ML20069L885
| ML20069L885 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0390, NUREG-0390-V08-N01, NUREG-390, NUREG-390-V8-N1, NUDOCS 9406200334 | |
| Download: ML20069L885 (30) | |
Text
- -
N U R EG-0390 Vol. 8, No. I i
-2 Tooica.Recor: Review S~:atus 4
U.S. Nuclear Regulatory Commission Office of Nuclear f(cactor Regulation ga an c,
o h
O
- I, E
e~'
9406200334 940531 PDR NUREG 0390 R PDR
. - -.... _.. -. _ - - ~ - ~ _ _ - ~ ~ _
4 4
t AVAILA0lLITY NOTICE l
Avadabihty of Reference Materials Cited in NRC Publications 4
Mcst documents cited in NRC pubhcations will be avadable from one of the fo!!owing sources; l
1.
The NRC Pubhc Document Room 2120 L Street, NW., Lower Level, Washington, DC 20555-0001
?
The Suponntendant of Documents, U.S. Government Pnnting Office, Mail Stop SSCP, Wash ng*on, DC 20402-932.8 3
The National lechnical Information Service, Spnngfield, VA 22161 Although the hsting that follows represents the majority of documents cited in NRC pubhca-l tions, it is not intended to be evhaustive.
Rderonced documents avadabte for inspection and copying for a fee from the NRC Pub!ic Document Room include NRC cortespondence and internal NRC memoranda; NRC buketint circu!ars, information notices, inspection and investigation notices; licensee event reports; vendor recorts and corresponconce; Commission papers; and opphcant and licensee docu-ments and correspondence.
The f ahomog documents in the NUREG senes are avadable for purchase from the GPO Sales j
Program: f ormal NRC stuff and contractor reports, NRC-sponsored conference proceedings internationM agreement reports, grant pubhcations, and NRC booklets and brochures. Also i
avaiiable are regu!atory guides, NRC regulations in the Code of Federal Regulations, and Na-clear Regulatory Commission Issuances.
Documents avadable from the National Technical Information Service include NUREG-senes l
reports and techn. cal reports prepared by other Federal agencies and reports prepared by the
{
Atomic Energy Commission, forerunner agency to the Nuclear Regufatory Comm scion.
Documents available from pubhc and special technical hbraries include a!I open hterature 7
itens, sut,h cs bookt journa! articles, and transactions, Fecoral Register notices, Federal and State leg:s!at:on, and congress onal reports can usually be obtained from these hbranes.
Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-ferenco proceed;ngs are avanable for purchase from the organization sponsoring the pubhca-t tion cited.
Single comes of NRC draf t reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U S. Nuclear f
Regulatory Comm#ssion, Washington, DC 20555-0001, j
Cocies of :ndustry codes and standards used in a substantive manner in the NRC regulatory l
process are maintained at the NRC Library,7920 Norfolk Avenue, Bethesda, Maryland, f u, use by the pubitc. Codes and standards are usually copyrighted and may be purchased from the 3
ong:nating organization or, if they are American National Standards, from the American N3-1:ana: Standards Institute,1430 Broadway, New York, NY 10018,
!I
NUREG-0390 Vol. 8, No.1 Toaical Report Review Status Manuscript Completed: May 1994 Date Published: May 1994 Program Management, Policy Development, and Analysis Staff OITice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
,p.u9 s..... d'
ABSTRACT This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) will process and respond to topical report submissions, and an accounting of all topical reports currently being reviewed by the NRC staff.
This report will be published semiannually, and each sponsoring organization with one or more topical reports under review will receive copies.
iii
CONTENTS A B S T RA C T.................................................................. i i i NUCLEAR REGULATORY COMMISSION LICENSING TOPICAL REPORT PROGRAM..............
1 LICENSING TOPICAL REPORT PROGRAM MANAGEMENT................................. 1 PROCEDURE FOR SUBMITTING LICENSING TOPICAL REP 0RT...........................
1 Submittal of Report for Review........................................
1 Submittal s Af ter Report Has Been Accepted for Review..................1 FORMAT OF LICENSING TOPICAL REP 0RT..........................................
2 Report Identifier.....................
........................ 2 Abstract..............
............................................... 2 Introduction..........................
........................ 2 Body of Report.................
..................................... 3 References................................
........................... 3 CRITERIA FOR ACCEPTING NEW LICENSING TOPICAL REPORTS FOR REVIEW............. 3 HANDLING OF PROPRIETARY REP 0RTS.............................................
4 CORRESPONDENCE FROM SPONSORING ORGANIZATION PERTAINING TO REPORT............ 5 STAFF REQUESTS FOR ADDITIONAL INFORMATION DURING REVIEW CYCLE...............
5 TRANSMITTAL OF STAFF EVALUATION OF REP 0RT...................................
5 PUBLICATION OF APPROVED VERSION OF REP 0RT...................................
5 PLACEMENT OF REPORT AND ASSOCIATED DOCUMENTS IN PUBLIC DOCUMENT R00M........
5 REVISIONS TO REP 0RT.........................................................
5 WITHDRAWAL OF REP0RT........................................................ 6 APPENDIX....................................
............................... 7 LICENSING TOPICAL REPORTS UNDER REVIEW BY THE NRC STAFF....................................................... 8 LIST OF VENDORS.............
........................................ 22 1
V
TOPICAL REPORT REVIEW STATUS NUCLEAR REGULATORY COMMISSION LICENSING TOPICAL REPORT PROGRAM Under the Nuclear Regulatory Commission (NRC) licensing topical report program, industry organizations may, on their own volition or at the request of the NRC staff, submit reports on specific safety-related subjects to the NRC and have them reviewed independently of any construction permit or operating license review. The purpose of this program is to minimize time and effort required of j
both industry and the NRC on subjects repeated in numerous licensing actions.
It provides for a single review and approval with subsequent referencing, rather that repetitive reviews of the same subject.
The reports already under review are given in the appendix.
LICENSING TOPICAL REPORT PROGRAM MANAGEMENT A topical report program manager (PM) has been assigned to manage and coordinate the overall program.
Each review branch with responsibility for the detailed technical review of a specific report will assign review specialists who will report to their own management on the detailed technical review matters.
PROCEDURE FOR SUBMITTING LICENSING TOPICAL REPORT Submittal of Report for Review A report (and requisite number of copies, as discussed below) submitted under the NRC licensing topical report program must be accompanied by a letter of transmittal.
The first paragraph of this letter must include a statement that the applicant is submitting a licensing topical report under the NRC licensing topical report program for review and acceptance for referencing in licensing actions.
This paragraph must specify the report identifier, title, and issue date. The transmittal letter and report should be addressed to the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; Document Control Desk; ATTN:
Chief, Planning, Program and Management Support Branch. If a report is not sent to this address, there is no assurance that it will be entered into the agency's workload information and scheduling program database for tracking.
The transmittal letter should also include any pertinent information about the timeframe of the review and first referencing action.
All correspondence with the NRC concerning licensing topical reports or special reports should include the report identifier specified by the submitting organization in the upper right-hand corner of the transmittal letter.
Submittals After Reoort Has Been Accepted for Review Licensing topical reports accepted for review must be submitted in hard copy in the following quantities.
Additional copies will be provided to the NRC staff upon request.
I d
Report Classification Hard Copy Nonproprietary reports 23 Proprietary reports Proprietary version 23 Nonproprietary version 12 These quantity requirements pertain to all review submittals including initial submittals, revisions, supplements, responses to requests for additional information, and NRC-approved versions.
FORMAT OF LICENSING TOPICAL REPORT Report Identifier Each licensing topical report should have a unique alphanumeric identifier for filing and reference purposes that is assigned to it by the submitting organization.
The report identifier should be typed in the upper right-hand corner of the first page or cover page of all documents relating to the report.
Each organization submitting licensing topical reports should consult with the NRC topical report PM to ensure that the identifier it selects does not conflict with that of another organization and to receive an NRC technical assistance control (TAC) number.
The identifier for all proprietary reports should have
" P" or "(P)" at the end.
Each nonproprietary version of a proprietary report should have the same identifier as the corresponding proprietary report except that "-NP" or "(NP)" should be included at the end.
NRC-approved versions of topical reports should have
"-A" after the identifier
("-P-A" for approved proprietary reports).
The initial submittal and all responses to NRC comments or requests for additional information regarding a specific licensing topical report should be identified by both the NRC TAC number and the submitting organization's identifier for that report followed by " Response to Comment," " Response to Request for Additional Information by the NRC Staff" or, if appropriate,
" Response by Appendix or Supplement to the Original Report."
The use of an addendum is discouraged.
It is possible that only a revision to the original report can constitute a response. This is acceptable when appropriate. However, each revision will entail a new review with the old review closed out.
Abstract The report must include an abstract no longer than one page that summarizes the contents of the report and the conclusions reached.
Introduction The report should have an introductory section that gives the purpose of the report and clearly defines its scope and applicability.
Any limitations or restrictions on the use of the report or its results or conclusions as determined by either the staff or the sponsoring organization should also be listed in this section.
2
Body of Renort l
The body of the report may be organized at the discretion of the sponsoring organization to suit its needs and the subject matter of the report.
It is recommended that long tabulations of data such as test results, computer program descriptions, detailed technical analyses, or derivations be included as appendices.
References The report should include a list of all pertinent references.
CRITERIA FOR ACCEPTING NEW LICENSING TOPICAL REPORTS FOR REVIEW The topical report PM will screen reports submitted for review under the licensing topical program in accordance with the following criteria.
No new report submitted by any organization will be accepted as a licensing topical report unless the PM, in conjunction with the cognizant technical review organization, determines that it qualifies as such.
In making such a determination, all four of the following criteria should be met:
(1)
The report deals with a specific " safety-related" subject regarding a nuclear power plant that requires a safety assessment by the NRC staff, such as component design, analytical models or techniques, or performance testing of components and/or systems that can be evaluated independently of any specific license application.
(2)
The report is, or is expected to be, referenced in a number of license or standardized reference design approval applications.
(3)
The report contains complete and detailed information on the specific subject presented. Conceptual or incomplete preliminary information will not be reviewed.
(4)
NRC approval of the report will result in increased efficiency of the review process for applications that reference the report.
Licensing topical reports addressing a new design or procedure not currently addressed in any license or standardized reference design approval application will require special consideration. In support of such a report, the sponsoring organization must submit documentation from at least two potential applicants of their intent to reference the report before NRC commits resources to perform the review. It is not the intent of the licensing topical report program to provide engineering evaluations of feasibility, economics, or desirability of material submitted that could directly or indirectly be used in sales promotion efforts.
Exceptions to these acceptance criteria may be allowed. These exceptions must be based on a staff decision that the evaluation of a proposed licensing topical report is in the public interest. The sponsoring organization should provide the staff with information that justifies such exceptions.
This may include such items as cost savings to the industry if implemented, or a consideration of whether the evaluation would contribute to the formation of a broader base for 3
resolving a present or developing safety-related subject generally evidenced by experience from operating nuclear power plants.
As an example, a proposed licensing topical report on a new pump design might be accepted for review, if experience at operating nuclear power plants indicated that currently installed pumps might be expected to infringe on the margins of safety to an unacceptable degree, and the new pump design might reasonably be expected to remedy the problem.
These exceptions will include a determination that NRC staff resources expended in the review of the licensing topical report will provide a foreseeable benefit equal to or greater than the impact from redirection and reduction of resources committed to other ongoing license actions, licensing topical report reviews, or generic technical issues.
When a sponsoring organization is planning a report that it believes can qualify as a licensing topical report, it should contact the topical report PM well in advance of the planned submittal to determine if the proposed report will satisfy the definition of a licensing topical report and,
- r so, to clarify the requirements for preparing and submitting the report A me-ting might be appropriate to discuss these issues. The topical report PM, u consultation with the staff technical specialists and management, will make a timely determination on the qualifications of the proposed report.
If the report qualifies as a licensing topical report, the sponsoring organization may then formally submit it for review.
The NRC staff may also find that addressing a safety-related matter in a licensing topical report is desirable.
In such a case, NRC management will contact the sponsoring organization and discuss the preparation of such a report.
If the organization agrees to prepare it, they will formally submit it for review.
Other types of reports that do not meet the criteria for licensing topical reports may be submitted as special reports.
HANDL:NG OF PROPRIETARY REPORTS When an organization submits a licensing topical report for NRC staff review pursuant to this NUREG series report and believes that portions of the submittal contain confidential business (proprietary) information, it must submit at least 12 copies of a nonproprietary version of the proprietary report at the same time it submits the proprietary report.
The proprietary report must show which portions of the document are proprietary by the use of italics, margin lines, underscoring, or by bracketing the proprietary material. A nonproprietary report should show what information has been deleted from the proprietary version because the submitting organization considers it to be proprietary. For example, if brackets are used in the proprietary version to show what portion of the information is considered proprietary, the nonproprietary version should have a blank portion between the brackets to show that information was removed.
Upon submittal of a properly marked licensing topical report (see 10 CFR 2.790) considered and justified as proprietary, the NRC staff will make a determination of whether or not it is proprietary and notify the submitting organization accordingly.
4
CORRESPONDENCE FROM SPONSORING ORGANIZATION PERTAINING TO REPORT All correspondence regarding licensing topical reports should be addressed to the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; Document Control Desk; ATTN: Chief, Planning, Program and Management Support Branch, and should contain both the appropriate report identifier and NRC TAC number in the upper right-hand corner.
STAFF REQUESTS FOR ADDITIONAL INFORMATION DURING REVIEW CYCLE The NRC staff can make requests for additional information on a licensing topical report under review either during a meeting or by letter.
The Chief of the technical review branch will transmit to the sponsoring organization written requests for additional information on licensing topical reports. The sponsoring organization will submit its responses to these requests and to staff comments during the review as information supplementary to the original report.
The technical review branch will schedule meetings with the sponsoring organization to discuss the contents of a licensing topical report.
TRANSMITTAL OF STAFF EVALUATION OF REPORT When the staff determines that a licensing topical report is acceptable for referencing, it will give the extent of and the conditions for acceptance, if any, in a letter transmitting the results of the evaluation. For a proprietary
- report, the transmittal letter will state that both proprietary and nonproprietary versions must be referenced in future license applications. The staff evaluation and letter of transmittal will be incorporated in the accepted version of the report when submitted.
PUBLICATION OF APPROVED VERSION OF REPORT After the staff accepts a licensing topical report for referencing, the sponsoring organization should publish an approved version.
A copy of the staf f's transmittal letter and its evaluation report should be inserted immediately after the title page of the approved version.
PLACEMENT OF REPORT AND ASSOCIATED DOCUMENTS IN PUBLIC DOCUMENT ROOM All nonproprietary correspondence regarding the review of licensing topical reports, all nonproprietary licensing topical reports, and all nonproprietary versions of proprietary reports will be placed in the NRC Public Document Room (PDR) located at 2120 L Street, N.W., Washington DC; telephone (202) 634-3273.
The sponsoring organization and the NRC staff should exercise care to ensure that any information identified as proprietary by the sponsoring organization is not used in any of the above correspondence and in licensing topical report evaluations.
Licensing topical reports are not placed in local PDRs; however, nonproprietary versions are available on request.
REVISIONS TO REPORT After a licensing topical report has been found acceptable for referencing, the sponsoring organization occasionally might need to add supplementary information 5
to keep it up to date. This is different from the sititation where the report has become obsolete and must be withdrawn. A proposed revision to an approved report is submitted to and reviewed by the NRC staff in accordance with the same requirements and procedures as those that apply to a new licensing topical report. The revision will have the same identifier as the base report with the suffix " Revision 1 or 2," etc. However, the NRC topical report PM will issue a new NRC TAC number.
When a revision to an accepted report is submitted for review, the "-A" designation will no longer be valid until the revision itself has been reviewed and accepted.
When the staff determines that the revised or supplementary material is acceptable for referencing, the sponsoring organization will submit the required number of complete new reports incorporating the revised or suppl ementary information.
Ihe revised report must contain a note on the cover page stating that it supersedes and replaces all earlier versions of the same numbered report.
The superseded reports will not be returned to the sponsoring organization.
WITHDRAWAL OF REPORT After a certain amount of time has elapsed, a licensing topical report may become obsolete, as determined by either the NRC staff or the sponsoring organization, because it does not adequately address the current state of the technology, or it t s no longer applicable because NRC criteria or regulations have changed, or for other reasons.
In this event, the sponsoring organization may, on its own volition, request that the report be withdrawn or the NRC staff may advise the sponsoring organization to do so.
On receipt of a letter from a sponsoring organization requesting withdrawal of a licensing topical report, the staff will categorize it as " withdrawn." Withdrawn reports are not acceptable as references in license applications.
The report may be replaced by an updated or new licensing topical report that has a new identifier and new NRC TAC number to avoid confusion with the withdrawn report.
I 6
. _ _....,__ _...._ _.. _ _ _._._.. _ _ _ _ _. _ _ _... _. _ _ ~. _ _ _. _ _. _ _ _ _.. _ _ _. _ _ _.. _ _.
i I
APPENDIX
.i b
i LICENSING TOPICAL REPORTS UNDER REVIEW BY THE NRC STAFF j
j LIST OF VENDORS 2
1 l
?
a s
a f
i i
N' f
i 1
1 I
i i
f' I
f f
i 3
l
?.
4'
,+
i 7
I.___.;....-..
_._...__.-_ -_ -_ _ _ __ ~.__..__ _... _ _ _ _. _. _. _. _ _ _ _ _ _... _ _,. _ _ _. _. _ _.,..
BABCOCK & WILCOX TaskID Title M04645 BAW-10060-NP - " REACTOR INTERNALS DESIGN / ANALYSIS FOR NORMAL i
UPSET & FAULTED CONDITIONS" M75040 "BAW-2086, "B&W J-R TEST PROCEDURE FOR WEDGE OPENING LOADED i
(WOL) FRACTURE TOUGHNESS SPECIMENS""
M79766 BWROG - THE NEW ATWS/ STABILITY CALCULATIONS M81851 BAW-10084P. REV.
3, PROGRAM TO DETERMINE IN-REACTOR PERFORM ANCE OF B&W FUELS. JULY 1991 M82189 BAW - 10183P FUEL ROD GAS PRESSURE CRITERION, JULY 1991 M83823 BWROG - BWR BELTLINE MATERIAL UPPER SHELF ENERGY ESTIMATION METHODS (GE-NE-523-18-1191)
M84643 BAW-10164P - REV.2 - ADVANCED COMPUTER PROGRAM FOR LIGHT WATER REACTOR LOCA AND NON-LOCA TRANSIENT ANALYSIS AUG.1992 M84800 BAW-10164P, REV.
3, RELAP/ MOD 2, B&W REV. 3 M84985 BAW-10168 P, REV.2,RSG LOCA, BWNT LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL FOR RECIRCULATING STEAM GENERATOR PLANTS M85120 BAW-10186P, EXTENDED BURNUP EVALUATION, NOVEMBER 1993 M86196 BAW-2178 P, LOW UPPER-SHELF TOUGH FRAC MECHANICS ANAL OF REAC VES OF B&WOG REAC VES WORK GRP FOR LEVEL C&D SVC.
M87102 BAW-10191-P, STAR SYSTEM COMPONENTS FOR REACTOR PROTECTION SYSTEM DIGITAL UPGRADES.
M87732 BAW-2192-P - LOW UPPER SHELF TOUGHNESS FRACTURE ANALYSIS OF REA. VESSEL OF B&WOG RVWG FOR LEVEL A&B CONDITION M87805 BAW-10189P, CHF TESTING AND ANALYSIS OF THE MARK-BW FUEL ASSEMBLE DESIGN, 9/93.
M88150 BAW-10168 NP - REV.3 - OCT. 1993 - RSG LOCA - BWNT LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL RECIRCULATING STEM PLANTS M88739 BAW-2181 NP, CRAFT 2 - RELAPS/ MOD 2 - COMPARISON FOR SMALL BREAK LOCA ACCIDENT ANALYSIS..
i I
BABCOCK & WILCOX TaskID Title M88899 BAW-10187P, APPENDIX F t
_g_
w a
=
COMBUSTION ENGINEERING l
TaskID Title j
M04685 CENPD-212-NP
" INSTRUMENT QUALIFICATION ENVIRONMENTAL QUALI j
FICAITON OF C-E INSTRUMENTATION EQUIPMENT, PARTS ONE.
M47020 CENPD-172A-NP "TR" PLANT PROTECTION SYSTEM WITH INTEGRATED AUTOMATIC TEST SYSTEM (SSPPS) INTERCONNECT DES M72033 "CEN-381-P LOW TEMP OVERPRESSURIZATION TRANSIENT P-T LIMIT FOR DETERMINATION LOW TEMP OP PROTE M75965 CEN RPA 89-112 ABB ATOM CONTROL ROD DROP ACCIDENT ANALYSIS METHODOLOGY FOR BWRS M75966 CEN-00-000 RPA-89-053 P ABB ATOM HIGH WORTH CONTROL RODS FOR BWRS ROD DROP ACCIDENT ANALYSIS M80895 ABB REPORT - RPA 89-053 "ABB HIGH WORTH RODS, ROD DROP ACCI-DENT ANALYSIS" M81374 CEN-403 - ESFAS SUBGROUP RELAY TEST INTERVAL EXTENSION j
M82272 CEN-405-P, REV.1-P APPLI OF REACTOR VESS SURVEILL DATA FOR EMBRITT MGMT M82718 CENPD--282P TECH MANUAL FOR CENTS CODE VOLUME 3 j
l M85911 CENPD-282 (P), VOL.
4, TECHNICAL MANUAL FOR THE CENTS CODE M86126 CENPD-283-P BOILING WATER REACTOR EMERGENCY CORE COOLING
]
EVALUATION MODEL: CODE SENSITIVITY FOR SVEA-96 FUEL.
4 M86193 CEN-420-P, VOL.
1, PART 1, SMALL BREAK LOCA REALI5fIC j
EVALUATION MODEL.
M87733 CEN-405-P REV. 2 - APPLICATION OF REACTOR VESSEL SURVEIL LANCE DATA FOR EMBRITTLEMENT MANAGEMENT.
M87910 CENPD-289-P, JUSTIFYING USE OF INSERT REPLACEMENT RODS IN ABB CENF FUEL ASSEMBLIES.
M88025 CENPD-284 P, CONTROL ROD DROP ACCIDENT ANALYSIS METHODOLOGY FOR BWR'S:
SUMMARY
AND QUALIFICATION M88029 CEN-420 P - VOL. 1 - SMALL BREAK LOCA REALISTIC EVALUATION COMBUSTION ENGINEERING TaskID Title M88447 CEN-420, P VOL. II, WITH SUPPLS. 1 AND 2 AND VOL. 3 SMALL BREAK LOCA REALISTIC EVALUATION MODEL 4
H.. _
DUKE POWER TaskID Title M85181 DPC-NF-2005-P TIIERMAL/ HYDRAULIC STATISTICAL CORE DESIGN MET!!ODOLOGY M88082 DUKE-2007 P - FUEL RECONSTITUTION ANALYSIS METHODOLOGY i w r-r-
w w --
d-~---
m
,e w-
UTILITY GROUP FOR REG. APPLICATION TaskID Title M80205 EPRI REPORT NP-6628 PROCEDURE FOR SEISMIC EVALUATION AND DESIGN OF SMALL BORE PIPING (NCIG-14)
M88026 EPRI-TR-102470 P"HIGH FREQUENCY SEISMIC EFFECTS" M88898 EPRI MOV TOPICAL REPORT REVIEW GENERAL ELECTRIC TaskID Title M57536 NEDO-30832-NP - "TR: "ELIMITATION OF LIMIT ON BWR SUPPRES SION POOL TEMPERATURE FOR SRV DISCHARGE WITH QUEN" M64221 NEDC-31336-P " GENERIC ELECTRIC INSTRUMENT SET POINT METHODO LOGY METHODOLOGY" M77253 NEDE 2 - 24011-P-A, AMENDMENT 23 " GENERAL ELECTRIC STANDARD APPLICATION FOR REACTOR FUEL" (GESTAR-11)
M80309 NEDC-31951P - IMPLEMENTATION OF IMPROVED WATER CHEMISTRY AND TECHNICAL BASIS FOR REVIDED PIPING INSPECTION SCHEDULES M81275 NEDO-31695 BWR SUPPERSSION POOL TEMPERATURE TECHNICAL SPECIFICATION LIMITS M82663 NEDC 31984P, GENERIC EVAL. OF GE BWR POWER UPRATE, SUPPL 1, DTD 10/91 M82823 NEDE-32177-P GENERAL ELECTRIC CO. TRACG COMPUTER CODE QUALIFICATION M83089 BWR'S GRP (GE RPT NEDC 32013P) SYSTEM ANALYSES FOR ELMINATION OF SELECTED RESPONSE TIMETESTING RREQUIREMENTS M83533 GE COMPANY REVIEW OF QA TOPICAL REPORT NEDO-11209-04A, "GE NUCLEAR ENERGY QAPD," FROM ACCEPTANCE OF REV 9 M84984 NEDC-31984 P - SUPPLEMENT 2, GENERIC EVALUATIONS OF GENERAL ELECTRIC BOILING WATER REACTOR POWER UPRATE, OCTOBER 1992 M85776 NEDC-32160 P, BWR OWNERS' GROUP LICENSING TOPICAL REPORT CALIBRATION INTERVAL EXTENSION.
M85913 NEDE-32176 (P), TRACG, MODEL DESCRIPTION, 2/93.
M85915 NEDE-32178 (P), APPLICATION OF TRACG MODEL TO SBWR LICENSING SAFETY ANALYSES, 2/93.
M87103 NEDE-32177-P, TRACG QUALIFICATION, REVISION 1, JUNE 1993.
M87911 NEDC-31858-P, REV.
2, BWROG RPT FOR INCREASING MSIV LEAKAGE RATE LIMITS & ELIMINATION OF LEAKAGE CONTROL SYSTEMS. I
SIEMENS TaskID Title M73094 "ANF-929 SUP 2 EVALUATION OF RANGE OF APPLICABILITY OF HEAT TRANSFER COEFFICIENTS PROPOSED FOR 9X9 M80400 ANF-90-145(P) VOLS. 1& 2 - RODEX3 FUEL ROD THERMAL-MECHANIC AL RESPONSE EVALUATION MODEL, ADVANCED NUCLEAR FUEL CORP.
l M81069 ANF-90-082(P) REV. 1 APPLICATION OF ANF DESIGN METHODOLOGY FOR FUEL ASSEMBLY RECONSTITUTION ADVANCE NUCLEAR FC, MAY '91 M81070 ANF-89-90(P) REV 1 GENERIC MECHANICAL DESIGH CRITERIA FOR BWR FUEL DESIGNS ADVANCED NUCLEAR FUEL CORP. APRIL 1991 M83302 XN-NF-82-49(P), REV.1, REVISED EXEM/PWR SMALL BREAK LOCA MODEL, SIEMENS NUCLEAR POWER CORP. SUPPLEMENT 1 M84245 EMF-92-116 P - GENERIC MECHANICAL DESIGN CRITERIA FOR PWR FUEL DESIGNS.
M84718 EMF-92-139(P), VOL.
3, REALISTIC LOCA ECCS EVALUATION MODEL ASSESSMENT FOR PWR LARGE BREAK LOCA ANALYSIS.
M84811 EMF-92-139(P), VOL.
2, S-RELAP 5 REALISTIC LOCA ECCS EVALUATION MODEL FOR PWR LARGE BREAK LOCA ANALYSIS.
M85182 EMF-92-139(P), VOLUME 1,
" REALISTIC LOCA ECCS EVALUATION MODEL METHODOLOGY FOR PWR. LARGE BREAK LOCA ANALYSIS,"12/92 M86765 EMF-93-074 (P), GENERIC MECHANICAL LICENSING RPT FOR ADVANCE D 17X17 FUEL DESIGN.
M87010 EMF-92-139(P), VOL 3 SUPPL 2, REAL LOCA ECCS EVAL MODEL ASSMT FOR PWR LARGE BREAK LOCA ANALYSIS ASSMT FOR CCTF TEST
[
M87011 EMF-92-139(P), VOL.
3, SUP 1, REAL LOCA ECCS EVAL MODEL ASSE SSMT FOR PWR LARGE BREAK LOCA ANALYSIS FLECHT SEASET 31504 M87012 EMF-92-139-P, V4, REALISTIC LOCA ECCS EVAL MODEL FOR PWR LARGE BREAK LOCA ANALYSIS-UNCERTAINTY ANALYSES, 7/93 M87013 ENF-92-139-P, V3, S7, REALISTIC LOCA ECCS EVAL MODEL ASMT FOR PWR LARGE BREAK LOCA ANALYSIS, W4 LOOP PWR SAM PROBLEM M87014 EMF-92-139-P, V3,S6, REALISTIC LOCA ECCS EVAL MODEL ASMT FOR PWR LARGE BREAK LOCA ANALYSIS-W 3-LOOP PWR SAM PROBLEM, 5/93 M87015 EMF-92-139-P, V3, SS, REALISTIC LOCA ECCS EVAL MODEL ASMT FOR PWR LRGE BREAK LOCA ANALYSIS ASMT UPTF TEST 6&7, 6/93 f I
(
l SIEMENS l
TaskID Title l
M87016 EMF-92-139-P V3,S4, REALISTIC LOCA ECCS EVAL MODEL ASMT FOR PWR LARGE BREAK LOCA ANALYSIS LOFT TEST L2-6, 6/93 M87017 EMF-92-139P V-3,S-3, REALISTIC LOCA ECCS EVAL MODEL ASMT FOR l
PWR LARGE BREAK LOCA ANALYSIS-ASMT LOFT L2-5, 6/93 i
M87174 EMF-074-SIEMENS POWER CORPORATION BWR STABILITY CODE, STAIF (EMF-CC-074(P), VOLUME 1)
M87906 EMF-074 (P), VOL.
2, STAIF: A COMPUTER PROGRAM FOR BWR STABILITY ANALYSIS-CODE QUALIFICATION RPT, 9/93 i
M87907 EMF-93-164(P), POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FOR INPAX-W IN WESTINGHOUSE PLANTS, SEPT. 1993.
M89013 STAFF REVIEW OF REV. 27 TO SIEMENS' POWER CORPORATION NUCLEAR DIV. (SPC) QA TOPICAL EMF-1A, DATED 1/31/94.
l i
e d
i.
2.
STONE & WEBSTER l
TaskID Title M04723 SWECO-7703-NP
" MISSILE-BARRIER INTERACTIONS" l
M81528 STONE & WEBSTER QAPD(TOPICAL REPORT SWSQAP 1-74A) FROM COMPL ETION OF REVIEW OF REVISION F THRU COMPLETION OF REVIEW OF 1
I i.
. _. _ _ _. _..... _. ~. _ _ _ _ _. _ _ _ _ _.... _. _
l WESTINGHOUSE TaskID Title M00789 WCAP-08163-NP
" REACTOR COOLANT PUMP INTEGRITY IN A LOCA" i
i M03000 WCAP-08687-P " ENVIRONMENTAL QUALIFICATION OF WESTINGHOUSE NSS CLASS IE EQUIPMENT" M04246 WCAP-08510-NP " METHOD FOR FRACTURE MECHANICS ANALYSIS OF l
NUCLEAR REACTORS UNDER SEVERE THERMAL THRANSIENTS" i
M04849 WCAP-09172-P "AN N-16 TRANSIT TIME FLOW MEASUREMENT SYSTEM (TTFM) DESCRIPTION AND PERFORMANCE" M04882 WCAP-09292-NP " DYNAMIC FRACTURE TOUGHNESS OF ASME SA508 CLASS 2A ASME SA533 GRADE A CLASS 2 BASE & HEAT AFFECTED.
M55319 WCAP-08354,SUPP.3-P "LONG TERM ICE CONDENSER CONTAINMENTCODE FOLLOWING STEAMLINE RUPTURE WITH SUPER HEATED STEAM" M61013 WCAP-10972-P - ABB ATOM-WESTINGHOUSE CORRELATION FOR PREDICT ING CPR MARGINS IN BOILING WATER REACTORS.
M64956
"(WCAP-10858-P-A) ADDENDUM 1 "AMSAC GENERIC DESIGN PACKAGE""
M66167 WCAP-11500-P " WESTINGHOUSE REFERENCE REPORT FOR BWR FUEL" M77257 WCAP 12488, WESTINGHOUSE FUEL CRITERIA EVALUATION PROCESS M79497 WCAP-12762 SECONDARY SIDE SAFETY INJECTION FUNCTION DELETION MODIFICATION M81078 WCAP-12909-P " WESTINGHOUSE ECCS EVALUATION MODEL: REVISED LARGE BREAK LOCA POWER DISTRIBUTION METHODOLOGY M81712 WCAP-12945-P, VOL.1, WESTINGHOUSE CODE QUALIFICATION DOCUMEN T FOR BEST ESTIMATE LOSS OF COOLANT ACCIDENT ANALYSIS M82099 WCAP-10924-P-REV. 2-VOLUME 2-ADDENDUM 3 - LARGE BREAK LOCA BEST ESTIMATE METHODOLOGY - UPPER PLENUM INJECTION MODEL IMP l
M82772 WCAP - 8183 REV. 19 - OPERATIONAL EXPER W WESTINGHOUSE CORES 12/31/90 N/P M83235 WCAP-13360 WESTINGHOUSE DYNAMIC ROD WORTH MEASUREMENT TECHNIQUE, MAY 1992 P 4. - - -
i WESTINGHOUSE TaskID Title 4
M83321 WCAP-12476, EVALUATION OF LOCA DURING MODE 3 AND MODE 4 OPERATION FOR WESTINGHOUSE NSSS.
I I
M83964 WCAP-12945-P VOL.
1, REV. 1-WESTINGHOUSE CODE QUALIFICATION DOCUMENT FOR BEST ESTIMATE LOSS OF COOLANT ACCIDENT.
M84324 WCAP 13246 P/WCAP 13412 NP W-GOTHIC - A COMPUTER CODE FOR ANALYSES OF THERMAL HYDRAULIC TRANSIENTS FOR NUCLEAR PLANT.
l M84796 WCAP-12945-P, VOL.
2, WESTINGHOUSE CODE QUALIFICATION DOC-1 UMENT FOR BEST ESTIMATE LOSS OF COOLANT ACCIDENT ANALYSIS.
M84797 WCAP 13524, APPOLO - A DIMENSIONAL NEUTRON DIFFUSION THEORY PROGPAM.
i M85165 WCAP-12610 VANTAGE + FUEL ASSEMBLY REFERENCE CORE REPORT.
M85290 NUMARC WCAP-13565 (NP) ALLOY 600 REACTOR VESSEL HEAD ADAPTOR CRACKING SAFETY EVALUATION.
4 M85707 WCAP-13589 P - ASSESSMENT OF CLAD FLATTENING AND DENSIFICAT-ION POWER SPIKE FACTOR ELIMINATION IN WESTINGHOUSE NUCLEAR M85732 WCAP-13525 (P), RV CLOSURE HEAD PENETRATION ALLOY 600 PWSCC (PHASE 2 )
i M85738 WCAP-13247 (P) STEAM GENERATOR TUBE UNCOVERY ISSUE.
M85835 WESTINGHOUSE TOPICAL ON-WCAP-8370 REV12A ORGANIZATIONAL j
CHANGES M85837 WCAP-13610 P - SAFETY EVALUATION SUPPORTING THE CONDITIONAL EXEMPTION OF THE MOST NEGATIVE EOL MODERATOR TEMPERATURE M85912 NUMARC WCAP 13565, REV.
1, (NP) ALLOY 600 REACTOR VESSEL HEA ADAPTOR TUDE CRACKING SAFETY EVALUATION.
M86251 WCAP-12945-P - VOLUME 3 -WESTINGHOUSE CODE QUALIFICATION 1
DOCUMENT FOR BEST ESTIMATE LOSS OF COOLANT ACCIDENT ANALYSIS M86416 WCAP-12610- APPENDIX B - EXTENDED BURNUP FUEL DESIGN METH-ODOLOGY AND ZIRLO FUEL PERFORMANCE MODELS ADDENUM 1(P)
M86720 WCAP-13677, 10 CFR 50.46 EVALUATION MODEL RPT: WCOBRA/ TRAC TWO-LOOP UPPER PLENUM IN MODEL UPDT TO SUPPORT ZIRLO/TM CLAD 4
)
~.,
G &
WESTINGHOUSE TackID Title M86764 WCAP-13749 (P), SAFETY EVALUATION SUPPORT THE CONDITION EXEMP OF THE MOST NEGATIVE EOL MOD TEMP COEFFICIENT MEASURE I
M87018 WCAP-12945-P, VOLS. 4&5, WESTINGHOUSE CODE QUALIFICATION DOCUMENT FOR BEST ESTIMATE LOSS OF COOLANT ACCIDENT ANALYSIS M88304 WCAP-13803 P, REV 1.,
GENERIC ASSESSMENT OF ASYMMERTRIC ROD CLUSTER CONTROL ASSEMBLY WITHDRAWAL.
M88305 WCAP-13864 NP, ROD CONTROL SYSTEM EVALUATION PROGRAM. l l
_ = = _ _.
i WESTINGHOUSE STEAM TURBINE-GENERATOR TaskID Title M65737 WSTG-4-P " ANALYSIS OF THE PROBABILITY OF THE GENERATION OF MISSILES FROM FULL INTEGRAL NUCLEAR LOW PRES..
7 LIST OF VEND 0RS ABB Combustion Engineering Nuclear Power B&W Nuclear Technologies Duke Power Company Electric Power Research Institute General Electric Company Siemens Power Corporation Stone & Webster Engineering Corporation Westinghouse Electric Corporation 1
22
NRC FORM 335 U.S. NUCLE AR REGUL ATORY COMMIS$10N
- 1. REPOR T NUMBE R f 2 891 (Cass8gned tg NRC Add Vol., Supp., Rey,,
NRCM 1107 and Addendurn Numbers,6f anyl 22m. 22w BIBLIOGRAPHIC DATA SHEET NUREC-0390 rsee wsr<uct.ons on the mers*>
yog, g, y0, g
- 7. TIT 4,E AND SUSTITLE Topical Report Review Status 3.
D ATE REponT PusLiSHED MoNrm vg4R MAY 1994
- 6. TYPE OF REPORT Regulatory
- 8. PE R FO RMING oRG ANIZ ATiON - N AM E AN D ADDR ESS itt NRC orownsr uivrsion. Oftwo or Roton. uS Nuclear Rnutarory Commossoon, and melme ndorest of contractor. orowse none and motet oidrwsti Program Management, Policy Development, and Analysis Staff Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING oRG ANlZ ATlON - N AM E AND ADOR ESS it! NRC. tror %me as abo #, if contractor. orovode NMC Comma, Ottne or Rnen. US Nucerer Rnutatory Commmaan, and malme eddres,L)
Same as above 10 SUPPLEMENTARY NOTES
- 11. ABST R ACT (200 =ordn er semi This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) will process and respond to topical report submissions, and an accounting of all topical reports currently being reviewed by the NRC staff. This report will be published semiannually.
l 12, RE Y WOR DS/DESCR '.PTORS (Lat wore oronreses andt wist assest researcher:M tocateng the recort.s
- 12. AV AILA81La r v $I A T EME NT Unlimited Topical Report
" " " ' " " ^ " ^ ' " ^
c rn,snen Unclassified e rn. R com Unclassified
- 15. NUMBER OF PAGES
- 16. PRICE NRC FORM 3J5 (1494
i on recycled paper i
f Federal Recycling Program
NUREG-0390, Vol 8, No.1 TOPICAL REPORT REVIEW STATUS MAY 1994 UNITED STATES nasT ct Ass MAit WUCLEAR REGULATORY COMMISSION PcST AGE AND FEES PA!D WASHINGTON. D.C. 20555-0001 ussac PE R'M T NO G 67 CFFICIAL BUS: NESS PENALTY FOR PR:VATE USE. $300 1 1AN19H SVES PUBLICAIIONS s
y E.
-POR-h0 REG 2kFN-6E7 CC gg WASpINGTOh,
.