ML20154N150
| ML20154N150 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/03/1986 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Berkow H Office of Nuclear Reactor Regulation |
| References | |
| P-86105, TAC-59787, NUDOCS 8603170215 | |
| Download: ML20154N150 (112) | |
Text
h PublicService m..
Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 March 3, 1986 Fort St. Vrain Unit No. 1 P-86105 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Mr. H. N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Inservice Inspection of High Energy Piping, Final Report
REFERENCES:
- 1. NRC letter, Denton to Walker, dated 2/7/86 (G-86062)
- 2. PSC letter, Walker to Berkow, dated 12/10/85 (P-85460)
- 3. NRC Policy Issue SECY 85-370 dated 11/22/85 (G-85488)
Dear Mr. Berkow:
Attached for your information is the final report on the Inservice Inspection program which PSC recently performed on the high energy piping at Fort St.
Vrain (FSV).
As discussed in the Safety Evaluation of Confirmatory Item 6, Inservice Inspection (Enclosure 6 to Reference 1),
this program inspected 35 critical areas of FSV's high energy piping, and verified the integrity of this piping in support of 35 percent power operation.
If you have any questions concerning this inspection, please contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, f
kh $$ 67 D. W. Warembourg, WMaetager 0 W AEn d G
PDR Nuclear Engineering Division i
Of DWW/SWC/ paw y'(
q 1
FORT ST. VRAIN LIMITED INSPECTION PLAN FOR HIGH ENERGY PIPING AS DEFINED UNDER EQ PROGRAM CONFIRMATORY ACTION 6 e
E TABLE OF CONTENTS.
Section 1:
INSPECTION PROGRAM Program Definition and Purpose Inspection Criteria Examination Point Selection Criteria Nondestructive Examination Methods Evaluation Criteria Section 2:
PROGRAM OBJECTIVES Selected Inspection Areas Nondestructive Examination Procedures Nondestructive Examination Personnel Inspection Preparation Section 3:
INSPECTIONS PERFORMED Points Examined and Comparison to Areas Selected Inspection Personnel Repairs Results Section 4:
CONCLUSIONS :
NONDESTRUCTIVE EXAMINATION PROCEDURES :
IS0 METRICS
I SECTION 1 INSPECTION PROGRAM
I i
Program Definition and Purpose The purpose of the program was to provide Augmented Inservice Inspection, of Category D (ANSI B31.1, 1967), high energy, secondary cooling systems at FSV. The inspections were designed to determine the present condition of these systems by random sampling and thereby confirm that no inservice induced deterioration has occurred. The original construction code (ANSI B31.1, 1967) which is the basis for system quality was not intended to be an inservice inspection code and did not provide volumetric inspection baseline standards except for field weld radiographs.
Therefore, ASME Section XI " Rules for Inservice Inspection of Nuclear Power Plant Components" 1980 Edition up to and including Winter 81 Addenda, was selected as guidance for the formulation of the nondestructive examination methods and procedures, including initial evaluation of inspection results.
The purpose of the inspection was to fulfill the requirements of Confirmatory Action 6 (Reference G-85488, Enclosure 1) in support of the FSV 35 percent power cperation during the Environmental Qualification schedule extension period, i.e.,
verify the current integrity of FSV's high energy piping.
Inspection Criteria Inspections will be performed in accordance with approved FSV inspection procedures (Attachment 1).
Examination Point Selection Criteria Examination points are selected to be representative of the various possible combinations of high energy systems, piping fabrication methods, materials of construction, and degradation phenomena as follows:
Systems: Main Steam (MS)
( FW)
Hot Reheat (HRH)
Cold Reheat (CRH)
Fabrication Methods: Seamless Hollow Forged Welded Plate Material Composition:
2-1/4% Cr - 1% Mo ASTM A335 Gr P22 2-1/4% Cr - 1% Mo ASTM A155 (A691) 2-1/4% Cr - 1% Mo ASTM A234, WP22 2-1/4% Cr - 1% Mo ASTM A182, F22 Carbon Steel A106, GR A or B Carbon Steel, A155 Carbon Steel, A234, WPB or WPC Degradation Phenomena: Thermal Fatigue Mechanical Fatigue Corrosion Erosion Page 1
f.
h An example of the process used in the selection of examination points for the main steam system is as follows:
Table 2A indicates that the main steam system piping has two types of fabrication, seamless and hollow forged and one type of material, 2-1/4% Cr - 1% Mo A335.
Combining this with the four degradation phenomena results in eight examination points for the main steam system piping. The examination points for the other three systems were selected in this manner except for feedwater where corrosion is not considered to be a contributing factor, since feedwater piping normally remains solid with deoxygenated water during plant shutdown.
All welds uncovered at the examination point were examined which provided a total of 85 examinations.
The following information is presented to demonstrate how the effects of the degradation phenomena are factored into the selection of the examination points.
Thermal Fatigue - Thermal fatigue is caused by the stresses created by thermal expansion and contraction as the pipe heats up and cools down. The critical areas are assumed to be those that see high stress values during each thermal cycle. These areas were identified using the thermal stress analyses for each system.
Mechanical Fatigue - The mechanical fatigue suffered by the pipe material is caused primarily by the continuous low amplitude vibration from fluid flow and equipment operation.
Since this type of cyclic stress analysis was not required for this vintage plant, the assumption is made that the response of the pipe to small vibrations is similar to the response to large vibrations such as those created by seismic events.
Using this basis, the critical areas for mechanical fatigue were selected based on the high stress areas in the Operating Basis Earthquake (OBE) analysis for each system.
The high purity and low oxygen content of the Corrosion water in the high energy piping systems result in a very low rate of generalized corrosion.
The primary concern was in identifying areas of localized corrosion of critical areas in which water may pocket during shutdown conditions.
Pipe low points and potential water pockets were identified as inspection points by reference to the isometric drawings showing the piping arrangement.
Page 2 L
I l
Erosion Erosion damage to the pipe can be caused by a number of mechanisms. Those of concern wera from water velocity and cavitation in the feedwater system, entrained water in the cold reheat system, entrained water downstream l
of desuperheaters, and solid particles in the main steam and hot reheat systems.
Regardless of mechanism, the areas of the pipe subject to erosion are primarily where changes in direction occur.
Inspection points were then selected by referring to the isometric for each system.
Creep Rupture - Note that creep rupture was not considered in the selection of examination points. The reason for this is that creep damage is a function of the time spent at temperature while under stress. The allowable stress levels established by the design codes are intended to limit creep damage to acceptable levels over the total design life of the plant. Variations in material properties and operating conditions have made advisable the examination of piping in older units for creep damage.
Since the estimated operating time at temperature for the main steam and hot reheat lines is less than two years, which is a small fraction of the plant design life, creep rupture was not considered a significant concern at this time.
Nondestructive Examination Methods t
The three types of examinations used during the implementation of this inspection plan, are defined as visual, surface, or volumetric.
The examination method (s) used is specified in (Standards for Examination Category,) " Examination Categories," table, below.
Visual Examination The visual examination was conducted to determine the condition of the part, component, or surface examined, including such conditions as cracks, wear, corrosion, erosion, or physical damage on the surface of the part or components.
Surface Examination A surface examination indicates the presence of surface cracks or discontinuities.
This method was conducted by either magnetic particle examination in accordance with Article 7 of ASME Section V, or liquid penetrant examination in accordance with Article 6 of ASME Section V.
Volumetric Examination A volumetric examination indicates the presence of discontinuities throughout the volume of material and was conducted by radiography in accordance with Article 2 of ASME Section V,
or by ultrasonic l
examination, in accordance with Appendix III of ASME Section XI.
Calibration standards employed during ultrasonic examinations comply with the design requirements of Appendix III of ASME Section XI.
l Page 3
r-Standards for Examination Categories The high energy piping covered under this inspection program is classified as Piping Design Class "D" in accordance with ANSI B31.1, (1967), Power Piping Code, and associated errata correction.
It is therefore, not subject to the conditions of Quality Group A, B, or C as defined by ASME Section III or Section XI, Divisions 1 or 2.
However, in order to maintain the equivalent safety margin of the acceptance standards of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, PSC applied the examination categories under Table IWC-2500-1:
Examination Categories l
EXAMINATION CATEGORY C-F, PRESSURE RETAINING WELOS IN PIPING l
l l
l Examin.
l l
l l
l ITEM l l Require./ l Examin.
l Accept. l Extent Of l
l No. l Parts Examined l Fig. No.. l Method l Standard l Examination l
lC5.11lCircumferential lIWC-2500-7 l Surface lIWC.iOOO l100% of each l l
l Weld l
l l
l weld requiring l l
l l
l l
l examination l
l l
l l
l l
l lC5.12l Longitudinal lIWC-2500-7 ISurface lIWC-3000 l2.5t - at the l l
l Weld l
l l
l intersecting l
l l
l l
l l circum. weld l l
l l
l l
l l
lC5.20l Piping Welds >1/2l l
l l
l l
l in. Nominal l
l l
l l
l l Wall Thickness l
l l
l l
l l
l l
l l
l lC5.21lCircumferential lIWC-2500-7 l Surface lIWC-3000 l100% of each l l
l Weld l
land l
l weld requiring l l
l l
l Volumetric l lexanination l
l l
l l
l l
l lC5.22l Longitudinal Weld lIWC-2500-7 l Surface lIWC-3000 l2.5t - at the l l
l l
land l
l intersecting l l
l l
l Volumetric l l circum, weld l l
l l
1 l
l l
lC5.30l Pipe Branch l
l l
l l
l l Connections >4 l
l l
l l
l l in. Nominal l
l l
l l
l l Branch Pipe Sizel l
l l
l l
l l
l l
l 1
lC5.31lCircumferential lIWC-2500-9 l Surface lIWC-3000 l100% of each l l
l Weld lto -13, l
l l weld requiring l l
l l inclusive l
l l examination l
l l
l l
l l
1 lC5.32l Longitudinal Weld lIWC-2500-12l Surface lIWC-3000 l2.5t - at the l l
l land -13 l
l l intersecting l
l l
l l
l l circum. weld i Page 4
r The selected components were be examined by the nondestructive method described under Nondestructive Examination Methods section in this program, to the extent as specified by the preceding categories.
Evaluation Criteria As stated in the " Standards for Examination Categories" Section of this Plan, the high energy piping required for inspection is classified as Piping Design Class "D" in accordance with ANSI B31.1, (1967), Power Piping Code.
This piping, therefore, was not subject to the inspection requirements required for Quality Group A, B, or C as defined by ASME Section III or Section XI, Divisions 1 or 2.
- However, since codes governing the inservice inspection of Class "D" piping do not exist, PSC utilized ASME Section XI as guidance for this augmented Inspection Plan. This transition from Class "0" to the ASME Section XI classification created the need for PSC to revise procedures for these inspections.
Additionally, construction system design did not consider ASME Section XI examination requirements nor provide baseline inspections; therefore, the examinations were performed to the extent practical to comply with the intent of the inservice inspection code (ASME,Section XI).
PSC did not perform any surface reconditioning of weld crowns since this would have decreased traceability to the original construction records, i.e., radiography.
Evaluation for continuation of service and acceptance of components was in accordance with the original construction code, ANSI B31.1, with consideration given to the applicable ASME Section XI Flaw Indication Standard (s) as guidance.
Page 5
r SECTION 2 PROGRAM OBJECTIVES i
l l
Page 6 t
Selected Inspection Areas The inspection areas selected, including selection factors, are listed on Table 2A. Marked up isometric drawings of the inspection areas are contained in Attachment 2.
Also included are isometric drawings which identify the hot and cold reheat, welded plate piping by cross-hatching on drawings 11A-154, 11A-155, 11A-156, 11A-161, 11A-162, 11A-163, 11A-164, 14A-87, and 14A-88.
Page 7
TABLE 2A l DRAWING l l
IINSPECil0Nl llNSPECil0Nl CONSTRUCTION l l PIPL l
NUMB R l_ NUMBER l_ NUMBER l l
ARIA l}YSilMI 50R l
IY PI l
l_ CLASS, SQLl WAQ _l l
1 l IW l ih.
f.
l Seamless lA106, GR. B l D2A I 11.75 1 1.514
- _L3188 1 5-99 l 20 l
l 2
i FW l Th. F.
l Hollow Forged lA106, GR. B*
D2A I 17.5 1 2.344 I L31100 l 5-103 1 305 l
l 3
l rw I
M.
F.
I Seamless lA106, GR. C D2A I 5
Sch XXS L2203 4 5-96 1 415 l
i l
4 l IW l M.
f.
l Hollow forged IA106, CR. B*
I D2A 13 1.742
. L2201 1 5-95 585 l
l 5
l IW i [ ro s.
I Ho l low f o rged lA106, CR. B l D2A 13 H 1.742 i L2202 1 5-92 452-455 l l
6 l IW l Eros.
l Ho l low Fo rged lA106, CR. B*
l D2A I 13 H 1.742 i L2201 1 5-95 585 l
l 1
i MS l 1h.
F.
I Ho l low F o rged lA335, CR. P2P l D1 1
16.25 h 2.715 l L2221 l 14A-93 330 l
l 8
l MS l 1h.
F.
l Seamless lA335, CR. P22 l D1 h 8.75 h 1.462 i L2286 1 14A-90 1 756 l
l 9
l HS l
M.
F.
I Seamless lA335, CR. P22 l D1 4 8.75 1 1.462 l L2271 h 14A-94 186 l
l 10 l HS l M.
f.
l Hol low f orged lA335, CR. P22 D1 l 16.25 1 2.715 l L2278 14A-99 205 l
l 11 1 MS l Corros.
1 Seamless lA335, CR. P22 01 l 8.75 1 1.462 l L22T1 1 14A-94
, 183-186 l i
l 12 l MS l Corros.
I Hollow Forged lA335, CR. P22 D1 l 20.75 1 2.996 l L5201 l 2-255 1 455 l
o l
13 l MS I Eros.
1 Seamless lA335, CR. P22 l D1 l 8.75 l 1.462 l L2271 1 14A-94 1 186 I
i 14 l MS I E ros.
l Ho l l ow F o rged lA335, CR. P22 l D1 i 16.25 11 2.715 i L2278 l 14A-99 l 205 l
l 15 l CRH I Th.
F.
I Seamless lA106, CR. B l D9 l 12 i Sch. 80 i L2295 l 11A-159 I 335 l
l 16 l CRH l Th.
f.
I Welded Plate lA515, CR. 60 l D9
! 32 l 1.268 i L5207 l 11A-164 l 990 l
l IT l CRil l M.
f.
I Scamless lA106, CR. B l D9 l 12 i Sch. 80 i L2295 l 11A-159 l 335 l
l 18 l CRH l M.
F.
I Welded Plate lA155, CR. 60 l D9 l 26.5 l 1.088 i L22250 l 11A-156 l 635 l
1 19 l CRH l E ro s.
I seamless IA106, GR. B l D9 l 14 l Sch. 80 l L2293 l 11A-159 l 411-415 I
,3 m
1 20 l CRH I Eros.
l Welded Plate lA515, CR. 60 l D9 1 32 l 1.268 l L5207 l 11A-164 1 990 l
un l
21 i CRH I Corros.
1 Seamless lA106, CR. B l D9 l 14 i Sch. 80 l L2293 l 11A-159 I 411-415 l l
22 l CRH l Cc.ros.
I Welded Plate lA515, CR. 60 l D9 1 32 l 1.268 i L5207 l 11A-164 l 990 1
00 l
23 l HRH l Th.
f.
I Scamless lA335, CR. P22 1 D3 l 11 1 0.800 l L2248 l 14A-76 l 350 l
l 24 l HRH I Th.
F.
l Seamless lA33$, CR. P??
I D3 l 11 l 0.800 l L2248 l 14A-76 I 355 l
l 25 l HRH l Ih.
f.
I Welded Plate IA155, CR. 2 1/4 CR, CL 18 D6 l 20 1 0.896 l L52200 l 14A-87 l 970 l
l 26 l HRH l M.
F.
I Scamless lA335, CR. P22 l D6 l 22 1 1.004 i L5217 l 14A-87 l 485 l
l 2T l HRH l M.
I.
l Hollow f orged lA335, CR. P22 1 03 l 22.25 l 1.714 l L22112 1 14A-85 l 205-211 I l
28 l HRH I M.
F.
I Welded Plate lA155, GR. 2 1/4 CR, CL 11 D6 l 20 1 0.896 l L52200 l 14A-81 l 495 l
l 29 l HRH l Corros.
l Seamless lA335, CR. P22 l D3 l 11 1 0.800 i L22105 l 14A-84 l 185 l
l 30 l HRH l Co r ro s.
l Hollow forged lA335, GR. P22 l D3 l 22.25 l 1.714 i L2252 l 14A-85 1 250-986 l l
31 l HRH l Co r ro s. l Welded Plate lA155, CR. 2 1/4 CF CL Il D6 1 34 l 1.511 i L5216 l 14A-87 l 540-550 l 32 l HRH I [ ros.
1 Seamless lA335, GR. P22 l D3 l 11 l 0.800 l L22105 1 14A-84 l 185-186 l 1
33 l HRH l E ros.
l Ho l low f o rged lA335, CR. P22 l 03 l 22.25 l 1.714 i L22112 l 14A-85 1 204 l
l 34 l HRH I E ros.
1 Welded Plate IA155, CR, 2 1/4 CR, CL 11 D6 l 34 l 1.511 l L5216 l 14A-87 l 540-550 l l
35**
l FW l Eros.
I Scamless IA106, CR. B l D2B l 6 l.864 l L21224 l 10A-66 l 231 l
l l
l l
1 I
l l
l 1
l I
o Additional Tolerances Per ASTM A530
- o T h i s a rea inspected due to historical erosion problems.
E Nondestructive Examination Procedures Copies of approved FSV examination procedures are attached (Attachment 1).
Nondestructive Examination Personnel Personnel performing the nondestructive examinations shall be certified as Level I, II or III, as appropriate, in accordance with QCIM-4 or NDE-1.
These personnel will be PSC employees or contractors.
Inspection Preparation Insulation will be removed and the surfaces prepared as necessary to perform these inspections.
The majority of the insulation is asbestos and as such requires special precautions for handling.
Page 9
F SECTION 3 INSPECTIONS PERFORMED Page 10
r Points Examined and Comparison to Areas Selected The insulation was removed and appropriate surface preparation performed for the areas selected for inspection on Table 2A.
Two areas (C&G) were included from earlier inspections which were not on Table 2A. Two areas (H&J) were included because the areas were available due to insulation removal for other reasons. One area (36) was added to the list to include a possible erosion area downstream of the main steam desuperheaters. When the insulation was removed from an inspection area, the exposed longitudinal or circumferential welds were inspected.
Inspections included magnetic particle, ultrasonic for thickness, and angle beam ultrasonic for defects whenever possible within the restraints imposed by supports attached to the piping.
Area 25 at the hot reheat steam chest was radiographed for the first PSC reports and since there is a pipe support interference, additional inspection was not performed. Three areas inspected were identified as potential mechanical fatigue or erosion areas (205-MOPT, IP 10/14; 206-A, IP27; & 204-MOPT, IP33),
but either did not have welds at all or did not have accessible welds so only base metal was examined, although they are numbered like and referred to as welds.
The following are summary totals from Table 3A (attached); and piping spool drawings.
I.
Number of Welds Inspected by System a.
Main Steam 23 b.
Feedwater 15 c.
Hot Reheat 31 d.
Cold Reheat 13 Total 52 II. Number of Welds Inspected by Type a.
Circumferential 74 b.
Longitudinal
_8 Total 82 III. Number of Welds Inspected by Potential Failure Mechanism a.
Thermal Fatigue 25 b.
Mechanical Fatigue 27 c.
Corrosion 15 d.
Erosion 15 e.
Other 7
Total 52 (Some Repeat)
IV. Number of Welds Inspected by Pipe Fabrication Type a.
Seamless 57 b.
Hollow Forged 5
c.
Welded Plate 20 Total 52 Page 11
V.
Number of Welds Inspected by Material Type a.
A335, P22 40 b.
A155, 2-14/% Cr - 1% Mo.
11 c.
A234, WP22 29 d.
A182, F22 12 e.
A106, B or C 18 f.
- 155, Carbon Steel 9
g.
A234, WPB or WPC 25 Total 82 (Some of the welds are for two different materials)
VI. Number of Inspections Performed a.
Magnetic Particle 79 b.
UT, Thickness 74 + 5 partial c.
UT, angle beam 73 + 4 partial d.
P.T (other than confirmatory) 3 i
l l
l l
L Page 12
TABLE 3A l
l Inspection Point (s) l Examine f or l
Mag i
1hickness l
Angle l
l l Weld No.
l l
l_Pa rticle l l
Beam l
Remarks l
lW1/20-A 11 (MFj lIhers, fat.
l1RM-2621 llP-1-T-01 IIP-1-45-01 l Recordable indication l
l 111.75 L3188-D2A l
l l
l lTRR-2659 l
l 1
l l
l l
l 50% of weld accessible l lW2/20-B l1 (MFj ITherm. Fat.
lTRM-2621 flP-1-T-01 llP-1-45-01 l
111.75 L3188-D2A l
l l
1 ldue to hanger.
I I
l l
l 8
l 1
l lW1/305-A l2 (MF) 11 he rm. Fat.
ITRM-2620 llP-2-T-01 llP-2-45-01 l45 degrees UT f rom elbov l
l17.5" L31100-D2A l
l l
. side only.
I l
1 I
I lW2/305-B 12 (MI)
HTherm. lat.
II T RM-2620 llP-2-T-01 11P-2-45-01 l
l17.5" L31100-D2A I
I l
l l
l l
l 1
l l
l IW1/415-8 l3 (MF)
Mech. Fat, hTRM-2619 llP-3-T-01 llP-3-45-01 Rough Weld Surface l
l 15" L2203-D2A l
l l
Irequired offset scan.
l l
1 l
1 I
h IW2/415-A 13 (MF)
IMech. Fat.
ITRM-2619 IP-3-T-01 llP-3-45-01 I
l 15" L2203-D2A l
l 1
l l
l 1
i H
I IW1/585-A th {MF) lHech. Fat.
ITRM-2618 ll l P-4/6-T-01 llP-4/6-45-01 h
l 113 L2201-D2A l
l l
l
,3 an I
l 1
l l
l "j
IW2/585-8 14 (MI) l Mech. Fat.
lTRM-2618 llP-4/6-T-01 llP-4/6-45-01 i
H 1
l l6 [MF) lErosion ITRM-2618 l l
113 L2201-D2A l
l l
l l
i i
1 I
I l
lW1/455-A 15[MF) l E rosion lTRM-2624 llP-5-T-01 flP-5-45-01 I
i 113 L2202-D2A l
l l
l H
I I
l l
l l
l l
lW2/455-B 15 {MI )
l E ro s ion ITRM-2624 IIP-5-T-01 (IP-5-45-01 l
l l
113 L2202-D2A l
l l
l l
l l
l l
l I
l l
lW3/452-A 15 gMI) l Erosion lTRM-2624 llP-5-T-01 IIP-5-45-01 I
l l
l13 L2202-D2A l
l l
l l
l l
l 1
l 1
l l
l l5 l Erosion lTRM-2624 llP-5-T-02 llP-5-45-01 l
l 113[MF) lW4/450-A L2202-D2A i
l l
l l
l l
l l
l 1
l l
1 I
IW1/450-B 15 {MF) l E ros ion IIRM-2624 llP-5-T-03 llP-5-45-02 l Rejectable surface l
l indications. Surface l
l l
110 L22266-D2A l
lTRM-2638 l l
[
l l
l l
l indications buffed out l l
l l
l l
l lsatisfactorily -
l l
l l
l l
l Ithickness checked arter I I
I l
I i
i leurring.
I i
l l
l 1
l l
l l
lW1/350-A 17 (MS)
IThere. Fat.
ITRM-2631 IID-7-T-01 IIP-7-45-01 l Downstream limitation I
l 18.75" L2216-D1 l
l l(1/16/86) l(1/17/86)
Idue to welded i
I I
I I
l 1
lattachments.
I l
l l
1 1
1 l
l lW2/350-0 17 (MS) l T he re. Fat.
ITRM-2631 lIP-7-T-01 llP-7-45-01 IFrom elbow side only.
I i
18.75" L2216-D1 l
l l(1/16/86) l(1/17/861 l
l 1
1 1
l l
l l
8 IWl/330-A l7 (MSj I T he re. Fat.
ITRM-2655 IIP-7-T-01 IIP-7-45-01 l
l l
116.25 L2221-D1 I
i l(1/19/86) l(1/19/86) l l
l l
l l_
l l
l I
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e X
X a
e N
e e
e o
e e
a e
o e
N N
N C
N N
N e
e D
G e
C m
a e
e e
=
w e
e e
e e
e e
e e
e e
e e
e e
e A
A A
A A
A A
A A
A A
A A
A A
A
_=-
= = - - - - - - - - - - - - - - - - - - - - - = - _ _
m e
e O
C C
e a
e
~
e m
C C
C c
e a
e e
e e
C M
M M
N N
k 1
m e
o e
e e
e e
w e
e O
C C
e e
(
-O C
C C
C C
C C
e%
0%
eJ e
o e
N N
e e
e e
o e
e e
e=
se e*
p I
e
=
w e
e e
N N
m
=
e e
e e
e e
e N
N N
O N
N N
c c
c C
e C
C C
C m
m e
W e
e o
e e
e e
e e
e e
e e
e e
e a
A A
A A
A A
A A
A A
A A
A A
A A
e
_ _ = - ------------=_-
(
N c
-A A
e e
o A
e C
C C
a e
m m
m m
UN N
N N
N N
N e
D P
3 N
N N
N N
0-@
40 4e Ce 4
mw.N N
N N
N N
N N
No No Ne N
N N
N N
E6 e
e e
e e
e e
e e
e e
o e
e e
e e E E
E E
E E
E E
E E
E E
E F
E E
Ag g
g g
g g
g c
e E
E E
E d
d g
=
=
---~~-----------
__-- =-- -------- =------------------
L O
C C
w U
u g
e e
a e
a a
a a
a e
E t
C e
e e
e e
e e
C w
w C
C C
w w
w w
w w
w 0
e e
g
-C O
4 4
E wC wc wc o
o e
m
=
8 E
E O
==
==
0 0
0 Em Em C
O O
W W
W
- 3
+3 X
E E
E E
w 6
6 6
6 C
6 6
6 Ce Em Em 6
6 6
6-L-
O C
C C
C C
C 6
uO 90 00 6
h b
GM Gd 2
I E
c I
E O
Gb 06 Ob O
O O
re 44 Q
Ew Ew Ew U
U O
ww
>=
-a wa
-C e
e e
O C
O O
O C
e e
A e
a e
e e
e m
a e
N O
O O
a0
=O C
O O
O C
O O
Q N
N N
N N
e a
Es Ee C
e e
e e
e e
e N
N N
N e
N N
EA Edi C
.N N
N J
J C
C Om U@
a e
C w
c G
e ad
J ad a
a
=N
=N wN wN O
aN aN aN
=N aN aN aN M
aM aM MMt MB MA M
N N
MN MN MN MN MN MN MN EE M ES M ER LE@ Ea EJ E NW NJ a
EJ Ed E4 EJ Ee EW Es we Ewe Ewe wwN
=N w
w W
w w
w w
w w
w N
w N
w N
e B
B N3 NE C
E r
s a
t t
t a
m o m.
Ca@ NC NA Ne cN AN ce me me em ea ne ce
-e a-a e-e
-N 4
0 A
C C
04 4
m
(
(
C m
(
(
C E
4 C
U m
=jo e
e o
e e
N e
e a
e e
e e
e e
,e e
e N
N N
e e
e o
e o
e e
o Dt-A A
A m
e o
e e
e m
M wN N
N N
N N
A N
e N
3 4
M M
3N N
N N
N N
N N
N, 2
9 2
2 9
2 2
2 9
2 2
2 9
m a
e
~
m M
2 2
4 Page 14
TABLE 3A I
linspection Point (s) i Examine For i
Mag Thickness l
Angle 1
i l_Wje d_Ilo.
I I
l_ fan igle RLMARI(S l
Beam i
Romerks l
lW1/990-8 116 (CRH) lihers. Fat.
11RM-2617 I IP-16/20/F2-T-01 llP-16/20/22-45-011 1
1 132" L5207-D9 l
l l
1 I
I I
I I
i IP-16/20/22-45-021 l
lW2/990-C 116 lCRH) l Therm. Fat.
ITRM-2617 lP-16/20/22-T-01 l
l 120f22(CRH) l Erosion /Corrosioni l
1 1
132 L5207-D9 1
l I
l l
I I
l l
l IW3/990-D 116 (CRH)
Therm. Fat.
ITRM-2617 llP-16/20/22-T-08 IP-16/20/22-45-02l I
l Longitud-132" L5207-D9 ilLong. Weld l
l 1
l linal I
l l
l l
l l
1 I
1 I
i i
l i
IW1/635-A l18 (CRH)
IMech. Fat.
l Thel-2641 IllP-18-T-01 ilP-18-45-01 l
l l Longitud-126.5" L22250-D9 l
l l
l l
l linal i
l l
l l
l l
l l
1 I
I I
I I
lW2/635-8 118 (CRH)
IMech. Fat.
ITRM-2641 llP-18-T-01 lIP-18-45-01 I
l l
126.5" L22250-D9 l
1 l
1 1
I I
I I
I I
I i
I lW3/635-C 118 ICRH)
IMech. Fat.
liRM-2641 llP-18-T-01 IIP-18-45-01 l
l
,a i
126.5" L22250-D9 I
l l
l l
l I
I I
I I
I I
I IW4/635-D 118 (CRH)
IMech. Fat.
ITRM-2641 llP-18-T-01 IIP-18-45-01 l
l l Longitud-126.5" L22250-D9 l
l l
l l
1 linal l
I I
I I
I l
I I
l l
I l
i I
lW1/415-R 119f21 ICRH)
I E rosion/Co rrosion l TRM-2651 IIP-19/21-T-01 lIP-19/21-45-01 l
l l
114 L2293-D9 l
1 l
IIP-19/21-60-01 1
1 1
I I
I I
i 1
I IW2/415-A 119f21 ICRH)
IE rosion/Corros ionlT RM-2651 ilP-19/21-T-01 llP-19/21-45-01 l Recordable 45 degree l
l 114 L2293-D9 I
I i
llP-19/21-60-01 langle beam indication i
1 l
l l
l l
lidentified as ID I
I l
l
?
I l
i geome t ry..
I I
I I
I I
I i
i IW1/350-B 123 (HRH) 11he re. Fat.
ITRM-2635 llP-23/24-T-01 llP-23/24-45-01 i
l i
111" L2248-D3 I
l l
l l
1 1
1 l
l l
l l
l lW2/350-A 123 (HRH)
I T he rs. Fat.
ITRM-2635 11P-23/24-T-01 IIP-23/24-45-01 l
l l
111" L2248-D3 l
l l
l l
l l
l 1
1 I
I l
lW3/355-A 124 lHRH)
I T he re. Fat.
BTRM-2635 llP-23/24-T-01 IIP-23/24-45-01 lFrom pipe side only, l
i Ill" L2248-03 I
l i
1 1-1 1
1 1
I l
1 i
l IW1/970-C 125 IHRH)
I T he re. Fat.
IN/A IN/A IN/A llRT. Only - TRR-2568 I
i 120" L52200-D6 l
l l
l l
l 1
i i
i l
i IW2/970-8 125 (HRH)
I Ihe re. Fat.
IN/A IN/A IN/A lRT. Only - TRR-2568 '
I ILongitud-120" L52200-D6 lLong. Weld l
l l
l I
linal i
I I
i 1
1 I
I I
I i
1 I
I i
lW3/970-A 125 (hRH)
IThere. Fat.
IN/A IN/A IN/A lRT. Only - TRR-2568 I
i 120" L52200-06 l
8 l
1 1
8 I
I I
I I
I I
I
TABLE 3A I
linspection Point (s) l Examine f or i
Mag i
Ihickness 1
Angle 1
l l JWeld_No __ l l
l_Parlicle l l
Beam i
Remark s l
l W1/485-8 126 (HHH)
IMech, fat.
lIRM-2637 llP-26-i-01 IIP-26-45-01 IReportable angle beam 8
l 122" L5217-D6 l
l l
l lindication identified l
)
i i
l 1
i las counter bore, i
i I
i l
i i
l I
(W2/485-A 126 (HRH)
IMech. Fat, liRM-2637 llP-26-T-01 IIP-26-45-01 l
l l
122" L5217-D6 l
l l
8 l
l l
l 1
I I
I H
I IW1/206-A 127 (HRH) l Mech. Fat.
likM-2645 I I P-2 7/3 3-T-01 IIP-27/33-45-01 h
I i
122" L22112-D3 1
1 I
l l
l l
l 1
I l
i 1
1 1
1 1
I I
I 127 IMech. Fat.
11RM-2640 llP-27-1-02 flP-27-45-03 Iscanned pipe side only. l IW1/213-A 122"(HRH)
L22120-D3A i
1 l
l l
l l
1 1
I i
l i
IW2/215-A 127 (HRH)
IMech. Fat.
ITRM-2640 IIP-27-T-02 IIP-27-45-05 l
l l
122" L22120-D3A l
l 1
l l
1 1
1 1
I i
1 l
l lW3/215-B 127 (HRH)
IMech. Fat.
liRM-2640 llP-27-T-02 IIP-27-45-05 l
1 1
122" L22120-D3A l
l l
l l
l
,3 l
l 4
l l
l l
l or (W4/83-A 127 (HRH)
IMech. Fat.
ITRM-2640 llP-2T-T-02 IIP-27-45-01 IScanned pipe side only -l j$
l 122" L221!0-D3A I
l l
l l recordable indication 1
I I
I i
i l
lidentified as ID & OD 1
I I
I l
l l
I geomet ry, i
U' I
l l
I I
l I
l lW1/432-A 127 (HRH)
IMech. Fat.
ITRM-2639 LIP-27-T-01 IIP-27-45-04 IScanned pipe side only -l i
122" L2253-D3A I
l l
l Irecordable indication i
l i
l I
i l
lidentified as ID & OD l
1 I
I I
I I
Igeometry.
1 I
I I
I I
I i
1 IW2/433-8 12T (HRH) l Mech. Fat.
ITRM-2639 IIP-27-T-01 IIP-27-45-06 1
1 1
122" L2253-D3A 1
i i
i 1
1 1
I I
I I
I I
I IW3/433-A l27 (HRH)
IMech. Fat.
liRM-2639 IIP-27-i-01
!IP-27-45-06 IRepo rtab le indications l l
122" L2253-D3A i
l l
l lidentified as ID & OD I
I l
l l
l l
Igeome t ry.
1 1
1 l
l l
l 1
1 IW4/85-A 127 (HRH)
IMech. Fat.
ITRM-2639 IIP-27-T-01 IIP-27-45-02 IScanned pipe side only. I i
122" L2253-034 I
l l
l l
l l
l 1
I I
I I
I lW1/495-8 128 (HRH)
IMech. Fat, liRM-2622 IIP-28-T-02 llP-28-45-02 l
l l
122" L5217-D6 I
i i
i i
l I
i l
i l
1 l
l lW2/495-A 128 (HRH)
IMech. Fat.
ITRM-2622 lIP-28-T-02 IIP-28-45-03 l Reportable indication l
I 122" L5217-D6 l
l l
l lidentified as ID l
I I
I i
1 1
Igeometry.
I I
I I
ITRM-2632 I i
11wo surface indications l I
l l
l l
l lbuffed out.
I I
I I
I I
i 1
l lW3/495-C 12S (HRH)
I Mech. Fat.
lTRM-2622 IIP-28-T-01 IIP-28-45-01 1 Peportable indication l
l 120" L52200-D6 I
I l
t identified as OD l
I l
l l
l l
' geometry.
1 I
I I
I I
I I
I L
==----------------
CD C
ad
=WOG E9
-G
- CedV U e O
Ob d=CU Ob
-V WO ge -
40 dG
(
=
d a u an da 66 n
da
o-On n
QQ 2
==
e3 UL3 a3 44 W
C 00 W
n b
t e
=VQd C
00 CW
-V C
4D 96 Ie
=D
-99 9
UC E
4 ab
=
e3 du e
E SV W-OdOD
=
GC
-O WO
-3m WO
0 a
G3 d004 03 D~
n%
u L
e09 C
nd
\\
t d=d 00 eV@db O
de Let ed aCm O De UU OCm seca
-39 9
t=
ato dC DOKen Que 03 g6ugs 3
e E=m EU E@2WW D
E=
=
=_----------------------------
l O
O O
l e
e e
e
~
~
+
c
~
~
~
~
~
+
e N
-E.lO O
a a
O O
O O
O 4
O O
m e e
e e
e e
e e
e e
a e
C i
C @ie N
N e
e b
b b
m b
o e
s (CR 3
m m
e 3
3 3
4 3
m 3
2 b
.e N.
N.
e e
e e
e e
N e
e at e
~
n c
e N
N N
N m
m m
m m
N m
M U
e e
a e
e e
e e
e e
e e
e I
L A
A A
A A
A A
A A
i
[
==_
=r_
I e
e
=
m l
O O
O e
e a
e C
=
=
e e
e e
e e
N e
l A
O O
e e
O O
O O
O O
e O
O O
"O t
u e
e N
N e
e e
e e
a m
a e
e t
m m
m e
4 4
e e
N N
e e
e e
e e
N e
e e
m
=
e C
S O
e N
e A
e N
N N
N m
m m
m m
m N
m m
m O
w e
e e
e e
e e
e e
e e
e e
e e
i a
A A
A 4
A A
A A
A A
I g
I
(
C i
=N N
N N
O em e
e C
e o
e 4
l UN N
2 4
m N2 N
N N
N d
d 4
m m-@
j JN N
N N
N NN N
N N
N N
N N
N N
We e
e e
e e e e
e e
e e
e e
e e
n;E E
E E
E KK E
E E
E E
E E
E E
Aix s
e e
m Em m
a m
E E
E E
E E
6=
C C
C C
O l
.O r
b e
e d
O O
O O
=
w 6
6 w
w w
W c
V U
e C
d d
C C
C C
C C
C=
C-t
=
4 e
o O
O O
O O
O Oc 6
E
=
=
=d
=
=
=
=
~
~e e
O
=O
=O
=O
-3 C
C C
C d
I e
e W
d W
e I
x O
O O
O O
O O
O
- e l
w m
C 6
6 6
k 6
L 6m w
e w
e e
r u
u 6
6 6
6 6
6 6C 6
0 0
0 0
I I
8 8
8 8
8 8s 00 6
6 6
6 O
O f
o us w
w w
w z
.==
l W
l M
I C
l m
O m
m m
e o
A C
C m
Q N
e i
f e
e as
- e Q
Q Q
=Q Q
Q e
e C.
Q
[
C O
Ze Z@
e e
e Ze e
e N
e w
O C
WO TO N
4 z@
~
4 4
N aN z.
z-ac --
g,
==
p N
e c4 I
d IN TN
-N
-N IN TN TN
-N IN ZN ZN ae
~N
- N d
U te MD N
N MN Kf Et c ze ze EN wN we
@e
- G 54 Z4 Na Ne Zw ZJ Km de KJ LJ Ed Ea EN Ed
@t 4
m m
m w
w
-4 EA w
e s
NC Na a
3 s
Na e
e e
a 3
-N C
CO
@C 7"
@w ON wd ed e3 ed
- 2 mN bO #8 e
t NN NN N=
Nw MN mm mm mm mm mm mN mm me me Oc t
I e
(
C U
de Qe Q
r'O3
(
(
2 4
e a
e O
e e
E 4
4 4
4 c3 e3 e
e e
e e
e e
e ir d e
e e
e e
+
+
m a
a ad 2d a
~
c
+
D' @ =
n D
G 2
P
&~
@~
Q m
N O
I# @
%@=
N@~
r4 N
N NCg m
a cq 4 C4 %
N FOC A N
3 3
3OC CC
- IJ a = 3 3
J 3
m m
as 3
3 3
3 3
l
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -....a.s.. - - - - - - - - - - - - - - -
P l
Page 17
TABLE 3A l
linspection Point ( s) l Examine f or l
Mag i
Ihickreess I
Angle I
I Weld No.
l l
l__Pa rticle l l
Beam l
Remarks i
IW1/115-8 lG ICRH) lintersects llRM-2642 llP-G-1-01 itP-G-45-01 IScan limited due to l
1 126.5" L22251-D9 ILong Weld l
I llP-G-60-01 l configuration k welded l l
l l
l 1
l l connection. Recordable l l
l l
l l
l lindication identified asi j
l l
l l
l 1
llD & OD geometry.
1 i
i I
I i
l i
1 I
tw2/115-A lG (CRHj ILong. Weld ITRM-2642 llP-G-T-01 llP-G-45-01 IRecordable indication l
ILongitud-126.5" L22251-D9 l
l l
llP-G-60-01 lidentified as 00 l
linal i
i l
1 I
i geome t ry.
l l
l l
1 1
I l
l IW1/200-A IH IMSI l
liRM-2634 llP-H-T-01 llP-H-45-01 1
I l
18.75" L2271-DI I
l l
l 1
l l
1 1
1 1
1 I
I Iw1/215-A IJ (MSI l
lTRM-2626 lIP-J-T-01 IIP-J-45-Os IRough surface required i i
16" L22287-Di l
l l
LIP-J-45-02 lorrset scan with scewd l l
l l
1 l
l ltransducer f rom pipe 1
I i
1 i
i i
Iside only.
I I
i 1
I I
I I
I IW2/492-A IJ IMSI I
liRM-2626 llP-J-T-01 IIP-J-45-01 IRecordable indication l
l 16" L22287-D1 l
l l
LIP-J-45-02 lidentified as ID l
,3 o,
I I
i 1
1 l
i geomet ry.
I "3
I I
I I
I I
i 1
lW3/492-8 lJ IMSI l
lTRM-2626 11P-J-T-01 11P-J-45-01 l Recordable indication l
i 16" L22287-Di l
l l
llP-J-45-02 lidentified as ID l
c3 1
1 1
I I
I i geome t ry.
Scanned elbowl i
1 1
1 1
1 Iside only.
1 1
1 1
1 1
1 1
I
Inspection Personnel The personnel who performed the surface, volumetric and or visual examinations were qualified in accordance with FSV procedure QCIM-4 or EBASCO procedure NDE-1, Personnel qualification records are available at FSV for inspection, Repairs One surface indication which could not be buffed out was detected by magnetic particle examination (BW1/435-A, IP31).
Disposition of NCR-86-030 resulted in grinding the indication out, repair by welding, heat treatment, and satisfactory reexamination.
Results No indications attributable to inservice induced degradation were noted in any areas examined.
l i
l l
l i
Page 19
SECTION 4 CONCLUSIONS Page 20
Augmented inspection of selected areas in main steam, feedwater, hot reheat, and cold reheat revealed no inservice induced defects.
Therefore, the current integrity of FSV's high energy piping has been verified, and the requirements of Confirmatory Action 6 in support of the FSV 35 percent power operation during the Environmental Qualification schedule extension period have been fulfilled.
1 I
l l
t Page 21
7.
l
[
NONDESTRUCTIVE EXAMINATION PROCEDURES QCIM-20 Liquid Penetrant Tc,t Procedure Issue 4 QCIM-23 Dry Magnetic Particle Inspection Procedure Issue 5 QCIM-24 Fluorescent Magnetic Particle Inspection Issue 3 QCIM-30 Radiographic Examination Procedure Issue 5 QCIM-38 Ultrasonic Examination of Class 1 and 2 Issue 1 Piping Welds Joining Similar and Dissimilar Materials Page 22
- ss,e 4 s
h[g X Public FCMT ST. VRAIN NUCLEAR GENEDATiNG STAriCN Page 1 of 5
$4fVICG
PUSUC SERVICS COMPANY OF COLORADO TITLE:
LIQUIO PENETRANT TEST PROCECURE (Solvent-Removable Visible Oye Penetrant)
I ISSUANCE AUTHORIZE 0
~
g 8Y N
bj
~m PORC
/
EF:ECTIV E PORC 6 5 5 JAN 8-1986 aEviEw cATE l %
1.0 PURPOSE This procedure describes a practice employed to detect discontinuttles open to the surface in nonporous materials.
2.0 APPLICA81LITY This procedure conforms to the latest edition & addenda of the appitcable Codes and applies to all solvent removanle visible dye penetrant examinations performed at Fort St. Vrain Station as required.
3.0 GENERAL RECUIREMENTS 3.1 Inspection corsonnel shall be qualif'ec in accordance with Procecure CCIM-4 3.2 Penetrant Materials:
The cenetrant aterials shall be of the solvert-remova014, visible cye penetrant type.
manufactured by tne Magna Flux Cor: oration, Sherwin Incorporated or Uresco Inc.
3.3 Denetrant materials of different manufacture shall not :e intermixed wnen cerforming a given test.
~~~
3.4 The penetrant materials snail have :een analyzed for sulfur content anc total malogens.
e resicual amount of total sulfur or halogens sna11 not exceed 1*. cy weignt.
Certification of tnese tests sna11 e :staired for eacn senetrant material used, giving caten numcers and test esults.
Caution:
The cremicals used for :'eantag arc 11oute
- enetrant testing are volatile and flam acle, treir va; ors may be toxic; safety precautions srall to taken in accorcance with the manufacturer's rec:mmencations, ou.c> m a ut Page 23
b' Public w sr. VRAIN MLEAR GENEAAN SmON 2 of 5 k
$CfVlCO**
PUBUC SERVICE COMPANY OF COLORADO 1.5 The liquid penetrant examination of intermediate weld layers shall include a minimum of 1/2 inch of the walls of the weld groove where possible.
The liquid penetrant examination of the finished weld shall include 1/2 inch of the basa metal on each side of the weld, where possible.
3.6 Satisfactory results may be obtained when the surface is in the as-welded, as-cast, or as-forged condition.
In some cases, surface preparation by grinding or macnining may be necessary to remove irregularities that would otherwise mask the indication or defects. Power wire brushing, gritblasting or sandblasting shall not be performed on any surface which is to receive a visible dye penetrant inspection.
The surface shall be free of scale,
- slag, weld ripples, and crevices which will* entras penetrant. Welds shall be final acceptance tested in the "as welded" surface condition.
The weld contour must blend into the base metal without undercutting that would mask the indication of defects.
4.0 PRCCECURE 4.1 precleaning 4.1.1 The surface to be tested and any adjacent area within at least one inen of tne surface to be tested shall be clean and f-se from oil, grossa, dirt or other foreign material.nich will interfere with the test.
Cleaning wtll be accomplished by vapor degreasing, ultrasonte cleaning or by
- dipping, spraying, swaboing or brushing with a nalogen and sulohur free solvent sucr as acetone or alconal. A final crecleaning snall be accomplished by dipping, spraying, swabbing or brusning with clear, unused or redistilled acetone, so that the area tested is well soaked.
Allow a minimum of five (5) minutes for the last t-sces to evaporate.
Examine visually for cleanliness.
4.2 Acolication of penetrant 4.2.1 The dye penetrant shall be acolied y crus 11ng, soraying or dicoing.
The test surface small te kept wetted for a minimum ceriod of ten (lC) minutes.
The temocrature of sne cart being cenetrant tested and the penetrant materials snall ce eetween 60*F and 125'F.
If there should te any complete drying of penetrant t ring tnis ceriod, tre surface shall be cleaned and retested.
- C8W'C1372 22 3843 Page 24
@C/ Service ~
Public roar sr. VRAIN NUCLEAD GENERATING STATION a
3 of 5 pusuc sanwes comeAm or cotonAno 4.3 Removal of Excess penetrant 4.3.1 The test surface shall be wiped dry as completely as possible with dry, clean absortent cloth or paper.
The remaining excess penetrant shall be removed by wiping with a cloth campened (not drioping) with the recommended cleaner.
Immediately dry with a clean, absortent cloth or paper.
Lint-free cloth or caper shall be used for final cleaning.
The time for surface drying after removal of last traces of excess penetrant and prior to application of developer shall be not less than five (5) or more than ten (10) minutes.
I 4.4 Acolication of Developer 1
s 4.4.1 The developer must be well mixed just prior to application. The developer shall be sprayed on the surface to be examined in a very thin even film.
The developer shall be allowed to dry naturally without fanning, compressed air, etc.
4.5 Test Intereretation L Retest 4.5.1 The indications, if any, shall be viewed and evaluated a minimum of seven (7) and no later than thirty (30) minutes af ter tre caveloper has dried.
4.5.2 One retest may be cerformed attnin the tnirty (30) minute limit specified in 4.5.1 acove by removing the developer utilizing a cry, clean cloth or pacer.
Use of a cleaner suen as acetone is prohibited.
Apolication of covelooer snall be performed as specified in 4.4 acove.
Test interpretation following a
retest shall be performed a minimum of seven (7) anc no later than ten (10) minutes af ter ne develo er nas cried.
4.6 Evaluation of Indications 4.6.1 Cefects wnich oc:ur as meenant:al cis::ntinuities at the surface will :e indicatec Oy oleecing out of the penetrant;
- however, localf:ed surface imoerfections such as may oc:gr facm macnining marts or surface concitions ay =rocuce sfmilar incications wnien are not relevant to tre cetection of defects.
scau.cim.m no Page 25
@C)$$fVITj" Public FORT ST. VDAIN NUCLEAR GENEDAT;NG STATION age 4 of 5 PUSUC SERVICE COMPANY OF COLORADO 4.6.2 Any indication which is believed to be nonrelevant shall be regarded as a defect until the indication is either eliminated by surface conditioning or it is demonstrated to be nonrelevant.
Nonrelevant indications and broad areas of pigmentation wnten would mask indications of defects are unacceptable and require retest.
4.6.2 Relevant indications are those which result from mechanical discontinuities. Linear indications are those indications in wnich the length is more tnan three times the width.
Rounded indications are indications which are circular ar elliptical with the length less than three times the width.
Only indications with major dimensions greater than 1/16 in shall be considered relevant.
4.7 Acceptance standard 4.7.1 Unless otherwise specified, the following relevant indications are unacceptable:
a)
Any cracks and linear indications, b)
Rounded indications with dimensions greater tnan 3/16 inen.
c)
Four or more rounded 1-dications in a line separated by 1/16 inch or 'ess edge-to edge, d)
Ten or more rounded incications in any sin square inenes of surface whose minor dimension is no less than one inch with these dimensions taken in the most unfavorable location relative to the indications :etng evaluated.
I 4.7.2 Acceptance of c:moonents examined urcer ASME I
Section XI shall be in accorcance witn Article 1
IWB-3000, and paragraon *a3-31*2 as it relates to l
Table IWB-3410-1, Acceptance Stancarcs" 4.3 Dest Cleaning 1.8.1 Witn the exception of defective areas recutring repair, the cenetrant materials sna11 :e removec :y fi-st wicing, then by cleaning witn acet:ee to a cegree snat no penetrant materials remain anon examined witn the unaided eye.
8Cau,C:372 22 3043 Page 26
ia;'5of5
@O Servirf Public Font 57. VDAIN NUCdM GENERATING STATICN pusuc sanvics comeamy os coton4oo 4.9 Records 4.9.1 Records shall be maintained on the PSC Liould Penetrant Test Report form (Attachment CCIM-28).
The test report shall be completed with all necessary information including penetrant materials type and batch numeers, f.e. SKL-5/A12345, SKC-5/B67890, etc.
a.9.2 Test reports shall be completed and administered per the requirements of procedure QC!M-2..
5.0 REFERENCES
5.1 ANSI B31.1 - Power Ptoing 5.2 ANSI 831.7 - Nuclear Power Pipf ng 5.3 ASME Code Section III - Nuclear Power Plant Components 5.4 ASME Code Section VIII - Pressure vessels 5.5 ASME SE165 - Liquid Penetrant Inspection 5.6 ASME Code Section V - Nondestructive Examination 5.7 QCIM-4, Noncestructive Examination Personnel Qualification and Certification.
5.8 CCIM-2 Preparation & Control of Nondestructive Examination Test Reports 1
5.9 ASME Code Section XI - Rules for Inservice Inspection of l
Nuclear Power Plant Components 6.0 ATTACHMENTS None l 7.0 COMMITSENTS The steo(s) and section(s) listed colow -ay 9et ce deleted l
without issuance of comoaraole controls.
The procedure itself, l
if initiated as a result of commit. ment cor ective action, may I
not :e coleted witnout issuance of comoaracle controls.
l 7.1 None 8C8%Ca T?2 22 3843 Page 27
- ss.e 5 QPublic FORT ST. VGAIN NUCLEAR GENERATING STATICN page 1 of 7 (Q $4fVlCG Pusuc senvoca COMPANY OF COLORADO TITLE:
ORY MAGNETIC PARTICLE INSPECTION PROCEDURE ISSUANCE AUTHORIZE 0 4 SY mA Q"C d 6 5 5 JAN 8-1986
$Yr'E I-S _ % _
1.0 PURPOSE This prdcedure outitnes the requirements for pe forming magnette parttele examination of surfa:e and slightly sub-surface discontinuities in materials with ferromagnetic properties using the direct or rectified current or AC or DC yoke with dry magnette particles.
2.0 APDLICASTLITY This crocedure con forms to the latest editions and addenda of the acD11 cable Codes and 40011e5 to dry magnetic particle examination performed at the Fort St. Vrain Station as required.
3.0 GENERAL REQU*REMENTS 3.1 Inspection personnel who perform sne cuttes specified in this procedure small be cualif ted in ac:ordance with the requirements of Procacure CCIM-4 3.2 The magnetizing equipment small be casable of incucing a magnette field of suitable intensity in :ne cart :eing exasined.
3.3 Ory irci powder shall be used as the 19scoction medt.m.
This material sna11 be of nign :er eao11 tty and icw retentivity, and of suitasle si:es anc snaces to proca:e readily magnette carticle indications.
- he color of e
medium snould be suen snat it rovides a :entrast to tre cackground of tne test surface. Test ssefac3 small not exceed 600*F.
3.3.1 Red, gray or wnite f ran cowder, 3arter Researen or equal shall be used.
W 8C8WCITP2 22 ms2 Page 28
@v Service ~
Public FCRT $7. VRAIN NUC:.0M GENET 1A7iNG STA7iCN
- ,g f7 pusuc sanwes comeamy os cotonaco 3.4 Surface Preparation 3.4.1 Prior to eramination, the test surface and any area adjacent to the test surface within one inen
- minimum, shall be dry and free of any extraneous matter that would interfere with the examination.
3.4.2 Detergents, organte solvents, descaling solution, paint removers, sand or grit
- blasting, and cegreasing are methods that may be used to clean test surface.
3.4.*
As-cast, as-rolled, as welded, and at-forgea surfaces are satisfactory for examination, provided the surface does r.o t interfere with the interpretation of the test.
3.5 When it is necessary to verify the adequacy or direction of the magnetizing field, the Magnetic Particle Field indicator descetbed in ASME Section V,
Article 25 (SA-275), Figure 8, or an equivalent indicator shall be used by positioning the indicator on the surface to be examined.
3.5.1 Whan using this indicator, a suitaele flux or field strength is indicated wnen a :'eariy defined line of magnetic particles forms a:ross the cooper face of the indicater wnen the magnetic particles are applied simultaneously witn :na magnetizing force.
4.0 PRCCEDURE 4.1 Pr:d Examination Method 4.1.1 Magnetization small ce continuous curing the examination.
4.1.2 The test area shall be magnetizac by using :ortacle pred type electrical contacts :ressac against one surface.
4.1.3 Prod spacing shall be at less: sta (6) inenes :ut not more inan eignt (8) inenes.
een tne geccetric configuration of a part is suen nat srec scacing of less tnan s1x (6) inenes fs re:uired, crec s: acing may e decreased tut at no it e sna11 scacirg e less than :nree (3) incnes.
4.1.4 8eeds must be sept clean and cressac to srevent arcing.
somic;v2 22 Jeu
_ _ _ Page 29 _ _ _ _ _ _ _ _ _ _. _.
QPublic FORT ST. VRAIN NUCLEAR GENERA 7;NG STATION 3 3f 7
/ SCTVICO*"
PusuC SERVICE COMPANY OF COLORADO 4.1.5 The magnetizing current shall be:
a)
Materfat with thickness less than 3/4" - 90 to 110 amp per inen of prod spacing.
b)
Materials with thickness greater than 3/4" -
100 to 125 amp per inch of prod spacing.
4.1.6 On each test
- area, a minimum of two (2) examinations shall be performed, with prod olaced so tne lines of flux of one examination are approximately at right angles to the lines of flux to the other.
4.1.7 Examinations shall be conducted with sufficient overlap to assure 100% coverage at the established sensitivity.
4.1.8 The iron powder shall be appited in a light, evenly distributed cloud with a parker Research (model PB-1) powder blower or equivalent.
Excess powder shall be removed by a low pressure air stream.
4.1.9 Demagnetization when required, shall be performed using the AC steo cown method.
4.2 Coil Mothed Longitudinal 4.2.1 Magneti:ation sna11 to c:stinuous during the examination.
4.2.2 The magnett:ing curaent snall Oe:
a)
For parts with a UO *atio greater than or equal to 4:
Amoere-turns =
35000
( L/ 0 )
- 2 b)
For marts with a UO ratic f ess tnan 4 out equal to or greater tnat 2:
Amoere-turns =
450C0 L/ 0 c)
Darts witn an L/0.atto less snan 2 sna11 not te testec Oy this netnod.
4.2.3 when :ne coil is made of a wounc caole around tre test mart, tne coil turns snall :e closely soa:ed.
rea m e m a m a Page 30
(~'
FCDT 57. VDAiN NUCWD GENER ATING STATiCN
[gpyhllc 4 ;f 7
/$4fVICO'"
PusuC seRVICS COMPANY OF COLORADO 4.2.4 The effective field extends six (6) inenes en either side of the coll.
a)
Long parts shall be magnetized in sections.
4.2.5 Particles shall be appited in accordance with Paragrapn 4.1.8.
4.2.6 At least two examinations shall ce performed on each area. The sec:nd examination shall be with itnes of magnetic flux perpendicular to the flux direction in the first examination.
4.2.7 A different means of magnetizing may be used for the second examination.
4.3 Of rect Contact (Ctreular) 4.3.1 Magnetization shall be continuous during the examination.
4.3.2 Ofrect or recti fied magnettzing current shall be used. The recutred current shall be determined using the following guidelines.
a)
Parts up to five (5) ine es in diameter:
700 to 900 amos per inen.
c)
Parts five (5) inches :: ten (10) inches in diameter:
500 to 700 amos ser inen.
c)
Parts ten (10) to fifteen (;5) inches in diameter:
300 to 500 amos er inen.
d)
Parts over fi f teen (15) inenes in diameter:
100 te 330 amos ser inen.
e)
For carts attn geometric s: aces ctner tnan
- round, tne magnetizing am:erage may
- e estaeltsned using the Magnette Particle Field Indicator per 3.5.
4.3.3 Particles shall ce acclied
'n ac::rcance witn Paragraan 4.1.3.
4.3.4 At least two examinations snail :e carr*ed :wt :n eacn area.
In the second examtration, tne lines of magnette flux shall be percencicular :: those for ne first examination.
A dif'erent ?eans of magnetizing may ce used for tne second examination, em c; m. :2. me Page 31
G')Public CRT ST. VAAIN NUC.EAD GENEAATING STA7;CN g
7 y Service ~
pusuc sanvics compaav or cotonaco 4.4 Yoke Method 4.4.1 The Yoke Method shall be Ifmited to 1ccating discontinuities open to the surface.
4.4.2 An A.C.
Yoke may be used providing the yoke has itfting power of at least ten (10) pounds and 0.C.
Yokes must have a 11f ting power of at least forty (40) pounds.
4.4.3 A pole spacing of 3 to 6 inches shall be used.
4.4.4 Particles shall be app 1ted in accordance with Paragraph 4.1.8.
4.4.5 At least two seoarate examinations shall be performed on each area.
The second examinations small be conducted with the Ifnes of the flus in a direction aeroendicular to the first direction. An alternate metnod of magnettzing may be used for the second examination.
4.4.6 Examinations shall be conducted with a minimum of one (1) inch overlap to assure 100 percent coverage.
5.0 CALIBQ.17tCN 5.1 Equipment with ammeters shall be cal *:-ated and sna11 have units meter accuracy verified by equf:?ent traceanle to a
National Standard.
The units meter small not deviate by more snan olus or minus 10% of full scale, relative to the actual current value as shown by test eter.
5.2 Yokes shall be calfbrated by determining tnote itfting power, per paragrann 4.4.2.
5.3 when ecutoment with uncalibrated a-eters must ce used, all tecnnt ues small te proven asing : e !'efd indicator cesertbed in Section 3.5 prior to use.
6.0 ACCE3*aNCE CRITERIA 5.'
Any indications.nten is celteved to :e een-relevant, small be regarced as a defect untti tre cefect
- s eitsinated :y surface conditionfng or 't 's re-examtred oy sne same or etner nondestrue fve test etrod.
sos W C.2'2 22
- 3 Page 32 s
QPublic FORT $7 V?AIN NUCLEAR GENEDATING STATION (Q $4fVICO'"
a 6 of 7 Pusuc sanvoca COMPANY OF COLORADO 6.2 The following relevant indications are unacceptable unless specified otherwise.
6.2.1 Any cracks or itnear indication.
6.2.2 Rounded Indications with dimensions greater taan 3/16 inch.
6.2.3 Four or more rounded indications in a line separated by 1/16 inch or less, edge to edge.
6.2.4 Ten or more rounded indicatfons in any six (6) square inches of surface with the major dimension of this area not to exceed six (6) Inches with the area taken in the most unfavorable location relative to the indications being evaluated.
l 6.3 Acceptance of components examined under ASME Section x!
l shall be in accordance with Article IWS-3000, and l
paragraph IWB-3112 as it relates to Table IW8-3410-1, l
Acceptance Standards."
7.0 RECCROS 7.1 Results shall be documented on the Pubite Service Comoany Magnette Particle Examination Reco t form (attacnment QC6M-28).
The test report shall :e completed with 411 necessary i n formation,
signed anc cated by QA/QC personnel.
7.2 Test resorts shall be consecutively numbered and acatnistered per tne requirements of Procacure CCIM-2.
semc.m u au Page 33
G PublicdServl30~
= car s?. VRMN NUCGAA GENERA 7iNG STA7;CN f$j*7of7 pusuc sanvics compam or coton4oo
8.0 REFERENCES
8.1 ANSI 831.1 - Power Piping 8.2 ANSI B 31.7 - Nuclear Power Pf ctng 8.3 ASME Section V - Nondestructive Examination l
8.4 ASME Section XI Rules for Inservice Inspection of l
Nuclear Power Plant Components l
8.5 QCIM-2 Preparation and Control of Nencestructive Examination Test Reports.
l S.6 QCIM-4 Nondestructive Examination Personnel Qualt f tcation and Certification.
9.0 ATTACHMENTS 9.1 None l 10.0 CCMMITMENTS l
The step ( s) and section(s) 11sted below may not be deleted l
without Issuance of comparable controls.
The procedure itself, l
if initiated as a result of commitment c:aractive action, may l
not ce deleted without issuance of compara:1e controls.
l 7.1 None eceu.c:m a w Page 34
O Service ~
Public FCRT ST. VR AIN NUCLEAR GENERATING STATION ag, of 9 Pusuc sanwes COMPANY OF C04.ORADO TITLE:
FLUCRESCENT MAGNETIC PARTICLE INSPECTICN ISSUANCE AUTHORIZEO d 4-#
By PORC 5 :i'TW E REVIEW 2 CRC 8 5 5JAN 9-Iccc OATE l Cl - N 1.0 PURPOSE This procedure outlines the requirements of a method used in performing magnetic particle examination of surfaca and sitgntly subsurface discontinuities in materials with ferromagne tic propertius using direct or rectified current or an AC or CC yone utilicing wet, fluccescent magnetic particles.
2.0 ApoLICABILITY This procedure conforms to the latest editions and addenda of the acolicable Codes and acoltes to all fNorescent magnette particle inscoction performed at PSC facti :'es as reQutred.
3.0 GENERAL RECUIREMENTS d
3.1 All personnel.no perform the duttes s:ecified in this procedure shall be cualified in ac:arcance witn the requirements of procedure QCIM-4 3.2 The magnetizing ecuicment shall be ca:acie of inductag a magnetic field of suitaole intensity
'n
- ne part teing examined.
3.3 Tae examinatten shall te c:ncuctec in a ca teaec area asing filtered black lignt.
The black 'f; : fntenst:y at tne surface uncer examination sna11 te eas. rec at least
- nce eveey 3 nours, and anenever tre oors 1cca: ten
's
- sanged, estng a meter wnien is sonst '<e
- it; : fn tre altraviole: 5:ec r.m and centerec on 365 ran: e:e s ( m)
(1650 A*).
l 3.4 T-o readings anali ce taken; the firs:.<1:rcut a filter anc tne sec:nc witn an ultravtalet (365 -)
asserotag filter sfaced :ver :ne sensing elemen sf tre meter.
ine sec:nc reacing sna11 s suotracted fr:m :Pe first anc :ne i
ctffersece snail be a mint um of 300u W/:m 8 3.5 ine elacs It;n
- uld sna11 be tur9ec on arc 4110 ec to l
arm us for a wint um of five minutes :r*ar :s use.
t seau.c. m a *:
Page 35 w
w M
Issue 3 O Service ~
Public FCRT ST. VRAIN NUCLEAR GENERATING STATION page 2 of 9 Pusuc sanwes COMPANY OF COLORADO 3.6 The test surface shall not exceed 135'F.
3.7 Surface Preparation 3.7.1 Satisfactory results are usually octained when the surfaces are in :ne as welded, as-rolled, as-cast or as-forged condition.
- However, surface preparation ny grinding or machining may te necessary whe*e surface traegularities could mass incications cue to discontinutttes.
3.7.2 Prior to examina:!cn, the surface to be examined and all adjacent areas within at least one inch shall be dry and free of all dirt, grease, If nt, scale, welding flux and scatter, oil or other extraneous matter that could interfere with the examination.
3.7.3 Cleaning may oe ac::molisned using detergents, organic solvents, descaling solutions, paint
- removers, vaoor degreasing, sand or grit blasting, or ultrasonic clesning metnods.
3.8 When it is necessary to verify ne a:acuacy or direction of the magneti:ing field, the Mag e::: Particle Field Indicator described in ASME See:':n V, Artfele 25 (SA 275), Figure 8 or an ecuivalent inct:nse snalt be used by positioning the indicator on :9e surface to be examined.
3.3.1 When using thf s inci: ster, a satta:1e flux or field streng:n is incicated anon a :?early deffnec 1tne of magnetic partt:!es forms a:r:ss :re ::::er face of sne incicator wnen :ne magen : =artt:!es are aos11ed simultaneously at:n tre ag ett:tng for:e.
If a clearly deff nec Ifne is :: #:r ec, or is not formed in tne desired ctre::t:, :ne magnett:ing tecnntoue shall :e :nanged or act.stec.
3.1 34:n Concentratten 1.7.1 The tnistal
- stn c:n=ent-a: :n
- / sus:eadac agret'
- artt:!as snowlc :e '-
n:::rcae:e atte acu/ac:.reas rec:mmencastens sne snealc :e c.ected
- y get tng volu.e measurements a-c matntained at tre s:ect fiec ::n=entration on a catly :ast s.
3.9.2 De ree:mmenced set tng volu o 1s fr:m 0.1 mi ts 0.5 m1 in a 100 ml atn samole, antess otne-wtse s:ectfiec by :ne manufacturer.
l som W C2372 22
- 3
l
- v-:a OService~
Pubile FORT ST, VRAIN NUCLEAR GENERATING STATION g 3 of 9 pusuc sanvics comeany or cotonaco 3.9.3 8ath concentration shall be determined by measuring its setting volume enrougn the use of an ASTM cear-snamed centrifuge tube witn a 1 m1 stem (0.05 ml divisions).
Before
- samoling, shake the sus:ension well to assure a snorougn mining of all particles.
Take a 100 ml portion of tne susoenston and allow it to settle for amorontmately 30 minutes.
The volume settling out at the bottom of the tube is indicative of the particle concentration in the bath.
If the batn concentration is low particle content, add a sufficient amount of carticle materials to cotain the desired concentration.
If the suspension is high in particle content, add sufficient vehicle to obtain the desired concentration.
3.9.4 If the particles amoear to be loose agglomerates rather that a solid layer, take a second sample.
If still agglomerated, the particles may nave become magnettred and the solution should be replaced.
3.10 Suspension Vehicles 3.10.1 Suscension Ventcles small ce : evron Base 011 'C' or ecu1 valent.
4.0 PROCEDURE 4.1 Paed Examination method.
4.1.1 w.agnetization sna11 te continuous during tne examinatton.
4.I.2 Ihe test area sFaII De 'aj*eti ed my vstrq **rticle pr0d type electrical contacts c'essed sgainst tee surface.
A13 ErCC sDacfag srall te at legg gt, (.3) 93;,.,g gyg not Scre tnan (3)
- incnes, aren t,
ge:-, r40 con #1juration of a garg ig g,;5 g.gg ;r;g gggg.gg of less tnan sin (6) te:neS
's "etuired. oros soa: tag ay :e de:reased but 4:
.o
..e 3 315 scactag og less tnan :nre, (3)
..._.,g, 4.1.4 Daods must ce kaot clean arc dressed to orevent ac n1at, I
i l
l
......,mu-
- - - - - _ _ - - - - - - - - - - Page 37
- '*-;a O Service ~
PUDllC FORT ST. VRAIN NUCLEAR GENERATING STATION page 4 of g pusuc senvics company or cotonaco 4.1.5 The magnettzing current shall be:
a)
Material with thickness less inan 3/4" - 90 to 110 amp per inen cf prod spectng, e
b)
Materials with tnickness greater than 3/4" -
100 to 125 amo per tnen of or:c scacing.
4.1.6. On each test
- area, a minimum of two (2) examinations small be performed, with prod placed so the Ifnes of flux of one esamination are doorontmately at right angles to the Itnet of flus to the other.
4.1.7 Examinations shall be conducted with suffletent overlap to assure 100% coverage at the estamitshed sensttivfty.
4.1.3 The wet fiuorescent particles shall be applied in a light, evenly distributed cloud.
4.1.9 Ce94gnettZation. =Nen required, shall be performed using the AC stescown method.
4.2 Call Method (Longitudinal) 4.2.1 Magnetization shall be continuous during the examination.
4.2.2 For this tecnnicus, magnett ation small be a::omolished by casting cue emt tnrougn a
tulti-turn fixed cott or cacie that is wracoed around tne part or se:sfon of te cart to be examined.
4.2.3 Ofre:S or re: tiffed :araent saa:1 :e usec.
!*e t
requirec field streagtn trall se
- st:s:stec cased on the lengtn (L) and tne cia etea (3) of tre cart in ac:oreance witn 4.2.4
- a. 3.
4: : :sfow.
t.o e g parts small se enanteed in Se:t*:as mot to e<cesc la 'a:nes and 13 in:nes small se.ses ':e tae maat
( t.)
in calculating te recutae: etc st eagtn.
~:a aca-:yl tner' a1 caats, (3) 1 a t ' te : e ast
.9
- asss-sectional stagonal.
4.2.4 fee -a;nett:* ng cu, aent small te ( s 'O'.):
a) for carts attn '/0 aatton rester tFan or 90 sal to 4:
a ceae tarns =
150*0
( '. 0 )
2 Page 38
- -:t O Service ~
Pubila FCRT ST. VAAIN NUCMAQ GENERATING STATION
$ of g pusuc senvice comeAmy or cos.onaoo b)
For parts with a L/0 retto less tnan 4 mut equal to or greater than 2:
Amoere-turns =
45000
( L./0) c)
Par *.s with an LD ratio less than two small not to tested Dy this method.
4.2.5 When :ne coil is made of a cable wound around the test part, tne coil turns shall be closely spaced.
4.2.6 Particles shall to appiled in accordance with Paragraph 4.1.8.
4.2.7 At least two examinations shall be performed on each area. The second examination shall be with lines of magnette flun perpendicular to the flux direction in :ne first esamination.
4.2.8 A different means of magnetizing may be used for the second examination.
4.2.9 Demagnett:ation, when recutres, shall ee performed using the AC 5tendown metnod.
4.3 Otreet Contact Metrod (Cte:ular) 4.3.1 Magneti:ation small be continuous during the examinattCn.
4.3.7 Ecr this tecnntque, magnet':ation shall be ac::mcitssed 3y passtag current inrougn tre part to be esamined.
4.3.3 Otreet or restified magneti:t ; :ar eat small :e used.
The recufred current sea:
- e deter-taed usteg the following guidelines.
a)
- rts.o to f be (5) Imenes t9 :stea diamete*:
4
';0 to 900 amos per in:n.
- )
marts
"<e (5) f e nes to (; ) ta: es M : ster cia eter: 500 to 700 am:s ce* te:n.
- )
8aats ten (10) to fif teen (;5) te =es in : uter
- tameter: 300 to 500 amos ea ta:n.
d) parts over fifteen (15)
'neses in cater eta ete*: 100 to 330 amos co
'nen.
scaw + m u a.:
Page 39
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- M-2t OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION age 6 of g Service ~
pusuc sanvics compam or cos.onaco e)
For carts with geometric shaces otner snan rounc, tne greatest cross-sectional diagonal in a plane at rignt angles to the current flow shall cetermine the inches to be used in the a:ove competitions.
f)
As an alternate, for non-:ylindrical parts
- only, the magnetizing am:erage may be estaclished by using the Magnetic Particle Field Indicator as specified in Section 3.8.
4.3.4 Partic!as shall be applied in accordance with paragraph 4.1.3.
4.3.5 At least two examinations shall be performed on each area. The second examination shall be witn Itnes of flux percendicular to the flux direction of the first examination.
4.3.6 A different means of magnetization may be used for the second examination.
4.3.7 Cemagnetization, when reautred shall be performed using sne AC stam-cown etnoc.
4.4 Central Conductor Method 4.4.1 Magnetization shall be c:atinuous during the examination.
i 4.4.2 For this technioue a central concuctor shall be used to examine tne internal sur aces of ring or d
cyltecrically snacec carts.
7,ts tecnntoue may also :e used for examinirg tne :.tsf ee surfaces of those snaces.
4.4.3 Where large dia9eter cylincers are to :q examt ec, tne conductor snall be positterec :!cte to tre internal surface of tre :yi'acea.
Wren ene c:ncactor is not centered, the :ta:.mfecea:e of tre cylin:er sna11 be examinec ta ice e ents.
A Wagrette Particle Field In:t:st:*,
a:cife:
4::o*:an:e attn Sectton 3.3, s all
- e ase: t:
estaclish tne extent of t5e at: t.9 4 may :e esamined for eacn conductor posttien.
4.4.4 Sars or cacies may be used as :ertaal :encuctors, l
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[QPublia sswe 3 FCAT ST. VOAIN NUCLEAR GENERATING STATION pag, 7 of 9 j $4fVICG"'
Pusuc sanvics COMPANY OF COLORADO 4.4.5 The field strength required sna11 de equal to that determined in Section 4.3 for a Single turn central conductor.
The magnetic field shall be increased in precortion to the numcar of times the central conductor cable passes througn a hollow part.
4.4.6 Particles shall be amplied in accordance with paragraph 4.1.3.
4.4.7 At least two examinations shall ce carried out on each area.
In the second examination, the Ifnes of magnetic flux shall be perpendicular to those for the first examination.
A di f ferent means of magnetizing may be used for the second examination.
4.4.8 Cemagnetization when required shall be performed using the AC step-down method.
4.5 Yoke Metnod 4.5.1 The Yoke Method shall be 1tmited to locating discontinuities open to the surface.
4.5.2 An A.C.
Yoke may be used caoviding the yoke has lif ting power of at least ten ('.0) pounds and O. C.
Yokes must have a If f ting ;o.ea of at least forty (40) pounds.
4.5.3 A pole spacing of 3 to 5 inches sna11 be used.
4.5.4 Particles snall be acolted in accorcance witn Paragracn 4.1.3.
4.5.5 At least two secarate exa-taations sna11 be cerformed on eacn area.
Tre se:ced esaminations sna11 be etncucted witn tne lires of tne flux in a direction eersencicular to the f'ast etrection.
an alternate metncd of ragneti:ing ay be used for tne second examination.
a 5.5 Examt ations small ce conductec attn a -in4-.-
- /
one in:n overlaa to assure ICC4 ::verage.
a.5.7 Ce agnett:atton, wnen recuirec sna!1 :e ;erder ec using tne AC stee-cown metnoc.
5.0 CAL:32A**0N
5.1 Magnett
Darticle ecutoment sna11 ce cal'oratec. as a minimum, at least once a year, or wreaever te ecuto ent nas teen aecatrec. overnauled or camagec.
nm c.rz :2 na Page 41
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- -:t Public FORT ST VRAIN NUC'. EAR GENERATING STATION pag 8 of g Service ~
Pusuc sanvics COMPANY OF COLORADO 5.2 Equipment with ammeters shall have units meter ac:uracy vertfted by equipment traceacle to a National Stancarc.
The units meter sna11 not deviate by more than plus or minus 1C". of full scale, relative to tne actual current value as shown by test meter.
5.3 Yokes shall be calibrated by determining their Iffting power, as per paragra:n 4.5.2.
5.4 When equipment witn uncaltbrated ammeters must be used, l
all technioues shall be proven using the field incicator described in Section 3.8 prior to use.
6.0 ACCEPTANCE CRITERIA 6.1 Any indication whten is believed to be non-relevant shall be regarded as a defect untti the defect is eliminated by surface conditioning or f t is re-examined by the same or otner noncestructive test method.
6.2 The following relevant indications are unacceptable unt-as specified otnerwise.
6.2.1 Any cracks or Itnear incteat':-
6.2.2 Rounded incteations witn : ensions greater than 3/16 inch.
6.2.3 Four or more rounded inct:stions in a ifne sacarated by 1/16 inen or less, ecge to edge.
6.2.4 Ten or more rounced indications in any six (6) souare inenes of surfa:e witn t.e major cimension of tnis area not to ex:eed s's (6) te: es altn tre area taken in tne most an#1<ceacle location relative to the incteations tet g evaiwatec.
I 6.3 Ac:ectance of com:enents examined ur:n-A$uE Section XI I
l shall be in ac:orcance nitr Artic'e lWB-3CCO, arc I
maragraon IWB-3112 as 1t relates to Tacle IW2-34;0-1, i
"Ac:ectance Stancarcs."
7.0 :CI~ ".EANING l
7.1 with tne exce tion of defective areas ecat ring recair.
- ne fluorescent magnetic particles snali ce e oved first by wi:Ing, tnen ey cleaning with scatore to a cegree that no partt:les re-atn wnen etamined with tre anat:ec eye.
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OPublic FORT ST. VOAIN NUCLEAD GENERATING STAT'ON pg 3 of 9
$4fVICG' Pusuc ssRvics COMPANY OF COLORADO 8.0 RECORQS 8.1 Results shall be documented on the ASC Magnetic Parti:le Examination Report Form (Attach. CCIM-29 The test shall be comoleted witn all necessary).
report informatton, signed and cated cy QA/QC personnel.
8.2 Records and reports generated as a result of tnis procedure small be c:mpleted and administereo per tne requirements of procecure CCIM-2.
9.0 RE~ERENCES 9.1 ASME Section V - Nondestructive Examination 9.2 ANSI B31.1 - Power Piping 9.3 ANSI B31.7 - Nuclear Power Piping 9.4 QCIM Pre 24 ration and Control of NOE Test Reports 9.5 QCIM-4 Nondestructive Examination Personnel Qualtftcation and Certification l
9.6 ASME Section XI, 1980 Editten un :: sed including Winter l
'81 Accenda 10.0 ATTACFwENTS None i 11.0 CC.wMIT*ENTS l
The stec(s) and section(s)
Ifstad :elon may not :e celeted l
- ttreut issuance of ccmcaracle controls.
Tre :r::ecure itself, I
if initiated as a result of c: mit. ment c:r t:tt ve acti:n, -a/
l not te coleted without issuance of :mcaracle :: tecis.
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!ss.e 5 OPublic roRT sr. VRAIN NUCLEAR GENERATING STATION Eage 1 of 13
$9fVICS Pusuc senvsca coaspassY OF cotonApo TITLE:
RA0f0 GRAPHIC EXAMINATION 84CCECURE ISSUANCE AUTHORIZED gy r-PoRC EF8ECTivE REVIEW Eptc 8 3 6 AUG2 91995 cirE q.L.gs 1.0 AURPOSE This crocedure describes the requirements of and the method used l
for radiograpnic examination at Fort St. Vrain Station.
2.0 AD8LICA8tLITY This procedure conforms to the latest editions and addenda of the acclic4 Die codes and acolies to Radiographic Inscoctions l
performed, as required, at Fort St. Vrain Station.
3.0 GENERAL REOUIREMENTS 3.1 All personnel performing and/or evaluating radiograonic examinations small be qualified in accordance with l
procedure QCIM-4 and the " Pub 11: Service Company of Colorado Incormorated Manual of C erating and Emergency Procedures for Radiograony".
3.2
- Orawings, contracts or D*ocess/Insooction Record Choctlists sna11 specify the extent of radiogrannte esamination, as recutred for eacn item.
Radiograonic locations small ce marted on the drawtegs as.acolicamle.
3.3 8aat Configuration: Constderation s all :e given to tae cesfgn parts, comoonents ard melds to ser91 interpretacle radiograpnic esamination.
3.3.1 Bacting Rings or $ trips: A bacting ring or stric, if it ts to De left in place, snowld ce of such sfce and conffguratton trat its image will rot interfere with the internaetation of the radiograpn.
3.4
$weface :!nism of Materials:
$wrfaces small satisfy sPe recuirements of tre toolicamle materials scocifications, with aeditional surface conditioning if mecessary, cy any suitacle process to a cegree snat surface ir equiarttles cannot mast or ce confwsed with discontinwikies, w oim n.me Page 44
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PUBLIC SERVICE COMPANY OF COLORADO 3.5 Surface Finish of the Welds:
The weld riooles or weld surface irregularities on both tne inside (wnere accessible) and outside, shall be removed by any suitante mechanical process to such a degree that the resulting radiographic contrast due to any irregularities cannot mask or be confused with the image of any objectionable defect.
The weld surface shall merge smoothly into the base material.
The finished surface at the reinforcement of all butt welded joints may be flush wtth the acjacent base material, or may rave a reasonably untform crown, not to exceed the limits noted in the referencing Code section or Specification.
3.6 Radiographic Sources 3.6.1 Radiation sources may be either X-ray equipment or radioactive isotopes.
Recommended X-ray machine voltage setting and radio-isotope sources to be used for radiography are in accordance witn l
Attachments QCIM-30 A, B, or C.
3.6.2 Exceot as provided in 3.6.3 the recommended minimum thickness for which radioactive isotopes may be used is as follows:
MATERIAL IRIO!UM M M 60, Steel 0.75 in.
1.50 Copoor or Hign Nickel 0.65 in.
1.30 in.
Aluminum 2.50 in.
3.6.3 when it is not practical to cerfe m idiograony within the Ilmitations of 3.6.1 or 3.6.2 or unen other radioactive isotones otrer than Iridium 1g2 or Cobalt 60 are used, tre crocedure small se proven satisfactory by actual demonstr'ation of penetrameter resolutions on the minimum tnickness of tne material radiograpned.
3.7 Radiograante 01ms. Screens 5 Radiograons 3.7.1 Radiographs sna11 be made using #11m fyse I or Tyoe
!!, Table 2, of ASTM SE 94 3.7.2 Intensifying screens wnen used, small ee Lead or Lead Alloys.
3.7.3 All film shall et processed & viewed in accordance witn recommended practice ASTM SE-94, cart !!!.
so==.ci m. m mo Page 45
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pusuc sanvoca COMPANY or cotonAoo 3.7.4 All radiographs shall be free from mechanical, enemical, or other blemisnes to the entent snat tney cannot mask or be confused with the image of any discontinuity in the ocject being radiograoned.
Such blantsnes include, but are not limited to:
a)
Fogging b)
Processing defects such as streaks, water marts, or chemical stains.
c)
Scratches, finger marks, crimps, dirtiness, static marks, smudges, or tears, d)
Loss of detail due to poor screen-to-flim contact.
e)
False indications due to defective screens or internal faults.
3.7.5 Scattered radiation may be reduced by suitable filtration.
As a
check on back-scattered radiation, a
lead symeel "0"
with minimum dimensions of 1/2" in height and 1/16" in thickness, shall be attached to the back of the flim holder.
If a Itght image of the " B '- appears on the radiograph, protection from the back scatter is insufficient and the ractograph is considered unacceptable.
3.7.6 The transmitted flim density through the radiographic tmage of the body of the appropriate penetrameter and the area of interest small be 1.8 minimum for single film viewing for radiographs made with an X-ray source and 2.0 mintmum for radiographs made with a gamma ray source.
For composite viewing of multicle film encoswees, eacn film of the comoestte set small rave a minimum density of 1.3.
The matimum density shall De 4.0 for either single or comoclite viewing.
A tolerance of 0.0$
in density is allowed for variations between densitomette readings.
3.7.7 O ther a densitometer or steo wed;e coesarison ffim small be used for judging film density reoutrements.
The density of step wedge compartson small ce vertfled witn a calineated sten nedge film l
traceacle to a National Stancard.
Ca11 oration I
sna11 se per QC:M-1.
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PutuC SERVICE COMPANY OF COLORADO 3.7.8 A system of radiograph idenstftcation ths11 be used to produce permanent t car t! /t c.t M or.
on tne radiograpn traceaDie to the joD numoer, component, weld or weld seem, or part numoers, as Jopropriate.
This identification system coes not necessarily require that the information appear as radiograante images.
In any case, this information shall not obscure the area of interest.
3.7.9 Location
- markers, which are to apoear as ractograchte images on the film, shall be placed on the part not on the cassette and their locations shall be marked on the surface of the part being radiogranned or on a man in a manner permitting the area of interest on a radiogrann to be accurately located on the part, and providing evidence on the radiograph that the reautred coverage of the region being esamined has been obtained.
4.0 SWARPNESS_OF RA0!0GAA84!C IMAGE 4.1 The following table 1: to be used as a guide but not for the rejection of radiograpns unless tne geometrical unsharpness exceeds 0.070 in..
Matertal Ug Thicknels.in.
Maximum.fn, under 2 0.020 2 through 2 0.030 Over 3 througn 4 0.040 Greater than 4 0.070 NOTE:
Material satekness is tne tM:aness on whten see constrameter is based, so== ici m. a. me T -- - ----- - --------- - - --- -- - ---- - -------- --- - -- - ------- -
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pusuc saavice com*** or cos.oaaoo 4.2 Geometric untmaroness of the radiograph shall be determined in accordance with:
Ug a Fd/0 where:
Ug geometrical unsharpness
=
F
= Source Size. A manufacturer's written statement documenting the actual or maximum Source size or focal spot shall be acceptable as Source Size verification.
- Ofstance, in.,
from Source Side of Weld or d
=
object being radiographed to the film.
0
=
distance, in., from Source of radiation to weld or object being radfographed.
5.0
! MAGE CUALITY !N0!CAf045 5.1 Radiography shall be performed with a technique of St.fficiont sensittvity to display the penetrameter image and the specified hole, wntch are essential indications of the quality im44e of the redtogaa:n.
The radiograons shall also disp'ay the identifying smeers & letters.
5.2 The penetrameters shall be manufactured and idenstfled in accordance with the reoutrecents or alternates allowed in ASTM SE-142 and Appendices of section V of the ASME Code.
A5ME standard penetrameters shall consist of snose l
specified in Attach. QC!M 300. Table 2.
I 5.3 Denstrameters of thicknesses specified in Attach. QC!M-300 Table 1 shall be used.
For any mater'al thickness range, a thinner penetrametet than Itsted for snat range may oe used, provided all otner escutrements for radiogranny are met.
For welds, the thienness on anten tne cenetrameter is based is the single well tnienness plus maximum reinforcement permitted.
Backing rirgs or strips are not to be considered as part of the weld or reinforcement snickness in penetrameter selection.
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pusuc sanvies conse4=v os cotonaoo 5.4 Penetrameters shall be placed adjacent to the weld seem except in instances where tne weld metal t:
not radtographically similar to the base matertal or wnere tne geometric configuration makes it imoractical, in wntch case the penetrameter shall be placed over the weld metal Where inaccessibility prevents the penetrameter being placed on the source side, a film side peaetrameter sna11 be placed on the film side of the joint, and a lead letter "F"
at least as nigh as the identification nummers small be placed adjacent to the penetrameter.
When configuration or size prevents placing the penetrameter on the object being radiograpned, it may be placed on a separate block of radiographic 411y sistlar material of a thickness eeutvalent to snat of the part or welding being radiograpntcally esamined.
5.5 Except as provided in 5.5.1 and 5.5.2, one penetrameter shall be used for each radiograph.
Eacn penetrameter shall represent an area of essentially untform radiograonic density as judged by a densitometer.
If the density of the radiograpn snrough the area of interest varies by more than minus 15 or plus 30 percent from the density through the area adjacent to the penetrameter, then an addttional genetrameter is required for the exceptional area or areas, except as provided in 5.5.3.b.
5.5.1 If one penetrameter acoears in the Itghtest area of a radiograon and anotner in tre darkest, the area around each genetrameter and the intervening densities on the radfograon are acceptable, provided the minimum density recutrements of 3.7.6 are met.
These accittonal penetrameters need not be normal to sne radiation source at these locations.
When calculating the allowable variation in density, sne calculation may be rounded to the nearest 0.1 *tthin the range specified in 3.7.6.
5.5.2 Where more than one film is used for an encosure, a genetrameter image small accese on eacn rectograon, escent when the source is placed on tne ants of the coject and a comolete circumference radiograoned with a single encosure is tanen, in wnten case at least snroe ecually soaced seest ameters are to no wied.
Wnere portions of longitudinal welds adjoining tne circumferential weld are being esamined simultaneously with sne circumferential neld, acetitional cenetrameters small :e pla:ed on tne longitudinal welds at tne end of sne sections of those welds ceing rectograoned. wnen an araay of cojects is radiogranaed, at least one cenetrameter small snow on eacn oeject imaged, w com a me Payn 49
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Pusuc senvics COMPANY OF COLORADO 5.5.3 If the penetrameter image does not show on one radiograph in double film technique but does snow in composite viewing, intercretation is permitted only by composite film viewing.
a)
If the weld reinforcement and/or backing strip are not
- removed, a
shim of material radiographically similar to the weld metal small be plated under the penetrameter.
The shim thickness shall be selected so the total thickness being radiographed under the penetrameter is essentially the same as the total weld thickness plus backing strip, if used and not removed, and other thickness variations such as in nozzle geometries.
b)
When thicker shims than required are used, the plus 305 density restriction may be exceeded, provided the required penetrameter sensitivity is displayed and density limitations are not exceeded.
6.0 M0!OGUPHIC ?!CHN!QUE 6.1 Sincie Wall Technique l
l 6.1.1 Radiography shall be doae using a single wall i
radiographic technique eenever practicable, i
Penetrameter Size and pla:ement shall be per l
Section 5.0.
6.1.2 For complete radiographic coverage if cylindrical girth welds, a minimum of four exposures 90' apart is recutred when the Source is placed outside and the film inside the object.
I 6.1.3 Attachment QCIM-30E contates sug;ested single wall radiographic techniques.
Other encosure arrangements may De made provided sney comply with
]
the requirements of tnis procacure.
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PUBUC SERVICE COMPANY OF COLORADO 6.2 Double - Wall Techniques 6.2.1 Double-Wall Viewing.
Unless otherwise specified, for materials and for welds in pipe tubes, 3 1/2 in.
(89 mm) or less in nominal outside diameter a technique may be used in which the radiation passes through two walls and the weld (material) in both walls is viewed for acceptance on the same film.
For welds, the radiation beam may be offset from the plane of the weld at an angle sufficient to separate the images of the source side and film side portions of the weld so there is no overlap of the areas to be interpreted, in which case a minimum of two exoosures taken at 90* to each other shall be made for each joint. As an alternate, the weld may be radiographed with the radiation beam positioned so the images of both walls are superimposed, in which case at least tnree exposures shall be made at 60* to each other.
For double wall viewing a source side penetrameter snall be used and placement shall be as indicated in Section 5.4 6.2.2 Sincle-Wall viewine a)
For materials and for. elds in pipe and tubes with nominal outside diameter greater than 3 1/2" (89 mm), radiogaannic examination shall be performed for single wall viewing only. An adequate numoer of exoosures shall be taken to ensure complete coverage, b)
For welds in pipe or tubes with a nominal outside diameter 3 1/2" (89 mm) or less, single-wall viewing may be used provided the source is offset from the clane of the weld centerline as outlined in 6.2.1.
As a minimum, three exposures 120' acart small be required.
A film sica eenetrameter shall be used and placement snall be as indicated in Section 5.4 l
6.3 rechniowes for section !X Oua11ricatioas l
6.3.1 Single wall technique with source side l
oenetrameters shall be
- used, except for i
- tecumferential butt welds jotning oice and tubes l
of nominal outside diameter of 3 1/2" or less, I
wnich sna11 be examined with the couble wall I
tecnnious with single wall viewing using a film I
side penetrameter, wcs m.a. no Page 51
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PusuC SERVICE CSMPANY CF C2LCRADO 7.0 TECHNICUE REQUIREWENTS 7.1 Radiographic examination shall be performed in accordance with a written and qualified technicua.
A copy of the technique shall be available to the inspector for reacy reference during film evaluation.
Eaca technique snall include at least the following information:
7.1.1 Number of films 7.1.2 Location of each film on the radiographed item 7.1.3 Orientation of location markers 7.1.4 Location of radiation
- source, including source-to-film distance and angle of beam 7.1.5 The kilovoltage (milliamperes or rads) and focal spot size (for x-ray machines) 7.1.6 The isotope type, inti;r;:i ty (in curies),
ar.d physical dimensions 7.1.7 Film brand and type 7.1.8 Type and thickness of screens 7.1.9 Masking, if used 7.1.10 Single or double viewing 8.0 ACCEPTANCE STANDAR0 l
8.1 Production or fabrications welds that are shown ey radiograpny to have any of the following types of discontinuities are unacceptacle.
3.1.1 Any type of crack or :ene of incomclete fusion or penetration.
8.1.2 Any other elongated inotcation wnich has a length greater than:
a) 1/4" for T up to 3/4" ine!usive, b) 1/3 7 for T from 3/4" to 2 1/4" inclusive, c) 3/4" for T over 2 1/4".
where T is tne thickness of the thinner portion of the weld.
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Pusuc sanvica COMPANY CF COLSCADO l
8.1.1 Any group of slag inclusions in line that have an aggregate length greater than T in length of 12 7 exceet where the distance between tne successive indications exceecs 6L where L
is longest indication in the group.
l 8.1.4 The maximum rounded indication dimension shall be l
20% of T or 1/8", whichever is smaller, exceot that l
an isoiated pore seoarated from an adjacent rounced l
indication by 1" or more.nay be 30% of T or 1/4",
l wnicrever is less.
l 8.1.5 The total area of reunded indications as determined l
frem the film shall not exceed 0.060 i souare inch l
in any 6" length of weld.
If the weld is less than l
6" long, the total pe-missable area of rounded l
indications shall be reduced in proportion.
l 8.1.6 In any 1"
length of weld or 2 T, whichevir is j
smaller, rounded indications may be clustered in l
total area to a concentration 4 times that i
permitted by 0.060 T (0.060 X T X 4).
Such l
clustered rounded indications shall be included in l
the total area of permissible indications in any 6"
]
length of weld which includes the cluster.
l 8.1.7 Al'gned rounded indications shall be acceptacle i
providing the summation of tne diameters of the i
rounded indications is no more than T in a length 1
12 T or 6",
whichever is
- less, providing each I
counced indication is scoarated by a distance of at l
least six times the diameter of the largest l
adjacent rounced indication.
Aligned rounded I
indications shall be incluced in the total area of l
permissible incications in any 6" lengtn of weld.
I 8.2 Qualification or cerformance test -cds that are shown by l
radiography to have any of tne following types of l
discontinuities are unacceptable.
l 8.2.1 Any type of crack or zone of incomplete fusion or l
I B.2.2 Any elongated slag inclusion wnien aas a length I
greater tnan:
l a) 1/8" for t up to 3/8 inch, inclusive i
b) 1/3 : for t over 3/8 to 2 1/4 inen, inclusive I
c) 3/4 inch for : over 2 1/4 inch ronuscim n.no Page 53
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8.2.3 Any group of slag inclusions in line that have an l
aggregate length greater than t in a lengtn of l
12 T, except when the distance between tne l
successiva inperfections exceeds 6L where L fs the l
length of the longest inperfection in the group.
l 8.2.4 The maximum permissible dimension for the rounded l
indications shall be 207, of t of 1/8", whichever is l
smaller.
l 8.2.5 For welds in material less than 1/8 inch in l
thickness, the maximum number of acceptable rounded l
indications shall not exceed 12 in a 6" length of l
weld.
A proportionately fewer number of rounded l
indications shall be permitted in welds less than l
6" in lenth.
l 8.2.6 For welds in material 1/8" or greater in thickness, I
the charts in Appendix I of ASME Section IX l
represent the maximum acceptable types of rounded l
indications illustrated in typically clustered, l
assorted, and randomly dispersed configurations.
~
l Rounded indications less than 1/32" in maximum l
diameter shall not be considered in the l
radiographic acceptance tests of welders and I
welding operators, in tnese ranges of material l
thicknesses.
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Page 54
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9.0 RADIOGRAPHIC REPORT FORM The results of the radiograph test shall be noted on the Radiographic Examination Report Sheet (Attachment QCIM-20) l 10.0 RECORDS and Radiographs generated as a result of this procedure Records the requirements sha11 be transmitted to the Record Center per in Procedures 0-17 and QCIM-2.
11.0 REFERENCE l
11.1 ANSI B31.1, " Power Piping" l
11.2 ANSI B31.7, " Nuclear Power Piping" l
11.3 ASME Section I, " Power B !!ars" ASME Section III, " Nuclear Power Plant Corsonents" l
11.4 ASME Section V, "Nondestruc.ive Examination" l
11.5 ASME Section VIII, " Pressure Vessels" l
11.6 ASME Section IX, " Welding and Brazing Qualifications" l
11.7 QCIM-2, " Preparation and Control of NCE Test Reports" l
11.8 QCIM-4,
" Nondestructive Examination Personnel l
11.9 Qualification and Certification" l
11.10 RPM-1, "PSC Incorporated Manual of Operating and Emergency l
Procedures for Radiography" l
12.0 ATTACFMENTS 12.1 CCIM-20A, Maximum Voltage for Steel QCIM-208, Maximum Voltage for Alloys of Copper and/or Hign 12.2 Nickel QCIM-20C, Maximum Voltage for Aluminum and Aluminum Alloys 12.3 12.4 CC M-200, Penetrameters 12.5 GCIM-20E, Single Wall Radiograpnic Tecnniques 12.6 CCIM-20F, Double Wall Radiographic Tecnniques m om.a.no Page 55
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5r:N SCfVICO' PUBUC SERVICE CEMPANY OF CSLC2 ADO MATERIAL THICKNESS, PENEIRAMETER CESIGNATICNS, AND ESSENT*AL HOLES FOR ALL RADIOGRAPHIC TECHNIQUES Penetrameter Nominal Source Sice Film Sice Single-Wall Material Thickness Essential Essential Range, in.
Designation Hole Designation Hole up to 0.25 incl.
10 4T 7
4T Over 0.25 thru 0.375 12 4T 10 4T Over 0.375 thru 0.'50 15 4T 12 4T Over 0.50 thru 0.625 15 4T 12 4T Over 0.625 thru 0.75 17 47 15 4T Over 0.75 thru 0.875 20 4T 17 4T Over 0.875 thru 1.00 20 4T 17 4T Over 1.00 thru 1.25 25 4T 20 4T Over 1.25 thru 1.50 30 2T 25 2T Over 1.50 thru 2.00 35 27 30 2T Over 2.00 thru 2.50 40 27 35 27 Over 2.50 thru 3.00 45 27 40 2T Over 3.00 thru 4.00 50 27 45 2T Over 4.00 thru 6.00 60 27 50 2T Over 6.00 thru 8.00 80 27 60 27 Over 8.00 thru 10.00 100 27 80 2T Over 10.00 thru 12.00 120 2T 100 2T Over 12.00 thru 16.00 160 2T 120 2T Over 16.00 :nru 20.00 200 27 160 2T PENETRAMETER dei!GNI.7:3N. THl:KNE55.
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Public FORT ST. VRAIN NUCLEAR GENERA 7iNG STATION age. -f *,
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION 1 of 15 pusue senvics comeAm or coi.onaoo TITLE: ULTRASONIC EXAMINATION OF CLASS 1 ANO 2 PIPING WELOS JOINING SIMILAR AND DISSIMILAR MATERIALS ISSUANCE 3""" 32..
oORC "d'8 5 o, JAN 8-1986 EF:ECTW E mEviEw oATE I %
1.0 PURPOSE 1.1 This procedure describes the manual ultrasonic angle beam examination of full penetration piping welds ranging in thickness from 0.2 to 6 inches.
This procedure is in accordance with the requirements of ASME Boiler and Pressure Vessel Code Section XI, 1980 up to and including Winter 81 Addenda.
2.0 APPLICABILITY 2.1 The principle objective of examiaation is the detection, location and evaluation of discontinuities within the weld and adjacent base metal. The -eld shall be examined by the angle beam tecnnique from the outside surface of the piping system.
3.0 GENERAL REQUIRESENTS 3.1 Personnel 3.1.1 All personnel performing narcestructive examination shall be certified in acc:rcance with ne condestructive examination :ersonnel cualification and certification wnten reflects tre gutcelines set forth by the scope of SNT-TC-1A.
Instrument 3.2.1 A culse-ecno ultrasonic f'aw cetection instrument shall be employed.
It sn411 generate, eceive, anc present on a catnode-ray ta:e (CRT) screen :ulses in a frequency range from :ne to 'tve.wH:.
3.2.2 The instrument shall be ecui::ec with a steccec gain c:ntrol caliorated in units :f 2 cB or less.
l 8C8+C; 372 22 wa2 Page 61
- ^;*-23
(@ Service ~
Public FORT ST. VRAIN NUCLEAR GENERATING STATION 2 of 15 D
rusuc sanvics comeAm or coton4oo 3.2.3 The system performance characteristics of the instrument shall be verified at least once a year.
3.3 Search Unit 3.3.1 Search units may contain either single or dual transducer elements.
3.3.2 The search units shall consist of a transducer and an angle beam wedge. The unit may be comprised of two separate parts or it may be an integral unit.
3.3.3 For general use, the search unit's transducer shall have an active area of not less than 0.04 sq inch nor more than 1.0 so inch.
Under certain circumstances, such as evaluation of indications, other sizes may be employed.
3.3.4 A nominal beam angle of 45 degrees in the material shall be employed. Other angles may be employed for evaluation of an indication, or where wall thickness, geometric configurations or metallurgical condition impedes effective use of 45 degrees angle beam for examination.
3.3.5 Nominal frecuency of 2.25 VHz shall be employed.
Other frecuencies may be employed if variables, such as production material grain structure, necessitate the use of other frequencies in order to assure penetration or improve resolution.
3.3.6 In general, shear mode of wave oropagation shall be used.
Refracted longitudinal mode of wave propagation may be used if grain structure or other condition impedes the use of shear wave.
3.3.7 The angle beam wedges sna11 be within : 3* of nominal value. This small te cneckec on a standard reference block such as IIW or Rompas onenever any doubt arises aceut the tolerances.
2.4 Couelant 3.4.1 An amoroved
- couglant, cacaole of c:ncucting ultrasonic vibrations from tre transcucer to tne examination surface, shall te usec.
3.4.2 The coualant identification and caten numoer snall be recorced on the calibration cata sheet.
8CW rCJ2 22 3843 Page 62
- M-33 0 Service ~
Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 15 pusuc ssRvics COMPANY OF COLORADO 3.5 Examination Coverage 3.5.1 Scanning shall be done with an overlapping of each scan at least by 10 percent of the transducer dimension measured perpendicular to the scan path.
3.6 Search Unit Movement 3.6.1 The rate of search unit movement shall not exceed 6 inches /second unless calibration has been verified at the higher scanning speed.
3.7 Scannino Sensitivity 3.7.1 Scanning shall be done at twice (+6 dB) the primary reference level as a minimum but recording of ultrasonic reflectors shall be done at the primary reference level.
3.8 Surface preparation 3.8.1 The examination surface shall be free of irregularities, Icose material, or coatings which may interfere with ultrasonic wave transmission.
3.9 Identification of Examination Areas 3.9.1 NED shall provide the pro:er identification system.
4.0 INSTRUMENT CALIBRATION 4.1 A check of the ultrasonic instruments screen height linearity shall be performed as descriced in Section 4.0, QCIM 36.
4.2 A check of the ultrasonic instruments amplitude control linearity shall be performed as cescribed in Section 5.0 of QCIM 36.
4.3 The instrument calibration may oe performed on any
. calibration block, including an IIW or Romoas block, and need rot be performed with the same searen unit used in the next examination.
1.4
'he instrument calibration for screen height anc amolitude control linearity shall be performed at tne ceginning of eacn period of extended use or every three months, whichever is less.
Ihis shall also be performec anenever any doubt arises aoout the instrument's functions.
meu.c.2n n-me Page 63
I
%**-23 h' )N pyhllC FORT ST. VRAIN NUCLEAR GENERATING STATION age 4 of 15 Service ~
Pusuc ssRvics COMPANY OF COLORAOC 5.0 BASIC CALIBRATION STANDAR05 5.1 The finish on the surfaces of the standard shall be representative of the surface finishes of the piping to be excmined.
5.2 The calibration standard shall conform to ASME Section XI, 1980 up to and including Winter 1981 Addenda.
6.0 SYSTEM CALIBRATION 6.1 General 6.1.1 Complete ultrasonic examination system calibration establishing the OAC curve, shall be performed prior to each examination, or series of similar examination.
6.1.2 Calibration shall include the complete ultrasonic examination system. Any change in search units, shoes, couolants, cables, ultrasonic instruments, recording devices, or any other parts of the examination system shall be the cause of calibration check.
The original calibration shall be performed on the easic calibration standard and calibration enecks snall te performed as per Article 6.3 of this procecure.
6.1.3 The maximum calibration indications shall be obtained with the sound beam oriented essentially perpendicular to the axis of the calibration reflector. The centerline of the search unit shall be at least 3/4 inen from the nearest side of tne standard.
6.1.4 The temperature di f ference :etween the examination and calibration standard surfaces snall not exceed 25'F (14*C).
6.1.5 Calibration shall be cerformed from the :utside surface of tne calibration standard.
=cau.ci m =. m Page 64
- =-li ypPublic (U Service ~
FORT ST. VRAIN NUCLEAR GENERATING STATION
$ fg rusuc senvice comeAny or cotonano 6.2 Calibration 6.2.1 The examination for reflectors parallel to the weld shall, in general, be performed by a one-half V path from two sides of the weld.
If variables, such as those referenced in Section 7.1 of this procedure, prevent the use of one-half V examination, the beam path shall be increased a minimum of one-half V until complete examination volume is covered.
The examination for reflectors transverse to the weld shall be performed by one-half V path in two directions along the weld.
It may also be necessary, particularly in thin wall piping, to increase the examination beam angle.
808W 'C; r2 22 3ea3 Page 65
- -;i MPublic FORT ST. VRAIN NUCLEAR GENERATING STATION (C/ $4fVlCe*
6 of 15 Pusuc sanvoca COMPANY OF COLORADO 6.2.2 One-half v path Technique To establish the sweep range, obtain the maximum response from the circumferentially oriented I.O.
notch, position this response at 0 on the sweep.
Next, obtain the maximum response from the 0.0.
notch, position this response at 8 on the sweep.
Continue positioning these responses until no further adjustment is necessary. Again obtain the maximum response from the I.O. notch and using the delay control only, shift this response to 8 on the
- sweep, t.cck the range and delay controls as the sweep is now established. Now obtain the maximum response from the axially oriented I.O.
notch and mark its location on the screen.
The slope and shape of the OAC curve shall be established using the 1/4T and 3/4T holes drilled parallel to the long axis of the calibration standard. Adjust the peak amolitude of the hole giving the higher response to 80 percent FSH. Mark the amplitude and location on the screen.
Without adjusting the instrument controls, maximize response from the remaining hole and mark its amplitude and location on the screen. Connect the amplitude points with a smooth curve and extracolate this curve an additional 1/4T to cover ';il examination range.
Next establish reference se9sitivity by setting the maximum response from the !.0. notch, at the OAC curve level.
This curve (CAC) is the primary reference level and recorcing of ultrasonic reflectors shall be perforated at tnis sensitivity.
As an alternate, a calibration using sound path may be used. The hori: ental base line culibration.
In inches, may te estamitshed using an IIW Block, Rompas Block or Miniature Angle beam Slock.
The range selected sna11 en suen snat at least 60 percent of the base line will reoresent tae examination area.
After tne s eep range is calibrated the sloce anc shace of the CAC curve and reference sensitivity shall ce estaclisnec ey tre tecnnique cescriced aeove.
scauC.T'2 U m3 Page 66
- -
- i hj'iPublic FORT ST. VRAIN NUCLEAR GENEDATING STATION g 7 of 15 Service ~
pusuc senvics comenav or coton4oo 6.2.3 Greater Than One-half V path Technique Using the required V paths, te full V, one and one-half V etc.,
establish the sweep range calibration by positioning responses from the appropriate 10 and 00 notches at convenient intervals along the sweep and mark notch locations on the screen.
The CAC shall be established by setting the maximum response from the one-malf V path ID notch to 80 percent (FSH) and mark the location on the screen.
Without adjusting the instrument controls, obtain the maximum response from the remaining notch echo (es) in the test region and mark the location (s) on the screen.
Connect the maximum amplitude points with a smooth curve to form the OAC. This curve is the primary reference level and recording of ultrasonic reflectors shall be performed at this sensitivity.
6.2.4 Recordino of Calibration Data Particulars of system calibration shall be recorded on the Calibration Data sheet.
6.3 Calibration Check 6.3.1 A system calibrat on
- neck, which is the verification of the instrument sensitivity and sweep range calibration, small be performed at the start and finish of each examination or series of similar examination, with any change in examination personnel, and at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> curing an examination.
Calibration enecks may be performed on either the standard used for initial calibration, or a simulator.
6.4 Corrective Action 6.4.1 If any point on the CAC carve nas decreasec 20 percent or 2 c8 of its amplituce, all cata sneets since the last calibration snall be marnec void. A new calibration snall be made and recorcec anc.tne voided examination area shall be reexamined.
6.4.2 If any coint on the OAC curve nas increasec, ore than 2 C*.
or 2 c3 of its amolituce, recorced incications taken since tr
'ast valfd calforation or calicration check snall :e esexamined, newc> m u ms Page 67
- -:3 pPublic (V Service ~
FORT ST. VRAIN NUCLEAR GENERATING STATION 3 of 15 Pusuc senvics company or cotonaco 6.4.3 If any point on the CAC curve has moved on the sweep line more than 10 percent of the sweep division
- reading, correct the sweep range calibration and note tne correction on the examination record.
If recordable reflectors are noted on the data sheets, those data sheets shall be voided, a new calibration shall be recorded, and the voided examination areas shall be reexamined.
7.0 EXAMINATION 7.1 Reflectors parallel to the Weld Seam The angle beam examination for reflectors parallel to the weld shall, in general, be performed by a one-half V path from two sides of the weld.
If variables such as access, weld configuration or wall thickness preclude half V examination, the examination shall be performed by at least a full V path from one sica of the weld.
7.2 Reflectors Transverse to the Weld Seam The angle beam examination for reflectors transverse to tne weld shall be performed on the aeld crown on a single scan path to examine the weld re:t by one-half V path in two directions along the weld in a single beam path.
If variables such as weld surface conditions preclude circumferential scans on the weld crown.
The examination shall be performed on the base material adjacent to tne weld's toe employing the one-half V path 60* snare wave technicue.
Scanning approximately 15' towares the weld centerline on a single scan path, in two cirections, on both sides of the weld crown, when accessiole.
l Calibration of the circumferential scan emoleying 15' skew I
angle sna11 ce performec in conformance witn 6.2.2, and y I
setting the sensitivity from sne I.D.
noten at l
approximately 15' from perpendicular.
7.3 Ofrections and Extent of Scanning Ult *asonic energy shall pass in all the recuired directions and the extent of scanni g snall be sacn :nat tre ultrasonic beam passes tnrougn the entire examination j
volume as incicated in Attachment CC M-38A of tnis precedure.
8CsgeiC1272 22 M43 Page 68
- - - - = - - - -
Z:w-3 SPublic FORT ST. VRAIN NUCLEAR GENERATING STATION (v Service ~
a 9 of 15 pusuc sanvics comeAn or cotonaoo 8.0 CATA RECORDING AND EVALUATION 8.1 Each indication that exceeds 20%
- DAC, shall be i
investigated to determine maximum percent of DAC.
l 8.2 For each indication that exceeds 50% of reference level (OAC) but does not equal 100% DAC, the following information shall be on the Indication Data Sheet.
8.2.1 Search unit location at peak amplitude and scan direction.
8.2.2 Peak amplitude as either Ob from reference level, or as a percent of DAC.
8.3 For each indication that equals or exceeds 100% DAC, the search unit location, orientation and the following information, shall be recorded on the indication data sheet.
8.3.1 Peak amplitude as either dB from the reference level (100% CAC), or as a percent of the OAC curve, sweep reading to reflector, search unit position (distanca from weld centerline) and sound beam direction.
8.3.2 Minimum sweep reading to eflector and position of search unit at reference level.
8.3.3 Maximum sweep reading to reflector and position of search unit at reference level.
8.3.4 Search unit positions or locations parallel to the reflector at the end points where tne reflector amplitude equals the reference level.
(length of reflector).
S.4 Indications that can be determined to be of a geometric or metallurgical origin (ie weld geometry, weld-to-base metal interface) need not be recorded on an indication data sheet. However, the amplitude and location from reference shall be recorded in the comments section of the calibration data sheet.
3.5 The cresence of a reflector of geometric origin small be confirma by one of tne following.
Fonu n c> 172. it. 3us Page 69
C:9-33 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION a
of 15 Service'-
eusuc sanvice comeAm or cos.onaoo 8.5.1 Review of the fabrication drawings of the pire weld edge preparation.
8.5.2 Review of the records from previous non-destructive examinations.
8.5.3 Perform supplemental non-destructive examinations.
9.0 RECORDS 9.1 A detailed ultrasonic examination report shall be prepared using the applicable report forms provided at the end of this procedure and any additional sketches or photographs as may be applicable.
If no reportable indications are detected it shall be so noted on the appropriate report form.
9.2 Data shall be entered, as required for each item in the blank space provided on the calibration data sheet, and if used, on the indication data sheet. Where data is not germane for the specific item the blank space shall be marked N/A to indicate that data is not applicable.
9.3 Prompt (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) notification of reportable indications shall be made to the representative cesiglated by NE0.
10.0 REFERENCES
10.1 ASME Section XI, 1980 Edition up to and including Winter
'81 Adcenda.
10.2 CCIM-4 Nondestructive Examination personnel Qualification and Certification.
10.3 QCIM Calibration of Ultrasonic Flaw Cetectors.
11.0 ANACHMENTS 11.1 QCIM-3SA - Examiaation Volume
';.2 QCIM-338 - Inservice Inspection Calibration Cata
.. 3 QCIM-38C - Inservice Inspection Incication Data
- .a CC
- M-330 - Inservice Inspection Skat
- n Sheet 8C#M 'C) 372 - 22 3k3 Page 70
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7.1 None sow ci m.:2 ano Page 71
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Page 75
T QCIM-36 Issue 3 0 Service Public FORT ST. VRAIN NUCLEAR GENERATIN3 STATION Page 1 of 4 pusuc senvece comramy or cotonaco l TITLE:
CALIBRATION OF ULTRASONIC FLAW DETECTORS ISShANCE
)
AUTHORIZED
-cy ~ W T' 7 BY
[y",C PORC 8 8 7 SEP 6 :1985 ll7,ECME 1.0 PURPOSE l
This procedure describes the recuirements of and the methods used in measuring the screen height linearity and the amplitude l
control linearity of pulse echo type ultrasonic flaw detectors.
2.0 SCOPE This procedure conforms to the latest editions and addenda of the applicable codes and applies to all pulse echo type l
ultrasonic flaw detectors used by Public Service Company.
3.0 GENERAL REQUIREMENTS 3.1 Personnel performing these calibrations /ceasurements shall l
be qualified in accordance with Procedure QCIM-4.
3.2 The instruments shall be the pulse echo type which can generate, receive and present on a cathode ray tube.
(CRT), high frequency sound energy impulses.
3.3 Both the screen height linearity and the amplitude control linearity shall be measured at the beginning of each period of extenced use or every three months, wnienever is less.
3.4 The search unit shall be of a frequency and angle so as to obtain the maximum response from the reference holes and notches when the sound beam is oriented perpendicular to the axes of thesi reflectors. (See Attacneent QCIM-36A) 3.5 Transducers may be fitted with shoes to maintain adeouate sound penetration or the proper sound beam angle in the test material.
3.6 Couplant shall be any material having good wetting characteristics that will provide for the transmission of ultrascund from the search unit to the test material.
et somsim.m see Page 76
r QCIM-36 Issue 3 0 Service ~
Public FORT ST. V2AIN NUCLEAR CENERATIN3 STATION Page 2 of 4 pusuc senvoca company or cotonano 1
3.7 Calibration blocks shall consist of IIW Reference Block (See Attachment QCIM-36A Fig. 2) or any calibration block l
which will provide amplitude differences and contains j
other convenient reflectors.
3.3 Settings and readings must be estimated to the nearest 1%
i of full screen.
4.0 MEASUREMENT OF SCREEN HEIGHT LINEARITY l
4.1 The ultrasonic instrument must provide linear vertical presentation within 25% of the full screen height for at least 80% of the full screen height (baseline to maximum calibrated screen point). To verify this, perform the following:
4.1.1 Position an angle beam search unit as shown in Attachment QCIM-36A, Fig.
1 or a straight beam search unit as shown in Attachment QCIM-36A, Fig. 2 so that indications can be observed from two reference points as shown in Attachment QCIM-36A, Fig. 3.
4.1.2 Adjust the search unit position to give a 2:1 ratio of amplitudes between the two indications with the larger set at 80% of full screen neight.
4.1.3 Without moving the search unit, adjust insitivity (gain) to successively get the larger indication from 100% to 20% of full screen height, in 10%
increments and read the smaller indication at each setting.
The reading must be 50% of the larger indication, within 5% of full screen height.
PCAMIC1372 22 3863 Page 77
QCIM-36 Issue 3 0 Service ~
Pubil]
FORT ST. VRAIN NUCLEAR CENERATIN3 STATION Page 3 of 4 rusuc senvece comeAmy or cotonAoo 5.0 MEASUREMENT OF AMPLITUDE CONTROL LINEARITY 5.1 The ultrasonic instrument must utilize an amplitude control, accurate over it's useful range to 220% of the nominal amplitude
- ratio, to allow measurement of indications beyond the linear range of the vertical display on the screen.
To verify this, perform the following:
5.1.1 Position an angle beam or straight beam search unit so the indication from a reference hole in a reference block is peaked on the screen.
5.1.2 With the increases and decreases in attentuation shown in 5.1.3, the indication must fall within the specified limits.
5.1.3 Indication Set at dB Control Indication Limits
% of Full Screen Change
% of Full Screen 80%
-6 dB 32 to 48%
80%
-12 dB 16 to 24%
40%
+6 dB 64 to 96%
20%
+12 dB 64 to 96%
6.0 RECORDS 6.1 Results of this calibration shall be documented en the ultrasonic test report form, Attachment CCIM-2C, ano shall be administered and transmitted in accordance with procedure QCIM-1.
7.0 REFERENCES
7.1 ASME Section V - Nondestructive Examination 7.2 QCIM Equipment and Tool Calibration 7.3 QCIM-2, Preparation and Control of NDE Test R2 ports 7.4 QCIM-3, Nondestructive Examination Personnel Qualification and Certification 8.0 ATTACHMENT 8.1 Attachment QCIM-36A, Linearity l
roncam.n ms Page 78
QCIM-36 Issue 3 O Service'"
Pubila FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 rusuc senvece couramy or cotonaoo l 9.0 COMMITMENTS I
The step (s) and section(s) listed below may not be deleted l
without issuance of comparable controls. The procedure itself, l
if initiated as a result of commitment corrective action, may l
not be deleted without issuance of comparable controls.
l 9.1 None I
FORMICJ 372 22 3043 Page 79
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