ML20076E614
| ML20076E614 | |
| Person / Time | |
|---|---|
| Issue date: | 05/12/1983 |
| From: | Speis T Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| REF-GTECI-A-43, REF-GTECI-ES, TASK-A-43, TASK-OR NUREG-0869, NUREG-0869-FC, NUREG-0869-FC-ERR, NUREG-869, NUREG-869-FC, NUREG-869-FC-ERR, NUDOCS 8306010166 | |
| Download: ML20076E614 (5) | |
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May 12, 1983 ERRATA SHEET for NUREG-0869 For Comment USI A-43 RESOLUTION POSITIONS The attached Federal Register Notice was inadvertently omitted from the report.
DIVISION OF TECHkICAL INFORMATION AND DOCUMENT CONTROL 8306010166 830512 PDR NUREG 0869 R PDR
7590-01 j
l U. S. NUCLEAR REGULATORY C0t' MISSION NOTICE OF ISSUANCE AND AVAILABILITY "FOR COMMENT" 0F NUREG-0897 ENTITLED " CONTAINMENT EMERGENCY SUMP PERFORMANCE;"
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STANDARD REVIEW PLAN SECTION 6.2.2, REV. 4 ENTITLED,
" CONTAINMENT HEAT REMOVAL SYSTEMS;"
NUREG-0869 ENTITLED "USI A-43 RESOLUTION POSITIONS" The U. S. Nuclear Regulatory Commission (NRC) staff has prepared the following documents for public comment:
NUREG-0897 entitled, " Containment Emergency Sump Performance;" Standard Review Plan Section 6.2.2, Rev. 4, entitled, " Containment Heat Removal Systems;" and NUREG-0869 entitled, "USI A-43 Resolution Positions." NUREG-0869 contains a draf t of the proposed Regulatory Guide 1.82, Rev. I entitled, " Sump for Emergency Core Cooling and Containment Spray Systems;" the A-43 supporting Value/ Impact Statement and.
summaries of the Committee to Review Generic Requirements Meetings No's 26 and 28 pertinent to Unresolved Safety Issue (USI) A-43.
These documents, when issued in final form, will serve as the NRC staff's resolution of USI A-43, " Containment Emergency Sump Performance." This issue was identified as l
an Unresolved Safety Issue in the 1978 Annual Report pursuant to Section 210 of the Energy Reorganization Act of 1974.
The central issue of Unresolved Safety Issue A-43 is the capability of the containment emergency sump to provide an adequate water source to sustain long-term recirculation cooling following a loss-of-coolant accident. The NRC staff has completed its technical evaluation of this issue and these findings are reported in NUREG-0897. Based upon extensive experimental data t
and analysis, the NRC staff proposes that certain revisions be made to the current sump review guidelines to incorporate these findings. The necessary modifications are contained in the proposed revisions to Standard Review Plan, Section 6.2.2, and Regulatory Guide 1.82.
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. 7590-01 The proposed changes to Standard Review Plan, Section 6.2.2 and Regulatory Guide 1.82 amend requirements that are subject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq). The final proposed changes will be submitted to the Office of Management and Budget for review and approval of the paperwork requirements following receipt and review of "For Comment" responses.
Comments are being solicited from interested organizations, groups and individuals. The staff will evaluate the comments received and address them in the final documents.
It should be clearly noted that these "For Comment" documents are not to be used es interim requirements. The staff plans to hold public meetings to discuss these findings and proposed changes to SRP, Section 6.2.2, and Regulatory Guide 1.82 on June 1-2, 1983 at the U.S. Nuclear Regulatory Commission, 7920 Norfolk Avenue, Bethesda, Maryland.
Copies of the "For Comment" documents will be available after May 13, 1983. Copies will be sent directly to utilities, utility industry groups-and associations and environmental and public interest groups. Other copies will be available for review at the NRC Public Document Room,1717 H Street, NW, Washington, D.C.; and the Commission's Local Public Document Rooms located in the vicinity of nuclear power plants. Addresses of these Local Public Document Rooms can be obtained from the Chief, Local Public Document Room Branch, U.S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, telephone (301) 492-7536.
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I 3-7590-01
_ Connents should be forwarded in writing to Mr. Karl Kniel, Division of Safety-Technology, U.S. Nuclear Regulatory Commission, Washington, D.C.
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20555, by ;
July 11, 1983.
i FOR THE NUCLEAR REGULATORY COMMISSION i
d Themis P. Speis, Director Division of Safety Technology Office of Nuclear Reactor Regulation I
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I 120555078877 1 1ANIA111S1 US NRC ACM CIV 0F TIDC PCLICY 6 PUB MGT BR-POR NUPEG W-501 WASHINGTON DC 20555 SUMtiARY STATEMENT Notice Issuance "For Comment" is being made of the following documents: NUREG-0897,
" Containment Emergency Sump Performance;" Standard Review Plan, Section 6.2.2, I
Rev. 4, " Containment Heat Removal Systems," NUREG-0869, "USI A-43 Resolution Positions."
The U.S. Nuclear Regulatory Commission (NRC) has issued the above listed documents to obtain public and industry comment. NUREG-0897 contains the proposed Regulatory Guide 1.82, Rev.1, " Sump for Emergency Core Cooling and Containment Spray Systems;" and the supporting A-43 Value/ Impact Statement, and Summary of the Committee to Review Generic Requirements Meetings No's 26 and 28. NUREG-0869 contains the staff's technical findings relevant to the resolution of USI A-43.
Based on these findings, the NRC staff has proposed certain modifications to the current sump review guidelines (i.e.,
SRP Section 6.2.2, Rev. 4, and Regulatory Guide -1.82, Rev.1).
When these documents are issued in their final form, they will serve as the NRC staff's resolution of USI A-43, " Containment Emergency Sump Performance."
The proposed changes to Standard Review Plan Section 6.2.2 and Regulatory Guide 1.82 amend requirements that are subject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq). The final proposed changes will be submitted to the Office of Management and Budget for review and approval of the paperwork requirements following receipt and review of "For Comment" responses.
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