ML20151N728
| ML20151N728 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/26/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-5-154, TAC-62870, NUDOCS 8601030102 | |
| Download: ML20151N728 (27) | |
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'Af M rs 5 4 Nuclear Construction Division Telecopy (41 -6 Nt$u g" HIP 552 5 December 26, 1985 United States Nuclear Regulatory Caumission Washington, DC 20555 ATTENTION: Mr. Lester S. Rubenstein, Director PWR Project Directorate No. 2 Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Preservice Inspection Progran Submittal
REFERENCES:
- 1) DLC letter 2NRC-4-096, dated June 29, 1984
- 2) DLC letter 2NRC-5-014, dated January 31, 1985
- 3) NRC letter to DLC, dated May 20, 1985
- 4) NRC letter to DLC, dated June 8,1985
- 5) DLC letter 2NRC-5-108, dated July 26, 1985
- 6) NRC letter to DLC, dated October 11, 1985 Gentlemen:
Duquesne Light Canpany (DLC) indicated in the July 26 letter (Refer-ence 5) that the PSI Progran would be submitted by Decenber 31, 1985. This submittal constitutes DLC's understanding of all documentation necessary for NRC review of the PSI Progran. This submittal addresses NRC conments (Refer-ence 4), SER Open Itens (Reference 6), and updates the earlier DLC submittals (References 1 and 2).
Documents applicable to NDE ultrasonic exanination of vessels and piping, bolting exani nation, Class 2 piping exanination criteria and iso-metrics, stean generator tubing exanination, administrative procedures, valve a n d puup testing, and generic relief requests applicable to the PSI Progran have been included in the acconpanying volume entitled "Duquesne Light Can-pany Beaver Valley Power Station Unit No. 2 Preservice Inspection Program."
Attachment 1 of this letter provides the finalized, updated Class 2 Piping Weld Exanination Summary based upon piping walkdown infonnation and reflected in Class 2 Piping Isonetrics (provided in the acconpanying volume).
The earlier submittal of this plan (Reference 2) was found to be acceptable by the staff (Reference 3).
Attachment 2 of this letter identifies the DLC position on weld over-lay, which has been provided to the NRC Region I Resident Inspector.
Attachment 3 of this letter identifies the documents included in the accompanying volune.
5601030102 e51226 2 PDR ADOCK 050 _
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United St'ates Nuclear Regulatory Connission Mr. Lester S. Rubenstein Preservice Inspection Program Submittal Page 2 DLC has established its own procedures for manual exanination of vessels, including the reactor vessel, and piping. These procedures provide resolution to NRC comments identified in Enclosure 3 of Reference 4.
In addition, the use of a 60* dual elenent " shallow angle" near sur-f ace technique specifically intended to examine volumes of material near the reactor vessel I.D. surf ace is in preparation to improve on the techniques included in this submittal . It is expected that these improved techniques will be incorporated into the reactor vessel (automatic) inspection procedure DMW-ISI-154 as a later revision in the second quarter of 1986. This revision will be available onsite for NRC review.
Therefore, DLC requests NRC approval of the Preservice Inspection Progran and closed status of SER open itens and FSAR questions applicable to this progran by March 1,1986.
DUQUESNE LIGHT COMPANY By [k J. J. Carey y Vice President JJS/wjs Attachments cc: Mr. B. K. Singh, Project Manager (w/a 1, 2, & 3, and volune)(3)
Mr. G. Walton, NRC Resident Inspector (w/a 1, 2, & 3, and volume)
SUBSCRIBE 0 AND SWORN TO BEFORE ME THIS J7K DAY OF -Atawclu.s_ , 1985.
f ru J Notary Public ANITA ELAINE REITER, NOTARY PUBLIC R03!NSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986
United SthteU Nuclear Regulatory Commission Mr. Lester S. Rubenstein Preservice Inspection Progran Submittal
- P ag e 4 -
JJS/wj s NR/NRC/ PSI /SUB Attachments bcc: J. J.'Carey - w/ attachments 1, 2, & 3 only E. J. Woolever - w/ attachments 1, 2, & 3 only R. S. Christner - w/o/ attachments C. E. Ewing - w/ attachments 1, 2, & 3 only J. A. Hultz - w/o/attachnents E. F. Kurtz, Jr. - w/o/ attachments J. H. Latshaw .- w/o/ attachments R. E. Martin - w/attactinents 1, 2, & 3 only T. P. Noonan - w/ attachments 1, 2, & 3 only R. J. Swiderski - w/attacnments 1, 2, & 3 only J. P. Thomas - w/attactinents 1, 2, & 3 only a G. L. Beatty - w/ attachments 1, 2, & 3 -only E. T. Eilmann - w/o/ attachments R. W. Fedin - w/o/attachnents K. M. Holcomb - w/o/ attachments J. Lee, Esq. - w/o/ attachments J. D. O'Neil - w/attactynents 1, 2, & 3 only S. L. Pernick, Jr. - w/o/attachnents
, K. A. Troxler - w/attachnents 1, 2, & 3 only T. J. Zogimann - w/o/attachnents
! A. A. Dasenbrock - w/o/ attachments D. E. Burke (CEI) - w/o/attactinents R. G. Schuerger (CEI) - w/o/ attachments B. M. Miller (2) (0EC) - w/o/attactinents T. Gerusky (PADER)' - w/o/attachmenti J. Silberg (SPPT) - w/o/attactr er .;
C. Richardson (S&W)(5) - w/o/attachig..cs J. Sutton (S&W) - w/o/attacivnents T. J. Lex (W) - w/o/ attachments
~
, B. Hall (WJ- - w/o/ attachments DLC/Qatel - w/ attachments 1, 2, & 3 only J. R. Houghton - w/attactynents 1, 2, & 3 only M. A. Zaki - w/attactynents 1, 2, & 3 only P. A. Cadena - w/o/attachnents W. H. Sikorski - w/attactinents 1, 2, & 3. only NCD File - w/ attachments 1, 2, & 3 only
United St'ates Nuclear Regulatory Commission Mr. Lester S. Rubenstein Preservice Inspection Program Submittal Page 3 COMMONWEALTH OF PENNSYLVANIA )
) Ss:
COUNTY OF ALLEGHENY )
The Manager, Regulatory Affairs, R. E. Martin, being first duly sworn, deposes, and says: that he is Manager, ~ Regulatory Affairs, of Duquesne Light Company, with legal authority to sign official correspondence on behalf of the Vice President, Nuclear Division, J. J. Carey, in relation to licensing
- for Beaver Valley Power Station, Unit 2, and is therefore authorized to submit the foregoing on behalf of the applicant.
CD7GY c2 7 / 9 l'd
- Date Manager, Regul atory Af f airs Sworn and. subscribed before me this
,2 M day of ,Ojen M , 1985.
ccd_
Notary Public d
ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES CCTOBER 20,1986 4
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TABLE 1 . ATTACHMENT 1
-a CLASS 2 PIPING WELD EXA111 NATION SUMf!ARY SHEET PAGE 1 0F 3 Sect. XI, Table IWC-2500-1, Exam. Cat. C-F-1 STAINLESS STEEL SYSTEMS:
1 2 3 4 5 6 7 8 9 10 11 12 13 14 74575 Sect. XI Selection Rules 83W83 Sect. XI Guidance Using 10% Selection (80W80 Examination Requirements)
Nonexenpt Welds ISI Rea'd Exans Nonexenot Welds ISI Reo'd Exans l Vol l Vol l l Voi 10.01 Vol System Exam =l Total Surf + and = Total Surf +land Only
= Total Surf 4 and Only gSurf As % of Prorata=l Surf land Onlyl Surf l y Surf l N/A l SS Welds Share lOnly Surf
.CHS' 114 0 114 27 0 27 567 462 121 1150 41.531 115 64 51 QSS - ------- Exempt IWC - 1220 ( b ) ------- 0 51 130 181 6.537 18 0 18 RH5 214 4 218 109 2 111 0 70 205 275 9.931 28 0 28 RSS ------- Exempt IWC - 1220 ( b ) ------- 0 130 28 158 5.706 16 0 16 515 361 162 523 116 48 164 186 520 299 1005 36.295 101 28 73 Subtot al SS 689 166 855 252 50 302 753 1233 783 2769 100.000 278 92 186 L 10% Sample = 277 examinations NOTES: A. 10CFR50.55a(b)(2)(iv) invokes requirements to use the 74575 Code for the above systems to determine only exemption criteria (IWC-1220) and selection criteria (IWC-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 surf ace and not volumetric examinations under the 83W83 Code is due largely to the fact that 2" NPS lines in these systems are of socket weld construction.
' O- C. ExemptionIWC-1220(b): Components in systems or portions of systems, other than e'nergency core cooling systems, which do not function during normal reactor operation.
CLASS 2 PIPlHG WELO ExnMINATION
SUMMARY
SHEET Sect. XI, Table IWC-2500-1, Exam. Cat. C-F-2 CARBON STEEL SYSTEMS:
1 2 3 4 5 6 7 8 9 10 11 12 13 14 80W80 Sect. XI Rules 83W33 Sect. XI Rules Nonumenpt Welds , 151 q'd Exans Nonexenpt Welds ISI Reg'd Exans vol Vol Vol 10.0L Vol Systen Surf + and = Total Surf [+ and + Exan = Total As % of Prorata l= Surf l+
Unlyl Surf Surf ll+and=
Only Surf Onlyl Surf Total N/A CS Welds Share lOnlyl Surf j- FWS U 54 54 0 14 14 0 54 0 54 28.421 8 0 8 MSS 3 71 74 1 15 16 3 71 0 74 38.947 11 1 10 SVS 96 0 96 24 0 24 0 62 0 62 32.632 9 0 9
. . - ==.....
Subtotal - CS 99 125 224 25 29 54 3 187 0 190 100 28 1 27 Subtotal - SS 689 166 855 252 S0 302 753 1233 183 2769 ---
278 92 186 TOTAL 788 291 1019 277 79 356 756 1420 783 2959 ---
306 93 213
= ... --
NUTE: A d? create of one carbon steel wen. which is required to be volunetrically exanined is realized by moving to l ., the 83W43 Code (Colunns 5 and 14). Pawever, this is of feet by the f act that the major portion of the nnneumpt carbon steel weld canoidates are located in the "ureak exclusion zone" wn ich is subject to an a97nented l volunetric examination progran during the operating phase of the plant. Therefore, additional j welds will be volunetrically exanined during each inservice inspection interval,
ATTACHMENT 1 PAGE 2 of 3 TABLE 1 (continued)
The shif t in.the number of required exaninations for Class 2 CHS and SIS Systens under 74S75 Selection Rules (fron the Table provided in the January 1,1985, submittal) is due to the current treatment of these systens as C-G versus C-F systens previously. Af ter 74S75 Selection Rules have been appl ied, C-G systens require a 50% sanple of welds to be exanined versus a 100% sanple for C-F systems.
Based upon a more thorough study, the justification for classifying CHS and SIS as C-G systens unoer 74S75 Rules is that they clearly have an "i nj ect ion" function, not a " reactor coolant circul ation" function. Whil e reactor coolant fluid is " processed" through a torturous fluid path to be available for the injection function, in tenns of pressure boundary, Safety Class 2 CHS and SIS systens are not part of the Reactor Coolant Systen deter-mi ned in accordance with valve isolation functions established by 10CFR 50.2(v).
The earlier submittal was based upon a count of welds fran isometric drawings for systens still under construction. Minor changes in other areas of this table reflect a walkdown verification of the installed piping, thus providing more accurate data on weld counts. Considering the current state of construction, it is not anticipated that any changes- that may occur prior to the final as-built status of these Class 2 Systens, would have any signi-ficant impact on the data presented in this table.
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1 ATTACHMENT 2 A REPORT OF QUALIFICATION PIPING ULTRASONIC EXAMINATION TECHNIQUES:
- 1. Ultrasonic technique for exanination of 0.7 inch and greater austenitic piping welds with OD weld deposited clad overlay.
- 2. Ultrasonic technique for exanination of cast austenitic main loop reactor coolant piping welds.
BACKGROUND Ultrasonic-technique identified above to be used at Beaver Valley Unit 2 baseline are Nuclear Energy Services (NES) techniques qualified and enployed at other nuclear power plants. Utilization of other site qualification records has been discussed with the Beaver Valley Unit 2 (BV-2) USNRC on-site representative and another Region 1 USNRC representative.
Technique ntuber 1 above has been qualified at the EPRI NDE Center by NES for Perry Nuclear Plant. Mr. Mike Schalles, the BV-2 NES site Supervisor has performed the EPRI NDEC qualification. The technique was developed for exanination of piping welds with corrosion resistant cladding. The technique employs dual elenent 45 degree refracted longitudinal search units, 3/4 x 3/4 or 1 x 1 inch in size. Supporting documentation verifying detection of 0.250 through 0.800 inch deep cracks (actual cracks) is attached (Appendix 1). One specimen had a 0.125 inch deep crack but no photograph of the UT instrument display was provided. This technique has also been demonstrated acceptably at Beaver Valley Unit 2 using overlayed mockups with simulated cracks representing as-built piping welds. The butt weld in one mockup proved to be acoustically worse-case when interrogating a simulated crack through the weld. This mockup rejected conventional code UT techniques. UT Exaainer training, and conversion factors to be applied to in-plant PSI exaninations will be established using the BV-2 mockups. The BV-2 mockups will be available for on-site performance denonstrations.
Technique 2 above was successfully denonstrated at USNRC Region 2 for use on
- Shearon Harris Nuclear Power P1 ant main loop piping CF8M fittings and elbows.
This qualification was performed on a CCSS/SCSS welded austenitic mockup owned by USNRC Region 2. The USNRC report of the denonstration is included as Appendix 2.
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i APPENDIX 1 Qualification of Beaver Valley Unit 2 UT Technique for Austenitic Pipe Welds I
with OD Weld Overlay.
BACKGROUND The UT technique to be enployed at Beaver Valley Unit 2 will be the sane technique qualified and enployed at Perry Nuclear Plant for pipe welds with i
corrosion resistant clad (CRC) overlay. The Perry CRC mockups represented exanination conditions much worse than Duquesne Light Conpany will experience during PSI of overlayed SS welds at BV-2. The technique will not be
- requalified at BV-2, however, augmented technique denonstrations may be 4
conducted. In further support of BV-2, Mr. Mike Schalles, the NES individual who perfonned the EPRI NDE Center qualification and directed on-site 4
exaainations for the Perry technique, will supervise the BV-2 in-site exaninations. The BV-2 technique qualification is a canbination of the attached data fran the Perry qualifications and use of Duquesne Light Canpany welded mockups with OD weld overlay simulating actual as-built conditions. The
, mockups provided the base selection models for considering several techniques including the Perry technique. The EPRI NDE Center mockups included actual cracked specimens. The BV-2 mockups contain simulated cracks, depths (5,10, and 2D%) located at selected positions and depths adjacent to the weld root.
Techniques were selected based.on detection of the simulated cracks from both sides of (and through) the weld. BV-2 thin wall (0.6") mockup showed that
- acceptable results can be achieved using conventional (shear wave) techniques.
When shear wave techniques are enployed, procedural requirenents will be
- - imposed which assure penetration through the overlay. It is expected that weld l root responses approximately 5-10 percent full screen height will be maintained.
4 APPENDIX
! 2. Photographs of UT Instrunent "A" scan display of cracks.
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NUCLEAR ENERGY SERVICES. INC.
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APPENDIX 2
' UNITED STATES aato n, NUCLEAR REGULATORY COMMISSION
[m w-
- REGION il
~
101 MARIETTA STREET,N.W. !
[ .
3 H- ,,, .
ATLANTA, GEORGI A 30323 EmJc8
%,,*... t 04 ms a. e. a NOV 2 61984 or--
Carolina Power and Light Company ATTN: Mr. II. E. Utley Executive Vice President Power Supply and Engineering and Construction 411 Fayetteville Street Raleigh, NC 27602 Gentlemen: , ,
~ '~
SUBJECT:
MEETING
SUMMARY
- REPORT NO. 50-400/84-40 This letter refers to the technical meeting held at your request in the NRC .
Region II Office on November 2, 1984. This meeting concerned activities
- authorized by NRC Construction Permit No. CPPR-158 for the Shearon Harris ,,
facility. , ,
The meeting provided Carolina Power and Light Company (CP&L) an opportunity to demonstrate the ability of their ultrasonic examination procedure and equipment,,
to detect, locate, and size actual crack flaws propagating from the pipe inside
) diameter in centrifugally cast stainless steel as discussed in the enclosed report.
It is our opinion that this meeting was informative and beneficial to both NRC and CP&L because of the exchange of information concerning inspection of cast stainless steel In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in NRC's Public Document Room unless you notify this office by telephone within 10 days of the date of this letter and submit written applica-tion to withhold information contained therein within 30 days of the date of the letter. Such application must be consistent with the requirements of 2.790(b)(1).
Should you have any questions concerning this matter, we will be pleased to discuss them.
Sincerely,
)
'W A' -
rrelli, Chief
- DvidM.%jectsBranch1 R actor Pro Division of Reactor Projects
)
Enclosure:
(See page 2) f r
. t
, .id.<y-4,
-lw
i Carolina Power and Light Company 2 hK)V 2 61984 :
) ,
Enclosure:
Inspection Report No. 50-400/84-40 r
cc w/ enc 1: ..- -
R. A. Watson, Vice President Harris Nuclear Project R. M. Parsons, Project General Manager e
)
t
UNITED STATES
/ c,g% NUCLEAR REGULATORY COMMISSION REGtONll Z' ' e .
j j 101 M ARIETT A STREET, N.W.
ATLANTA, GEORGI A 30303
\,*e.*/ .
Report No.: ~56-400/84-40 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Docket No.: 50-400 License No.: CPPR-158 Facility Name: Harris 1 Inspection Conducted: NRC Regional Office, Atlanta, Georgia Inspectors: \ e a M MA // -O O - k Y Date Signed .
J. % Coley, Reactor E g neer ,,
'~
//- 20 -g</ -
/N. > n 2 = - - L -m Date Signed R Ws teactor Engineer Approved by: ///a. s!t 4 M Blake, Section Chief Date Signed
) ngneeringBranch Division of Reactor Safety
SUMMARY
Scope: On November 2,1984, a technical meeting was held with Carolina Power and Light Company (CP&L), representatives in the Region II Office for the purpose of providing CP&L an opportunity to demonstrate the capability of their ultrasonic examination procedure and equipment to detect actual flaws and artifical reflec-tors in Region II's Centrifugally Cast Stainless Steel (CCSS) test specimens.
CP&L was successful in detecting the I.D. reflectors, including cracks. Region !!'s CCSS test specimens represented examination conditions much worse than CP&L will experience during the examination of the Shearon Harris wrought stainless steel reactor coolant loop piping. Therefore, CP&L's procedure IST-501, and ultrasonic equipment have demonstrated conservative detection capability for the preservice examination at the Shearon Harris facility.
,gu qq.
1
) -
REPORTDEiAILS l
- 1. Person Cont'Ected 1
Licensee Employees
- T. Bromback, Project Specialist, CP&L
- S. Pruitt, Senior Specialist, CP&L Other Organizations
- R. Saunders, level III, Nuclear Energy Services (NES) .
- 2. Technical Issues Involved CP&L Shearon Harris, and NES personnel identified in paragraph 1 above, visited the Region II Office on November 2,1984, to demonstrate the ,
capability of their ultrasonic examination procedure (IST-501) and equipment - #
to detect, locate, and size actual crack flaws propagating from the pipe -
inside diameter in Centrifugally Cast Stainless Steel (CCSS). Although the Shearon Harris facility does not have the difficult-to-examine CCSS piping in their reactor coolant loop piping, CP&L will be using a refracted --
longitudinal wave transducer. The refracted longitudinal wave transducer is
) the only practical method of inspecting difficult-to-penetrate weld volumes and most cast stainless steels. However, the refracted longitudinal wave mode suffers significant mode conversion when interfacing with corner type reflectors such as I.D. pipe cracks. Therefore, CP&L wanted to test their procedure and equipment detection capability prior to the start of' their preservice baseline examinations at ,the Shearon Harris Unit 1 facility.
Region II provided the CCSS specimens for CP&L's performance demonstration test. All cracks and artificial reflectors were covered so that the licensee had no prior knowledge of their location. CP&L used a Krautkramer-Branson USL-38 instrument and dual 1 MHz by 1 inch transducers. The transducers had lucite wedges ground to fit the contour of the reactor coolant loop piping at a specific focal length.
NES performed the actual examination of the test specimens and Region !!
personnel provided guidance and monitored the ultrasonic instrument calibration and subsequent crack detection techniques used by the participants. After the participants had completed the examination of the weld samples, the cracks, and artificial reflector were revealed to the licensee by performing a liquid penetrant test on the sample.
- 3. Meeting Conclusions During the technical meeting at the Region II Office, CP&L successfully demonstrated the capability of their ultrasonic examination procedure and
) equipment to detect actual flaws in the volume subject to examination.
ATTACHMENT 3 Docunents Included in Volume "Duquasne Light Conpany Beaver Valley Power Station Unit No. 2 Preservice Inspection Progran" 1.0 DLC PSI PROGRAM ADMINISTRATIVE PROCEDURE:
NCDP No. 1.13, Rev . 1, "ASME Section XI Preservice Inspection Progran Administrative Procedure" 2.0 DLC PSI PROGRAM / PLANS DOCUMENTS 2.1 NCDP No. 2.13, Rev. 2, "ASME Section XI Integrated Preservice Inspection Progran" 2.1.1 NCDP No. 2.13.5, Rev.1, " ASME Section XI Preservice Inspec-tion Plan for Class 2 Pressure Retaining Conponents" 2.1.2 NCDP No. 2.13.6, Rev.1, " ASME Section XI Preservice Inspec-tion Visual Exani nation Criteria for Pressure Retaining Components and Component Supports" 2.1.3 NCDP No. 2.13.7, Rev.1, " ASME Section XI Preservice Inspec-tion Plan for Cla.- 1 Pressure Retaining Components" 2.2 NCD Specification No. 10080-DMS-0002, Rev. 2, " Specification for Preservice Stean Generator Eddy Current Inspection Beaver Valley Power Station Unit No. 2" 2.3 Punp and Valve Test Plan for Preservice Inspection 2.3.1 DLC Startup Manual Chapter 3.7, "ASME Section XI Puup and Valve Administrative Procedure" 2.3.2 PST Pump Testing Requirenents 2.3.3 PST Valve Testing Requirenents 3.0 DLC ISI DEPARTMENT MANUALS 3.1 DLC ISI Departnent Administrative Manual Procedures 3.1.1 GP-101, Rev. O, "Establishnent of Reference Points and Data Recording" 3.1.2 GP-102, Rev. O, " General Inspection Requirenents" 3.2 DLC ISI Department NDE Manual Procedures 3.2.1 UT-300, Rev. O, " General Requirenents for Ultrasonic Exani-nations"
1
- j. 3.2.2 UT-301, Rev. O, " Screen Height and Amplitude Control Linearity" 3.2.3 UT-302, Rev. O, " Procedure for Ultrasonic Exanination of Ferritic Piping Systens" 3.2.4 UT-303, Rev. O, " Ultrasonic Exanination of Austenitic Systens" 3.2.5 UT-305, Rev. 0, " Manual Ultrasonic Exanination of Studs and Bolting (High Gain Technique)"
3.2.6 UT-306, Rev. 0, " Manual Ultrasonic Exanination of Welds in Vessels Over Two Inches in Thickness" 3.2.7 UT-307, Rev. 0, " Manual Ultrasonic Exanination of Vessel ,
Welds fran 0.2 Inches Up to and Including 2 Inches in Thickness" i 3.2.8 UT-310, Rev. O, " Manual Ultrasonic Exanination of Welds in
. Reactor Vessels" 4.0 CONTRACTOR PROGRAMS / PROCEDURES 4.1 DMW-IS I-41, Rev. O, "Manu al Ultrasonic Exanination of Reactor Coolant Pump Flywheels" 4.2 DMW-ISI-154, Rev. 2, "Preservice Inspection of Reactor Vessels"
[
5.0 CLASS 2 PIPING IS0 METRICS 6.0 R_ELIEF REQUESTS 6.1 Vessel Relief Requests 6.2 Pump Testing Relief Requests 3
1 1
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