ML20217M169
| ML20217M169 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/24/1996 |
| From: | Stewart D, Withrow R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20217M144 | List: |
| References | |
| STA-750, NUDOCS 9805040449 | |
| Download: ML20217M169 (45) | |
Text
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4 COMANCHE PEAK STEAM ELECTRIC STATION STATION ADMINISTRATION MANUAL QUALITY RELATED CIIECK VALVE RELIABILITY PROGRAM PROCEDURE NO. STA-750 REVISION NO. 3 SORC MEETING NO.: 94 -4 / 4 DATE: Ml'/ 94 EFFECTIVE DATE: #4-d'7-94
-'EORx INEORMATION ONLL MAJOR REVISION 9805040449 980430 t
PDR ADOCK 05000445 P
PDR PREPARED BY (Print):
dux/E 5 TEuMA T EXT: d757' TECHNICAL REVIEW BY (Print): / 6.fv/TA//dW EXT: 794Y APPROVED BY:
b-DATE: l,J41-PLANT MANAGER
I CPSES PROCEDURE NO.
STATION ADRIINISTRATION MANUAL STA-750 l -
l CHECK VA.LVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 2 OF 45 1.0 PURPOSE 1.1 Overall Obiective of Procram The aim of the Program is to ensure that key check valves perform as designed. This is to be accomplished through the identification of existing and incipient check valve failures, via non-intrusive monitoring and disassembly examination.
The Check Valve Reliability Program (CVRP) was established to satisfy INPO SOER 86-03 concerns. The program has subsequently become useful in fulfilling certain IST requirements (Ref. 3.1.4); although specific data may be collected and analyzed in accordance with this procedure this application is governed by STA-702 (Ref. 3.2.14).
1.2 Procedure Purpose The intent of this procedure is to:
a) establish test / exam frequencies, methods, and acceptance criteria, b) provide performance monitoring requirements, c) defme departmentalinterfaces.
2.0 APPLICABILI'IY
2.1 General
all Ul, U2, and Common check valves, especially those inc uded in the following l
systems:
AF, CC, CO, CS, DG (air start), EX, FW, MS, RH, SI, SW
2.2 Soecific
emphasis on those check valves listed in Attachment 8.D.
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 l
CHECK VALVE RELIABILITY PROGRAM REVISION NO.3 PAGE 3 OF 45 3.0 BEFERENCES l
3.1 Develooment References J
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'3.1.1 INPO SOER 86-03, " Check Valve Failures or Degradation", 10/15/86
[CDF-24859).
3.1.2 INPO letter dated 7/2/90. providing clarification to SOER 86-03.
l 3.1.3 Nuclear Network Entry TI4637, " Check Valve Disassembly and Inspection Activities," 10/29/90 (further INPO insight into letter of 7/2/90).
3.1.4 Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs", 4/3/89.
3.1.5 NUREG-1352, " Action Plans for Motor-Operated Valves and Check Valves",
June 1990.
3.1.6 TE 92-1417, documentation of unit differences with respect to Kalsi Design Review 3.1.7 TE 93-0200, Function evaluation of those valves (within original scope of 278) which were omitted from the SOER 86-03 Design Review.
3.1.8 TE 93-2485, justification documentation for STA-750 inclusion / exclusion of valves re-evaluated under TE 93-0200.
3.1.9 CDF 26346, Ongoing Regulatory Commitment on BWIP check valves concerning disc-to-body interaction,1/20/93.
3.1.10 NRC letter dated 6/26/90 to ASME O&M Committee Chairman J. DeWease.
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'8 CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750
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t CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 4 OF 45 j
l 3.1.11 Stewart, D., " Comanche Peak Check Valve Reliability Program," Proceedings of the Second NRC/ASME Symposium on Pump & Valve Testing, July 1992, NUREG/CP-0123, with Supplement 1.
3.1.12 Stewart, D., " Acoustic Emission Testing of Piston Check Valves", Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing, July 1994, NUREG/CP-0137.
3.2 Performance References 3.2.1 Kalsi Engineering, "SOER 86-3 Check Valve Application Review: Document No.
1624," 2 Volumes, 11/30/89 [ Fulfillment ofINPO SOER 86-03 Item 2: CPSES Design Review].
3.2.2 B&W Nuclear Technologies (BWNT), "Ultracheck USA 2.2 User's Manual, BWNT-TM-98" 3.2.3 BWNT, "Ultracheck Basic Training Manual - Version 2.1/2.2.1, Revision 0", June j
1994.
3.2.4 BWNT, " Inductive Valve Motion Sensor Module Operating Instructions,"
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Revision 1, July 29,1993 (Drawing No. 1222418-A).
3.2.5-Liberty Technologies, "QUICKCHECK User Manual, Specification No.
QCX-1-UM-02." (Trace Analysis Reference) 3.2.6 Liberty Technologies, " Training Manual for QUICKCHECK Check Valve Diagnostic System, QCX 200-TM-00",1990. (Trace Analysis Reference) 3.2.7 Nuclear Industry Check Valve Group, " Evaluation of Nonintrusive Diagnostic Technologies for Check Valves (NIC-01)," Vendor Volume 1: Acoustic Signature j
Analysis Test Data, CANUS Corporation (1990). (Trace Analysis Reference) f l
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CPSES PROCEDURE NO.
STATICN ADMINISTRATION MANUAL STA-750 CHECKVALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 5 OF 45 3.2.8 PCB Piezotronics, Inc., " Operating Instructions for Medel 483Al16-Channel Rack-Mounted Power Supply."
3.2.9 TEAC Corporation, "TEAC RD-120T/RD-130T PCM Data Recorder Instruction Manual."
3.2.10 VibraMetrics, Inc., " Accelerometer Instruction Manual, Vibramite and Micromite Series."
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3.2.11 VibraMetrics, " Application Note AN 117, Using Super Magnets with High Frequency Accelerometers," March 1982.
3.2.12 STA-504, " Technical Evaluation" 3.2.13 STA-608, " Control of Measuring and Test Equipment" (Applicable only when CVRP determines valve operability, e.g., IST. Not necessary for SOER 86-03 activities; operability call is made during the disassembly examination, requested based upon non-intrusive test results.
Reference TE 91-3458).
3.2.14 STA-702, " Surveillance Program" 3.2.15 STA-711, "ASME Section XI Pump and Valve Inservice Testing" 3.2.16 STA-736, " Equipment Performance Monitoring Program" l
3.2.17 STA-170, " Software Quality Assurance for Application Software" l
3.2.18
" Post-Work Test Guide" 3.2.19 MSM-GO-0221, " Sensor Mount Installation" 1
CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 6 OF 45 i
4.0 DEFINITIONS / ACRONYMS 4.1 Desian Review Applications review, INPO SOER 86-03 recommendation 2, which identifies check valves susceptible to degradation due to improper sizing, orientation, or misapplication.
4.2 Event
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One particular episode of data acquisition, as identified by the TEAC tape recorder.
4.3 Power Snectral Density (PSD) l Frequency domain (Hertz) representation of a discrete time series (seconds) trace, computed using the Fast Fourier Transform (FFT) algorithim.
4.4 Inservice Testing (IST)
ASME Section XI Pump and Valve Inservice Testing. Surveillance testing, required by Technical Specification 4.0.5, which obtains information used in determining the operational readiness of certain Class 1,2,3 and non Code-class pumps and valves.
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4.5 Ultracheck Framatome's (formerly BWNT's) non-intrusive diagnostic system for check valves, consisting of a portable data acquisition unit and USA (Universal Signal Analysis) Software.
It is designed to status / monitor internal check valve degradations and verify component operability. The system includes both acoustic and magnetic flux technologies. (SQA-Doc l
ID194) 1
CPSES PROCEDURE NO.
l STATION ADMINISTRATION MANUAL STA-750 CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 7 OF.45 l
4.6 Ouickchec};
l Liberty Technologies' non-intrusive diagnostic system for check valves, consisting of a l
portable data acquisition unit (DAU) with an independent post-processing module and Quickcheck SoRware (Version 1.0, SQA Doc. ID 0047). Results are equivalent to that I
obtained with Ultracheck. Quickcheck is no longer used for STA-750 data analysis, but the manuals remain an analysis reference.
4.7 Surveillance Work Order (SWO)
A uniquely numbered form containing instructions that may be used to specify, control and document surveillance performance, in accordance with STA-702.
4.8 Igst Data, from a panicular event, downloaded from the data tape into the sonware for analysis.
4.9 Wear /Fatiuue Index Summary form of Kalsi Engineering's CVAP (Check Valve Analysis and Prioritization) sonware calculations for check valve wear and fatigue. The wear index represents the estimated hinge pin wear of a swing or tilt disc valve. The fatigue index represents the calculated fatigue life of the disc stud, for a swing check valve. The degee to which the wear or fatigue life is consumed is categorized by assigning an index number to both calculations, as explained in Table 1 of Ref. 3.2.1: from 1 = very low (0 - 7% life usage, limit to 14 plant cycles) to 5 = very high (> 56% usage, limit to < 2 plant cycles).
Initial CVRP priorities were based upon the wear /fati ue index 3
(index 4 & 5 = priority A,2 & 3 = B,1 = C).
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r-1 CPSES PROCEDURE No.
STATION ADMINISTRATION MANilAL STA-750 I
CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 8 0F-15 5.0 RESPONSIBILITIES 5.1 Maintenance Engineering Manager 5.1.1 Maintain the CVRP, including keeping this procedure current.
5.1.2 Assign a CVRP Responsible Engineer.
5.2 Check Valve Reliability Procram (CVRP) Resoonsible Encineer 5.2.1 Select check valves for non-intmsive testing and disassembly examination.
5.2.2 Establish test / exam acceptance criteria.
5.2.3 Determine non-intrusive monitoring frequency.
5.2.4 Schedule CVRP tests / exams.
5.2.5 Evaluate CVRP test / exam data, per this procedure.
5.2.6 Identify adverse trends which are indicative ofincipient component failure. (Ref.
3.2.16) 5.2.7 Identify and initiate warranted corrective action, in response to CVRP data.
5.2.8 Provide, to P&T, any information (e.g., parameters to monitor, monitoring duration) necessary for the generation of requested plant computer data print-outs.
5.2.9 May perform CVRP data acquisition, in accordance with this procedure.
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STATION AD.TIINISTRATION MANUAL STA-750 l
CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 9 OF 45 5.3 Performance Test Engineerine Suoervisor 5.3.1 Ensure plant computer data print-outs are generated upon request for specified CVRP non-intrusive tests, to assist in evaluation of test data. (All parameters needed to accomplish this will be provided by the CVRP RE).
j 5.4 Mechanical Maintenance Manaaer 5.4.1 Ensure CVRP identified exam criteria are incorporated into appropriate check valve disassembly procedures or work documents.
5.4.2 Perform disassembly examinations.
5.4.3 Manufacture and install / remove acoustic emission sensor mounts, in accordance with MSM-GO-0221.
5.4.4 Perform corrective maintenance.
5.5 Operations Support Supervisor 5.5.1 Ensure CVRP work scope is included in Surveillance Work Orders.
5.6 Data Acquisition Personnel Manager (eg.. OC Manager) 5.6.1 Perform CVRP data acquisition, in accordance with this procedure.
5.6.2 Provide test personnel.
5.6.3 Ensure appropriate access (e.g., RWP) for test personnel.
5.6.4 Coordinate the activities of site / contractor personnel performing CVRP I
tests / exams.
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 10 OF 45 l
6.0 INSTRUCTIONS Current functional testing (IST) establishes check valve ooerability, but not necessarily reliability. (reliability encompasses and extends the timeline of operability). Per Reference 3.1.10, recurrent and long-standing industry check valve problems have been due, in part, to the inadequacy ofIST to detect internal degradation. Although IST ensures check valve operability under test conditions, it does not ensure valve actuation, as required, under other anticipated operating conditions. The intent of this PM program is to establish check valve a
reliability.
l 6.1 Background - Desien Review l
Kalsi Engineering was contracted by CPSES to perform an SOER 86-03, " Applicability Evaluation" (the second SOER recommendation) of all check valves within 11 Unit I systems (the eight systems recommended by the SOER, plus three suggested by industry experience), a total of 278 check valves.
l Typically, non-nuclear safety-related check valves less than two inches in size and those used I
infrequently (less than 5% of the plant operating cycle) were not included in the complete analysis; therefore,149 valves out of 278 were analyzed.
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO.3 PAGE 11 OF 45 6.1.1 Priority Valves from Design Review Of the above 149 valves, all but 25 were considered suitable for long-term operation: 15 were identified as accelerated wear / fatigue concerns,10 as disc seating concerns (AF system). In addition,18 FW check valves were recommended for inspection due to erosion / corrosion susceptibility. (These 18
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check valves are indirectly monitored via the CPSES Corrosion Monitoring Program, STA-730).
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6.2 CVRP Pooulation (Attachment 8.D) 6.2.1 The program adopted the analyzed Kalsi population of 149 Unit i valves and their Unit 2 counterparts, as its program population.
i 6.2.2 Unit differences (Unit 2 compared to Unit 1), with respect to the Design Review, were subsequently evaluated and incorporated into the program (Ref. 3.1.6).
6.2.3 Valves from the 11 systems ofinterest which were omitted from the Design Review analysis were subsequently re-evaluated resulting in specific additions to the program (Ref. 3.1.7 and 3.1.8) 6.2.4 Check valves may be added to or subtracted from the program based on non-intrusive testing, disassembly examination results, or site maintenance history.
6.2.4.1 Emphasis should be placed on those check valves whose consequences of failure are severe from a standpoint of nuclear safety, personnel safety, or the ability to sustain reliable plant operations.
6.2.5 CVRP Priority Initial prioritization was based upon Kalsi Report recommendations. Subsequent changes in assigned priority have been based on non-intrusive test data or disassembly exam results, accomplishing a validation / modification to the original Design Review.
CPSES PROCEDURE NO.
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STATION ADMINISTRATION MANUAL STA-750 i
CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 12 OF 45 6.3 Preventive Maintenance Tests / Examinations 6.3.1 The CVRP is composed of two parts:
6.3.1.1 Non-Intrusive Testing (Fault Finding PMS)
Choice of methods:
Acoustic Emission (AE)
Magnetic-Flux (exterior placement of magnet) 1 Ultrasonic Test (UT)
Radiography Thermography or temperature profiles (to indicate valve leakage)
Other, intmsive data collection may be used to support the non-intrusive testing:
- Pressure (Fig. 7.4)
- Flow e Fiber optic /boroscopic probes
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 13 OF 45 NOTE This procedure only provides instruction for AE and Magnetic-Flux testing. AE is the intended primary diagnostic method to be used within the CVRP and is the only technique upon which IST operability calls (Definition 4.4) are based. Other methods may be called out as conditions warrant.
6.3.1.2 Disassembly Examination (Condition Directed PMs)
Specific exam instructions should be incorporated into appropriate i
Mechanical Maintenance check valve disassembly procedures or work documents.
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6.3.2 Test Summary.D provides the Test Table. This is designed to be used a. -
worksheer during test activities. A copy of the Test Table is completed for the applicable valves and attached to a PM task list, the vehicle for scheduling and documenting the accomplishment of required testing. (Note that IST activities are l
governed by STA-702; although specific data may be collected and analyzed in accordance with this procedure, test activities are handled by dedicated surveillance work orders.)
6.4 Acoustic Emission (AE) Testing 6.4.1 Test Frequency 6.4.1.1 As a minimum, the frequencies (" priorities") listed in Attachment 8.D should be met.
6.4.1.2 Baseline data should be collected prior to the end of RFO2, regardless of assigned " priorities"; during this period, the valve is assumed to be in good condition, unless maintenance records prove otherwise. Collection of baseline data by the end of RF02 j
eliminates the nced to open valves for the purpose of verifying AE l
baseline data.
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CPSES PROCEDURE NO.
STATION ADMINIS'11tATION MANUAL STA-750 CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 14 OF 45 6.4.1.3 Baseline data should be re-established following any maintenance activities which would affect previous baseline data: any stnictural alteration to the valve body or internals (Ref. 3.2.18).
6.4.1.4 If a component is unavailable for data collection during its scheduled monitoring period due to maintenance or operational constraints, data should be collected within the next monitoring period that the component becomes available.
6.4.1.5 Disassembly candidates identified by the Kalsi Report should be tested acoustically in advance of the Report's recommended exam outage, to allow for prioritization of candidate valves and a re-evaluation of the necessity for disassembly.
6.4.2 Sensor Mount Construction and Installation 6.4.2.1 Typical sensor mount construction should be per MSM-GO-0221.
The mount material shall be compatible with the valve body material.
6.4.2.2 Mount attachment methods for standard temocratu.rg soplications (valves with normal operating temperatures s350*F):
a)
Semi-permanent epoxy mounts (mount installation per MSM-GO-0221, using CMAR-91-002, Devcon Titanium Putty). Once installed. the sensor mounts should be left in pjAqc, to ensure data repeatability and trending.
b) Superglued mounts (should only be used for temporary installation). These are only useable on application surfaces
<!75'F. (Ref: CMAR TUE 270-89B, CMAR 93-00l).
c) Magnetic mounts (with upfront approval of CVRP Responsible Engineer).
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA 750 i
CllECK YALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 15 OF 45 I
-6.4.2.3 Mount attachment methods for high temoerature aoolications
(>350'F):
a) Magnetic mounts, with sensor " construction" as described in.A.
b) No scheme yet available for stainless steel body, high temperature valves. Those valves which see a temperature of s350F during the test event may use " standard temperature" mounts during the test.
6.4.2.4 Mounting scheme should be consistent among "like groupings" (per Kalsi Report, Vol.1, Reference 3.2.1) of valves.
6.4.3 AE Data Collection 6.4.3.1 Data collection should be performed in accordance with applicable equipment manuals (e.g., References 3.2.8,3.2.9,3.2.10,3.2.11) l and Attachments 8.A and 8.B.
PRECAUTIONS: In order to avoid adversely affecting the quality of the AE data, the following precautions should be observed:
- 1. Do not lean or place hands on the valve during AE data acquisition.
- 2. Do not run AE cabling over energized equipment.
- 3. Do not allow cable runs greater than 200 ft. (between valve and tape recorder) for ICP-type accelerometers.
- 4. Stay consistent with accelerometer model number and mounting scheme, among like valves (per Kalsi Report, Ref. 3.2.1).
l 6.4.3.2 Appropriate test conditions (e.g., "obtain closure during OPT-201 A") should be provided on Attachment 8.D, unless otherwise specified by the CVRP RE.
CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 l
CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 16 OF 45 6.4.3.3 Because at least 10 seconds of data is required to perform an FFT, ensure that each taped event is of a ndnimum duration of 10 seconds.
6.4.3.4 When recording a transient activity, an additiomi 10 seconds l
(minimum) of steady state data should be taken.
6.4.3.5 Test information should be recorded on Form STA-750-1. If AE
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data acquisition is being performed simultaneously with an IST activity, note the IST or SWO on Form STA-750-1.
6.4.4 Qualifications of AE Test Personnel 6.4.4.1 In addition to specific department requirements and/or qualifications, personnel responsible for CVRP AE data acquisition and/or evaluation should meet the requirements listed in.C.
6.4.4.2 Forward completed Form STA-750-2 to Nuclear Training for processing in accordance with STA-106.
I 6.4.5 AE Data Evaluation (Figures 7.2 thru 7.4) 6.4.5.1 Data analysi., should be performed using Framatome's USA Software (guidance provided in Ref. 3.2.2 or 3.2.3). Results should be compared with previous AE signatures (esp. baseline) of the valve under evaluation. Plant computer data covering the test period should be used to support the AE data. IST results and maintenance history may also be helpful.
6.4.5.2 Documentation of the data evaluation should consist of a completed Form STA-750-1, with supportive analysis print-outs, attached to either a Technical Evaluation (Form STA-504-6) or an applicable Work Order.
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i CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA 750 j
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CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 17 OF 45 l
6.4.5.3 AE data may be used to determine the following concerns:
i EVALUATION CROSS REFERENCE EVALUATION CONCERN (FIGURE NO.)
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a) Achievement of a full open or closed stroke 7.2.4 (e.g., following a pump start /stop) b) Quality of seat, including detection of leakage, 7.3, pg.1&2 j
qualitatively c) Valve performance under steady state now Figure 7.3 conditions identify flow conditions causing e
" tapping" and " fluttering" (baseline full stroke data should be used to verify any back stop or seat impacting) compare the identified flow conditions with actual operating conditicas as j
design review validation I
1 note operating conditions that represent severe service conditions (for those check valves that experience a variety of flow conditions)
Normal plant operation should not require a check valve to operate under severe conditions.
If a valve is found to be fluttering violently, (e.g.,60% V min in Figure 7.3) under normal plant operation,its design / application should be reviewed. Likewise,if tspping persists following a forward flow full stroke actuation, into normal operation flow, the valve design and/or application should be reviewed.
6.4.5.4 Since flow-induced deterioration of check valves is typically a long-term phenomenon, the evaluation should put an emphasis on that j
AE data reflecting normal operation (e.g., normal flow range impacting).
1 CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 f
CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 18 OF 45 6.4 6 Trending of AE Data 6.4.6.1 AE data for each CVRP check valve should be trended by comparing current field data with baseline and othei previous data.
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l 6.4.6.2 Negative trending results indicative of a potentially adverse internal
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condition, should be validated by disassembly examination.
l 6.4.6.3 Trending should be performed quarterly, in accordance with STA-736 (Ref. 3.2.16) 6.5 Magnetic Flux (MF) Testina: AC and DC External Magnetic Placement) Techniaue 6.5.1 General MF data compliments the AE data by indicating relative valve disc / disc arm position and stability, during an open/close stroke of the valve.
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6.5.2
' Test Frequency 4
Use of MF Testing is to be on a case-by-case basis only. as called out by CVRP RE, and as an accomoaniment to AE testina.
6.5.3 MF Data Collection Data collection should be performed in accordance with Reference 3.2.4 with the following exceptions:
for DC MF monitoring on high temperature valves, the Vortex Tube is not, typically, to be used. Rather, stay time of the Hall Effect Probe (Mag Flux Concentrator) should be limited to 30 minutes maximum.
CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CHECK VALVE RELIABILITY PROGRAM REVISION NO.3 PAGE 19 OF 45
.6.5.3 e
for DC MF monitoring, the " slag guard" pads should be used whenever possible.
method of securement of magnets (used with DC method) to valve body e
exterior is temporary only and selected by data acquisition personnel (and noted on Form STA-750-1); DC probe and AC sensor coil mounting studs may be semi-permanently fixed to valve body with Devcon Titanium Putty.
(CMAR 91-002). (Ref. 3.2.4)
DC method is typically used on carbon steel body valves; AC method is used only on stainless steel body valves Test information should be recorded on Form STA-750-1.
6.5.4 Qualification ofMF Test Personnel "MF Test Personnel Qualification" is an accessory certification to "AE Test Personnel Qualification.". Details are provided in Attachment 8.C.
6.5.5 MF Data Evaluation MF data analysis should be per ormed concurrent with AE data r
6.5.5.1 analysis.
6.5.5.2 References 3.2.2,3.2.3,3.2.5,3.2.6, and 3.2.7 provide analysis guidance.
6.6 Disassembly Examination 6.6.1 Disassembly should be done when the examination results will confirm some condition predetermined by another (e.g., non-intrusive) technique. (Ref. 6 4.6.2)
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 20 OF 85 6.6.2 Exam Expansion 6.6.2.1 If disassembly exam results warrant, an immediate examination of the remaining valves in the Kalsi-specified group (Ref. 3.2.1) should be conducted.
7.0 FIGURES 7.1 Figure 7.1 "CVRP Disassembly Examination Flowchart" 7.2 Figure 7.2 - AE Data Evaluation: Determination of Full Open/ Closed Stroke (Ref. 3.1.8, 3.1.12) 7.3 Figure 7.3 - AE Data Evaluation: Condition Monitoring (Ref. 3.1.11,3.1.12) 7.4 Figure 7.4 - AE Data Evaluation: Simultaneous Use of Multiple Non-Intrusive Test Methods (Ref. 3.1.11, 3.1.12) 8.0 ATTACHMENTS / FORMS 8.1 Attachments 8.A CVRP Data Acquisition Equipment 8.B Gain Settings for AE Data Acquisition System (Ref. 3.2.2) 8.C Qualification of Personnel 8.D Test Table /CVRP Population
CPSES PROCEDURE NO.
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STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 21 OF 45
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8.2 Forms 8.2.1 Form STA-750-1, CVRP Data Log Sheet 8.2.2 Form STA-750-2, Personnel Qualification Record 9.0 RECORDS When completed, the following forms, reports, or other documents generated in response to this procedure shall be dispositioned in accordance with STA-302, " Station Records" 9.1 Form STA-750-1, CVRP Data Log Sheet 9.2 Form STA-750-2, Personnel Qualification Record 1
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CPSES PROCEDURE NO.
j STATION ADMINISTRATION MANUAL STA-750 i
CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 22 OF 45
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FIGURE 71 PAGE 1 OF 1 CVRP DISASSEMBLY EXAMINATION FLOWCHART I
OF CVRP SPECIAL NTEREST:
A) VISUAL INSPECTCN COMMENTS
- 8) MEASUREMENTS TAKEN "CONCITCN DIRECTED
RWO*MM MM WORK ORDER
=
F CFED VAULTED l
MSM l
PROBLEM OENTFIED l
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- U
'CVRP RE REVIEW I
Noticaton to CVRP RE OF l
l MM ORP invoNement L.
i CPSES PROCEDURE No.
STATION ADMINISTRATION MANUAL STA.750 l
CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 23 OF 45 l
FIGURE 7 2 PAGE 1 OF 2 1
AE DATA EVALUATION: DETERMINATION OF FULL OPEN/ CLOSED STROKE l
(Closure Verification)
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i
CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISIONNO 3 PAGE 24 OF 45 FIGURE 7.2 PAGE2OF2 AE DATA EVALUATION DETERMINATION OF FULL OPEN/ CLOSED STROKE I
I 1
DETERMINATION OF IMPACT SOURCE ON IN-SERIES CHECK VALVES USING SIGNAL MAGNITUDE COMPARISON o.c utnse M I
5
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Il D.
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 l
CllECK VALVE RELIABILITY PROGRAM REVISION NO.3 PAGE 25 OF 45 l
1 l
FIGURE 7.3 PAGE 1 OF 3 AE DATA EVALUATION: CONDITION MONITORING EVALUATION MATRIX FOR PISTON CHECK VALVE CLOSURE EVENT AE DATA h
~
IMPACTING ASSOCATEDWTH A CHANGE N FLOW (hgn pass emelope l
of ether cnannel, raw cata trace of sacreed channel) l N
y 1fY
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channel) channel)
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s== memesi plug) l l
t
CPSES PROCEDURE NO.
STATION ADMIN 1. RATION MANUAL STA-750 CHECK VALVE RELIABILITY PROGRAM REVISION NO.3 PAGE 26 OF 45 FIGURE 7.3 PAGE 2 OF 3 AE DATA EVALUATION: CONDITION MONITORING TAG NO
' 357 EVENT.
Ee=w - Pso
~
(my FJ ms 3 CONDIT M FRCM DATA FOURE NO.
CLOSURE EDIMP. EV V/N SantWerweavel r
MULTIPLE I CTN Y/N
/
)
POST RE GE LEVELS G
N/L/M/H Y STATE L PRCR TO CLOSURE G
L/M/H NOTABLE ACT FREQUENCY Y/N LOW FProtFNCY STEADY STATE ACTMTY PROR TO L/M/H CLOSURE OSC1LLATON EV0ENT Y/N CHARACTERISTC CLOSURE T (SHAPE OF CURVE)
Y/N BWP ONLY: EVDENCE OF DISO i 800Y CONTACT Y/N ODCN EVCNT-
,, g CEFNED OPEN IMPACT Y/N STEADY STATE LEVELS FOLLOWING OPEN G
L/M/H NOTABLE IMPACT FREQUENCY Y/N LOW FREQUENCY STEADY STATE ACTMTY FOLLOWING CPEN L/M/H G
OSCLL/~ON EVOENT Y/N
$5 CHARACTERISTC OPEN EVENT (SHAPE OF CUWE)
Y/N CONCLUSCNS VALVE N SATISFACTORY CONDITION PM DISASSEMBLY RECOMhENDED (WR s 1
COMMENT 5:
f 1
i
1 CPSES STATION ADMINISTRATION MANUAL PROCEDURE NO.
l i
STA-750 CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 27 OF 45 EIG RE 7.3 PAGE 3 OF 3 AE DATA EVALUATION CONDITION MONITORING PSD OF STEADY STATE IMPACTING ON 3" BWIP MODEL 75510 CHECK VALVE 80 UZEM l l
}
lU 4
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Plot 1:
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- 81" "
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- 0010 ?
i O
3 00 5000 7500 10000 l
- 1925 yar 3k'I? seisnic analys:s:
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.m
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CHECK VALVE RELIABILITY PROGRAM l REVISIONNO.3 PAGE 28 OF 45 FIGURE 7 4 PAGE 1 OF 1 AE DATA EVALUATION: SIMULTANEOUS USE OF i
i MULTIPLE NON. INTRUSIVE TEST METHODS l
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i CPSES PROCEDURE NO.
i STATION AD311NISTRATION 31ANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 42 OF 45 ATTACHMENT 8.D PAGE 11 OF 14 TEST TABLE /CVRP POPULATION Cd 3d 4
=a j
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CPSES PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-750 CIIECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 43 OF 45 I
i 1
ATTACHMENT 8,D PAGE 12 OF 14 i
TEST TABLE /CVRP POPULATION 3s ux i
29 l
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CPSES l
4 PROCEDURE NO.
i
. STATION ADMINISTRATION MANUAL STA-750 I
CHECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 44 OF 45 I
l ATTACHMENT 8.C PAGE 13 OF 14 TEST TABLE /CVRP POPULATION 3
5t a=
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CPSES PROCEDURE NO.
~
STATION ADMINISTRATION 3!ANUAL STA-750 l
CllECK VALVE RELIABILITY PROGRAM REVISION NO. 3 PAGE 45 OF 45 i
ATTACHNENT 8.D PAGE 14 OF 14 TEST TABLE CVRP POPULATION LEGEND' V
selected for task list TAG Tag Number mmas urut designator (any unit differences are noted in the table)
RECOMMENDED TEST EVENT Ut procede alreferenceslisted TEST SKETCII NO.
from departmental Test Sketch Book (not a controlled document)
TEMP Valve Temperature high (ii) or standard (S) temperature application type of sensor and putty (during test event)
(used to install mount), based on normal operating temperature per Line tjst, CPES-41011 liigh temperature is defined as >350F.
MATL Valve Body ifatenal 1 - carbon steel (and Sensor Mount 2 - 300 series stainless steel ifount Material)
SCAFF*
ScatTolding yes (Y) or no (N)
If y es. height is provided in parentheses If a 6 foot stepladder is needed 7 tL is noted.
(
If an extension ladder only it required, EL is noted j
INSUL' Insulauon yes (Y) or no (N), followed oy t>y in parentheses.
per Line List:
A-ant -sweat, B-thennal, C= reflective PRI Pnonty I
AE TESTING FREQUENCY TPJORITY "
PLANT OPERATIONAL YEARS PLANT REFUELING CYCLES Al j
A2 I
l Ill 2
B2 2
C1 4
C2 4
l D
N/A N/A
prianty level includes the number 1 or 2, which defines the test opportunity: I = tested at power, 2 = tested dunng outage conditions priority level D stands for PM disassembly (no acceptable test esent), followed by exarn frequency in years.
For those marked "IST*, the AE test is also an ASME XI test. For exarnple, "C2/IST(o),A2" indicates that although this valve has a CVRP priantf of C2, it is also an IST valve requiring an ope.: stroke verification each outa e (either cold a
shutdown or refueling, as dictated by IST Plan)
UI & 2 prionties are idenucal, unless specifwally noted Contact CVRP RE concernir.g discrepancies or missing infonnation m Acadunent 8.D.
- provided for information only