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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20211N8891999-09-0707 September 1999 Safety Evaluation Supporting Amends 245 & 236 to Licenses DPR-77 & DPR-79,respectively ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively ML20196J8021998-12-0707 December 1998 Safety Evaluation Supporting Amends 240 & 230 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively ML20195H0831998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 226 to Licenses DPR-77 & DPR-79,respectively ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20236S4081998-07-0101 July 1998 Safety Evaluation Supporting Amends 233 & 223 to Licenses DPR-77 & DPR-79,respectively ML20248L1961998-06-0808 June 1998 Safety Evaluation Supporting Amends 232 & 222 to Licenses DPR-77 & DPR-79,respectively ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20216E4701998-03-0909 March 1998 Safety Evaluation Approving Exemption from Updated FSAR Requirements of 10CFR50.71(e)(4) for Sequoyah Nuclear Plant,Units 1 & 2 ML20203K6811998-02-20020 February 1998 Safety Evaluation Supporting Amends 231 & 221 to Licenses DPR-77 & DPR-79,respectively ML20198P9171998-01-13013 January 1998 Safety Evaluation Supporting Amend 230 to License DPR-77 ML20217D7881997-09-29029 September 1997 Safety Evaluation Supporting Amends 229 & 220 to Licenses DPR-77 & DPR-79,respectively ML20211G2061997-09-23023 September 1997 Safety Evaluation Supporting Amends 228 & 219 to Licenses DPR-77 & DPR-79,respectively ML20210J5951997-08-12012 August 1997 Safety Evaluation Supporting Amends 227 & 218 to Licenses DPR-77 & DPR-79,respectively ML20151L7981997-07-14014 July 1997 Safety Evaluation Supporting Amends 226 & 217 to Licenses DPR-77 & DPR-79,respectively ML20148S0581997-07-0101 July 1997 Safety Evaluation Supporting Amends 225 & 216 to Licenses DPR-77 & DPR-79,respectively ML20140F0311997-06-10010 June 1997 Safety Evaluation Supporting Amends 224 & 215 to Licenses DPR-77 & DPR-79,respectively ML20138D2581997-04-28028 April 1997 Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909 ML20137Y8911997-04-21021 April 1997 Safety Evaluation Supporting Amends 223 & 214 to Licenses DPR-77 & DPR-79,respectively ML20137R6071997-04-0909 April 1997 Safety Evaluation Supporting Amends 222 & 213 to Licenses DPR-77 & DPR-79,respectively ML20101M5761996-04-0303 April 1996 Safety Evaluation Supporting Amend 211 to License DPR-79 ML20100N5711996-03-0404 March 1996 Safety Evaluation Supporting Amends 220 & 210 to Licenses DPR-77 & DPR-79,respectively ML20097D4191996-02-0707 February 1996 Safety Evaluation Supporting Amends 218 & 208 to Licenses NPF-77 & NPF-79,respectively ML20097F2211996-02-0505 February 1996 Safety Evaluation Supporting Amends 217 & 207 to Licenses DPR-77 & DPR-79,respectively ML20095F9891995-12-11011 December 1995 Safety Evaluation Supporting Amends 216 & 206 to Licenses DPR-77 & DPR-79,respectively ML20094N5341995-11-21021 November 1995 Safety Evaluation Supporting Amends 215 & 205 to Licenses DPR-77 & DPR-79,respectively ML20094D2451995-10-30030 October 1995 Safety Evaluation Supporting Amend 204 to License DPR-79 ML20093E1191995-10-11011 October 1995 Safety Evaluation Supporting Amend 214 to License DPR-77 ML20093B9471995-10-0404 October 1995 Safety Evaluation Supporting Amends 213 & 203 to Licenses DPR-77 & DPR-79,respectively ML20092N0711995-10-0202 October 1995 Safety Evaluation Supporting Amends 212 & 202 to Licenses DPR-77 & DPR-79,respectively ML20092H0811995-09-15015 September 1995 Safety Evaluation Supporting Amends 211 & 201 to Licenses DPR-77 & DPR-79,respectively ML20092G7071995-09-13013 September 1995 Safety Evaluation Supporting Amends 210 & 200 to Licenses DPR-77 & DPR-79 ML20087L4671995-08-22022 August 1995 Safety Evaluation Supporting Amends 207 & 197 to Licenses DPR-77 & DPR-79,respectively ML20086C2861995-06-29029 June 1995 Safety Evaluation Supporting Amends 205 & 195 to Licenses DPR-77 & DPR-79,respectively ML20085M1581995-06-14014 June 1995 Safety Evaluation Supporting Amends 204 & 194 to Licenses DPR-77 & DPR-79,respectively 1999-09-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20211N8891999-09-0707 September 1999 Safety Evaluation Supporting Amends 245 & 236 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20212A1841999-08-25025 August 1999 Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively 05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
ML20196J8021998-12-0707 December 1998 Safety Evaluation Supporting Amends 240 & 230 to Licenses DPR-77 & DPR-79,respectively ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20195H0831998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 226 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With 1999-09-07
[Table view] |
Text
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UNITED STATES g'
'j-NUCLEAR REGULATORY COMMISSION l
2 WASHINGTON, D.C. 20555-0001 f
a SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION j
RELATED TO THE RELIEF FROM CERTAIN RADIOGRAPHIC REQUIREMENTS l
t-SEQUOYAH NUCLEAR PLANT. UNITS 1 AND 2 i
TENNESSEE VALLEY AUTHORITY DOCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
in a letter dated May 4,1999, the Tennessee Valley Authority (TVA) submitted a request for relief from certain radiographic image quality indicator (101 or penetrameter) requirements at -
the Sequoyah Nuclear Plant (SON), Units 1 and 2. TVA proposed an alternative to the plaque-type penetrameters specified by the 1989 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), which is the applicable edition for the Sequoyah second 10-year Inservice Inspection (ISI) interval. The penetrameters are used to ensure that the desired sensitreity, definition, and contrast has been achieved in radiographic examination of materials.
2.0 BACKGROUND
l Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2 and 3 components (including supports) must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions of the Code and Addenda that become effective subsequent to the editions specified in paragraphs (g)(2) and (g)(3) of this section and that are incorporated by reference in paragraph (b) of this section, to the extent practical within the limitations of design, geometry and materials of construction of the components.
2.1 Code Reauirements -
As noted above, the applicable ASME Section XI Code for the SON second 10-Year ISI interval I
is the 1989 Edition with no addenda. In a submittal dated November 21,1995, TVA proposed
. to use ASMF unde Case N-416-1," Alternate Pressure Test Requirement for Welded Repairs or Installatior, of Replacement Items by Welding, Class 1,2, and 3,Section XI, Division 1," for SON Units 1 and 2. TVA's proposed alternative to the Code was authorized in a letter from the U.S. Nuclear Regulatory Commission (NRC) dated April 27,1998, with its approval of the second 10-year ISI interval program. Specifically, TVA was authorized to use ASME Code Case N 416-1. This Code case requires that non-destructive examination of welds be 4
performed in accordance with the applicable Subsection of the 1992 Edition (no addenda) of Section lli of the Code.
ENCLOSURE 9907080035 990628 PDR ADOCK 05000327 0
PDR e
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tThe use of penetrameters is contained in paragraphs NB-5111 and NC-5111 to Section lli of the 1992 Edition of the Code, that state in part " JRadiographic examination shall be in accordance with Section V, Article 2, except that... the penetrameters of Table NB-5111-1 (and NC-5111-1) shall be used in lieu of those shown in Table T-276 [of Section V)." Tables NB-5111-1 and
~ NC-5111-1 specify only plaque-type penetrameters.
2.2 Reauest for Acoroval of an Alternative Section 10 CFR 50.55a(a)(3) states that Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g),
and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall i'
demonstrate that:
(i) the proposed alternatives would provide an acceptable level of quality and safety, or" t(ii) : compliance with the specified requirements of this section would result in hardship of unusual difficulty without a compensating increase in the L
. level of quality and safety.
TVA has requested approval for an alternative to the penetrameter requirements in paragraphs NB-5111 and NC-5111 to Section lli of the 1992 Edition of the Code as cited above.
- Specifically, TVA proposes to use wire-type image quality iadicators (i.e., penetrameters) for
- radiographic examinations as provided for in ASME Code, Section'lli,1992 Edition with 1993 Addenda.
2.3 Basic for Alternative j
L L
TVA believes that plaque-type penetrameters are difficult to use due to their physical placement and radiographic characteristics. The placement of flat plaques on curved surfaces of pipe L components usually need some forni of shimming. After positioning the plaque on test material and performing a radiographic examination, the recorded radiographic characteristics of the essential T hole is often obscured or distorted due to specimen anomalies, part geometry, or film j
l-artifacts outside the area of interest. These difficulties create re-shoot conditions. The l
- re-shoots have an adverse as-low-as-reasonably-achievable impact due to the additional radiation exposure to the radiography crew.
. TVA believes that the wire-type IQ1 is superior to the plaque-type IQI for nuclear piping component applications. Wire IQls can be placed directly across the area of interest, thus
. encompassing the object's range of density and geometry. The 1-inch minimum length of the l~
' essential 1Q1 wire eliminates the problem of indicator loss due to distortion, anomalies, and part
- geometry. The wire-type IQis provide the same function as the plaque-type penetrameters by J
indicating a change in thickness and spatial resolution of the image without the use of shim blocks and pipe standards.
Wire IQls have been shown to provide quality and sensitivity equivalent to plaque-type L
penetrameters as documer ted in Table 4 of American Society for Testing and Materials (ASTM) ys j
i-
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=
i :
i K
1
[,
- E 747-87. Equivalent sensitivity has also been demonstrated in ASME Section V, Article 22, LStandard SE-747. Because of the equivalent sensitivity, the proposed alternative (i.e., wire IQls) provides results that are equivalent to the current testing method of plaque-type penetrameters. Therefore, the quality of the inspection and resulting safety of the plant, based on the inspection results, are not impacted by this proposed attemative, thus providing an I
acceptable level of quality and safety.
3.0 EMALUATION Volume 17 of the Ninth Edition of the Metals Handbook, published in 1989, states that wire-type penetrameters are widely used in Europe, and a standard design is used in the United Kingdom, Germany, the Netherlands,' and Scandinavia and by the International Organization for j
' Standardization and the International Institute of Welding. The handbook goes on to state that
. wire penetrameters specified in ASTM E 747-87 are widely used in the United States. ASTM developed this specification using a public forum with approval by public consensus. The ASTM Standard E 747-87 referenced in the Metals Handbook is identical to the 1989 Edition of ASME's Standard SE-747-87.
Wire penetrameters were not included in Section lil of the. Code until the 1992 Edition with 1993
.. Addenda. Although the 1992 Edition with 1993 Addenda of the Code has not been endorsed'at this time by NRC, it was developed through the consensus-building process used by Section ill of the Code. The NRC participates in these forums.
I In the staff's review of TVA's proposed altemative, the staff assembled a table for wire penetrameters from standards that are currently being used in industfy. To assemble the table,
- plaque number and essential hole size from Table 4 to SE-747 to Section V was merged with i
the same from Table NB-5111-1 (NC-5111-1) to the 1992 Edition of Code. The wire diameters
)
from Table 4 to SE-747 to Section V was compared against the wire diameters from Table j
NB-5111-1 (NC-5111-1) to Section lli of the 1992 Edition with 1993 Addenda of the Code. The j
comparison showed that wire diameters were essentially the same. Of the 18 wire diameters in the newly created table, two wire diameters were more conservative (smaller diameters), two wire diameters interpolated from two known values were less conservative (larger diameters),
i and 14 wire diameters were identical to the wire diameters in Table NB-5111-1 (NC-5111-1) to the 1992 Edition'with 1993 Addenda of the Code. Based on the above comparison of commonly used industry references and the widespread use of wire penetrameters in industry, the staff believes that wire penetrameters listed in Table NB-5111-1 (NC-5111-1) to the 1992 Edition with 1993 Addenda of the Code will provide an acceptable level of quality and safety.
4.0 CONCLUSION
Based on the above evaluation, the staff concludes that the proposed alternative to use IQls for radiography examinations as provided for in ASME Section Ill,1992 Edition with 1993 Addenda, provides an acceptable level of quality and safety. Therefore, the staff authorizes the use of the i
proposed attemative pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Contributor: Donald Naujock, NRR.
Dated: June 29, 1999 1
ll