ML20128H133
| ML20128H133 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/06/1985 |
| From: | Singh B Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-62870, NUDOCS 8507090422 | |
| Download: ML20128H133 (30) | |
Text
- _ _ _ _ _ _ - _ - _ _
4 JUN 0 61985 N
Docket No.: 50-41R.
APPLICANT:
Duquesne Light Company (DLC)
FACILITY:
Beaver Valley Power Station, Unit 2
SUBJECT:
MEETING
SUMMARY
- PRESERVICE INSPECTION PROGRAM q
On December 12,198Yr, NRC and applicant representatives met in Bethesda, Maryland to discuss Preservice Inspection (PSI) Program. A meeting notice is enclosed as Enclosure 1.
A summary of the major topics of discussion is provided in Enclosure 2 which also contains agenda and attendance list.
The applicant is still preparing the PSI program. At the meeting, the staff agreed to provide written comments (Enclosure 3) on the preliminary PSI program that was submitted on June 29, 1984. The staff is prepared to discuss the review with the applicant at his convenience.
B. K. Singh, Project Manager Licensing Branch No. 3 Division of Licensing
Enclosures:
As stated cc: See next page DISTRIBUTION Docket File LB#3 Reading BKSingh JLee GWKnighton DL:LB#3 3
BKSingh ighton 05/30/85 05p/85 8507090422 850606 PDR ADOCK 05000412 G
____--____________.-_-____.._____)
Beaver Valley Mr. John J. Carey Vice President, Nuclear Duquesne Light Company Robinson Plaza Building, No. 2, Suite 110 PA Route 60 Pittsburgh, Pennsylvania 15205 Gerald Charnoff, Esq.
Mr. R. E. Martin, Manager Engineering Jay E. Silberg, Esq.
Beaver Valley Two Project Shaw, Pittman, Potts & Trowbridge Duquesne Light Company 1800 M Street, N.W.
Robinson Plaza Building No. 2, Suite 110 Washington, DC 20036 PA Route 60 Pittsburgh, Pennsylvania 15205 Mr. C. W. Ewing, Quality Assurance Zori Ferkin Manager Assistant Counsel Quality Assurance Department Governor Energy Council Duquense Light Company 1625 N. Front Street P. O. Box 186 Harrisburg, PA 15105 Shippingport, Pennsylvania 15077 Mr. John J. Carey Vice President, Nuclear Duquense Light Company Director, Pennsylvania Emergency P. O. Box 4 Management Agency Pittsburgh, Pennsylvania 15205 Room B-151 Transportation & Safety Building Harrisburg, Pennsylvania 17120 Mr. T. J. Lex Mr. Thomas Gerusky Westinghouse Electric Corporation Bureau of Radiation Protection Power Systems PA Department of Environmental P. O. Box 355 Resources Pittsburgh, Pennsylvania 15230 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Mr. P. RaySircar Stone & Webster Engineering Corporation BVPS-2 Records Management Supervisor P. O. Box 2325 Duquesne Light Company Boston, Massachusetts 02107 Post Office Box 4 Shippingport, Pennsylvania 15077 Mr. Glenn Walton U. S. NRC John A. Lee, Esq.
P. O. 181 Duquesne Light Compary Shippingport, Pennsylvania 15077 1 0xford Centre 301 Grant Street Mr. Thomas E. Murley, Regional Admin.
Pittsburgh, Pennsylvania 15279 U. S. NRC, Region I 631 Park Avenue King of Prussia, Pennsylvania 15229
F
, Mr. - E F. Kurtz, Jr., Manager Regulatory Affairs Beaver Valley Two Project Duquense Light Company Robinson Plaza Buidling No. 2 Suite #210 PA-Route 60 Pittsburgh, Pennsylvania 15205
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Docket No. 50-412 MEMORANDUM FOR: George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing FROM:
.B. K. Singh, Project Manager Licensing Branch No. 3, Division of Licensing
SUBJECT:
FORTHCOMING MEETIN8 BETWEEN THE NRC AND DUQUESNE LIGHT COMPANY DATE & TIME:
December 12, 1984 9:00 AM LOCATION:
AR-2242 Air Rights Building Bethesda, Maryland PURPOSE:
To discuss Preservice Inspection Program.
PARTICIPANTS *:
NRC B. Singh M. Hum C. Cheng et. al.
Ducuesne Light Company J. Szyslowski et. al.
- k by B. K. Singh, Project Manager Licensing Branch No. 3 Division of Licensing cc: See next page
- Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open fleeting Statement of NRC Staff Policy",
43 Federal Register 28058, 6/28/78. Those interested in attending this meeting should make their intentions known to the Project Manager, B. K. Singh, at (301) 492-8423, by no later than December 11, 1984.
MEETING SUMARY - BEAVER VALLEY UNIT 2 PRESERVICE INSPECTION PROGRAM This summary was prepared with the technical assistance of DOE Contractors from the Idaho National Engineering Laboratory.
A public meeting was held in Bethesda, MO on December 12, 1984. Attachment 1 is the agenda that was followed. Attachment 2 lists the meeting attendees.
Under agenda item 1, Objectives of Review, the joint responsibilities of the region and NRR were explained. A summary of the NRR review was presented and the information required to complete the staff review was described. The applicant and the staff agreed that no decision would be made at the meeting regarding acceptability of weld selections for PSI.
Under agenda item 2, Schedule and Status of PSI, a handout (Attachment 3) was provided. The Applicant stated that the examination procedures are being updated to the W-80 Addenda. The staff agreed to transmit to the Applicant written comments on the PSI program submitted on June 29, 1984 including procedures.
For agenda item 3, Class 2 Piping Weld Selection 83 Code, Winter 83 Addenda, the Applicant docketed a proposal to utilize the W-83 Addenda in a letter dated October 19, 1984. The information in that letter was not current. The Applicant stated that work on Class 2 weld preparation for PSI had been stopped and that walkdowns of the Class 2 piping systems in January 1985 were planned if agreement on the piping weld selection approach could be obtained. The Applicant's detailed analysis of applying the W-83 Addenda was then presented and a handout (Attachment 4) was provided. Use of the W-83 Addenda was desired to make the PSI weld selection more compatible with anticipated ISI require-ments. This is important to assure that the required welds are profiled during the preservice examination. Preparation of welds for inservice examination before plant operation is desirable because radiation exposure is not a problem. Other advantages of the W-83 Addenda is that all surface only
m
)
. examination requirements are deleted (except for socket weld and cranch connections), and volumetric examination is applied to pipe with wall thick-nesses 3/8 inch and greater, instead of only pipe with wall thickness greater than 1/2 inch.
The Stainless Steel Systems Summary Table, in Attachment 4, shows the total number of welds to be examined dropping from 467 to 133 when comparing the 80W80 Code with the 74575 Code for weld selection (10 CFR 50.55a(b)(2)(iv) requirement) with the requested use of the 83W83 Code. Also the QSS and RSS systems (ECCS systems) are totally exempt in the 74S75 Code selection. This is not compatible with NRC Question 250.1 which states in part:
" Paragraph 50.55a(b)(2)(iv) requires that ASME Code Class 2 piping welds in the Residual Heat Removal Systems, Emergency Core Cooling Systerz and Containt.ent Heat Removal Systems shall be examined. These systems could not be completely exempted from preservice volumetric examination br ed on Section XI exclusion criteria contained in IWC-1220. To satisfy the inspection requirements of General Design Criteria 36, 39, 42, and 45, the preservice inspection prcgram must include volumetric examination of a representative sample of reld in the RHR, ECCS and Containment Heat Removal System."
Additions to the austenitic Class 2 volumetric and surface examination list were discussed. Sampling plans of 7.5% and 10% were included in PSI Progrars submitted by other applicants and described in these SERs. The Applicant agreed to consider these areas further.
The Carbon Steel Systems Summary TaDie, Attachment 4, contains half as many welds for examination with the 83W83 Code rules as with the 80W80 Code rules.
The Applicant was not planning to perform a preservice volumetric examination of the high energy fluid system subject to augmented ISI based on SRP Section 3.6.2.
Use of radiography for the augmented ISI and the possible use of
F
. fabrication radiographs for " baseline" information were discussed.
Paragraph IWA-2100 of Section XI defines inservice inspection to include preservice inspection requirements unless a distinction is made in the text. Other Applicants have performed a baseline examination of welds subject to augmented ISI. The staff will provide the Applicant with a letter to this subject.
Problems with the effectiveness of radiography for detection of service-induced flaws were discussed.
For agenda item 4, Review of PSI Plan, the staff has prepared an SER that defines the information required to complete the review. The Applicant expects to have their PSI plan iseued around April 1, 1985.
Examinations are scheduled to begin in June 1985.
For agenda item 5, Examination Selection Criteria for Class 1 Piping Welds, the Applicant explained that the Class 1 piping do not have longitudinal seam welds and that static cast fittings are used.
Exclusion from examination criteria based on make-up capacity and chemistry control are not being used in the PSI program.
For agenda item 6, Piping System Examinations, centrifugally cast pipe and statically cast fittings are used in the primary coolant loop. The number of calibration blocks for the centrifugally cast and statically cast materials was discussed. Significant differences in acoustical properties between statically cast, centrifugally cast and ferritic components have been observed and cali-bration blocks should be fabricated for each type of material.
Many of the Class 2 welds which may be scheduled for ultrasonic examination have an overlay weld deposit applied during fabrication to meet dimensional requirements. The Applicant is evaluating the volumatric examination requirements for this piping.
. The basic calibration blocks and examination process should take this cladding into account. The Applican', plans to identify the location of the overlaid welds during the system walkdowns.
For agenda item 7, Reactor Vessel Examination, the areas to receive special near surface examination were shown.
Limitations to examination will be submitted as relief requests.
For examination of other vessels, the use of notes in the PSI plan covering impractical Code requirements was discussed. One note indicates that surface examination will be used in lieu of volumetric examination for thin wall vessels. Ultrasonic examination of thin wall vessels can be effective if higher frequency, smaller size search units are selected. The staff does not expect to review alternatives to Code requirements as noted in the PSI Program.
For agenda item 8, Steam Generator and Pressurizer Nozzle Examinations, the Applicant expects that relief from Code requirements would be requested.
For agenda item 9, UT of Bolts and Studs, the use of a flat bottom hole for calibration reflectors may not be effective for the detection of flaws.
Improvements of Appendix VI of Section XI (W-83 Addenda) were discussed. The Applicant agreed to submit the examination procedures for bolting with the PSI plan.
For agenda item 10, Relief Requests, the format and the necessary technical justification for relief requests were discussed.
The Applicant provided a specification to be used by the verder for the 100%
eddy current examination of steam generator tubing.
I AGENDA FOR BEAVER VALLEY UNIT 2 MEETING PRESERVICE INSPECTION PROGRAM DECEMBER 12, 1984 9:00 a.m.
Topics for Discussion:
1.
Objectives of Review (NRC Staff Presentation) 2.,
Overview of Schedule and Status of PSI (Applicant Presentation) 3.
Class 2 83 Winter 83 Addenda Piping Weld Selection (Applicant Presentatio,n and Discussion)
~
4.
Review of PSI Plan (NRC Staff Presentation) 5.
Examination Selection Criteria for Class 1 Piping Welds and Exemptions Based on IWB-1220 and IWC-1220 (Discussion) 6.
Piping System Examinations--Procedures, Examination Coverage, Weld Build-up, Practice with One-Sided Access, Practice with Limitations to Examination, and Results (Discussion) 7.
Reactor Vessel Examination -- Calibration blocks, procedures, results, areas that are impractical to examine, Regulatory Guide 1.150, and examination for surface defects (Discussion)
g-8.
Steam Generator and Pressurizer Nozzle Examinations (Discussion) 9.
UT of Bolts and Studs (Discussion) 10.
Relief Requests (Discussion)
- 11. Questions and Summary O
- 6
ATTENDANCE LIST BEAVER VALLEY, UNIT 2 PRESERVICE INSPECTIDN PROGRAM December 12, 1984 B. K. Singh, NRC/NRR/DL/LBf3 R. A. McBrearty, NRC/RI J. F. Cook, EGAG Idaho A. F. Mosso, DLC/QA J. J. Szyslowski, DLC M. A. Zaki, DLC D. C. Adamonis, Westinghouse M. R. Hum, NRC G. W. Martin, DLC M. A. Weaver, Westinghouse J. R. Houghton, DLC-NCD Engineering B. Lefebvre, Westinghouse W. A. Weis, SwRI J. J. Hayden. DLC/SQC R. M. Reba, DLC W. H. Sikorski, DLC C. Cheng, NRC/NRR
1 Assa 11 Pett!svtCE tusPECTtou (PSt PROCRAM S PSI PROGRAM OvtRALL STATUt Tranesitted PSI Prestas to WRC*fer appreest 6/84 Develegemet of Class t' weld selectise Criteria (83W8M to reduse r equired esaminettoe 12/04 0 P91 PROCRAM PtANS STATUS Class I and 1 Pressure ter minina Ceaseeest e tam.
o Plan sad procedures secolete:
6/45 tsemisatten eeneelle to starts 6/05
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METHODOLOGY 1.
Line Designation Tables a)
Determine lines at 6", and It 2" in NHSI.
b)
Exempt systems by line size.
c)
Exempt systems by temperature and pressure if applicable.
2.
Remaining Systems:
a)
List all lines in nonexempt size range.
b)
Identify lines on Flow Diagram, c)
Apply IWC-1220 exemptions on a line-by-line
- basis, d)
Identify remaining nonexempt lines.
3.
Nonexempt Lines:
a)
Compare Iso to Flow Diagram.
b)
Count welds on Iso, c)
Tabulate by type s butt, branch, term. end, etc.
d)
Identify required examinations.
e)
Tally welds and examination methods.
4.
Independent review of 1, 2, and 3 5.
Record tallies on Summary Sheets.
6.
Apply Section XI :s! alations for required exams.
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CLASS 2 EXDIPT PIPING WELD EXANINATION SLBW4ARY SHEET Sect. XI, Table IWC-2500-1, Exam. Cat. C-F-1 (Sheet 1 of 2)
STAINLESS STEEL SYStetS:
System 80W80 Sect. XI Rules 8 3W8 3 Sect. XI Rules BDG
- Exempt IWC - 1220 (c)
Exempt IWC - 1222 (a)
Exempt IWC - 1220 (c)
Exempt IWC - 1222 (a) cys DAS
= = = = = - -
- Exempt IWC - 1220 (b) (c)
Exempt IWC - 1222 (a) (c)
DGS
Exemp t IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
FNC
Exempt IWC - 1220 (b)
Exempt IWC - 1222 (c)
Gr;
Excep t IWC - 1220 (c)
Exempt IWC - 1222 (a)
===-
pCs
Exempt IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
---==--- =
IAC
Exempt IWC - 1220 (b) (c)
Exempt IWC - 1222 (a) (c) gx;
Exempt IWC - 1220 (c)
Exempt IWC - 1222 (a)
PAS
-- - - _ - ---- Emeept IWC - 1220 (c)
Exempt IWC - 1222 (a)
~
=---- Exempt IWC - 1220 (c)
Exempt IWC - 1222 (a)
RCS SSR
Exempt IWC - 1220 (c)
Exempt IWC - 1222 (a) vie;
==---- =-- Exempt IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
IWC-1220 (b): Componients of systems, or portions IWC-1222: Components within systems, or portions of systems, other than Desidual Heat Removal of systems, other than the RHR, ECC, and Systems and Emergency Core Cooling Systems, CHR Systems.
that are not required to operate above a pressure of 275 psig or above a temperature IWC-1222 (a): vessels, piping, pumps, valves and of 2000 F.
other components NPS 4 and smaller.
IWC-1220 sc): Component connections (including IWC-1222 (c): Vessels, piping, pumps, valves and nozites in vessels and pumps), piping and other components of any size in systems or asr. ciated valves, and vessels and their portions of systems that operate (when the ate.chments that are 4" nominal pipe size system function is required) at a pressure and smaller.
equal to or less than 275 psig and at a temperature equal to or less than 2000 F.
W CLASS 2 EXEMPT PIPING WELD EXAMINATION SL394ARY SHEET Sect. XI, Table IWC-2500-1, Exam. Cat. C-P-1 (Sheet 2 of 2)
CARBON STEEL SYSTEMS:
System 80W80 Sect. XI Rules 8 3W8 3 Sect. XI Rules BDG
===---- Exempt IWC - 1220 (c)
Exempt IWC - 1222 (a)
Exempt IWC - 1220 (b)
=--
Exempt IWC - 1222 (c)
CVS
Exemp t IWC - 1220 (b) ----------
Exempt IWC - 1222 (c)
FPW
Exempt IWC - 1220 (b) ----------
Exempt IWC - 1222 (c)
Ewt
==
===-- Exempt IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
-- --- Exempt IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
--- =-
- Exempt IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
HVR
Exempt IWC - 1220 (b)
Exempt IWC - 1222 (c) pCS
- Exempt IWC - 1220 (b) (c) ------
Exempt IWC - 1222 (a) (c)
== Exempt IWC - 1220 (b) (c) ------
Exempt IWC - 1222 (a) (c) ------
rr.c
Exempt IWC - 1220 (c) ----------
Exempt IWC - 1222 (a)
=- Esempt IWC - 1220 (b) ----------
Exempt IWC - 1222 (c)
SWS IWC-1220 (b): Components of systems, or portions IWC-1222: Components within systems, or portions of systems, other than Residual Heat Removal of systems, other than the RNR, ECC, and Systees and asergency Core Cooling Systems, CHR Systems.
that are not required to operate above a pressure of 275 psig or above a temperature IWC-1222 (a): Vessels, piping, pumps, valves and of 2000 F.
other components NPS 4 and smaller.
IWC-1220 (c): Component connections (including IWC-1222 (c): Vessels, piping, pumps, valves and nozzles in vessels and pumps), piping and other components of any size in systems or associated valves, and vessels and their portions of systems that operate (when the attachments that are 4" nominal pipe size system function is required) at a pressure and smaller.
equal to or less than 275 psig and at a temperature equal to or less than 2000 F.
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l CLASS 2 PIPIl0G WELD EXAMINATION SENSEARY SitEET Sect. II, Table IWC-2500-1, Exas. Cat. C-F-1 (Sheet 1 of 2)
STAltE.ESS STEEL SYSTEMS:
s 1
2 3
4 5
6 7
8 9
10 11 12 13 14 74S75 Sect. XI Rules 8 3W83 Sect. XI Itules leonexempt Welds ISI Req'd Exams Nonexempt Welds ISI Iteq'd Exams 3 vol I
I vol 3
I Vol I 8
7.5%
I
' vol Systee Surf + and = Total Surf + and = Total Surf + and + Exas = Total As % of Prorata = Surf + and Only a Surf e Only e Surf Only l Surf a N/A e SS Welds Share l Only e Surf Cas 110 0
110 54 0
54 526 431 110 1057 40.192 80 44 36
= Es -opt IWC - 1220 lb)
=
0 47 125 172 6.595 13 0
13 Q55 ass 214 0
214 108 0
108 0
64 203 267 10.238 20 0
20
== Except IWC - 1220 (b) ---------
0 126 28 154 5.905 12 0
12 RSS
==
SIS 341 152 493 216 89 305 176 494 278 948 36.350 71 19 52 l 89 665 l 152 l 817 702 l 1162 l 744 m al 378 467 2608 100 196 63 133 NOTES:
A.
10CFR50.55a (b) (2) (iv) invokes requirements to use the 74S75 Code for the above systems to deter-eine only exemption criteria (IWC-1220) and selection critesla (INC-2411 and Table IWC-2520, Cat. C-F and C-G).
The preservice requirement and the specific required examination method remain in accordance with the Code of choice, namely 80W80.
B.
The high number of welds in the CHS and SIS Systems which are candidates for surface and not volumetric examinations under the 83W83 Code is due largely to the f act that 2" NPS lines in these systems are of socket weld construction.
C.
Exemption IWC-1220(b): Components in systems or por tions of systems, other than emergency core cooling systems, which do not function during normal reactor operation.
(
Advantages of Utilizing the 83W83 Code for SS Systems:
An increase of 44 welds which are required to be volumetrically examined is realized in both the PSI and ISI populations by moving to the 8 3W83 Code (columns 5 and 14).
Selection criteria for 74575 rules is based upon Title 10 invocation of 74S75, IWC-2411: multiple stream selection criteria. The 74S75 pre-service requirement (IWC-2100) was not invoked by Title 10. Therefore the 80W80 preservice requirement (IWC-2200) applies to the 89 SIS welds selected in accordance with the above.
- Under 83W83 rules, a larger population of welds are candidates for volumetric examination due to revised wall criteria and inclusion of 2-4" NPS high pressure safety injection lines.
Previously,100% of the volumetric examinations were concentrated into one (SIS) system. Under 83W83 rules, the volumetric examinations are applied to only 7.5% of the candidates, but with a not increase in the number of required examinations as above, and the examinations would then be spread out over five systems. While a lower percentage of SIS weld candidates are examined volumetrically, this latter distribution of examinations provides a more uniform, and therefore better sampling method to detect service induced flaws in all of these systems of eratical concern.
Two systems which were previously exempt would now be included in the nonexempt population subject to volumetric examination under 83W83 rules.
Adoption of the 83W83 Code for PSI would make our Program compatable e
with the ISI Program. Code Case N-400s or the equivalent 83W83 Code for Class 2 piping components, or an essentially unchanged later addenda thereof is anticipated to be the mandatory ISI Code in ef fect 12 months prior to the issuance of BVPS-2 Operating License as dictated by 10CFR50.55a (g) (4) (1).
o CLASS 2 PIPING WELD EIANINATION SIDOGARY SHEET Sect. XI, Table IWC-2500-1, Exam. Cat. C-F-2 (Sheet 2 of 2)
- STEEL SYSTWes:
1 2
3 4
5 6
7 8
9 10 11 12 13 14 SONGO Sect. II Rules 83tf83 Sect. XI Itules stonexempt Welds ISI Req'd Exams Nonexempt Welds ISI Reg'd Exams 3 Vol l
I vol I I vol l I
7.5% 3
' vol System surf + and = Total Surf + and = Total Surf + and + Exam = Total As % of Prorata = Surf + and Only, Surf I Only Surf e Only eSurf i N/A e CS Welds Share Only Surf EM 0
49 49 0
12 12 0
49 0
49 25.926 7
0 7
I seSS 3
71 74 1
16 17 3
71 0
74 39.153 11 1
10 SVS 100 0
100 25 0
25 0
66 0
66 34.921 10 0
10 l 1oe al 101 120 223 26 28 54 3
186 0
189 100 28 1
27 asort: A decrease of one weld which is required to be volumetrically examined is realised by moving to the 83uG3 code (columns 5 and 14). Nowever this is of fset by the f act that the major portion of the nonexempt I
weld candidates are located in the " break exclusion zone
- which is subject to an augmented volumetric emanimation program during the operating phase of the plant. Therefore, additional welds will lie volumetrically examined during each inservice inspection interval.
Advantage of Utilizing the 83tfS3 Code for CS Systems:
- SVS is now included in the population subject to volumetric examination due to inclusion of 3/8" through 1/2* well under this examination requirement.
BEAVER VALLEY UNIT 2 COMMENTS ON THE PRESERVICE INSPECTION (PSI) PROGRAM These comments were p'repared with the technical assistance of DOE contractors from the Idaho National Engineering Laboratory.
The following comments apply to the preliminary PSI Program submitted by the,
Applicant in a letter dated June 29, 1984. The staf f anticipates that these comments will be considered during the preparation of the final PSI Program and a specific response from the Applicant is not recuested.
A.
Paragraph 1.0.
The Materials Engineering Branch, Division of Engineering, is not responsible for the review of the containment leakage test require-ments described in 10 CFR 50, Appendix J.
B.
Paragraph 6.1.8.
This section states that all recordable indications will be recorded and investigated by a Level II or Level III examiner.
Recording requirements also apply to ultrasonic indicatfor:s of geometric or metallurgical origin determined by IWB-3514.5.
Procedure DWM-ISI-206 " Manual Ultrasonic Examination of Welds" states in paragraph 8.2 that the examiner shall determine if the indications are valid or non-valid based on his evaluation of test conditions and esta. Valid indications are reflectors caused by flaws. Non-valid ir.dications are reflectors from sources other than flaws.
Paragraph 9.2 ttates that valid flaw indications that produce a response equal to or exceeding 15 of the primary DAC curve shall be recorded and dimensioned.
}
l
I
. Staff Comments:
The PSI Program and the examination procedure are not consistent.Section XI does not make a distinction regarding recordable ultrasonic indications.
Geometric and metallurgical indications do not have to be compared with the acceptance standards as provided by IWB-3514.5.
Ultrasonic indications determined to be flaws should not be recorded and dimensioned based on amplitude criteria as stated in the examination procedure.
This subject was addressed in staff 250.3 which states in part:
"Any crack-like indication, regardless of ultrasonic amplitude, discovered during examination of piping welds or adjacent base metal materials should be recorded and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector."
Suggested recording requirements shown below were obtained from recent ASME Code Section XI action.
4.5.1 Recording Requirements 4.5.1.1. Flaw Indications (a) Any indication of a suspected flaw shall be recorded regardless of amplitude.
. (b) Any other indications that are not determined to be of geometrical or metallurgical origin shall be recorded if they are 20 percent of DAC or greater and originate in the HAZ or adjacent base metal or if they are 50 percent of DAC or greater and originate in the weld.
4.5.1.2 Indications Determined to be of Geometric or Metallurgical Origin (a) The following steps shall be applied in order to classify an indication to be of geometric or metallurgical origin:
- 1) Plotting and verifying coordinates,
- 2) Reviewing fabrication or weld preparation drawing,
- 3) As an option, applying other NDE methods or techniques (for example, alternate UT beam angles, radiography, ID and/or OD profiling),
- 4) Interpreting the area containing the reflector in accordance with the applicable procedure.
(b) For baseline or preservice examinations of new or replaced piping, indications 20 percent of DAC or greater shall be recorded.
(c) For inservice examinations, indications 50 percent of DAC or greater shall be recorded. For indications evaluated and recorded in accordance with (a) and (b) above, the evaluation and recording does not have to be repeated for subsequent examinations.
F s The discussions regarding valid and non-valid indications are applicable to most of the manual ultrasonic testing procedures.
C.
Paragraph 6.1.10.2 of Procedures 2.13 states that calibration standards /
calibration blocks shall comply with the appropriate Code Article to the extent practical. When DLC encounters problems in Code compliance regarding material availability or physical size, etc., the actual or as-built calibration standard shall be demonstrated acceptable in accordance with IWA-2240.
Staff Comment:
Paragraph III-3410 and III-3411 of Section XI define specific requirements for the number, dimensions and material specifications for the basic calibration blocks for piping. The reactor coolant pressure boundary piping is fabricated from cast stainless steel pipe and elbows and the Class 2 piping systems contains many stainless steel welds with overlays.
Calibration blocks should be provided to meet the requirements of Section XI and should be of the same material specification and metallurgical structure as the material on that side of the weld joint being examined.
D.
Paragraph 3.8 of the piping procedurt (151-206) requires establishing sensitivity from a side-drilled-hole at the 3/4 wall-thickness location in lieu of the Code required notch.
Staff Comments:
Detection of notches and/or known inside diameter surface flaws should be verified in calibration blocks representing the material for each side of the welds being examined.
.g-5-
E.
Paragraph 7.7.4 of procedure 151-206, requires only a single scan path in two directions.
Staff Comment:
This may not be adequate for austenitic materials and Supplement 7 or Code Case N-335 should be considered.
F.
Procedures 151-147, ISI-47, and 151-206 all require a minimum scan overlap of 10% of the transducer.
Staff Comments:
The increased scan overlap provisions from later editions of the Code and Code Case N-335 should be considered.
G. Standard Radiography.
Staf f Comments:
Standard radiography may not be capable of detecting and characterizing service-induced flaws because the detection of cracks normally requires the central axis of the radiation bear to be within 10' from the normal of the predominate crack plane.
If radiography is to be applied for preservice examinations a technical justification should be provided, including qualification and special procedure requirements, to demonstrate that radiography is an effective volumetric examination technique for detection of service-induced flaws.
H.
Paragraph 6.4.6 of Procedure 2.13 indicates that the volumetric examination procedure for bolting is being prepared.
k t
' Staff Comment:
The use of flat bottom holes as calibration reflectors may not be effective for the ultrasonic examination of large diameter, long bolts.
I.
Note 8 to the DMW-PSI-100 Table states that ultrasonic examination is not feasible due to material thickness and surface examination will be substituted. This note is applied to the Seal Water Heat Exchanger.
Staff Comments:
Limitations to required examinations and alternatives to ASME Code requirements should not be addressed by footnotes in the PSI Program. The Applicant should identify specific requests for relief from impractical requirements and provide a technical justification.
J.
Paragraph 6.7.1 of Procedure 2.13 states that both NF and Non-NF supports receive a preservice examination in accordance with Subsection IWF. At DLC discretion, the construction Code may be utilized for final acceptance of Non-NF supoorts.
I Staff Comment:
i Paragraph lWF-2200 (b) of Section XI requires that the preservice examination of supports, that are constructed in accordance with NF, shall be performed
'Yollowing the initiation of hot functional tests.
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MEETING SUFFARY DISTRIBUTION YY m
Local PDR NSIC PRC System LB3 Reading Attorney, OELD GWKnighton Project Manager BKSingh JLee NRC PARTICIPANTS S. K. Singh R. A. McBrearty M. R. Hum C Cherig l
bec: Applicant & Service List i.
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