ML20107B052
| ML20107B052 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1996 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0390, NUREG-0390-V10, NUREG-390, NUREG-390-V10, NUDOCS 9604150318 | |
| Download: ML20107B052 (36) | |
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Vol.10 j
l Topical Report Review Status l
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation
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AVAILABILITY NOTICE Availability of Reference 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 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 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 agreement 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.
I Documents ava,ilable from the National Technical information Service include NUREG-series j
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 l
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. Nuclear 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.
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NUREG-0390 Vol.10 i
N Topical Report Review Status f
i Manuscript Completed: February 1996 Date Published: March 1996 Division ofInspection and Support Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
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ABSTRACT This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) processes and responds to topical report submittals, and an accounting, with review schedules, of all topical reports currently accepted for review by the NRC.
This report will be published annually.
Each sponsoring organization with one or more topical reports accepted for review receives copies, i
iii NUREG-0390
CONTENTS l
ABSTRACT 111
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NUCLEAR REGULATORY COMMISSION LICENSING TOPICAL REPORT PP.0 GRAM 1
l LICENSING TOPICAL REPORT PROGRAM MANAGEMENT...............
1 PROCEDURE FOR SUBMITTING LICENSING TOPICAL REPORTS I
Submittal of Reports for Review..................
I Copy Requirements.........................
I FORMAT OF LICENSING TOPICAL REPORTS...................
2 t
Report Identifier.........................
2 Abstract 2
introduction 2
i Body of Report 3
L References 3
1 CRITERIA FOR ACCEPTING NEW LICENSING TOPICAL REPORTS FOR REVIEW.....
3 l
l HANDLING OF PROPRIETARY REPORTS.....................
4 i
l CORRESPONDENCE FROM SPONSORING ORGANIZATION PERTAINING TO REPORTS....
5 l
NRC REQUESTS FOR ADDITIONAL INFORMATION DURING REVIEW CYCLE.......
5 TRANSMITTAL OF NRC EVALUATION OF REPORTS 5
PUBLICATION OF APPROVED VERSION OF REPORTS...
5 PLACEMENT OF REPORTS AND ASSOCIATED DOCUMENTS IN PUBLIC DOCUMENT ROOM..
5 REVISIONS TO REPORTS 6
WITHDRAWAL 0F REPORTS..........................
6 APPENDIX.................................
7 EXPLANATION OF APPENDIX 8
TOPICAL REPORTS ACCEPTED FOR REVIEW.................
9 1
I i
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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 to the NRC on specific safety-related subjects 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 both industry and the NRC by providing for a single review and approval of the safety-related subject with subsequent referencing in licensing actions, rather than repetitive reviews of the same subject. The reports currently accepted for review are given in the appendix.
4 LICENSING TOPICAL REPORT PROGRAM MANAGEMENT l
A topical report program manager (PM) manages and coordinates the overall program.
Each review branch with responsibility for the detailed technical review of a specific report assigns review specialists who report to their own management on the detailed technical review matters.
PROCEDURE FOR SUBMITTING LICENSING TOPICAL REPORTS t
Submittal of Reports 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, lhe transmittal letter and report should be addressed to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; 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.
e 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.
Copy Reauirements Licensing topical reports must be submitted in hard copy in the following quantities.
Additional copies will be provided to the NRC staff upon request.
1 I
Report Classification Hard Copy Nonproprietary reports 15 Proprietary reports Proprietary version 15 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 REPORTS 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, and the old review will be closed out.
Abstract l
Each report should include an abstract no longer than one page that summarizes the contents of the report and the conclusions reached.
Introduction i
Each 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.
Body of Report The body of each 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 Each report should include a list of all pertinent references.
CRITERIA FOR ACCEPTING NEW LICENSING TOPICAL REPORTS FOR REVIEW The cognizant technical review organization screens reports submitted for review under the licensing topical report program in accordance with the following criteria.
No new report submitted by any organization will be accepted as a licensing topical report unless 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 that present a new design or procedure not currently addressed in any license or standardized reference design approval application 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 the NRC commits resources to perform the review.
It is not the intent of the licensing topical report program to provide engineering evalu3tions 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 an NRC decision that it is in the public interest to evaluate a proposed licensing topical report.
The sponsoring organization should provide the NRC with justification for such exceptions.
This may include such items as cost savings to the industry if implemented, or a consideration of whether 3
the evaluation would contribute to the formation of a broader base for 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 qvalify 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, if so, to clarify the requirements for preparing and submitting the report. A meeting might be appropriate to discuss these issues.
The topical report PM, in 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.
l The NRC 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.
If accepted for review under the licensing topical report program, the report will be listed in the appendix to this NUREG series report.
If the report is rejected for review, the sponsoring organization will be notified of this decision.
HANDLING 0F PROPRIETARY REPORTS i
When an organization submits a licensing topical report for NRC review pursuant to this NUREG series report and believes that portions of the report 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 are proprietary by the use of italics or margin lines or by underscoring or 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 NUREG-0390 4
)
l should have a blank portion between the brackets to show that information was removed. Upon submittal of a properly marked licensing topical report (see Section 2.790 of Title 10 of the Code of Federal Reaulations) considered and justified as proprietary, the NRC will determine whether or not the information should be withheld from public disclosure and will notify the submitting organization accordingly.
CORRESPONDENCE FROM SPONSORING ORGANIZATION PERTAINING TO REPORTS All correspondence regarding licensing topical reports should be addressed to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington, DC I
l 20555-0001; ATTN: Chief, Planning, Program and Management Support Branch, and should contain both the appro the upper right-hand corner. priate report identifier and NRC TAC number in NRC REQUESTS FOR ADDITIONAL INFORMATION DURING REVIEW CYCLE The NRC may request 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 NRC EVALUATION OF REPORTS When the NRC 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 NRC evaluation and letter of transmittal will be incorporated in the accepted version of the report when submitted.
PUBLICATION OF APPROVED VERSION OF REPORTS After the NRC accepts a licensing topical report for referencing, the sponsoring organization should publish an approved version. A copy of NRC's transmittal letter and its evaluation report should be inserted immediately after the title page of the approved version.
PLACEMENT OF REPORTS 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 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 5
3 4
evaluations.
Licensing topical reports are not placed in local PDRs; however, nonproprietary versions are available on request.
REVISIONS TO REPORTS J
l After a licensing topical report has been found acceptable for referencing, the sponsoring organization occasionally might need to add supplementary information to keep it up to date. This is different from the situation 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 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 NRC 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 supplementary information. The revised repoit must contain a note on the cover page stating that it supersedes and replaces all earlier versions of the same numbered repart. The superseded reports will not be returned to the sponsoring organization.
WITHDRAWAL OF REPORTS After a certain amount of time has elapsed, a licensing topical report may become obsolete, as determined by either the NRC or the sponsoring organization, because it does not adequately address the current state.of the technology, or it is 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 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 NRC 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.
4 i
APPENDIX TOPICAL REPORTS ACCEPTED FOR REVIEW BY THE NRC STAFF 7
EXPLANATION OF APPENDIX TASK ID Technical Assignment Control (TAC) number used for tracking purposes REV Name of the organization reviewing the topical report TITLE Name of the topical report APPL DATE Date of the letter transmitting the topical report to NRC SCHEDULE ACT START Planned or actual technical review start date TR COMP Planned or actual technical review completion date ACTION COMPLETE Date of document which closes action on the topical report (NRC letter of approval or rejection, sponsoring organization letter of withdrawal)
ACT HOURS Staff hours that have been charged in the review of a topical report SCH REM HOURS Remaining number of scheduled staff hours to complete review of topical report APPL ACCESSION Accession number given the letter transmitting the topical report when submitted to NRC for review l
X-Cancelled H-Hold L-Target Date Passed C-Complete X(CR) -
Scheduled at a constant rate of x hours per week; i.e.,
4(CR) indicates 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week Unassigned -
Not yet assigned to a reviewer in organization shown Suppressed -
Reviewer currently not on NRR staff NOTES:
j The appendix does not reflect contractor costs.
j The estimates shown in the appendix are based on workload and resource projections that are focused on the next 6 months.
Priority of a review task is determined primarily on the basis of safety significance, risk considerations, and operational impact.
Schedules are subject to change in the event of higher priority, safety-related issues.
Report Date 02/07/96 Topicet Manager Report (Condmoed)
For AOS EXNWUSTION ENGINEERING Schedate Sch.
Appl Act TR Sctlen Act.
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Title Date Start Complete Complete Neure Moure Acceeelon I
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CEN RPA 89-112 - Aes ATON CONTROL ROD (01/31/90) (07/18/92) (--/--/-- ) (12/31/96T) 150 10 9002060263 i
OROP ACCIDENT ANALYSIS METMEBOLOGY FOR SWRS SRNSA 07/18/92 12/31/96 150 10 M75966 CEN-00-000 RFA-89-053 P - AOS ATOM MIGN (01/31/90) (07/18/92) (--/--/-- ) (12/31/96T) 128 to 9002060263 WORIM CONTROL RODS FOR BWRS ROD DROP ACCIDENT ANALYSIS SRNBA 07/18/92 12/31/96 128 10 m
M80895 A88 REPORT - RPA 89-053 "A88 MIGM WORTM (02/09/90)
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M81374 CEN-403 - ESFAS SUBGROUP RELAY TEST (07/31/91) (09/07/91)
(--/--/-- ) (03/31/96T) 376 60 9511280181 INTERVAL ENTENSION NICBA 01/08/94 03/31/M 284 42 MICBA 03/28/92 03/31/ %
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Title Date Start Complete Complete Hours Hours Accession c3 M87910 CEWPD-289-P, JUSTIFYING USE OF INSERT (09/30/93) (01/01/94)
(--/--/-- ) (04/30/96T) 75 19 9310050224 REPLACEMENT RODS IN ABB CENF FUEL ASSEMBLIES.
SRXBA 01/01/94 04/30/ %
75 19 M88025 CENPD-284-P - CONTROL ROD DROP ACCIDENT (10/01/93) (03/26/94) (--/--/-- ) (02/29/96T) 217 2 9310140114 ANALYSIS METHODOLOGY FOR BWR'S:
SUMMARY
AND QUALIFICATION SRXBA 03/26/94 02/29/ %
217 2
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M89487 CENPD-290-P - ABB BWR GENERIC CONTROL (02/16/94) (08/06/94) (--/--/-- ) (12/31/%T) 31 24 9402280297 ROD DESIGN METHODOLOGY SRXBA 08/06/94 12/31/96 31 24 M89663 CENPD-288 - ABB SEISMIC /LOCA EVALUATION (05/26/94) (09/03/94)
(--/--/-- ) (03/15/961) 237 18 9406060335 METHODOLOGY FOR BWR FUEL SRXBA 09/03/94 03/15/%
237 18 i
Report Date 02/07/96 Topical Manager Report (Condensed)
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Title Date Start Conplete Complete Nours Hours Accession M90188 CENPD-285 - FUEL ROD DESIGN METHODS FOR (06/08/94) (09/03/94) (--/--/-- ) (02/15/967) 248 7 9406150153 BWRS SRMBA 09/03/94 02/15/M 248 7
M90189 CENPD-287 - FUEL ASSEMBLY MECHANICAL (06/17/94) (09/03/94) (--/--/-- ) (02/29/M T) 241 1 9406270348 DESIGN METHODOLOGY FOR BWRS SRXBA 09/03/94 02/29/%
241 1
M91197 CENPD-300-P - REFERENCE SAFETY REPORT (12/08/94) (01/07/95) (--/--/-- ) (02/29/96T) 228 10 9412160044 W
FOR BWR RELOAD FUEL PD42 09/02/95 --/--/--
30 0
PD42 09/16/95 --/--/--
10 0
SRxBA 02/04/95 02/10/95C 3
SRxBB 01/07/95 02/29/M 185 10 SRxBC 02/04/95 02/06/95C 1
M92883 CENPD-294-P - THERMAL HYDRAULIC (06/19/95) (08/12/95)
(--/--/-- ) (11/17/MT) 78 17 9507030114 STABILITY METHODS FOR BWRS SkXBA 08/12/95 11/17/96 78 17 E
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Title Date Start Couplete Complete Mours Mours Accession c3 M92981 C-E OWNERS GROUP - JOINT APPLICATION (07/27/95) (08/05/95) (--/--/-- ) (08/25/97T) 733 1194 9508220084 REPORTS FOR TECH SPEC ACT EXTENSIONS EELOA 09/16/95 04/30/96 98 105 SPS88 09/09/95 08/25/97 102 658 SPS88 10/14/95 03/08/ %
147 64 SRX88 09/23/95 09/30/96 10 28 SRX88 12/02/95 02/22/96 10 9
SRX88 09/16/95 09/30/%
83 46 TS8 08/05/95 09/30/96 283 285 M93253 CEN-622 - GENERIC UPPER SHELF VALUES FOR (07/07/95)
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LINDE 1092, 124, & 0091 RV WELDS EMC8
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(--/--/-- ) (02/29/%T) 75 5 9509150078 METHODOLOGY FOR BOILING WATER REACTORS SRXBA 09/23/95 02/29/M 75 5
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Title Date Start Complete Complete Hours Hours Accession M84985 BAW-10168-P, REV.2 - RSG LOCA, SWNT LOCA (11/10/92) (02/27/93)
(--/--/-- ) (05/03/96T) 81 27 9211200193 EVALUATION MODEL FOR RECIRCULATING STEAM GENERATOR PLANTS SRXB8 10/02/93 05/03/M 73 27 SRX88 02/27/93 08/01/94X 9
n85120 BAW-10186-P - EXTENDED OURNUP (11/24/92) (05/22/93) (--/--/-- ) (04/30/96T) 140 9 9212030353 EVALUATION, NOVEMGER 1993 SRXBA 05/22/93 04/30/M 120 4
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M91466 BAW-10199-P - BWU CRITICAL HEAT FLUX (12/16/94) (03/11/95) (--/--/-- ) (03/29/%T) 88 16 9501130212 CORRELATIONS.
SRXBA 03/11/95 03/29/M 88 16 M93346 BAW-10193P - RELAPS/M002-B&W FOR SAFETY (08/14/95) (11/11/95) (--/--/-- ) (09/25/%T) 2 249 9508180260 7C ANALYSIS OF B&W-DESIGNED PWRS g
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Title Date Start Couplete Complete Mours Mours Accession c3 M933%
BAW-2244 - S&WOG PRESSURIZER TOPICAL (08/31/95) (09/23/95)
(--/--/-- ) (12/20/96T) 174 0 9509060173 REPORT FOR GLRP 10/07/95 --/--/--
Suppressed 21 0
09/30/95 --/--/--
S w essed 4
0 PDLRA 09/23/95 --/--/--
26 0
PDLRA 12/16/95 --/--/--
3 0
PDLRB 09/23/95 --/--/--
71 0
PDLRB 09/23/95 --/--/--
49 0
M93556 BAW-10159P-A - EXTENDED APPLICATION OF (04/24/95) (09/16/95)
(--/--/-- ) (02/29/96T) 12 5 9504280344 BWCMV-CORNELATION OF CRITICAL MEAT FLUX g
A IN MIXING VANE GRID FUEL ASSEP. TO WE SRXBA 09/16/95- 02/29/%
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M93638 BAW-2228P, REV 1, FRACTURE MECH. ASSESS. (08/15/95) (10/07/95)
(--/--/-- ) (12/31/%T) 21 0 9508300156 0F POSTULATED OUTERSURFACE, SEMI-ELLIP CIRCUM RV N0ZZLE-TO-PIPE WELD FLAWS EMCB
--/--/--
12/31/95 0
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18 0
POSTB 10/07/95 --/--/--
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M94376 BAW-2245 - INITIAL RT-NOT OF LINDE 80 (09/22/95)
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Appl.
TaskID Rev.
Title Date Start Complete Complete Mours Nours Accession M92914 NFSR-0111 - BWR TRANSIENT ANALYSIS (06/26/95) (08/19/95)
(--/--/-- ) (09/30/96T) 191 255 9507060338 METHODS TOPICAL REPORT HQMBB 11/04/95 01/26/95C 3
SRMBA 08/19/95 09/30/ %
162 232 SRMBA 11/11/95 03/31/96 26 23 w
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- D
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6 Appt Act TR Action Act.
Res.
Appl.
g TaskID Rev.
Title Date Start Couplete Complete Hours Hours Accession c3 M88898 EPRI NOV - TOPICAL REPORT REVIEW (02/22/94) (06/11/94) (--/--/-- ) (02/29/96T) 397 0 9410310173 EMEB 12/02/95 --/ -/--
4 0
EMEB8 06/18/94 5tCR) 353 PD33 07/09/94
--/--/--H 9
0 PD33 06/11/94
--/--/--H 32 0
i M91235 EPRI-102323 - Guidelines for (12/19/94) (01/14/95)
(--/--/-- ) (10/09/98T) 585 281 9412270123 Electromagnetic Interference for Testing Power Plants MICB 11/11/95 --/--/--
8 0
HICBA
--/--/-- --/--/--
0 0
gm MICBB 09/16/95 --/--/--
20 0
HICBE 01/14/95 10/09/98 557 281 r
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Rest.
Appl.
TaskID Rev.
Title Date Start Complete Complete Hours Mours Accession M77253 10EDE-24011-P-A, AM 23 - GE STANDARD (01/19/90) (01/04/92)
(--/--/-- ) (11/25/967) 11 0 9303300067 APPLICAT10ei FOR REACTOR FUEL (GESTAR-11)
SRXB
--/--/-- 10/20/90C 0
SRXBA 01/04/92 11/25/%
11 0
M85776 NEDC-32160-P - BWROG " CALIBRATION (01/08/93) (05/01/93)
(--/--/-- ) (06/30/96T) 301 22 9302040000 INTERVAL EXTENSION" HICBA 05/01/93 06/30/%
253 0
HICBA 11/05/94 06/30/ %
45 22 PDSTB 08/26/95 --/--/--
4 0
g N
M85913 NEDE-32176-(P) - TRACG, MODEL (02/23/93) (03/13/93) (--/--/-- ) (09/01/97T) 849 345 9303030220 DESCRIPTION, 2/93.
SASG 03/20/93 03/28/97 62 118 SCSB 09/18/93 02/16/95C 7
SRXBC 03/13/93 09/01/97 773 166 SRXBC 04/08/95 03/24/97 7
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i Report Date 02/07/96 Topical Manager Report (condensed)
For GENERAL ELECTRIC 2
CZ PD]
Schedule Sch.
f)
Appl Act TR Action Act.
Rom.
Appl.
hj Task!D Rev.
Title Date Start Complete Complete Hours Nours Accession c3 l-M85915 NEDE-32178-(P) - APPLIC. OF TRACG MODEL (02/25/93) (03/20/93) (--/--/-- ) (11/24/97T) 555 560 9303030233 TO SRWR LICENSING SAFETY ANALYSES, 2/93.
SASG 03/20/93 08/22/97 46 152 SCS8 09/18/93 02/16/95C 7
SRMBC 03/20/93 11/24/97 498 348 SRN8C 04/08/95 03/24/97 5
60 i
F M87103 NEDE-32177-P - TRACG QUALIFICATION, REV (07/12/93) (08/28/93)
(--/--/-- ) (07/14/96T) 747 290 9307270022 1, JUNE 1993.
PER88 09/24/94 07/14/ %
9 0
g 00 SCSB 11/19/94 05/30/96 68 17 SRMBC 08/28/93 07/14/96 671 273 L
M87911 NEDC-31858-P, REV 2 - BWROG RPT FOR (09/01/94) (10/23/93)
(--/--/-- ) (03/31/96T) 220 16 INCREASING MSIV LEAKAGE RATE LIMITS &
ELIMINATION OC LEAKAGE CONTROL SYSTEMS DRPE 12/04/93 06/20/94x 1
ECGBA
--/--/--
10/04/94C 0
EMEBA 02/11/95 03/31/96 8
16 EMEBA 10/30/93
--/--/--H 127 0
PD11 10/23/93 05/27/94C 3
SCSB 12/17/94
--/--/--H 5
0 SPLBA 11/06/93 05/13/95C 76
+
l s
Report Date 02/07/ %
Topical Manager Report (Condensed)
For GENERAL ELECTRIC Schedule Sch.
Appl Act TR Action Act.
Rem.
Appl.
TaskID Rev.
Title Date Start Couplete Complete Mours Nours Accession I
l M89259 NEDC-32264, Rev 1 - APPLICATION OF PSA (02/03/94) (04/23/94) (--/--/-- ) (02/29/967) 383 5 9410120118 TO GL-89-10 IMPLEMEN-TATION (BWROG)
EMEB8 04/23/94 02/29/96 85 0
PD33 01/07/95
--/--/--H 58 0
SPSBB 04/23/94 02/29/ %
240 5
i i
M89629 NEDO-31331 - PROCEDURE GUIDELINES MODS (04/18/94) (06/18/94) (--/--/-- ) (10/06/97T) 1T/2 408 i
ADDRESSING ATWS STABLILITY ISSUE PERBB 08/06/94 10/06/97 4
0 SPLBA 08/06/94 08/05/94C 8
}
SPSBA 08/06/94 10/12/94X 30 g
O SPSBs 08/06/94 10/12/94X 15 SRXBA 06/1C/94 03/31/%
20 13 SRXBA 06/18/94 02/28/%
1181 31 SRXBA 06/18/94 02/29/%
3%
12 SRXBA 06/18/94 11/30/95C 52 SRXBC 09/30/95 10/06/97 66 353 M90468 NEDC-32339-P - REACTOR STABILITY (04/1&/94) (10/29/94)
(--/--/-- ) (03/01/%T) 168 8 9405250192 LONGTERM SOLUTION: ENHANCED OPTION 1-A (APPLICABILITY)
SRXBA 11/18/95 03/01/96 2
8 SRXBA 10/29/94 04/24/95C 92 7
SRXBA 07/29/95 01/31/96L 74 0
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Report Date 02/07/96 Topical Meneger Report (Condensed)
For GENERAL ELECTRIC CPD i
m Schedale Sch.
G) f, Appt Act TR Action Act.
Rom.
Appl.
[pj TeskID Rev.
Title Date Start Complete Complete Hours Hours Accession cp M91528 MFN-118 GE SAFETY LIMIT MCPR FOR GE (09/28/96) (04/01/95) (--/--/-- ) (12/22/97T) 1%
1 9410040252 13 FUEL (JKF 94-14)
SRMBA 12/02/95 02/29/96 24 1
SRxBA D4/01/95 12/22/97 172 0
M91680 NEDC-32424P - GENERIC GIUIDLINES FOR GE (02/24/95) (03/11/95) (--/--/-- ) (03/01/96T) 439 47 9503080407 BWR EXTENDED POWER UPRATE EMCBC 09/23/95 09/28/95C 5
EMEBA 04/15/95 12/31/95C 76 EMEBA 04/15/95
--/--/--H 2
0 HICBS 04/15/95 03/01/96 6
20 h3 c)
P031 08/12/95 --/--/--
144 0
PD31 03/18/95
--/--/--H 16 0
PDLRA
--/--/-- --/--/--
0 0
PERBB 12/30/95 --/--/--
2 0
PERBB 09/16/95 --/--/--
1 0
SCSS 04/15/95 01/11/96C 31
[
SPLBA 09/09/95 03/01/96 9
4 SPSBA 12/16/95 11/11/11X 2
SPSBB 12/16/95
--/--/--H 8
0 SRXBA 03/11/95 04/03/96 111 23 SRxBC 12/02/95 01/16/96C 27 1
l
Report Date 02/07/96 Topical Manager Report (Condensed)
For GENERAL ELECTRIC Schedule Sch.
Appl Act TR Action Act.
Rom.
Appl.
TasklD Rev.
Title Date Start Complete Complete Hours Mours Accession M92882 NEDO 32465 - REACTOR STABILITY DETECT (06/28/95) (07/15/95)
(--/--/-- ) (12/15/977) 90 23950f140107 AND SUPPRESS SOLUTIONS LICENSING BASIS METHODOLOGY AND REACTOR APPLICATION SRMBA 09/02/95 12/15/97 68 20 SRXBA 07/15/95 01/31/96L 22 3
M93279 NEDE-24011-P-A GENERIC METHODOLOGY (08/16/95) (08/26/95) (01/15/96C) (--/--/-- )
102 0 9303300067 CHANGE TO GESTAR SRxBA 08/26/95 01/15/96C 102 ro w
M93649 NEDO-32339, SUPPLEMENT 3 - REACTOR (08/21/95) (09/30/95) (--/--/-- ) (02/29/96T) 7 10 9508250291 STABILITY LONG-TERM SOLUTION: EhMANCED OPTION 1-A FLOW MAPPING METHODOLOGY SRXBA 09/30/95 02/29/ %
7 10 M94251 NEDo-32339, SUPP 4 - ENHANCED OPTION I-A (10/30/95)
(--/--/-->
(--/--/-- ) (03/31/MT) 0 50 GENERIC TECH SPECS SRXBA
--/--/-- 03/31/96 0
50
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Report Date 02/07/96 Topical Manager Report (condensed)
For SIEMENS 7
Ey Schedule Sch.
g Appl Act TR Action Act.
Res.
Appl.
y TasklD Rev.
Title Date Start Complete Complete Mours Mours Accession o
l M80400 ANF-90-145(P) VOLS 1 & 2 - RODEK3 FUEL (05/06/91) (08/07/93)
(--/--/-- ) (02/29/96T) 191 1 9104230075 l
R00 THERMAL-MECHANIC AL RESPONSE EVALUATION MODEL, ADVANCED NUCLEAR FUEL CORP SRxBA 08/07/93 02/29/%
191 1
M84245 EMF-92-116 P - GEMERIC MECHANICAL DESIGN (08/03/92) (05/07/94) (--/--/-- ) (02/29/96T) 127 2 9205050140 CRITERIA FOR PWR FLTL DESIGNS.
SRxBA 05/07/94 02/29/%
12/
2 NN M85182 EMF-92-139(P), VOL 1 - REALISTIC LOCA (12/01/92) (09/11/93)
(--/--/-- ) (10/20/97T) 42 433 9212040297 ECCS EVALUATION MODEL METHODOLOGY FOR PWR LARGE BREAK LOCA ANALYSIS, 12/92 SRxBB 09/11/93 10/20/97 42 433 M92881 EMF-95-084(P) - PWR NEUTRONICS DESIGN (06/19/95)
(--/--/--)
(--/--/-- ) (12/31/96T) 0 99 9506290221 CODE / CODE SYS EVAL & VALIDATION SRxBB
--/--/--
12/31/ %
0 99 M94336 EMF-1125, SUPP 1, APP C - ANFB CRITICAL (11/30/95)
(--/--/-->
(--/--/-- ) (12/31/%T) 10 73 9512050173 POWER CORRELATION APPLICATION FOR CD-RESIDENT FUEL SRxBA
--/--/--
12/31/%
10 73 i
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.m.
i Report Date 02/07/96 Toolcel MeneBer Report (Condensed)
For WESTINGNGUSE Schedule Sch.
Appl Act TR Action Act.
Rom.
Appl.
TaskID Rev.
Title Date Start Complete Complete Mours Mours Accession M61013 WCAP-10972-P - ABB ATOM-WESTINGHOUSE (01/29/86) (07/04/92) (--/--/-- ) (03/31/96T) 227 0 3602050335 CORRELATION FOR PREDICTING CPR MARGINS IN BWRs SRxBA 07/04/92 03/31/%
227 0
t t
M61712 WCAP-12945-P - WESTINGNOUSE CODE (08/31/91) (10/19/91) (01/31/95C) (03/30/96T) 321 0 9108150130 QUALIFICATION DOCLMENT FOR BEST l
ES11 MATE LOCA ANALYSIS EELBA
--/--/-- 09/30/93C 0
SaxBB 10/19/91 01/31/95C 321 ro GJ M82099 WCAP-10924-P-REV. 2-VOLUME 2-ADDENDUM 3 (04/30/91) (03/14/92) (--/--/-- ) (04/05/96T) 296 19 9104290088
- LARGE BREAK LOCA BEST ESTIMATE METHODOLOGY - UPPER PLENUM INJECTION MODEL SRxBB 03/14/92 04/05/%
296 19 M83964 WCAP-12945-P VOL 1, REV. 1 -
(06/10/92) (12/17/94)
(--/--/-- ) (10/20/97T) 1409 446 9206240140 WESTINGHOUSE CODE QUALIFICATION DOCUMENT FOR BEST ESTIMATE LOCA SASG 03/11/95 04/18/97 60 29 SRxBB 06/17/95 08/25/97 279 156 SRxBB 12/17/94 10/20/97 1070 262 7C cn G)8
Report Date 02/07/96 Topical Manager Report (Condensed)
For WESTINGNOUSE 7kQ Sche &te Sch.
6 Appl Act TR Action Act.
Rom.
Appl.
TeokID Rev.
Title Date Stsrt Complete Complete Mours Mours Accession c3 M84324 WCAP-13246-P & WCAP-13412-NP - W-GOTHIC, (07/31/92) (01/27/96)
(--/--/-- ) (12/31/96T) 22 672 9208040270 A COMPUTER CODE FOR ANALYSES OF THERMAL HYDRAULIC TRANSIENTS FOR NUCLEAR PL SCSB 01/27/ % 12/31/ %
22 672 l
M86764 WCAP-13749-P - SAFETY EVALUATION SUPPORT (06/01/93) (10/01/94)
(--/--/-- ) (11/10/%T) 340 8 9306080365 THE CONDITION EXEMP OF THE MOST NEGATIVE EOL MOD TEMP COEFFICIENT MEASURE SRXBA 10/01/94 11/10/%
3'O 8
m 4
M90784 WCAP-10054-P, ADO 2 & WCAP-10081-NP -
(08/31/94) (11/19/94)
(--/--/-- ) (10/22/%T) 157 59 9409080185 WESTINGHOUSE NOTRUMP SBLOCA MODEL SRXBB 11/19/94 10/22/%
21 19 SRXBB 08/05/95 08/24/95C 34 i
SRXBC 08/26/95 03/30/ %
31 40 SRXBC 11/25/95 10/22/ %
71 0
M91155 WCAP-13524-P, REV 1 - APPOLLO, A (08/24/94) (12/31/94)
(--/--/-- ) (12/31/96T) 61 150 9409140344 ONE-DIMENSl%AL NEUTRON DIFFUSION THEORY PROGRAM SRXBA 12/31/94 01/21/%X 25 SRXBB 01/20/96 12/31/ %
36 150 I
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Report Date 02/07/ %
Topical Meneger Report (Condensed)
-For WESTINGNOUSE
(
Schedule Sch.
l Appt Act TR Action Act.
Remi.
Appl.
Task!D Rev.
Title Date Start Complete Complete Hours Nours Accession M92312 WCAP-11992 - JOINT WEST. OWNERS 5/02/95) (05/20/95)
(--/--/-- ) (03/31/96T) 277 98 9505100058 GROUP / WEST. PROG: ATWS RULE ADMIN.
l PROCESS l
1 SPSes 06/24/95 OI/31/%
182 27 l
SRxas 05/20/95 03/31/ %
95 71 M93254 WCAP-14416/7-P/NP - WESTINGHOUSE SPENT (07/28/95) (09/02/95) (--/--/-- ) (09/15/96T) 126 53 9508080195 FUEL RACK CRITICALITY ANALYSIS METHODOLOGY SRxB8 09/02/95 09/15/ %
126 53 ru un M93299 WCAP-14404-P, METHODOLOGY FOR INCORP.
(07/26/95) (08/26/95) (--/--/-- ) (08/04/97T) 9 79 9508070096 HOT LEG N0ZZLE GAPS INTO BASH SRxBB 08/26/95 08/04/97 9
79 M93914 WCAP 8370, REV 12AR, QUALITY MGMT (09/15/95) (10/28/95) (--/--/-- ) (12/31/%T) 26 0 9509220218 SYSTEMS DOCUMENT, REV 1 HQM88 10/28/95 12/31/ %
26 0
M94005 WCAP-14181 - EVALUATION OF THE POTENTIAL (09/21/95) (01/27/ % ) (--/--/-- ) (12/31/%T) 12 61 9509260067 g
FOR DILUTING PWR SPENT FUEL TOOLS.
Q PD31
--/--/--
--/--/--
0 0
6 SPLBA 01/27/M 10/01/ %
12 61 w
40 O
Report Date 02/07/96 Topical Meneger Report (Condensed)
For WSTI-8K 7cNy Schedule Sch.
6 Appl Act TR Action Act.
Rom.
Appt.
y Taskt0 Rev.
Title Date Start Complete Ccaplete Mours -Mours Accession c3 et94035 WCAP-14449-P - APPLICATION OF BEST (08/31/95) (11/18/95)
(--/--/-- ) (12/31/96T) 2 242 9500070056 ESTIMATE LARGE BREAK LOCAMETHODOLOGY (WESTINGHOUSE PWR'S WITH UPPER PLEMUM INJECT SRMBB 11/18/95 12/31/96 2
242 M94337 WCAP-14219 & WCAP-14432 - av CLOSURE (10/27/95)
(--/--/-->
(--/--/-- ) (12/31/96T) 0 0 9511210166 MEAD LENETRATION SUPPLEMENTAL ASSESSMENT OF NRC SER ISSUES.
--/--/--
--/--/--
0 0
EMCBA
--/--/--
--/--/--
0 0
N I
M94338 WCAP-14483 - GENERIC METHODOLOGY FOR (12/01/95) (01/27/%)
(--/--/-- ) (12/31/MT) 6 58 9512080004 EXPANDED COLR.
SRXBB 01/27/% 12/31/ %
6 58 M94339 WCAP-14492/3 - VESSEL PENETRATION WELD (10/3' N) (10/28/95)
(--/--/-- ) (12/31/96T) 0 0 9512040352 REPAIR (PRESENTATION MATERIALS FROM 95 10 31 MTG)
EMCB 10/28/95 12/31/ %
0 0
Report Date 02/07/96 Topical Menager Report (Candensed)
For W STINGNEW5E Schedule
!<:h.
Appl Act TR Action Act.
Res.
Appl.
TeokID Rev.
Title Date Start Ceeplete Complete Mours Nours Accession l
M94340 WCAP-14545/6 - LASER WELDED SLEEVING (12/08/95) (10/28/95) (--/--/-- ) (12/31/96T) 0 0 9512130113 STATUS PRESENTATION MATERIALS FROM 951109 MTG.
Ence 10/28/95 12/31/ %
0 0
N N
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Report Date 02/07/96 Topical Meneger Report (Condensed)
For WESTINGNOUSE STEAM TURSINE-GENERATOR t
c:D m
Schedule Sch.
C)
Appl Act TR Action Act.
Rom.
Appl.
- oy TaskID Rev.
Title Date Start Complete Complete Mours Hours Accession c:>
t M65737 WSTG-4-P/NP - ANALYSIS OF THE (10/30/84)
(--/--/--) (--/--/-- ) (07/31/96T)
PRotA8!LITY OF THE GENERATION MISSILES I
FROM FULL INTEGRAL NUCLEAR LOW PRESSURE i
Total Nunber of Tasks =
67 fu CO l
I i
I l
6
-w
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION
- 1. REPORT NUMBER (2-89)
(Assigned by NRC, Add Vol.,
NRCM 1102, Supp., R3v., and Addendum Nurn-320n a202 BIBLIOGRAPHIC DATA SHEET bar8-
'f enY-)
(Se. instructuns on ine reverse)
NUREG-0390 Vol.10
- 2. mLE AND SUBTMLE Tbpical Report Review Status
- 6. AUiHO H(b)
- 6. TYPE OF REPORT Regulatory 7, PERIOD COVERED (inclusive Dates) 2/1/95 - 1/31/96
- 8. PERFORMING ORGANIZATION - NAME AND ADDRESS (11 NRC, provide Dmsson, Office or Region U.S. Nuclear Regulatory Corrmssion, and malling address; if contractor, provide name and malling address.)
Division of Inspection and Support Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING ORGANIZATION - NAME AND ADDRESS (if NRC, type "Same as above"; if contractor, provide NRC Divisloa, Offee or Region, U.S. Nuclear Regulatory Commission, and ma. ling address.)
Same as 8. above
- 10. SUPPLLMENTARY NOTES
- 11. ABSTRACT (200 words or less)
This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) processes and responds to topical report submittals, and an accounting, with review schedules, of all topical reports currently accepted for review by the NRC. This report is published annually.
- 12. KEY WOROS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.)
- 13. AVAILABILITY STATEMENT Unlimited
- 14. SECURITY CLASSIFICATION (This Page)
Unclassified (This Report)
Unclassified
- 15. NUMBER OF PAGES
- 16. PRICE
=
NRC FORM 335 (2-89)
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NUREG-0390Mol.10 TOPICAL REPORT REVIEW STATUS MARCH 1996 UNITED STATES NUCLEAR REGULATORY COMMISSION RRST MSS M POSTAGE AND FEES PAID WASHINGTON, D.C. 20555-0001 USNRC PERMIT NO. G-67 1 1AN 1205551 W3M OFFICIAL BUSINESS eVCS USNRC-0A{McVBLICATIONS PENALTY FOR PRtVATE USE, $300 h" pO -NU"E C' DC 2c555 waseint>To"
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