ML20149B059
| ML20149B059 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1997 |
| From: | Elliot B, Carolyn Fairbanks, Albert Lee, James Medoff, Strosnider J, Wichman K Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| CON-FIN-J-2391 NUREG-1612, NUDOCS 9707140087 | |
| Download: ML20149B059 (65) | |
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i NUREG-1612 h
Status Report: Reactor Vessel Integrity Database l
I l
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation C.J. Fairbanks, A.D. Lee, J. Medoff, J.R. Strosnider, K. R. Wichman, B. J. Elliot Cf*l j
i 49
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I!Illllll0lllll]lll[gjj l-71 970731 1612 R PDR
AVAILABILITY NOTICE Availability of Refere'nce Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:
1.
The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.
The Superintendent of Documents. U.S. Government Printing Office, P. O. Box'37082 Washington, DC 20402-9328 m
3.
The National Technical Information Service, Springfield, VA 22161-0002-Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.
Referenced documents available for inspection 'and copying for a fee from the NRC.Public -
3 Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports;-
vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.
The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agrecment reports, grantee reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission Issuances.
Documents available from the National. Technical information Service include NUREG-series.
reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.
Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-ference proceedings are available for purchase from the organization sponsoring the publica-tion cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section,'U.S. Nu' lear e
Regulatory Commission, Washington DC 20555-0001.
Copies of industry codes and standards used in a substantive manner in the NRC regulatory
. process are maintained at the NRC Library, Two White Flint North 11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018-3308.
i NUREG-1612 i
d l Status Report: Reactor Vessel
- Integrity Database I
i l
Manuscript Completed: June 1997 Date Published: July 1997 i
C. J. Fairbanks, A. D. Lee, J. MedofT, J. R. Strosnider, K. R. Wichman, B. J. Elliot Divisi n of Engineering Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Wcshington, DC 20555-0001 f.# "*%,
W..... )
_ _ _ - ~
ABSTRACT i
The U.S. Nuclear Regulatory Conunission (NRC)
Some of the data categories contain data inputs of developed the Reactor Vessel Integrity Database docketed" information; other data, categories contain 4
(RVID) following the staff's review of licensee computed numerical values, which may or may not 3
responses to Generic Letter (GL) 92-01, Revision I be docketed.
De programming logic used for (Ref.1). The database summarizes the properties of calculations in the RVID follows the methodology in the reactor pressure vessel (RPV) beltline materials Regulatory Guide (RG) 1.99, Revision 2 (Ref. 2).
for each operating commercial nuclear power plant.
For the Palisades RPV, the data and information ne RVID contains four tables for each plant:
contained in the RVID, Version 1.1, are current (1) background information table, (2) chemistry data through April 12,1995; the data and information for table, (3) upper-shelf energy table, and (4) pressure-the RPVs of all other operating commercial nuclear temperature limits or pressurized thermal shock table.
power plants are current through December 31,1994.
References and notes follow each table documenting ne staff will update the RVID periodically to reflect the source (s) of data and presenting supplemental the latest information available.
Information l
information. Additionally, the RVID has " sort" and contained in the industry's responses to the closeout l
" data search" capabilities. He user can select a letters to GL 92-01, Revision 1, and in the industry's desired grouping of plants and then specify responses to GL 92-01, Revision 1, Supplement 1 information categories to search and list.
(Ref. 3), are not necessarily reflected in this version, but will appear in a future version of the RVID.
De design of the RVID consolidates the industry's RPV data in a convenient end accessible marmer.
)
iii NUREG-1612
--.. ~.. ~.
l t
i CONTENTS Page Abstract.............................................................iij AbbfWViations
..........................................................IX l. Introduction....................................................... 1 - 1 l
l l
2 Background....................................................... 2-1 l
2.1 Staff Review Process for GL 92-01, Revision 1........................... 2-1 2.2 Software and Database Objectives.................................... 2-1 3
Development and Design of Summary Tables.................................. 3-1 3.1 Source Documents............................................... 3-1 3.2 Table Formats.................................................. 3-1 3.2.1 P-T Limits Summary Table (BWRs) or PTS Summary Table (PWRs).............. 3-1 1
3.2.2 Upper-shelf Energy (USE) Summary Table.............................. 3-4 3.2.3 Chemistry Summary Table........................................ 3-6 3.2.4 Plant Background Information Table.................................. 3-6 3.3 Quality Assurance
............................................... 3-7 4
Distribution....................................................... 4-1 5
NUREG 1511, Supplement No.1
.........................................51 6
Comparison of the RVID to the Industry Database "RPVDATA"...................... 6-1 7
Summary and Conclusions.............................................. 7-1 8
References........................................................ 8 - 1 i
I v
r
=
APPENDICES r
t i
l I
A RVID User's Manual
.................................................A-1 l
B Sample RVID Summary Files B-1 t
l t
l l
l l
I i
l vii NUREG-1612 i
i l
i i
ABBREVIATIONS B&W Babcock and Wilcox Company NSSS nuclear steam supply system BAW topical report designation issued by the OD outer diameter Babcock and Wilcox Company P-T pressure-temperature BWR boiling water reactor PTS pressurized thermal shock CE Combustion Engineering Company PWR pressurized water reactor CF chemistry factor QA quality assurance CFR Code ofFederal Regulations RAI request for additionalinformation EMA equivalent margins analysis RG Regulatory Guide EOL expiration of license RPV reactor pressure vessel EPRI Electric Power Research Institute RTsm reference temperature relative to the f
neutron fluence (E > 1 MeV) nil ductility transition l
GE' General Electric Company RTrrs reference temperature for purposes of l
assessing pressurized thermal shock at i
GE-NE topical report designation issued by the expiration of licensee General Electric Company ARTum mean value of the adjustment in the GL generic letter RTym value as a result of neutron irradiation of the beltline material ID inner diameter RVID Reactor Vessel Integrity Database IRTum initial RTym value - the reference l
temperature for unirradiated materials USE upper shelf energy MTEB old abbreviation - Materials and W
Westinghouse Corporation l
Chemical Engineering Branch, l-Division of Engineering, NRR WCAP topical report designation by the Westinghouse Corporation NEI Nuclear Energy Institute l
1/4 T location at one-quarter of the reactor l
NRC U.S. Nuclear Regulatory Commission vessel wall thickness as measured l-relative to the inner vessel wall surface l
NRR Office of Nuclear Reactor Regulation i
l l
ix NUREG-1612
i 1 INTRODUCTION f
b U.S. Nuclear Regulatory Commission (NRC) desired grouping of plants (e.g., all plants) or can developed the Reactor Vessel Integrity Database limit the search to either pressurized-water reactors (RVID) following the staff's review of licensee (PWRs), boiling-water reactors (BWRs), specific responses to Generic Letter (GL) 92-01, Revision 1 owners groups, or selected individual plants, and then (Ref.1). %e database summarizes the propesties of specify up to 10 information categories to search and the reactor vessel beltline materials for each operating list.
commercial nuclear power plant.
The staff revised the RVID and expanded the User's ne design of the RVID consolidates the industry's Manual as a result of its assessment of the RVID, RPV data in a convenient and accessible manner.
Version 1.1, and comments from the database users.
Some of the data categories contain data inputs of in June 1996, the staffissued the RVID, Version 1.1,
" docketed" information; other data categories contain Revision 1, on the World Wide Web. De Web site computed numerical values, which may or may not for the RVID, Version 1.1, Revision 1,
is be docketed.
http://www.nre. gov /NRR/adwl/rvid.htm. To access the Homepage, one must have an Internet account The RVID contains four tables for each plant:
and a Web browser such as Mosaic', Lynx, or 2
(1) background information table ne staff issued Administrative Letter 95-03, (2) chemistry data table Revision 1, " Availability of the Reactor Vessel Integrity Database," on July 10,19% (Ref. 4), to (3) upper-shelf energy table inform the industry of the RVID, Version 1.1, Revision 1.
(4) pressure-temperature (P-T) limits or pressurized thermal shock (PTS) table.
- 1. Mosaic is a trademark of Mosaic communications.
- 2. Lyn is a tudend oRyu ReaWmc Wm, k References and notes following each table document the source (s) of data and provide supplemental
- 3. Netscape is a tudemark of the Netscape Communications information. Additionally, the RVID includes " sort" corporation.
and " data search" capabilities. Users can select a i
11 NUREG-1612
2 BACKGROUND 2.1 Staff Review Process for GL 92-01. Revision 1 2.2 Software and Database Obiectives The U.S. Nuclear Regulatory Commission (NRC)
The staff created the RVID to use as ta tool for issued Generic Letter (GL) 92-01, Revision 1 assisting the staff in its evaluations of domestic (Ref.1), to obtain infonnation naadal to===aan RPVs. The staff designed the RVID in a manner that boensee compliance with requirements and enabled consolidation of materials pmperty data and commutmaata regarding reactor pressure vessel (RPV) information in a convenient and accessible manner.
integrity. De staff issued GL 92-01, Revision 1, in Additionally, the staff designed the RVID to provide a simplified means through which information response to concerns that arose as a result of the staff's review of the vessel integrity assessments for important to evaluating RPV integrity could be the Yankee Rowe RPV.
disseminated to the public and industry.
The staff compiled data from the responses to ne staff's objective for the software design was to GL 92-01, Revision 1, in the RVID computerized present the information in an efficient " user-friendly" t
l amaahana Based on review of the data in the database manner. Therefere, the staff designed the database's j
and plant-specific reviews, the staff concluded that screens in " Windows-type" formats and summarized licensees may not have considered all the relevant the plant-specific information into four tables for each data in their RPV======aats. Derefore, the staff, plant. The staff added " sort" and " query" capabilities issued Supplement I to GL 92 01, Revision I to enable the user to select a customized set of (Ref. 3), in May 1995. The supplement required that information categories from the data and information l
all addressees identify, collect, and analyw the categories contained in the four tables.
impact of any new data pertinent to the sta :tural integrity of their RPVs relative to the requirements Since the RVID was developed as a relational d
of 10 CFR 50.60 (Ref. 5),10 CFR 50.61 (Ref. 6),
database, the staff selected FoxPro as the l
and Appendices G and H to 10 CFR Part 50 programming language for the database. FoxPro was (Refs. 7 and 8), as well as any potential impact on selected in order to minimize run times.
The l
low temperature overpressure protection (LTOP) calculated values in the database were coded limits or pressure-temperature (P T) limits.
according to the methodologies of Regulatory Guide 1.99, Revision 2 (Ref. 2).
All licensees have responded to GL 92 01, Revision 1, Supplement 1.
Some licensees have The following system requirements (configuration) provided additional data that were not provided in are needed in order to operate the RVID:
their initial response to the GL. However, in regard 386 personal computer (486 preferred) to GL 92-01, Revision 1, Supplement 1, no licensee i
has yet to identify any significant RPV integrity
- DOS Version 5.0 or above issue. Most licensees have indicated that they are
- 6 to 8 megabytes RAM e color monitor (preferred) participating in the owners group activities that will determme whether new information is available. The o mouse (preferred) industry is coordinating the owners group activities e files = 99 through the Nuclear Energy Institute (NEI). The o buffers =20 l
Boiling Water Reactor Vessel and Internals Project l
(BWRVIP) is coordinating activities for boiling-water The staff recommends use of a 486 personal reactors (BWRs). De Combustion Engineering computer in order to reduce run times. De staff also Owners Group (CEOG) and Babcock and Wilcox recommends use of a color monitor and a mouse so Owners Group (B&WOG) have instituted programs that the user may take advantage of the color-based, to resolve the issue concerning weld chemistry
" Windows-type" format and mouse-driven menu variability.
- 4. FoxPro is a tradernark of the Microsoft Corporation.
l 21 NUREG-1612
l l
i i
functions. In addition, the staff recommends that consult with their resident computer experts for 1
users consult with their resident computer experts to assistance if they are not familiar with the features of l
adjust any files or buffers in the database. Use of a this file.
computer setup that is less sophisticated than the minimum recom-N configuration listed above The staff included " help" features throughout the may result in error messages (for example, "Too design of the RVID in order to make the database i
many files are open" and "Too many memory more user friendly. A user who has difficulty variables") during access to the database. h file navigating or understanding the system, may tum to and buffer configurations set up the available space in the help features for assistance, b RVID User's which FoxPro may work. If not enough space is Manual accompanies the diskettes to provide j
available, the system may
- crash" (fail) during access additional detailed information regarding the system.
to the datahama. b file and buffer configurations b User's Manual also appears (in a re-edited form) for the operating system are designated in the in Appendix A to this report.
config.sys file. b staff recommends that users
)
l 5
NUREG-1612 2-2
(
-. --. - - - -._ - =
- - ~ = --. - - -. -
L 3 DEVELOPMENT AND DESIGN OF
SUMMARY
TABLES 3.1 Source Documents (3) an upper-shelf energy (USE) table he data and information inputted into the RVID (4) a P-T limits table (boiling-water reactors, were provided by licensees as pan of their RPV BWRs) or a PTS table (pressurized-water integrity evaluations. The staff used the following reactors, PWRs),
documents as sources of information and data for development of the Reactor VesselIntegrity Database He summary reports are presented as tables; each (RVID) tab les:
beltline material is identified in one column, and various information categories are identified in other
- licensee responses to Generic Letter columns. References and notes follow each table to (GL) 92-01, Revision 1 (Ref.1) document the original sources of data and to provide supplemental information not incorporated into the
- licensee responses to staff requests for tables. An example of each of the tables appears in additional information (RAls)
Appendix B to this report.
e documents referenced in licensee responses to 3.2.1 P-T Limits Summary Table (BWRs) or GL 92-01, Revision 1 IrTS Summary Table (PWRs)
- surveillance capsule reports Each BWR has a P-T limits table; each PWR has a FTS table. Information headings for these tables are e pressure-temperature (P-T) limits submittals as follows:
- pressurized thermal shock (IrrS) submittals Column 1:
Plant Name contains the name of the plant, date of expiration of Except for data and information regarding the license (EOL), and docket number.
Palisades RPV, the data and information contained in the RVID, Version 1.1, are reflective of " docketed
- Column 2:
Beltline Identification provides the information through December 31, 1994. The data plant-specific beltline material and information for the Palisades RPV are current identification, which generally through April 12, 1995. The staff reviewed the data consists of a component and information regarding the Palisades RPV during description, location, and number.
the development of the RVID, Version 1.1.
He staff summarized its evaluation of the FTS assessment Column 3:
Heat Identification Number for the Palisades RPV in a letter to the licensee, identifies the heat number of the dated April 12,1995 (Ref. 9).
beltline material. The following items represent possible suffixes that may be used in conjunction 3.2 Table Formats with or in lieu of the Heat Number Identifications for RPV beltline The staff designed the format of the RVID to contain materials:
four tables for each plant:
(S)- when this suffix is used after (1) a background information table a heat number for a specified beltline weld material, the suffix (2) a chemistry data table indicates that a single wire was used in the single arc welding (SAW) process.
I I
3-1 NUREG-1612 i
\\
(T) - when this suffix is used after a Column 5: ID Neutron 71uence O EOL is the heat number for a specified beltline neutron fluence value at the inner weld material, the suffix indicates that diameter (ID) of the reactor vessel a tandem wire was used in the SAW at EOL His value is either cited process.
directly or calculated by applying l-the neutron fluence of the one-l
. NA/W-A - when this suffix is used in quarter thickness (1/4 T) location,
)
lieu of a heat number the suffix as reported in the licensee's most l
indicates that a corresponding heat recent submittal for the beltline number was not available for the plant material, to the neutron fluence l
specific beltline weld material specified attenuation equation in Regulatory l
in Column 2 of the Summary File. In Guide (RO) 1.99, Revision 2 i
the event that more than one weld did (Ref. 2). All entries are given in not have an available heat number for a umts of 10 n/cm'.
given plant, these would be identified as NA/W B, NA/W-C, etc.
Column 6: IRTm is the initial RT,w of the l.
unirradiated material as defined in NA/PL-A - when this suffix is used in ASME Code Section III, paragraph 1
lieu of ;a heat number, the suffix NB-2331, or from alternative indicates that a corresponding heat methodologies, in accordance~ with
)
number was not available for the plant Branch Technical Position MTEB
.l specific beltline plate material specified 5-2 in Standard Review Plan in Column 2 of the Summary File. In Section 5.3.2 (Ref.10).
l the event that more than one plate did l-not have an available heat number for a Column 7: Method of Determining IRTm is given plant, these would be identified as the method of determming the l
NA/PL-B, NA/PL-C, etc.
initial reference temperature. De l
following methods provide 'the NA/F-A - when this suffix is used in possible inputs to this column:
lieu. of a heat number, the suffix
)
indicates that a corresponding heat B&W Generic indicates the initial number was not available for the plant-reference temperature is the generic l
specific beltline forging material value for all Linde 80 welds j
i specified in Column 2 of the Summary fabricated by Babcock and Wilcox, File. In the event that more than one excluding material heat number forging did not have an available heat 72105.
number for a given plant, these would be identified as NA/F-B, NA/F-C, etc.
Generic indicates that the initial reference temperature is the generic
)
Column 4: ' RTm O EOL provides the reference value for Linde 0091, Linde 1092, temperature as adjusted for the effects Linde 124, and ARCOS B-5 welds of neutron irradiation at the EOL. This fabricated by' Combustion adjusted reference value temperature is Engineering.
equivalent to the sum of the initial l
RTum value, margin value, and MTEB 5-2 indicates that the initial j
ART,w value at EOL.
reference temperature is a value I
determined using the methodology I
in Branch Technical Position l
MTEB 5-2 in Standard Review Plan Section 5.3.2.
i l
l
~
NRC Generic indicates that the initial Column 12:
Margin is a numerical-quantity reference temperature is a bounding added to cover uncertainties in the generic value for heat number 72105 values of initial RT,m, copper and welds fabricated by Babcock &
nickel measurements, fluence, and Wilcox.
the calculational _ procedures involved in deternuning RT,m.
' Plant Specific indicates that the initial
- Ihe margin is calculated according reference ~ temperature value was to the methodology of RG 1.99, determined from tests on material Revision 2. According to the RG, removed from the same material heat the Margin = 2*(a,2 + c/)*8, 8d as was the identified beltline material.
Column 13:
Method of Determining Marginis Column 8: - ART,arr O EOL is the mean value of the method of determuung the the adjustment in reference margin value.
The following temperature caused by irradiation.
methods provide the possible inputs ARTum is calculated in accordance to this column:
with the FTS rule as follows: ART,m
= (CF)*f** **" 8, where CF is the Table. indicates that the margin chemistry factor and f (in units of term was calculated using a j
2 10E19 n/cm ) is the neutron fluence of standard deviation for the increase i
the beltline material projected at EOL.
in reference temperature of15.6 *C (28 *F) - for welds and 9.4 *C l
Column 9:. Muence Factor @ EOL is calculated (17 'F) for base metal.
as follows: fluence factor at EOL =
f* * * * *"'* 8 where f (in ' units of Sury. Capsule indic'ates that the 2
10E19 n/cm )is the neutron fluence of margin term was calculated using a the beltline material projected at EOL.
standard deviation for the increase in reference temperature of 7.8 *C Column 10: Chemistry Factor is the chemistry (14*F) for welds and 4.7 *C factor for irradiated reference (8.5 *F) for base metal, temperature evaluation.
Column 14:
Cu% provides the copper content, Column 11: Method of Determining CF is the cited directly from the licensee's method of determining the cheinistry value, except when more than one
~ factor.
The following methods value was reported (in which case provide the possible inputs to this the staff used the average value).
column:
Table indicates that the chemistry factor was deternuned using the best-
- 5. Hero o, is the mandard deviation for the initial RT,w. If a estimate chemistry values (copper and maured value of initial RT,w for the material in quemion is nickel) and the tables in RG 1.99' awaable, o, is to be eminuied from the precision of the test Revision 2.
method, if not. and generic mean values for that cleas of material are used, og i ihe siandard deviationobtained from the set of data used to establish the mean.
Calculated indicates that the chemistry factor was determined using the plant-
- 6. The standard deviation for ART,w, o.. is 15.6*c (28*F) for specific surveillance data, welds and 9.4*C (17*F) for base nwial, except that o, need not excud 0.50 times the nwan value of ART,w. If two or more
- '""*"""d''"'"
Override indicates that the chemistry establish the ART,w, the values for 04 may be cut in half.
factor was determined using a methodology approved by the NRC.
3-3 NUREG-1612
Column 15: Ni% provides the nickel content, cited Column 12:
Margin-calculated from the inputs directly from the licensee's value, of a, and a,.
except when more than one value was reported (in which case the staff used 3.2.2 Upper-shelf Energy (USE) Summary Table the average value).
Information headings for the USE Summary Tables The following represent columns in the Summary File include:
for IFTS/P-T Limits whose numerical or text values are entered directly from a source document:
Column 1:
Plant Name contains the name of the plant, date of EOL, and docket Column 1: Plant Name number.
Column 2: Beltline Identification Column 2:
Beltline Identification provides the j
plant-specific beltline material Column 3: Heat No. Identification identification, which generally consists of a component Column 5: ID Neutron Fluence @ EOL description, location, and number, j
Column 6: IRTum Column 3:
IIeat Number Identification identifies the heat number of the Column 7: Method of Determining IRTum beltline material. A number of suffixes may accompany or be used Column 9: Chemistry Factor, in the case of an in lieu of the heat number Override identifications in this column.
Refer to the suffixes described Column 11: Method of Determining Chemistry under the informational heading for Factor Column 3 in Section 3.2.1 of this Chapter.
Column 12: Margin-inputs of a a id -
l i
Column 4:
Material Type provides the Column 13: Method of Determining Margin material type for each plate, Column 14: Cu% (the average value is listed if more than one value is reported)
Column 5:
USE @ EOL @ 1/4 T is the calculated upper-shelf energy value Column 15: Ni% (the average value is listed if (in ft-lb) at EOL as determined for more than one value is reported).
the one-quarter thickness location of the RPV.
The following columns represent columns in the Summary File for PTS /P-T Limits whose numerical Column 6:
1/4 T Neutron Fluence @ EOL is data have been obtained by using the calculational the neutron fluence value at EOL l
methodology of RO 1.99, Revision 2:
for one-quarter thickness location of the RPV. This value is either Column 4: RTrrs @ EOL cited directly or calculated by applying the ID neutron fluence, as Column 8: ARTum @ EOL reported in the licensee's most recent submittal for the beltline Column 9: Fluence Factor @ EOL material, to the neutron fluence attenuation equation in RG 1.99, Column 10: Chemistry Factor Revision 2. All entries are given in units of 10" n/cm'.
NUREG-1612 3-4 l
_-_.._.___.__._____._..-m i
i Column 7: Unirradiated USE is the unitradiated Sister Plant indicates that the upper-shelf energy in units of ft-Ib.
unitradiated USE was derived by using the reported value from other Column 8: MethodofDetermining Unirradiated plant (s) with the same weld wire USE describes the method of heat number.
deternunmg the unirradiated upper-shelf energy. The following methods EMA indicates that an unirradiated provide the possible inputs to this USE is unnecessary because the column:
licensee has satisfied the USE requirements of Appendix G to Direct-for plates, this indicates that 10 CFR Part 50 (Ref. 7), through l
the unirradiated USE was determined an equivalent margins analysis.
l from Charpy-V tests on transverse test specimens. For welds, this indicates Column 9:
% Drop USE @ EOL @ 1/4T that _ the unirradiated USE was describes the percentage drop in determined from Charpy-V test data.
USE from the initial unirradiated j
value to the value projected to 65 % indicates that the unirradiated occur at EOL as a result of USE was calculated in accordance radiation embrittlement.
with Section 1.2 of Branch Technical Position MTEB 5-2, "Frecture Column 10: Method Determ % Drop describes
)
Toughness Requirments" at 65 % of the method of determining the the USE value obtained from percentage drop in USE.
The l
Charpy-V tests on longitudinal test following methods provide the specimens.
possible inputs to this column:
Generic indicates that the unitradiated Position 1 of RG 1.99, Rev. 2 USE was reported by the licensee indicates that the percentage drop in I
from USE data of other plants with USE was determined using the similar materials to the beltline percentage copper and the material.
methodology in Position 1 of RG 1.99, Revision 2.
NRC Generic indicates that the unirradiated USE was derived by the Surveillance Data indicates that the i
staff from the USE data of other percentage drop in USE was plants with similar materials to the determined using surveillance data beltline weld.
and the methodology in Position 2 of RG 1.99, Revision 2.
10,30,40 or 50 'F indicates that the unirradiated USE was derived from EMA indicates that the percentage Charpy-V tests conducted at 10, 30, drop in USE is unnecessary 40 or 50 *F.
because the licensee has used an equivalent margins analysis to Sury Weld indicates that the satisfy the USE requirements of unirradiated USE was from the.
Appendix G to 10 CFR Part 50.
surveillance weld having the same weld wire heat number.
l 3-5 NUREG-1612
\\
_ _ ~ _ -. _ _. _.
Column 11: Cu% provides the copper content, cited Column 2:
Bdtline Identification contains the dimetly from the licensee's report, plant-specific beltline material except that when more than one value identification, which generally was reported, the staff used the average consists of a component
. of the reported values, description, location, and number.
'Ibe following represent columns in the Summary File Column 3:
Heat No. Ident. indicates the for USE whose numerical or text values are entered beltline material heat number.
directly from a source document:
Column 4:
%Cu provides the copper content, Column 1: Plant Name cited directly from the licensee's report, except that when more than i
Column 2: Beltline Identification one value was reported, the staff used the average of the reported Column 3: Heat No. Identification values.
Column 4: Material Type Column 9:
%Ni provides the nickel content, cited directly from the licensee's Column 7: Unirradiated USE report, except that when more than one value was reported, the staff I
Column 8: Method of Determining USE used the average of the reported values.
Column 10: Method of Determining % Drop the phosphorous Column 14: %P provides Column 11: Cu% (the average value is cited if content, cited directly from the l
more than one value is reported) licensee's report, except that when i
more than one value was reported, The following columns '~ represent columns in the the staff used the average of the Summary File for USE Limits whose numerical data reported values.
have been obtained by using the calculational j
methodology of RG 1.99, Revision 2:
Column 15: %S provides the sulfur content, cited directly from the licensee's j
Column 5: USE @ EOL @ 1/4T report, except that when more than one value was reported, the staff Column 6: 1/4T Neutron Fluence @ EOL used the average of the reported values.
)
Column 9: % Drop'@ EOL @ 1/4T i
All other columns are blank at this time, for all i
3.2.3 Chemistry Summary Table plants.
4 Information headings for the Chemistry Summary 3.2.4 Plant Background Information Table Tables include:
The plant background information table contains Column 1: Plant Name contains the name of the general information for each plant, including the plant, date of EOL, and docket following data:
1 number.
I
- Plant Name
- Docket Number NUREG-1612 3-6
- NSSS (Nuclear Steam Supply System) Vendor
- Diablo Canyon, WCAP-12811
- Vessel Manufacturer
- McGuire 2, WCAP-13516
- Date of License Expiration
- Millstone 1, GE-NE-523-165-1292, I
e Vessel Beltline nickness
- Calvert Cliffs, BAW-1260
- Vessel Inside Radius The PR EDB is a comprehensive collection of data from surveillance reports and other published reports of commercial nuclear reactors. However, the data 3.3 Ouality Assurance have not been verified by reactor vendors, and the capsule data were not evaluated according to The staff performed a quality assurance (QA) check credibility criteria.
Surveillance data for the of the data and information contained in the RVID.
following plants were excluded from the RVID The staff compared data from the source documents Surveillance Files because credibility could not be to the data in the RVID and ind*p-lantly verified established:
I the accuracy of calculated database values. The staff attributed small discrepancies in the calculated values
- Haddam Neck, Capsule A/BMI-1070, not to differences in the methods for performing credible for welds calculations or for rounding off numerical values.
- Quad Cities 1, not credible for welds
_1 I
Each licensee received copies of the summary tables for its respective plant (s). The staff requested that
- Turkey Point 3 and 4, not credible for weld licensees confirm the applicability of the unirradiated heat no. 71249 properties, neutron fluence, and chemical composition j
that provided the basis for the plant summaries.
The staff did not complete credibility studies of plant-i Most licensees confirmed that the data in the RVID specific surveillance data prior to issuance of the are applicable to their plants; however, some original version (Version 1.1) of the RVID. The licensees submitted new or additional data for their staff compared data values from the PR-EDB to data vessels in their plant-specific responses to the staff's stored in the RVID under " Surveillance Capsule i
closeout letters to GL 92-01, Revision 1, or in their Reports" in order to identify and correct I
plant-specific responses to GL 92-01, Revision 1, discrepancies and data entry errors. The staff added Supplement 1 (Ref. 3).
Most licensees have a means ofidentifying surveillance data as credible or participated. in the vessel integrity data searches non-credible in the RVID Version 1.1, Revision 1, performed by the industry owners groups in order to and completed a credibility assessment for the address the issues raised in the GL.
The new following eight nuclear plants: (1) Kewaunee, information is expected to be available by the end of (2) Indian Point Unit 2, (3) Indian Point Unit 3, Summar 1997. The staff will assess all new plant (4) Maine Yankee, (5) Robinson Unit 2,
l data, and any revisions to the plant-specific data will (6) North Anna Unit 1, (7) Haddam Neck, and l
be reflected in a future version of the RVID. Data (8) Diablo Canyon Unit 1. The staff assessed the l-regarding decommissioned plants have not been surveillance data for these units because the RVID l
included in the database, reflected that surveillance data were being utilized for
^
calculation of the chemistry factor for the limiting Data for each surveillance capsule report are listed material in the reactor vessel. The staff determined individually, ne source for surveillance data was that the licensees for Kewaunee, Indian Point Unit 2, l
'the-Power Reactor - Embrittlement Database Indian Point Unit 3, Maine Yankee, Robinson Unit 2, (PR-EDB), Version 2 (Ref. I1), with the exceptions and North Anna Unit I had two or more sets of I
that data from the following plant-specific credible surveillance capsule data for the limiting surveillance capsule reports were added:
materials in their vessels (reflected as credible "Y" in the database). The staff determined that the licensees
- Cooper, GE-NE-523159-1292 for Haddam Neck and Diablo Canyon Unit I did not i
3-7 NUREG-1612
have two credible sets of surveillance capsule data for to review surveillance data and will make appropriate the limiting materials in their vessels (reflected as changes for non-credible surveillance data credible 'N' in the database). The staff will continue accordingly in future versions of the RVID.
NUREG-1612 3-8 1
I
t 4 DISTRIBUTION 1
l The staff presented the RVID to the public at an copy printouts of the Sununary Tables for each plant.
l NRC/NEI Workshop that occurred on July 13,1995, Availability of Revision 1 to the RVID Version 1.1, and
--~mM the availability of the database in on the World Wide Web' has made dissemination of Administrative letter 95-03, " Availability of the the RVID more efficient.
Reactor Vessel Integrity Database" (Ref. 12).
Revision 1 of the Administrative Letter (Ref. 4)
Distribution of the RVID began in August 1995.
announced the availability of the RVID Version 1.1, Several hundred copies have been distributed to date.
Revision 1. This is the version of the RVID that is The wide range of requestors comprises licensees, currently available on the world-wide web.'
For research institutions and universities, public interest users who do not have access to a web browser such groups and individuals, State government agencies, 8
as Mosaic, Lynx', or Netscape, the RVID is and foreign regulatory agencies.
l
- available, free of charge, by writing to:
l
- 7. He world wide web location for the RVID Version 1.1,
[
RVID Project Manager.
Revision 1. is http://www.nrc. gov /NRR/adw!/rvid.htm.
j U.S._ Nuclear Regulatory Commission Mailstop O-7D4
- s. Mo.aic i. a trademark of Mosaic communications.
Washington, DC 20555-0001 9.
Lynx is a trademark of Lynx Real-Time Systems. Inc.
For issuance of the original version of the RVID, M. Netscape is a trademark of the Netscape Communications each set of diskettes for the database was corporation.
accompanied by an RVID User's Manual and hard-l l
\\
I 1
4-1 NUREG-1612
,, - ~,
-. - ~.
i 5 NUREG-1511, SUPPLEMENT NO.1 The RVID was a source of data and information for Supplement No. I to NUREG-1511 (Ref.14), a l
NUREG-1511, " Reactor Pressure Vessel Status summary of the staff's assessment of the industry's l
Report * (Ref.13). In addition to being the source of responses to GL 92-01, Revision t Supplement 1.
background information for the report's Reactor
'Ihe supplement to the NUREG r port also described Vessel lategrity Database Summary Sheets (as new inforntion regarding Re sion 1 of the RVID provided in Appendix B to the report), the RVID was and future revisions to tb-atabase.
l the source for the staff's determination of each l
plant's limiting beltline material (s), and respective The staff is cc ;stly switching the environmant for RTrra and USE data, information, and references.
accessing the RVID data to a more user-friendly format. Microsoft Access" software is being used
{
On May 19,1995, the staff issued Supplement I to to bring the database into the Windows environmant Generic Im (GL) 92-01, Revision 1 (Ref. 3), to (as opposed to the current DOS-based Foxpro" ensure that industry licensees were considering all software),
relevant data in their RPV assessments and to resolve j
Sny apparent discrepancies in regard to the data ll. Access and FoxPro ars trademarks of the Microsoft reported in response to GL 92-01, Revision I corpor. tion.
l (Ref.
1).
In October 1996, the staff issued l
l 1
I I
l l
i 1
1 i
i
(
)
5-1 NUREG-1612
l l
6 COMPARISON OF THE RVID TO THE INDUSTRY l
DATABASE "RPVDATA" l
l The original version of RVID is now contained in the The NRC staff and industry are currently working j
industry database "RPVDATA' which is maintained together to resolve inconsistencies between the two by the Electric Power Research Institute (EPRI).
databases. The NRC will make revisions to the RPVDATA runs under Microsoft Access'2 and is a RVID subsequent to the completion of the staff's flat file (no computations are performed within the reviews of the industry's responses to GL 92-01, database).
Revision 1, Supplement 1 (Ref. 3). At that time, it will be possible to compare the NRC and industry RPVDATA also contains several ' tiers" of databases and to establish an NRC-approved baseline l
information which are not in the RVID. Examples database. Subsequently, it may be possible to have include details of weld property sampling and the industry maintain the database with NRC comparisons of licensee "best estimate" chemical oversight. The NRC will be able to verify the composition values with docketed information.
updates by comparisons with docketed plant l
information.
- 12. Access" is a trademark of the Microsoft Corporation.
l l
l i
l l
i l
6-1 NUREG-1612
7
SUMMARY
AND CONCLUSIONS The NRC developed the RVID following the staff's The staff compared data from the source documents review of licensee responses to Generic letter (GL) to the data in the RVID and indepaadmatly verified 92-01, Revision 1 (Ref.' 1).
The database the accuracy of calculated database values. The staff summarizes the properties of the reactor vessel attributed small discrepancies in the calculated values beltline materials for each operating commercial to differences in the methods for performing nuclear power plant.
calculations or for rounding off numerical values.
De staff designed and developed the RVID to reflect Each licensee received copies of the summary tables
]
the current status of RPV integrity. The design of for its respective plant (s). The staff requested that
'1 the RVID consolidates the plant-specific data and licensees confirm the applicability of the unirradiated information in a convenient and accessible manner.
properties, neutron fluence, and chemical composition Some of the information categories (data fields) that provided the basis for the plant stimmaries, contain data ~ inputs from docketed information; Most licensees confirmed that the data in the RVID others contain data that represent computed numerical are applicable to their plants; however, some values, which are not necessarily docketed, licensees submitted new or additional data for their vessels in their responses to the staff's closeout letters The objective of the software design was to present regarding GL 92-01, Revision 1, or in their responses the information in an. efficient ' user-friendly" to GL 92-01, Revision 1, Supplement 1 (Ref. 3).
manner. Therefore, the staff designed the RVID Licensees have participated in the vessel integrity screens in " Windows-type" formats and summarized data searches performed by the industry owners the plant-specific information in four tables per plant.
groups in order to address the issues raised in the De staff added " sort". and " query" capabilities to GL. The new information is expacted to be available by the end of Summer 1997. De staff will assess all provide the user-with the ability to select a customized set of information categories from the new plant data, and any revisions to the plant-specific data will be re.ded in a future version of the r
data and information categories contained in the four tables.
RVID.
He staff used the following documents as the sources The staff revised the RVID and expanded the user's ofinformation and data for development of the RVID manual as a result of the its assessment of the RVID tables: licensee responses to GL 92-01, Revision 1, Version 1.1 and comments from database users. He licensee responses to staff RAls, documents staffissued Revision 1 to RVID, Version 1.1, on the referenced in the responses to GL 92-01, Revision 1, world-wide web in June of 1996." To access the
. surveillance capsule reports, and as applicable, P-T homepage, one must have an Internet account and a limits or ITS submittals. The data and information web browser such as Mosaic'd, Lynx", or Netscape.
containad in the RVID, Version 1.1, with the Administrative Letter 95-03, Revision 1. " Availability exception of Palisades, are current through of the Reactor Vessel Integrity Database" (Ref. 4)
)
December 31, 1994. The data and information for was issued on July 10,1996, to inform the industry the Palisades RPV are current through of the availability of the RVID.
1 I
April 12,1995. The staff evaluated the Palisades RPV during the development of the RVID,
- 13. m World Wide Web location for the RVID Version 1.1, Version 1.1.
The staff summarized the FTS Revision 1 is nitp://www.nrc. gov /NRR/adwl/rvid.htm.
evaluation for the Palisades RPV in a letter to the
' ' M "i" I' ' *d* """ * "N C """.* *d "' '
Consumers Power Company (the licensee for Palisades) dated April 12,1995 (Ref. 9).
- 15. Lynx is a trademark of Lynx Real-Time Systems. Inc.
%e staff performed a quality assurance (QA) check
- 16. Netscape is a trademark of the Netscape Communications of the data and information contained in the RVID.
C TPoradon.
j 71 NUREG-1612 l
r I -
=.
m.,~,.
.y
h staff did not complete credibility studies of plant-Reactor Vessel Integrity Datah==a Summary Sheets specific surveillance data prior to issuance of the (as contained in Appendix B to the report), the RVID original version (Version 1.1) of the RVID.
was the source for the staff's determination of each De staff compared data values from the PR EDB plant's limiting beltline material (s) and the respective (Ref. 11) to data stored in the RVID under RT,rs and USE data, information, and references. In
" Surveillance Capsule Reports" in order to identify addition, NUREG-1511. Supplement No.1 (Ref.14),
and correct discrepancies and data entry errors. The also contained a chapter that describes new staff added a means ofidentifying surveillance data as information regarding Revision 1 of the RVID and credible or not-credible in the RVID Version 1.1, future revisions to the database.
Revision 1, and completed a credibility assessment for the following eight nuclear plants: (1) Kewaunee, h original version of RVID is now contained in the (2) Indian Point 2,
(3) Indian Point 3,
industry database 'RPVDATA' which is maintained (4)
H.R. Robinson 2, - (5) Maine Yankee, by EPRI. RPVDATA runs under Microsoft Access" (6) North Anna 1,
(7) Haddam Neck, and is a flat file (no computations are performed and (8) Diablo Canyon 1.
b staff assessed the within the database),
surveillance data for these units because the RVID reflected that surveillance data were being utilized for The staff is currently switching the environment for calculation of the chemistry factor for the limiting accessing the RVID data to a more user-friendly material in the reactor vessel. The staff determined format. Microsoft Access" software is being used to that the licensees for Kewaunee, Indian Point 2, bring the database into the Windows environment (as Indian Point 3, Maine Yankee, H.R. Robinson 2, and opposed to the current DOS-based Foxpro" North Anna 1 had two or more sets of credible software),
surveillance capsule data for the limiting materials in their vessels (reflected as credible "Y" in the The NRC will revise the RVID after it completes its datahana). De staff determined that the licensees for reviews of the industry's responses to GL 92-01, H=ldam Neck and Diablo Canyon 1 did not have two Revision 1. Supplement 1. At that time, it will be credible sets of surveillance capsule data for the possibir to compare the NRC and industry databases limiting materials in their vessels (reflected as and establish an NRC-approved baseline database.
credible 'N' in the database). The staff will continue Subsequently, it may be possible to have the industry to review surveillance data and will make appropriate maintain the database with NRC oversight, b NRC changes for non-credible surveillance data will be able to verify the updates by comparisons accordingly in future versions of the RVID.
with docketed plant information.
b RVID was a source of data and information for
- 17. Access" and FoxPro are trademarks of the MicrosoA NUREG-1511, " Reactor Pressure Vessel Status corporation.
Report" (Ref.13). In addition to being the source of background information for the report's l
l l
4 NUREG-1612 7-2
8 REFERENCES 1.
Generic Iatter 92-01, Revision 1, " Reactor Vessel Structural lategrity.10 CFR 50.54(f)," March 6,1992.
2.
Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials," May 1988.
3.
Generic Letter 92-01, Revision 1, Supplement 1, " Reactor Vessel Structural Integrity," May 19, 1995.
4.
NRC Administrative Letter 95-03, Revision 1, " Availability of the Reactor Vessel Ittegrity Database,"
July 10,1996.
l 5.
Title 10, Code offederal Regulations, Section 50.60, " Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation."
6.
Title 10, Code of Federal Regulations, Section 50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
7.
Title 10, Code of Federal Regulations, Part 50, Appendix G, " Fracture Toughness Requirements."
8.
Title 10, Code offederal Regulations, Part 50, Appendix H, " Reactor Vessel Material Surveillance Program Requirements."
9.
Letter from E.G. Adensam, Acting Director - Division of Reactor Projects lil/IV, Office of Nuclear Reactor Regulation, to K.M. Haas, Plant Safety and Licensing Manager - Palisades Plant, " Palisades Plant -
Pressurized Thermal Shock Safety Evaluation (TAC No. M83227)," April 12,1995.
i
- 10. NUREG-0800, " Standard Review Plan," Section 5.3.2, ' Pressure-Temperature Limits," Branch Technical i
l I
Position MTEB 5-2, " Fracture Toughness Requirements," Revision 1, July 1981.
I
- 11. NUREG/CR-4816, ORLN/TM-10328/R2, Rev. 2, "PR EDB: Power Reactor Embrittlement Database, Version 2," January 1994.
- 12. NRC Administrative Letter 95-03, " Availability of the Reactor Vessel integrity Database," August 4,1995, i
- 13. NUREG 1511, " Reactor Pressure Vessel Status Report " December 1994.
- 14. NUREG 1511 Supplement 1, " Reactor Pressure Vessel Status Report," October 1996.
l 9
8-1 NUREG-1612
~ ~ ~
APPENDIX A Reactor Vessel Integrity Database Version 1.1 Revision 1 User's Manual Initial Publishing: June 1996 Edited: June 1997 Republished for NUREG-1612: July 1997 U.S. Nuclear Regulatory Commission I
A-1 NUREG-1612
DISCLAIMER NOTICE
)
This database was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of its employees, makes any warranty, expressed or implied, or assumes any legal liability of responsibility for any third-party's use, or the results of such use, of any information, apparatus, product, or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.
f
)
i S
I i
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. NUREG-1612 A-2
P i
ABSTRACT 1
4 The Reactor Vessel Integrity Database (RVID) was developed following NRC staff review of licensee responses to Generic Letter (GL) 92-01, Revision 1. The database summarizes the properties of the reactor vessel beltline materials for each ooerating commercial nuclear power plant.
iN RVID contains four tables for each plant: (1) background information table, (2) chemistry data i
table, (3) upper-shelf energy table, and (4) pressure-temperature limits or pressurized thermal shock table.
References and notes following each table document the source (s) of data and provide supplemental j
information. Additionally, the RVID has " sort" and " data search" capabilities. The user can select a desired grouping of plants and then specify information categories to search and list.
De RVID was designed and developed to reflect the current status of reactor pressure vessel integrity, l
and the data are consolidated in a convenient and accessible manner. Some of the data categories are inputs of docketed information; other data categories are computed values, which are not necessarily docketed. The programming logic used for calculations in the RVID follows the methodology in Regulatory Guide 1.99, Revision 2.
He data and information contained in the RVID are current through December 31,1994, except for the data and information for the Palisades nuclear plant which are current through April 12,1995. He Palisades reactor pressure vessel was being evaluated during the development of the RVID, Version 1.1.
On April 12, 1995, in a letter to the licensee, the staff summarized its PTS evaluation. The RVID will be updated periodically to reflect the latest information available. Information contained in the responses to the staff's closecut letters to GL 92-01, Revision 1, and information contained in industry submittals t
to GL 92-01, Revision 1, Supplement 1, are not necessarily reflected in this version, but will be included in a future version of the RVID.
A-3 NUREG-1612
)
i I
CONTENTS F
page DISCLAIMER NOTICE.............................................. A-2 '
l d
ABSTRA CT..................................................... A-3 l
1.0 SET U P TH E S YSTEM........................................... ' A-7 I
- 1.1 System Requirements...........
............. A -7
\\
1.2 Files & Buffers
............ A-7
)
i 1.3 LAN Configurations
............................................A-7
-)
l.4 Transferring RVID Files to Hard Disk
.......................A-8 1.4.1 Instruction A - Setting Up the RVIDPUB. BAT Batch File.................... A 1 1.4.2 Instruction B - Moving the RVIDPUB. BAT Batch File to the C:\\ BATCH Directory A-9 i
1.5 Preparing a Windows Icon or DOS Menu Addition
........................A 1.5.1 Preparing a Windows Icon
.....................................A-10 1.5.2 Preparing a DOS Menu Addition
......... A-10 2.0 START USING RVID........................................... A-l l 2.1 Starting the Database........................................... A :
. 2.2 Selecting Main Menu Options
.....................................A-11 2.2.1 System Menu A-12 2.2.2 Reports Menu A-12 2.2.3 Applications Menu
...............................A-12 2.2.4 About Menu A-13 3.0 PRINTING REPORTS A-13 l
l 3.1 Printing PTS Summary, USE Summary, and Chemistry Data Reports............ A-13 3.2 Printing Reports from Queries
.....................................A-14 NUREG-1612 A-4
1 i
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1 i
page l
3.2.? Selecting a Base Metal
........................................A-15 1
3.2.2 Selecting a Heat Wire and Flux Type............................... A-16
)
3.2.3 Entering Query Selection Criteria
.................................A-16 i
l 4.0 PLANT INFORMATION......................................... A-18 i
4.1 Viewing Plant Information
.......................................A-18 1
4.2 Finding a Plant Record
.........................................A-19 4.3 Selecting Browse Menu Options.................................... A-20 4.4 Viewing Forgings, Plates, Welds, and Surveillance Data..................... A-20 i
5.0 USING HELP OFTIONS
.........................................A-21 6.0 REINDEX & PACK............................................ A-21 7.0 SETTING PREFERENCES
.......................................A-22 8.0 BACKCROUND AND SOURCE DOCUMENTS.......................... A-22 9.0 EXPORTING QUERIES TO A SPREADSHEET
..........................A-24 10.0 NOMENCLATURE FOR USE, PTS, AND CHEMISTRY DATA
SUMMARY
REPORTS A-24 10.1 Summary File for FTS/P-T Limits
.................................A-24 10.2 Summary File for Upper Shelf Energy
...............................A-27 10.3 Summary File for Chemistry Data.................................. A-30 1
1.0 REFERENCES
............................................... A-30 12.0 COMMENTS AND FEEDBACK
...................................A-30 A-5 NUREG-1612
l FIGURES me i
Figure 0.
DOS Generated Systems Menu
.................................A-9 i
Figurel. Main Menu A-I l Figure 2.
Main Menu Options........................................ A-12 Figure 3.
Summary Reports Menu A-13 Figure 4.
Report Selection Screen A-14 Figure 5.
Query Subjects Screen A-15 Figure 6.
Example Box A-16 Figure 7.
Query Selection Criteria Screen A-17 Figure 8.
Plant information Screen..................................... A-18 Figure 9.
Record Search Box A-19 1
Figure 10. Browse Screen A-19 i
Figure ll. Reindex & Pack Screen A-22 l
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NUREG-1612 A-6
i l
-REACTOR VESSEL INTEGRITY DATABASE USER'S MANUAL 1.0 SET UP THE SYSTEM i
This section gives step-by-step instructions for getting your computer ready to run the Reactor Vessel Integrity Database (RVID).
I 1.1 System Reautrements The following system requirements are needed in order to operate the RVID:
386 personal computer (486 preferred)
DOS Version 5.0 or above 6 to 8 megabytes RAM l
color monitor (preferred) mouse (preferred)
L
- files =99 l
l buffers =20 1.2 Files and Buffers Files and buffers are best adjusted by your resident computer expert. If you do not have the minimum system requirements listed above you will encounter such errors as "Too many files are open" and "Too many memory variables." These files and buffer configurations set up the space available in which FoxPro' may work. If there is not enough space the database will fail. These configurations are in the config.sys file; however, if you are not familiar with this file you should consult your resident computer expert for assistance.
1.3 LAN Confieurations l
This version of RVID was not specifically designed to work in a networked environment; however, it can l
limp along under that scenario. A user may encounter several problems when multiple users try to access the system simultaneously. These problems are listed at the top of the next page:
- 1. Foxb is a tndemaA of the Microsoft Corporation.
A-7 NUREG-1612 t
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-. ~ ~... --
i
- 1) If a user tries to Reindex the database while another user is in the system, an error message will appear stating that the operation cannot be completed because another user is in the system. Hat will only be resolved when the other user logs out of the system.
- 2) If several users try to run different reports simultaneously, the user will get the same error message as stated above. Several of the files are used exclusively because indexes are recreated. Herefore, only one user can run the reports at a time.
1.4 Tr== 4fina RVID Files to Hard Drive Create a directory called "RVID" and copy files from the system diskettes to your hard drive by following these steps:
Start at the DOS prompt in the DOS root directory ( C:\\> ) or change to the root directory by typing CD\\ and pressing the < Enter > key.
You will now be at the DOS prompt in the root directory ( C:\\> ).
j Type MD\\RVID and press < Enter > to create ait "RVID" subdirectory.
Type CD\\RVID and press < Enter >. You whl now be at the DOS prompt in the RVID subdirectory ( C:\\RVID\\> ).
Follow the instructions below to copy the files from the diskette (in your "A:" drive) to the RVID subdirectory on your hard drive.
Type COPY A:\\*.* and press < Enter >.
Repeat for each of the five diskettes. De diskettes may be copied in any order.
Now that you have copied the files from the diskettes to your hard drive, you need to ensure that you have an RVIDPUB. BAT file. Since you are in the RVID subdirectory ( C:\\RVID\\> ), type dir *, bat and press the < Enter > key. His will give you a listing of all the batch files in the subdirectory. If you do not see RVIDPUB. BAT batch file, you will need to create it. If such a batch file exists, skip to Section 1.4.2 of this Appendix (Instruction B); otherwise, go on to Section 1.4.1 of this Appendix (Instruction A).
1.4.1 Instruction A - Setting Up the RVIDPUB. BAT Batch File Create an RVIDPUB. BAT batch file. To create the batch file you need to type edit and press the
< Enter > key. You will find yourself in the DOS edit function. Your cursor defaults to the first line.
Perform the following actions:
(1) Type CD\\RVID, then press < Enter >.
(2) Type RVIDPUB, then press < Enter >.
NUREG-1612 A-8
(3) Simultaneously press the Alt and F keys. It will bring up a menu as is illustrated below (Figure 0).
New Open Save Save As Print Exit Figure 0. DOS Generated Systems Menu (4) Select Exit (or hit the < x > key) to exit from the DOS edit function.
(5) A message will appear asking the user if the user wants to save the document before exiting. Select Yes (or hit the <y> key). The system will then save the RVIDPUB. BAT file and exit from the DOS edit function.
(6) You will then be at the DOS prompt in the RVID subdirectory ( C:\\RVID\\> ).
(7) Continue on with Instruction B.
1.4.2 Instruction B - Moving the RVIDPUB. BAT Batch File to the C:\\ BATCH Directory l
You are ready to move the RVIDPUB. BAT file from the C:\\RVID directory to the C:\\ BATCH directory.
l This is accomplished by performing the following actions:
(1) Start at the DOS prompt in the RVID subdirectory ( C:\\RVID\\> ) or change to the RVID subdirectory by typing CD\\RVID. You will now be at the DOS prompt in the RVID subdirectory
( C:\\RVID\\> ).
l (2) Type COPY RVIDPUB. BAT C:\\ BATCH and press < Enter >.
l (3) Type DEL RVIDPUB. BAT and press < Enter >.
Note that most personal computer systems have the BATCH directory already established. If your system does not have a BATCH directory established, consult your DOS software manual for instruction.
Creating a BATCH file will involve editing the AUTOEXEC. BAT file; therefore, the assistance of available software support services is recommended.
However, as an alternative to creating the C:\\ BATCH directory, you may access the RVID by doing the following:
(1) Start at the DOS prompt in the RVID subdirectory ( C:\\RVID\\> ).
(2) Type FOXR RVIDPUB and press < Enter >.
A-9 NUREG-1612
l.5 Prenarine a Windows Icon or DOS Menu Addition If you intend to run the RVID using Windows, then add an icon to your screen by following the steps below under " Preparing a Windows Icon." If you intend to stan RVID directly from DOS, follow the steps below under " Preparing a DOS Menu Addition." If you do not wish to modify or work with a DOS menu, you may disregard the explanations that follow and skip to Section 2.0, " Start Using RVID" on page A-11.
1.5.1 Preparing a Windows Icon Perform the following actions to prepare a " Windows" icon for the RVID:
(1) Start Windows.
(2) Select the Applications icon. If there is no Applications icon, select an icon that you would like to use in place of it.
(3) Select New from the File menu.
(4) Select Program Item.
(5) Select OK.
(6) In the Description field, type Reactor Vessel Integrity Database or RVID (7) In the Command box, type C:\\ BATCH \\RVIDPUB. BAT (8) In the Working Directory, type C:\\RVID (9) Select OK.
Your new icon will allow you to start the RVID system.
1.5.2 Preparing a DOS Menu Addition (1) Type CD\\ DOS and press < Enter >. You will now be in the C:\\ DOS directory.
(2) Type EDIT MENU.TXT and press < Enter >. Your menu will appear on the screen. If the screen is blank, it means that your MENU.TXT file is in a different directory.
(3) Add RVID to your DOS menu with the following description: Reactor Vessel Integrity Database.
-(4) When you are ready to save your new menu, press < Alt >. The File menu will be highlighted.
i (5) Press the up arrow twice to highlight the Exit option.
NUREG-1612 A-10
i (6) Press < Enter >.
(7) Press < Enter > 'again to save the changes. You will be taken back to the DOS prompt.
(8) Type MENU and press < Enter > to view your new menu.
2.0 START USING RVID This section describes the RVID and some of its menu options; also, it gives a brief summary of the options in the Main Menu. NOTE:. After installing the RVID, a reindex and pack must be executed before accessing the data and information files (see Section 6.0, Reindex & Pack for instructions). This step is not necessary for subsequent use of the RVID.
2.1 - Startine the Database Perform one of the two actions listed below, as appropriate, to access the RVID:
(1) To start RVID in DOS, type RVIDPUB and press < Enter >, or (2) To start RVID in Windows, select the RVID icon.
i The Main Menu will appear as shown in Figure 1.
l l System Reports Files Applications About l Hgure 1. Main Menu i
2.2 Selecting Main Menu Options
'Ihe following procedures work the same way in every screen of RVID. If you are using a mouse, select a menu by doing the following:
Point and click on the desired menu or menu option.
If you do not have a mouse, select a menu or menu option in the following way:
Press Alt once to highlight the desired system menu.
Press key corresponding to the bold letter in the desired menu option to display the options in next menu desired. For example, from the Main Menu options, press the R key to access the options for the Reports menu.
Also, you may press arrow keys to display the menu options and to highlight the option you want; then press < Enter > to select the option.
To quit working with the menu:
1 l
A-Il NUREG-1612
Press Alt. All menus will be deactivated. Also, if you are working with a database reco:d and have activated the menu, press Alt again to remove the menu. The cursor will return to its original position on the screen.
You may activate or deactivate menus as often as you wish by pressing Alt. The options available in the Main Menu are shown in Figure 2. The following subsections briefly summarize the Main Menu options shown in Figure 2.
System Reports File Applications About 4
Help Summary..
Import Data Plant Information Exit to DOS Queries Export Data i
Reindex & Pack Preferences Figure 2. Main Menu Options 2.2.1 System Menu Help displays instructions for using all the screens in the database.
Exit to DOS quits RVID and takes you back to the Windows screen or the DOS prompt.
2.2.2 Reports Menu Summary... lets you print three kinds of summary reports (Summary Files): (1) the Summary File for Pressurized Thermal Shock (PTS) or Pressure-Temperature (P-T) Limits, (2) the Summary File for Upper Shelf Energy (USE), and (3) the Summary File for Chemistry Data.
Queries lets you customize the type of information that you want printed in a report.
2.2.3 Applications Menu Plant Information displays background and surveillance capsule information about individual commercial nuclear reactor plants.
Reindex & Pack removes deleted records and reorganizes the database to use disk space more efficiently.
Preferences displays printer selections.
NUREG-1612 A-12
2.2.4 About Menu Dis option displays the following information concerning the RVID: (1) a disclaimer notice and (2) an address for forwarding comments, feedback, and requests for RVID diskettes or hard copies.
i i
3.0 PRINTING REPORTS i
RVID lets you print reports with almost any combination of information on them. Besides being able to print out the Summary Reports for pressurized thermal shock (ITS) or pressure-temperature (P-T) limits, upper shelf energy (USE), and chemistry data, the user may customize the information in the desired printout by querying to the information in the Summary Report. In the event that an error message (red box) is displayed when the printer is selected, highlight " Ignore" to begin printing.
{
3.1 Printine PTS Summary. USE Summarv. and Chemistry Data Reoorts 1
i j;
To print out summary reports:
l l
Select Reports from the Main Menu options.
Select Summary... from the Reports submenu options. RVID will display the Summary Reports Menu as shown in Figure 3.
PTS Summary USE Summary Chemistry Data Figure 3. Summary Reports Menu Select the type of summary report you would like to print out. No matter which type you select, the Report Selection Screen will appear like the example shown in Figure 4 on the next page.
1-From the Select List box at the top of the screen, select all plants that you would like to print information about. The names of all plants you select will appear in the Selected box at the bottom.
l.
If you have a mouse, you may use the scroll bar to the right of the list to find a name you want, point l
and click to highlight it, and click < Move > to add it to the Selected box. Or, you may click < Move All> to add all names at once. Conversely, if you decide to remove some or all of the selections from the Selected box, click < Remove > or < Remove All>.
r If you do not have a mouse, you may highlight a name either by using the arrow keys or by typing the first letter of the plant name.. RVID will display the first occurrence of that letter. Den press j~
< Enter > to add the desired name to the Selected box.
After you have selected all the names of plants you want on the report, select <OK>.
1-A-13 NUREG-1612 4
[
i Select List:
ARKANSAS NUCLEAR 1 ARKANSAS NUCLEAR 2 BEAVER VALLEY 1
< Move >
< Remove >
< Move All>
< Remove All>
Selected:
ARKANSAS NUCLEAR 1
<0K>
< Cancel >
Figure 4. Report Selection Screen Choose either Printer or Screen to send the report to the desired form of output.
3.2 Printine Reoorts from Oueries To print a report with customized information:
Select Reports from the Main Menu options.
Select Queries from the Reports submenu. The Query Subjects Screen will appear as depicted in Figure 5 on the following page. The Query Subjects Screen lets you choose very specific categories for the report.
In the boxes labeled Reactor Type, Material, and Owner's Group, you may choose just one category for each. If you do not select a specific reactor type, material, or owner's group, the report will show all reactor types, materials, and owner's groups. If you want your report to show fewer records, you may choose a specific reactor type, material, and owner's group; the more specific you are, the smaller your report will be.
In the Vessel Fabricator and Vessel Designer boxes, you may select as many vessel fabricators and designers as you wish. The more you select, the more records will appear in your report. Selecting no fabricators from the Vessel Fabricator box is the same as selecting all of the fabricators from the Vessel Fabricator Box. Selection of the vessel designers specified in the Vessel Designer box works the same way. To perform the query:
Select any combination of Reactor Type, Material, and Owner's Group.
NUREG-1612 A-14
1 i
Query Subjects
-Reactor Type-Vessel Fabricator-Base Metal
(*) All Plants
[ ] B&W
( ) PWR
[ ] CE
( ) BWR
[ ] Rotterdam
[ ] CB&I
--Naterial
(*) All Material
( ) Plates
( ) Forgings
-Vessel Designer-( ) Welds
[ ] B&W
[ ] CE Flux Type
-Owner's Group-
[ ] Westinghouse
(*) None
[ ] GE
( ) B&WOG
( ) BWROG
( ) CE00 Next Page
( ) WOG
< Clear Settings >
< Close Query Figure 5. Query Subjects Screen Select as many Vessel Fabricators and Vessel Designers as you would like RVID to search for.
The Base Metal, Heat Wire, and Flux Type boxes on the right side of the screen work in conjunction with the Material box and let you further narrow your search of records so that RVID will print only those plant records that contain the specific base metal, heat wire, or flux type you select. The three boxes are dependent on the type of material you selected in the Material box. You may choose a Base Metal if you selected Plates or Forgings. You may choose a Heat Wire and a Flux Type if you selected Welds. If you selected All Material, it means that you want RVID to accept all types of base metals, heat wires, and flux types, so none of the three boxes will be accessible.
3.2.1 Selecting a Base Metal If you selected Plates or Forgings, follow the instructions below. If you selected Welds, refer to the procedure described in Section 3.2.2, " Selecting a Heat Wire and Flux Type," of this User's Manual.
If you selected All Material, refer to the procedure described in Section 3.2.3, " Enter Query Selection Criteria," of this User's Manual.
Select the Base Metal box. RVID will display a list of base metals (as shown in Figure 6 on the following page). If you do not have a mouse, press < Tab > or the down arrow to move the cursor to the Base Metal box and press < Enter > to display the list.'
l l
- 2. NOTE: If you try to select either the Ifeat Wire or the Flux Type box, RVID will display the following mesange: " selection l
inconsistent with material. Please select Welds;" if the message appears, press any key to remove it. RVID will move your
{
cursor to the top of the Material box.
j l
A-15 NUREG-1612 1
i
A 302 A A 302 B A 302BM A 336 A 508 Figure 6. Example Box l
Select the type of base metal you want RVID to search for. In the Base Metal box, RVID will display the name you selected.' '
l Select < Next Page> to select more options and to print the report RVID will display the Query l
Selection Criteria Screen, which is shown in Figure 7 on the following page. If you do not have a mouse, press < Shift-Tab > or the up arrow to move the cursor to the < Next Page> selection and press < Enter >.
I L
3.2.2 Selecting a Heat Wire and Flux Type l
l If you selected Welds in the Material box, select the Heat Wire or the Flux Type box. RVID will display a list of each that you can choose from. if you do not have a mouse, press < Shift-Tab >
or the up arrow to move the cursor to the Flux Type box and press < Enter >. Then you can move the cursor up to the Heat Wire box and press < Enter >.'
Select a heat wire or a flux type or both, if desired. RVID will display the names you selected in the Heat Wire and Flux Type boxes.
. Select <Next Page> to select more options for your report. RVID will display the Query l
Selection Criteria Screen, which is shown in Figure 7 on the following page. If you do not have a mouse, press < Tab > or the down arrow to move the cursor to the < Next Page> selection and press < Enter >.
L 3.2.3 Entering Query Selection Criteria Select < Next Page> if you have not already done so to display the Query Selection Criteria Screen (as shown in Figure 7 on the following page).
The Query Selection Criteria Screen (as shown in Figure 7 below) shows the names of columns that you l
L.
may print in the report. He first option, Alphabetical, corresponds to the Plant Names column, which
- 3. N(7TE: some base metale correspond only to forgings and some correspond only to platea. If you select a base metal that does not correspond to the type of material you selected in the Material box, RVID will display the following message for about 3 esconds: "This base metal is associated with plates / forgings. settings will now clear." RVID will then display a new Query subjects screen. You will need to select options again and choose a different base metal.
I l
- 4. NOTE: If you try to select the Base Metal box, RVID will display the following message: " selection inconsistent with material.
Please select Plates or Forgings." If the message appears, press any key to remove it. RVID will move your cursor to the top of the Material box.
NUREG-1612 A 16 i
_ _ _ _. ~ _ _ _ _. _ _. _ _. _ _ _ _. _
w31 always be the first column in the report. The second column will always be Plant Identifiers. You may choose additional columns by entering a number (1,2, 3, etc.) next to the names. He numbers you enter determine the order in which the columns will be displayed on the report (after the plant name and plant identifier) and the order in which those columns will be sorted.
For example, if you entered the number I next to % S, the number 2 next to Alphabetical, and the number 3 next to % Ni, RVID would print four columns: Plant Names, Plant Identifiers, Percent Sulfur, and Percent Nickel (in that order), with the Percent Sulfur column sorted first, the Plant Names column sorted second, and the Percent Nickel column sorted third. In other words, because you entered the number 1 next to % S, RVID would display all records in numerical order from the lowest to highest percent sulfur. Also, because you entered the number 2 next to Alphabetical, RVID would display plant names in alphabetical order for each set of records that had the same value for percent sulfur. Percent nickel would then be sorted last, if necessary.
If you do not enter a number to the left of a column name, RVID will not include that column in the report. However, if you do not enter any numbers, RVID will include all columns in the report.
If you enter the same number next to two column names (such as the number i next to both % Cu and
% S), RVID will sort them in the order shown in Figure 7 (percent copper first and then percent sulfur).
Enter numbers to select the order in which the columns you want in the report will be displayed and sorted.
Select < Run Query >.
l Query Subjects
-Reac Query Selection Criteria tal
(*) Al
( ) PW
( ) BW
_ Alphabetical
_ 1/4t Fluence 9 E0L
--N a
_ ID Fluence 9 E0L re
(*) Al
_ % Cu
_ Initial RTndt
( ) P1
_ % Ni
_ RTpts 9 E0L
( ) Fo
_%P
_ Unirradiated USE
( ) We
_%S
_ USE 9 E0L
_ Chemistry Factor
_ % Drop of USE 9 E0L pe
-Owner
_ Margin
_ E0L Date
(*) N
()B
( ).B Run Query
()C
< Prior Page
()W
< Close Query >
Mgure 7. Query Selection Criteria Screen A-17 NUREG-1612
..- - ~ ~..-.-..
To see the report on the screen, press < Enter > ; to print the report, type P and press < Enter >.
RVID will display the message " Executing query..." until the report is ready, if you decided to view the report on the screen, you may use the options'in the Browse menu to find records (see details on the Browse menu).'
Press < Esc > to go back to the Query Selection Criteria Screen.
Select < Prior Page> to select options for another report, if desired.
Select <Close Query > to go back to the Main menu.
4.0 PLANT INFORMATION
'4.1 Viewing Plant Information 4
Plant Information provides basic background information for each plant, and surveillance data based upon information from the Power Reactor Embrittlement Database (PR-EDB), Version 2.
Plant Information also provides the a, and ai values used to calculate the margin.
Plant Information Docket No:
Update Plant Name:
/ /
< Help
< Next >
Ver
< New
< Prior >
Manufacturer:
< Modify >
< Top License No:
E0L Date :
I NSSS Designer:
E0L Years:
< Cancel >
< Bottom >
Thickness Reactor Type :
l L
h
< Locate >
Vessel Radius :
Owner Group 4
Limiting Closure Material Flange Heat Number :
Flange Material Unirr Rtndt :
i Material Type :
References :
Additional Notes Figure 8. Plant Information Screen Select Applications from the Main Menu Options (Figure 2.); then select Plant Information from the Applications menu. RVID will display the Plant Information Screen (as shown in Figure 8 above) for the first record in the file.
NUREG-1612 A 18
View the Plant Information 4.2 Findine a Plant Record On the right-hand side of the Plant Information screen is the Record Search box (as shown in Figure 9 to the right), which
< Next >
helps you fmd the plant record you want to view. The Record
< Prior >
Search Box has the following features:
< Top
< Next> displays the next record in the file (in ascending order according to plant docket numbers).
Bem
< Prior > displays the previous record.
< Locate >
< Top > displays the first record in the file.
Figure 9. Record Search Box
< Bottom > displays the last record.
< Locate > lets you select < Browse > to display the Browse screen, which shows a list of plant records. An example of the Browse screen is shown in Figure 10 (as shown below).
At the top of the Browse screen, you will find the Browse menu, which has several options to help you further search for plant records (see Section 4.3, " Selecting Browse Menu Options," regarding these options). Perform the following steps to display the information for a particular plant record in the Browse Screen:
Highlight any field for the particular record in the Browse Screen (Figure 10.).
System Reports Application Record Browse NI PLANT Pl_docno Pl_name Pl_licen Pl_nsss Pl _r 50-313 ARKANSAS NUCLEAR 1 NPR-51 B&W 09/20 50-368 ARKANSAS NUCLEAR 2 NPF-6 C-E 09/20 50-334 BEAVER VALLEY l DPR-66 WESTINGHOUSE 09/20 50-412 BEAVER VALLEY 2 NPF-72 WESTINGHOUSE 09/20 50-155 BIG ROCK POINT DPR-6 GF 09/20 50-456 BRAIDWOOD 1 NPF-72 WESTINGHOUSE 09/20 50-457 BRAIDWOOD 2 NPF-71 WESTINGHOUSE 09/20 50-259 BROWNS FERRY l DPR-33 GE 09/20 50-260 BROWNS FERRY 2 DPR-52 GE 09/21 50-296 BROWNS FERRY 3 DPR-68 GE 09/21 50-325 BRUNSWICK 1 NPR-71 GE 04/16 50-324 BRUNSWICK 2 NPR-62 GE 04/16 50-454 BYRON 1 NPF-37 WESTINGHOUSE 09/21 50-455 BYRON 2 NPF-66 WESTINGHOUSE 09/21 Figure 10. Browse Screen NUREG-1612 A-19
Press < Esc > or, if using a mouse, click once on the yellow box in the upper left-hand corner close the Browse Screen; then, Select < Quit >. RVID will then display the Plant Information Screen for the particular rec selected.
4.3 Selectine Browse Menu Ootions The Browse menu contains the follwing options:
Change displays the records list in the Browse screen in a different format.
Grid off/on removes / adds the grid lines in the Browse screen.
Size Field lets you make fields (columns) in the Browse screen either wider or narrower. Press
< Tab > and < Shift-Tab > to move the cursor to fields you want to size. Use arrow keys to alter the size of fields. Press < Esc > to quit sizing fields.
Move Field lets you move any field (celumn) to any location in the Browse screen. Press < Tab >
l and < Shift-Tab > to move the cursor te fields you want to move. Use arrow keys to move fields.
Press < Esc > to quit moving fields.
Resize Partitions ica you move the entire Browse screen. Use arrow keys to move the Browse screen. Press < Esc > to quit.
Goto... displays a screen with the following options (press < Tab > to move the cursor from one selection to another):
- Top takes you to the first record in the list.
- Bottom takes you to the last record in the list.
- Record lets you enter the number of the record you want to see. For example, to move to the ninth record in the list, enter 9.
- Skip lets you enter the number of records you want to skip. For example, if you are on the ninth record in the list and want to skip to the twentieth record, enter 11.
- Goto carries out the option you select.
- Cancel takes you back ta the records list without moving your cursor.
4.4 Viewine Foreines. Plates. Welds. and Surveillance _Qata The Application submenu in the Main Menu Options (Refer to Figure 2.) allows the user to access the Plant Information screen, and view further information about a particular plant. You may also view NUREG-1612 A 20
l
\\
f records with forging, plate and weld material data and surveillance data. To view the appropriate data:
Select Plant Information from the Application submenu. The Plant Information Screen will appear (Refer to Figure 8.) for the first record in the file.
- - Find the plant record that you want to work with by doing the following steps.
- - Select < Locate >.
- Select < Browse > to display records.
- Find the record you want to view or modify, and highlight any field in the record.
- Press the < Esc > key.
- Select < Quit >. RVID will take you back to the Plant Information Screen and display the plant information for the specific record you highlighted.
1 l
Select either Forgings, Plates, Welds, or Surveillances from the Application submenu. RVID will display the screen with appropriate type of information for the plant you selected.
After viewing the type of data desired, select < Close> to get back to the Plant Information Screen.
5.0 USING HELP OPTIONS The System submenu contains an option called Help Topics, which displays information concerning every aspect of the database.
Select Help Topics from the System submenu.
With the Help Topics screen, you may locate and view information.
Locate Help Topics l
Scroll up and down to look for the subject desired. Click on the desired topic for detailed l
information.
6.0 REINDEX & PACK j
The Reindex & Pack feature was included in RVID to let the NRC staff delete records and organize the remaining records to more efficiently use the disk space in the computer. In other words, it reorganizes the data to make data files smaller, so they do not take up so much space on the hard drive.
To reindex and pack the database:
Make sure you are at the Main menu.
l A-21 NUREG-1612
F 1:
I s
Select Reindex & Pack from the Applications menu. RVID will display the Reindex & Pack screen as shown in Figure 11.
Removal of deleted records and file l
reindex will take approximately 2 l
minutes.
Do you wish to continue?
I YES N0 i
t r
Figure 11. Reindex & Pack screen.
- Press < Enter > to select YES.
RVID will delete all records in the database that have been marked for deletion. His means that when you were working with plant information records or code records, you should have selected Toggle Delete from the Record menu for each record you wanted to delete. Hat way, those records were marked for deletion, and would be deleted only after you select Reindex & Pack.
After RVID deletes marked records, it eliminates the excess space between remaining records and makes your database run faster. The Reindex & Pack process will take approximately 2 minutes to complete.
7.0 SE'ITING PREFERENCES The Preferences option allows printer selection.
Printer Settings:
- For the Default Printer, select LOCAL for LPTl or REMOTE for LPT2.
P
. For the Printer Type, the < L> key for a laserjet printer or the <M> key for a dot matrix printer.
8.0 BACKGROUND
AND SOURCE DOCUMENTS In addition to the licensee responses to GL 9241, the following documents were included in the review process and development of the RVID:
)
surveillance capsule reports j
- documents referenced in GL 92-01 NUREG-1612 A-22 i
~
PTS and P-T limits submittals (as applicable)'
responses to the staff's requests for additional information (as applicable) a ne plant summary reports were derived from the staff review of these documents. The staff requested that licensees confirm the applicability of the unirradiated properties, neutron fluence, a
'hemical composition data that provide the basis for the plant summaries. The majority' of liceh.,oes have confirmed that these data are applicable to their plants. Data regarding decommissioned plants has not been included in the RVID.
The source for surveillance data was the Power Reactor Embrittlement Database (PR-EDB),
l-Version 2, with the following exceptions:
Surveillance capsule reports for the following plants were added:
- Cooper, GE-NE-523-159-1292
- Diablo Canyon, WCAP-l'2811
- McGuire 2, WCAP-13516
- Millstone 1, GE-NE-523165-1292
- Calvert Cliffs 1, BAW-1260 De PR-EDB is a comprehensive collection of data from surveillance reports and other published reports on commercial nuclear reactors. However, not all of the data have been verified by reactor vendors, and the capsule data were not evaluated according to credibility criteria. Surveillance data for the following plants were excluded from the RVID Surveillance Files because credibility could not be established:
Haddam Neck, Capsule A/BMI-1070, not credible for welds Quad Cities 1, not credible for welds Turkey Point 3 and 4, not credible for weld 71249 Surveillance data will be reviewed by NRC staff according to credibilitycriteria of the revised rule (10 CFR 50.61) or Regulatory Guide (RG) 1.99, Revision 2, and incorporated into a future version of the RVID.
l The RVID performs logarithmic calculations on the difference between the measured and unirradiated USE. In the event that the measured USE is equal to or greater than the unirradiated USE, the RVID cannot perform the calculation and, therefore, disregards the surveillance data for that capsule and material. In one case, the surveillance data were adjusted to accommodate this programming logic:
Robinson 2, Capsule V, intermediate shell W10201-5, the unirradiated USE was changed from 100 to 101 ft-lb. This programming issue will be reviewed and addressed in a future version of the RVID.
The database can contain information that is not docketed (i.e., results of calculated procedures that use docketed information). Source documentation and notes for each plant can be found in the References section.
Data in the RVID for the Palisades RPV are current through April 12, 1995. The data in the RVID for all other plants are current through December 31,1994. Surveillance data, with the exception noted, j
are current with the data contained in the PR-EDB, Version 2.
6 j
f A 23 NUREG-1612
9.0 EXPORTING OUERIES TO A SPREADSIIEET 5
The user may export a query to a spreadsheet (i.e., software such as Lotus, QuattroPro', etc.) by following the directions for tha: particular software to import the file WRKQUERY.DBF from the C:\\RVID subdirectory. This may be done only with the last RVID query that the user has selected. To export another query, the user must return to the RVID, run the query, return to the spreadsheet, and repeat the process.
10.0 NOMENCLATURE: USE. PTS. AND CIIEMISTRY DATA
SUMMARY
REPORTS This section explains the column headings and nomenclature used in the format of the USE, PTS, and Chemistry Data Summary Reports. Instructions for accessing these reports can be found in this Appendix under Section 3.0, " Printing Reports." There is a corresponding USE, PTS /P-T Limits, and Chemistry Summary Report for each plant. The summary reports are presented as tables; each beltline material is identified in one column, and various information categories are identified in other columns.
10.1 Summary File for PTS /P-T Limits Each BWR has a P-T limits table; each PWR has a PTS table. Information headings for these tables are as follows:
Column 1: Plant Name contains the name of the plant, date of expiration oflicense (EOL), and docket number.
Column 2: Beltline Identification provides the plant-specific beltline material identification, which generally consists of a component description, location, and number.
i Column 3: Ileat Identification Number identifies the heat number of the beltline material. The following items represent possible suffixes that may be used in conjunction with or in lieu of the Heat Number Identifications for RPV beltline materials:
(S) - when this suffix is used after a heat number for a spec.fied beltline weld material, the suffix indicates that a single wire was used in the single an welding (SAW) process.
(T) - when this suffix is used after a heat number for a specified beltline weld material, the suffix indicates that a tandem wire was used in the SAW process.
NA/W-A - when this suffix is usedi.4ieu of a heat number the suffix indicates that a corresponding heat number was not available for the plant specific beltline weld material specified in Column 2 of the Summary File. In the event that more than one weld did not have an available heat number for a given plant, these would be identified as NA/W-B, NA/W-C, etc.
- 5. Lotus is a trademark of the Lotus Corporation.
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- 6. QuattroPro is a trademark of Novell. Inc.
l NUREG-1612 A-24 l
NA/PL-A - when this suffix is used in lieu of a heat number, the suffix indicates that a corresponding heat number was not available for the plant specific beltline plate material specified in Column 2 of the Summary File. In the event that more than one plate did not have an available heat number for a given plant, these would be identified as NA/PL-B, NA/PL-C, etc.
NA/F-A - when this' suffix is used in lieu of a heat number, the suffix indicates that a l
corresponding heat number was not available for the plant-specific beltline forging material specified in Column 2 of the Summary File. In the event that more than one forging did not have an available heat number for a given plant, these would be identified as NA/F-B, NA/F-C, etc.
l Column 4: RTm o EOL provides the reference temperature as adjusted for the effects of neutron irradiation at the EOL. This adjusted reference value temperature is equivalent to the sum of the initial RTm value, margin value, and ART, value at EOL.
Column 5: ID Neutron Fluence @ EOL is the neutron fluence value at the inner diameter (ID) of the i
reactor vessel at EOL. This value is either cited directly or calculated by applying the neutron fluence of the one-quarter thickness (1/4T) location, as reported in the licensee's l
most recent submittal for the beltline material, to the neutron fluence attenuation equation l
in Regulatory Guide (RG) 1.99, Revision 2. All entries are given in units of 10 n/cm.
2 Column 6: IRTm is the initial RTm of the unirradiated material as defined in ASME Code Section l
III, paragraph NB-2331, or from alternative methodologies, in accordance with Branch Technical Position MTEB 5-2 in Standard Review Plan Section 5.3.2 (NUREG-0800).
I Column 7: Method of Determining IRT, is the method of determining the initial reference temperature. The following methods provide the possible inputs to this column:
B&W Generic indicates the initial reference temperature is the generic value for all Linde 80 welds fabricated by Babcock and Wilcox, excluding material heat number 72105, i
l Generic indicates that the initial reference temperature is the generic value for Linde 0091, Linde 1092, Linde 124, and ARCOS B-5 welds fabricated by Combustion Engineering.
MTEB 5-2 indicates that the initial reference temperature is a value determined using the methodology in Branch Technical Position MTEB 5-2 in Standard Review Plan Section 5.3.2.
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l NRC Generic indicates that the initial reference temperature is a bounding generic value for heat number 72105 welds fabricated by Babcock & Wilcox.
Plant Specific indicates that the initial reference temperature value was determined from tests on material removed from the same material heat as was the identified beltline
- material, i
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Column 8: ART, O EOL is the mean value of the adjustment in reference temperature caused by irradiation. ARTutrr is calculated in accordance with the PTS rule as follows: ARTm =
(CF)*fa28. aim n, where CF is the chemistry factor and f (in units of 10E19 n/cm ) is the 2
l neutron fluence of the beltline material projected at EOL.
l Column 9: Fluence Factor O EOL is calculated as follows: fluence factor at EOL = fe23. aim o l
where f (in units of 10E19 n/cm ) is the neutron fluence of the beltline material projected 2
at EOL.
Column 10: Chemistry Factor is the chemistry factor for irradiated reference temperature evaluation.
Column 11: Method of Determining CF is the method of determining the chemistry factor. The following methods provide the possible inputs to this column:
Table indicates that the chemistry factor was determined using the best-estimate chemistry values (copper and nickel) and the tables in RG 1.99, Revision 2.
l Calculated indicates that the chemistry factor was determined using the plant-specific L
surveillance data.
Override indicates that the chemistry factor was determined using a methodology approved by the NRC.
Column 12: Margin is a numerical quantity added to cover uncertainties in the values of initial RTm, copper and nickel measurements, fluence, and the calculational procedures involved in i
determining RTm. The margin is calculated according to the methodology of RG 1.99, j
Revision 2. According to the RG, the Margin = 2*(a,2 +,,2)as, u Column 13: Method of Determining Margin is the method of determining the margin value. The following methods provide the possible inputs to this column:
Table indicates that the margin term was calculated using a standard deviation for the increase in reference temperature of 15.6 "C (28 *F) for welds and 9.4 *C (17 *F) for base metal.
Sury. Capsule indicates that the margin term was calculated using a standard deviation for l
the increase in reference temperature of 7.8 *C (14 *F) for welds and 4.7 *C (8.5 *F) for base metal.
Column 14:
l Cu% provides the copper content, cited directly from the licensee's value, except when i
more than one value was reported (in which case the staff used the average value).
- 7. Here o is the standard deviation for the initial RTm. If a measured value of initial RTm for the material in question is s
available, ei s to be estimated from the precision of the test method. If not, and generic mean values for that class of material i
are used, a is the standard deviation obtained from the set of data used to establish the mean.
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- 8. The standard deviation for ARTm, o, is 15.6*C (28'F) for welds and 9.4'C (17'F) for base metal, except that a, need not exceed 0.50 times the mean value of ARTm. If two or more sets of credible surveillance data are available and are used to establish the ARTm, the vejuca for o, may be cut in half.
NUREG-1612 A-26 l
l
Column 15: Ni% provides the nickel content, cited directly from the licensee's value, except when more than one value was reported (in which case the staff used the average value).
He following represent colunms in the Summary File for PTS /P-T Limits whose numerical or text values are entered directly from a source document:
Column 1: Plant Name Column 2: Beltline Identification Column 3: Heat No. Identification Column 5: ID Neutron Fluence @ EOL Column 6: IRT, Column 7: Method of Determining IRTm Column 9: Chemistry Factor, in the case of an Override Column 11: Method of Determining Chemistry Factor Column 12: Margin-inputs of ai and a, Column 13: Method of Determining Margin Column 14: Cu% (the average value is listed if more than one value is reported)
Column 15:- Ni% (the average value is listed if more than one value is reported).
The following represent columns in the Summary File for PTS /P-T Limits whose numerical data have been obtained by using the calculational methodology of RG 1.99, Revision 2:
Column 4: RTm @ EOL Column 8: ARTm @ EOL Column 9: Fluence Factor @ EOL Column 10: Chemistry Factor Column 12: Margin-calculated from the inputs of a, and a,.
10.2 Summary File for Uoner-Shelf Energy (USE)
Information headings for the USE Summary Tables include:
Column 1: Plant Name contains the name of the plant, date of EOL, and docket number.
A-27 NUREG-1612 l
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Column 2: Beltline Identification provides the plant-specific beltline material identification, which generally consists of a component description, location, and number.
Column 3: Heat Number Identification identifies the heat number of the beltline material. A numb of suffixes may accompany or be used in lieu of the heat number identifications in this l
column. Refer to the appropriate Heat Number Identification suffixes described under the informational heading for Column 3 in Section 10.1 of this Appendix.
Column 4: Material Type provides the material type for each plate, forging or weld.
Column 5: USE O EOL 01/4 T is the calculated upper-shelf energy value (in ft-lb) at EOL as determined for the one-quarter thickness location of the RPV.
Column 6: 1/4 T Neutron Fluence O EOL is the neutron fluence value at EOL for one-quarter thickness location of the RPV. This value is either cited directly or calculated by applying the ID neutron fluence, as reported in the licensee's most recent submittal for the beltline i
material, to the neutron fluence attenuation equation in RG 1.99, Revision 2. All entries j
are given in units of 105 n/cm.
2 Column 7: Unirradiated USE is the unirradiated upper-shelf energy in units of ft-lb.
l-Column 8: Method of Determining Unirradiated USE describes the method of determining the unirradiated upper-shelf energy. The following methods provide the possible inputs to this column:
Direct-for plates, this indicates that the unirradiated USE was determined from Charpy-V I
tests on transverse test specimens. For welds, this indicates that the unirradiated USE was determined from Charpy-V test data, t
i 65 % indicates that the unirradiated USE was calculated in accordance with Section 1.2 of Branch Technical Position MTEB 5-2, " Fracture Toughness Requirments" at 65 % of the l
USE value obtained from Charpy-V tests on longitudinal test specimens.
Generic indicates that the unirradiated USE was reported by the licensee from USE data of other plants with similar materials to the beltline material.
NRC Generic indicates that the unirradiated USE was derived by the staff from the USE data of other plants with similar materials to the beltline weld.
10,30,40 or 50 *F indicates that the unitradiated USE was derived from Charpy-V tests conducted at 10, 30,40 or 50 *F.
Sury Weld indicates that the unitradiated USE was from the surveillance weld having the same weld wire heat number.
Sister Plant indicates that the unirradiated USE was derived by using the reported value from other plant (s) with the same weld wire heat number.
l 4
NUREG-1612 A-28 i
EMA indicates that an unirradiated USE is unnecessary because the licensee has used an equivalent margins analysis (EMA) to satisfy the USE requirements of Appendix G to Part 50 of Title 10, Code ofFederal Regulations (10 CFR Part 50, Appendix G).
Column 9: % Drop UST @ EOL @ 1/4T describes the percentage drop in USE from the initial unitradiated value to the value projected to occur at EOL as a result of radiation embrittlement.
Column 10: Method Determ % Drop describes the method of determining the percentage drop in USE.
The following methods provide the possible inputs to this column:
Position 1 of RG 1.99, Rev. 2 indicates that the percentage drop in USE was determined using the percentage copper and the methodology in Position 1 of RG 1.99, Revision 2.
Surveillance Data indicates that the percentage drop in USE was determined using surveillance data and the methodology in Position 2 of RG 1.99, Revision 2.
EMA indicam that the percentage drop in USE is unnecessary because the licensee has used an equi,Jent margins analysis to satisfy the USE requirements of 10 CFR Part 50, Appendix G.
Column 11: Cu% provides the copper content, cited directly from the licensee's report, except that when more than one value was reported, the staff used the average of the reported values.
The following represent columns in the Summary File for USE whose numerical or text values are entered directly from a source document:
Column 1: Plant Name Column 2: Beltline Identification Celunm 3: Heat No. Identification Column 4: Material Type Column 7: Unitradiated USE Column 8: Method of Determining USE Column 10: Method of Determining % Drop Column 11: Cu% (the average value is cited if more than one value is reported)
The following represent columns in the Sumraary File for USE whose numerical data have been obtained by using the calculational methodology of RG 1.99, Revision 2:
l Column 5: USE @ EOL @ 1/4T Column 6: 1/4T Neutron Fluence @ EOL A-29 NUREG-1612
1 Column 9: % Drop @ EOL @ 1/4T i
l 10.3 Summary File for Chemistry Data Informc: ion headings for the Chemistry Summary Tables include:
Column 1: Plant Name contains the name of the plant, date of EOL, and docket number.
Column 2: Beltline Identification contains the plant-specific beltline material identification, which generally consists of a component description, location, and number.
Column 3: Heat No. Ident. indicates the beltline material heat number.
Column 4: %Cu provides the copper content, cited directly from the licensee's report, except that when more than one value was reported, the staff used the average of the reported values.
Column 9: %Ni provides the nickel content, cited directly from the licensee's report, except that when more than one value was reported, the staff used the average of the reported values.
Column 14: %P provides the phosphorous content, cited directly from the licensee's report, except that when more than one value was reported, the staff used the average of the reported values.
Column 15: %S provides the sulfur content, cited directly from the licensee's report, except that when more than one value was reported, the staff used the average of the reported values.
All other columns are blank at this time, for all plants,
11.0 REFERENCES
'Ihe Reference Section lists references of source documents and notes for each plant, and appears at the end of each Summary File.
'12.0 COMMENTS AND FEEDBACK Although every effort has been made to ensure that the information contained in the RVID is accurate, information and data obtained from the RVID are not considered official. Every user explicitly acknowledges that all information obtained from the RVID is provided "as is" without warranty of any kind, either expressed or implied, including, but not limited to, the implied warranties of merchantability and suitability for a particular purpose, and that the entire risk of acting on information obtained from the RVID, including the entire cost of all necessary remedies, is with those who choose to act on such information and not with the operators of the RVID.
Efforts have also been made to ensure that the RVID is " user-friendly" and that the programming logic is accurate. Comments and feedback regarding all aspects _of the RVID and suggestions for futuro versions are encouraged and may be sent to:
NUREG-1612 A-30
RVID Project Manager U.S. Nuclear Regulatory Commission Mailstop O-7D4 Washington, DC 20555 - 0001
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A-31 NUREG-1612
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INDEX About menu A-13 Plant Records........... A A-21 All Material A-15 Plates
........ A-15, A-16 Applications menu A-12 Preferences.............. A-12, A-22 Base Metal.............. A-15, A-16 Printer Settings............... A-22 Botwm................. A-19, A-20 Printer Type................. A-22 Browse............... A A-21 Pr io r...................... A-19 Browse menu............. A-19, A-20 Prior Page A-18 Browse screen............ A-19, A-20 Program Item
................A-10 Cancel..................... A-20 PTS Summary... A-13, A-24, A A-30 Change A-20 Queries........... A-12, A A-18 Chemistry Data
...... A-13, A-24, A-30 Query Selection Criteria
... A A-18 Close Query..............
A-18 Query Subjects.......
.. A-14, A-15 Default Printer................ A-22 Quit
............... A -20, A-21 Exit to DOS................. A-12 Reactor Type................. A-14 Exporting Data (Queries)
A-24 Record, goto...
.. A-20 Fil e menu................... A-12 Reindex & Pack
...... A-12, A-21, A-22 Flux Type............... A-15, A-16 Remove............... A-13, A-14 Forgings................ A-15, A-16 Remove All............. A-13, A-14 Goto............
A-20 records:
Goto...
A-20 finding..........
A-19, A-21 Grid off/on..........
A-20 d el eting................... A-22 Heat Wire............... A-15, A-16 plant
............ A A-21 H elp.................. A-12, A-21 reports:
Locate................. A-19, A-21 Chemistry Dat.'...... A-13, A-24, A-30 Main Menu.............. A-11, A-12 PTS Summary A-12, A-24, A A-30 Main Menu Options........ A-11, A-12 query........... A-12, A A-18 Material............... A A-16 USE Summary..... A-13, A A-27 menu:
Reports menu
................A-12 Abou t.................... A-13 Resize Partitions............... A-20 Applications.........
A-12 Run Query.................. A-17 F il e,...............
A-12 Select List Box............ A-13, A-14 Reports..................
A-12 Selected Box.
....... A-13, A-14 System..........
A-12 Size Field
... A-20 menu options:
Skip A-20 main menu.........
A-11, A 12 Summary....
... A-13, A A-30 select................ A-II, A-12 Surveillance
. A-20, A-21 Move A-13, A-14 System menu.......
A-12 Move All..............
A-13, A-14 Toggle Delete A-22 Move Field.........
A-20 Top................... A-19, A-20 New...................... A-10 USE Summary....... A-13, A A-27 N ext....................
A-19 Vessel Designer........... A-13, A-14 Next Page.....
A-16 Vessel Fabricator.......... A-13, A-14 Owner's Group A-14 Wel d s................. A-15, A 16 Plant Information..... A-12, A A-21 NUREG-1612 A 32
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C 06/24/9F 11:A4 31 REACTOR WEsSEL INitGRit? DATAAAM Chenf etry Data file Staneery Pager 2
tote method of tense of Average Date Nethod of targe of Average Ptent Set tline -
uset me source for Determin.
Cu veture vetue ef source for Determin.
el veture value ef meme Ident.
Ident.
1 Cu Cu Cu Cu 1 El ut si si 1P 1S References far Artensee Bucteer 1 (centframd)
N Chantetry Facter ter W-112 eseid wee calculated fras Oconee 1, Point Beech 2, 34uuE Ree. 1.
These survelttence eselde were fabricated with the same heet caster es W-1$2ANO-1, and Ranche Sece survelttance date that use reported in BAlf-1803, Itindt, for neute belt forging te a mean vetue from 24 fortnpa eletter to AYE 131.
The date le reported in 94W-10064P eruf hee a standard devoletten of 31er.
Fluence data report in SAW-2222.
tAf5E for plet*e CS129-2, C5114-2, C5120-1 and C 5114-1 reported in OAu-2222.
lAfSE for fort ATE 131 mes 95/95 teterance timit that esos reported in saw-2222.
Table B-6, Sample RVID Summary File for Chemistry Data (Continued) z C
b Q
l E
U
N;;C Pomu 33s U.S. NUCLEAR REQULATORY COMMisslON
- 1. REPORT NUMBER Ebe2' WClL"oh'#,.'h7 ""'
no'. noa BIBLIOGRAPHIC DATA SHEET iswurnscrw oi, rne nsru) n99gg_353g
- 2. TITLE AND SusitTLE Status Report: Reactor Vessel Integrity fbtabase jE REP Rms$5sEo 3.
July 1997
- 6. TYPE OF REPORT C.J. Fairbanks, A.D. Lee, J. N doff Technical J.R. Strosnider, K.R. Wichnan, B.J. Elliot
- 7. PE RIOD COV E R E O rinciume Datest
- s. PE RFORMING ORGANIZATSON - N AME AND ADDRESS ter Nnc. orove omnoon. orrace or nepen. v.s Nuenese nogenerary commossoon, and meanne sodreu. oo contractor. orose name sad memne andress}
Division of Engineering Office of Nuclear Reactor Regulation U.S. Nxlear Regulatory Coimission W shington, D.C. 20555-0001 e SPONSORING ORG ANtZATlON - N AM E AND ADOR ESS tir unc. troe seme a eso.e, to contractor. oro, eor Nnc cov.uon. orrare or neeson. ys nuenner neouserorv commmoon, auf maitane ed**eri Same as atove
- 10. SUPPLEME NT ARY NOTES R A85 TRACT The U.S. Nuclear Regulatory Commission (NRC) developed the Reactor Vesselintegrity Database (RVID) following the staff's review of licensee responses to Generic Letter (GL) 92-01, Revision 1 (Ref.1). The database summarizes the properties of the reactor pressure vessel (RPV) beltline materials for each operating commercial nuclear power plant.
The RVID contairs four tables for each plant: (1) background information table, (2) chemistry data table, (3) upper-shelf energy table, and (4) pressure-temperature limits or pressurized thermal shock table. References and notes follow each table documenting the source (s) of data and presenting supplemental information.
Additiona#y, the RVID has ' sort
- and " data search' capabilities. The user can select a desired grouping of plants and then specify information categories to search and list.
The design of the RVID consolidates the industry's RPV data in a corwenient and accessible manner. Some of the data categories contain data inputs of ' docketed' information; other data categories contain computed numerical values, which may or may not be ' docketed *. The programmeng logic used for calculations in the RVID follows the methodology in Regulatory Guide (RG) 1.99, Revision 2 (Ref. 2).
For the Polisades RPV, the data and information contained in the RVID, Version 1.1, are current through April 12, 1995; the data and information for the RPVs of av other operating commercial nuclear poww plants are current through December 31,1994 The staff win opdate the RVID periodically to reflect the latest informatior, available.
Information contained in the industry's responses to the closeout letters to GL 92 01, Revision 1, and in the industry's responses to GL 92 01 Revision 1, Supplement 1 (Ref. 3), are not necessarily reflected in this version, but will appear in a future version of the RVID.
12 KE Y WOROS/DESCRiPTORS fuse wants oro reses raes e m essest resesseners an sacersae ene neoort n
e i3. AvAiLAaiui y sI AT EwtNI thlimited Reac?or Vessel Integrity Database, RVID, Pressurized Thenrel Shock, Upper-Shelf Energy, ' " " " " ' " " * " * "
- Radiation Embrittlement, Reactor Pressure Vessel, Pressure-Taperature Limits, Generic Letter 92-01, Revision 1, NJREG-1511, Equivalent Nrgins Analysis, thclassified Reactor Vessel Beltline Nterials thclassified
- 15. NUMBhR OF PAGES
- 16. PRICE hAC PoRM 2351249) v
Printed
- on recycled paper Federal Recycling Program
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