 10" CK SA C O CVT RR VRR-6 i

P 856-A E-4 2 B 10" GA MO O O NA Notes 3, 6 856-B E-4 2 B 10" GA MO O O NA Notes 3, 6 857-A F-8 2 B 6" GA M C C NA Note 3

4

)

INSERVICE TESTING PROGRAM

• ASME CLASS 1, 2 & 3 VALVES ' Revision 1 -

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACli NUCLEAR PLANT Page 6 UNIT 1 System ' SAFETY INJECTION EYSTEM P&ID 110E017 Sheet 2 C

a b 8 8 a e"* u 6 . .& . . # ~t *t i 1 8  :

y A3 An A* 3* $% j*

my t te -

d8 Valve No O y0 $M j M @M $ $$ $$ Remarks 857-B F-7 2 B 6" GA M C C NA Note 3 876-A F-9 2 B 2" GL M O O NA Notes 1, 3 876-B F-9 2 B 2" GL M O O NA i Notes 1, 3 879-B F-13 2 B 3/4" GL M C C NA Notes 1, 3 884 F-lO 2 B 3/4" GL M ,

C C NA Notes 1, 3 888-A I-10 2 B 6" GA M O O NA Notes 1, 3 888-B 11 - 1 0 2 B 6" GA M O O NA Notes 1, 3 889-A I- 10 2 C 6" CK SA C O pp VRR-7 889-B 11 - 1 0 2 C 6" CK SA C O VRR-7 891-A G-10 2 C 2" CK SA C O CVT OP 891-B G-9 2 C 2" CK SA C O CVT OP 894 11 - 5 2 B 2" GL M O O NA Note 3 895 11 - 5 2 C 2" CK SA C C NA Note 3 896-A I-7 2 B 6" GA MO O O NA Notes 1, 3, 6 896-B 11 - 7 2 B 6" GA MO O O NA Notes 1, 3, 6

s k

r 1 a

. m e

T R I 9 N

U 1

. 3 n' 4 e o8 7 t i-s6 o

.- i0e N vg e1 a O R0P N fg 0 R R u sM R R V V 4

2 E .ttm 5 5 t

e

$ ullE 4 4 e

h S .s*-

,:E 4 PP 7

1 0

E 4 7 T ,

0 ,:E $ A 1 d 1 i 3

bY:aC D 5dm C C C I

P ada8p.

l a 0 0z O O C

)

4Oa!< O O A A M

.e( 4 gs> L L L G G G

_ .am "

M ss> "

2 2

4

/

Y 3 E

l N

A P

T S goeuu M Y

_ O S ss> B B B SC ME T N AVRN O RLEA I GAWL T OVOP R P C

E

ao 2 2 2

. P3 R J CA N G&IE I N RL 1 1 3 I2TC Y T

NM 8u H H

I T

S ,CU EN E E1L F T EH A S C S ESNA CAI E o ILSB N VCN m A B R OT e e - -

EECN t v 7 9

7 9

8 9

SMST s l 8

NSIO y a 8 8 I AWP S V

. ~

INSERVICE TESTING PROGRAM +

ASME CLASS 1, 2 & 3 VALVES Revision 1 -

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil NUCLEAR PLANT Page 8 UNIT 1 System SAFETY INJECTION SYSTEM P&ID 110E017 Sheet 3 m .

? a b C 8 8 3

• a e

bl = .? . .  % ~d At* i '

8 33 A A* 3* Et j$ # t.8 ja da Valve No O $ $$ yM y M @M m $ $$ gM $$ Remarks-831-A F-6 3 B 2" GL M O O NA Notes 1, 3 831-B E-7 3 B 2" GL M O O NA Notes 1, 3 831-C D-7 3 B 2" GL , M C C NA Notes 1, 3 831-D D-6 3 B 2" GL M C C NA Notes 1, 3 840-A G-5 3 C 3/4" VB SA C O CVT RR VRR-5 840-B G-5 3 C 3/4" VB SA C O CVf RR VRR-5 847-A 11- 8 2 C 2" CK SA C O CVT OP 847-B D-8 2 C 2" CK SA C O CVT OP 858-A I-3 2 C 6" CK SA C O VRR-8 858-B C-3 2 C 6" CK SA C O R VRR-8 860-A I-10 2 B S" GA MO C O BT OP 15 Note 6 860-B I-10 2 B 6" GA MO C- O BT OP 15 Note 6 860-C C-10 2 B 6" GA MO C O BT OP 15 Note 6 860-D C-10 2 B 6" GA 10 C O BT OP 15 Note 6 cvT RR 862-A I-11 2 A/C 6" CK SA C O AT RR VRR-9 Note 10

.~ _ . - ., __ , .

INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 ..-

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil NUCLEAR PLANT Page 9 UNIT 1 System SAFETY INJECTION SYSTEM P&ID 110E017 Sheet 3

$ c M j t' 8 8 S e"' o e . .a . .  % ~t *t i  %:

Valve No O 0

A*

y$

Aa y "M A*

3*

M l1 a*

'O M N$

t te ja gM d8

-$ $ Remarks CVT RR 862-B C-ll 2 A/C 6" CK SA C O AT RR VRR-9 Note 10

'q 863-A F-5 3 B 3/4" GL M C C NA Note 3 868-A I-12 2 B 6" GA M O C NA Notes 1, 3 868-B C-12 2 B 6" GA M O O . NA

• Notes 1, 3 870-A I-3 2 B 6" GA MO O O NA Notes 1, 3, 6 8

1 870-B C-3 2 B 6" GA 10 O O NA Notes 1, 3, 6 871-A I-5 2 B 6" GA MO C O BT OP 15 Note 6 I

871-B C-5 2 B 6" GA MO C O BT OP 15 Note 6 i 874-A II-8 2 B 2" GL M O O NA Notes 1, 3 874-B D-8 2 B 2" GL M O O NA Notes 1, 3 IICV-836- A F-7 3 B 2" GL AO C O 20 Note 12 IICV-836-B E-7 3 B 2" GL AO C O FfT 20 Note 12 C

872 G-6 3 C 3/4" RV SA C O RVT 864-A 11-11 2 B 3/4" GL M C C AT RR Note 10 a

864-B C-11 2 B 3/4" GL M C C AT RR Note 10

INSERVICE TESTING PROCRAM '

ASME' CLASS 1, 2 & 3 VALVES Revision 1

• WISCONSIN ELECTRIC POWER COMPANY 01-06-84

, POINT BEACH NUCLEAR PLANT Page 10 UNIT 1 System AUXILIARY COOLANT SYSTEM P&ID 110E018 Sheet 1 m .

? a b a

a b 8 5 a e"* u m .& . . # ~t *t i 1:

Valve No O 8

3? An A*

$0 $M $

B*

Et j' jS mj

1. 4

$j ja gM yj da Remarks 700 B-13 1 B 10" GA MO C C NA Notes 3, 6 701 B-13 1 B 10" GA MO C C

• NA Notes 3, 6 704-A D-9 2 B 8" GA M O O NA Note 3 t

704-B C-10 2 B 8" GA M O O NA Note 3 709-A D-6 2 B 8" GA M O O NA Notes 1, 3 709-B D-5 2 B 8" GA M O O NA Notes 1, 3 710-A D-6 2 C 8" CK SA C O Note 12A 710-B C-6 2 C 8" CK SA C O g Note 12A f

712 F-ll 2 B 3/4" GL M C C NA Note 3

713-B D-5 2 B 8" GA M C C NA Note 3 i

j 714-A E-8 2 B 6" GA M O O NA Note 3 715-A F-7 2 B 8" GA M O O NA Notes 1, 3 l

715-B F-5 2 B 8" GA M O O NA Notes 1, 3 i

l 715-C F-7 2 B 1" GL M -

C C NA Note 3 716-A G-10 2 B 8" GA M O O NA Notes 1, 3

INSERVICE TESTING PROGRAM +

ASME CLASS 1, 2 & 3 VALVES Revision 1 ..

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACl!-NUCLEAR PLANT Page 11 UNIT 1 System AUXILIARY COOLANT SYSTEM P&ID 110E010 Sheet 1 m .

$ c M f

e .

D o

S t at 0 E i * %:

v 8 a 33 3* 3* B* "E t j* # t.8 da Valve No j y yj jM yh jh jj mj j jy 38 gj jj Remarks 716-B G-10 2 B 8" GA M O O NA Notes 1, 3 716-C G-10 2 B 8" GA M C C NA Note 3 716-D G-10 2 B 8" GA M C C NA Note 3 720 D-13 1 B 10" GA MO C C NA Note 3 733-A E-9 2 B 2" GL M O O NA Note 3 733-B B-9 2 B 2" GL M O O NA Note 3 742 11 - 1 0 2 B 8" GA M C C NA Notes 1, 3 IICV-624 G-9 2 B 8" BTF AO O O NA Note 3 IICV-625 G-9 2 B 8" BTF AO O O NA Note 3

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

INSERVICE TESTING PROGRAM -

i ASME CLASS 1, 2 & 3 VALVES Revision 1 ..

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page '12 UNIT 1 System AUXILIARY COOLANT SYSTEM P&ID 110E018 Sheet 2 c

N o 5 o a r< ,4 .Mc E 4

er s. p M a 2 so g 5. , ,.  ! s. : -

l Ualve No O O *

• 4 u o >U >m > 4 sc m p. mQ E4 E4 E Em MM Remark 8 1 i

i AT RR

754-A F-13 2 A 4" GA 10 0 C g, gg 15 Notes 6, 11, 13

754-B F-10 2 A 4" GA PO O C 15 Notes 6, 11, 13 T C 755-A 2

^ ~

j E-13 A/C 4" CK SA O C Note 11

~

755-B E-10 2 A/C 4" CK SA O C Note 11

]

759-A F-il 2 A 4" GA MO O C 15 Notes 6, 11, 13 759-B F-8 2 A 4" GA MO O C 15 Notes 6, 11, 13 C

767 E-7 2 A/C 2" CK SA O C Note 11 C

769 F-5 2 A 2" GL AO O C 4.5 VRR-O Note 11 4

1 1

INSERVICE TESTING PROGRAM -

ASME CLASS 1, 2 & 3 VALVES Revision 1 .-

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil NUCLEAR PLANT Page 13 UNIT 1 System AUXILIARY COOLANT SYSTEM P&ID 110E018 Sheet 4 o

m e C

b ko 8 a

8 e4 ,4 ev 3 e ci e M e a

E $ 5$ $* 5* $* 05 h$ # #8 h 55 Valve No O $ $$ $$ $ M @$ mN $ $0 xm j$ Remarks 811 11 - 9 2 B 2" DIA M C C NA Note 3 819 11- 9 2 B 2" GL M C C NA Note 3 820 C-7 2 B 2" GL M C C NA Note 3 m

INSERVICE TESTING PROGRAM -

AStiE CLASS 1, 2 & 3 VALVES Revision 1 **

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 14 UNIT 1 System REACTOR COOLANT SYSTEM P&ID 541F091 i

s ~ c 8 e 4 e M4  !

o O .Y . uM

E

8 8' E. E. jE lS t8 e u. 3% 4' Valve No 8 o

4 o

yo 14 ym 18 pp o 4p 0 8 a p.

D4 mo H

:S HE Mt Em th mm Ren: arks AT RR 508 H-12 2 A 2" DIA AO O C g OP 15 Note 11 528 H-ll 2 A/C 3/4" CK SA O C Note 11 AT RR ~

538 H-12 2 A 3/4" GL AO O C BT OP 15 Note 11 FST OP 549 D-6 1 B 3/4" GL M C C NA Note 3 PCV-430 H-5 1 B 3" GL AO C O BT CS 4.5 VRR-0 Note 14

• PCV-431-C I-5 1 B 3" GL AO C O BT CS 4.5 VRR-0 Note 14 PCV-434 I-7 1 C 4" RV SA C O RVT Note 2 PCV-435 I-6 1 C 4" RV SA C O RVT Note 2 515 I-5 1 B 4" GA MO O C BT 3P (CS) 60 Note 15 516 H-5 1 B 4" GA MO O C BT 2P (CS) 60 Note 15 529 H-11 2 C 2" C SA C C

^ ~

Note 11 595 H-12 2 A 1" DIA M O C Note 11 O

A 539 ,H-12 A 3/4" 2 GL AO O C m h.

m 15 Note 11 1 -

s k

y r a

m e

T R I 2 2 2 N 2 2 2 U , , ,

0 0 0 1 0 0 0 1 1 1 1 1 1 n4 5 s s s o8 1 e e e e e e t t t t t t i - o o o o o o s6 N M N N N N i0 e vg e1 a R0P o:.$

tn$

. " aeM 5 5 5 5 5 5 j 1 1 1 1 1 1 e$ Rg R RPP hS RPS PS 2

Rg R$ ROO bC ROC OC 9

0 p F p T T T T 1 $ T{, Tj, TTS hSTTS hS 4 Ap Ap ABF hFABF $P 5

Cate$

A- C C C C C C D

I P I $

l 8!h$

~ O O O O O O

- O O O O O O e#3M A A A A A A L L L L L L

.a$ G G G G G G n$ "

8 8

8 8

8 "8

.ay / / / / / /

3 3 3 3 3 3 Y

N A b&s$

P M .a$ A A A A A A O

SC M ME T E AVRN T RLEA S GAWL Y .:y 1 1 1 1 1 1 OVOP S R P P3 R G CA N 0 O 0 2 2 2 G&I E I 1 l 1 1 1 1 N RL L . je0y - - - - - -

I2 TC P G F E E F E T ,CU M S EN A E1L S T EH S C ESNA CAI E o ILSB N A B C VCN m e - - -

R OT e v 6 6 6 1 3 5 EECN t 6 6 6 5 5 5 SMSI s l 9 9 9 9 9 9 NSIO y a I AWP S V 1 i l

4

. ~

INSERVICE TESTING PROGRAM .

ASME CLASS 1, 2 & 3 VALVES Revisica 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 16 UNIT 1 4

Systtm CIIEMICAL & VOLUME CONTROL SYSTEM P&ID 684J741

- a 8 -

n sM eY  !

i M o O e uM P 0 4 a $5 l Valva No O y $0 $M $h Mh @M mY $ -$ j gm ja; Remarks 304-C A-14 1 A/C 2" CK SA O C Note 11 304-D A-15 1 A/C 2" CK SA O C Note 11 i

313 C-12 2 A 3" GA MO O C AT RR 15 Notes 11, 16, 6 BT CS ar MM i 313-A C-13 2 A 2" GA AO O C BT CS 15 Notes ll, 16 s FST CS 370 C-13 2 A/C 3" CK SA O C Note 11 371 D-13 2 A 2" GL AO O C ${ h$ 4.5 VRR-( Notes 11, 16 FST CS 371-A D-13 1 A 2" GL AO O C $h h$ 15 Notes 11, 16 .

FST CS 1296 A-14 1 A 2" GL AO C C AT RR Notes 9, 11 i

i i

i

INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VALVES Revision 1 .*

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACl! HUCLEAR PLANT Page 17 UNIT 1 System WASTE DISPOSAL SYSTEM P&ID 6845J971 Sheet 1

1. c b

a i

' 8 8 3 r*

• u

e . .& . . # ~t *t i 1

Valve No O

O $

A* An

$ [j yM A*

y 3* Et M @R jn mj t.8

$j n d B.

$$ Remarks 816 C-6 2 A 4" DIA M C C AT RR Notes 9, 11 -

AT RR 1003-A C-6 2 A 3" DIA AO O C gT OP 25 Note 11 AT' RR 1003-B C-6 2 A 3" DIA AO O C BT OP 25 Note 11 FST OP 1698 C-6 2 A 2" DIA AO C C AT RR Notes 9, 11 1713 B-5 2 A/C 2" CK SA O C Note 11 RR 1721 C-6 2 A 4" DIA AO O C bh bk5 75 Note 11 FRT nP 1723 D-6 2 A 3" DIA AO C C AT RR 30 Notes 9, 11 1728 D-6 2 A 3" DIA AO C C AT RR 30 Notes 9, 11 AT RR 1786 B-5 2 A 1" DIA AO O C BT OP 20 Note 11 vsT op 1787 B-S 2' A 1" DIA AO O C b rem bh no 15 Note 11 1788 B-5 2 A 3/4" DIA AO C C AT RR 10 Notes 9, 11 1789 B-5 2 A 3/4" DIA AO C C AT RR Notes 9, 11 1793 B-5 2 A 1" DIA M C C AT RR Notes 9, 11 i

INSERVICE TESTING PROGRAM .

ASME CLASS 1, 2 & 3 VALVES Revision 1 .-

WISCONSIN ELECTRIC POWER COMPANY 01-06-84

POINT BEACH NUCLEAR PLANT Page 18 UNIT 1 System MAIN AND REHEAT STEAM lP&ID M-201-1

19 N g 4 c b -

M o N HM .Y  ! . wN er s. s.

l

: g ga 5: , . . 15 : -

Valve No O U >U >m >h 0 sc 0

2 p. mo E1 E4 E Em gg Remarks CV-2015 H-7 2 B 6" GL AO C C NA Note 3 I

CV-2Ol6 E-7 2 3 6" GL AO C C NA Note 3 CV-2017 G-7 2 C 30" CK AO O C 4.5 VRR-0 Note 17 CV-2Ol8 D-9 2 C 30" CK AO O C 4.5 VRR-O Note 17 BT OP CV-5958 B-lO 2 B 2" GL AO O C FST OP 15 Note 10 AT RR CV-5959 E-10 2 B 2" GL AO O C NT OP 10 Note 10 TT RR CV-2083 B-9 2 B 3/4"' DIA AO O C NT b$ 4.5 VRR-O Note 10 AT RR CV-2084 F-9 2 B 3/4" DIA AO O C bT OP 4.5 VRR-0 Note 10 AT RR MS-126 C-5 2 B 3" GA M O O NA Notes 1, 3 MS-235 E-8 2 B 3" GA M O O NA Notes 1, 3 MS-237 F-8 2 B 3" GA M O O NA Notes 1, 3 MS-251 E-6 2 B 3/4" GA M O O NA Notes 1, 3 MS-252 F-6 2 B 3/4" GA M O O NA Notes 1, 3 MS-2017-A G-4 2 C 30" CK SA O C CVT CS Note 17 MS-2018-A D-4 2 C 30" CK SA O C. CVT CS Note 17

INSERVICE TESTING PROGRAM

' ASME CLASS 1, 2 & 3 VALVES Revision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 19 UNIT 1 Systrm MAIN AND REHEAT STEAM P&ID M-201-1

1. p u a 8 fs M o O aM eY b e wN p N M N '$

Valva No j d jO yM jh jh jj mj j jj m jj Remarks RV-2005 G-8 2 C 6" RV SA C O RVT Note 2 RV-2006 G-8 2 C 6" RV SA C O RVT Note 2 RV-2007 G -7 2 C 6" RV SA C O RVT Note 2 RV-2008 G-7 2 C 6" RV SA C O RVT Note 2 RV-2010 D-8 2 C 6" RV. SA C O RVT Note 2 RV-20ll D-8 2 C 6" RV SA C O RVT Note 2 RV-2012 D-7 2 C 6" RV SA C O RVT Note 2 RV-2013 D-7 2 C 6" RV SA C O RVT Note 2 SA-9 F-7 2 B 3" GA AO O C p 15

! TV-2082 B-5 2 3 2" DIA AO O C BT OP 4.5 VRR-0 MOV-2019 F-6 2 C 3" SCK MO C O CVT OP 20 Note 6 MOV-2020 E-6 2 C 3" SCK MO C O CVT OP 20 Note 6

$ INSERVICE TESTING PROGRAM ASME CLASS 1, 2'& 3 VALVES Revision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 20 UNIT 1 System SERVICE WATER P&ID M-207-1 l

N c M 0

D o o

s eu 0 e u

.o a -e4 -

o ma

? #!? 8. Eo j. [d s !! u u.  ! is 4*

Va1ve No U o

U >U >M >

o st

• o 35 p. MQ e

E4 sE E4 E 5U EM e

MM Remarks 4 D-2 3 B 24" BTF M O O NA Notes 1, 3 9 D-2 3 B 24" BTF M O O NA Notes 1, 3 10 D-1 3 B 16" BTF M O O NA Notes 1, 3 -

4 11 D-1 3 B 16" BTF M O O NA Notes 1, 3 12 D-1 3 B 16" BTF M O O NA Notes 1, 3 i

13 F-1 3 B 16" BTF M O O NA Notes 1, 3 9

14 F-1 3 B 16" BTF M O O NA Notes 1, 3 15 F-1 3 B 16" BTF M O O NA Notes 1, 3 l

16, G-2 3 B 24" BTF M O O NA Notes 1, 3 l 21 G-2 3 B 24" STF M O O NA Notes 1, 3 1

32-A D-1 3 C 16" CK SA C O CVT OP 32-B D-1 3 C 16" CK SA C O CVT OP l

32-C D-1 3 C 16" CK SA C O CVT OP i

32-D F-1 3 C 16" CK SA C O CVT OP i 32-E F-1 3 C 16" CK SA C O CVT OP

t 1

i INSERVICE TESTING PROGRAM 4

ASME CLASS 1, 2 & 3 VALVES Revision 1 -

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 21 UNIT 1 System SERVICE WATER P&ID M-207-1 m o

$* c M N

t'o 8 o

8 e4 we e9 3

s e

e u

w us

• 0 m o tn o e n yv xu l x ee

$ E 30 30 3* 3* RY $0 M MS '

dE y $h $$ mj Valve No O y6 yM M $ $$ jj Remarks 32-F F-1 3 C 16" CK SA C O CVT OP

.; 42 B-2 3 B 24" BTF M O O NA Notes 1, 3 43 B-3 3 B 4" GA M O 0 NA Notes 1, 3 47 B-4 3 8 8" GA M O O NA Notes 1, 3 T

48 B-3 3 B 6" GA M O O NA Notes 1, 3 49 B-2 3 B 6" GL M O O NA Note 3 i 57 C.-3 3 B 6" GA M O O NA Notes 1, 3 i

j 58 C-2 3 B 6" GL M O O NA Note 3 61 C-3 3 B 4" GA M O O NA Notes 1, 3 63 H-2 3 B 30" BTF M O O NA Notes 1, 3 l

l 129 E-7 3 B 4" GA M O 'O NA Notes 1, 3 132 E-5 3 B l}" GA M O O NA Notes 1, 3 132-B E-5 3 B 1)" GA M O O NA Notes 1, 3 133 D-5 3 B 13" GL M O O NA Notes 1, 3 i

j 140 B-5 3 B 8" GA M O O NA Notes 1, 3 1

1 ii4I'  ;!

i l l i: ji!ljl1lj

• 4 no MzitasOm 8mm8En mm8 +

>(n3tc nEcU n3 N "ew $r_gt a zeA mpha.

• 4 o

sHtO@tHz o tMmOj o gtj m @ tlU on@32 owlh A mOH2* t o 5Oz z geg =

• h

• n eo@ ,. ~

n cNto e t9 ncc itl<HQ 5aE menu 3bo4Iw s e e m t n i a y r n o T n r o o i

= e t i o t li et f s d s eg e e a at kc = k ee r

o s

a ve ve ve ue mi rs oe t te 4 o iu lt l z l p tp rr s sd xr l q

<mM<* zo o l aa ai ay cy oo ti e eo at ee E nW ot C C VC VS VT AT NP SD T TM MS RR NA* ?m w o t u: o t4 3 O O z> ZO w Wm N NN~ ?m w o wi o tam 2 O O z>

t ZO 2w Wm w MN^ ?m w o t

wi o t4 3 O O z> ZO w Hm w O<amwm ?w w o t u* o> g n O o t8 @ a*m #$io O<a mwo ?w w o t a* o> g n O o te @ a'm #$eo 2O?wme@ ?m w o t w# o tsm g O O m> ZO w Wm N, @

2O?wmwo ?m w o t wi toem g O O 2> ZO w Wo w, @

2O?wmeo 7w w o t u^= o tem g O O 2> ZO w Wm , O 3O?wmeW 7w w o t u"a o tem g O O 2> ZO w Ww w, @

n Nmi i<aoeo 7w w o t H*. nF g n O o tH @ uo

-

• l m

.N D(

d m

- =

n:

~

auw oaw @

?

7 4 l Qt awm mom tseuqeR feileR emit ekortS w

mumixaM edoM tseT 2 v

Y 8 tseT $

Y ,

noitceriD 3

U ekortS 0

m noitisoP

_ 3 lamroN epyT rotautcA 3 epyT evlaV g eziS

• evlaV m

' z l  % yrogetaC evlaV ot g<$n>zd m <t m $ w 8$@5 m m ssalC mw m 5, ,

"*n$ x

• l E N @ .p Q setanidrooC 7 N '$ $ d l mH dt c: o '

8 M llll M DC l m o m m mmz w 1 0>H$

s *t m ot z c

a EoO mmoz c

3 i

mxmm m w m

w zmH o M s>zm m <

I INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VAL'!ES Revision 1 .

WISCONSIN ELECTRIC PCiiER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 24 UNIT __

1 i

i I System ypqyyy ,g, lP&ID M-207-3 J

i M g u a b e 0 0 0 a0 ev l e ma

! %o #F H#e E.

• ES 18 o u. It d' l Valva No 8 d e av jO jY N ap jp yp Sh j2 Nu gg mb a

8 me

• y gg xm af jg Remarks I

! 286 G-6 3 B 12" GA M O O NA Note 3 i

t j 288 G-6 3 B 12" BTF M C C NA Note 3 289 G-5 3 B 12" BTF M C C NA Note 3-290 G-5 3 B 12" GA M C C NA Note 3 294 G-5 3 B 12" BTF M C C NA Note 3 295 G-5 3 B 12" BTF M C C NA Note 3 296 G-4 3 B 12" GA M O O NA Note 3 307 E-4 3 B 12" GL M O O NA , Note 3 322 E-6 3 B 12" GL M O O NA Note 3 MOV-2816 B-2 3 B 6" GA MO O C BT OP 40 Note 6 315 E-5 3 B 12" GL M O O NA Note 3 I I

282 H-4 3 B 20" BTF M O O NA Notes 1, 3 TCV-12A E-6 3 B 2" GA AO O O NA Note 3 TCV-12B E-4 3 B 2" GA AO O O NA Note 3  ;

BT OP TVLW-61 G-4 3 U 8" GA AO O C FST OP 10

(

R 9'

e #

ot W

~ n e

d =

E w m e IkE E g k z

78* -

OY $

wom tseuqeR feileR emit ekortS O * *

~ w w mumixaM edoM tseT 88 8 8 w

S tseT 5@ 8 8 b

3 noitceriD ekortS n e g U

0 T noitisoP

_ o o o lamroN epyT rotautcA g g g epyT evlaV o a a l eziS * *

• evlaV m m m l M l 2

@ yrogetaC l

evlaV m m e I h i Qn*

k$2 m w w w hhh 4* T g SSalC Tw = s ODgg M N m o e o SetanidrooC O  ? W 1

, E"RzNg e <

y " =

m 5

s Mm "r "m e  ?  ?

h 8 8

- gmm 2 b. 'm m anS"2 B a E ?  ?

km h h N

2 H >nr ET MO nf <

i

s k

1 r a

m e

T R I

N 3 3 3 3 3 U , , , , ,

1 1 1 1 1 1 3 3 3 3 3 3 3 3 3 3 s s s s s n4 6 e. e e e e e e e e e e e e e e o8 2 t t t t t t t t t t t t t t t i - o o o o o o o o o o o o o o o s6 N N N N N N M N N N N N N N N i 0 e vg e1 a R0P

,:yj 1

g e 3.o j

uj $

4 7

0 A A 2 A A A A A A A A A A A A A

- u$ N N N N N N N N N N N N N N N M

D catpy

• m .

O O O O O O O O O O O O O O O I

P M sth@

~

O O O O O O O O O O O O O O O A A A A M M 8#3M S S S S M M M M M M M M M

. A A A A A K K K K L L L L L A G

3j C C C C G G G G G G G G G G sM " " " " " " " " "

"8 "8

.aj "8 8 8 8 8 8 8 8 "8 2 "8 8 8 Y

N A

P e&3O B C C C C B B B B B B B B B B d

C 3j SC ME T AVRN R RLEA 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 GAWL E OVOP T .:$

R P A P3 R W CA E 4 2 3 2 4 3 4 2 3 1 2 3 2 4 3 G&IE - - - - - - - -

N RL C je O E

E B B B B B B I2TC I B B B B G E E T V S ,CU EN R E1L E T EH S S C ESNA o CAI E N A B C D ILSB - - - -

VCN m e e 5 5 S 5 4 2 5 8 1 4 7 9 5 7 9 R OT v 1 1 I 1 4 8 8 8 9 9 0 0 1 1 1 EECN t l 1 1 1 1 1 1 2 2 2 2 2 SMSI s NSIO y a I AWP S V _

s e

e s

1 k r

a m

e T R I

N 6 6 3 U , , ,

1 1 1 1

7 s s s n4 2 e e e o8 t t t i - o o o s6 N N N i0 e vg e1 a o R0P ,$hj hn

%Nj -

.b" * . 0 0 m 4 4 e.

hh e

$j Ng P P O O 4 -

7 0

2 T T A

- N$ B B N M

caNNj O O O Rfm 8DYR C C O

" j

• h O O 8NNj M M M

• h A A A

.Ny G G G NM 2 2 "

.My 1 1 8

_ Y l

- N .

A b8$0 P

M oMy B B B O

SC .

ME T AVRN RLEA GAWL R 3 3 3 OVOP E m$$

T

- R P A

P3 R CA W m G&I E 2 3 2 o e.

N RL E - - -

m I 2TC C I

eOa4 o8 G G B w

m

- T CU V m

+

S ,EN R 7 8

. E1 L E 0 0 +

T El i -

_ S C S 9 9 ESNA 2 2 CAI E o - - -

I LSB N V V +

VCN m O O e e

R OT e e M M 0 -

EECN t v 1 1

- 2 2

SMSI s l NSI O y a e I AWP S V

t. l

_ s k

1 r a 3 3 m 2 2 e

T R , ,

I 1 1 N 1 1 U , ,

9 9 1

s s n48 e e o82 t t i - o o s6 N N i0 e vg e1 a R0P M tm u:am 3e.snm I uE

.sx

.:8 O O 9

6 2

- ,:8 M

bs ao C C D .stm I

P cManA l O O H g ez

.eU A 4O3e< S 'M

.eU K A ss> C G

.am " "

es> 4 4 Y

N A

P go:uu C M

s> / A O A SC ME T AVRN RLEA 2 GAWL :ao 2 OVOP R R P I P3 R A CA G&I E E 7 7 N RL C - -

I2TC I :NM 8u F F T CU V S ,EN R E1L E T EH S S C ESNA CAIE o ILSB N 4 1

VCN m e

R OT e -

EECN t v C A S

SMSI s l 2 NSI O y a I AWP S V

e s

k 1 r a

m e

T R I

. N U

1 1 1 1 1 1 1 1 1 n4 9 e e e e o82 t t t t i - o o o o

. s6 N N N N i0 e vg e1 a C R0P u:g, - o_

R R

dg R R

. V V 5 5 R" ao$ 4 4

- s j 5

t e

e

'] RP RP h tg Rg RO R S

9

1. g TTm Tr, 0 AB AB 2

M 4s'j C C C C

_ D o$

_ I

. P 8utg l O O O O Eg tE O O A A 8:aa A A S S

• $ A A K K

.Ag G G C C ng " - " "

.Ag 2 2 2 2 Y .

_ N A ka3a P C C M .Ag A A / /

O A A SC R ME T AVRN I A

RLEA 2 GAWL T .:g 2 2 2 OVOP N R P P3 R E CA M G&IE U 5 5 5 5 N RL R - - - -

I2TC T Ej,8a D D D D T CU S S ,EN N E1 L I T EH S C A A ESNA o - -

CAIE N 3 4 ILSB 7 8 3 3 VCN m e 4 4 R OT e A A

EECN t v 0 3

0 3 I I SMSI s i NSIO y a I AWP S v

,< j

.4 l .

! . 4 i

INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VALVES Revision 1

• WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 30 UNIT 1 AUXILIARY STEAM, I! EATING STEAM, I System ct TT.Trn & !IOT WATyp l P&ID M-214 C

$ N o b O E #

a . .& . . # "t At i ' %:

8  : A* 3 3*

yh 3* j* # t.* jj : Pr Valve No O y y8 yM Mh @Et M mj $ $j xm $$ Remarks

!!V-632 C-7 2 A 3" GA M C C AT RR Notes 9, 11 IIV *i33 A-7 2 A 1}" GA M C C AT RR Notes 9, 11 liv-818 C-7 2 A 3" GA M C C AT RR Notes 9, 11 liv-808 A-7 2 A 13" GA M C C AT RR Notes 9, 11 ilV-809 A-7 2 A 13" GA M C C AT RR Notes 9, 11 t

(

l l

_ = - - - _ _ .

o _

s k

r 1 a 4 4 4 4 m 2 2 2 2 e

T R , , , ,

I 1 1 1 1 N 1 1 1 1 U - , , , ,

1 1 1 1 9 9 9 9 1 1 1 1 1 s s s s n4 1 e e e e e e e e t t t t t t t t o8 o o o o o o o o i3 N N N N N N N N s6 i0e vg e1 a 0 0 0 0 0 0 0

~

R0P #* l ;0 R R

R R

R R

R R R R R R R R m* :14 V V V V V V V 5 5 5 5 5 5 5

$8 .%sm 4 4 4 4 4 4 4 84uE

.s% P S u:E4 O O O C C C C l l p

5 y 1

2 u:Ed M

6saaQ C C C C C C C C D .tsm I

P aSdnp. O O O O C C C C

~ l e2

.e6 A O O O O O O O uB*H< S S S S A A A A

.eU F F F F K A A A T T T T C G G G B B B B 2s>

.sm "

1 1

1 1" 6

3 "6

3 6

3 6

3 Ea>

Y N N O A I yo? u C P T /

M A I #> A A A A A A A A O L SC I ME T T AVRN N RLEA E 2 2 2 2 2 2 2 2 GAWL V :ao OVOP R P D P3 R N CA A 4 3 3 4 3 3 3 3 G&I E - - - - - - - -

N RL G E%3?8u G G F F G G E E I2 TC N T ,CU I S EN T K E1 L A H A B C T EH E C - - -

S C H 0 0 0 2 3 4 5 ESNA o A 0 0 0 1 1 4 4 CAI E N - 2 2 2 2 2 2 2 ILSB 0 3 3 3 3 3 3 3 VCN m e 0 - - - - - - -

R OT e v 2 V V V V V V V EECN t 3 C C C C C C C SMSI s l NSIO y a I AWP S V l , i

~'

INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VALVES Revision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 32 UNIT 1 System AUXILIARY FEEDWATER SYSTEM M 917 E a -l bl i:'

. 8, 8 8 a r* u

. . . # "2 w" t i .!! ':

8 33 An A *' 3* Et j' # #4 R 48 Valve No j $ jO jY j j jj my j jj $ $$ Remarks 18 B-7 2 B 3" GA M O O NA Notes 1, 3 19 D-7 2 B 3" GA M O O NA Notes 1, 3 30 D-5 3 B 3" GA M C C NA Notes 1, 3 31 B-7 2 B 3" GA M O O NA Notes 1, 3 43 E-5 3 B 3" GA M C C NA Notes 1, 3 44 C-7 2 B 3" GA M O O

• NA Notes 1, 3 4

75 E-5 3 B 1" GA M C C NA Note 3

,! i 4

I 78 E-5 3 B 1" GA M C C NA Note 3 1

80 F-5 3 B 1" GA M C C NA Note 3 84 D-5 3 B 1" GA M C C NA Note 3 87 C-6 3 B 1" GA M C C NA Note 3  ;

89 E-5 3 B 1" GA M C C NA Note 3 h 100 B-7 2 C 3" CK SA C O CVT CS Note 19 101 D-7 2 C 3" CK SA C O CVT CS Note 19 j 102 B-7 2 C 3" CK SA C O CVT CS Note 10

INSERVICE TESTING PROGRAM -'

ASME CLASS 1, 2 & 3 VALVES Revision 1 .-

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 33 UNIT 1 Systtm AUXILIARY FEEDWATER SYSTEM lP&ID M-217

$ c M j D 8 8 3 n" o u .

as an a-

1. ~t s- jM 8:

• t en u es jaa %:

S Valve No O y jj yM y y M$ $ $$ $ $$ Remarks 104 C-7 2 C 3" CK SA C O CVI CS Note 19 106 B-7 2 C 3" CK SA C O CVT CS Note 19 107 D-7 2 C 3" CK SA C O CVP CS Note 19 108 B-4 3 C 4" CK SA C O CVT CS Note 19 7

109 D-4 3 0 3" CK SA C O CVT CS Note 19 110 F-4 3 C 3" CK SA C O CVT CS Note 19 111 C-3 3 C 6" CK SA O C Note 20 112 D-3 3 C 4" CK SA O C Note 20 g

113 F-3 3 C 4" CK SA O C Note 20 466-A C-7 2 C 16" CK SA O C CVT CS Note 21 466-B C-7 2 C 16" CK SA O C CVT CS Note 21 1.14 G-4 3 C 1" CK SA C C NA Note 3 115 D-4 3 C la CK SA C C NA Note 3 116 F-4 3 C 1" CK SA C C NA Note 3 117 A-5 3 C 3" CK SA C C NA Note 3

INSETNICE TESTING PROGRAM

• ASME CLASS 1, 2 & 3 VALVES Revision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NiiCLEAR PLANT Page 34 UNIT 1 System AUXILIARY FEEDWATER SYSTEM PLID g_217 5

m .

N c M h N o 0 0 E v e . .& . . t "t *t i f 1:

Valva No O 8

U 33 32 3 3*

yO yM y Mh Et j$

ja my

1. 4 38 48

$@ gM yy Remarks

.4 476-A D-7 2 C 16" CK SA O C CVT CS Note 21 476-B D-7 2 C 16" CK SA O C CVT CS Note 21 CV-4002 B-3 3 B 1" GA AO C C NA Note 3 CV-4007 D-4 3 B 1" GA AO C C NA Note 3 CV-4012 D-4 3 B 3", GA AO C O B O 10 Note 3 CV-4014 E-4 3 B 1" GA AO C C NA Note 3 CV-4019 F-4 3 B 3" GA AO C O 10 Note 3 O

MOV-4000 D-7 3 B 3" GL MO O O NA Notes 1, 3, 6 MOV-4001 B-7 3 B 3" GL MO O O NA Notes 1, 3, 6 MOV-4006 C-3 3 B 6" GA MO C O BT OP 40 Note 6 MOV-4009 D-3 3 B 4" GA MO C O BT OP 40 Note 6 MOV-4016 E-3 3 B 4" GA MO C O BT OP 40 Note 6 MOV-4020 F-5 3 B 3" GA MO O C BT OP 25 Notes 1, 3, 6 MOV-4021 F-5 3 B 3" GA MO O C BT OP 25 Notes 1, 3, 6

~

MOV-4022 D-6 3 B 3" GA MO O C BT OP 25 Notes 1, 3, 6

-.m_ -__. _ _ _ _ __

9 e

e 9 m

~ E b

m H

~ =

C M 8 o

=

78*

$Y$

wom tseuqeR feileR f

emit ekortS m mumixaM edoM m tseT O J-w H Y

tseT m noitceriD D ekortS 0

m noitisoP lamroN epyT rotautcA g

epyl' evlaV a

euS

y evlaV h

E

• g

@ yrogetaC y g k evlaV s

mo-n s 8

n"%GNE mw 5

=

5 ssalC

• oD 5 $

yh g SetanidrooC O e c e

$Mhz 5 -

5 " "m 9 g s w eg=E "m E

= 2 e.

EnE"Z B a 1 ky h 2mHo N i . . . . . . .

- INSERVICE TESTING PROGRAM

• ASME CLASS 1, 2 & 3 VALVES Reivision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 36 UNIT 1 System POST ACCIDENT CONTAINMENT VENTING SYSTEM lP&ID M-224 m e .

C y V U 8 3 e"* e o . . 8, . . # "t *u i 13 0 33 An A* 3* Et 3* # #4 j$a :18 i Valva No O O y0 yM y Mh j$ mY $ $$ z $$ Remarks 4 E-6 2 A 2" DIA M C C AT RR Notes 9, 11 5 E-6 2 A 2" DIA M C C AT RR Notes 9, 11 8 E-5 2 A 3/4" DIA M C C AT RR Notes 9, 11 9 E-5 2 A 3/4" DIA M C C AT RR Notes 9, 11 12 D-6 2 A 2" DIA M C C AT RR Notes 9, 11 13 D-5 2 A 2" DIA M C C AT RR Notes 9, 11 G

e e

1

INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VALVES Revision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 37 UNIT 1 System EMERGENCY DIESEL AIR STARTING SYSTEM (3D) P&ID M-209 Sheet 10 m .

C j b 8 8 S e" o e . .a . . # O *t -

i

• 1 8  ; RB h* h* B* "02 f* u u8 3B n B.

Valve No O $ $0 yM j $ $$ m$ $ $j gM $$ Remarks 3-31 E-7 3 C l}" CK SA C C NA 3-3 E- 7 3 B ll" GL M O O NA 3-5 D-7 3 B 13" GL M O O NA 3-7 C-6 3 B ll" GL M O O NA 3-9 C-6 3 B 1)" GL M O O NA 3-17 E-7 3 B ll" GA M O O NA 3-19 D- 7 3 B ll" GA M O O NA CV-3057-B B-5 3 B l}" GL AO C O BT OP 3-32 D-4 3 B ll" GA M C C NA 3-28 E-4 3 C ll" CK SA C C NA 3-30 E-4 3 C 13" CK SA C C NA 3-4 E-4 3 B ll" GL M O O NA 3-6 D-3 3 B 1)" GL M O O NA 3-8 C-3 3 B 1)" GL M O O NA 3-10 C-3 3 B GL M O O NA l 1}"

s k

r 1 a m

e T R I

N U

1 2 2 n4 e e 8 t t o8 3 o o i - N N s6 i0 e

- vg e1 a ~

R0P a' m uMME fe e$ m _

0 1 _

t _

e e E _

e P _

h S

1. 1. $ O _

T T 9 T V V 0 ##$ B R R 2

M 5Y e a O O O D es m I

P cMd#M l C C C H @

) $p A

- D O A A S S 3

( aO" M M

E e@p T L V V S $Mj G R R Y

S G "

N eNM " 4

/

4

/

I 3 T $H$ 1 3 3 Y R N A T

A P S noEM0 C M B C O R $H$

I SC A ME T AVRN L RLEA E 3 3 3 GAWL S $4$

OVOP E R P I P3 R D CA 4 6 4 G&I E Y - - -

N RL C e#MEoO B E E I2TC N T ,CU E S EN G E1L R A B A T EH E - - -

S C M 7 7 7 ESNA E o 5 5 5 CAI E N 0 0 0 ILSB 3 3 3 VCN m e - - -

R OT e v V V V EECN t s l C R R SMSI y a NSIO V IAWP S t , l: -il i 1 i. '  ! I. a , k

5

. ;y -

INSERVICE TESTING PROGRAM '

ASME CLASS 1, 2 & 3 VALVES. Revision 1 .-

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 39 UNIT 1 System EMERGENCY DIESEL AIR STARTING SYSTEM (4D) P&ID M-209 Sheet 10 m .

$ c M j t' 8 8 41 e s .

e . . 8, . . # ~t *t x i'.  %:

8 RB R* R*

y B* l2 y*

j$ mj

1. %.8 n8 Valve No O $ $$ $$ M $ $j jj Remarks 4-31 E-7 3 C ll" CK SA C C NA

4-3 E-7 3 B ll" GL M O O NA 4-5 D-7 3 B ll" GL M O O NA i

! 4-7 C-6 3 B GL M O O NA ll" -

4-9 C-6 3 B ll" GL M O O NA

! 4-17 E-7 3 B ll" GA M O O NA 4-19 D-7 3 B ll" GA M O O NA

~

CV-3058-B B-5 3 B ll" GL AO C O BT OP 4-32 D-4 3 B ll" GA M C C NA l 4-28 E-4 3 C ll" CK SA C 'C NA t

l 4-30 E-4 3 C ll" CK SA C C NA

! l 4-4 E-4 3 B ll" GL M O O NA

4-6 D-3 3 B ll" GL M O O NA l 4-8 C-3 3 B ll" GL M O O NA 4-10 C-3 3 B ll" GL M O O NA

l ! !

s k

r 1 a m

e T R I

N U

1 2 2 n4 0 e e o8 4 t t i - o o s6 N N i0e vg e1 a R0P M- M ~

u:#M 3e esMm 0 I 5E 1

t e e3E e

h ,e9 P S O T T

,e8 T V V 9 B R R 0

2 M $Yv o ee m O O O D

I G

P cds p l

a g o:z  : C C C

) eh D 4M;o< O A A 4

(

A S J M

E eh V T L V S

Y s > G R R S

' G e m )

4 4

N I

T s > 1 /

3

/

3 Y R

• N A A T gor 0 P S M

O R e > B C C SC I ME T A AVRN RLEA L GAWL E  : o 3 3 3 OVOP S R P E P3 R I CA D G&I E 4 6 4 N RL Y :NNi o - - -

I2TC C -

B E E T

S ,EN CU N E

E1L G T EH R A B A S C E - - -

ESNA M o 8 8 8 CAI E E 5 5 5 ILSB N 0 0 0 VCN m e 3 3 3 R OT e v - - -

EECN t l

V V V SMSI s C R R NSIO y a I AWP S V

(

V y S PWAI _

I I a OISN D D l s I SMS _

v t NCEE I I a e TO R l

9 m NCV l N BSLI o D EI AC E ANSE I C S O HE T N NE L ,1 E I S D D Z UC T

- - O8uj E CT2I .

l 9 D LR N l EI &G

_ A AC N R 3P D P R 2 2 $;. POVO R LWAG _

E AELR _

A NRVA C T EM _

I' CS B B O O

$R. R M P

$R&b M A

A N

K Y 2  ? E

" " $R. U _

P MR W A

D D jR.

T E

I I A A R h*

M M MB%8 O O jl" l S2t8 P I

C C myA D _

jiU3c P

$# B _

M _

2 3

n n 1 Ja myAs Bn4 m} o P0R a1e g v N N e0i o o 6s t t i e e 8o 4 4n 1 1 1

,1 ,1 l1 2 2 3 3 U N

I R T e

m a 1 r

k s

1 4

• e 9'

s INSERVICE TESTING PROGRAM - VALVES b.2 UNIT 2 4

INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 ,,

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 1 UNIT 2 System SAFETY INJECTION SYSTEM lP&ID llOE035 Sheet 1 c:

D o b O 4 6h E

. .& . . # "O Ju i  %:

8 33 3* 3*

yh 3* j$1 j* # t.8 33 d&

Valve No O C yy yM Mh $ mj $ $j zm $$ Remarks 834-A J-lO 2 B 1" GL AO C C NA Note 3 834-B F-10 2 B 1" GL AO C C NA Note 3 834-C J-6 2 B 1" GL M O O NA Note 3 835-A H-lO 2 B 1" GL AO C C NA Note 3 835-B E-10 2 B 1" GL AO C C NA Note 3 839-A F-8 2 B 3/4" GL AO C C NA Note 3 839-B F-9 1 B 3/4" GL AO C C NA Note 3 839-C F-9 2 B 3/4" GL AO C C NA Note 3 839-D F-8 1 B 3/4" GL AO C C NA Note 3 841-A H-ll 2 B 10" GA MO O O NA Notes 3, 6 841-B E-ll 2 B 10" GA MO O O NA Notes 3, 6 AT OP VRR-842-A H-12 1 A/C 10" CK SA C O CVP E-CS 19 CVT *RR AT OP VRR-342-B E-12 1 A/C 10" CK SA C O g SpjS 19 843-A I-10 2 B 3/4" GL M C C NA Note 3 84 3-B E-10 2 B 3/4" GL M C C NA Note 3

1 ~

INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 ,,

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 2 UNIT 2 j System SAFETY INJECTION SYSTEM lP&ID 110E035 Sheet 1 i

e l

1. g a c 8 L M o O a-4 eY  ! e uM E O $E $ c' $e fe lM $e u oe $ d' Valve No O o

M o

YN

>0 YM

>m YS

> E4 ob

• • U o$

l2; As UM WQ E4

$3 E4 E

$U Em e

MM Remarks 844-A I-11 2 B 1" GL AO C C NA Note 3 844-B E-ll 2 B' 1" GL AO C C NA Note 3 845-A H-12 1 A/C 10" CK SA C O , VRR-2 845-B D-12 1 A/C 10" CK SA C O p VRR-2 845-C G-12 1 A/C 2" CK SA C 0 VRR-2 845-D D-12 1 A/C 2" CK SA C O p VRR-2 845-E E-12 1 A/C 3/4 " CK SA C O VRR-2 8

845-F G-12 1 A/C 3/4" CK SA C O VRR-2 AT RR i 846 J-5 2 A 1" GL AO O C BT OP 4.5 VRR-O Note 11

- FST OP 850-A B-8 2 B 10" GA MO C O BT OP lb Note 6 850-B B-ll 2 B 10" GA MO C O BT OP 10 Note 6 851-A B-5 2 B 10" GA MO C O BT OP 130 Note 6  ;

851-B A-5 2 B 10" GA MO C O BT OP 130 Note 6 852-A C-ll 2 B 6" GA MO C O BT CS 15 Notes 4, 6 852-B C-ll 2 B 6" GA MO , C O BT CS 15 Notes 4, 6

INSERVICE TESTING PROGRAM .

ASME CLASS 1, 2 & 3 VALVES Revision 1 ,.

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT - Page 3 UNIT 2 System SAFETY INJECTION SYSTEM lP&ID 110E035 Sreet 1

$ c M a b 8 8 3 u a . .a . .  % t at 4:

: 2: a: 2 "h p u a al* u Valva No O d yj yM jh M @M mj $ $$ Em yy Remarks CVP E-CS 853-A C-12 1 A/C 6" CK SA C O Cyr RR VRR-3 Note 5 AT E-CS CVP E-CS 853-B B-12 1 A/C 6" CK SA C O y gg VRR-3 Note 5 CVP E-CS 853-C C-13 1 A/C 6" CK SA C O CVT RR VRR-3 AT E-CR 853-D B-13 1 A/C 6" CK SA C O VT RR VRR-3 AT E-CS 861-A C-8 2 C 3 /4 " RV SA C O RVT Note 2 866-A H-5 2 B 4" GA MO O O NA Note 3 866-B H-5 2 B 4" GA MO O O NA Note 3 t CVP E-CS l 867-A H-13 1 A/C 10" CK SA C O CVT RR VRR-4 AT E-CS 867-B E-13 1 A/C 10" CK SA C O * '

AT E-CS 878-A D-12 2 B 2" GL MO C C BT CS 15 Notes 4, 6 878-B D-12 2 B 2" GL MO O O NA Note 3 878-C G-12 2 B 2" GL MO C O DT CS 15 Notes 4, 6 878-D H-12 2 B 2" GL MO O O NA Note 3 878-s E-ll 2 B 2" GL M O O NA Notes 1, 3 878-F G-12 2 B 2" GL M O O NA Notes 1, 3

i i I , ; . 1 ' !: i . ,i j, {

V S y

PWAI a OI SN __

9 8 8 8 l s I SMS 5 3 3 8 v t NCEE _

7 0 0 7 e e TO R

- - m NCV B A N BSLI EI AC o ANSE S C S A i l E T F L -

E N E ,1 E S _

T UC T _

I F J F O8ej0m Y CT2I

- - - - LR N 6 1 1 6 I EI & G .

0 0 N AC _

J R 3P _

E P R C POVO 2 2 2 2 de T LWAG I AELR O NRVA _

N T EM S

CS j3e O A C C C Y M .

S P _

O3eb T E

A N

M Y _

3 1 1 1 / jAe

" " " 4

" Ma G R R R j3e L V V V -

A S S S ME%8 O A A A j$~

C C C C M1T18 P I

D C O O O m3

• j *8ac A R R R $# 1 T V V V 1 T T T 0 E

0 3

R y# 5 R

y4 S

gyfa h e

e M8a "Me t 1

y4%

y&;o P0R a1e g v e0i N N N N 6s o o o o i t

e t

e t

e t

e 4 8o 4n 1 2 2 2 1 0

U N

I R T e

m a

r 2 k

s

e INSERVICE TESTING PROGRAM *

• ASME CLASS 1, 2 & 3 VALVES Revision 1 **

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 i

POINT BEACil NUCLEAR PLANT Page- 5 UNIT 2

~

System SAFETY INJECTION SYSTEM lP&ID 110E035 Sheet 2

$ c M j t' 8 8 J r" '

u b = .& . . # t *t i  %:

8 8 33 A* A* B* "Et 8* # u.8 33 48 Valve No O y y8 yM $ $ $$ $$ $ $$ Em jj Remarks 820-A G-3 2 B 2" GL M O O NA Note 3 l 825-A H-5 2 B 12" GA MO C O BT OP 20 Note 6 825-B H-5 2 B 12" GA MO C O BT OP 20 Note 6 825-C H-5 2 B 2" GA AO O O NA Note 3

!, 826-A J-6 3 B 8" GA MO O O NA Notes 3, 6 ,

826-B J-7 3 B 8" GA MO C O BT CS 15 Notes 5, 6 826-C J-7 3 B 8" GA MO C O BT CS 15 Notes 5, 6 827-A J-8 3 B 8" GA M O O NA Note 3 827-B J-8 3 B 8" GA M O O NA Note 3 a

829-A H-ll 2 B 4" GA M C C NA Notes 1, 3 i

829-B H-ll 2 B 4" GA M C C NA Notes 1, 3 854-A E-4 2 C 10" CK SA C O CVT RR VRR-6 854-B E-4 2 C 10" CK SA C O CVT RR VRR-6 t

! 856-A E-4 2 B 10" GA MO O O NA Notes 3, 6 856-B E-4 2 B 10" GA MO O O NA Notes 3, 6

,i

INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 ,.

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT 3EACH NUCLEAR PLANT Page 6 UNIT 2 System SAFETY INJECTION SYSTEM lP&ID 110E035 Sheet 2 0 c M 3 b 8 8 3 o" o a . .& . . # ~t *t i 3 1 8 a 33 3n 3* 3* 01 3* # #e *8 da Valve No O U yd yj $ M @M mj $ $j M $$ Remarks 857-A F-8 2 B 6" GA M C C NA Note 3 857-B F-7 2 B 6" GA M C C NA Note 3 876-A F-9 2 B 2" GL M O O NA Notes 1, 3 876-B F-9 2 B 2" GL M O O NA Notes 1, 3 879-B ,

F-13 2 B 3/4" GL M C C NA Notes 1, 3 884 F-10 2 B 3 /4" GL M C C NA Notes 1, 3 888-A I-10 2 B 6" GA M O O NA Notes 1, 3 888-B H-lO 2 B 6" GA M ') O NA Notes 1, 3 889-A I-10 2 C 6" CK SA C O VRR-7 R

889-B H-10 2 C 6" CK SA C O p VRR-7 891-A G-10 2 C 2" CK SA C O CVT OP 891-B G-9 2 C 2" CK SA C O CVT OP 894 H-5 2 B 2" GL M O O NA Note 3 895 H-5 2 C 2" CK SA C C NA Note 3 896-A I-7 2 B 6" GA MO O O NA Notes 1, 3, 6

s 2 k

_ r

_ a m

_ e 6 R

. T

_ I ,

N 3 U

1 1 3 s

n4 e e o87 t t i - o o s6 N N i0 e vg e1 a .

0 O R0P u:8$ - -

R R R R t$ V V 2 5 5 ea" ao 4 4 t j

_ e e

h S

_ s. @

_ u$ O 5

3

_ 0 E T 0 A A 1 e$ N N 1

aat $ O C C C D .3m I

P M 8thj

~

O O O C O O O 8uaM M A A M A L L L

.a$ G G G G n$ " " "

4 6 2 2 /

.a$ 3 Y M N E ,

A T b8aO

. P S

- M Y .aj B B B B O S SC ME T

_ N AVRN O RLEA I GAWL T :d 2 2 2 2

_ OVOP C R P E P3 R J CA N 1 G&I E I 7 1 3 N RL m?{b8O - -

_ I2TC Y H H H I T T S ,CU EN E E1 L F T EH A

_ S C S ESNA o CAI E N B A B ILSB VCN m e e 7

8

_ R OT v 6

9 7

9 9 9

_ EECN t l 8 8 8 8 s

SMSI y a NSI O V

_ I AWP S

• ~

INSERVICE TESTING PROGRAM <

ASME CLASS 1, 2 & 3 VALVES Revision 1 .*

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACII NUCLEAR PLANT Page 8 UNIT 2 System SAFETY INJECTION SYSTEM P&ID 110E035 Sheet 3

~

0 a 3 1

$ D o 5 0 a e . .e . . # ~t *#

t' i

• t:

8  : A* 38 3* 3* 01 81 # #4 38 48 Valve No O $ $$ $M y M j 8, My $ $$ gM $$ Remarks 831-A F-6 3 B 2" GL M O O NA Notes 1, 3 831-B F-7 3 B 2" GL M O O NA Notes 1, 3 831-C D-7 3 B 2" GL M C C NA Notes 1, 3 831-D D-6 3 B 2" GL M C C NA Notes 1, 3 840-A G-5 3 C 3/4" VB SA C O CVT RR VRR-5 840-B G-5 3 C 3 /4 VB SA C O CVT RR VRR-5 847-A 11- 8 2 C 2" CK SA C O CVT OP 847-B D-8 2 C 2" CK SA C O CVT OP 858-A I-3 2 C 6" CK SA C O VRR-8 p

858-B C-3 2 C 6" CK SA C O VRR-8 p

860-A I-lO 2 B 6" GA MO C O BT OP 15 Note 6 860-B I-lO 2 B 6" GA MO C O BT OP 15 Note 6 860-C C-lO 2 B 6" GA MO C O BT OP 15 Note 6 860-D C-10 2 B 6" GA MO C O BT OP 15 Note 6 862-A I-ll 2 A/C 6" CK SA C O CVT RR VRR-9 Note 10 AT RR

9 INSERVICE TESTING PROGRAM <

ASME CLASS 1, 2 & 3 VALVES Revision 1 * -

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil NUCLEAR PLANT Page 9 UNIT- 2 Systen SAFETY INJECTION SYSTEM lP&ID 110E035 Sheet 3

? c A a b 8 8 a

• e u 4 . .? . .  % "D Rn i n %'a e  : 33 A* A*

y B* Et j* # t.* jj M8 Valve No O $ y8 yM M @M mj $ $@ gm j$ Remarks 862-B C-ll 2 A/C 6" CK SA C O VRR- 9 Note 10 863-A F-5 3 B 3/4" GL M C C NA Note 3 868-A I-12 2 B 6" GA M O O NA Notes 1, 3 868-B C-12 2 B 6" GA M O O NA Notes 1, 3 870-A I3 2 B 6" GA MO O O NA . Notes 1, 3, 6 870-B C-3 2 B 6" GA MO O O NA Notes 1, 3, 6 871-A I-5 2 B 6" GA MO C O BT OP 15 Ncte 6 871-B C-5 2 B 6" GA MO C O BT OP 15 Note 6 874-A 11 - 8 2 B 2" GL M O O NA Notes 1, 3 874-B D-8 2 B 2" GL M O O NA Notes 1, 3 HCV-836-A F-7 3 B 2" GL AO C O g 20 Note 12 IICV-836-B E-7 3 B 2" GL AO C O 20 Note 12 872 G-6 3 C 3/4" RV SA C O RVT 864-A 11 - 1 1 2 B 3/4" GL M C C AT RR Note 10 864-B C-11 2 B 3/4" GL M C C AT RR Note 10

~.'

INSERVICE TESTING PROGRAM ASME CLASS 1, 2 & 3 VALVES Revision 1 WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACil HUCLEAR PLANT Page 10 UNIT '2 I

System AUXILIARY COOLANT SYSTEM lP&ID 110E029 Sheet 1

$ c M a b 8 8 a " u 4 . .e . e  % RR ln  %;

8 8 33 3 A* BE "0 1 'u j* #- #4 da Valve No O $ $$ $M $ Mh @M m$ $ $@ $$ Remarks 700 B-13 1 B 10" GA MO C C NA Notes 3, 6 701 B-12 1 B 10" GA MO C C NA Notes 3, 6 704-A D-9 2 B 8" GA M O O NA Note 3 9 -

704-B C-10 2 B 8" GA M O O NA Note 3

, 709-A D-7 2 B 8" GA M O O NA Notes 1, 3 709-B C-6 2 B 8" GA M O O NA Notes 1, 3 710-A D-7 2 C 8" CK SA C O g Note 12A

, 710-B C-6 2 C 8" CK SA C O g Note 12A 712 F-ll 2 B 3/4" GL M C C NA Note 3 713-B J-5 2 B 8" GA M C C NA Note 3 j 714-A E-8 2 B 6" GA M O O NA Note 3 715-A F-6 2 B 8" GA M O O NA Notes 1, 3 715-B F-5 2 B 8" GA M O O NA Notes 1, 3 715-C F-7 2 B 1" GL M C C NA Note 3 l 716-A G-lO 2 B 8" GA M O O NA Notes 1, 3 l

INSERVICE TESTING PROGRA.; ,

ASME CLASS 1, 2 & 3 VALVES Revision _1 ,,

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACII NUCLEAR PLANT Page 11 UNIT 2 System AUXILIARY COOLANT SYSTEM P&ID 110E029 Sheet 1 m .

O c h a b

. 8, 8 8 a e" o G = . . # ~d . # i' . * %

8 33 32 3* 3* E1 ya # t.8

• d8 Valve No O y y8 yM j M @M mj $ $j -

M$ Remarks 716-B G-10 2 B 8" GA M O O NA Notes 1, 3 716-C G-10 2 B 8" GA M- C C NA Note 3 716-D G-lO 2 B 8" GA M C C NA Note 3 720 D-13 1 B 10" GA MO C C NA Note 3 l

733-A E-9 2 B 2" GL M O O- NA Note 3 733-B B-9 2 B 2" GL M O O NA Note 3 742 H-10 2 B 8" GA M C C NA Notes 1, 3 IICV-624 G-9 2 B 8" BTF AO O O NA Note 3 .

j 11CV-625 G-9 2 B 8" BTF AO O O NA Note 3 4

t i

)

i 4

INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 , ..

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 12 UNIT 2 System AUXILIARY COOLANT SYSTEM P&ID llOE029 Sheet 2 C

j b 8 8 3 e"* o i

c - .& . . # t At i  %:

Valve No 0

O a

33 An 3' 3* "Et y0 yM y M jM ja my t.8 33 d8

$j xm jj Remarks 754-A F-13 2 A 4" GA MO O C 15 untes 6, 11, 13 C

754-B F-10 2 A 4" GA MO O C 15 Notes 6, 11, 13 C

~

755-A E-13 2 A/C 4" CK SA O C Note 11 O

~

755-B E-10 2 A/C 4" CK SA O C Note 11 R

759-A F-ll 2 A 4" GA MO O C 15 Notes 6, 11, 13 C

759-B F-7 2 A 4" GA MO O C 15 Notes 6, 11, 13 l C

~

767 E-7 2 A/C 2"- CK SA O C. Note 11

~

769 F-5 2 .A. 2" GL AO O C 4.5 Note 11 I

'2 s k

r a

m e

T R I

N U '

1 3 3 n4 3 e e o81 t t i - o o s6 N N i0 e vg e1 a R0P am*h m$H 4

t .b* e$k e

e E h

S etk om$

8 1

0 E

O om$ A A l N N l

a3nE4$

eb u ) C C D

I P 8HNm$

l

@ C C H

ogg 8a" M M M egg A

_ I L

$Hj D G eNM " "

M ' NMy 2 2 Y E

.N T S

_ A Y ho$aj P S M $Hj B B O T SC N ME T A AVRN L RLEA O GAWL O $4Hg 2 2 OVOP C R P P3 R Y CA R G&I E A 9 9 N RL I I2 TC L .$*b?OO 1 1

I T CU I S ,EN X E1 L l U

T .Ei A S C ESNA o CAI E N ILSB VCN m e

R OT e 1 9 EECN t v 1 1 SMSI s l 8 8 NSIO y a I AWP S V l ,! 1

i 1

INSERVICE TESTING PROGRAM e ASME CLASS 1, 2 & 3 VALVES Revision 1 ..

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACII NUCLEAR PLANT Page 14 UNIT 2 System REACTOR COOLANT SYSTEM lP&ID 541F445

19 N 4 c $

5 3 -S et  ! e ut

? $ $$ $o 5e fo fN be o ve bb M*

Valve No o O M o

YN

>0 YM

>m >U Yb es: U o$

z p.

UM mO e

E4 eE E4 %

$U Em e

MM Remarks AT RR 508 11 - 1 2 2 A 2" DIA AO O C pg gg 15 Note 11

~

528 11- 1 1 2 A/C 3/4" CK SA O C Note 11 AT RR 538 11- 1 2 2 A 3/4" GL AO O C BT FRT OP np 15 Note 11 549 D-6 1 B 3/4" GL M C C UA Note 3 PCV-430 11 - 5 1 B 3" GL AO C O BT CS 4.5 VRR-C Note 14 PCV-431-C I-5 1 B 3" GL AO C O BT CS 4.5 VRR-C Note 14 PCV-434 I-7 1 C 4" RV SA C O RVT Note 2 PCV-435 I-6 1 C 4" RV SA C O RVT Note 2 515 I-5 1 B 4" GA MO O C BT OP (CS: 60 Note 15 516 H-5 1 B 4" GA MO O C BT OP (CS 60 Note 15

~

529 11-11 2 C 2" C SA C C p Note 11 595 11 - 1 2 2 A 1" DIA M O C Note 11 O

539 H-12 2 A 3/4" GL AO O C Bh CP 15 Note 11 vem no _.

INSERVICE TESTING PROGRAM ,

- ASME CLASS 1, 2 & 3 VALVES Revision 1 .. .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR. PLANT Page 15 UNIT 2 1

System SAMPLING SYSTEM P&ID 541F448 ,

4 c

! h o b M E v

- 'o

. . Pn . . t t .at i t; yh jh' "Et

-o i e A* A* A *- 3 j$n t t.8 sg.

~

Valve No O y y0 yM jM m $ $, j $g Remarks j

AT RR SS6-A G-10 1 A 3/8" GL AO O C pg gg 15 Note 10 AT RR 3/8" 4 '

966-B F-10 1 A .GL AO O C BT OP 15 Note 10 FST OP AT RR

' 966-C E-10 1 A 3/8" GL AO O C BT OP 15 Note 10 PCP AD AT RR 951 G-12 1 A 3/8" GL AO O C BT OP 15 Notes 10, 22 FST cs AT RR 953 F-12 1 A 3/8" GL AO O .C BT OP 15 Notes 10, 22 1:'ST CS 955 E-12 1 A 3 /8 GL AO O C $'k' @ 15 Notes 10, 22 FST CS i

1 i

t I

L*

INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 ,.

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 16 UNIT 2 System CHEMICAL & VOLUME CONTROL SYSTEM &ID 685J175

$ c M 6

j . .a D

8

1. ~t 8

• t S e" A

u Valve No 8

O $

33 A

$$ yM y A* E*

M Et

$M jmj #

1. e

$j E

jj d8 gm j$ Remarks

^ ~

304-C A-10 1 A/C 2" CK SA O C Note 11 304-D CK SA C

^ ~

Note 11 A-ll 1 A/C 2" O AT RR 313 C-8 2 A 3" GA MO O C BT CS 15 Notes 11, 16, 6 313-A C-13 2 A 2" GA AO O C $$ $ 15 Note 11, 16 FST bS

~

370 C-9 2 A/C 3" CK SA O C Note 13

~

371 D-9 2 A 2" GL AO O C Bh C$ 4.5 Notes 11, 16 FST CS O 371-A D-13 2 A' 2" GL AO O C b3 FST b

CS 15 Notes 11, 16 1296 A-ll 1 A 2" GL AO C C AT RR Notes 9, 11 i,

I

b" INSERVICE TESTING PROGRAM ,

ASME GLASS 1, 2 & 3 VALVES Revision 1 ..

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 17 UNIT 2 System WASTE DISPOSAL SYSTEM P&ID 684J971 Sheet 1 m .

O a b a b 8 8 a e" u 4 . .a . . # t *t 1 2 4:

s  : A* A* 3* 3* "E 1 # #4 38 d&

Valve No O $ y0 yM y M $M 3*$

m3 $y g$ $$ Remarks 816 C-6 2 A 4" DIA M C C AT RR Notes 9, 11 AT RR 1003-A C-6 2 A 3" DIA AO O C BT OP 25 Note 11 PST Op AT RR 1003-B C-6 2 A 3" DIA AO O C BT OP 25 Note 11 PST OP 1698 C-6 2 A 2" DIA AO C C AT RR Notes 9, 11 1713 B-5 2 A/C 2" CK SA O C Note 11 C

AT RR 1721 C-6 2 A 4" DIA AO O C BT OP 30 Note 11 FST OP 1723 D-6 2 A 3" DIA AO C C AT RR 30 Notes 9, 11 1728 D-6 2 A 3" DIA AO C C AT RR 35 Notes 9, 11 AT RR 1786 D-5 2 A 1" DIA AO O C BT OP 35 Note 13 PST OP AT RR 1787 B-5 2 A 1" DIA AO O C pg gg 15 Note 11 1788 B -5 2 A 3/4" DIA AO C C AT RR 4.5 VRR-0 Notes 9, 11 1789 B-5 2 A 3/4" DIA AO C C AT RR Notes 9, 11

1793 B-5 2 A 1" DIA M C C AT RR Notes 9, 11

INSERVICE TESTING PROGRAM ,

ASMS CLASS 1, 2 & 3 VALVES Revision 1 .+

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT . Page 18 UNIT 2 System tRIN AND REHEAT STEAM P&ID M-2201-1

N g 4 c b a HM eY uN M o N e E E $E $e $e fe fM se # 4e -a s M*

Valve No u O M o

NN

>U NO

>m N$

>U uD o$ $M

h ,"4 h 2 As MQ E4 E4 E Xm Mg Remarks RV-2005 H-3 2 C 6" RV SA C O RVT Note 2 RV-200v H-3 2 C 6" RV SA C O RVT Note 2 RV-2007 H-4 2 C 6" RV SA C O RVT Note 2 RV-2008 H-4 2 C 6" RV SA C O RVT Note 2 RV-2010 D-3 2 C 6" RV SA C O RVT Note 2 RV-20ll D-3 2 C 6" RV SA C 0 RVT Note 2 RV-2012 D-4 2 C 6" RV SA C O RVT Note 2 1

l RV-2013 D-4 2 C 6" RV SA C O RVT Note 2 SA-10 F-4 2 B 3" GA AO O C p 15 TV-2082 B-7 2 B 2" DIA AO O C BT OP 4.5 VRR-0 MOV-2019 F-5 2 C 3" SCK MO C O CVT OP 20 Note 6 MOV-2020 E-5 2 C 3" SCK MO C O CVT OP 20 Note 6 l

i' INSERVICE TESTING PROGRAM

• ASME CLASS 1, 2 & 3 VALVES Revision 1 .

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACl! NUCLEAR PLANT Page 20 UNIT 2 System SERVICE WATER P&ID M-207-1 m .

? a b b U o $ 0 e . .a .. .  % ~t at e 42 i

• t:

0 3* A* 3* 3* 01 8* # u.8 ~8 M Pr Valve No O d y$ $M y M .O y M$ $ $j $ $$ Remarks 111 11 - 7 3 B 8" GA M O O NA Notes 1, 3 112 11- 7 3 B 6" 'GA M O O NA Notes 1, 3 SV-2090 G-7 3 E 1}" GA SO C O BT OP 110 G-6 3 B 1)" GA M O O NA Notes 1, 3 120 F-7 3 B 4" GA M O O NA Notes 1, 3 125 E-7 3 B 13" GL M O O NA Notes 1, 3 104 11 - 2 3 B 20" GA M O O NA Notes 1, 3

.L_ -,_ _.

I l )l

~ ,

5 s

k 2 r a

m e

T R I

N 3 3 3 3 3 3 3 3 3 3 3 U , , , , , ,

1 1 1 1 1 1 1 1 1 1 1 1 3 3 3 3 1 s s s s s s s s s s e

s e

n4 2 e e e e e e e e e e e e e t o8 t t t t t t t t t t t t t t i - o o o o o o o o o o o o o o o s6 N N N N N N 1 1 N N N N N N N N i0 e vg e1 a .

R0P , g$

1d$

e Ao 4

7 0 A A A A A A A A A A A A A A A 2 #* N N N N N N N N N N N N N N N M

cat

• O O O O

• jm O O O O O O O O O O O D

I P 8$1g l

O O O O O O O O O O O O O O O

~Ej

• h A A A A 8#3j M M M M M M M S S S S M M M M

• h A A A A A A A L L L L

.Ay G G G G G G G C C C C G G G G

• M "

0 "0 " " " " " "

3y 1 1 2 8 "8 8 8 8 8 "8 "8 "8 "8 "8 "8 Y

N A ta3j P

M .Ay B B B B B B B C C C C B B B B O

SC ME T AVRN RLEA GAWL R .:y 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 OR V.O P P E T

P3 R A CA W 6 8 7 6 6 G&IE 7 5 4 8 7 6 6 8 6 7 N RL E ,bJe88 - - - - - - - - - - - - - - -

I2TC C H H H G G G G G G G G D D D D T ,CU I S EN V E1L R T EH E S C S ESNA o CAI E N ILSB A B C D VCN m e 1 R OT e 6 5 2 8 8 0 0 - - - - 8 5 4 EECN t v 2 2 5 4 2 3 5 5 5 1

5 5 1

5 2

5 2

6 2

6 2

SMSI s l 2 2 2 2 2 2 2 1 1 NSIO y a I AWP S V i II l lll lllll l l l l.ll l L

~ ,

s 2 k r

a m

e T R I

N U

1 6 6 3 n4 e e e o8 2 t t t i - 2 o o o s6 N N N i0 e vg e1 a R0P o;&$

%M$

e *a3m 5 5 3 3 sf 4k P P

1. $ O O 4

7 0

2 T T A

- #$ B B N M

CS%* N O O O 2jm D

I P 8st$

l C C O

~lj O O 3%3y M M M A A L e3y G G G .

• M 2 2 "

1 1 8 e3$

Y N

A i?e* $

P M B B B O eA$

SC ME T AVRN R RLEA E GAWL T 3 3 3 OVOP A .:$

R P W P3 R CA E G&I E C 8 7 6 N RL I m$jm0O - - -

I2 TC V C C C T CU R S ,EN E E1 L S T EH 7 8 S C 0 0 ESNA CAI E o 9 9 ILSB N 2 2 VCN m e V V 3

R OT e EECN t v O M

O M

7 2

SMSI s l NSIO y a IAWP S V

. , l <! ' l ll

. ! i! !

- ~ .

i$

s 2 k r

a m .

e T R I 8 N 1 U

6 1 6 3 s

n4 3 e e e o8 2 t t t i - o o o s6 N N N i0e vg e1 a R0P o:&$

%d$

.hs a 0 0 aj 2 2 P S

1. $ O C 7

0 2

1. $ T A T 2 B N B M .

Ca#* y C O C D #3m I

P 8t1M O O O

~E@

O O 8#3M M M M A A A

.A$ G G G nM " " "

.Aj 6 6 6 Y

N A ba* $

P M .A$ B B B O

SC ME T AVRN RLEA R GAWL E .%$ 3 3 3 OVOP T R P A P3 R W CA G&I E E 6 6 5 N RL C . je0O - - -

I2TC I C C C T CU V S ,EN R E1L E T EH S S C 7 0 ESNA 1 8 CAIE o 8 8 I LSB N 2 2 9 VCN m e V V

R OT e v 7

EECN t O 2 O SMSI s l M 5 M NSIO y a I AWP S V

,l1 l-!j e

t Jo s

2 na 3 3 m 2 2 e

T R , ,

I 1 1 N 1 1 U , ,

9 9 1

s s n4 4 e e o8 2 t t i - o o 9 s, 6 N N 0 e

- g "e 1 a 4 R0P ,8Sg

%Mg

.R" .

8g jj 4g

1. g R c O 9

0 #g 2

M aa#' g C C D #8g I

P 8O1g l O O "0g

& g.

A 8#3g S M

• $ K A

.3g C G ng " "

.Ag 4 4 Y

N .

A k&3g P C M .3g / A O A SC ME T AVRN RLEA GAWL =g 2 2 OVOP R P P3 R R CA I G&I E A 2 2 N R' =3jc8a - -

I 2 T C' E C

E E T CU I I S ,EN E1 L V

. T EH R S C E ESNA S CAI E o ILSB N 5 1

VCN m e C R OT e -

EECN t v l

- A S

SMSI s l NSI O y a -_

I AWP S v .

ll1l l l( 1.11l l ll l

INSERVICE TESTING PROGRNM

< ASP.E CLASS 1, 2 & 3 VALVES Revision 1 ,,

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 25 UNIT 2 ,

System INSTRUMENT AIR P&ID M-209 Sheet 5 I

a

$* c b D o

8 a ve 8

av 3 ."e a e a a

em

>e o

>e e

>e o

e

-s e v xo u

x

- sa a ee 4 we oe oe v. o ~4 :s I

Valve No o e y

av jd an yM ap pp yy Mp jM yu a

mj a o

$gg gy ag ja; Remarks O $ gm AT RR

• 3047 G-7 2 A 2" GA AO O C BT OP 4.5 VRR-0 Note 11 I FST OP ,

AT RR 1 3048 G-7 2 A 2" GA AO O C BT OP 4.5 VRR-0 Note 11 i _ FST OP i (

'~ AT RR j IA-35-A G-8 2 A 2", CK SA O C

• CVT OP

, AT RR L IA-36-A G-8 2 A 2" CK SA O C "

CVT OP f

i l

h i

F 1

INSERVICE TESTING PROGRAM. ,

ASME CLASS 1,.2 & 3-VALVES Revision 1 .*

WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 26 UNIT 2 System AUXILIARY STEAM, IIEATING STEAM P&ID M-2214 m G C

a r4 .

b O

o-M S

• A w4 99 3- e" G

9 M in su 4 0 N M$

Valve No O y $0 $M $h Mh j$ mj $ $j gM jj Remarks liv-636 E-2 2 A 3" GA M C C AT RR Notes 9, 11 IIV-637 C-3 2 A 11" GA M C C AT RR Notes 9, 11 IIV-263 E-3 2 A 3" GA M C C AT RR Notes 9, 11 l

IIV-808 C-2 2 A 1)" GA M C C AT RR Notes 9, 11 t

HV-809 C-2 2 A 1)" GA M C C AT RR Notes 9, 11

• i

\

i t

^

i r -

INSERVICE TESTINC PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 . p WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 27 UNIT 2 Syctem HEATING AND VENTILATION lP&ID M-2215 3 c A j k 8 8 a s" o e . .a . . # ~t *t q* %:

8 33 A* A* 3* Et 3l # #4 'g j da Valve No O $ $$ yM yh y j$ my $ $$ zm jj Remarks 3200-A CHK F-3 2 A/C 1" CK CA O C Note 11 CV-3200-A F-3 2 A 1" GA SO O C 4.5 VRR-O Note 11 O

CV-a200-B E-3 2 A 1" GA SO O C 4.5 VRR-O Note 11 O

CV-3200-C E-4 2 A 1" GA SO O C 4.5 VRR-O Note 11 O

36" CV-3212 G-3 2 A BTF AO C C 4.5 VRR~0 Notes 9, 11, 24 CV-3213 G-3 2 A 36" BTF AO C C 4.5 VRR-O Notes 9, 11, 24 C

CV-3244 D-3 2 A 36" BTF AO C C 4.5 VRR-O Notes 9, 11, 24 CV-3245 D-3 2 A 36" BTF AO C C 4.5 VRR-O Notes 9, 11, 24

6 INSERVICE TESTING PROGRAM ,

ASME CLASS 1, 2 & 3 VALVES Revision 1 2 WISCONSIN ELECTRIC POWER COMPANY 01-06-84 POINT BEACH NUCLEAR PLANT Page 28 UNIT 2 System AUXILIARY FEEDWATER SYSTEM P&ID M-217 m o b C h f N N

$ M E

, e . .& . . t Et i 4:

8 33 A* 3* 3* "Et j$ a #* u.8 48 Valve No O $ $0 yM y j jM m e $$ 38 mM jj Remarks 32 E-7 2 B 3" GA M O O NA Notes 1, 3 45 G-7 2 B 3" GA M O O NA Notes 1, 3

\ .

56 F-7 2 B 3" GA M O O NA Notes 1, 3 57 G-7 2 B 3" GA M O O NA Notes 1, 3 100 F-7 2 C 3" CK SA C O CVT CS Note 19 101 G-7 2 C 3" CK SA C O CVT CS Note 19 193 E-7 2 C 3" CK SA C O CVT CS Note 19 4

105 G-7 2 C 3" CK SA C O CVT CS Note 19 106 F-7 2 C 3" CK SA C O CVT CS Note 19 107 G-7 2 C 3" CK SA C O CVP CS Note 19

)

108 G-4 3 C 4" CK SA r O CVT CS Note 19 111 H-3 3 C 6" CK SA O C Note 20 466-A F-7 2 C 16" CK SA O C CVT CS Note 21 466-B F-7 2 C 16" CK SA O C CVT CS Note 21 114 G-4 3 C 1 CK SA C C NA Note 3

i .

l rN m

m N

4 b

O O 59$ N

- ~ e - -

siM

8*

=

z

=

=

EY$

zom tseuqeR feileR emit ekortS numixaM a edoM tseT O O @

tseT $ $ $ $

noitceriD O O O O O O O ekortS 0

m noitisoP O O O O O O lamroN epyT rotautcA g g @ @ g @

epyT

'vl*V 9 9 9 9 9 9 '

= eziS  : 8

'vl^V a  % 1 4 4

• E 4

> yrogetaC sO g l5 evlav O O m a e e gGEh" E N N w w W u h SSalC mw w <>

aegg g a u u u a w g$ E setaniarooc  ? 9 Y  ?  ? Y E"R*

j 'p

• d E

"8*M " 8 8 OCSE  ! *

• 8 8 8 8 EOS* 8 *  ?  ? i  ?  ?  ?

NE8E % 7 0 0 2 5 5 5 E?$0 4 &

1\lll1 ' '

a

_ o 6

s k

2 r a

m e

T .R I 1 1 1 1 1 1 N 1 1 1 1 1 1 U , , , , , ,

9 9 9 9 9 9 1

s s s s s s n4 0 e e e e e e o8 3 t t t t t t i - .

o o o o o o s6 N N N N N N i0 e vg e1 a * .

R0P e:8$

%4$

.R*A3m e(3g 4j R R R R R R

1. $ R R R R R R 4

2 2 T T T T T T

- #$ A A A A A A M

a!<t' j C C C C C C D Ajm I

P l

8tt$ C C C C C C "E@

M 8 d' E

T B#3j M M M M M M S

Y S

G

• A I

A I

A I

A I

A I

A I

N .Aj D D D D D D I

T N

E *M " "

V " " 4 4 " "

.Aj 2 2 / / 2 2 T 3 3 Y N N E A M t' &3d P N M I

.A$ A A A A A A O A SC T ME T N AVRN O RLEA C GAWL .8$ 2 2 2 2 2 2 OVOP T R P N P3 R E CA D G&I E I 4 4 4 4 4 5 N RL C .0ye8O - - - - - -

I2 TC C E E D D D D T ,CU A S EN E1L T T EH S S C O p

ESNA CAI E o I LSB N VCN m -

e 9 R OT e 4 5 8 2 3 EECN t v 1 1 SMSI s l NSI O y a I AWP S V lI ll l lllll 1lll 1l.

. a t

+

e 2 a e

T R 3 3 I 2 2 N

U , ,

1 1 1 1 1

s s n41 e e o83 t t i- o o .

s6 N N i0e vg e1 a R0P

.:ya m 4 A I R8 ;e8 j1

_ .s 1

ue O O 3

2 M

B ue P

a i:s t

C C

, D %3m I

_ P a 8aha

" O O B

s#3x M M R

2 A I

A I

E T .as D D A

W

_ P nu " "

U .as 2 2 E

Y K

_ N A ,

A c8sa M

P M R .as B B

_ O O SC T i ME T C AVRN A RLEA E GAWL R .:a 2 2 OVOP R P D P3 R N CA A 2 1 G&IE N RL D i3c:a - -

.I2TC E E D T Z S ,CU EN I E1L N T EH O S C I ESNA E CAI E D o I LSB N l 9 l VCN m e

R

.EECN OT t

s 1

- I D

I D

SMSI y e NSI O S v I AWP j e i

i

/

APPENDIX B REQUEST FOR RELIEF FOR VALVES b s.

VALVE RELIEF REQUEST NO. O Sy5 tem General, Units 1 and 2 Component: Rapid acting power operated valven with a stroke time of three seconds or less.

Category: As applicable.

Class: As_ applicable.

Function: Safety related.

TP".t Requirement: Section XI - Division 1 IWV-3413 Power Operated Valves The stroke time of all power-operated valves shall be measured to the nearest second or 10% of the maximum allowable stroke time, whichever is less, whenever such a valve is full-stroke tested.

If an increase in stroke time of 25% or more from the previous test for valves with stroke times greater than 10 seconds or 50% or more for valves with stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed. In any case, any abnormality or erratic action shall be reported.

Btsis For Relief: Measuring the stroke time for rapid acting valves, per the requirements, is not practical as highly sophisticated measurement devices and valve modifications would become r.ecessary. In addition, slight deviations in stroke times that would be encountered under normal conditions would result in exceeding code allowables due to ths very restrictive band within this tbme range.

Alternate Tatting: Stroke time of rapid acting valves shall be measured to the nearest one-half second. If an increase in stroke time of 1.5 seconds greater than the previous test is experienced, then the test frequency shall be increased to once each month until corrective action is taken.

VALVE RELIEF REQUEST NO. 1 System: . General Component: Unit 1, Safety Related Valves Category: .As applicable Class: As applicable Function: Safety related Test-Requirement: Comply with.the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, Division 1,1977 Edition and Addenda through Sumner,1978, per the requirements of 10.CFR 50.55a.

Basis For Relief: To achieve identical inspection bases for each unit, for the Section XI pump and valve inservice testing program.

Alternate Testing:- Comply with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, Division 1,1977 Edition and Addenda through Summer, 1979.

VALVE RELIEF REQUEST NO. 2

-Syrtem: Safety Injection, Units 1 and 2.

Component: 845-A, B, C, D, E, F Category: A/C C1"> s s : 1 Function: Valves open with differential pressure to provide flow path from safety injection pumps to the reactor coolant system and reactor vessel. Normally closed. In the closed position, these valves serve as reactor coolant system pressure isolation valves.

T r.t Requirements: Exercise the valves every three months and perform a seat leakage test every two years.

B uis For Relief: During normal operation, the safety injection pump discharge pressure of 1500 psig is insufficient to overcome reactor coolant system pressure. If the ptunps could overcome reactor coolant system pressure, a reactivity excursion and thermal transient would' take place during the injection of highly borated cold water. Testing during cold shutdown is prohibited because the pumps are deactivated for overpressurization protection. . Lack of a recirculation path prohibits partial stroking.

Alternate Trating: These valves will be full stroke exercised at refueling.

Seat leakage testing will be in accordance with the requirements of Technical Specification 15.3.16, " Reactor Coolant System Pressure Isolation Valve Ieakage Tests".

VALVE RELIEF REQUEST NO. 3 System: Safety Injection, Units 1 and 2.

Component: 853-A, B, C, & D Category: A/C Class: 1 Function: Valves open with differential pressure to provide flow path for reactor vessel safety injection flow.,Normally closed. In the closed position, these valves serve as reactor coolant system pressure isolation valves.

Test Requirements: Exercise the valve every three months and perform a seat leakage test every two years.

-Basis For Relief: Full or partial stroking during normal operation is not possible because icw head safety injection pump discharge pressure is insufficient to overcome reactor coolant system pressure. Even if the pump discharge pressure was high enough, any stroking could cause the injection of cold borated water into the system, resulting in a power and thermal transient.

Stroke testing the subject valves during cold shutdowns is possible, however, not desirable unless " Event V" valve testing is also scheduled. The " Event V" testing assures valve integrity, thus minimizing the possibility of a inter-system IDCA which bypasses containment. Exercising these valves during every cold shutdown may reduce the assurance that the valve is, in fact, properly seated, as established via the

" Event V" testing.

Alternate Testing: These valves will be full stroke exercised during pump full flow test at refueling. These valves will be full stroke exercised at cold shutdowns which also require the performance of " Event V" valve testing. Seat leakage testing will be in accordance with the requirements of Technical Specification 15.3.16, " Reactor Coolant System Pressure Isolation Valve Leakage Tests".

VALVE RELIEF REQUEST NO. 4 System: Safety Injection,-Units 1 and 2.

Component: 867-A Category: A/C 1

Class:

Function: Valve opens with differential pressure to provide flow path for safety injection system to loop A of the reactor coolant system. Normally closed. In the closed position, this valve serves as a reactor coolant system pressure isolation valve.

Test Requirements: Exercise the valve every three months and perform a seat leakage test every two years.

Basis For Relief: During normal operation, safety injection pump discharge pressure of 1500 psig is insufficient to overcome reactor coolant system pressure so full or partial stroke testing is not possible.

During cold shutdowns, partial or full stroke testing via the use of the accumulators or safety injection pumps is not allowed to prevent any possibility of a low temperature overpressurization event.

A full stroke test could be possible during refueling, when the reactor vessel head is removed, but the volume and flow rate required for the test could possibly damage core internals.

There would also be the possibility of forcing a nitrogen l

bubble through the reactor coolant system and refueling cavity

! resulting in possible safety implications which makes this testing concept inadvisable.

Alternate j

Testing: This valve will be partial stroked tested during the transition

period from hot shutdown to cold shutdown. This will be considered a cold shutdown test. However, this testing will not be performed if it will result in disturbing an " Event V" valve which is not required to be tested within the associated cold shutdown. In addition, this valve will be disassembled and inspected once per 10 year ISI interval. Seat leakage testing will be in accordance with the requirements of Technical Specification 15.3.16, " Reactor Coolant System Pressure Isolation Valve Leakage Tests".

VALVE RELIEF REQUEST NO. 5

- System: Safety Injection, Units 1 and 2 Component: 840-A & 840-B Category: C Class: 2 Function: Valves open under differential pressure to protect the spray additive tank from excessive vacuum conditions and allow injection of spray additive.

Test.

Requirement: Exercise the valves every three months per IWV-3522.

Basis For

- Relief: Due to the nature of the spray additive fluid and system arrangement, in-place testing of these valves is not desirable.

To_ maximize system availability, since testing requires valve removal, testing will not be performed at operation or cold shutdowns.

Alternate T,eg ing: These valves will be exercised during reactor refueling outages.

s I

l VALVE RELIEF REQUEST NO. 6 j System 3afety Injection, Units 1 and 2 -

Component: 854-A & B Category: C Class: 2 Function: Valves open with differential pressure to provide flow path from refueling water storage tank to low head safety injection pumps (RHR) during safety injection. Normally closed.

Test Requirement: Exercise the valves every three months.

' Basis For Relief Valve stroking is not poscible during normal operation because the RHR pump discharge pressure is insufficient to overcome reactor coolant system pressure during normal operation.

During cold shutdown condition, full stroke testing the valves is not possible because the reactor coolant system dues not contain a sufficient expansion volums'and that there is no return flow path back to the refueling water storage tank for recirculation. .

Alternate Testing: These valves will be full stroke exercised during the pump full flow test at refueling.

1

1' VALVE RELIEF REQUEST NO. 7 System: Safety Injection, Units 1 and 2 Component: 889-A & B Category: C Class: 2 ,

Function: . Valves open with differential pressure to provide flow path from the safety injection pumps to the reactor coolant system. Normally closed.

Test Requirement: Exercise the valves every three months.

Basis For Relief: During operation, the safety injection pump discharge pressure (1500 psig) is insufficient to overcome reactor coolant system pressure. The recirculation line size is also insufficient' to allow full stroke exercising during operation.

During cold shutdowns, testing is prohibited because the safety injection pumps are deactivated for low temperature overpressurization protection reasons. Thus, a full stroke test is not possible.

Alternate Testing: These valves will be full' stroke tested during the pump full flow test at refueling shutdowns. These valves are also partially stroke exercised during operation.

9 i

VALVE RELIEF REQUEST NO. 8 System: Safety Injection, Units 1 and 2

- Component: 858-A & B

- Category: C Class: 2 Function: Valves open with differential pressure to provide flow path from refueling-water storage tank to the spray pump suction. Normally closed. )

Test Require.nent : Exercise these valves every three months.

Basis For

- Relief 'These check valves can only be full stroke tested during a full-flow test of the spray pumps. A full-flow test of.the spray pump would require actual spraying of borated water through the-spray nozzles in containment.

Alternate Testing:- This. valve..will be partial stroke exercised during the containment spray system. test required in the Technical Specification.

-During reactor refueling shutdowns, this valve will'be dis-assembled and visually inspected.

r 4

e

9 VALVE RELIEF REQUEST NO. 9 Systerit: Safety Injection, Units 1 and 2 Component 862-A G B Category: A/C Class: 2 Function: Valves open with differential pressure to provide flow path from the spray pumps to the containment spray nozzlee.

Normally closed. In the closed position, this valve serves as a containment isolation valve.

Test

- Requirement: Exercise the valves every three months.

. Basis For Relief: These check valves can only be full stroke tested during a full-flow test of the spray pumps. A full-flow test of the spray pumps would require actually spraying borated water through the spray nozzles in containment. Partial stroke testing of these valves could also result in spraying containment, thus, will not be performed.

Alternate-Testing: These valves will be disassembled and visually inspected at reactor refueling outages.

Seat leakage testing of these valves will be performed in accordance with 10 CFR 50, Appendix J.

- . -,, m.- _.-_,, , , - ._ _ . , . - _ _ . . , , . ~ . _ - ~ _. , , . - -

, VALVE RELIEF REQUEST NO. 10 Systems' Auxiliary. Coolant, Unit?. 1 and 2-

, Comporeent: 755-A & B Category: A/C Class: '2 Funchion: ' Valves close.With differential pressure to isolate the component

. cooling line in the event of containment isolation. Normally

. open.

1 Test ~

Requirement: Exercise the valves every three months and perform a seat leakage test every two years.

Basis For' Relief: To properly stroke test the valve requires the' securing of componeret cooling water flow to the reactor coolant pump.

This is not practical during normal operation because it could require the possible securing of a reactor coolant pump.

Only method to verify full closu;& is to perform leak test on the valve.~

Alternate Testing: These valves will be full stroke exercised at refueling.

Seat leakage. testing will be performed in accordance with 10 CFR 50,' Appendix J.during reactor refuelings.

9 .'

C-

E VALVE RELIEF REQUEST NO. 11_

System:- Reactor Coolant, Units 1 and 2

-Component: 528 Category: 'A/C Class: 2

Functions- Valve closes with differential pressure to isolate the nitrogen line to isolate the containment. Normally closed.

Test Requirement: - Exercise the valve every three months and perform a seat leakage test every two years.

- Basis For Relief: Valve is nomally closed. The only method to verify closure

i - is by leak test.

4 1Alterndte Testing: This valve will be, full stroke exercised at refueling.

Seat leakage testing will be performed in accordance with 10 CFR 50, Appendix 3 during reactor refueling outages.

+

-N t , , ,,y', , , - - - - , ,~, -e--, sw--- , , - - , < - - - . - , - . . e---. -e e-w--n - v

VALVE RELIEF REQUEST NO. 12 System: Chemical & Volume Control, Units 1 and 2 Component: 304-C & D Category: A/C Class: 2 Function: Valves shut with differential pressure to isolate the seal water injection line in the event of a containment isolation.

Normally open.

Test Requirement: Exercise the valves every three months and perform a seat leakage test every two years.

Basis For Relief: Valve is normally open. The only way to verift- full closure to to secure reactor coolant pump seal flow and perform valve leak test. Closure of this valvo could cause reactor coolant pump damage.

Alternate Testing: These valves will be verified closed via the performance of a seat leakage test at reactor refueling outages.

4

.- 4 ..

,c

.o '

s i

VALVE RELIEF REQUEST NO. 13 iSystem: Chemical & Volume Control, Units 1 and 2 ,

Component: 370 Category: - A/C Class: -2

, Function: Valve closes.with differential pressure to isolate the charging

- line in the event of a containment isolation. Normally closed.

Test.

Requirement: Exercise the valves every three months and perform a seat leahage test every two years.

Basis For Relief: Valve is norme.lly open. The only way to verify full closure j is to secure normal charging flow and perform valve leak test. Closure of this valve will cause a transient to rt: actor ,

coolant pump seal injection flow with possible pump damage resulting.

Alternate. '

. Testing:- This valve will be verified closed via the performance-of r

a seat leakage test at reactor refueling outages.

1 4

i a

i e c

l' I

+

~n ..m-+m,- . , , . , , . n,-. . - m.,--c, - - - , e., ,n- . ,,, - , - . .. w ,- e v - m + . - .,,r, , - - - ,-r.,

VALVE RELIEF REQUEST NO. 14 .

System: haste Disposal System, Units 1 and 2 .

Component: 1713 Category: A/C Class: 2 Function: Valve shuts with differential pressure to isolate this nitrogen supply line in the event of a containment isolation. Nomally closed.

Test Requirement: Exercise the valve every three months and perfom a seat leakage test every two years.

Basis For Relief: The valve is normally shut. The only way to verify closure is to perform a valve leak test.

Alternate Testing: This valve will be verified closed via seat leakage testing at reactor refueling outages.

4 e

e

4 VALVE RELIEF REQUEST No. 15 System: Auxiliary Coolant System, Units 1 and 2 Component: 767 Category: A/C Class: 2 Function: Valve closes with differential pressure to isolate the component cooling line to ef"ect containment isolation.

Test Requirement: Exercise the valve every three months and perform a seat leakage test avery two years.

Basis For Relief: The only method to verify closure 1.3 by a seat leakage test, which is not performed during reactor operation for ALARA purposes.

Alternate Testing: This valve is leak tested par 10 CFR 50, Apper,lix J during refueling outages. ,

VALVE RELIEF REQUEST.NO. 16 System: Heating & Ventilation, Units 1 and 2 Component: 1200-A CHK Category: A/C Class: 2 Function: This valve closes with differential pressure, in the contr.inment gas and particulate radiation monitor return line, to effect containment isolation.

Test Requirertent : Exercise the valve every three months and perform a seat leakage test every two years.

Basis For Relief: During normal operation, gases from a continuous sampling system return to the containment through this line/ valve.

To Test this valve during operation, or cold shutdown, it would be necessary to disc- arge potentially radioactive gases

. to the environitent. There is no mechanism to partially ctroke this valve.

Alternate Testing: This valve will be verified closed using seat leakage testing at reactor refueling outages.

_-i

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

VALVE RELIEF REQUEST NO. 17

, System: Emergency Diesel Generator Air Starting System, Units 1 and 2

' Components: CV-3057-A, CV-3057-B, CV-3058-A & CV-3058-B Category: .B i

Class:- 3

. Function: This valve opens.to provide starting air to the diesel generator.

- Test' Requirements ,

Measure stroke time and analyze per IWV-3413.

Basis For.

Relief: This is a rapid acting valve. Valve design prohibits visual observance of stroking. Failure of the valve to stroke would result in the failure of,the diesel generator to start on the initial attempt. Since the diesel generators are tested

. biweekly, the subject valve is tested monthly.

Alternate -

Testing: Valve stroke' testing is performed monthly, in. conjunction with the diesel generator start testing. Valve stroking  ;

parameters will be considered acceptable if the associated diesel ~ generator. start was acceptable. If the diesel generator failed to start, at no fault of the valve, the valve stroking

. parameters will be considered acceptable, which will be proven with a restart following diesiel generator corrective action.

se -

/

O VALVE RELIEF REQUEST NO. 18 System: Reactor Coolant, Units 1 and 2 Component: 529 l Category: A/C i

Class: 2 Function: The valve closes with differential pressure to isolate the reactor makeup water supply line to the pressurizer relief tank to effect containment isolation.

Test Requirement: Exercise the valve every three months and perform a seat leakage test every two years.

. Basis For

' Relief: The valve is normally closed. The only method to verify closure is by a seat leakage test.

Alternate Testing: This valve will be full stroke exercised at reactor refueling outages. Seat leakage testing will be performed in accordance with 10 CFR 50, Appendix J.

VALVE RELIEF REQUEST NO. 19 Sy~ tem: Safety Injection, Units 1 and 2.

Component: 842-A & B C tegory: A/C Clnss: 1 Function: Valves open with differential pressure to provide flow path from accumulators to reactor coolant system during loss-of-coolant accident with plant depressurization. Normally closed.

In the closed position, these valves serve as reactor coolant system pressure isolation valves.

T:st Requirements: Exercise the valves every three months and perform a seat k leakage test every two years.

Basis For Rt lef: During normal operation, accumulator pressure of 700 psig cannot overcome reactor coolant system pra-ssure so full or partial stroke testing is not possible. Partial stroke testing during operation via use of L..e test line is also not possible as it would result in violating minimum accumulator levels as setforth in the plant Technical Specifications. A full or partial stroke test is not practical during cold shutdown because the higher pressure accumulators would be connected to the solid primary system which could result in a low temperature overpressurization event. A full stroke test could be possible during refuelings, when the reactor vessel head is removed, but the volume and flow rate required for the test could possibly damage core internals. There would also be the possibility of forcing a nitrogen bubble through the reactor coolant system and refueling cavity resulting in possible safety implications which makes this testing concept inadvisable.

Alternate Trsting: These valves will be partial stroked tested during the transition period from hot shutdown to cold shutdown. This will be considered a cold shutdown test. However, this testing will not be performed if it will result in disturbing an

" Event V" valve which is not re mired to be tested within the associated cold shutdown.  ; addition, these valves will be disassembled and visusM ,+ eted once per 10 year ISI interval. Seat leakage _c .r- t il be performed quarterly coincident with the SI p.#,g Lee and a seat leakage rate of Sgpm or less will be considered acceptable.

\

a VALVE RELIEF REQUERT NO. 20 System: Service Water, Units 1 and 2 Component: ISV-2090 and 2SV-2090 Category: B Class: 3 Function: Valve opens upon a auxiliary feedwater pump start to provide cooling water the the turbine driver's bearings.

Test Requirement: Measure the stroke time and analyze per IWV-3413.

Basis For Relief: This is a rapid acting valve. The valve design prohibits visual observance of stroking. Failure of the valve to stroke would result in unusually high turbine bearing temperatures l during testing.

l Alternate Testing: This valve will be stroke tested during associated auxiliary fcedwater pump testing. Acceptable valve operation will be based on acceptable bearing temperatures during testing.

l l

l

.