ML20104A387
| ML20104A387 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/28/1979 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML19305A338 | List: |
| References | |
| NUDOCS 7903130374 | |
| Download: ML20104A387 (55) | |
Text
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. h POINT BEACH NUCLEAR PLANT I
I UNIT NO. 2 j
i INSERVICE TEST PLAN I
FEBRUARY 1979 i
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INSERVICE TEST PLAN This inservice test plan was prepared in response to U. S. Nuclear Regulatory Commission requirements contained in Part 50.55a of Title 10 Code of Federal Regulations (10 CFR 50.55a).
The tests and inspections required by this test plan are in accord-ance with the American Society of Mechanical Engineers' (ASME) Boiler and Pressure Vessel Code,Section XI,1974 edition with addenda through Sumer, 1975.
This inservice test plan is applicable to Unit 2 of the Point Beach Nuclear Plant, Two Creeks Wisconsin.
Unit 2 was placed into comercial operation on October 1,1972. The plan is applicable to pump and valve periodic testing for the 20-month time period from June 1,1979, through January 31, 1981.
For inservice inspection of plant pressure boundaries, the plan is applicable for the 40-month period June 1,1979, through September 30, 1982.
The inservice test plan is divided into three sections.
Section 1 details the pump and valve periodic tests; section 2 details the inservice inspection tests, and section 3 contains color-coded piping diagrams.
O i0 CFR 50.55e Provides for regeests for reisef by iiceasees from ASME Boiler Code requirements which are deemed impractical. The requirements considered to be impractical at Point Beach Nuclear Plant are identified in the individual sections of this test plan.
It is not possible to determine in advance all the tests and inspections which are impractical to perform.
Therefore it is anticipated that as additional tests and inspections are attempted, some may be identified as being impractical.
The pumps, valves, piping, and other equipment covered by this plan are safety-related ASME Class 1, 2 or 3.
Not all ASME class equipment is safety-related. The equipment determined to be safety-related for the purpose of this test plan is that equipment identified as being safety related in the Final Facility Description and Safety Analysis Reports for Point Beach Nuclear Plant.
Safety related systems and components are those plant features necessary to assure the integrity of the reactor coolant pressure boundary, the capability to shut down the reactor and maintain it in a safe shutdown condition, or the capability to prevent or mitigate the consequences of accidents which could result in exposures not permitted by the Code of Federal Regulations.
The equipment determined to be ASME Class 1, 2 or 3 is that equipment determined to be ASME Class 1, 2 or 3 in the Operating Point Beach Nuclear Plant Materials Repairs, and Modifications Quality Assurance Manual, QA Volume 2.
The color-coded piping and instrumentation diagrams from QA Volume 2 have been color-coded to indicate the safety-related boundaries and are reproduced in Section 3 of this test plan.
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PUMP AND VALVE __ TESTING PROGRAMS ys
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v Part 1 - Pump Testing This section lists those nuclear safety related pumps which make up the Point Beach Nucit.ar Plant Unit 1 inservice pump testing program. The function, code classification, test parameters to be measured, test intervals, additional testing, and specific relief requested from the ASME Section XI requirements are listed for each of the pumps to be tested in accordance with this program.
Relief from those ASME Section XI requirements identified herein as impractical is requested.
1.
PISA &B, High Head Safety injection Pumps Function: High head safety injection Code Class: ASME Section Ill, Code Class 2 Test parameters to be measured:
O' This is a fixed resistance system test 1.
Discharge pressure E.
Bearingtemperature(measuredannually) 3.
Test line flow rate 4.
Vibration amplitude 5.
Fluid temperature Test Intervals: Monthly during periods when the plant is above cold shutdown conditions.
Relief from impractical ASME Code Section XI requirements:
1.
Relief is requested for the requirement for suction pressure and differential pressure measurement.
This pump is operated with a constant suction head, the refueling water storage tank (RWST). The RWST level is maintained at essentially 99% in accordance with Section 15.3.3 of the Technical Specifications and there is no practical value in measuring a constant suction n()
pressure.
Revision 2 February 1979 1.1
I 4
Additional Testina: Once a year during refueling a full flow test is h-conducted while the refueling cavity is being filled. This test allows a head flow curve verification to be made at higher flow rates.
2.
P10A&B. Residual Heat Removal Pumps Function: Low head safety injection Code Class: ASME Section III, Code Class 2
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Test parameters to be measured:
This is a fixed resistance system test 1.
Discharge pressure i
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Suction pressure l_
3.
Bearing temperature (measured annually) 4.
Vibration amplitude O
s-riuid t P ratur-Test Intervals: Monthly during periods when the plant is above cold shutdown conditions.
Relief from impractical ASME Code Section XI requirements: None Additional Testina: There are no additional tests which are considered necessary.
Revision 2 February 1979 1.2 i
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k 3.
P14A&B. Containment Spray Pumps O
Function: Containment depressurization Code Class: ASME Section III. Code Class 2 Test parameters to be measured:
This is a fixed resistance system test 1.
Discharge pressure 2.
Bearing temperature (measured annually) 3.
Vibration amplitude 4.
Fluid temperature Test Interval: Monthly during periods when the plant is above cold shutdown conditions.
Relief from impractical ASME Code Section XI requirements:
1.
Relief is requested for the requirement for suction pressure and differential pressure measurement. This pump is operated at a constant suction head, the refueling water storage tank (RWST). The RWST is maintained at essentially 99% in accord-ance with Section 15.3.3 of the Technical Specifications and there is no practical value in measuring a constant suction pressure.
Additional Testina: There are no additional tests which are considered necessary.
4.
P29. Turbine-Driven Auxil f ary Feedwater Pumps Function: Steam generator auxiliary feedwater Code Class: ASME Section !!!. Code Class 3 O
Revision 2 1.3
r-Test parameters to be measured:
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This is a fixed resistance system test 1.
Discharge pressure 2.
Suction pressure 3.
Turbine RPM 4.
Bearing temperature (measured annually) 5.
Vibration amplitude i
6.
Fluid Temperature Test Interval: Monthly during periods when the plant is above cold shutdown conditions.
Relief from impractical ASME Code Section XI requirements: None Additional Testing: There are no additional tests that are considered necessary.
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5.
P38AAB. Electrically-Driven Auxiliary Feedwater Pumps Function: Steam generator auxiliary feedwater Code Class: ASME Section !!!, Code Class 3 Test parameters to be measured:
l This is a fixed resistance system test l
1.
Discharge pressure 2.
Suction pressure Revision 2 (V
February 1979 a
1.4
3.
Bearing temperature (measured annually)
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4.
Vibration amplitude 5.
Fluid temperature Test Interval: Monthly during periods when the plant is above cold shutdown conditions.
Relief from impractical ASME Code Section XI requirements: None Additional Testing: There are no additional tests that are considered necessary.
6.
P32A, 8. C, D, E & F. Service Water Pumps Function:
Provide vital cooling water Code Class: ASME Section III, Code Class 3 Test parameters to be measured:
1.
Discharge pressure 2.
Circulating water forebay level 3.
Vibration amplitude 4.
Fluid temperature Revision 2 p
February 1979 V
1.5
Test Intervals: At least monthly. The two running pumps are (O :
normally tested every two weeks. Then the pumps are shifted to i
V the preferred pumps for the next two weeks period and they are tested.
Relief from impractical ASME Code Section XI requirements:
l 1.
Relief is requested for the requirement of differential pressure measurement.
The forebay level is measured with each test and it will enable any variation in discharge pressure which is caused by forebay level changes to be explained.
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l 2.
Relief is requested for the requirement of measuring bearing temperature.
These pumps are vertical, water-lubricated pumps and bearing temperature is not accessible.
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3.
Relief is requested for the requirement to measure flow. The l
measurement of discharge pressure will allow pump wear to be evaluated. The redundancy provided (six pumps with only four required) will insure required capacity at all times without i
installing flow instrumentation.
?O Additional Testing: There are no additional tests which are considered i
necessary.
Part 2 - Valve Testing This section lists the nuclear safety related valve testing requirements which I
make up Point Beach i.uclear Plant inservice valve testing program. This section is divided into four subsections. They are:
i A.
Category A Valve Leak Testing Requirements l
B.
Category A'& B Valve Testing Requirements C.
Category C, D, and E Valve Testing Requirements D.
Valve Testing Requirements Determined to be Unpractical Revision 2 February 1979 1.6
A.
Category A Valve Leak Testing Requirements y
tv The'following valves are leak tested during refueling outages in accord-ance with Appendix J:
WL-1721 Common suction to reactor coolant drain tank pumps Test valve between WL-1721 and containment penetration (A-E) 816 Refueling water storage tank recirculating pump (P33) suction from refueling cavity (A-E)
WL-1698 Reactor coolant drain tank divert valve to -19' sump WL-1003A Reactor coolant drain tank pump (P18) suction WL-1003B Reactor coolant drain tank pump (P66) suction 3 71 Reactor coolant system letdown isolation 31 3 Reactor coolant pump seal water return DI-9 Demineralized water to containment (A-E) l DI-10 Demineralized water connection between DI-9 and the containment l
(A-E)
Containment permanent test connection (A-E)
WL-1786 Pressurizer relief tank and reactor coolant drain tank vent WL-1713 Nitrogen supply to reactor coolant drain tank check valve (A-C) i WL-1787 Pressurizer relief tank and reactor coolant drain tank 528 Nitrogen sulply check valve to pressurizer relief tank (A-C) 846 Nitrogen supply to safety injection accumulators Post-accident vent system valves 12 and 13 (A-E)
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l 370 Nonnal charging check valve (A-C) 966C Hot leg sample l
966B Pressurizer liquid sample l
966A Pressurizer gas space sample 304C Seal injection to "A" reactor coolant pump (A-C) 304D Seal injection to "B" reactor coolant pump (A-C)
Permanent test connection valve "B" (A-E) 529 Reactor makeup water check valve to containment (A-C) 508 Reactor makeup water to containment H-8containmentsampleline(A-E) 2 H -9 containment sample line (A-E) 2 Post-accident containment ventilation valve #4 Post-accident containment ventilation valve #6 Post-accident containment ventilation valve #5 Post-accident containment ventilation valve #7 l
1296 Auxiliary charging line IA-33A Instrument air to containment check valve (A-C)
IA-3047 Instrument air to containment l
IA-34A Instrument air to containment check valve (A-C)
IA-3048 Instrunent air to containment j
SA-C '
Serviceairtocontainmentcheckvalve(A-C) 538 Pressurizer relief tank to gas analyzer 539 Pressurizer relief tank to gas analyzer '
hm 1.7
t 2084 "B" steam generator sample (n\\
2083 "A" steam generator sample d-1788 Reactor coolant drain tank to gas analyzer 1789 Reactor coolant drain tank to gas analyzer 2045 "B" steam generator blowdown 2042 "A" steam generator blowdown 632 Heating steam to containment (A-E) (A-E) 633 Condensate return from containment B&E Containment test connection valves (A-E) l 862A Spray pump discharge check valve (A-C) l 8628 Spray pump discharge check valve (A-C) 1723 Sump "A" drain valve 1728 Sump "A" drain valve 3212 Purge exhaust valve 3213 Purge exhaust valve 3244 Purge supply valve 3245 Purge supply valve 3200C Ril/12 supply piping 32008 R11/12 supply piping i
Valve #4 Ril/12returnpiping(A-C) l 3200A Ril/12 return piping l
767 Component cooling water to excess letdown heat exchanger (A-C) l 769 Component cooling water from excess letdown heat exchanger l
D-7 Drain valve on component co'oling water line from excess letdown l
heat exchanger (A-E) 755A Component cooling water to "A" reactor coolant pump (A-C)
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759A Component cooling water from "A" reactor coolant pump 1
755B Component cooling water to "B" reactor coolant pump (A-C) 7598 Component cooling water from "B" reactor coolant pump B.
Category A and B Valve Testing Requirements The following valves will be cycled every three months:
538 Pressurizer relief tank to gas analyzer (containment isolation) 539 Pressurizer relief tank to gas analyzer (containment isolation) 508 Reactor makeup water to containment (containment isolation) 371 Normalletdown(containmentisolation) 1296 Auxiliary charging 825A High head safety injection pump suction from RWST 8258 High head safety injection pump suction from RWST 856A low head safety injection pump suction from RWST 056B Low head safety injection pump suction from RWST s97A Safety injection test line return to RWST 8978 Safety injection test line return to RWST 2838 Service water from 4D heat exchanger 2839 Service water from 3D heat exchanger
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l 2907.
- Service water from containment ventilation coolers C'.
2908 Service water from containment ventilation coolers 860A Spray to containment 860B Spray to containment 860C.
Spray to containment 8600 Spray to containment 4020 "B" auxiliary feed pump discharge to Unit 1 "B" steam generator 4021 "B" auxiliary feed pump discharge to Unit 2 "B" steam generator 4022 "A" auxiliary feed pump discharge to Unit 2 "A" steam generator 4023 "A" auxiliary feed pump discharge to Unit 1 "A" steam generator 2015 "B" steam generator atmospheric steam dump 2016 "A" steam generator atmospheric steam dump 2002 P29 supply trip valve l
2083-
"A" steam generator sample (containment isolation) 2084 "B" steam generator sample (containment isolation) 2042 "A" steam generator blowdown isolation 2045 "B" steam generator blowdown isolation 2019 "B" steam generator supply to P29 2020 "A" steam generator supply to P29 l
SA-10 Unit 2 steam supply to radwaste system SA-9 Unit I steam supply to radwaste system l
1698 Reactor coolant drain tank valve to -19' sump 1003A Reactor coolant drain tank pump suction 10038 Reactor coolant drain tank pump suction 1786 Pressurizer relief tank and reactor coolant drain tank vent l
1787 Pressurizer relief tank and reactor coolant drain tank vent j
Q 846 Nitrogen supply to safety injection accumulators 966A pressurizer gas space sample
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966B Pressurizer liquid sample i
966C Hot leg sample 3047 Instrument air to containment 1
3048 Instrument air to containment 1788 Reactor coolant drain tank to gas analyzer 1789 Reactor coolant drain tank to gas analyzer 1723 Sump "A" drain 1728 Sump "A" drain l
3200A Ril/12 return piping 3200B Rll/12 supply piping 3200C Rll/12 supply pipirq t
l 850A "B" sump suction te low head safety injection pump l
850B "B" sump suction to low head safety injection pump 851A Sump "B" suction to low head safety injection 851B Sump "B" suction to low head safety injection l
852A Low head safety injection reactor vessel isolation 8520 Low head safety injection reactor vessel isolation 4006 Service water supply to p29 l
4016 Service water supply to P38B l
4009 Service water supply to P38A i
1721 Common suction to reactor coolant drain tank pumps O
Revision 2 February 1979 1.9
1 Q
C.
Category C. D. and E Valve Testino Requirement _s_
For the purpose of this listing, the use of the term " cold shutdown" is assumed to mean a shutdown to less than 2000F on the primary systems which has an anticipated duration of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
Tested Every Cold 1.
Category C Check Valves 3 Months Shutdown 710A&B Residual heet removal pump discharge x
842A&B Safety injection accumulator discharge x
847A&B Containment spray system flow x
to eductor 853A,B,C&D First and second off low x
I head safety injection 854A&B Residual heat removal pump suction x
l 8678 First off high head safety injection x
889A&B High head safety injection x
j pump discharge I
Service water to containment coolers (4) x Service water pump discharge (6) x i
"A" and "B" main steam x
Auxiliary feed pump suction (3) x Auxiliary feed pump suction (3) x First-off auxiliary feed to steam j
generator (2) x Second-off auxiliary feed to steam j
generator x
a i
2.
Category C Relief Valves Category C relief valves will be tested for their setpoint.
Frequency i
will be per Section XI.
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887 Safety injection test line I
861A Residual heat removal to reactor vessel 434 Pressurizer 435 Pressurizer 2005 "B" steam generator 2006 "B" steam generator 2007 "B" steam generator 2008 "B" steam generator 2010 "A" steam generator i
O zoii "A" se 9 a r tor 2012 "A" steam generator 2013 "A" steam generator 203 CVCS letdown Revision 2 february 1979 1.10
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3.
Category D Valves
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There are no category "D" valves which require testing in accord-ance with ASME Section XI.
4.
Category E Valves There are no category "E" valves which are tested other than those classified as category "AE".
These valves are so identified in the category "A" list.
D.
Valve Testing Requirements Determined to be Impractical.
The following listed valves have one or nore Code requirements which have been determined to be impractical. The specific Code requirements identi-fled as being impractical together with supporting information and tests to be performed in lieu of the Code requirement are listed after each valve.
Relief from the ASME Section XI requirement identified herein is requested.
1.
842A&B. "A" and "B" Safety Injection Accumulator Discharge Check Valves f]
Function: Normally closed swing check valve which opens on differential pressure to allow the accumulators to deliver borated water to the reactor coolant system.
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. O February 1979 1.11 w
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m Code Class: ASME Section III, Code Class l I
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_ Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements:
1.
IWV-3520, b Requirements for swing disk-type valves.
Support Information:
1.
It is impractical to reasure differential pressure across the valves. Verification of valve opening by reducing system pressure to slightly below the accumulator pressure and noting a water level decrease in the ar.cumulator is a practical method of verifying valve operability.
Inservice Testing in lieu of Section XI: None Implementation Schedule:
It is already in implementation:
O 2.
867A&B, "A" and "B" Loop Safety injection First Off Check Valves Function: Normally closed swing check valves which open on differential pressure to allow the accumulators and the high head safety in.jection system to deliver borated water to the reactor coolant system.
Code Class: ASME Section III, Code Class 1 Valve Category per Section XI:
IWV-2000-C O
Revis4on 2 February 1979 1
1.12
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Impractical Code Requirements:
1.
IWV-3520, a & b - Test frequency (867A only) 2.
IWV-3520, b Requirements for swing disk-type valves.
Support Infomation 1.
It is impractical to test valve 867A except during refueling shutdown. The pressure source required to insure flow could also potentially overpressurize the reactor coolant system.
2.
It is impractical to measure differential pressure across these valves.
Flow can be measured, however in accordance with the following paragraph.
Inservice Testing in Lieu of Section XI: Once per refueling a full flow test is conducted of the high head safety injection system in order to insure the pumps and valves are functioning properly.
Implementation Schedule:
It is already in implementation, n
3.
845A, B, C, D, E & F High Head Safety Injection Second Off Check Valves V
Function:
Normally closed check valves which open on differential pressure to allow the high head safety injection system to deliver borated water to the reactor coolant system.
Code Class: ASME Section III, Code Class 1 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements:
1.
IWV-3520, a S b - Test frequency Support Information 1.
It is impractical to test these valves except during refueling shutdown.
The pressure source required to insure flow could also potentially overpressurize the reactor coolant system.
Inservice Testing in Lieu of Section XI: Once per refueling a test is completed which verifies flow through the check valves.
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Implementation Schedule:
It is already in implementation.
Revision 2 February 1979 1.13
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889A&B, High Head Safety Injection Pump' Discharge Check Valves
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'1 Function:
Normally closed swing check valves which open on high head safety injection delivery of borated water to the reactor coolant system.
Code Class: ASME Section III, Code Class 2 Valve Category per Section XI:
IWV-2000-C.
Impractical Code Requirements 1..
IWV-3520, a & b - Test frequcncy 2.
IWV-3520, b Requirements for swing check-type valves Support Information 1.
It is impractical to full flow test these check valves except during l
the system flow test conducted during refueling. Partial stroking is performed quarterly during pump testing.
2.
It is impractical to measure differential pressure across these valves.
Flow can be measured, however in accordance with the O
following paragraph.
l
_ Inservice Testing in Lieu of Section XI: Once per refueling a test is conpleted which verifies flow through the check valves.
Implementation Schedule:
It is already in implementation.
5.
853A, B, C&D, Low Head Safety injection First and Second Off Check Valves Function: Normally closed swing check valves which open on differential pressure to allow the low head safety injection system to deliver borated water to the reactor coolant system.
Code Class: ASME Section III, Code Class 1 Valve Category per Section XI:
iliV-2000-C Impractical Code Requirements 1.
IWV-3520, b Requirements for swing disk-type valves.
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Revision 2 February 1979 1.14 L -..
Support Information
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l.
It is impractical to measure differential pressure across these valves.
Flow can be measured, however in accordance with the following paragraph.
Inservice Testing in Lieu of Section XI: Once per refueling a full flow test will be conducted of the low head safety injection system in order to insure the pumps and valves are functioning properly.
Implementation Schedule: The test will be implemented at the next refueling upon approval of the Section XI testing program.
'6.
710A&B, Residual Heat Removal Pump Discharge Check Valves l
Function: Normally closed swing check valves which open upon delivery of borated water via the low head safety injection.
Code Class: ASME Section III, Code Class 2 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements l
1.
IWV-3520, b Requirements for swing disk-type check valves.
l O Support Information 1.
It is impractical to measure differential pressure across these val ves.
Flow is measured, however during cold shutdown in accordance withIWV-3520(b).
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
Implementation Schedule:
Not applicable.
Revision 2 February 1979 1.15 n.
3 7.
854A&B, Residual Heat Removal Pump Suction Check Valves Function: Normally closed swing check valves which open upon delivery of borated water via the low head safety injection.
Code Class: ASME Section III, Code Class 2 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, b Requirements for swing disk-type valves.
Support Information 1.
It is impractical to measure differential pressure across these valves.
Flow can be measured, however in accordance with the following paragraph.
Inservice Testing in Lieu of Section XI: Once per refueling a full flow test will be conducted of the low head safety injection system in order to insure the pumps and valves are functioning properly.
V Implementation Schedule: The test will be implemented at the next refueling upon approval of the Section XI testing program.
8.
858A&B, Containment Spray Pump Suction Check Valves Function: Normally closed swing check valves which open on differential pressure to allow the containment spray system to spray the containment atmosphere.
Code Class: ASME Section III, Code Class 2 Revision 2 February 1979
,n)
L 1.16
s Valve Category per Section XI:
IWV-2000-C
' Impract' cal ' Code Requirements i
1.
IWV-3520 Support Infomation 1.
It is impractical.to test these valves. The piping design does not allow design flow through these valves except when they are actually spraying into the containment..
1 Inservice Testing in Lieu of Section XI: There is no additional test-ing needed.
Implementation Schedule: Not applicable, 9.
862A&B, Containment Spray pump Discharge Check Valves O
renction: Normeiiv ciosed swins check valves which open on differentiai c
pressure to allow the containment spray system to spray the containment atmosphere.
Code Class: ASME Section III, Code Class 2 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520 Support Infomation 1.
It is impractical to test these valves other than the leakage test now being conducted. The piping design does not allow design flow through these valves except when they are actually-spraying.into the containment.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
-1.17
Implementation Schedule: Not applicable V
- 10. 840A&B, Spray Additive Tank Vacuum Breaker Valves Function: To open on differential pressure and allow air to back fill the tank as the level is being dropped.
Code Class: ASME Section III, Code Class 3 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520 Support Information 1.
It is impractical to test these valves. The containment spray _
system design does not provide for' raising or lowering the
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additive tank level except in the actual spraying into the con-V tainment atmosphere.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
Implementation Schedule: Not applicable.
- 11. 767, Component Cooling to the Excess Letdown Heat Exchanger Containment Isolation Check Valve Functicn: To close and isolate the component cooling line in the event of a containment isolation.
Code Class: ASME Section III, Code Class MC Valve Category per Section XI:
IWV-2000-C O
1.18
Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this check valve other than its leakage test on a refueling interval.
It is located in containment and testing on more than a once per year basis will cause unnecessary exposure.
Inservice Testing in Lieu of Section XI: There is no additional' testing needed.
Implementation Schedule: Not applicable
- 12. 755A&B, Component Cooling to the Reactor Coolant Pumps Containment Isolation Check Valves Function: To close and isolate the component cooling line in the event 4
of a containment isolation.
Code Class: ASME Section III, Code Class MC Valve Category per section XI:
IWV-2000-C Impractical Code Reautrements i
1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this check valve other than its leak-age test on a refueling interval.
It is located in containment and testing on more than a once per year basis will cause unnecessary radiation exposure.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
3(J 1.19
Implementation Schedule: - Not applicable V
- 13. 304C&D, Chemical and Volume Control System Reactor Coolant Pump Seal Injection Containment __ Isolation Check Valve Function: To close and isolate the seal injection line in the event of a containment isolation.
Code Class:.ASME Section III, Code Class 1 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support-Infonnation
'O 1.
It is impractical to test this check valve other than its leak-age test on a refueling interval. It is located in containment and testing on more than a once per year basis will cause unnecessary radiation exposure.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
l Implementation Schedule: Not applicable l
~
- 14. 370. Chemical and Volume Control S_ystem Normal Charging Line Containment Isolation Check Valve Function: To close and isolate the normal charging line in the event i
of a containment isolation.
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Code Class: ASME Section III, Code Class 2
' O 1.20
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l Valve Category per Section XI': IWV-2000-C
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Impractical Code Requirements--
i 1.
IWV-3520,.a & b' - Test frequency F
Support Information :
i 1.
It is impractical to test this check valve other than its' leak-age test on a refueling interval.
It is located in containment and testing on more than a once per year basis will c6use unnecessary radiation exposure.
Inservice Testing in Lieu of Section XI: There is no additional testing.
needed.
Implementation Schedule: Not applicable i
i
- 15. P29, Steam Driven Auxiliary Feedwater Pump Suction and Discharge Check Valve 4
l Function: Nonnally closed swing check valves which open upon an auxiliary feedwater start signal, to deliver condensate to the steam generator.
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Code Class: ASME Section III, Code Class 3 4
f Valve Category per Section XI:
IWV-2000-C l'
i j
Impractical Code Requirements j
1.
IWV-3520, b Requirements for swing disk-type check valves.
Support Information i
l 1.
It is impractical to measure differential pressure across the valves. Verification of system flow will be done during each pump flow test.
3 Inservice Testing in Lieu of Section XI: In accordance with the requested pump waiver a flow test will be done during plant cooldown.
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Implementation Schedule: The test will be implemented at the next U,,
refueling upon approval of the Section XI testing program.
- 16. P38A&B. Electric Driven Auxiliary Feedwater Suction and Discharge Check Valve
~ Function: Normally closed swing check valves which open on an auxiliary feedwater start signal to deliver condensate to the "A" and "B" steam generators.
Code Class: ASME Section III, Code Class 3 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, b Requirements for swing disk-type check valves.
Support Infonnation Q'
l.
It is impractical to measure differential pressure across the valves. Verification of system flow will be done during each pump flow test.
Inservice Testing in Lieu of Section XI:
In accordance with the requested 1
pump waiver a flow test will be done during plant cooldown.
Implementation Schedule: The test will be implemented at the next refueling upon approval of the Section XI testing program.
~
- 17. Auxiliary Feedwater System First and Second Off Check Valves (6)
Function: Normally closed swing check valves which open upon an auxiliary feedwater start signal, to deliver condensate to the steam generators.
Code Class: ASME Section III, Code Class 2 O
1.22
~
Valve Cateoory per Section XI:
IWV-2000-C y
-tJ Impractical Code Requirements 1.
IWV-3520, b Requirements for swing disk-type check valves.
Support Information 1.
It is impractical to measure differential pressure across the valves. Verification of system flow will be done during each pump flow test.
Inservice Testing in Lieu of Section XI:
In accordance with the requested pump waiver a flow test will be done during plant cooldown.
Implementation Schedule: The test will be implemented at the next refueling upon approval of the Section XI. testing program.
- 18. 529. Reactor Makeup Water Supply to Pressurizer Relief Tank Containment O
iseiet'ee check veive Function: To close and isolate the pressurizer relief tank in the event of a containment isolation.
Code Class: ASME Section III, Code Class MC Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this check valve other than its' leak-age test on a refueling interval.
It is located in containment and testing on more than a once per year basis will cause j
unnecessary radiation exposure.
1.23
Inservice Testing in Lieu of Section XI: There is no additional testing
(,-)~.
needed.
Implementation Schedule: 'Not applicable
- 19. 528. Nitrogen Supply to the Pressurizer Relief Tank Containment Isolation Check Valve Function: To close and isolate the pressurizer relief tank in the event of a containment isolation.
Code Class: ASME Section III, Code Class MC Valve Category per Section XI: IWV-2000-C Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this check valve other than its leak-age test on a refueling interval.
It is located in containment and testing on more than a once per year basis will cause unnecessary radiation exposure.
In addition it is part of a closed (Nitrogen) system outside containment.
Inservice Testina in Lieu of Section XI:
needed.
There is no additional testing Implementation Schedule: Not applicable
- 20. 1713. Nitrogen Supply to Reactor Coolant Drain Tank Containment Isolation Check Valve Function: To close and isolate the reactor coolant drain tank in the event of a. containment isolation.
' O
-1.24
' Code Class: ASME Section III, Code Class MC i
a Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this check valve other than its leak-age. test on a refueling interval.
It is part of a closed (Nitrogen) system outside containment.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
Implementation Schedule: Not applicable
- 21. Containment Service Water Recirculating Cooler Supply Swing Check Valves (4)
Function: To open and allow proper service water flow to the containment coolers.
Code Class: ASME Section III, Code Class 3 Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, b Requirements for swing disk-type valves S.upport Information 1.
It is impractical to measure differential pressure across these valves. Verification of opening-is made by installed flow meters in the line.
Inservice Testing in Lieu of Section XI: There is no additional testing x
needed.
1.25 e.
h Implementation Schedule: Not applicable
- 22. 33A & 34A, Instrument Air to the Containment. Containment Isolation Check Valves Function: To close and isolate containment in the event of a containment isolation.
Code Class: ASME Section III, Code Class MC Valve Category per Section XI:
IWV-2000-C i
Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support Information
(])
1.
It is impractical to test these chec'k valves other than the leak-age test on a refueling interval. The secondary boundary valves 3047 & 3048 are tested quarterly.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
i Implementation Schedule: Not applicable
- 23. Service Air to the Containment, Containment Isolation Check Valve Function: To close and isolate containment in the event of a containment i
isolation.
Code Class: ASME Section III, Code Class MC 4
Valve Category per Section XI:
IWV-2000-C Ag 1.26
Impractical Code Requirements
.,-*)
' ' ~
1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this valve other than the leakage test on a refueling interval. The service air to containment is normally isolated and only cut into the containment when needed.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
Implementation Schedule: Not applicable
- 24. Rll/12 Containment Radiation Monitor Process Return to Containment, Containment Isolation Check Valve Function: To close and isolate containment in the event of a containment Q
isolation.
Code Class: ASME Section III, Code Class MC 4
Valve Category per Section XI:
IWV-2000-C Impractical Code Requirements 1.
IWV-3520, a & b - Test frequency Support Information 1.
It is impractical to test this valve other than the leakage test on a refueling shutdown.
The secondary boundary valve 3200A is tested quarterly.
Inservice Testing in Lieu of Section XI: There is no additional testing needed.
p Implementation Schedule: Not applicable l
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SECTION 2 a g INSERVICE INSPECTION i
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n INSERVICE INSPECTION V
This section covers the inservice ir.spection of pressure boundaries.
It includes inspection of safety related ASME Class 1, 2, and 3 piping, pumps, valves, pressure vessels and heat exchangers. The inspection program for the third forty-month period of the first ten-year inspection interval is presented in tabular fonnat on the following pages.
In the inservice inspection test plan the ITEM NO. listed is the item number assigned by Tables IWB-2600 and IWC-2500 of Section XI of the ASME Boiler and Pressure Vessel Code. The EXAM. CAT. listed is the examination category as assigned by Tables IWB-2500 and IWC-2520.
In those cases where the examination requirement is not included in Tables IWB-2500 or IWC-2520, the applicable paragraph number is listed. EXAM. METH. is the examination method abbreviated as follows:
VT Visual examination PT Surface examination using dye penetrant MT Surface examination using magnetic particle techniques UT Volumetric examination using ultrasonic techiques The INSPECTION INTERVAL (10-YEAR) REQUIREMENT lists the overall testing requirement for the ten-year interval as shown in the 1975 summer addenda to the 1974 Boiler Code.
In general, the PLANNED TESTS DURING 3RD 40-MONTH PERIOD reflect one third of the 10-year requirements. Notable exceptions to this are tests such as system hydrostatic pressure tests and reactor vessel inspections that are perfonned only once during the ten-year period and those examination requirements that are impractical. The tests and examinations that are impractical for the Point Beach Nuclear Plant are identified in the REMARKS column of the test plan.
Relief from those ASME Section XI requirements identified herein as impractical is requested, i
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l POINT BEACH NUCLEAR PLANT l
UNIT 2 INSERVICE TEST PLAN 1
f CLASS 1 l
INSPECTION PLANNED TESTS COPP0NENT TO ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED N0.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS REACTOR PRESSURE VESSEL FIGURE 4.2-1 Closure head to flange weld Bl.3 B-C UT 100%
33-1/3%
Flange to Shell Weld Bl.3 B-C UT 100%
33-1/3%
Instrumentation Penetrations in Lower Head Bl.5 B-E VT 25% (IWA-5000) 25% (IWA-5000)
Control Rod Drive Penetra-tions in Closure Head Bl.5 B-E VT 25% (IWA-5000) 25% (IWA-5000) n3 Closure studs and nuts Bl.8 B-G-1 UT 100%
16 studs and 16 nuts 48 total PT/MT 100%
16 studs and 16 nuts 32 previously inspected Ligaments between threaded stud holes Bl.9 B-G-1 UT 100%
16 Closure Washers Bl.lC B-G-1 VT 100%
16 washers Closure Head Cladding Bl.13 B-I-l VT 100% of 6 patch 100% of 2 patch areas areas each 36 sq.in.
PT 100% of 6 patch 100% of 2 patch areas areas each 36 sq.in.
Upper Internals B1.17 B-N-3 VT 100% of visually 100% of visually accessible attach-accessible attachment ment welds and welds and surfaces surfaces a
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U POINT BEACH NUCLEAR PLAT 1T UNIT 2 INSERVICE TEST PLAN CLASS 1 IflSPECTION PLANT!ED TESTS COMP 0NErlT TO ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE,EXAMIllED NO.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD RErdARKS Vent Line Penetrations in l
Closure Head Bl.19 B-P VT 100% (IWA-5000) 100% (IWA-5000)
Monitoring Taps Bl.19 B-P VT 100% (IWA-5000) 100% (IWA-5000)
Incore Instrumentation Piping and Seal Table Bl.19 B-P VT 100% (IWA-5000) 100% (IWA-5000)
L.2
POIfiT BEACH riUCLEAR PLA!1T UNIT 2 INSERVICE TEST PLAN CLASS 1 ITISPECTION PLANNED TESTS COMPONENT TO 1 REM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMIl4ED N0.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS PRESSURIZER FIGURE 4.2-1 Upper Head to Upper Shell Weld B2.1 B-B UT 5% of weld length 5% of weld length Upper Shell Longitudinal Weld B2.1 B-B UT 10% of weld length 10% of weld length Safety Nozzle Inside Radiused Section B2.2 B-D UT 100%
, 100%
m Spray Nozzle Inside Radiused Section B2.2 B-D UT 100%
100%
Heater Penetrations B2.3 B-E VT 25% (IWA-5000) 25% (IWA-5000)
Safety Nozzle to Safe End Weld B2.4 B-F UT 100%
100%
PT 100%
100%
Spray Nozzle to Safe End Weld 82.4 B-F UT 100%
100%
PT 100%
100%
Support Skirt B2.8 B-H UT 10% of weld length 3-1/3% of weld length Cladding B2.9 B-I-2 VT 100% of 1 patch 100% of 1 patch area area of 36 sq.in.
Temperature, Sampling and Level Nozzles 82.10 B-P VT 100% (IWA-5000) 100% (IWA-5000)
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POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS-1 INSPECTION PLANNED TESTS C0ff0NENT TO ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED
.N0.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS STEAM GENERATORS
~
FIGURE 4.2-1 Nozzle Inside Radiused Sec-tion B3.2..B-D UT 100%
B Steam Generator Inlet and Outlet Nozzles will be examined.
Nozzle to Safe End Weld B3.3 B-F UT 100%
A Steam Generator Outlet and B Steam Generator Outlet Buttered m
Connections will be n
examined.
PT 100%
A Steam Generator Outle t and B Steam Generator Outlet Buttered Connections will be examined.
Cladding B3.8 B-I-2 VT 100% of one patch 100% of one patch area 36 sq.in.
area per Steam Generator per Steam Generator Pressure Retaining Bolting B3.1C B-G-2 VT 100%
11 Manway Bolts from Each Steam Generator will be examined I
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V POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS 1 INSPECTION PLANNED TESTS COMP 0NENT TO ITEM EXAt1 EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAM.INED
_N0.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS REGENERATIVE HEAT EXCHANGER FIGURE 9.2-1 Circumferential Welds B3.1 B-B UT 5% of the length 5% of the length of 4 12 total of each weld welds will be examined.
8 previously inspecte d Nozzle to Shell Weld B3.2 B-D UT 100%
4 welds-will be examined 12-total 8 previously inspected Integrally Welded Supports 83.7 B-H UT 10% of weld length None Ultrasonic examinatior of the support ta vessel tack welds is na
'a not practical because of the curvatures of the vessel end caps.
Liquid penetrant examination of these welds is not practical due to masking caused by penetrant entrap-ment between the support member and vessel shell.
VT 10% of each weld length' Visual examination of the accessible portior s of these welds will be performed in lieu of-ultrasonic examinatiorl, Radiation levels arour d the residual heat ex-changer are 2r to 3r.
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O POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN 4
CLASS 1 INSPECTION PLANNED TESTS COMPONENT TO ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMIilED N0.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS PIPING FIGURES 4.2-1, 6.2-1 and 9.2-1 Circumferential and Longitudinal Pipe Welds Larger Than One Inch Diameter B4.5 B-J JT 25% of circumferen-Approximately P4 cir-291 total tial welds and cumferential welds will 49 previously adjoining one foot be examined.
inspected.
lengths of longitu-dinal welds.
Branch Pipe Connection Welds Larger than Six Inch Diameter B4.6 8-J JT 25%
One weld will be 4 total examined.
Branch Pipe Connection Welds Six Inch or smaller B4.7 B-J PT 25%
One weld will be 18 total examined.
4 previously inspected Socket Welds Larger than 4
One Inch B4.8 B-J UT 25%
Approximately 31 socket 379 total welds will be examined.
64 previously inspected Integrally Welded Supports 84.9 B-K-1 UT 25%
One Weld will be examined 8 total 3 previously inspected
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POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS 1 INSPECTION PLANNED TESTS COMPONENT TO ITEM EXAM EXAf1 INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED
.N0.
CAT.
METH.
REQUIREMENT 40110 NTH PERIOD REMARKS Support Components on Piping Larger than One Inct Diameter B4.10 B-K-2 VT 100 33-1/3% of Support Components will be examined.
Piping One Inch Diameter or less 84.11 B-P VT 100% (IWA-5000) 100% (IWA-5000)
Pressure Retaining Bolting Two Inch-Diameter or less 0*
in Piping Larger than One s
Inch Diameter 84,12 B-G-2 VT 100%
Flange Bolting of 12 total approximately 4 flanges will be examined.
4
POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS 1 INSPECTION PLANNED TESTS COMP 0NENT TO ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED
.NO.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS REACTOR COOLANT PUMPS FIGURE 4.2-1 Studs In Place B5.1 B-G-1 UT 100%
8 studs Studs, When Removed B5.2 B-G-1 UT 100%
8 studs per pump Bolting will not be PT/MT 100%
8 studs per pump disassembled for the sole purpose of exam-ination but if removed for some other to reason it will be examined.
Studs and Nuts, in Place or When Removed B5.3 B-G-1 VT 100%
8 studs and 8 nuts per pump Ligaments B5.3 B-G-1 VT 100%
8 ligaments per pump This examination will be performed only if bolting is disassembled Integrally Welded Supports B5.4 B-K-1 UT 25%
None Volumetric examination of these welds is not practical. The surface is rough and ultrasonic waves do not propagate well in the cast stainless material.
POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS 1 3
INSPECTION FLANNED TESTS COMPONENT T0 ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED NO.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS VT
- 2 for pump A A visual examination
- 1 and #3 for pump B will be performed 'in lieu of the.volu-metric examination.
ll Support Components B5.5 B-K-2 VT 100%
33-1/3% of the support components will be examined.
Pump Casing Welds B5.6 B-L-1 UT 100% of one pump none Volumetric examina-tion of these wilds.
na is not practical.
titrasonic waves do not propagate well in the cast stainless material.
Also the surface roughness is a probl em. We are keeping abreast of the technology in this area and if a
technological advan-ces make volumetric examination of these welds practical in the future the inspections will be performed.
O O
O POINT BEACH NUCLEAR PLAtlT UNIT 2 IflSERVICE TEST PLAN CLAS5 1 IflSPECTION PLANNED TESTS COMP 0NEllT TO ITEM EXAM EXAM IflTERVAL (10 YEAR)
DURING 3RD BE EXAMINED N0.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS VT 100% of weld of one A visual examination pump will be performed in lieu of the ultra-sonic examination.
Pump Casing 85.7 B-L-2 VT 100% of one pump 100% of one pump C
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POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS 1 INSFECTION PLANNED TESTS COMP 0NEUT TO ITEM EXAM EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED NO.
CAT.
METH.
REQUIREMENT 40 MONTH PERIOD REMARKS VALVES
~
FIGURES 4.2-1, 6.2-1 and 9.2-1 Valve Bodies on Valves Exceeding Four Inch Diameter B6.7 B-M-2 VT The interval Three valves will be Valve 700 is a 10 inc h' pressure surfaces of examined if operational Darling Gate Valve, one valve in each conditions permit.
Valves _853A, B, C group of valves of Valve 700, Either Valvo and D are 6" Velan the same design, 853A, B, C or D and Check Valves, Va'lves manufacturing method Either Valve 701 or 701 and 720 are 10 n3 and manufacturer 720.
inch Velan Motor-that perform similar Operated Gate Valves.
functions.
Valves One Inch Diameter or smaller B6.8 B-P VT 100% (IWA-5000) 100% (IWA-5000)
Pressure Retaining Bolting Less than Two Inch Diameter on Valves Larger than One Inch Diameter B6.9 B-G-2 VT 100%
Bolting of approximately 10 valve ;
will be examined.
9 4
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O P0lflT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN CLASS 1 I!!SPECTION PLANfiED TESTS COMP 0NEiiT TO SUB EXAM IllTERVAL (10 YEAR)
DURING 3RD BE EXAMINED ARTICLE METH.
REQUIREMENT 40 M0flTH PERIOD REMARKS System Leakage and Hydrostatic Pressure rests System Leakage Test Reactor Coolant System IWB-5200 VT After each refueling After each refueling.
outage outage System Hydrostatic Pressure Test Reactor Coolant System IWB-5200 VT Once, at or near the One system hydrostatic end of the inspection pressure test will be na
[g interval performed a
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POINT BEACH NUCLEAR PLANT UNIT 2 INSERVICE TEST PLAN
-CLASS 2 INSPECTION PLANNED TESTS COMPONENT TO SUB EXAM INTERVAL (10 YEAR)
DURING 3RD BE EXAMINED PARAGRAPH t1ETH.
REQUIREMENT 40 MONTH PERIOD REMARKS System Pressure Tests Class 2 Safety Related Components Exempted Components
'IWC-2412(a)
VT 100% except open-33-1/3% of the exempted ended portions of a components will be non closed system examined Nonexempt Components IWC-2412(b) 100% except open-100% of the nonexempt to ended portions of a components will be g;
non closed system examined b
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'M POIflT BEACH !!OCLEAR PLAI4T UtlIT 2 It4 SERVICE TEST PLAff -
CLASS 3
~
IllSPECTI071 PLAfl!iED TESTS COMP 0i1ErlT TO EXAM INTERVAL (10 YEAR)
DURIi4G 3RD BE EXAMIllED ARTICLE METH.
REOUIREMENT 40 M074TH PERIOD REMARKS SE tgg Pressure Tests-
~
.i Class'3 Safety Related I
t Systems and Components IWD-2000 E
100% of components 33-1/3% of the. class 3 co@onents wilI be exaniined Visual Examination During Operation or During l nservice Inspection s
a Class 3 Safety Related -
ro L-Systems and Components IWD-2000 VT 100% of components 100% of the Class 3 i
during 1/3 of each components will be inspection interval examined L
4 4
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O SECTION 3 O
PIPING AND INSTRUMENTATION DIAGRAMS i
O
f PIPING AND INSTRtMENTAil0N DIAGRAMS The piping and instrumentation diagrams are presented in this section as an aid to understanding the system configurations and classi-fication of components at the Point Beach Nuclear Plant.
The diagrams are color-coded as follows:
Black Basic piping diagram Red Class I components Green Class 2 components Blue Class 3 components Yellow Instrumentation Brown Containment Purple Safety Related Boundary i
The class 2 components are further coded by symbols to identify those components that are classified as exempted by subarticle IWC-1200.
Many components meet more than one of the requirements of IWC-1200.
In these instances only one of the criteria is coded.
0-0-0 Components four inches or smaller nominal diameter X-X-X Components that perfonn an emergency core cooling function and have controlled water chemistry a-a-a Components which do not function during normal reactor operation i
1 i
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LIST OF FIGURES PAGE FIGURE DESCRIPTION 3.1 4.2-1 Reactor Coolant System Process Flow Diagram 3.2 6.2-1 Safety Injection System, Sheet 1 3.3 6.2-1 Safety Injection System, Sheet 2 3.4 6.2-1 Safety Injection System. Sheet 3 3.5 9.2-1 Chemical and Volume Control System 3.6 9.2-2 Chemical and Volume Control System 3.7 9.2-4 Chemical and Volume Control System 3.8 9.3-1 Auxiliary Coolant System 3.9 9.3-2 Auxiliary Coolant System 3.10 9.3-3 Auxiliary Coolant System 3.11 Drawing M-2207 Piping and Instrument Diagram, Service Water 4
3.12 Drawing M-207 Piping and Instrument Diagram, Service Water, Sheet 1 4
3.13 Drawing M-207 Piping and Instrument Diagram, Service Water, Sheet 2 3.14 10.2-1 Piping and Instrument Diagram Main and Reheat Stea.m 3.15 10.2-2 Piping and Instrument Diagram Condensate and Feedwater 3.16 10.2-5 Piping and Instrument Diagram Auxiliary Feedwater System 3.17 11.1-2 Waste Disposal System Process Flow Diagram Sheet 2 O
PAGE FIGURE DESCRIPTION O
3.18 Drawing G-276-P Cryogenic Noble Gas Removal System Sheet 1 3.19 Drawing G-276-P Cryogenic Noble Gas Removal System, Sheet 2 3.20 Drawing F-2077-P Radwaste Component Cooling Water 3.21 Drawing F-2070-P Radwaste Steam 3.22 Drawing F-2069-P Letdown Gas Strippers 3.23 Drawing F-2068-P Blowdown Gas Strippers 3.24 Drawing F-2071-P Radwaste Condensate 3.25 Drawing 110E018 Auxiliary Coolant System Engineering Flow Diagram 1
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