ML20108D169
| ML20108D169 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/03/1996 |
| From: | Muench R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-96-0027, ET-96-27, NUDOCS 9605070307 | |
| Download: ML20108D169 (32) | |
Text
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W4pLF CREEK NUCLEAR OPERATING CORPORATION Richard A. Muench Vice President Engineering May 3, 1996 ET 96-0027 U.
S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D. C.
20555
Reference:
1)
Letter dated March 6, 1996, from J.
C.
Stone, NRC, to N.
S.
Carns, WCNOC 2)
Letter WM 95-0129, dated August 30, 1995, from N.
S.
Subject:
Docket No. 50-482:
Response to Request for Additional Information, Second 10-Year Inservice Inspection Interval Gentlemen Attached is Wolf Creek Nuclear Operating Corporation's (WCNOC) reply to the Request for Additional Information transmitted by Reference 1.
WCNOC's reply includes new Relief Requests I2R-19 and I2R-20.
This reply also includes j
Relief Request I2R-17, which has been rewritten for clarification.
The Enclosure provides a copy of ASME Code Case N-509 for your convenience.
l Relief Request I2R-17 was previously submitted by Reference 2.
It requests the l
use of alternative rules for system pressure testing of Standby Emergency Diesel Generator Subsystem components.
Relief Request I2R-17, as revised by l
this transmittal, supersedes Relief Request I2R-17 submitted by Reference 2.
Relief Request I2R-19 requests the use of the alternative requirements of Code Case N-498-1 for the Second Interval Inservice Inspection Program.
Relief Request I2R-20 requests the use of the alternative requirements of Code Case N-509 for the Second Interval Inservice Inspection Program.
This transmittal was discussed with the NRC Project Manager and the NRC Reviewer on April 24, 1996.
070053 9605070307 960503 ieI' /
PDR ADOCK 05000482 G
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l PO. Box 411 ! Burhngton, KS 66839 / Phone. (316) 364 8831 l
An Equal Opporturuty Empbyer M F HC VET s
50 - h
ET 96-0027
+
ie Prga 2 of 2 If you should have any questions regarding this response, please contact me at (316)364-8831, extension 4034, or Mr. Richard D.
Flannigan at extension 4500.
Very truly yours, aAaaw(
Richard A. Muench RAM /jra Attachment Enclosure cc:
L.
J.
Callan (NRC), w/a W.
D. Johnson (NRC), w/a J.
F.
Ringwald (NRC), w/a J.
C.
Stone (NRC), w/a l
a Attachment to ET 96-0027 Page 1 of 26 i
i Response to Request for Additional Information i
The following information is provided in response to the Request for Additional Information on the Second Interval Inservice Inspection Program Plan dated March 6,
1996.
Request Item a.
Section 2.1.3 states that Code Case N-498-1, " Alternative Rtdes for 10-Year System Hydrostatic Testing for Class 1,
2, and 3 Systems," has been approved for use until it is incorporated into Regulatory Guide 1.147.
Relief given to Wolf Creek i
Generating Station during the first interval does not apply to subsequent intervals.
Is it the licensee's intent to submit for relief to use this Code Case during the second 10-year interval?
Response Item a.
It is the intent to have the ability to use the alternatives provided by Code case N-498-1 in the second 10-year interval.
Relief Request I2R-19 is provided for requesting use of the alternatives provided by Code Case N-498-1.
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Attachmant to ET 96-0027 Page 2 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST I2R-19 (Page 1 of 2)
COMPONENT IDENTIFICATION Code Classes:
1, 2,
and 3
References:
Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 Examination Categories B-P, C-H, D-A, D-B, and D-C Item Numbers:
All Item Numbers within Categories B-P and C-H; and D1.10, D2.10, and D3.10
==
Description:==
Alternate Rules for 10-Year System Hydrostatic Testing of Class 1, 2, and 3 Systems.
Component ID:
All Class 1, 2,
and 3 Systems CODE REQUIREMENTS Class 1 Systems Table IWB-2500-1, Examination Category B-P requires the performance of a system hydrostatic test and accompanying visual examination VT-2 of all Class 1 system components at or near the end of each interval.
Class 2 Systems Table IWC-2500-1, Examination Category C-H requires the performance of a system hydrostatic test and accompanying visual examination VT-2 of all Class 2 components within the pressure retaining boundary of the system at or near the end of each interval.
The pressure retaining boundary is defined as all system components up to and including the first normally closed valve or valve capable of automatic closure when the system safety function is required.
Class 3 Systems Table IWD-2500-1, Examination Categories D-A, D-B, and D-C, require the performance of a system hydrostatic test and accompanying visual examination VT-2 of all Class 3 components within the pressure retaining boundary of the system at or near the end of each interval.
The pressure retaining boundary is defined as all system components up to and including the first normally closed valve or valve capable of automatic closure when the system safety function is required.
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e' Attachment to ET 96-0027 Page 3 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST I2R-19 (Page 2 of 2)
BASIS FOR RELIEF Relief is being requested to allow the use of alternative requirements for system hydrostatic testing of Class 1,
2 and 3 systems as detailed in Code Case N-498-1.
The basis for this request is as follows:
1)
The ASME Section XI Working Group on Pressure Testing concluded that no additional benefit would be gained by conducting the existing class 1,
2, and 3 system hydrostatic tests versus performing the 40 month pressure tests at nominal operating pressure.
2)
Licensees incur considerable time, radiation dose, and monetary resources carrying out hydrostatic test requirements.
3)
The NRC staff has recognized, through approval for use of Code Case N-498-1 in WCNOC's first inspection interval, that
.. compliance with the Section XI hydrostatic testing requirements results in hardship and/or unusual difficulty for the licensees without a compensating increase in the level of quality and safety."
4)
The alternate rules of Code Case N-498-1 provide an acceptable level of quality and safety.
d PROPOSED ALTERNATIVE EXAMINATION The requirements of Code Case N-498-1 may be used as an alternative to the system hydrostatic testing requirements.
PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3, 1995 through September 2, 2005.
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f Attochment to ET 96-0037 Page 4 of 26 i
Request Item b.
1 1
j Section 2.1.5 adopts Code Case N-509,
" Alternative Rules for the Selection and j
Examination of Class 1,
2, and 3 Integrally. Welded Attachments. "
The licensee j
expects Code Case N-509 to be incorporated into Regulatory Guide 1.147 prior to inspection activities at Wolf Creek Generating Station; therefore, a request for relief to use Code Case N-509 has not been provided.
Explain how Code Case N-509 j
is being implemented at Wolf Creek; include the total population of non-exempt j
integral attachments by class and samples scheduled for examination by class.
i Response Item b.
}
As discussed during the telecon on April 24, 1996, that included Wolf Creek f
personnel, Tom Sala from VECTRA, NRC personnel, and NRC contract personnel from i
INEL, the original submittal had included the total population of Class 1, 2,
and
}
3 integrally welded attachments on a system basis.
The applicable listings included identification of which components were selected for examination.
The i
primary concern by the plan reviewers was whether the submittal had included all integrally welded attachments and was not limited to those supports selected through implementation of Code Case N-491.
WCNOC personnel reassured the plan reviewers that the total population was included in the submittal and it was agreed that additional information did not need to be submitted.
In addition to the above, a relief request is being submitted to incorporate the alternatives provided by Code Case N-509 in the event approval for incorporation into Regulatory Guide 1.147 does not occur prior to completion of the first 40-month period of the second 10-year inspection interval.
Therefore, Relief Request I2R-020 is provided requesting use of the alternatives provided by Code Case N-509.
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Attachm nt to ET 96-0027 Page 5 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN j
RELIEF REQUEST I2R-20 (Page 1 of 2) l COMPONENT IDENTIFICATION Code Classes:
1, 2 and 3
References:
Table IWB-2500-1, Table IWC-2500-1, Table IWD-2500-1 Examination Categories: B-II, B-K 1, C-C, D-A, D-B, D-C Item Numbers:
Ba.10, B8.20, B8.30, B8.40, B10.10, B10.20, B10.30, C3.10 C3.20, C3.30, C3.40, D1.20, D1.30, D1.40, D1.50, D1.60, D2.20, D2.30, D2.40, D2.50, D2.60
==
Description:==
Alternate Rules for the Selection and E:tamination of Class 1,
2 and 3 Integrally Welded Attachments Component Numbers:
All Class 1,
2 and 3 Integral Attachments Subject to Inservice Inspection CODE REOUIREMENTS Class 1 Attachments Table IWB-2500-1, Examination Categories B-H and B-K1 require the performance of surface or volumetric examinations, as applicable, on integral attachments with a design thickness of 5/8" or greater.
Class 2 Attachments Table IWC-2500-1, Examination Category C-C requires the performance af a surface examination on integral attachments with a design thickness of 3/4" or greater.
Class 3 Attachments Table IWD-2500-1, Examination Categories D-A, D-B, and D-C require the performance of a visual VT-3 inspection on integral attachments.
For complete details on ASME Section XI Code examination requirements, see Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1.
BASIS FOR RELIEF Relief is being requested to allow the use of alternate requirements for the examination and selection of Class 1,
2 and 3 integral attachments detailed in Code Case N-509.
The basis for this request is as follows:
l Attachmtnt to ET 96-0027 Paga 6 of 26 J
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST I2R-20 (Page 2 of 2) 1)
During the first inservice inspection interval at the Wolf Creek Generating Station, no inservice flaws were detected in integrally welded attachments which would affect safety or compromise the integrity of the plant.
2) within the commercial nuclear power
- industry, failures of integral attachments have been very rare and have not affected plant safety.
When failures or inservice defects are found in integral attachments, they are usually associated with a support which has been damaged during operation.
l Therefore, flawed or broken integral attachments are typically detected i
during the investigation of damaged supports rather than during scheduled inservice inspections.
One feature of Code Case N-509 is to focus the examination of integral attachments on instances where the deformation of the assoc.ini.ed supports is identified.
This requirement will increase the likelihood of ~ c,cating damaged integral attachments and thereby increase the level of quality and safety provided by those alternative rules, as compared to the rules of the 1989 Edition of Section XI.
3)
There is a significant amount of man-rem exposure and cost associated with the scheduled inspection of Class 1, 2 and 3 integral attachments.
1 4)
Unlike ASME Section XI, 1989 Edition, the alternate selection criteria of Code Case N-509 does not impose a minimum thickness requirement for the l
inspection of an integral attachment.
Therefore, a greater population of i
integral attachments will be available for inspection because selection will not be limited to those above an arbitrary thickness.
This provision improves the quality and safety level established by these examinations.
5)
The alternate rules of Code Case N-509 provide an acceptable level of quality and safety.
PROPOSED ALTERNATE EXAMINATION
)
The requirements of Code Case N-509 will be used to select and examine integrally welded attachments. A copy of this Code case is enclosed.
PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3, 1995 through September 2, 2005.
s Attachmsnt to ET 96-0027 Page 7 of 26 Request Item c.
In Requests for Relief I2R-03, I2R-04, I2R-05, I2R-06, and I2R-09, which address welds that have received partial ultrasonic examinations, it is unclear how the coverages were calculated.
Provide detailed information on how the coverage was determined, including the cumulative coverage for each examination area.
Also provide a detailed drawing of each examination area depicting all limitations.
Response Item c.
l The second interval relief requests that. involve examination limitations included the same information as was provided for review and approval of the first interval
- relief requests for the; same limitations in nearly all cases.
Additional information can be provided for most of the subject relief requests.
These are discussed individually as follows:
I2 R-Oh The information provided was the same as that provided for. the first 10-year interval.
- However, this component's second interval examination (automated portion only) had been performed during Refueling Outage 8 in the Spring of 1996 and new coverage percentages were obtained.
Figure 1 represents a drawing (not to scale) of the Flange to Upper Reactor vessel Shell Weld and the applicable beam directions / angles are listed with the appropriate examination coverages.
The manual examination portion from the flange surface was 90% complete for I
the first 10-year interval and is therefore expected to be the same for the second interval.
The amount of coverage for weld metal (WM) interrogation I
is shown as a separate value to identify the amount of coverage in the volume where a crack would have a higher probability of presence.
The information provided was the same as that provided for the first 10-year interval.
Additional information in the form of a drawing (not to scale) is provided in Figures 2 and 3.
In addition, the weld identification for this relief request needs to be corrected, the actual weld identification is CH-103-101.
I2R-05: A drawing provided for review and approval of the first 10-year interval relief request was inadvertently omitted in the submittal for the second 10-year interval.
This drawing is represented by Figure 4.
No other additional information is provided.
The second 10-year interval submittal included all of the information provided for approval of the first 10-year interval relief request. No additional information is provided.
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Attachmtnt to ET 96-0027 Page 8 of 26 12R-09:
The second 10-year interval submittal included all of the information provided for approval of the first 10-year interval relief request. No additional information is provided.
In addition to the above relief requests, the NRC contract reviewers had requested, during the telecon on April 24,
- 1996, coverage percentage information for Relief Request I2R-18.
This too included the came information as the approved relief request contained for the first 10-year interval.
These are Reactor Coolant System branch connection components that allowed only a single sided examination (pipe side only). Coverage of 100% was achieved from the one side and of both directions on the parallel scan (composite coverage of 75%).
However, because of material properties as discussed in the relief request, the examiners were unable to accomplish an extended beam path to examine from the opposing direction.
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Attachment to ET 96-0027 Page 9 of 26 Comnosite Coverage 64.8% - 2 angles 46.7% - 2 angles /2 directions 100% - 0' Scan Coverare Summary Parallel (2 angles) - 51.3%
Parallel (2 angles /2 directions) - 51.3%
g m.
Perpendicular (2 angles) - 78.2%
18' Nom.
Perpendicular (2 angles /2 directions) - 42.0%
Zero Degree - 100%
Weld RV 101-121 (WM) 1 4
Examination Volume (EV)
)
Coverage Breakdown for Parallel Scans O' - 100 %
45' - 97% WM, 51.3% EV(cw), 51.3% EV(ccw) i 60' - 97% WM, 51.3% EV(cw), 51.3% EV(ccw) 70* - 100% WM, 65.2% EV(cw), 65.2% EV(ccw)
Coverage Breakdown for Perpendicular Scans 0* - 100 %
45' - 58.0% WM(up), 74.8% WM(dn), 48.9% EV(up), 64.5% EV(dn) 60' - 86.9% WM(up), 27.0% WM(dn), 76.8% EV(up), 42.4% EV(dn) 70* - 0% WM(up),100% WM(dn),19.1% EV(up), 78.0% EV(dn)
Figure 1 RV-101-121 Scan Limitations (I2R-03)
.=.._____m.
4 Attachment to ET 96-0027 Page 10 of 26 Distance necessary to completely examine WRV - 14.5" 4
A h ved
.75" Distance Achieved - 5.75" N'
l Cooling Duct Ring 360 Degrees l
,f Exit Point Limitation l
t d
e fe b
y a
abc represents portion of weld not examined in two directions by 45' = 16.8%
ade represents portion of weld not examined in two directions by 60' = 47.3%
FIGURE 2 CH-103-101 Scan Limitation Cooling Ring Limitation i
(I2R-04) 1
j Attechment to ET 96-0027 Page 11 of 26 l Scan Area]
LUG l
Typ of J l
9.7" a :_
l Cil-103-101 l I(
- I I
8" I
Total weld length = 457" Length obstructed by 3 lugs = 24" 24/457 =.0525 = 5.3%
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FIGURE 3 l
CH-103-101 Scan Limitation l
(Lug Limitations only)
(
(IR2R-04)
.=-_. _...._.
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Attachmtnt to ET 96-0027 j
Paga 12 of 26 t
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J Support Flange
)
E E
EBB 01D-SEAM-1-W C+
I Code Data Plate 1
+-- Support Leg Typ of 4 i
Supnort Leg Locations 21" to 45" CCW from Datura N 61 1/4" to 81 1/4" CW from Datum N 38" to 64" CW form Datum N 43" to 67" CCW from Datum N 1
FIGURE 4 j
EBB 01D-SEAM-1-W Limitations (I2R-05) 1
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Attachment to ET 96-0037 Page 13 of 26 Request Item d.
Request for Relief No.
I2R-11 asks for generic relief for vessels when flaws are detected that are determined to be construction related.
Since Wolf Creek is entering its second 10-year interval, the locations of pre-existing flaws should be known.
Provide a list of examination areas containing pre-existing flaws.
In addition, provide detailed drawings and technical justification explaining why each flaw is considered a construction or fabrication flaw versus a service-related flaw.
Response 7;em d.
Rel;4f Request I2R-11 was based on ASME Code Conr.nir tee actions currently in process.
A number of issues a still require resolution.
Therefore, Wolf Creek Nuclear Operating Corporation withdraws Relief Request I2h-11.
Request Item e.
Request for Relief No. I2R-17 seeks relief from pressure test requirements for Class 3 diesel generator support systems.
Describe the burden associated with the Code requirement.
Response Item e.
Relief Request I2R-17 is based primarily on the Technical Specification testing required for operability providing an acceptable level of quality and safety.
The burden associated with pressure testing the subject subsystems is primarily an administrative burden and was not intended to be a large basis for relief.
Therefore, Relief Request I2R-17 has been rewritten without hardship and burden as a basis.
4 In addition, the request contains more detailed information on the testing performed to meet the Technical Specification Surveillance Requirements.
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Attachment to ET 96-0027 Page 14 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST I2R-17 (Page 1 of 4)
COMPONENT IDENTIFICATION Code Class:
3
References:
IWD-2500, Table IWD-2500-1 1
Examination Category:
D-B Item Number:
D2.10
==
Description:==
Alternative Rules For System Pressure Testing of
)
Standby Emergency Diesel Generator Subsystem Components Applicable Components:
Code Class 3 components within the Standby Diesel l
Generator "A"
and "B"
Starting Air, Jacket Cooling j
Water, Intake and Exhaust Air and Fuel Rack Supply Air Subsystems CODE REOUIREMENT i
Table IWD-2500-1, Category D-B requires that a system pressure test per IWD-5222 be performed each inspection period and a system hydrostatic test per IWD-5223 be performed each inspection interval on pressure retaining components.
BASIS FOR RELIEF Pursuant to 10 CFR 50. 55a (a) (3) (i), relief is requested on the basis that the proposed alternatives provide an acceptable level of quality and safety.
Comoonent Damian. Classification and Section XI Aeplicability Due to the safety related function of the Standby Emergency Diesel Generators at WCGS, the components within the Starting Air, Jacket Cooling Water, Intake and Exhaust Air and Fuel Rack Supply Air Subsystems were designed per ASME Section III, Class 3 or equivalent codes and standards based on the criteria in ANSI N18.2, which was used in the design and classification of WCGS systetas and components as a supplement to Regulatory Guide 1.26 criteria. Accordingly, per Technical Specification 4.0.5 Surveillance Requirements, ASME Section XI was employed during the first interval at WCGS.
Standby P==rgency Diesel Generator Testina Recuir== ants a
The applicable testing requirements for these components include those in Technical Specification Surveillance Requirements 4.8.1.1.2 and 4.0.5.
The Surveillance Requirements of 4.8.1.1.2 include extensive operability testing and inspection for the Standby Emergency Diesel Generators (and associated subsystems, components, etc.) at frequencies between 31 days and 10 years.
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Attachm nt to ET 96-0027 Page 15 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN i
J RELIEF REQUEST I2R-17 (Page 2 of 4)
ASME Section YI Testina Reauir-mtg i
The Surveillance Requirements of 4.0.5 include inservice inspection and inservice testing per ASME Section XI.
System pressure testing (at operational pressure) of Code Class 3 components is required to be performed once per inspection period a
(approximately 40 months); and system hydrostatic testing (at pressures above operational) of Code Class 3 components is required to be performed once per inspection interval (10 years) per Table IWD-2500-1 of Section XI.
Code Case N-498-1, which allows system pressure testing to be performed in lieu of hydrostatic testing has been requested for use per 2nd Interval Relief Request
)
Ooerability Testina In Lieu of Section XI Testina l
I The focus of the Technical Specification Surveillance Requirements is,slightly 4
different; 4.8.1.1.2 concentrates on component operability and 4.0.5 (inservice inspection) concentrates on component pressure boundary integrity.
Because I
successful Standby Emergency Diesel Generator operability testing requires the dssociated subsystems such as the Starting Air, Jacket Cooling Water, Intake and Exhaust Air, and Fuel Rack Supply Air to maintain pressure boundary integrity,
)
this operability testing indirectly verifies individual component integrity and is therefore deemed to provide an equivalent level of quality and safety to that of ASME Section XI inspections.
The repeatability of subsystem instrumentation (pressure and temperature) recorded during testing provides supporting data for the " indirect verification j
of component integrity." In addition, operations personnel specifically trained in the design and testing of the Standby Emergency Diesel Generators are aware of 1
the necessity to maintain pressure boundary integrity for certain components and
?
also of the necessity to maintain adequate flow characteristics for open ended components which provide intake air and process exhaust air.
Although not a specific step in the Surveillance Procedure, visual verification of component pressure boundary integrity and adequate flow is an understood responsibility of l
the operations personnel performing Standby Emergency Diesel Generator i
operability testing.
If evidence of leakage or inadequate flow is identified during testing, written notification is forwarded to plant maintens.nce for corrective actions or repairs and follow-up confirmatory testing is performed.
The following paragraphs provide specific procedural actions which support the use of the alternative operability testing in lieu of ASME Section XI System Pressure Testing and VT-2 Visual examination.
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Attachmtnt to ET 96-0027 Page 16 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF I2R-17 (Page 3 of 4)
Starting Air Subsystem Per WCGS Surveillance Procedures STS KJ-005A & B, which are performed monthly, the Standby Emergency Diesel Generators are tested for operability.
As part of these procedures, the pressure of the two starting air tanks for each Standby Emergency Diesel Generator is recorded to assure the associated discharge valves are properly performing their function (thereby satisfying Inservice Testing for valves).
The satisfactory completion of this test also provides a positive indication that the pressure boundary integrity of the Starting Air Subsystem is intact.
In addition, WCGS Surveillance Procedures STS KJ-002A & B, which are also performed monthly, include steps to verify starting air tank pressure at 2, 5,
10 and 15 minute points during the subsystem valve testing.
A pressure drop of 20 psig maximum (from 600 peig, approximately 3.34%)
is allowable to satisfactorily complete the test.
This data also provides a positive indication that pressure boundary integrity is being maintained for the Starting Air Subsystem.
Based on the monthly frequency and data collected during these alternative tests, WCNOC considers that testing performed to satisfy the Technical Specification Surveillance Requirements is an acceptable alternative to Section XI System Pressure Testing.
Jacket Water Coolina Subsystem i
Similar to the Starting Air Subsystem, Jacket Water Cooling pressure and temperature data is recorded every 30 minutes as part of Standby Emergency Diesel j
Generator testing in accordance with Surveillance Procedures STS KJ-005A & B.
Normal values for this data are provided within the procedures as well as limit (s) for the recorded values which provide a means to assess the data recorded. Again, this data provides a positive indication that pressure boundary integrity is being maintained. Based on the monthly frequency and data collected during these alternative tests, WCNOC considers that testing performed to satisfy the Technical Specification Surveillance Requirements is an acceptable alternative to Section XI System Pressure Testing.
Air and Fuel Rack supolv Air Subsystem The air manifold temperature and pressure data associated with the Air and Fuel Rack Supply Air Subsystem is also recorded every 30 minutes as part of Standby Emergency Diesel Generator testing iu accordance with Surveillance Procedures STS KJ-005A & B.
Normal values for this data are provided within the procedures as well as limit (s) for the recorded values which provide a means to assess the data recorded. Again, this data provides a positive indication that pressure boundary integrity is being maintained. Based on the monthly frequency and data collected during these alternative test, WCNOC considers that testing performed to satisfy the Technical Specification Surveillance Requirements is an acceptable alternative to Section XI System Pressure Testing.
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Attachmsnt to ET 96-0027 Paga 17 of 26 WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUESI I2R-17 (Page 4 of 4)
Int;ake and avhmust Air Subsystem Adequate flow of the Intake and Exhaust Air Subsystem is demonstrated by successfully operating the Standby Emergency Diesel Generators during testing.
Specifically, the intake air vacuum data in inches of water is recorded every 30 minutes as part of Standby Emergency Diesel Generator testing in accordance with Surveillance Procedures STS KJ-005A &
B.
This data provides a positive indication that proper flow is being maintained and in turn proper exhaust flow is also being maintained.
WCNOC considers that testing peric,rmed to satisfy the Technical Specification Surveillance Requirements is an acceptable alternative to Section XI System Pressure Testing.
Per Surveillance Requirement 4.8.1.1.2.g, each Standby Emergency Diesel Generator is subjected to an inspection in accordance with procedures prepared per the manufacturer's recommendation.
The inspections performed per this procedure govide additional assurance that the components within the Starting Air, Jacket Cooling Water, Intake and Exhaust Air, and Fuel Rack Supply Air subsystems demonstrate pressure boundary integrity and the ability to provide adequate flow for satisfactory Standby Emergency Diesel Generator Operation.
Based on the information provided, WCNOC requests relief from the Section XI requirements to perform system pressure testing on the Code Class 3 Standby Emergency Diesel Generator subsystems listed above on the basis that Technical Specification Surveillance Requirements of 4.8.1.1.2 provide an acceptable level j
of quality and safety.
PROPOSED ALTERNATE EXAMINATION WCNOC will implement the operability testing of Technical Specification Surveillance Requirement 4.8.1.1.2 in lieu of ASME Section XI System Pressure Testing.
PERIOD FOR WHICH RELIEF IS REQUESTED Relief is requested for the second inspection interval, September 3, 1995 through September 2, 2005.
i Attachmtnt to ET 96-0027 Page 18 of 26 Request Item f.
Provide a list of the ultrasonic calibration standards being used during the second 10-year ISI interval at Wolf Creek Generating Station.
This list should include the calibration standard identifications, material specifications, sizes, the applicable component, and any variance from Code requirements.
1 Response Item f.
As discussed during the April 24, 1996, telecon, provision of this information on a component by component basis would be voluminous; therefore, it was agreed that 1
a table listing the
- blocks, block specification information, and Code Categories / Item Numbers that the components that utilize the itemized block applies too.
Table I lists the calibration standards required for the ultrasonic (UT) examinations scheduled in the Second Interval Inservice Inspection Program Plan.
The calibration standard design and material selection is in accordance with-Subarticle III-3400 of Appendix III of ASME Section XI.
Nomenclature definitions for the listed calibration blocks follow Table I.
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Attachment to ET 96-0027 Paga 19 of 26 TABLE I i
WCGS CALIBRATION STANDARDS BLOCK DESCRIPTION / TITLE APPLICABLE CATEGORY (S) /
l NUMBER ITEM NUMBER (S) i 101 WC-03-PS-03.000-SA533-GR.A-CL-2-CSCL-B-B/B2.11 i
101 B-B/B2.12 l
l B-D/B3.110 B-D/B3.120 102 WC-03-SG-03.000-SA533-GR.A-CL-2-CS-102 C-A/C1.10 C-A/C1.20 C-A/C1.30 4
)
C-B/C2.21 C-B/C2.22 104 WC-5.0-SG-05.035-SA216-WCCA-CSCL-104 B-B/B2.40 B-D/B3.140 105 WC-29-XXX-02.33-SA351-CF8A-CCSS-105 B-J/B9.11 106 WC-27 1/2-XXX-02.21-SA351-CF8A-CCSS-106 B-J/B9.31
)
108 WC-E-28-0.934-28-0.934-LR-ST-SA234-WPC-C-F2/C5.51 CS-108 USAR/3.6.2
]
110 WC-S-2.5-14-SA193-GR.B7-CS-110 C-D/C4.40 111 WC-03-40S-00.216-SA312-TP304-SS-111 USAR/3.6.2 f
112 WC-03-160-00.438-SA312-TP304-SS-112 C-F-1/C5.21 j
USAR/3.6.2 i
113 WC-04-160-00.531-SA508-CL.2-CS-113 USAR/3.6.2 114 WC-04-160-00.531-SA312-TP304-SS-114 B-J/B9.11 C-F-1/C5.21
]
115 WC-04-160-00-531-SA106-GR.B-CS-115 USAR/3.6.2 l
116 WC-14-080-00.750-SA106-GR.B-CS-116 C-F-2/C5.51
)
USAR/3.6.2 I
j' C-F-1/C5.11 117 WC-06-160-00.719-SA312-TP304-SS-117 B-J/B9.11 118 WC-12-140-01.125-SA312-TP304-SS-118 B-J/B9.11 B-J/B9.31 C-F-1/C5.11 119 WC-14-120-01.094-SA106-GR.B-CS-119 USAR/3.6.2 l;
120 WC-10-140-01.000-SA376-TP304-SS-120 B-J/B9.11 121 WC-10-140-01.000-SA312-TP304-SS-121 B-J/B9.11 i
122 WC-10-140-01.000-SA358-TP304-CL.1-SS-B-J/B9.11 122 C-F-1/C5.11 C-F-1/C5.12 123 WC-10-080-00.594-SA333-GR.6-CS-123 C-F-2/C5.51 f
USAR/3.6.2 5
124 WC-14-120-01.094-SA333-GR.6-CS-124 USAR/3.6.2 0
126 WC-12-140-01.125-SA376-TP304-SS-126 B-J/B9.11
}
127 WC-14-120-01.094-SA508-CL.1-CS-127 USAR/3.6.2 l
129 WC-12-080-00.688-SA333-GR.6-CS-129 C-F-2/C5.51 USAR/3.6.2 130 WC-14-160-01.406-SA376-TP316-SS-130 B-J/B9.11 4
131 WC-16-080-00.844-SA106-GR.B-CS-131 C-F-2/C5.51 4
132 WC-28-01.500-SA106-GR.B-CS-132 USAR/3.6.2 134 WC-28-XX1-01.500-SA155-KCF70-CL.1-CS-C-F-2/C5.51 134 135 WC-28-XX1-00.934-SA155-KCF70-CL.1-CS-USAR/3.6.2 135 i
1
I
/
Attachment to ET 96-0027 Page 20 of 26 TABLE I Continued WCGS CALIBRATION STANDARDS BLOCK DESCRIPTION / TITLE APPLICABLE CATEGORY (S)/
i NUMBER ITEM NUMBER (S) l 136 WC-32-XX1-01.292-SA155-KCF70-CL.1-CS-136 C-F-2/C5.51
)
C-F-2/C5.52 137 WC-B-3.0-17-SAS40-GR.B23-CL.4-CS-137 USAR/3.6.2 140 WC-N-7.0-7.99-SA540-GR.B24-CL.3-CS-140 B-G-1/B6.40 141 WC-B-4.5-31.5-SAS40-GR.B24-CL.4-CS-141 B-G-1/B6.180 144 WC-2.0-HPCI-02.000-SA240-TP304-SS-144 C-A/C1.20 C-B/C2.21 145 WC-31-XXX-02.24-SA351-CF8A-CCSS-145 B-J/B9.11 148 WC-10-080-00.594-SA106-GR.B-CS-148 USAR/3.6.2 152 WC-F-05-01.440-SA105-CL1500-CS-152 USAR/3.6.2 155 WC-S-7.0-58-SA540-GR.B24-CL 3-CS-155 B-G-1/B6.30 156 WC-02-160-00.344-SA312-TP304-SS-156 USAR/3.6.2 157 WC-03-80S-00.300-SA312-TP304-SS-157 USAR/3.6.2 159 WC-04-080-00.337-SA106-GR.B-CS-159 USAR/3.6.2 161 WC-E-04-080-04-080-LR-ST-SA234-WPB-CS-161 USAR/3.6.2 162 WC-04-080-00.337-SA234-WPB-CS-162 USAR/3.6.2 163 WC-04-080-00.337-SA105-CS-163 USAR/3.6.2 165 WC-R-10-080-08-080-C-SA234-WPB-CS-165 USAR/3.6.2 166 WC-03-040-00.216-SA105-CS-166 USAR/3.6.2 l
~
168 WC-28-MS-01.520-SA508-CL.1-CS-168 USAR/3.6.2 169 WC-NSE-04-160-SA508-CL.2-04-160-SA182-B F/B5.40 F316L-BI-169 170 WC-NSE-06-160-SA508-CL.2-06-160-SA182-B-F/B5.40 F316L-BI-170 171 WC-NSE-14-160-SA508-CL.2-14-160-SA182-B -F/B5.4 0 F316L-BI-171 172 WC-00.875-RHR-00.750-SA240-TP304-SS-172 C-A/C1.10 173 WC-14-080-00.750-SA333-GR.6-CS-173 C-F-2/C5.51 USAR/3.6.2 175 WC-11-RPV-11-SA533-GR.B-CL.1-ASCL-175 B-A/Bl.11 B-A/Bl.12 B-A/Bl.30 B-D/B3.90 176 WC-9-RPV-9-SA533-GR.B-CL.1-ASCL-176 B-A/Bl.11 B-A/Bl.12 B-A/Bl.21 B-A/Bl.40 177 WC-7-RPV-7-SA533-GR.B-CL.1-ASCL-177 B-A/Bl.21 B-A/Bl.22 178 WC-F-XX-33-SA533-GR.B-CL.1-ASCL-178 B-D/B3.90 179 WC-NSE-XXX-3-SA182-GR316-CL.XX-XXX-3-SA508-B-D/B3.90 GR.XX-CL2-BI-179 B-D/B3.100 B-F/B5.10 180 WC-F-06-00.562-SA105-CL900-CS-180 USAR/3.6.2 181 WC-06-40S-00.280-SA312-TP304-SS-181 C-F-1/C5.11 C-F-1/C5.12 USAR/3.6.2 182 WC-24-STD-00.375-SA312-TP304-SS-182 C-F-1/C5.11 183 WC-12-STD-00.375-SA312-TP304-SS-183 C-F-1/C5.11
!' i Attachm:nt to ET 95-0027 Page 21 of 26 l
TABLE I Continued WCGS CALIBRATION STANDARDS BLOCK DESCRIPTION / TITLE APPLICABLE CATEGORY (S) /
NUMBER ITEM NUMBER (S) 184 WC-14-STD-00.375-SA312-TP304-SS-184 C-F-1/C5.11 189 WC-16-STD-00.375-SA312-TP304-SS-189 C-F-1/C5.11 1
~
s 4
/
Attschmtnt to ET 96-0027 Page 22 of 26 CALIBRATION BLOCK IDENTIFICATION SYSTEM 1.
Vessels E - H - 202 - XX. XXX - SAXXX - GRXXX - CLXX - M - M 1
2 3
4 5
6 7
8 9
1:
WC - Wolf Creck plant specific designation 2:
Nominal Plate Thickness 3:
Vessel from which obtained; use following abbreviations:
j RHR - Residual Heat Removal Heat Exchanger RPV - Reactor Pressure Vessel SG - Steam Generator PS -
Pressurizer HPCI -
Boron Injection Tank ACC - Accumulator Safety Injection Tank MS - Main Steam 4:
Measured thickness to nearest thousandth of an inch 5:
Material SA designation 6:
Material grade designation 7:
Material class designation 8:
Material - use abbreviations listed in II below 9:
Unique number (101,
- 102, 103, etc.) as assigned to each calibration standard from the master list II.
Piping E - E - 2Q2 - XX XXX SAXXX - GRXXX - CLXXX M-M 1
2 3
4 5
6 7
8 9
1:
WC - Wolf Creek plant specific designation 2:
Nominal pipe size j
3:
Pipe schedule i
4:
Measured pipe wall thickness to the nearest thousandth of an inch (average of at least two measurements) 5:
Pipe material SA designation 6:
Pipe material grade designation 7:
Pipe material class designation, if appropriate 8:
Pipe material - use abbreviations as follows:
- Carbon or Alloy Steel CSCL - Carbon Steel with Stainless Steel Cladding CSS
- Cast Stainless Steel IN - Inconel AL - Aluminum SS - Stainless Steel ASCL
- Alloy Stainless Steel with Stainless Steel Cladding 9:
Unique number (101,
- 102, 103, etc.)
assigned to each calibration standard from the master list.
/
Attachment to ET 96-0027 Page 23 of 26 III Fittings A. Elbow E -E - H - E - H - H - H - H - SAXXX - GRXXX. CLXXX - H - H 1
2 3
4 5
6 7
8 9
10 11 12 13 1:
WC - Wolf Creek plant specific designation 2:
"E" denotes elbow 3:
Nominal pipe size of first (either) end 4:
Pipe schedule or measured wall thickness of first end 5:
Nominal pipe size of second (other) end 6:
Pipe schedule or measured wall thickness of second end 7:
"SR" if elbow is standard radius "LR" if elbow is long radius 8:
"ST" if elbow is standard tangent "LT" if elbow is long tangent 9:
Material SA designation 10: Material grade designation 11: Material class designation 12: Material I - use abbreviations listed in II above 13: Unique number (101,
- 102, 103, etc.)
assigned to each calibration standard from the master list B. Tees E - I - n - n - n - H - SAXXX - GRXXX. CLXXX - M - M 1
2 3
4 5
6 7
8 9
10 11 1:
WC - Wolf Creek plant specific designation 2:
"T" denotes use 3:
Nominal pipe size of main tee portion 4:
Pipe schedule / measured wall thickness of main Lee portion 5:
Nominal pipe size of branch part of tee 6:
Pipe schedule of measured wall thickness of branch part of tee 7:
Material SA designation 8:
Material grade designation 9:
Material class designation 10: Material - use abbreviations listed in II above 11: Unique number (101,
- 102, 103, etc.)
assigned to each calibration standard from the master list
_ -...- ~ _.__.-.. - -. ~ -
/
Attachm:nt to ET 96-0027 Paga 24 of 26 i
l C: Reducers l
E - E - XX - XX - XX - XX - X - SAXXX - GRXXX CLXXX - XX - XX 1
2 3
4 5
6 7
8 9
10 11 12 l
1:
WC - Wolf Creek plant specific designation l
2:
"R" denotes reducer 3:
Nominal pipe size of larger end l
4:
Pipe schedule or measured wall thickness of larger end 5:
Nominal pipe size of 3maller end 6:
Pipe schedule or measured wall thickness of smaller end 7:
"C" if reducer is concentric I
"E" if reducer is eccentric 8:
Material SA designation 9:
Material grade designation l_
10: Material class designation 11: Material - use abbreviations listed in II above 12: Unique number (101, 102, 103, etc.) as assigned to each calibration standard from the master list D.
Flanges E - E - XX - XX - SAXXX - GRXXX. CLXXX - XX - XX 1
2 3
4 5
6 7
8 9
i i
1:
WC - Wolf Creek plant specific designation 2:
"F" denotes flange 3:
Nominal pipe size 4:
Pipe schedule or measured wall thickness 5:
Material SA designation 6:
Material grade designation 7:
Material class designation 8:
Material - use abbreviations per II above 9:
Unique number (101, 102, 103, etc.) as assigned to each Calibration Standard from the master list E. Weldolets l-E - XXX - XX - XX.XXX - SAXXX CLXXX - XX - XX i
l 1
2 3
4 5
6 7
8 1:
WC - Wolf Creek plant specific' designation 2:
Nominal size - third digit optional 3:
Schedule i-4:
Measured wall thickness to nearest thousandth of an inch
)
(average of at least two measurements) 5:
Material SA designation 6:
Material - use material listed in II above l
7:
Unique number (101,
- 102, 103, etc.)
assigned to each calibration standard from the master list
.'E t
Attachment to ET 96-0027 i
Page 25 of 26 IV.
Bolting I
E - X - X - XX - SAXXX - GRXXX CLXXX - XX - XX 1
2 3
4 5
6 7
8 9
i 1:
WC - Wolf Creek plant specific designation i
2:
"N" if a nut "B"
if a bolt "S"
if a stud 3:
Nominal diameter 4:
Nominal length 5:
Material SA designation 6:
Material grade designation 7:
Material class designation 8:
Material - use abbreviations listed in II above 9:
Unique number (101, 102, 103, etc.)
as assigned to each calibration standard from master list V.
Bimettalics E -HSE - XXX - XXX - SAXXX - GRXXX CLXXX - XX - XXX - SAXXX -
1 2
3 4
5 6
7 8
9 10 GRXXX CLXXX - HI - XX 11 12 13 14 1
WC - Wolf Creek plant spec 2fic designation 2:
NSE - To denote nozzle to safe end 3:
Nominal pipe size of first (either) end 4:
Pipe schedule or measured wall thickness of first end j
5:
Pipe material SA designation of first end i
6:
Pipe material grade designation, if appropriate 7:
Pipe material class designation, if appropriate 8:
Nominal pipe size of second (other) end j
9:
Pipe schedule or measured wall thickness of second end.
10: Pipe material SA designation of second end
- 11. Pipe material grade designation if appropriate 12: Pipe material class designation if appropriate 13: BI - To denote Bimetallic 14: Unique number (101,
- 102, 103, etc.) as assigned to each calibration standard from the master list
4 Attachmint to ET 96-0027 Paga 26 of 26 Request Item g.
Please verify that there are no additional relief requests, other than those submitted on August 30, 1995.
If additional relief requests are required, the licensee should submit them for staff review.
Response Item g.
Relief Requests 12R-19 and I2R-20 are submitted in response to previous items.
No additional relief requests are identified for submittal with the Second Interval Inservice Inspection Program Plan.
4 i
i l
e
/
CASE N-509 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: November 25,1992 See Numeric Index for expiration and any reaffirmation dates.
Case N 509 1.1 Exemption Criteria Alternative Rules for the Selection and Examinalon (a) The exemption criteria provided in IWB 1220, of Class 1,2, and 3 Integrally Welded Attachments IWC-1220, and IWD-1220 may be applied to ClassSection XI, Division 1 1,2, and 3 components respectively, with integrally welded attachments, required to be examined in ac-Inquhy: What alternative requirements to those of cordance with Table 2500-1.
IWB, IWC, and IWD may be used to select and (b) Class 1,2, and 3 integrally welded attachment examine integrally welded attachments?
examinations performed as a result of component support deformation cannot be credited under the Reply: It is the opinion of the Committee that the req rements of N2m or N242, IWC2m
' Tc5Pec-following rules may be used to select and examine integrally welded attachments:
- y,jY' (a) This Case is limited to Examination Categories B-H, B-K-1, C-C, D-A, D-B, and D-C.
1.2 Inspection Schedule (b) Class 1,2, and 3 component supports shall be selected for examination m accordance with IWF of Class 1,2, or 3 integrally welded attachments se-the 1989 Edition with the 1990 Addenda.
lected for examination by sample selection criteria in accordance with Table 2500-1, Examination Cate-(c) Except for the selection of component supports for examination, all references to Section XI within gories B-K, C-C, and D-A, shall meet the require-this Case shall be from the edition and addenda spec-ments of IWB-2411 or IWB-2412, IWC-2411 or ified in the Owner's Inservice Inspection Program.
IWC-2412, or IWD-2411 or IWD-2412, repectively.
1.3 Additional and Successive Examinations 1.0 SCOPE (a) Class 1,2, and 3 additional and successive ex-amination requirements of IWB 2430 and IWB-2420 These requirements apply to examination and for Class 1, IWC-2430 and IWC 2420 for Class 2 and sample selection of Class 1,2, and 3 integrally welded 3 as applicable, shall be applied to integrally welded attachments of vessels, piping, pumps, and valves attachments whose examinations reveal flaws or rel-listed in Table 2500-1 as follows:
evant conditions that exceed the acceptance stan-(a) Table 2500-1, Examination Category B-K shall dards of IWB-3000, IWC-3000, and IWD-3000, re-be used for Class 1 integrally welded attachments in spectively.
Examination Categories B H and B K 1 of IWB.
(b) When integrally welded attachments are ex-(b) Table 2500-1, Examination Category C-C shall amined as a result of identified component support be used for Class 2 integrally welded attachments in deformation and the results of these examinations Examination Category C-C of IWC.
exceed the applicable acceptance standards listed (c) Table 2500-1, Examination Category D-A shall above, additional or successive examinations shall be be used for Class 3 integrally welded attachments in performed when determined necessary based on an Examination Categories D-A, D-B, and D C of IWD.
evaluation by the Owner.
985 l
th -
- zg a
g UI m Q8 TABLE 2500-1 EXAMINATION CATEGORIES iL EXAMINATION CATEGORY B-K, INTEGRAL ATTACHMENTS FOR CLASS 1 VESSELS, PIPING, PUMPS, AND VALVES g-Examination Item Requirements /
Examination Acceptance Extent of Frequency of v.
No.
Parts Examined
- Fig. No.
Method Standard Examination *3 Examination
- B10.10 Pressure Vessels IWB-2500-13, Surface' IW8-3516 100% of required areas of each Each idmtified occurrence and Integrally Welded
-14, and -15 welded attachment each inspection intervat*
h Attachments a
810.20 Piping IWB-2500-13, Surface IWB-3516 100% of required areas of each Each identified ecs.o
.J and g
Integrally Welded
-14, and -15 welded attachment each inspection interval'
8 N
.I Attachments x
M B10.30 Pumps IWB-2500-13, Surface IWB-3516 100% of required areas of each Each identified occurrence and asO Integrally Welded
-14, and -15 welded attachment each inspection intervag.
Attachments g'
810A0 Valves IWB-2500-13, Surface IWB-3516 100% of required areas of each Each identified occurrence and Integrally Welded
-14, and -15 welded attachment each inspection interval
- Attachrnents NOTES:
(1) Examination is limited to those integrally welded attachments that meet the following conditions:
(a) the attachment is on the outside surface of the pressure retaining w h
(b) the attachment provides carryonent support as defined in NF-1110; and (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the cornponent.
En (2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.
En (3) Selected sarryles of integrally welded attachments shall be examined each inspection interval (4) In the case of multiple vessels of similar deM function and service, only one integrally welded attativnent of only one of the multiple vessels shall be selected for examination.
h (5) For piping, pumps, and valves, a sangle of 10% of the welded attachments associated with the -
--% supports selected for examination under the 1990 Addenda, IWF-2510 shall tus be examined.
(6) Examination is required whenever component support member deformation (e.g., broken, bent, or pulled out parts) is identified during operation, refueling, malmenance, examination, inservice inspecting or testing.
(7) For the configuration shoum in Fig. IWS-2500-14, a volumetric examination of volume A-B-C-D from side (8-C) of the circumferential welds may be performed in lieu of the surface examination of surfaces A-D and 8-C.
E.
TABLE 2500-1(CONT'D)
EXAMINATION CATEGORIES EXAMINATION CATEGORY C-C, INTEGRAL ATTACHMENTS FOR CLASS 2 VESSELS, PtPING, PUMPS, AND VALVES Erasnination Item Requiressents/
Erasnination Acceptance Extent of Frequency of No.
Parts Erasnined' Fig. No.
Method Standard Exasninationu Exasnination*
{
C3.10 Pressure Vessels IWC-2500-5 Surface IWC-3512 100% of required areas of each Each identified occurrence and integrally Welded welded attachment each inspection interval
- Attachments m
C3.20 Piping IWC-2500-5 Surface IWC-3512 100% of required areas of each Each identified occurrence and g
welded attachment each inspection interval
- is Integrally Welded M
Attachments O
C3.30 Pumps IWC-2500-5 Surface IWC-U12 100% of required areas of each Each identified occurrence and h
welded attachment each inspection interval' 28 Integrally Welded Attachments C3.40 Valves IWC-2500-5 Surface l'WC-3512 100% of required areas of each Each identified occurrence and welded attachment each inspection interval
- M Integrally Welded Attachments NOTES:
s (1) Examination is limited to those integrally welded attaciments that meet the following conditions:
y ra (a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component sgport as defined in NF-1110; and (c) The attachment weld joins the attachment either directly to the surface of the cornponent or to an integrally cast cr forged attachment to the component.
O (2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.
M (3) Selected samples of integrally welded attachments shall be examined each inspection interval (4) In the case of multiple vessels of similar design, function and service, only one integrally welded attachment of only one of the multiple vessels shall be selected for examination.
(5) For piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under the 1990 Addenda, IWF-2510 shall be examined.
(6) Examination is required whenever component support member deformation (e.g., broken, bent, er pullets out parts) is identified during operation, refueling, maintenance, examination, O
inservice inspection, or testing.
3D en ITI E
Z$
di 5 oa m-
- e 4
"S.
zg 8
W UI m TABLE 2500-1 (CONT'D)
O -Q EXAMINATION CATEGORIES g
EXAMINATION CATEGORY D-A, INTEGRAL ATTACHMENTS FOR CLASS 3 VESSELS, PIPING, PUMPS, AND VALVES b
- 3 Examination j
Item Requirements /
Examination Acceptance Extent of Frequency of c.
No.
Parts Examined
- Fig. No, Method Standard Examinationu Examinationu D1.10 Pressure Vessels IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of each Each identified c,ccurrence and Integrally Welded welded attachment each inspection interval Attachments 01.20 Piping IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of each Each identified occurrence and Integrally Welded welded attachment each inspection interval h
Attachments g
a 01.30 Pumps IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of each Each identified occurrence and
[
Integrally Welded welded attachment each inspection interval o
Attachments p
lC 01.40 Valves IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of each Each identified occurrence and g
,g Int *grally Welded welded attachment each inspection interval o
N Attachments N
NOTES:
d (1) Examination is limited to those integrally welded attachments that meet the following conditions:
(a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-1110; and y
(c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the corgonent.
(2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.
p (3) Selected samples of integrally welded attachments shall be examined each inspection interva!. All integrally welded attachments selected for examination shall be subject to corrosion, as n
determined by the Owner, such as the integrally weld =d attachments of the Service Water or Emergency Service Water systems. In the case of nwitiple vessels of similar design, o
function and service, the integrally welded attachments of only one of the multiple vessels shall be selected for examination. For integrally welded attachments of piping, pumps, and valves a 10% sample shall be selected for examination. This percentage,& nple shall be proportional to the total number of nonexempt integrally welded attachments connected to the piping, pumps, and valves, located within each system subject to these exrminations.
(4) Examination is required whenever coneonent support member deformation (e.g., broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examination, inservice inspection, or testing.