ML20115D862
| ML20115D862 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/28/1996 |
| From: | Carstens D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20115D861 | List: |
| References | |
| EWI-09.04.01, EWI-9.04.01, NUDOCS 9607150319 | |
| Download: ML20115D862 (117) | |
Text
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4 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 i
Page 1 of 117 ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS SECTION PAGE 1.0 I NT R O D U CTI O N......................................................
5 1.1 Relationship with Technical Specifications..........................
5 1.2 Qualification of Test Personnel..................................
5 j
1 1.3 IST Program Component Selection Criteria.........................
5 1.4 Component Tables and Figures...................................
6 2.0 PUMP INSERVICE TESTING PROGRAM................................
6 3.0 VALVE INSERVICE TESTING PROGRAM.............................
6 3.1 Containment isolation Valves....................................
7 3.2 Pressure Isolation Valves.........................................
7 3.3 C R D Valve s....................................................
7 3.4 D e fe rred Te sting...............................................
7 3.5 Pa rt-stroke Te sting..........................................
7 3.6 Fail-Safe Actu ato rs..............................................
8 3.7 Valve Position Indication Verification..............................
8 3.8 P a s sive Va l ve s..................................................
8
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3.9 S t ro ke Ti m e s...................................................
8 4.0 R E LI E F R EQ U E STS..................................................
9 4.1.
Pump Testing Relief Requests....................................
9 4.1.1 P R-1 (TEST M ETHOD)................................
9 4.1.2 PR-3 (INSTRUMENT RANGE)...........................
10 4.1.3 P R-6 (H PCI VIBRATION)................................
10 4.1.4 PR-8 (CALCULATING INLET PRESSURE)...............
12 4.1.5 PR-9 (INSTRUMENT RANGE)...........................
13 REVIEW AND APPROVALS e
Prepared By: [)% Q u Reviewed By:/fy OC Review Req'd: YES OC Meeting Number: zon Date: M r-.%
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Approved By:
Md Date: m_g O
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3087 (DOCUMENT CHANGE. HOLD. AND COMMENT FORM) incorporate + +4-M0 d-062*- f T- (M Resp Supv: GSE l Assoc Ref: AWi-09.04.01 O JSR: Y Fru, 2' vrs!o ARMS: 09.04.01 l Doc Type: 3005 l Admin initials: Uf-Date:U M(4/M t
I/kmk 9607150319 960710 PDR ADoCK 05000263 P
e MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Ol Page 2 of 117 ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS SECTION PAGE 4.2 Valve Testing Relief Requests....................................
15 4.2.1 RBCW-1 (EXERCISE EACH REFUELING)...............
15 4.2.2 ESW-1 (TEST CHECK VALVES AS PAIRS)................
16 4.2.3 SC-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP)..
17 4.2.4 N B-1 (S RV TE STI N G ).................................
18 4.2.5 REC-1 (EXERCISE EACH REFUELING).......
19 4.2.6 CRD-1 (TESTING DURING SCRAM TEST)...............
20 4.2.7 CRD-2 (TEST EACH REFUELING).......
21 4.2.8 RHR-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP).
21 4.2.9 CS-1 (TEST CHECK VALVES AS PAIR)...................
22 4.2.10 SLC-1 (TEST EACH REFUELING).......................
22 4.2.11 RWCU-1 (TEST EACH REFUELING)..................
23 4.2.12 I A 2 (TEST EACH REFUELING)........................, 23 4.2.13 SW-1 (TEST CHECK VALVES AS PAIRS)................
24 4.2.14 ESW-2 (TEST CHECK VALVES AS PAIRS)...............
24 4.2.15 GR-2 (LRT INCREASED FREQUENCY).................
25 4.2.16 GR-3 (LRT DURING APP J TEST)...................
25 4.2.17 GR-4 (STROKE TIME ACCEPTANCE BANDS)............
26 4.2.18 GR-5 (COLD SHUTDOWN TESTING)....................
27 4.2.19 GR-7 (SP TEST LESS THAN 70 PSI) 27 4.2.20 RSW-1 (CONTROL VALVE TESTING)...................
28 5.0 DEFERRED TESTING JUSTIFICATIONS..................
31 5.1 Mechanical Vacuum Pump lsol Valves.........................
31 5.2 R BCCW lsolation Valves......................................
31 5.3 Feedwater Check Valves Backflow Test..........................
31 5.4 M SIV Fail S afe Te st..........................................
32 5.5 RECIRC Pump Discharge Valves.................
32 5.6 AO Testable Check Valves..............................
33 5.7 R H R I nte rlocks............................................
33 5.8 HPCI Backflow Tests..
34 5.9 RCIC Backflow Tests.....
34 5.10 Air to DW.....................
35 g
5.11 PASS XFV Tests 35 W
5.12 Backfill Check Valves 36 1/kmk
b MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 3 of 117 3
ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS SECTION PAGE 5.13 X FV Te s t s......................................................
36 5.14 Ai r to DW l l........................................
37 5.15 Air to T-R ing Seals..............................................
37 5.16 Air S upply Check Valves.........................................
37
6.0 REFERENCES
38 7.0 R EQU I R ED R ECOR D S.............................................
39 i
8.0 FIGURES.........................................................
40 l
8.1 M ai n S t e a m.................................................
40 8.2 Fe e d wate r...................................................
41 l
8.3 Reactor Recirculation.........................................
42 l
8.4 Co re S p ray................
43 8.5 RHR Loop A.........
44 8.6 RH R Loop B.........
45 8.7 H P C l ( St eam ).............................................
46 f
8.8 H P C I (Wat e r).................................................
47 l
8.9 R CIC (S team)..............................................
48 l
l 8.10 R C I C (Wate r)...............................................
49 8.11 SBLC.......................................................
50 8.12 Primary Containment Atmospheric Control.......................
51 8.13 EDG-ESW...............................................
52 8.14 ESW.....................................................
53 8.15 RHRSVV 54 8.16 CRD-HCU..................................................
55 8.17 CRD-SDV...................................................
56 8.18 Com p re s sed Ai r/FP C C.........................................
57 j
8.19 R B C C W/C ST................................................
58 j
8.20 Liquid R adwaste/RWC U........................................
59 8.21 TIP.........................................................
60 8.22 Excess Flow Check Valves 61 8.23 CGC, DIV I.
62 l
8.24 CGC, DIV ll.
63 8.25 Primary Containment Sampling 64 h
J 8.26 Diesel Generator Auxiliaries.........................
65 8.27 Mechanical Vac Pump /Recirc Seal lnj...........................
66 1/kmk
1 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 -
Page 4 of 117 j
ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS SECTION PAGE 8.28 Level Inst Backfill / Hard Pipe Vent..............................
67 8.29 Safety G rad e N2..............................................
68 j
9.0 ATTA C H M E N TS......................................................
69
{
9.1 P u m p Te stin g Table............................................
69 i
9.2 Valve Table Sym bols...........................................
70 j
9.3 Va 've Testing Table............................................
73 1
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4 1
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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 5 of 117
1.0 INTRODUCTION
l This program identifies the pump and valve inservice testing that will be performed at the Monticello Nuclear Generating Plant to comply with the requirements of 10CFR50.55a and Technical Specification 4.15.B. This program applies to the Third Ten Year Inservice inspection Interval beginning May 31,1992, and ending May 31, 2002. As specified in 10CFR50.55a(b) (1-1-91 Edition), the effective edition of Section i
XI of the ASME Boiler and Pressure Vessel Code applied to this program is the 1986
testing requirements as allowed by Regulatory Guide 1.147 and 10CFR50.55a(f)(4)(iv).
Hereafter in this document, the inservice testing requirements of ASME Section XI and ASME OM will be ccliectively referred to as "the Code" unless a more specific reference is necessary.
1.1 Relatior4 ship with Technical Specifications Monticello will meet all requirements of both the Code and plant Technical Specifications unless there is a specific conflict between the two. In such cases, plant Technical Specifications will govern. Code requirements that cannot be met due to Technical Specification guidance will be identified in relief requests or Technical Specification changes will be prepared.
OV 1.2 Qualification of Test Personnel Personnel performing pump and valve testing per the Code will be qualified in accordance with the IVonticello Nuclear Plant Quality Assurance Program. This is in keeping with the requirements of ASME Section XI, as clarified by ASME Code Interpretation XI-1-82-06R.
1.3 IST Program Component Selection Criteria The components selected for this program are limited to Code Class 1,2, or 3 pumps and valves as stated in 10CFR50.55a. The document that identifies Class 1,2, and 3 components at Monticello is the Color Coded P&lD Q-List Extension. This document shows components that are Quality Groups A, B and C which correspond Code Classes 1,2, and 3 respectively. These components are then judged as to whether they meet the Code scope criteria or if they are exempted from testing by the Code.
Component functions that mitigate the consequences of accidents that are beyond single failure criteria (i.e., beyond the design basis) are not included in this program. For example, valve positions that apply exclusively to Emergency Operating Procedure actions are not included as safety positions that must meet Code testing requirements.
Subcomponents of safety related pumps or equipment are not identified as separate items and will be tested as an integral part of the inservice test. For n
example, the operational readiness of subcomponents of the HPCI pump, such
(')
as the auxiliary oil pump and the turbine driven oil pump, is verified by the satisfactory completion of the HPCI pump's inservice test. Similarly, subcomponents of the emergency diesel generator, such as the jacket water I/kmk
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MONTICELLO NUCLEAR GENERATING PLANT EW1-09.04.01 i
TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 6 of 117 g
l cooling pump and the engine fuel transfer pump, are not included in the IST l
program because they are considered to be an integral part of the emergency diesel generator and are verified by surveillance testing done on the diesel generator. In addition, such subcomponents are not designed to be individually l
tested in accordance with Code rules.
1.4 Component Tables and Figures The components selected for testing are listed in the Tables of Attachments 9.1 and 9.3. This program also provides system figures in Section 8.0 to be used as schematic aides in understanding the pump testing loop and active valve function. These figures are simplified and not controlled drawings, therefore, the P&lD referenced in the tables should be used in lieu of the figures when a detailed understanding of the system is desired.
2.0 PUMP INSERVICE TESTING PROGRAM The pump test program is conducted in accordance with Part 6 of ASME/ ANSI OMa-1988 as allowed by ASME Coos Case N-465, except for relief requested under the provisions of 10CFR50.55a. Attachment 9.1 identifies the pump inservice testing performed at Monticello. This table lists each pump required to be tested, each parameter to be measured, and applicable relief requests. These relief requests are included in Section 4.1 of this program.
g i
The 10CFR50.55a specification of Class 1,2, and 3 components has been used as criteria for including pumps in this program. Non Class 1,2, or 3 pumps judged important to safety are also included in the program. These pumps are easily identified by the word "None"in the ASME class column of the aump testing table. Testing of non-class pumps will be performed in accordance wit 1 the Code to the extent practical.
l Relief requests will not be submitted for non-class pumps if the Code requirements can not be met.
l 3.0 VALVE INSERVICE TESTING PROGRAM The valve test program for Monticello is conducted in accordance with Subsection IWV of Section XI of the 1986 Edition of the ASME Boiler and Pressure Vessel Code, except for relief requested under the provisions of 10CFR50.55a and where all applicable portions of OMa-1988 Part 10 have been invoked. The valve testing performed is shown in the tables of Attachment 9.3. These tables are ordered by P&lD number.
Symbols used to abbreviate the valve test tables are explained in Attachment 9.2.
l Valves judged important to safety but outside the scope of Subsection IWV are also included in the program. These valves are easily identified by the word "None" in the ASME class column of the valve testing table. Testing of these non-code valves will be 3erformed in accordance with the Code to the extent practical.
Relief requests will not 3e submitted for non-code valves if Code requirements cannot be met.
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MONTICELLO NUCLEAR GENERATING PLANT EWl.09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 g
Page 7 of 117 V
3.1 Containment isolation Valves Containment isolation valves (CIV) falling within the scope of the Code are tested in accordance with the Section XI requirements of IWV-3400, Category A, l
with the exception of the seat leakage tests (IWV-3420). The seat leakage I
testing performed on these valves meets the intent of Section XI, but the actual test procedures will be conducted in accordance with the 10CFR50, Appendix J, l
i Type C, ClV test program. See relief request GR-3 in Section 4.2.16.
All CIVs have been categorized as A-Active or A-Passive, and will, as a minimum, be leak tested per 10CFR50, Appendix J. Passive valves will in general have no other testing performed.
3.2 Pressure Isolation Valves The purpose of the plant Pressure Isolation Valves (PlVs) is to reduce the l
possibility of an inter-system LOCA which would occur by pressurizing low pressure systems to pressures exceeding their design limits. These Category A l
valves willbe fully tested per IWV-3420, with the exception of relief requested under GR-2 (see Section 4.2.15).
3.3 CRD Valves The CRD valves included in this program are the scram discharge volume vent h
and drain valves, the sc check valves, the charg, ram inlet and outlet valves, the scram discharge he l
d i
ing water header check valves and the cooling water header check valves. These valves will be functionally tested during the individual rod scram time test required by Technical Specifications to be performed once each operating cycle. An additional test will be performed for the charging water header check valves each refueling.
The cooling water header check valve is also tested by normal control rod motion. Since each partially or fully withdrawn operable control rod is exercised one notch at least once a week in accordance with Technical Specifications, this l
valve will be tested at least quarterly.
3.4 Deferred Testing Valves that cannot be tested during power operation are identified by reference to a Deferred Testing Justification (DTJ)in Attachment 9.3. They are also generally identified by an FC or FR under " Tests Pfrmd". The deferred testing justifications are contained in Section 5.0 of this program.
3.5 Part-stroke Testing The goal of this program is to perform full-stroke tests of all appropriate valves in order to assess the operational readiness of the valves via evaluation of valve degradation. With the exception of those valves for which specific relief has been requested, all valves will be full stroke tested.
O(d Part-stroke testing of power-operated valves is often not possible, due to valve logic circuitry which only allows full-open or full-closed valve movement.
Moreover, the intent of the Code is to assess valve operability through inservice I/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 8 of 117 testing; while a part-stroke exercise does provide some measure of confidence in valve operability, it does not provide assurance of valve safety-related function. In addition, a part-stroke of a power-operated valve has the possibility, through human or mechanical error, to cause adverse plant consequences (isolation of cooling water, plant transients, etc.) via an inadvertent full-stroke.
Therefore, quarterfy part stroke testing of the power-operated valves that are full stroke tested during Cold Shutdowns will not be performed.
Check valves whose safety function is to open will be full stroked when possible.
Since disk position is not always observable, the NRC staff has stated that
" verification of the plant's safety analysis flow rate through the check valve would be an adequate demonstration of full-stroke requirement. Any flow rate less than design will be considered part-stroke exercising." Based on this position, check valves within the scope of this test program will be at least part-stroke exercised whenever any flow is passed through thy valve. Check valves are full-stroke tested on at least the Code required frequency unless identified by relief request. Check valves for which a full-stroke exercise can not be confirmed, therefore, will be identified by an appropriate relief request.
3.6 Fall-Safe Actuators No special tests will be performed for the valves with fail-safe actuators where normal cycling of the valve by the control switch removes the actuator power source. For these valves, the fail-safe function is tested by normal valve exercise testing. All other fail-safe valves will be tested in accordance with IWV-3415.
3.7 Valve Position Indication Verification Verification of valve position indicator accuracy will be performed in accordance with Section XI IWV-3300 with the exception of those valves for which specific relief has been requested.
3.8 Passive Valves These valves, which have no Code operability testing requirements, are valves in safety-related system which are not required to change position in order to accomplish their required safety-function. Monticello has categorized as B-Passive all non-containment isolation valves which are required by procedure to be maintained in their safety-related position. Any valves which are administratively locked-open or locked-closed in their safety-related position arc also considered Category B Passive. Due to the lack of testing requirements, these valves may be excluded from Attachment 9.3.
l 3.9 Stroke Times l
l Valves with extremely short stroke times (less than 2 seconds) have stroke times of such short duration that comparison of measurements with previous data for specified percentage increases is not indicative of degrading valve performance.
With measurement of stroke times to the nearest second per IWV-3413(b), a very small increase in stroke time will result in an extremely large percentage change. Verification that valves meet a specified maximum stroke time of short duration provides adequate assurance of operability.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 9 of 117 Also, the comparison of valve stroke times to the previous test results, without any evaluation of overall change in stroke time from initial test data, is not the oatimum method of gauging valve performance. Therefore, relief has been o]tained (GR-4) from comparing the current valve stroke time with previous stroke time data per IWV-3417 and as an alternative, the current valve stroke time data will be compared with a reference value stroke time taken when the valve is known to be in good condition.
4.0 RELIEF REQUESTS 4.1 Pump Testing Relief Requests 4.1.1 PR-1 (TEST METHOD)
System: Standby Liquid Control (SBLC)
P&lD:
M-127 Pumps:
P-203A and P-203B l
Class:
2 Function:
To inject liquid poison into the reactor.
Impractical Test Requirement:
OM-6-4.6.5; Flow Rate Measurement:
OM-6-5.6; Duration of Tests Basis for Relief: The positive displacement SBLC pumps are designed to pump a constant flow rate regardless of system resistance. The SBLC system was not designed with a flow meter in t.he flow loop. The system was designed to be tested using a test tank where the change in level can be measured over time. This test methodology also limits the pump run time based on the size of the test tank. The cost associated with installing a flow meter would be impractical since changes in tank level over time is an accunio way to measure flow. The orifice used by flow meters could also result in an area where sodium pentaborate crystals accumulate and possibly restrict flow.
Alternative Testing: Determine pump flow rate by measuring changes in tank level over time. The pump will be started with suction from the condensate storage system and will discharge to the test tank. After approximately two minutes of operation the pump will be stopped and the change in level over the measured time will be converted to flow rate by the following formula:
O(GPM) = 261.8 X AL (In)/At (Sec) where 261.8 includes tank dimensions and unit conversions The vibration testing will be performed while recirculating an adequately filled test tank.
(
Therefore, the duration of test code requirements for vibration testing will be met.
Approval: Relief granted in SER dated July 6,1993.
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MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 10 of 117 4.1.2 PR-3 (INSTRUMENT RANGE)
M-120, M-121 Instruments: FT-10-111 A, FT-10-111B, FT-10-97A and FT-10-978 Class:
2 and 3 l
l Function:
Provides a flow signal to an indicating device.
l Impractical Test Requirement:
OM-6-4.6.1.2(a); Full scale range of each analog instrument SHALL NOTbe greater than three times the reference value.
Basis for Relief: Flow transmitters FT-10-111 A, FT-10-111B, FT-10-97A, and FT-10-978 are each designed to indicate flow while two parallel pumps are operating (RHR and RHRSW). During inservice testing, only one pump operates at a time. The resulting reference value of flow for one pump is less than one-third of the instrument's range. Replacing the flow transmitter to meet this requirement would not meet the design intent of providing a flow signal for two pump operation. Installing a second flow transmitter in parallel is impractical and a burden that does not increase the public's safety. These existing transmitters are very reliable. Past calibration records show the typical AS FOUND accuracy is 0.25% of full scale.
Alternative Testing: Use the existing station instruments to measure pump inservice test parameters. Perform a loop check on the flow instrumentation for these systems that verifies the AS FOUND accuracy is within 2% of 3 times the reference value of any RHR or RHRSW pump. This will be done as part of the routine calibration schedule.
Approval: Relief granted in SER dated July 6,1993.
4.1.3 PR-6 (HPCI VIBRATION)
System: High Pressure Coolant injection (HPCI)
P&lD:
M-124 Pump:
P-209 Class:
2 Function:
Injects coolant into the reactor vessel independent of AC power.
Code Test Requirement:
OM-6 Table Sa and paragraph 6.1; Vibration Alert limit of 0.325 in/Sec for the horizontal vibration data points and the resulting increased pump test frequency.
Basis for Relief: 10CFR Part 50, Section 50.55a(a) (3) states (in part):
" Proposed alternatives to the requirements of paragra ahs (c), (d), (e), (f),
and (h) of this section or portions thereof may be usec when... (ii) 1/kmk 1
MONTICELLO NUCLEAR GENERATING PLANT EW1-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 11 of 117 Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The HPCI pump consists of a centrifugal main pump, a separate centrifugal booster pump, a speed reducing gear for the booster p mp, and a Terry turbine steam driver.
All these components are mounted horizontall along the same drive train. Therefore, there are four independently balanced and aligned rotating assemblies that are coupled together. This configuration is significantly different than the typical singt pump and electric motor that the OM 6 limits are based on. As a result, the normal baseline) vibration readings in the horizontal direction on both the booster pump and main pump are approximately 0.325 in/Sec.
Application of a 0.325 in/Sec alert limit would require us to enter accelerated test frequency each time the pump was tested because one or more of these points measured would exceed this limit. Prior to the third ten year interval, the alert limit of 0.325 in/Sec was not a code requirement at Monticello. We have many years of in service test data showing that baseline vibrations at 0.325 in/Sec represent acceatable pump operation and that vibration levels have not trended up. We have also haa these vibration levels analyzed by an Engineering Consultant that specializes in vibration analysis. Their analysis shows that this pump can operate at vibration levels up to 0.700 in/Sec.
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NPRDS component history was reviewed for this type of pump. No failures attributed to Q
extended hours of pump operation at vibration levels exceeding 0.325 in/Sec were found. The pump manufacturer, Byron-Jackson, also stated that these vibration levels did not require corrective action.
Implementing the alert limit of 0.325 in/Sec would recuire us to constantly have the HPCI pump on accelerated test frequency. This wou d result in a monthly pump inservice test instead of quarterly. The intent of increased test frequency is to closely monitor a pump that is deteriorating from its baseline values. In this case, the pump would be operating at its normal vibration range and no change would be seen. The additional 8 tests a year would require a significant amount of time and resources and only create additional maintenance due to normal wear of the system. Modifications to try and reduce the vibration levels, such as installing new shafts and impellers, are extremely expensive and may not reduce the vibration levels. Therefore, requiring an alert limit of 0.325 in/Sec on the HPCI pump is an extreme hardship without a compensating increase in public safety.
An appropriate alert limit for these vibration data points is 0.500 in/Sec. This is based on previous test history, a review of industry data, the vibration analysis performed, and discussions held with the pump's manufacturer.
Alternative Testing: A vibration alert limit of 0.500 in/Sec will be used for the pump horizontal vibration data points. The OM-6 Code's required action limit of 0.700 in/Sec will be adhered to.
Approval: Relief granted in SER dated September 9,1994.
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i MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 12 of 117 4.1.4 PR-8 (CALCULATING INLET PRESSURE)
System: Emergency Service Water, RHR Service Water P&lD:
M-811 Pump:
P-111 A-D and P-109A-D Class:
3 Function:
To provide cooling to safety related equipment; to provide decay heat removal.
Impractical Test Reauirement:
Measuring pump inlet pressure directly.
Basis for Relief: These pumps are vertical line shaft pumps submersed in the plant intake basin. By design, there is no intet to the pump that can provide pressure measurement instrumentation.
Alternative Testing: De! canine pump inlet pressure by converting the static head of water above the pump ir:let to p. essure with the following formula:
P (PSI) = (H (FT) - PEL (FT) X 0.433 where H is the basin level elevation, and PEL is the pump inlet elevation h
The 0.433 factor is based on the density of water at 40 F. The same factor at the design basis temperature of 90 F is 0.431. The difference of 0.002 LB/in -FT is 2
considered negligible.
The basin ievel elevation will be measured from an instrument that is calibrated per OM-6 requirements.
Approval: In a letter dated July 6,1993, the NRC stated this relief request was not required. However, this relief request was written in response to a previous NRC SER, l
dated September 24,1992, Action Item 5.9. Therefore, this relief request will remain in the program and be considered approved by NRC.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 13 of 117 4.1.5 PR-9 (INSTF;UMENT RANGE)
System: High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC)
P&lD:
M-124 HPCI and M-126 RCIC Pumps:
P-209 HPCI and P-207 RCIC Class:
2 Function:
To inject coolant into the reactor independent of AC power.
Test Requirement from which Relief is Sought:
OMa-1988 Part 6 paragraph 4.6.1.2(a), analog instrument range SHALL NOTexceed 3
)
times the reference value.
Basis for Relief: 10CFR Part 50, Section 50.55a(a)(3) states (in part):
" Proposed alternatives to the requirements of paragra ahs (c), (d), (e), (f), (g),
and (h) of this section or portions thereof may be usec when...
(i)
The proposed alternatives would provide an acceptable level of quality O
and safety,..."
V Inservice pump testing is performed in accordance OMa-1988 Part 6. The differential pressure for the HPCI and RCIC pumps is determined by subtracting the indicated suction pressure from the indicated discharge pressure. The HPCI pump suction pressure is read in the Control Room from instrument PI 23-116, which is sent a 10 to i
50 mAmp signal from local transmitter PT-23-100. The RCIC pump suction pressure is read locally from instrument PI-13-66. The relevant data for the instruments is as follows:
REFERENCE INSTRUMENT PUMP RANGE VALUE RATIO PI-23-116 P-209 30" Hg Vacuum 33.7 PSI 114.7/33.7 = 3.4 to 100 PSI (See NOTE 1)
PT-23-100 P-209 10 to 50 mAmps 21.7 mAmps 40/11.7 = 3.4 (See NOTE 2)
PI-13-66 P-207 30" Hg Vacuum 33.7 PSI 114.7/33.7 = 3.4 to 100 PSI (See NOTE 1)
NOTE 1:
The vacuum range for the pressure indicators was converted to PSI for determining the ratio. 30" HG Vacuum = 14.7 PSl; thus the RANGE = 100 + 14.7 =
114.7 PSI. The same principle was applied to the reference value (REF VAL) instrument, the
. With a reference value o()
of 19 PSIindicated on the reference value used for the ratio determination is 19 + 14.7 = 33.7 PSI.
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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 14 of 117 NOTE 2:
The pressure transmitter has a 10 to 50 mAmp range, or a span of 40 mAmps. The ratio for this instrument must be determined by reducing the reference value to its value on the 40 mAmp span (i.e.,21.7 mAmps equates to 11.7 mAmps on the 40 mAmp span).
The code requires the instrument range to be less than 3 times the test parameter reference value. The 2% code allowable instrument tolerance is then taken from this range requirement. The same instrument calibration tolerance can be applied to these instruments by simply calculating the code required tolerance from the code equivalent range as follows:
2% OF CODE REFERENCE CODE EQUlVALENT EQUIVALENT INSTRUMENT VALUE RANGE RANGE PI-23-116 33.7 PSI 3 x 33.7 = 101 PSI i2 PSI PT-23-100 21.7 mAmps 3 x 11.7 = 35.1 mAmps 10.7 mAmps PI-13-66 33.7 PSI 3 x 33.7 = 101 PSI i2 PSI The existing instrument calibration tolerances are i2 PSI for the pressure indicators and 10.8 mAmps for the pressure transmitter. The calibration history for these instruments shows that they easily meet these existing tolerances. Recent calibration i
records show the instruments' AS FOUND accuracy of 1% or less of the code equivalent range.
Under the provisions of 10CFR50.55a(a)(3), this alternative to the Code requirement is proposed in that the alternative provides an equivalent level of quality and safety. The proposed alternative satisfies the code intent in that the accuracy of the instrumentation to assess the operational readiness of the HPCI and RCIC pumps will be maintained within Code requirements.
Alternative Testing: The instruments identified above will be calibrated to 2% of a code equivalent range. The code equivalent range will be calculated by rnultiplying the test parameter reference value by three. For pressure indicators PI-23-116 and PI-13-66 this will result in a allowable tolerance equal to i 2 PSI on the output or 0.7 mAmps on the input (Note: PI-23-116 may be calibrated by determining the mAmps input signal required to establish a set PSI output).
Pressure transmitter PT-23-100 will be calibrated to i 0.7 mAmps for the reasons discussed above.
Approval: Relief granted in SER dated December 8,1994.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 15 of 117 4.2 Valve Testing Relief Requests 4.2.1 RBCW-1 (EXERCISE EACH REFUELING)
System:
Reactor Building Cooling Water Valve:
RBCC-15 Category:
A, C-1 Class:
2 Function:
System check valve for system penetrating primary containment.
Impractical Test Requirement:
IWV-3521; Test Frequency - exercise at least once every three months, quarterly.
Basis for Relief: This check valve is the inboard primary containment isolation valve for a system considered in service during plant operation. The normally open check valve requires an exercise in the reverse flow direction which can only be verified by bak testing. Primary containment leak testing performed each refueling, i.e.,
10 CFR 50 Appendix J, constitutes proper valve exercising. Closing this valve durin power operation would result in temperature transients in the equipment it supplies, g o
including Recirc pump seals, possibly resulting in equipment damage. Also, this valve (j
supplies drywell cooling during power operation and cold shutdown. Performing leak testing per Appendix J during Cold Shutdown would require de-inerting, entering containment, and shutdown of drywell cooling for an extended period, causing equipment damage and personnel hazard.
Alternative Testing: Exercise valve during refueling (at least once every two years) in conjunction with Appendix J leak testing.
Approval: Relief granted SER dated September 24,1992.
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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 16 of 117 4.2.2 ESW-1 (TEST CHECK VALVES AS PAIRS)
System:
Emergency Service Water Valve:
SW-101, SW-102, SW-103, SW-104 Category: C-1 Class:
3 Function: To prevent diversion of ESW flow to non-safety related systems, impractical Test Requirement:
Individual valve closure testing per IWV-3520.
Basis for Relief: Each pair of valves, SW 101/SW-102 and SW-103/SW-104, are in series with no test taps installed between them. Safety function is assured if either one of the pair of valves will provide safety function. This means that testing of the pair of valves will verify system safety function.
i Alternative Testing: Test each pair of valves, SW-101/SW-102 and SW-103/SW-104 l
quarterly by back flow testing each pair. If the pair fails a test, corrective action will be taken on both valves.
Approval: Relief granted in SER dated September 24,1992.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 l
TITLE:
INSERVICE TESTING PROGRAM Revision 3 p
Page 17 of 117 V
4.2.3 SC-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP) i System:
Condensate Storage Transfer (a.k.a. Service Condensate)
Valve:
CST-88, CST-92, CST-94, CST-98 Category: C-1 Class:
2 Function:
These are the boundary valves between the safety related RHR pumps discharge piping and the non-safety related service condensate keep fill system.
Code Test Requirement:
IWV-3520; Full stroke exercise, frequency and method.
Basis for Relief: 10CFR50, Section 50.55a(f) (5) & (6) states (in part):
(5) (iii) If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee SHALL notify the commission...
(6) (i)... The commission may grant relief and may impose alternative requirements... giving due consideration to the burden upon the licensee...
These valves have a closed safety position since they prevent diversion of RHR flow into the service condensate system. There are no test taps or instrumentation installed that would allow testing that proves by positive means that the disc moves to the seat on cessation or reversal of flow. Installation of test taps and isolation valves to reverse flow test these valves is a burden.
Generic Letter 89-04 position 2 allows grouping identical valves and testing them by disassembly and inspection on a refuel frequency.
Alternative Testing: These valves will be grouped and tested in accordance with Generic Letter 89-04 position 2 as follows:
Group: CST-88, CST-92, CST-94, CST-98 All these check valves are the same size, type, and manufacturer. They all perform identical functions and have the same fluid through them. CST-92 and CST-94 interface with the A loop RHR discharge piping while CST-88 and CST-98 interface with B loop RHR discharge piping. Over the course of a refuel cycle, the valves experience the same service condit,ons through the same number of RHR system inservice tests i
and roughly the same RHR loop operating time in shutdown coofing. The valves are all in the same orientation. Therefore, they meet the design and service condition l
grouping criteria of Generic Letter 89-04, position 2.
l Approval: Relief granted in SER dated September 9,1994.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 18 of 117 4.2.4 NB-1 (SRV TESTING)
System:
Nuclear Boiler / Main Steam Valve:
RV-2-71 A, RV-2-718, RV-2-71 C, RV-2-71 D, RV-2-71 E, RV-2-71 F, RV-2-71G, RV-2-71H Category:
B, C-1 Class:
1 Function:
To provide automatic depressurization or overpressure protection for the reactor coolant pressure boundary.
Code Test Requirement:
IWV-3410, Valve Exercising Test Basis for Rellef: 10CFR50, Section 50.55a(f) (5) & (6) states (in part):
(5) (iii) If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee SHALL notify the commission...
(6) (i)... The commission may grant relief and may impose alternative requirements... giving due consideration to the burden upon the licensee...
In addition,10CFR Part 50, Section 50.55a(a) (3) states (in part):
" Proposed alternatives to the requirements of paragraphs... may be used when (i) The proposed alternatives would provide an acceptable level of quality and safety,..."
These valves have an active, self actuation safety function to open and relieve an overpressurization condition in the reactor vessel. The valves also have an i
auxiliary actuating device (as defined in OM-1-1981) that acts to open the valves and depressurize the reactor vessel. This function allows low pressure emergency core cooling systems to inject during a LOCA (ADS) and also controls reactor pressure in certain design transients (Iow low set). The ADS automatic actuation provides for depressurizing the reactor vessel to permit low pressure ECCS system injection during a loss of coolant accident. The low low set automatic actuation provides control of the opening and closing setpoint following a scram during pressurization transients.
Although these valves have an auxiliary actuating device, they can not be treated and tested as category B, power operated valves. The requirements to stroke time them quarteriy is not within the design capability of the valves or the plant. First of all, these valves have a passive safety function to remain closed and provide reactor coolant pressure boundary. Exercising them during power operation would cause a severe reactor power and pressure transient that could result in a reactor scram. It also increases the potential for second stage or pilot stage leakage due to seat wear or fouling. If this leakage is high enough, it can cause a spurious SRV lift and prevent reclosure of the valve. This condition is 1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 19 of 117 1
equivalent to an unisolable small break LOCA event. The NRC states in several documents that such challenges to the ADS function of the main steam l
safety / relief valves should be minimized. Therefore, justification to perform an exercise test on a once-per-cycle frequency is well established.
The reason the valves can not be stroke timed is that there is no direct indication of valve position. Their stroke time can only be measured by indirect means such as changes in turbine bypass valve position indication. This results in a high degree of variability in the measured stroke times due to other plant variables such as reactor pressure, turbine bypass valve position, measuring instrumentation response time, etc. This prohibits repeatable test conditions without a heavy burden on the licensee to fix these parameters each time. This burden is not offset by an increase in public safety since it is the consensus of the entire industry that stroke time testing is not a valuable indicator of margin to failure, for any valve.
Alternative Testing: These valves will be monitored for degradation by testing them in accordance with all applicable sections of OM-1-1981, including the requirements for auxiliary actuating devices. The valves will also be tested in accordance with Technical Specification 4.6.E which includes disassembly and inspection of at least two SRVs each refueling outage.
All SRVs will be exercised at reduced system pressure, in place, each operating cycle to verify the open and close capability of the valve.
Approval: Relief granted in SER dated August 25,1995.
l 4.2.5 REC-1 (EXERCISE EACH REFUELING)
System:
Recirc Loops Pumps and Motors Nuclear Boiler System Valve:
XR-27-1, XR-27-2, XR-25-1, XR-25-2 j
Category:
A, C-1 Class:
2 i
Function:
Prevents reversal of flow from recirc seals to the CRD System.
Impractical Test Requirement:
IWV-3521, Test Frequency - exercise at least once every three months, quarterly.
1 Basis for Relief: These valves are the inlet valves for the lower recirc pump seals.
Exercising could result in loss of seal water to lower seals of the Reactor Coolant Recirculation pumps causing plant trip or ec uipment damage. The reactor coolant recirculation pumps are normally operated c uring all plant operating conditions except refuelinq. Testing during Cold Shutdown would require entering containment, de-inerting, and performing testing identical to 10CFR50 Appendix J testing, which contributes to an unnecessary burden on the Licensee with no corresponding increase in plant safety.
Alternative Testing: Exercise the valves closed during refueling, in conjunction with Appendix J leak testing.
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MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 20 of 117 gW Approval: Relief granted in SER dated September 24,1992.
4.2.6 CRD-1 (TESTING DURING SCRAM TEST)
System:
Control Rod Hydraulic System Valve:
CRD-114, CV-126, CV-127 Category:
C-1, B-1, B-1 l
Class:
2 Function:
CRD-114; Exhaust scram discharge flow from the CRD during a scram.
CV-126; Provide a scram accumulator pressure to the bottom of the control rod drive piston during a scram.
CV-127; Exhaust scram discharge water from the top of the control rod drive piston during a scram.
impractical Test Requirement:
IWV-3411, IWV-3521; Test Frequency - exercise at least once every three months, quarterly.
Basis for Relief: The above listed valves are located on each of the 121 hydraulic control L 'its. There is no practical method of testing these valves in accordance with Section x1 requirements. Testing these valves during power operation requires rapid insertion of each control rod. This introduces rapid reactivity transients and unreasonable wear of the control rod drive mechanism.
Alternative Testing: Proper operation of these valves will be verified by the individual control rod scram time test performed each refueling.
Approval: Relief granted in SER dated September 24,1992.
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MONTICELLO NUCLEAR GENERATING PLANT EWi 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 21 of 117 e
4.2.7 CRD-2 (TEST EACH REFUELING)
System:
Control Rod Hydraulic System Valve:
CRD-115 Category: C-1 l
Class:
2 Function:
Prevents depressurization of accumulator charges on cessation of flow.
Impractical Test Requirement:
IWV-3521; Test Frequency - exercise at least once every three months, quarterly.
Basis for Relief: The above listed valve is located on each of the 121 hydraulic control units. These valves can be tested to verify proper seating only by doing a special test l
1 during cold shutdown / refueling.
Alternative Testing: The test would involve depressurizing the accumulator charging water header and watching for accumulator low pressure alarms. Depressurizing the charging water header would cause a reversal of flow and the ball discs of the CRD-115 i
l valves should move to their seats if a ball disc dld not move to its seat, the associated accumulator would rapidl depressurize and an alarm on low accumulator pressure O
would be received shortl thereafter. This test will be performed at least once each V
operating cycle, i.e., refu ling.
Approval: Relief granted in SER dated September 24,1992.
4.2.8 RHR-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP)
System:
Residual Heat Removal Valve:
RHR-8-1, RHR-8-2 Category: C-1 Class:
2 Function:
Provide minimum flow recirculation from the RHR pumps.
Impractical Test Requirement:
Full flow test open quarterly per IWV-3520.
Basis for Relief: There is no means of measuring flowrate through this valve during quarterly pump testing. Operating the pump with only the minimum flow recirculation line available is not good operating practice, as recommended by the NRC for pump l
protection. This means there is no normal test method to examine these valves condition except disassembly.
Alternative Testing: These valves have been disassembled and manually exercised p
with no discernible degradation detected. Based on the results of these inspections, i,'J one valve will be inspected each refueling outage alternating between the valves. If degradation is detected, repairs will be made and the remaining valve SHALL also be inspected.
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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 22 of 117 Approval: Relief granted in SER dated September 24,1992.
4.2.9 CS-1 (TEST CHECK VALVES AS PAIR)
System:
Core Spray Valve:
CST 103-1, CST-104-1 Category: C-1 Class:
2 Function:
To prevent diversion of core spray flow to condensate storage system.
Impractical Test Requirement:
Individual valve closure testing per IWV-3520.
Basis for Relief: Valves CST-103-1 and CST-104-1 are in series with no test taps installed between them. Safety function is assured if either one of the valves will provide safety function. This means that testing of the pair of valves will verify system safety function.
Alternative Testing: Test the pair of valves, CST-103-1 and CST-104-1, quarterly by back flow testing the pair. If the pair fails a test, corrective action will be taken on both valves.
Approval: Relief granted in SER dated September 24,1992.
4.2.10 SLC-1 (TEST EACH REFUELING)
System:
Standby Liquid Control System Valve:
XP-6, XP-7 Category:
A, C-1 Class:
1 Function:
Standby Liquid Control Injection Check Valves impractical Test Requirement:
IWV-3521; Test Frequency - exercise at least once every three months, quarterly.
Basis for Relief: To verify forward flow operability during normal operation would require firing a squib valve and injecting water into the reactor vessel using the SLC pumps. This is impractical due to the extensive maintenance and cost required to replace squib valves. The SLC system would also be inoperable while changing the squib valves.
Alternative Testing: Verify forward flow operability during refueling while performing the standby liquid control system injection test, which pumps demineralized water into the reactor vessel. Reverse flow testing will be performed during Appendix J leak rate testing.
Approval: Relief granted in SER dated September 24,1992.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 p
Page 23 of 117 V
4.2.11 RWCU-1 (TEST EACH REFUELING)
System:
Reactor Water Cleanup Valve:
RC-6-1, RC-6-2 Category: C-1 Class:
2 Function:
Prevent flow diversion from HPCl/RCIC injection.
Impractical Test Requirement:
Full stroke quarterly per IWV-3520.
Basis for Relief: Closure testing these valves requires testing identical to Local Leak Rate Testing. Closing these valves interrupts RWCU flow, which is required in all modes except refueling tn maintain water chemistry and reduce radioactivity. Closure testing would require an extended period of inoperability of the primary feedwater system, as well as HPCl/RCIC during power operation. in Cold Shutdown, RWCU operates to reduce reactor coolant system contamination.
Alternative Testing: Verify closure at refueling by performance of back flow testing.
Approval: Relief granted in SER dated September 24,1992.
'd 4.2.12 IA-2 (TEST EACH REFUELING)
System:
Instrument Air-Reactor Building Valve:
Al-226-1 and Al-625 Category:
A, C-1 Class:
2 Function:
Prevent reversal of flow in TIP purge line.
Impractical Test Requirement:
IWV-3521; Test Frequency - exercise at least once every three months, quarterly.
Basis for Relief: Check valves Al 226-1 and Al-625 are normally open check valves that are in service during all modes of operation. In addition, there is no practical means available to verify their discs travels promptly to the seat on cessation or reversalof flow.
Alternative Testing: Exercise valve by performance of 10CFR50 Appendix J leak testing during refueling.
Approval: Relief granted in SER dated September 24,1992.
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i MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 24 of 117 4.2.13 SW-1 (TEST CHECK VALVES AS PAIRS)
System:
RHR Service Water Systems and Makeup Intake Structure Valve:
SW-21-1, SW-22-1; SW-21-2, SW-22-2 Category: C-1 Class:
3 Function:
Prevents reversal of RHRSW flow into the service water system.
Impractical Test Requirement:
Individual valve closure testing per IWV-3520.
Basis for Relief: Each pair of valves, SW-21-1/SW-22-1 and SW-21-2/SW-22-2, are in series with no test taps installed between them. Safety function is assured if either one of the pair of valves will provide safety function. This means that testing of the pair of valves will verify system safety function.
Alternative Testing: Test each pair of valves, SW-21-1/SW-22-1 and SW-21-2/SW-22-2, quarterly by back flow testing each pair. If the pair fails a test, corrective action will be taken on both valves.
Approval: Rellei granted in SER dated September 24,1992.
4.2.14 ESW-2 (TEST CHECK VALVES AS PAIRS)
System:
Service Water Systems and Makeup Intake Structure Valve:
SW-15, SW-16; SW-17, SW-18; ESW-13, ESW-14; ESW-15, ESW-16 Category: C-1 Class:
3 Function:
Prevents reversal of flow from emergency water system into the service water system.
Impractical Test Requirement:
Individual valve closure testing per IWV-3520.
Basis for Relief: Each pair of valves are in series with no test taps installed between them. Safety function is assured if either one of the pair of valves will provide safety function. This means that testing of the pair of valves will verify system safety function.
Alternative Testing: Test each pair of valves quarterly by back flow testing each pair.
If the pair fails a test, corrective action will be taken on both valves.
Approval: Relief granted in SER dated September 24,1992.
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MONTICELLO NIJCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3
{
Page 25 of 117 4.2.15 GROtLRT INCREASED FREQUENCY)
System:
Various Valve:
Various Category: A and AC pressure isolation valves (PlV)
Class:
As applicable Function:
Various Impractical Test Requirement:
IWV-3427(b); Trending and Corrective action for leakage rates for valves 6 inch nominal pipe R' and larger.
Basis for Relief: These valves are located inside containment or inside radiation areas during operation and testing on an increased frequency would increase radiation i
exposure for testing personnel. Testing is now being performed during refueling to minimize exposure. With increased frequency, operational constraints would be placed i
upon the plant during cold shutdown. Monticello Nuclear Plant feels that +he leakage rates for valves 6 in, and larger do not show enough consistency in the leve' of degradation prior to reaching the maximum leakage limit to justify maintaining these i
additional corrective action and trending, requirements. This is in keeping with the NRC j
f,)
ap 3 roved OM-10 code on Inservice Testing of Valves, which does not require trending of eakage rates.
v Alternative Testing: Test in accordance with OMa-1988 part 10 paragraph 4.2.2.
~
Approval: Relief granted in SER dated September 24,1992.
4.2.16 GR-3 (LRT DURING APP J TEST)
System:
Various i
Valve:
Various Category: All those identified category A or A/C containment isolation valves in the valve testing tables.
3 Class:
As Applicable Function:
Various impractical Test Requirement:
IWV-3421 through 3425 regarding leak rate test i
methodology, and IWV-3427(b).
1 Basis for Relief: In keeping with NRC Staff position, all CIV testing SHALL be performed under 10CFR50 Appendix J in addition to IWV-3426 and IWV-3427(a) of Section XI. Testing per 10CFR50 Appendix J meets the intent of leak rate testing per i
Section XI, but will be controlled via the Local Leak Rate Testing Program.
1 Alternative Testing: Monticello SHALL test all CIVs under the requirements of 10CFR50 Appendix J, in addition to IWV-3426 and IWV-3427(a) of Section XI.
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 26 of 117 h
Approval: Relief granted in SER dated September 24,1992.
4.2.17 GR-4 (STROKE TIME ACCEPTANCE BANDS)
System:
Various Valve:
Various Category:
A, B Class:
Various Function:
Various impractical Test Requirement:
IWV-3413; Power Operated Valves, IWV-3417; Corrective Action Basis for Relief: Generic Letter 89-04 Position 6 recognizes that measuring changes in stroke times from a reference value as opposed to measuring changes from the previous test is a bettc,r way to detect valve degradation. Generic Letter 89-04 Position 5 and OMa-1988, Part 10 provide NRC approved methodology for establishing a stroke time reference value, an acceptable stroke time band, and a limiting stroke time value.
The alternative testing is in accordance with this methodology.
Alternative Testing: The power operated valve testing will be performed in accordance with OMa-1988, Part 10, paragraphs 4.2.1.4,4.2.1.8, and 4.2.1.9. The acceptable band and Limiting Stroke Time (LST) will be determined as follows (RV time in Sec):
Operator Tvpe Ref Value Ace Band LSI Motor RV > 10 0.85RV '.15RV 1.3RV 2 s RV s 10 0.75RV - 1.25RV 1.5RV Other RV > 10 0.75RV - 1.25RV 1.5RV 2 s RV s 10 0.50RV - 1.50RV 2.0RV All RV < 2 s2 2
in addition, if a more restrictive value of stroke time exists in the Technical Specifications or the Updated Safety Analysis Report, it will be used as the LST instead of the value calculated above.
Approval: Relief granted in SER dated September 24,1992.
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j MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 l (~]
Page 27 of 117 v
4.2.18 GR 5 (COLD SHUTDOWN TESTING)
System:
See Valve Testing Table Valve:
See Valve Testing Table Category: Various Class:
Various Function:
Various l
Impractical Test Requirement:
IWV-3412; Complete all cold shutdown frequency exercise testing prior to plant startup.
Basis for Relief: IWV-3412 has no allowance to startup the plant prior to completing the cold shutdown frequency exercise testing. The NRC approved OM-10 code on valve testing states that it is not the intent of the Code to keep the plant in cold shutdown in order to complete cold shutdown testing and it allows valve exercising to be deferred to refueling outages if quarterly and cold shutdown testing is not practical.
Monticello has changed the frequency of many check valve exercise tests from refueling to cold shutdown in response to the Technical Evaluation Report comments in this program's SER dated September 24,1992. This makes a large number of reverse flow check valve tests which are quite labor and time intensive required at cold I
3 I (d shutdown. Requiring that all cold shutdown tests be completed prior to startup is l
impractical and a burden especially for unplanned and short outages.
Alternative Testing: Cold shutdown valve exercising for unplanned or forced outages, SHALL commence 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 is achieved. All valve testing does not have to be completed prior to subsequent plant startup. For extended outages, including refueling, where all required testing can be completed, exception to the above start time may be taken. However, during these extended outagos, all cold I
shutdown frequency testing will be completed prior to plant startup, in the event cold shutdown doesn't require specific de-inerting of containment, those valves requiring containment access for cold shutdown testing will be deferred until the next cold shutdown that provides containment access.
Approval: Relief granted in SER dated September 9,1994.
4.2.19 GR-7 (SP TEST LESS THAN 70 PSI)
System:
various l
l Valve:
Various Relief Valves Category: C Class:
Various Function:
To provide overpressure protection at 70 PSI or less, impractical Test Requirement:
IWV-3512, Test Procedure and OM-1-1981 paragraphs 1.3.3.1.5(b) and 1.3.4.1.5(b), Valves Not Meeting Acceptance Criteria 1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 28 of 117 Basis for Relief: OM-1-1981 requires that if a relief valve exceeds its stamped set pressure by 3% or greater, then the valve requires corrective action. This requirement is unnecessarily restrictive for valves with a set pressure of 70 PSI or less as it is smaller than the design and construction tolerances. The ASME Boiler and Pressure Vessel Code, Section 111, specifies a tolerance of plus or minus 2 PSI for the design and operation of overpressure protection safety valves with a setpoint up to 70 PSI.
Applying a 2 PSI tolerance for periodic testing of relief valves with a setpoint up to and including 70 PSI is within the requirements of Section ill of the Code and is of no threat to the pressure boundary of power piping designed to nuclear quality standards.
Alternative Testing: For relief valves with a setpoint less than or equal to 70 PSI, the setpoint acceptance criteria will be 12 PSI. For relief valves with setpoints greater than 70 PSI, the setpoint acceptance criteria will not exceed 3% of the stamped set aressure. If a more restrictive acceptance band is required by the system design or icense basis, then that criteria SHALL govern.
i Approval: Relief granted in SER dated October 25,1993.
4.2.20 RSW-1 (CONTROL VALVE TESTING)
System:
Residual Heat Removal Service Water (RHRSW)
Valve:
CV-1728 and CV-1729 Category: B-1 Class:
3 Function:
To open, providing a flow path for RHRSW through the RHR heat exchanger.
Test Requirement from which Relief is Sought:
Section XI, paragraph IWV-3413, (a) The limiting value of Full-stroke time of each power operated valve SHALL be specified by the Owner. Full-stroke time is that time interval from initiation of the actuating signal to the end of the actuating cycle.
(b) The stroke time of all power operated valves SHALL be measured to the nearest second...whenever such a valve is full-stroke tested.
Section XI, Paragraph IWV-3417, (a) If, for power operated valves, an increase in stroke time of 25% or more from the previous test,... test frequency SHALL be increased to once each month until corrective action is taken....
Basis for Relief:
10CFR Part 50, Section 50.55a(f) (5) and (6) states, (in part):
(5)(iii) If the licensee has determined that conformance with certain h
code requirements is impractical for its facility, the licensee SHALL notify the commission....
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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3
(
Page 29 of 117 (6)(i)... The commission may grant relief and may impose altemative requirements... giving due consideration to the burden upon the licensee....
In addition,10CFR Part 50, Section 50.55a(a)(3) states (in part):
" Proposed alternatives to the requirements of paragraphs... may be used when...
(i) The proposed alternatives would provide an acceptable level of quality and safety,..."
IWV-3413 requires that a limiting value of full stroke time be established for a power operated valve and that the stroke time be measured whenever such a valve is full stroke tested. Performing full stroke time testing of these valves is impractical based on i
the control scheme design of the valves, adverse plant impact, and the functional l
requirements of the valves.
lWV-3413 states that full stroke time is that time interval from initiation of the actuating signal to the end of the actuatin,g cycle. The control scheme design of these valves does not receive an actuation signal (neither by manual handswitch nor by automatic logic) to stroke to the position required to fulfill their safety function. RHRSW valves CV-1728 and CV-1729 are air operated control valves on the outlet line of the RHRSW l
side of the "A" and "B" RHR heat exchangers, respectively. These control valves (d_)
maintain a differential pressure between the RHRSW process stream and the RHR l
l process stream during RHRSW system operation. The valves are controlled by a positioner, controlled by a differential 3ressure indicating controller (DPIC). The DPIC l
senses pressure on the RHRSW disclarge line and the RHR inlet line to the RHR heat i
exchanger. The desired differential pressure control point, and thus the desired valve position for system flow, is manually set by the operator by manual adjustment of the DPIC setpoint. The valve positioner positions the valve and modulates the valve position as necessary to maintain this control point. Stroke time testing of these valves on quarterly basis is not consistent with the design of the valve's control scheme and is not in the interest of plant safety.
These valves are interlocked to receive a closed signal when the Residual Heat l
Removal Service Water (RHRSW) pumps are de-energized. This interlock is provided to ensure that system water inventory is not lost during system shutdown. Stroke time i
testing of valves CV-1728 and CV-1729 when the Residual Heat Removal Service l
Water pumps are de-energized would result in the loss of liquid fill for a significant portion of the RHRSW system as well as re I
to minimize the potential for water hammer. quire the bypassing of an interlock des Such testing increases the possibility of an adverse water hammer during startup of the RHRSW system as well as requires filling and venting of the system following the stroke time testing. In addition to the adverse impact on plant operation, such testing results in an undesirable burden on plant resources via the expenditure of person-hours and person-rem to perform system filling and venting.
Stroke time testing of the valves during RHRSW pump operation negates the loss of O
system fill concern; however, this testing would also have an adverse impact on plant safety and equipment int rity. Stroke time testing during pump operation would O
require the valve be initial in the closed position during pump operation. Establishing l
the initial test conditions o a closed valve during pump operation would result in an l/kmk
JONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 30 of 117 h
undesirable deadheading of the pump. Subsequent opening of the valve to perform stroke time testing will result in pump runout if a single RHRSW pum a is in operation, an undesirable condition which adversely impacts pump integrity and performance.
The pump runout concern can be addressed by stroke timing the valve open during operation of both RHRSW pumps; however, this exacerbates the pump deadheading concerns and would result in undesirable transients on the system.
Proper stroke time testing would require the plant to modify the control logic of the valves. This hardship is not offset by an increase in public safety. In addition, the application of stroke time testing requirements to control valves has recently become an issue with the OM code committee and is subject to change and/or clarification. The proposed attemative testing is an effective means to ensure the valves perform their safety function and is consistent with other valve category test requirements, such as check valve exercising.
Alternative Testing:
IWV-3412 provides for demonstrating the necessary valve disk movement by observing indirect evidence (such as changes in system pressure, flow rate, level, or temperature), which reflect stem or disk position. The most representative test of the capability of valves CV-1728 and CV-1729 to perform their intended function is performed during inservice testing of the RHRSW pumps. Quarterly testing of the RHRSW pumps verifies the capability of the valves to operate properly to pass the maximum required accident flow as well as the valve position necessary to achieve required flow conditions. Testing of the valves in this manner demonstrates valve performance capability and provides a means to monitor for valve degradation.
Approval: Relief granted in SER dated August 25,1995.
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MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 31 of 117 5.0 DEFERRED TESTING JUSTIFICATIONS 5.1 Mechanical Vacuum Pump Isol Valves System: Steam Jet Air Ejectors P&lD:
M-104, SH-2 Valves:
AO-1825A, AO-1825B Justification: These valves are not required to be inservice tested by 10CFR50.55a.
They are normally closed during power operation and have a closed safety position. To cycle and stroke time the valves, the mechanical vacuum pump must be started and stopped. Plant operating procedures prohibit operation of the mechanical vacuum pump above 5% power for safety reasons, therefore, the valves will be tested on a cold shutdown frequency.
5.2 RBCCW isolation Valves System: Reactor Building Cooling Water System P&lD:
M-111 Valves:
MO-1426, MO 4229, MO-4230 Justification: These valves are normally open to supply cooling water to critical drywell components such as recirculation pump seals and the drywell coolers. They have a closed safety position as primary containment isolation valves. Full stroke testing these valves interrupts cooling flow to the Drywell and the system is non-redundant. Therefore, cycling these valves risks losing cooling to the Drywell which will result in equipment damage and plant shutdown due to high Dr or temperature. The valves will be tested on a cold shutdown frequency. ywell pre 5.3 Feedwater Check Valves Backficw Test System: Feedwater P&lD:
M-115 Valves:
FW-91-1, FW-91-2, FW-94-1, FW-94-2, FW-97-1, FW-97-2 Justification: These valves are open during power operation as feedwater injection check valves. FW 97-1,2 and FW-94-1,2 have an open safety position because they are in the HPCI or RCIC injection flow path. They have a closed safety position as containment isolation valves. These valves are verified open quarterly as part of normal plant operation. The only method of cycling these valves closed is to perform a reverse flow test. That requires isolating and venting the system and installing O
temporary bypasses (hoses, gages, etc). This cannot be performed without shutting d
down the plant and entering the Drywell. Therefore, the closed position of these valves will be tested on a cold shutdown frequency.
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O MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 32 of 117 FW-91-1,2 have a closed safety position to prevent the diversion of HPCI or RCIC injection away from the vessel. The only method of cycling these valves closed is to perform a reverse flow test. That requires isolating and venting the system and installing temporary bypasses (hoses, gages, etc). This cannot be performed without shutting down the plant and entering the Drywell. Therefore, these valves will be tested on a cold shutdown frequency.
5.4 MSIV Fall Safe Test System: Main Steam P&lD:
M-115 Valves:
AO-2-80A through D Justification: These valves have a closed safety position as primary containment isolation valves. They have a safety related air supply that acts to open and close them. The valves also have a spring to assist them closed. The safety related air supply and springs are taken credit for closing the valves in accident analyses. Since the fail safe function of the valve spring is not independently tested during the quarterly exercise test, a special test to vent the air supply and locally monitor valve stem movement is required. This test cannot be done during power operation since the valves are located inside the Drywell which is not accessible during power operations.
The fail safe test of these valves will be performed on a cold shutdown frequency.
5.5 RECIRC Pump Discharge Valves System: Recirc Loops Nuclear Boiler P&lD:
M-117-1 Valves:
MO 2-53A, MO-2-538 Justification: These are the reactor recirculation pump discharge valves which are normally open during power operation to allow reactivity control using the recirculation pumps. Their safety position is closed to direct LPCI flow into the reactor. The valves cannot be cycled dunng power operation without securing the associated pump and severely interrupting core flow. This can cause equipment damage and also results in i
severe changes in power level which can cause plant shutdown. The valves will be tested on a cold shutdown frequency.
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MONTICELLO NUCLEAR GENERATING PLANT EWl.09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 33 of 117 5.6 AO Testable Check Valves System: RHR P&lD:
M-120, M-121 Valves:
AO-10-46A, AO-10-46B System: Core Spray P&lD:
M-122 Valves:
AO-14-13A, AO-14-13B System: RCIC P&lD:
M-126 Valves:
AO-13-22 Justification: These testable check valves have full reactor pressure holding them o
closed during power operation. The air operator on the check valve is for test purposes only and cannot lift the disc against full reactor pressure. To ensure full stroke using the air operator, the valves will be tested when the reactor is depressurized on a cold shutdown frequency.
5.7 RHR Interlocks System: RHR P&lD:
M-121 Valves:
MO-2026, MO-2027, MO-2029, MO-2030 Justification: These RHR valves are normally closed and have a closed safety position. They have interlocks in their open direction logic that prevents them from opening above a certain reactor pressure, approximately 75 PSIG. This interlock protects the low pressure piping of the RHR system from the high pressure reactor coolant on the other side of these valves. Since these valves are impractical to test during power operation, they will be tested on a cold shutdown frequency.
^
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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 34 of 117 5.8 HPCI Backflow Tests System: HPCI P&lD:
M-123, M-124 Valves:
HPCI-9, HPCI-10, HPCI-14, HPCI-15, HPCI-31, HPCI-65, HPCI-71 Justification: The only way to test the closed safety position of these valves is by using a reverse flow test. Testing them at power requires isolating and venting the system which includes manual valve realignments, opening motor operated valve breakers, and defeating auto start logic which is a significant burden on plant resources. This total loss of system function dramatically reduces the level of safety during power operation. Therefore, the closed position of these valves will be verified by doing a reverse flow test on a cold shutdown frequency.
The open safety position of HPCI-9 and HPCI-10 will be verified during the quarterly inservice test of toe HPCI system. The open safety position of HPCI-31 will be verified on a refuel outage frequency by disassembly and inspection as allowed by OM-10 and 10CFR50.55a (f) (4) (iv). A partial stroke of HPCI-31 will also be performed on a cold shutdown frequency with the same justification as stated in the preceding paragraph.
5.9 RCIC Backflow Tests l
System: RCIC P&lD:
M-125, M-126 Valves:
RCIC-9, RCIC-10, RCIC-16, RCIC-17, RCIC-31, RCIC-57, RCIC-59 Justification: The only way to test the closed safety position of these valves is by using a reverse flow test. Testing them at power requires isolating and venting the system which includes manual valve realignments, opening motor operated valve breakers, and defeating auto start logic which is a significant burden on plant resources. This total loss of system function dramatically reduces the level of safety during power operation. Therefore, the closed position of these valves will be verified by doing a reverse flow test on a cold shutdown frequency.
The open safety position of RCIC-9 and RCIC-10 will be verified during the quarterly inservice test of the RCIC system. The open safety position of RCIC-31 will be verified on a refuel outage frequency by disassembly and inspection as allowed by OM-10 and shutdown freque)n(cy) w(iv). A partial stroke of RCIC-31 will also be performed o 10CFR50.55a (f 4 ith the same justification as stated in the preceding paragraph.
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4 MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 35 of 117 v
5.10 Air to DW l
System: Safety Grade N to DW 2
P&lD:
M-131, SH-10 Valves:
Al 598, Al-708, Al-713, Al-714, Al-730, SV-4235 i
Justification: These valves must be open to supply safety grade nitrogen for critical l
component functions inside the Drywell, among them holding the inboard MSIVs open.
Since the inboard MSIVs fail closed, any interruption of the air supply to them during power operation risks a plant transient from the MSIVs drifting closed. All of these valves, except SV-4235, can only be exercised by), isolating and venting l
across the check valve. Therefore, these valves will be tested on a cold shutdown i
frequency.
l SV-4235 (among others) is not required to be inservice tested by 10CFR50.55a, however, it is included in this test program as good operating practice. Cold shutdown testing frequency is judged to be appropriate to adequately monitor the condition of this valve. Since there are administrative advantages to including SV-4235 in the same test l
procedure as the other valves in the system, it will be tested on a cold shutdown i
frequency.
3 (G
l I
5.11 PASS XFV Tests System: PASS P&lD:
NF-96042 l
Valves:
PAS-59-5, PAS-59 6 l
Justification: These valves are normally open and have a closed safety position to isolate the non-safety post accident sampling (PAS) system from the safety related RHR system. These valves are tested by isolating the system, installing temporary bypasses (hoses, gages, etc.) and performing steps similar to, but more extensive than, l
a check valve seat leakage test. Since this test is done in a high radiation area and it renders the non-redundant PAS system out of service, these valves will be tested on a cold shutdown frequency.
l l
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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 36 of 117 5.12 Backfill Check Valves System: CRD P&lD:
M-116 Valves:
BF-12, BF-14, BF-24, BF-26, BF-35, BF-37, BF-46, BF-48 Justification: These valves are normally open and have a closed safety position to separate the non-safety control rod drive system from the safety related reactor coolant pressure boundary. The lines containing these valves tie into sensitive reactor vessel instrumentation that is important during both power operation and cold shutdown operation. These valves are verified closed by isolating and venting the system, installing temporary bypasses (hoses, gages, etc.), and performing a reverse flow, seat leakage test. Therefore, these valves will be verified closed on a refuel outage frequency as part of their seat leakage test. This frequency is allowed by OM-10 and 10CFR50.55a (f) (4) (iv).
5.13 XFV Tests System: Various h
P&lD:
Various Valves:
XFV-1 thru 89 Justification: These valves are normally open and have a closed safety position as a primary containment barrier. The closed position of these valves is tested by installing temporary bypasses (hoses, gages, etc.) and performing st,eps similar to, but more extensive than, a check valve seat leakage test. The isolation of the lines containing these excess flow check valves takes instrumentation out of service that is important during both power operation and cold shutdown operation. These valves will be tested on a refuel outage frequency as allowed by OM-10 and 10CFR50.55a (f) (4) (iv).
This frequency is consistent with the Technical Specification requirement to verify proper operation of these valves once per cycle.
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MONTICELLO NUCLEAR GENERATING PLANT EWI 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 O)
Page 37 of 117
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5.14 Air to DW ll System: Instrument Air P&lD:
M-131, SH-12 Valves:
Al-571 Justification: This valve is normally open to supply instrument air to certain Drywell components, including the ADS and LLS function of two safety relief valves. It has a closed safety position as a primary containment isolation valve. Its closure test is performed b gages, etc.) y isolating and venting the system, installing temporary bypasses (hos and performing a reverse flow, seat leakage test. Therefore, this valve will be tested on a cold shutdown frequency.
5.15 Air to T-Ring Seals System: Instrument Air - Reactor Building P&lD:
M-131, SH-14 C
Valves:
Al-613 thru 613, Al-663, Al-666, Al-669, Al-672, Al-675, Al-678, Al-681, Al-683, Al 685, Al-694, Al-695 Justification: These check valves are not required to be inservice tested by 10CFR50.55a. They are included in the program as good operating practice. The valves either open or close to ensure safety grade nitrogen is directed to the primary containment atmospheric control valves. The check valves are tested by isolating and venting the system, installing temporary bypasses (hoses, gages, etc.), and verifying full or no reverse flow across them. Due to the burden of this testing, these valves will be tested on a refuel outage frequency. This is consistent with OM 10 and 10CFR50.55a(f)(4)(iv).
5.16 Air Supply Check Valves System: Various P&lD:
Various Valves:
See Valve Testing Tables Justification: These check valves are not required to be inservice tested by 10CFR50.55a. They are included in this program as good oractice. Their closed Josition is important to safety by ensuring air is not rapidly ost after a postulated air line areak. The check valves are tested by isolating and venting the system, installing m
temporary bypasses (hoses, gages, etc), and verifying no reverse flow across them.
Due to the burden of this testing, these valves will be tested on a refuel outage frequency. This is consistent with OM 10 and 10CFR50.55a(f)(4)(iv).
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i MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 38 of 117
6.0 REFERENCES
6.1 10CFR50.55a(g); inservice Inspection 6.2 1986 Edition ASME Boiler and Pressure Vessel Code - Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components 6.3 Monticello Nuclear Plant; Piping and Instrument Diagrams 6.4 Monticello Nuclear Plant; Technical Specifications 6.5 Regulatory Guide 1.26 6.6 ANSI /ASME OM Standards
- OM-1-1981 Relief Valve Inservice Testing
- OM-6 Pump Inservice Testing
- OM-10 Valve Inservice Testing 6.7 Monticello Updated Safety Analysis Report
- Section 5, Containment Isolation
- Section 6, Plant engineered Safeguards
- Section 14, Plant Safety Analysis 6.8 Northern States Power Letter Dated August 12,1982, from D.M. Muso!f to Director NRR; Sul;%ct: Supplemental Information Concerning inservice Testing Program 6.9 Northern States Power and NRC correspondence on Event V valves 6.10 NRC Generic Letter No. 89-04," Guidance on Developing Acceptable Inservice Testing Programs" 6.11 4 AWi-01.03.03 (COLOR CODED P&lD Q-LIST EXTENSION) 6.12 Regulatory Guide 1.147 9
I/kmk
4 MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 39 of 117 7.0 REQlj_lRED RECORDS 7.1 Not Applicable l
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@ F ACCIDENT TOOXYGEN TO HYDROGEN-SAMPLING ANALYZER OXYGEN ANALYZERS M3 y
v v
m O
SV SV-4001B W
g -4001 A j g -4082 SV-3307 Sv j
j
-4 m SV-4081 SV-330s SV-4020A SV-4020B o
a o m O
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r-DW-3 3
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Q CONTAINMENT) DW-2 e
3 X
R FROM CV-3313 CV-3314 DW-95 DW-6 DW-5 DW-93 CV-3312 CV-3311 TO M
i J
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e O
e e
e
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 65 of 117 O
FIGURE l
8.26 Diesel Generator Auxillaries 2
3 8!
85 i
3 2
T s.
r
,X
,V 7
a 3
s a
8" w!+! l+!
i l
%.,- se
,,- se l
1 f+ ! i+ 1 x
4 b,--e Y
%,ee I
i x
..g 3
2 + ! ", + !
2
-x Y
M,,-,se
%,,-,se
! (d~
g g
IX IX
!al 1
eh b l
c
,=
c n,
~z O
w g
6
+
+
25i I"5-
"xx Y l
ewse e-vse "I
E w
h
$g g$
, -VSe y
g 9-VSe Qf O$f
~
Q$
h+ 2
-K4 T l +T-ac+--
t-VSe 4-VSe F'
i w
i 7
h%
l@
EWi-09 04.0126 mx uw 1127 DWG j
I/kmk
3P
-4 %
3 AO-18258 5 h OG-22-2 I
kJ A
)
TO m D
~~
l OFFGAS m
[
FROM
^~
^
CONDENSER l
o OG-22-1 2
I kJ t
r, v
g g P-3 t/) r s=
m g 4
a =
5 0 g
m
-4 m 2.
-4 0 9
2 $
2T C i 3 5 m
o 5 a
a
'o "U
3i 3>
?>
E To Cf)
XR-25-1 XR-27-1 FROM )
I
)
TO 11 CRD L
( RECIRC. PUMP SEAL
- T
? 8:
E "o 8
O XR-25-2 XR-27-2
[
o gg 4
hy FROM I I
)
TO 12 CRD l
( RECIRC. PUMP SEAL g
o e
9 9
e
MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 67 of 117 FIGURE 8.28 Level Inst Backfill / Hard Pipe Vent 4
I l
V BF-12 BF-14 J L BF-24 BF-26 BF-35 BF-37 BF-46 BF-48 CRD NST I f I f A k A L O
'J
'J AO-4539 AO-4540 PSD-4543 FROM
(
L2 g2 i
( VENT CONTAINMENT >
FT 77 i
i I f I f I f A k A k A k I f V
4 k 4 L O
'J
'J
.01 28 1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 68 of 117 FIGURE 8.29 Safety Grade N2 sv RV-2-71 A fiV-2-718
)
RV-2-71C RV-2-71 E SV-4234 Al-700 Ab599 R ]2] 1 SV-4235 Ab708 Al-598 29 $
X N
N X
, Q IU*7ja "
U go_
Ab730 Al-12-1 Al-12-0 AO-2-80B Al-12-2 Al-12-10 AO-2-80C 1 f 1 f 1 f Al-12-3 Al-12-11 AO-2-800 j g j g j g AL12-4 Al-12-12 1 P T-49A,B,C,D LJ LJ J L M
N LJ Al-714 Al-713 Ab705 Al-706 O
EWi-09 04.0129 1130 DWG 1/kmk
4 MONTICELLO NUCLEAR GENERATING PLANT EWi 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 69 of 117 9.0 ATTACHMENTS ATTACHMENT 9.1 Pumo Testing Table Parameter to be Measured Pump Pump Pump ASME Delta 2 Relief P&lD No.
Number Name Class Speed 1 Press Vibration Flow ReqNo.
M-120 P-202B RHR 2
NA X
X X
4.1.2 i
M-120 P-202D RHR 2
NA X
X X
4.1.2 M-121 P-202A RHR 2
NA X
X X
4.1.2 M-121 P-202C RHR 2
NA X
X X
4.1.2 M-122 P-208A Core Spray 2
NA X
X X
M-122 P-2088 Core Spray 2
NA X
X X
M-124 P-209 HPCI 2
X X
X X
4.1.3,4.1.5
(
M-126 P-207 RCIC 2
X X
X X
4.1.5 M 127 P-203A SLC 2
NA X
X X
4.1.1 M-127 P-203B SLC 2
NA X
X X
4.1.1 M-133 P-11 DOTP NONE NA X
X X
M-811 P-109A RHRSW 3
NA X
X X
4.1.2,4.1.4 M-811 P-109B RHRSW 3
NA X
X X
4.1.2,4.1.4 M-811 P-109C RHRSW 3
NA X
X X
4.1.2,4.1.4 M-811 P-109D RHRSW 3
NA X
X X
4.1.2,4.1.4 M-811 P-111 A ESW 3
NA X
X X
4.1.4 M-811 P 111B ESW 3
NA X
X X
4.1.4 M-811 P-111C ESW 3
NA X
X X
4.1.4 M-811 P-111 D ESW 3
NA X
X X
4.1.4 NH-94896 CGCP-1 A CGC 3
NA X
X X
NH-94897 CGCP-1 B CGC 3
NA X
X X
NOTE 1:
Not applicable to constant speed pumps.
O NOTE 2:
Discharge pressure is used for positive displacement pumps P-203A, P-203B and P 11.
l/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 70 of 117 ATTACHMENT 9.2 Valve Table Symbols l
SYMBOLS USED TO DESIGNATE VALVE TYPE Symbol Meaning CK Check Valve i
BF Butterfly Valve i
GT Gate Valve GL Globe Valve RV Pressure Relief Valve RD Rupture Disk AN Angle Valve PL Plug Valve SC Stop Check XP Explosive Shear Valve l
DI Diaphragm l
AR Air Relief BA Ball Valve FV Excess Flow Check Valve SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE Syne '
Meaning MO Motor AO Air SO Solenoid MA Manual SA Self Actuating SYMBOLS USED TO DESIGNATE VALVE POSITION Symbols Meaning O
Open j
C Closed NOTE:
Monticello Nuclear Plant may revise, without notice, the identified positions listed in " Normal Position" and " Safety Position" based on changes in valves function / system configuration.
1/kmk l
MONTICELLO NUCLEAR GENERATING PLANT EW1-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 n
Page 71 of 117 Q
ATTACHMENT 9.2 Valve Table Symbols (cont'd)
SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT Symbol Meaning CE Control valve exercise per IWV-3412, performed quarterly.
DI Disassemble and inspect the valve each refueling outage as allowed by OM-10 j
and 10CFR50.55a(f)(4)(iv), unless otherwise noted.
i EX Explosive valve tett per IWV-3610.
FC Stroke Test per IWV-3400/3520, on a cold shutdown frequency (with stroke time i
measurement, as appropriate).
FE Full stroke test on a quarterly frequency (with stroke time measurement as appropriate) per IWV-3400, or full stroke test of check valves per IWV-3520.
FR Stroke test per IWV-3400, on a refueling frequency (with stroke time measurement, as appropriate), as allowed by OM-10 and 10CFR50.55a(f)(4)(iv),
or a relief raquest.
FS Fail safe test per IWV-3415.
LJ Leak test per 10CFR50, App J, performed during refueling outages.
LK Leak test per IWV-3420, performed during refueling outages.
PC Partial stroke exercise test on a cold shutdown frequency as allowed by OM-10 and 10CFR50.55a(f)(4)(iv).
Pl Position indicator test per IWV-3300, performed during refueling outages.
RD Rupture disk test per IWV-3620.
RR See relief request for testing details.
SP Periodic relief valve test per IWV-3510.
SYMBOLS USED TO DESIGNATE SECTION XI VALVE CATEGORY Symbol Meaning i
A Valves with specified maximum seat leakage rate.
B Valves with no specified maximum seat leakage rate.
C Self-actuating (check, relief valves).
C D
Actuated by energy source capable of only one operation (rupture disks, explosive valves).
1/kmk
=
]
A I
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.09 i
TITLE:
INSERVICE TESTING PROGRAM Revision 3 j
Page 72 of 117 ATTACHMENT 9.2 Valve Table Symbols (cont'd) 1 i
j SYMBOLS USED TO DESIGNATE ACTIVE AND PASSIVE VALVES i
i Symbol Meaning 1
Active - valves which are required to change position to accomplish a specific i
function.
2 Passive - valves which are not required to change position to accomplish a j
specific function.
}
I 1
A l
i 9
l i
1/kmk I
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 73 of 117 ATTACHMENT 9.3 Valve Testing Table SYSTEM: Steam Jet Air Ejectors P&lD NO.: M 104-2 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd l RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-1825A None B-3 B1 6
BF AO C
C FE 5.1 FC AO-1825B None B-3 B-1 6
BF AO C
C FE 5.1 FC O
O 1/kmk
J MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 74 of 117 O
ATTACHMENT 9.3 yalve Testing Table (cont'd)
SYSTEM: Condensate & Domineralized Water Storage System P&lD NO.: M-108 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd DM-151 2
E-1 A-2 1
GT MA C
C LJ LJ DM-152 2
E-1 A-2 1
GT MA C
C LJ LJ O
O 1/kmk
4 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 75 of 117 L
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Reactor Building Cooling Water System P&lD NO.: M-111 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd MO-1426 2
E-4 A-1 8
GT MO O
C FE,LJ, 5.2 FC,LJ, Pl Pl MO-4229 2
E-4 A-1 8
GT MO O
C FE,LJ, 5.2 FC,LJ, Pl Pl MO-4230 2
E-3 A-1 8
GT MO O
C FE,LJ, 5.2 FC,LJ, Pi PI RBCC-15 2
E-3 A,C-1 8
CK SA O
C FE,LJ 4.2.1 FR LJ l
l l
D i
l O
1/kmk l
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 76 of 117 a
g 1
ATTACHMENT 9.3 yalve Testing Table (cont'd)
SYSTEM: RHR Service Water P&lD NO.: M-112 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests i
Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd f
RV-3202 3
C-5 C-1 2.5 RV SA C
C-4 C1 2.5 RV SA C
A-5 B-1 12 GL AO C
CV-1729 3
A-4 B-1 12 GL AO C
1/kmk
i MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3
(^;
Page 77 of 117 v
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Emergency Service Water Systems P&lD NO.: M-112 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd SW-101 None E-1 C-1 3
CK SA O
E-1 C-1 3
CK SA O
C FE 4.2.2 RR SW 103 None E-3 C-1 3
CK SA O
E-3 C-1 3
CK SA O
O 1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 78 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Service Condensate System P&lD NO.: M-114-1 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd CST-88 2
B-5 C-1 2
CK SA O
B-5 C-1 2
CK SA O
C FE DI CST-92 2
B-5 C-1 2
CK SA O
B-5 C1 2
CK SA O
B-6 C-1 2
CK SA O
B-6 C-1 2
CK SA O
B-6 C-1 1
CK SA O
C FE DI O
\\
l/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 tO Page 79 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Nuclear Boller System Steam Supply P&lD NO.: M-115 ASME P&lD Sect XI Size Vlv Act Norm Safety Req'd RelReg Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd FW-91 1 2
A-3 C-1 14 CK SA O
C FE 5.3 FC FW-91 -2 2
A-5 C-1 14 CK SA O
C FE 5.3 FC FW-94-1 1
A-3 A,C 1 14 CK SA O
FC(C),
LJ FW 94-2 1
A-4 A,C-1 14 CK SA O
FC(C),
LJ FW-97-1 1
A-3 A,C-1 14 CK SA O
FC(C),
LJ FW-97-2 1
A-4 A,C-1 14 CK SA O
FC(C),
LJ
%/
XFV-1 2
E-2 A,C 1 1
C FE,LK 5.13 FR,LK XFV-2 1
D-2 A,C-1 1
C FE,LK 5.13 FR,LK XFV-3 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-4 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-5 1
D-2 A,C 1 1
C FE,LK 5.13 FR,LK XFV-6 1
B-2 A,C-1 1
C FE,LK 5.13 FR,LK XFV-7 1
C-2 A,C-1 1
C FE,LK 5.13 FR,LK XFV-8 1
B-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV 9 1
C-5 A,C-1 1
C FE,LK 5.13 FR.LK b
4 G
1/kmk
_MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 80 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Nuclear Boller System Steam Supply P&lD NO.: M-115 j
ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests
. Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-2-80A 1
C-5 A-1 18 GL AO O
C FE,LJ, 5.4 FE,LJ, Pl,FS Pl,FS AO-2-808 1
E-5 A-1 18 GL AO O
C FE,LJ, 5.4 FE,LJ, Pl,FS PI,FS AO-2-800 1
E-2 A-1 18 GL AO O
C FE,LJ, 5.4 FE,LJ, Pl,FS Pl,FS AO-2-80D 1
C-2 A-1 18 GL AO O
Pl,FS Pi,FS AO-2-86A 1
C-5 A-1 18 GT AO O
C FE LJ, FE,LJ, Pl Pl AO-2-868 1
E-5 A-1 18 GT AO O
C FE,LJ, FE,LJ, Pl Pl AO-2-86C 1
E-2 A-1 18 GT AO O
C FE,LJ, FE,LJ, Pi PI AO-2-86D 1
C-2 A-1 18 GT AO O
C FE,LJ, FE,LJ, Pl Pl MO-2373 1
B-5 A-1 3
GT MO C
C FE,LJ, FE,LJ, Pi Pl MO-2374 1
B-6 A-1 3
GT MO C
RV-2-71 A 1
B-4 B,C-1 6
RV SNAO C
O SP,FE 4.2.4 SP,FR, RR RV-2-71 B 1
D-4 B,C-1 6
RV SNAO C
RV-2-71C 1
D-3 B,C-1 6
RV SNAO C
RV-2 71D 1
B-3 B,C-1 6
RV SA/AO C
RR RV-2-71 E 1
B-4 B,C-1 6
RV SA/AO C
RV-2 71F 1
B-3 B,C-1 6
RV SNAO C
O SP,FE 4.2.4 SP,FR, RR RV-2-71 G 1
D-4 B,C-1 6
RV SNAO C
O SP,FE 4.2.4 SP,FR, RR RV-2-71 H 1
D-3 B,C 1 6
RV SNAO C
RR 1/kmk i
MONTICELLO NUCLEAR GENERATING PLANT EWi 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 O
Page 81 of 117 l
i ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Reactor Pressure Relief P&lD NO.: M-115-1 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd RV-3242A None A-5 C1 8
RV SA C
RV-3243A None C-6 C-1 8
RV SA C
O SP SP RV 3244A None C-4 C-1 8
RV SA C
O SP SP RV-3245A None A-4 C-1 8
RV SA C
O SP SP RV-7440A None A-6 C-1 8
RV SA C
O SP SP RV-7441A None A-4 C-1 8
RV SA C
O SP SP RV-7467A None C-5 C-1 8
RV SA C
O SP SP RV-7468A None C-4 C-1 8
RV SA C
C-7 A,C-1 1
C FE,LK 5.13 FR.LK XFV-11 2
C-7 A,C-1 1
C FE,LK 5.13 FR,LK
/G XFV-12 2
A7 A,C-1 1
C FE,LK 5.13 FR,LK XFV-13 2
A-7 A,C 1 1
C FE,LK 5.13 FR,LK XFV-14 2
C-3 A,C 1 1
C FE.LK 5.13 FR,LK XFV-15 2
C-3 A.C-1 1
C FE,LK 5.13 FR,LK l
XFV-16 2
A-3 A,C 1 1
C FE,LK 5.13 FR,LK j
XFV-17 2
A-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-18 2
A-3 A,C-1 1
C FE,LK 5.13 FR LK XFV-19 2
C-3 A,C-1 1
C FE,LK 5.13 FR,LK l
XFV-20 2
A-7 A,C-1 1
C FE,LK 5.13 FR,LK XFV-21 2
C-7 A,C-1 1
C FE,LK 5.13 FR,LK l
l 1
J l
I/kmk l
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 82 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Vesselinstrumentation Nuclear Boller System P&lD NO,: M-116 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd Rel Req Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd BF-12 2
B-3 A,C-1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF 14 2
B-3 A,C 1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF-24 2
B-3 A,C-1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF-26 2
B-3 A,C-1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF-35 2
A-3 A,C-1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF-37 2
A-3 A,C-1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF-46 2
A-3 A,C-1 0.37 CK SA O
C FE,LK 5.12 FR,LK BF-48 2
A-3 A,C-1 0.37 CK SA O
C FE.LK 5.12 FR,LK XFV-22 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-23 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK
~
XFV-24 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-25 1
D-6 A,C-1 1
C FE,LK 5.13 FR,LK XFV-26 1
D-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-27 1
C-5 A,C 1 1
C FE,LK 5.13 FR,LK XFV-28 1
C-5 A,C-1 1
C FE.LK 5.13 FR,LK XFV-29 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-30 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-31 1
C-5 A,C 1 1
C FE LK 5.13 FR,LK XFV-32 1
C-5 A,C 1 1
C FE,LK 5.13 FR,LK XFV-33 1
C-5 A.C-1 1
C FE,LK 5.13 FR,LK XFV-34 1
C-5 A,C-1 1
C FE,L K 5.13 FR,LK XFV-35 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-36 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-37 1
C-5 A.C-1 1
C FE,LK 5.13 FR,LK XFV-38 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-39 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV40 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-41 1
C-3 A,0-1 1
C FE,LK 5.13 FR,LK l
I/kmk i
1
MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 83 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Vessel Instrumentation Nuclear Boller System P&lD No.: M 116 (cont'd)
ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd XFV-42 1
C-3 A,C-1 1
.O C
FE,LK 5.13 FR,LK XFV-43 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-44 1
C-3 A,C 1 1
C FE,LK 5.13 FR,LK XFV-45 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-46 1
C-3 A,C 1 1
C FE,LK 5.13 FR,LK XFV-47 1
C-3 A,C 1 1
C FE,LK 5.13 FR,LK XFV-48 1
C-3 A,C 1 1
C FE,LK 5.13 FR,LK XFV-49 1
C-3 A,C-1 1
C FE LK 5.13 FR,LK XFV-50 1
C3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-51 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK O
XFV-52 1
D-5 A,C 1 1
C FE,LK 5.13 FR,LK XFV-53 1
D-3 A,C 1 1
C FE,LK 5.13 FR,LK XFV-54 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-55 1
D-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-56 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-57 1
D-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-88 1
D5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-89 1
D-3 A,C 1 1
C FE,LK 5.13 FR,LK I/kmk
9 MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 84 of 117 ATTACHMENT 9.3 Valve Te.ating Table (cont'd)
SYSTEM: Recirc Loops Nuclear Boller System P&lD NO.: M-117-1 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Poa Tests or DTJ Pfrmd CV-2790 2
D-5 A-1 0.75 GT AO O
C FE,LJ, FE,LJ, Pl Pl CV-2791 2
D-6 A-1 0.75 GL AO O
C FE,LJ, FE,LJ, Pl Pl MO-2-53A 1
B-2 B-1 28 GT MO O
B-6 B-1 28 GT MO O
B2 A,C-1 1
C FE,LK 5.13 FR,LK XFV-59 1
B-2 AC1 1
C FE,LK 5.13 FR,LK XFV-60 1
A-3 A,C 1 1
C FE,LK 5.13 FR,LK XFV-61 1
B-6 A,C-1 1
C FE,LK 5.13 FR,LK XFV-62 1
B-6 A,C-1 1
C FE,LK 5.13 FR,LK XFV-63 1
A-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-64 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-65 1
D-5 A C-1 1
C FE,LK 5.13 FR,LK XFV-66 1
E-2 A,C-1 1
C FE,LK 5.13 FR,LK XFV-67 1
C-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-68 1
C-5 A,C-1 1
C FE,LK 5.13 ' FR,LK XFV-69 1
E-6 A,C-1 1
C FE,LK 5.13 FR,LK XFV-70 1
E-6 A,C-1 1
C FE,LK 5.13 FR,LK XFV-71 1
E-2 A,C 1 1
C FE,LK 5.13 FR,LK XFV-72 1
E-6 A,C 1 1
C FE,LK 5.13 FR,LK XFV-73 1
E-6 A,C-1 1
C FE,LK 5.13 FR,LK XFV-74 1
E-2 A,C 1 1
C FE,LK 5.13 FR.LK XFV-75 1
E-2 A,C 1 1
C FE,LK 5.13 FR,LK XFV-76 1
D-2 A,C-1 1
C FE,LK 5.13 FR,LE XFV-77 1
D-2 A,C-1 1
C FE,LK 5.13 FR,LK O
1/kmk
'M MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Q
Page 85 of 117 V
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Recirc Loops Pumps and Motors Nuclear Boller System P&lD NO.: M 117-2 ASME P&lD Sect XI l Size Viv Act Norm Safety Req'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd XR-271 2
D-3 A,C-1 1
CK SA O
C FE,LJ 4.2.5 FR,LJ XR-27-2 2
D-5 A,C-1 1
CK SA O
C FE.LJ 4.2.5 FR,LJ XFV-78 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-79 1
C-3 A,C-1 1
C FE,LK 5.13 FR,LK i
XFV-80 1
C-4 A,C-1 1
C FE,LK 5.13 FR,LK XFV-81 1
C-4 A,C-1 1
C FE LK 5.13 FR,LK O
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 86 of 117 ATTACHMENI 9.3 Valve Testing Table (cont'd)
SYSTEM: Control Rod Hydraulic System (Recirc)
P&lD NO.: M-118 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd XR-25-1 2
A-4 A,C-1 1
CK SA O
C FE,LJ 4.2.5 FR,LJ XR-25-2 2
A-4 A,C-1 1
CK SA O
C FE,LJ 4.2.5 FR,LJ 9
O I/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 87 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Control Rod Hydraulic System P&lD NO.: M-119 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests j
Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd CRD-114*
2 B-6 C-1 0.75 CK SA O/C O
FE 4.2.6 FR CRD-115*
2 B-4 C-1 0.50 CK SA O/C C
FE 4.2.7 FR CRD-138*
2 E-4 C-1 0.50 CK SA O/C C
FE FE CV-126*
2 C-5 B-1 1
GL AO C
O FE 4.2.6 FR CV-127*
2 C-6 B-1 0.75 GL AO C
O FE 4.2.6 FR CV-3-32A 2
E-3 B-1 1'
GL AO O
E-1 B-1 1
GL AO O
E-4 B-1 1
GL AO O
E-1 B-1 1
GL AO O
D-3 B-1 2
GL AO G
D-2 B-1 2
GL AO O
D-3 B-1 2
GL AO O
D-2 B-1 2
GL AO O
- Typical of 121 control rod drive units O
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 88 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Residual Heat Removal System P&lD NO.: M 120 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al 243-2 None A5 A,C-1 0.75 CK SA O
C FE,LK 5.16 FR,LK Al-244-2 None A-5 A,C-1 0.75 CK SA O
C FE,LK 5.16 FR,LK Al-610-2 None B-4 A.C-1 0.75 CK SA O
C FE,LK 5.16 FR,LK Al-610-4 None C-4 A C-1 0.75 CK SA O
C CE,LK 5.16 FR,LK AO-10-468 1
D-2 A,C-1 16 CK SA C
O/C FE,PI, 5.6 FC,PI, LK LK CV-1995 2
B-4 B-1 2
GL AO C
C-4 B-1 2
GL AO C
C-3 8-1 20 GT MO O
A-2 B-1 18 GT MO C
C-5 B-1 14 GL MO O
D-6 B1 12 GT MO C
D-6 B-1 10 GL MO C
D-5 A-1 4
GL MO C
O/C FE,LJ, F E,LJ, Pl Pl MO-2013 2
D-3 A1 16 GL MO O
O/C FE,LJ, FE,LJ, Pl Pl MO-2015 1
D-3 A-1 16 GT MO C
O/C FE,LJ, FE,LJ, Pl,LK Pl,LK MO-2021 2
E-3 A1 10 GT MO C
O/C FE,LJ, FE,LJ, Pl Pl MO-2023 2
E-2 A-1 10 GT MO C
O/C FE,LJ, FE,LJ, Pl Pl MO-4085B 1
D1 B-1 4
GT MO C
A-5 C1 10 CK SA C
B-5 C1 10 CK SA C
O/C FE FE RHR-6-2 1
D-2 B-2 16 GT MA O
O Pi PI RHR-8-2 2
C-3 C-1 3
CK SA C
B-3 C-1 1
RV SA C
C-3 C-1 1
RV SA C
E-6 C-1 1
RV SA C
1 MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 I
Page 89 of 117 ATTACHMENT 9.3 yJive Testing Table (cont'd)
SYSTEM: Residual Heat Removal System P&lD NO.: M-120 (cont'd)
ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd RV-4282 2
B-6 C1 2.50 RV SA
.C O
SP SP RV-4908B None A-5 C-1 0.25 RV SA C
1/kmk
1 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 9l Page 90 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Residual Heat Removal System P&lD NO.: M 121 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al-243-1 None A-3 A,C-1 0.75 CK SA O
C FE,LK 5.16 FR,LK Al-244-1 None A-3 A,C-1 0.75 CK SA O
C FE.LK 5.16 FR,LK Al-610-1 None A-4 A,C-1 0.75 CK SA O
C FE,LK 5.16 FR,LK Al-610 3 None C-6 A,C-1 0.75 CK SA O
C FE LK 5.16 FR,LK AO-10-46A 1
D-5 A,C-1 16 CK SA C
O/C FE,PI, 5.6 FC,PI, LK LK CV-1994 2
B-4 B-1 2
GL,AO C
C-5 B-1 2
GL AO C
B-6 B-1 20 GT MO O
B-6 B-1 18 GT MO C
B-3 B-1 14 GL MO O
D3 B-1 12 GT MO C
C-3 B-1 10 GL MO C
C-3 A-1 4
GL MO C
O/C FE,LJ, FE,LJ, Pl Pl MO-2012 2
D-5 A-1 16 GL MO O
O/C FE LJ, FE,LJ, Pl Pl MO-2014 1
D-5 A-1 16 GT MO C
O/C FE,LJ, FE,LJ, Pl,LK Pl,LK MO-2020 2
E5 A-1 10 GT MO C
O/C FE,LJ, FE LJ, Pl Pl MO-2022 2
E5 A-1 10 GT MO C
O/C FE,LJ, FE,LJ, Pi PI MO-2026 1
E-6 A-1 4
GT MO C
C FE,LJ, 5.7 FC,LJ, PI,LK Pl,LK MO-2027 1
E-6 A-1 4
GT MO C
C FE,LJ, 5.7 FC,LJ, PI,LK Pl,LK MO-2029 1
D-6 A-1 18 GT MO C
C FE LJ, 5.7 FC,LJ, Pl,LK Pl,LK MO-2030 1
C-6 A-1 18 GT MO C
C FE,LJ, 5.7 FC,LJ, Pl,LK Pl,LK MO-2032 2
C-4 B-1 4
GT MO C
C FE,PI FE,PI MO-2407 None C-4 B-1 4
GT MO O
I/kmk I
1 MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 91 of 117
)
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Residual Heat Removal System P&lD NO.: M-121 (cont'd)
ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests l
Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd MO-4085A 1
C-6 B-1 4
GT MO C
A-4 C-1 10 CK SA C
O/C FE FE RHR-2-3 2
B-4 C-1 10 CK SA C
O/C FE FE l
RHR-6-1 1
D-6 B-2 16 GT MA O
O Pl PI I
RHR-8-1 2
C5 C-1 3
CK SA O
RV-1990 2
B-5 C-1 1
RV SA C
C-5 C-1 1
RV SA C
l RV-2004 2
D2 C1 1
RV SA C
RV-2025 2
E-4 C-1 1
RV SA C
B-6 C-1 1
RV SA C
RV-4281 2
B-2 C-1 2.50 RV SA C
\\
RV-4908A None A-4 C-1 0.25 RV SA C
l 1
i, 1/kmk l
MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 92 of 117 O
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Core Spray System P&lD No.: M-122 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReg Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-1413A 1
E-3 A,C-1 8
CK SA C
O FE,Pl, 5.6 FC,PI, LK LK AO-14138 1
E-4 A,C-1 8
CK SA C
O FE,PI, 5.6 FC,PI, LK LK CS-9-1 2
C-2 C1 10 CK SA C
O FE FE CS-9-2 2
C-5 C-1 10 CK SA C
O FE FE CS-13-1 1
E-3 B-2 8
GT MA O
O Pl Pl CS 13-2 1
E-4 B-2 8
GT MA O
O Pl Pl CST-103-1 None E-2 C-1 2
CK SA O
E-2 C-1 2
CK SA O
A-3 B-1 12 GT MO O
A4 B-1 12 GT MO O
D-2 B1 6
GL MO C
D-5 B-1 6
GL MO C
E-3 A-1 8
GT MO O
O/C FE,LJ, FE,LJ, Pl Pl MO-1752 2
E-5 A1 8
GT MO O
O/C FE,LJ, FE,LJ, Pl Pl MO-1753 1
E-3 A1 8
GT MO C
O/C FE,LJ, FE,LJ, Pl,LK Pl,LK MO-1754 1
E-5 A-1 8
GT MO C
O/C FE,LJ, FE,LJ, Pl,LK Pl,LK RV-1745 2
E-2 C-1 2
RV SA C
E-6 C-1 2
RV SA C
C-3 A,C-1 1
C FE,LK 5.13 FR,LK XFV-83 1
D-4 A,C-1 1
C FE,LK 5.13 FR,LK O
4 I/kmk 4
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 93 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: High Precsure Coolant injection System (Steam Side)
P&lD NO.: M-123 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd CV-2046A 2
C1 B-1 1
GL AO O
C FE,PI FE,PI CV-2394A None A-3 B-1 1
GL AO O/C C
C-5 A,C-1 16 CK SA C
FC(C),
LJ HPCI10 2
C-5 A,C-1 16 CK SA C
FC(C),
LJ HPCI14 2
B4 C-1 2
CK SA C
C FE 5.8 FC HPCI-15 2
B-5 C-1 2
CK SA C
C FE 5.8 FC HPCI-18 2
A-2 C-1 2
CK SA C
O FE FE HPCI-20 2
A-3 C-1 2
CK SA C
O FE FE HPCI-65 2
B-6 C-1 2
CK SA C
C FE 5.8 FC J
HPCI-71 2
B-6 C-1 2
CK SA C
C FE 5.8 FC MO-2034 1
D-5 A-1 8
GT MO O
O/C FE,LJ, FE LJ, Pl Pl MO-2035 1
D4 A1 8
GT MO O
O/C FE,LJ, FE,LJ, Pl Pl MO-2036 2
D-2 B-1 8
GT MO C
C-5 D-1 16 RD SA C
O RD RD PSD-2039 None C-5 D-1 16 RD SA C
O RD RD RV-2056 3
B3 C1 1.50 RV SA C
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-85 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK 1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 94 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: High Pressure Coolant injection System (Water Side)
P&lD NO.: M 124 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al-611 None C-4 A,C-1 0.75 CK SA O
C FE,LK 5.16 FR,LK AO-23-18 2
B-5 C-1 12 CK SA C
B-4 B-1 2
GL AO C
A-4 C-1 14 CK SA C
O/C FE 5.8 Di(0),
FC(C),
PC(O)
HPCI-32 2
E-4 C-1 14 CK SA C
O FE FE HPCI-42 2
A-4 C1 4
CK SA C
O FE DI MO-2061 2
A-5 B1 14 GT MO C
A-4 B-1 14 GT MO C
D-3 B1 14 GT MO O
B-5 B-1 12 GT MO C
B-5 B1 12 GT MO C
C-5 B-1 8
GL MO C
D-3 C-1 1
RV SA C
I/kmk
\\
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 95 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: RCIC (Steam Side)
P&lD NO.: M 125 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd CV-2082A 2
C-1 B-1 1
GL AO
.O C
FE,PI FE,PI CV-2848 None A-4 B-1 1
GL AO O/C C
D-5 A-1 3
GT MO O
O/C FE,LJ, FE,LJ, Pi PI MO-2076 1
D-4 A-1 3
GT MO O
O/C FE,LJ, FE,LJ, Pl Pl MO-2078 2
D-2 B-1 3
GL MO C
A-3 B-1 2
GL MO C
B-6 A,C-1 8
CK SA C
FC(C),
LJ RCIC-10 2
B-6 A,C-1 8
CK SA C
/'~
t FC(C),
LJ RCIC-14 2
A-4 C-1 2
CK SA C
O FE FE RCIC-16 2
A-5 C-1 2
CK SA C
C FE 5.9 FC RCIC-17 2
B-5 C1 2
CK SA C
C FE 5.9 FC RCIC-57 2
B-6 C1 1.50 CK SA C
C FE 5.9 FC RCIC-59 2
B-6 C-1 1.50 CK SA C
C FE 5.9 FC RV-2097 3
B-3 C1 1
RV CA C
C-5 D-1 8
RD SA C
O RD RD PSD-2090 None C-5 D-1 8
RD SA C
O RD RD XFV-86 1
D-5 A,C-1 1
C FE,LK 5.13 FR,LK XFV-87 1
D-5 A,C 1 1
C FE,LK 5.13 FR,LK O
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 96 of 117 A'lTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: RCIC (Water Side)
P&lD NO.: M-126 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al-612 None C-5 A,C 1 0.75 CK SA O
C FE,LK 5.16 FR,LK AO-13 22 2
B-5 C-1 4
CK SA C
A-3 B-1 2
GL AO C
A-5 B-1 6
GT MO C
D-4 B1 6
GT MO C
D-4 B-1 6
GT MO O
B-5 B-1 4
GT MO C
B-5 B-1 4
GT MO C
D-5 B1 4
GT MO C
A-4 C-1 6
CK SA C
O/C FE 5.9 Di(O),
FC(C),
PC(O)
RCIC-37 2
A-4 C-1 2
CK SA C
O FE Di RCIC-41 2
D-4 C-1 6
CK SA C
O FE FE RV-2103 2
D-3 C-1 1
RV SA C
I/kmk
MONTICEl.LO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 g-Page 97 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Standby Liquid Control System P&lD NO.: M 127 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd XP-11-14A 2
D-5 D-1 1.50 XP SA C
O EX EX l
XP-11-14B 2
E-5 D-1 1.50 XP SA C
O EX EX RV-11-39A 2
C-4 C1 1.50 RV SA C
B-4 C-1 1.50 RV SA C
C-4 C-1 1.50 CK SA C
O FE FE XP-3-2 2
B-4 C1 1.50 CK SA C
O FE FE XP-6 1
D-6 A,C 1 1.50 CK SA C
O/C FE,LJ 4.2.10 FR,LJ
, XP-7 1
C-6 A,C-1 1.50 CK SA C
O/C FE,LJ 4.2.10 FR,LJ O
i 1
I/kmk
c l
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 i
TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 98 of 117 9
l ATTACHMENT 9.3 Valve Testing Tabla (cont'd)
SYSTEM: Reactor Water Cleanup System P&lD NO.: M-128 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd MO-2397 1
D-8 A1 4
GT MO O
C FE,LJ, FE,LJ, Pl Pl MO-2398 1
D-7 A-1 4
GT MO O
C FE,LJ, FE LJ, Pl PI RC-6-1 2
D-6 A,C-1 1.5 CK SA O
C FE,LK 4.2.11 FR,LK RC-6-2 2
D-7 A.C-1 1.5 CK SA O
C FE,LK 4.2.11 FR,LK O
l O
r I/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 99 of 117 ATTACHMENI 9.3 Valve Testing Table (cont'd)
SYSTEM: Primary Containment Nitrogen Control System P&lD NO.: M-130 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd CV-3267 2
C-4 A-1 1
GL AO O
C FE,LJ, FE,LJ, Pl Pl CV-3268 2
C-4 A-1 1
GL AO O
C FE,LJ, FE,LJ, Pl Pl CV-3269 2
D-4 A-1 1
GL AO O
C FE LJ, FE,LJ, Pl Pl CV-3311 2
C-5 A-1 1
GL AO O
C FE,LJ, FE,LJ, Pl Pi CV-3312 2
C-5 A-1 1
GL AO O
C FE,LJ, FE,LJ, Pi Pl CV-3313 2
C-4 A-1 1
GL AO O
C FE,LJ, FE,LJ, Pl Pl CV-3314 2
C-5 A-1 1
GL AO O
C FE,LJ, FE,LJ, Pi Pl SV-3307 2
C-5 A-1 0.75 GL SO O
C FE LJ, FE LJ, Pl Pl SV-3308 2
C-5 A-1 0.75 GL SO O
I/kmk
]
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 100 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Containment Atmosphere Monitoring System P&lD NO.: NH-91197 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReg Tests Val /e No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd SV-4001 A 2
B-6 A1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl Pl SV-40018 2
B-6 A1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl Pl SV 4002A 2
A-5 A1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl PI SV-4002B 2
A-4 A1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl Pi SV 4003A 2
A-5 A-1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl Pl SV-4003B 2
A4 A-1 0.75 GL SO C
C FE,LJ, FE LJ, Pi Pl SV-4004A 2
A-4 A-1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl PI SV-4004B 2
A-4 A-1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl Pl SV-4005A 2
B-4 A-1 0.75 GL SO C
C FE,LJ, FE,LJ, PI Pi SV-4005B 2
B-4 A1 0.75 GL SO C
C FE,LJ, FE,LJ, Pi Pl SV-4020A 2
A-6 A-1 0.75 GL SO C
C FE,LJ, FE,LJ, Pl Pl SV 4020B 2
A-6 A-1 0.75 GL SO C
Pl Pi 4
1 I
l l
O I/kmk
}'
MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 l
TITLE:
INSERVICE TESTING PROGRAM Revision 3
- p.
Page 101 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd) i SYSTEM: Post Accident Sampling P&lD NO : NF-96042 t
ASME P&lD Sect Xi Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd PAS-58-1 2
B-7 C-1 0.75 CK SA
.C C
FE FE PAS-58-2 2
A7 C-1 0.75 CK SA C
C FE FE PAS-59-5 2
C FE 5.11 FC PAS-59-6 2
C FE 5.11 FC SV-4081 2
C-5 A-1 0.75 GL SO C
C FE,LJ, FE LJ, Pl Pl SV-4082 2
C-5 A1 0.75 GL SO C
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT CWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 102 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Service Air System P&lD NO.: M 131 SH4 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AS-78 2
D-8 A-2 1
GT MA C
C LJ LJ AS-79 2
D-7 A-2 1
GT MA C
C LJ LJ O
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 g
Page 103 of 117 V
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: MSIV/SRV Pneumatic Supply System P&lD NO.: M 131 SH10 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al-12-9 2
A-3 C-1 1
CK SA O
O FE FE Al-1210 2
A-3 C-1 1
CK SA O
O FE FE Al-1211 2
B-3 C-1 1
CK SA O
O FE FE Al-12-12 2
A-3 C-1 1
CK SA O
O FE FE Al-598 2
B-5 A,C 1 1
CK SA O
O/C FE,LJ 5.10 FC,LJ Al-599 2
C-5 A,C-1 1
CK SA O
Al-700 2
C-5 A,C-1 1
CK SA O
O/C FE,LJ FE,LJ Al705 None D-6 A,C-1 1
CK SA O
C FE,LK FE,LK Al-706 None D-6 A,C-1 1
CK SA O
B-5 A,C-1 1
CK SA O
O/C FE,LJ 5.10 FC,LJ p
Al-713 None B-6 A,C-1 1
CK SA O
C FE,LK 5.10 FC,LK kM Al-714 None B-6 A.C 1 1
CK SA O
C FE,LK 5.10 FC,LK Al-729 None C-7 A,C-1 0.75 CK SA C
O FE FE Al730-None B-7 A,C 1 0.75 CK SA C
O FE 5.10 FC SV-4234 None C-5 A-1 1
GL SO O
O FE,PI, FE,PI, LK LK SV 4235 None B-5 A1 1
GL SO O
I/kmk
l
-i MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 104 of 117 i
ATTACHMENT I
9.3 Valve Testing Table (cont'd)
SYSTEM: Instrument Air Reactor Building P&lD NO.: M 131 SH12 I
ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al 13-4 None D-3 A,C-1 0.75 CK SA C
C FE,LK 5.16 FR,LK Al 13-7 None A-3 A,C-1 0.75 CK SA C
C FE,LK 5.16 FR,LK Al-571 2
C-5 A,C 1 2
CK SA O
C FE,LJ 5.14 FC,LJ I
CV-1478 2
C-5 A1 2
GL AO O
1 i
I l
O 1/kmk
1 MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 l
TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 105 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Instrument Alr-Reactor Building P&lD NO.: M-131 SH14 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd Al-226-1 2
C-4 A,C 1 0.25 CK SA O
C FE,LJ 4.2.12 FR,LJ Al-613 None D-7 A,C 1 0.37 CK SA C
C FE,LK 5.15 FR,LK I
Al-614 None C-7 A,C 1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-615 None C-6 A,C-1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-616 None C-6 A,C-1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-617 None B-6 A,C-1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-618 None B-1 A,C 1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-619 None B-1 A.C-1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-625 2
C-4 A,C-1 0.37 CK SA O
C FE,LJ 4.2.12 FR,LJ Al-629 2
66 A,C-1 0.37 CK SA C
C FE,LJ FE,LJ Al-663 Ncne C-6 C-1 0.37 CK SA O
O FE 5.15 FR Al-666 None C-5 C1 0.37 CK SA O
O FE 5.15 FR Al-669 None C-6 C1 0.37 CK SA O
O FE 5.15 FR Al-672 None A-6 C1 0.37 CK SA O
O FE 5.15 FR l
Al-675 None B-1 C-1 0.37 CK SA O
O FE 5.15 FR l
Al-678 None B-1 C-1 0.37 CK SA O
O FE 5.15 FR Al-681 None 86 C-1 0.37 CK SA O
O FE 5.15 FR Al-683 None B5 A,C 1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-685 None C-4 A,C 1 0.37 CK SA C
C FE,LK 5.15 FR,LK Al-694 None B-5 C1 0.37 CK SA O
O FE FE l
Al-695 None C-4 C1 0.37 CK SA O
O FE FE l
CV-7956 2
B-6 A-1 0.75 GL AO C
Pl PI O
1/kmk l
o MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Pag. 106 of 117 ATfACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Diesel Oil P&lD NO.: M-133 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd FO-2 None C-3 C-1 1
CK SA O
C FE FE FO-5 None D-3 C-1 2
CK SA O/C O
FE FE FO-43 None B-2 C-1 1.5 CK SA O/C O
FE FE FO-44 None B-2 C-1 1.5 CK SA O
O FE FE GSA-32-1 None B-4 C1 0.75 CK SA O/C C
FE FE GSA-32-2 None B-3 C-1 0.75 CK SA O/C C
FE FE GSA-32-3 None E-2 C1 0.75 CK SA O/C C
FE FE GSA 32-4 None E-2 C-1 0.75 CK SA O/C C
FE FE RV 1523 None D-3 C-1 0.75 RV SA C
O SP SP RV-3216 None B-3 C-1 0.50 RV SA C
O SP SP RV 3217 None B-3 C1 0.50 RV SA C
O SP SP RV-3218 None A-3 C-1 0,50 RV SA C
O SP SP RV-3219 None B3 C1 0.50 RV SA C
O SP SP RV 3220 None B3 C-1 0.50 RV SA C
O SP SP RV-3221 None A3 C-1 0.50 RV SA C
O SP SP RV-3224 None E-2 C1 0.50 RV SA C
O SP SP RV-3225 None E-3 C-1 0.50 RV SA C
O SP SP RV 3226 None E3 C-1 0.50 RV SA C
O SP SP RV-3227 None E2 C-1 0.50 RV SA C
RV-3228 None E3 C1 0.50 RV SA C
O SP SP RV-3229 None E3 C1 0.50 RV SA C
1/kmk
9 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 107 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Fuel Pool Cooling & Cleanup System P&lD NO.: M-135 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd PC-20-1 None E-3 C-1 6
CK SA
.O C
FE DI PC-20-2 None E-3 C-1 6
CK SA O
C FE Di NOTE:
These valves are not required to be tested by 10CFR50.55a and are included in the IST Program as good practice. Since the Code requirements for IST are not mandatory, these valves will be tested by grou aing them together and performing a disassembly and nspection of one each refueling outage without including a relief request.
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=
.l MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 108 of 117 i
ATTACHMENT 9.3 Valve Testing Table (cont'd) i SYSTEM: Open (Dirty) Radwaste Sump System P&lD NO.: M-137 2
ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-2541A 2
E-2 A1 2
GT AO O
C FE,LJ, FE.LJ, Pl Pl AO-25418 2
E1 A-1 2
GT AO O
G 4
i O
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 i
Page 109 of 117 l
ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Closed (Clean) Radwaste Sump System P&lD NO.: M 138 i
ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd l
AO-2561A 2
E-2 A-1 2
GT AO O
Pl Pl AO-2561B 2
E1 A-1 2
GT AO O
Pl PI
!!O I
l J
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 110 of 117 ATTACHMENT 9.3 Valve Testina Table (cont'd)
SYSTEM: Primary Containment & Atmospheric Control System P&lD NO.: M 143 j
ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests
, Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-2377 2
C2 A-1 18 BF AO C
C FE,LJ, FE,LJ, Pl PI-AO-2378 2
B-3 A-1 18 BF AO C
C FE,LJ, FE,LJ, Pl Pl AO-2379 2
C-2 A-1 20 BF AO C
O/C FE,LJ, FE,LJ, Pl Pi AO-2380 2
B-2 A-1 20 BF AO C
O/C FE,LJ, FE,LJ, Pl Pi AO-2381 2
C-3 A-1 18 BF AO C
C FE,LJ, FE,LJ, Pl Pl AO-2382A None B-4 A,C-1 18 CK SA C
O/C FE,LK, FE,LK, Pi Pl AO-2382B None B-4 A,C 1 18 CK SA C
O/C FE,LK, FE LK, Pl Pl AO-2382C None B-4 A,C 1 18 CK SA C
O/C FE,LK, FE,LK, Pl Pl AO-2382E None B-4 A,C 1 18 CK SA C
O/C FE,LK, FE,LK, Pi PI AO-2382F None B-4 AC1 18 CK SA C
O/C FE,LK, FE,LK, Pl Pl AO-2382G None B-4 A,C 1 18 CK SA C
O/C FE,LK, FE,LK, Pl Pl AO-2382H None B-4 A,C-1 18 CK SA C
O/C FE,LK, FE,LK, Pl Pl AO-2382K None B-4 A,C-1 18 CK SA C
O/C FE LK, FE,LK, PI Pl AO-2383 2
B-6 A-1 18 BF AO C
AO-2386 2
D-6 A1 18 BF AO C
C FE,LJ, FE,LJ, Pl Pl AO-2387 2
D-6 A-1 18 BF AO C
C FE,LJ, FE,LJ, Pl Pi AO-2896 2
C-6 A1 18 BF AO C
C FE,LJ, FE,LJ, Pl Pl CV-2384 2
A-6 A1 2
GL AO C
MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 111 of 117 ATTACHMENT 9.3 Valve Testina Table (cont'd)
SYSTEM: Primary Containment & Atmospheric Control System P&lD NO.: M-143 (cont'd)
ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd CV-2385 2
C-6 A-1 2
GL AO C
Pl Pl D W V-8-1 2
B-2 A,C-1 20 CK SA C
D W V-8 2 2
C-2 A.C-1 20 CK SA C
)
OV i
l O
1/kmk
l MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 l
TITLE:
INSERVICE TESTING PROGRAM Revision 3 l
Page 112 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd) l SYSTEM: Service Water Systems and Makeup Intake Structure P&lD NO.: M-811 (RHRSW)
ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AV 3147 3
C-4 C1 3
B8 C-1 3
C FE FE 1
1 AV-3149 3
B-4 C-1 3
C FE FE AV-3150 3
B8 C1 3
C FE FE RHRSW-1 1 3
C-4 C-1 12 CK SA C
O/C FE FE l
RHRSW-1-2 3
C-8 C-1 12 CK SA C
C-4 C1 12 CK SA C
C-8 C1 12 CK SA C
O/C FE FE RHRSW-3-1 3
C-4 B1 18 GT MA C
O FE FE RHRSW-3-2 3
C7 B-1 18 GT MA C
C-4 B1 0.5 GL MA C
O FE FE I
RHRSW-21-2 3
C8 B1 0.5 GL MA C
O FE FE RHRSW-21 -3 3
C-4 B1 0.5 GL MA C
C-8 B-1 0.5 GL MA C
O FE FE I
RV-3038 3
C-4 C-1 1
RV SA C
C-7 C-1 1
RV SA C
C-3 C-1 1
CK SA O
C-7 C-1 1
CK SA O
C FE 4.2.13 RR SW 22-1 None C-3 C1 1
CK SA O
C FE 4.2.13 RR SW 22 2 None C7 C-1 1
CK SA O
l 9'
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 l
Page 113 of 117 ATTACHMENT 9.3 Valve Testina Table (cont'd)
SYSTEM: Service Water Systems and Makeup intake Structura P&lD NO.: M-811 (ESW)
ASME P&ID Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AV-3155 3
B-5 C-1 2
C FE FE AV-3156 3
B-6 C-1 2
C FE FE AV-4024 3
C-4 C-1 1
C FE FE AV-4026 3
C-6 C-1 1
C FE FE ESW-1 1 3
B-5 C-1 4
CK SA C
O FE FE ESW-12 3
B-6 C-1 4
CK SA C
O FE FE ESW-2-1 3
C-5 B-1 4
GT MA C
O FE FE ESW-2-2 3
C-5 B-1 4
GT MA C
O FE FE ESW-3-1 3
C-5 B-1 4
GT MA C
O FE FE ESW-3-2 3
C-6 B-1 4
GT MA C
C-7 B-1 4
GT MA O
CK SA O
D-6 C-1 4
CK SA O
C FE 4.2.14 RR ESW-15 None D-5 C1 4
CK SA O
D-4 C1 4
CK SA O
C FE 4.2.14 RR ESW-17 None C-6 C-1 4
CK SA C
C-4 C-1 4
CK SA C
O FE FE ESW-19 3
C-6 B-1 4
GT MA C
O FE FE ESW-20 3
C-4 B-1 4
GT MA C
O FE FE SW-15 None D-7 C-1 4
CK SA C
D-7 C-1 4
CK SA C
C FE 4.2.14 RR SW-17 None D-7 C-1 4
CK SA C
D-7 C1 4
CK SA C
,a._
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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 114 of 117 ATTACHMENT 9.3 V31ve Testing Table (cont'd)
SYSTEM: Combustible Gas Control System Div I(East)
P&lD NO.: NH-94896 I
ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-7422A 2
D-7 A-1 4
GL AO C
O/C FE,LJ, FE,LJ, Pl,FS Pl,FS AO-7423A 2
D-7 A-1 4
GL AO C
O/C FE LJ, FE,LJ, PI,FS Pl,FS AO-7424A 2
B-7 A-1 6
GL AO C
O/C FE,LJ, FE,LJ, Pl,FS Pl,FS AO-7425A 2
B-7 A-1 6
GL AO C
O/C FE,LJ, FE,LJ, PI,FS Pl,FS CGC-12-1 3
A-5 C-1 1.50 CK SA C
O/C FE FE MO-4043A 3
D-5 B-1 3
GL MO C
C-5 B-1 3
GL MO C
B-4 B-1 0.75 GL MO C
B-5 C-1 1
RV SA C
A-6 B-1 2
GL SO C
A-6 B-1 2
GL SO C
A5 B-1 0.75 GL SO C
1/kmk
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 115 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Combustible Gas Control System Div II (West)
P&lD NO.: NH-94897 ASME P&lD Sect Xi Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-7422B 2
D-7 A-1 4
GL AO C
O/C FE,LJ, FE,LJ, Pl,FS PI,FS AO-74238 2
D-7 A-1 4
GL AO C
O/C FE,LJ, FE,LJ, Pl,FS Pl,FS AO-7424B 2
B-7 A1 6
GL AO C
O/C FE LJ, FE.LJ, Pl,FS PI,FS AO-74258 2
B7 A-1 6
GL AO C
O/C FE,LJ, FE,LJ, Pl,FS Pl,FS CGC-12-2 3
A-5 C-1 1.50 CK SA C
O/C FE FE MO-4043B 3
D-5 B-1 3
GL MO C
C-5 B-1 3
GL MO C
B-4 B-1 0.75 GL MO C
RV-4032B 3
B-5 C-1 1
RV SA C
A-6 B-1 2
GL SO C
A-6 B-1 2
GL SO C
A-5 B-1 0.75 GL SO C
MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 116 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Traversing incore Probe System P&lD NO.: GE0719E520 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd TIP-1-1 2
D-5 A-1 0.25 BA SO C
C FE,PI, FE,PI, LJ LJ TIP-2-1 2
D-5 A-1 0.25 BA SO C
C FE,PI, FE,PI, LJ LJ TIP-3-1 2
D-6 A-1 0.25 BA SO C
C FE,PI, FE,PI, LJ LJ TIP 1-2 2
D5 D-1 0.25 XP XP O
C EX EX TIP-2-2 2
D-5 D-1 0.25 XP XP O
C EX EX TIP-3-2 2
D-5 D-1 0.25 XP XP O
C EX EX O
O 1/kmk
s MONTICELLO NUCLEAR GENERATING PLANT EWI 09.04.01 TITLE:
INSERVICE TESTING PROGRAM Revision 3 Page 117 of 117 ATTACHMENT 9.3 Valve Testing Table (cont'd)
SYSTEM: Hard Pipe Vent P&lD NO.: NH-116629 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No.
Class Coord Cat (in.)
Type Type Pos Pos Tests or DTJ Pfrmd AO-4539 2
C-3 A-2 8
BF AO C
C LJ LJ AO-4540 2
C-4 A-2 8
BF AO C
C LJ LJ g
PSD-4543 None B-6 D-2 10 RD SA C
C RD RD l
O O
1/kmk
_ _ _ _ _ _ - _ _ _ _