ML19275A857
| ML19275A857 | |
| Person / Time | |
|---|---|
| Issue date: | 08/28/1979 |
| From: | Hoyle J NRC OFFICE OF THE SECRETARY (SECY) |
| To: | |
| References | |
| ACRS-MA-0777, ACRS-MA-777, NUDOCS 7910190325 | |
| Download: ML19275A857 (8) | |
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0 777 d g N /h; Federal Register Notice ADVISORY COMMITTEE ON REACIDR SAFEGUARDS NUCLEAR REGUINIORY COMMISSION Notice of Meeting In accordance with the purposes of Sections 29 and 182b. of the Atomic Energy Act (42 U.S.C. 2039, 2232 b.), the Advisory Committee on Reactor Safeguards will hold a meeting e.1 June 14-16, 1979, in Room 1046, 1717 H Street, NW, Washington, DC.
Notice of this meeting was published on May 24,1979 (44 FR 30177).
The agenda for the subject meeting will be as follows:
Thursday, June 14, 1979 8:30 A.M. - 11:30 A.M.:
Executive Session (Open/ Closed) - The Committee will hear and discuss the report of the ACRS Chairman regarding miscellaneous matters relating to ACRS activities. A por-tion of this session will be closed to discuss classified information related to the operation of nuclear powered naval ships.
We Committee will hear and discuss the report of its Subcommittees on the status of the W ree Mile Island Nuclear Station and the implica-tions regarding nuclear power plant design of the tree Mile Island Nuclear Station Unit 2 Accident which occurred on March 28, 1979.
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. 11:30 A.M. - 1:00 P.M.:
Meeting with NRC Staff (Open) - The O
Comittee will meet with members of the NRC Staff to hear reports on the status of the tree Mile Island Nuclear Station Unit 2 and the NRC Staff evaluation of industry replies to I&E Bulletins 79-05,79-05A, 79-05B, 79-06,79-06A, 79-06B, and 79-08, NRC orders to the operators of Babcock and Wilcox nuclear plants, and NRC Staff action in response to ACRS recommendations regarding the March 28, 1979 accident at the Wree Mile Island Nuclear Station Unit 2 ('IMI-2).
2:00 P.M. - 2:30 P.M.:
Executive Session (Open) - The Committee will consider items to be discussed during its meeting with the NRC Comissioners including ACRS Interim Reporte No. 2 and No. 3 regarding implications of the March 28, 1979 accident at 'IMI-2, use of quantitative risk assessment as a regulatory basis, and the need for ACRS review of proposed regulations regarding transportation of spent nuclear fuel.
2:30 P.M. - 3:30 P.M.:
Meeting with NRC Comissioners (0 pen)
(Room 1130) - The Committee will meet with the NRC Commis-stoners to discuss items noted above.
3:0 P.M. - 4:00 P.M. : Executive Session (Open) - The Commit-tee will hear and discuss the report of its Subcommittee on Operating Reactors and consultants who may be present regard-1184 301
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. ing the request for an increase in power level for the Mill-stone Nuclear Power Station Unit 2.
Portions of this session will be closed if necessary to discuss Proprietary Information related to this matter.
4:00 P.M. - 5:30 P.M.:
Millstone Nuclear Power Station Unit 2 (open) - The Committee will hear and discuss presentations by members of the NRC Staff and the applicant regarding the request for an increase in power for the Millstone Nuclear Power Station, Unit 2.
Portions of this session will be closed if required to discuss Proprietary Information related to this matter.
5:30 P.M. - 6:30 P.N : Executiva Session (Open) -
'Ihe Committee will hear and discuss reports of its Subcommittees on matters related to nuclear power plant safety including pro-posed revisions to NRC Regulatory Guides, use of probabilistic assessment as a regulatory requirement and return to operation of the Fort St. Wain Nuclear station.
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e Friday, June 15, 1979 8:30 A.M. - 11:00 A.M.:
Meeting with Metropolitan Edison Company (Open) - The Committee will hear presentations by and hold dis-cussions with representatives of the Metropolitan Edison Company regarding the accident which occurred at 'IMI-2 on March 28, 1979, activities following the accident, and the current status of the plant. Portions of this session will be closed as required to discuss Proprietary Information related to this matter.
11:00 A.M. - 1:00 P.M.:
Meeting with Babcock and Wilcox Com-pany (open) - The Committee will hear presentations by and hold discussions with representatives of the Babcock and Wilcox Com-pany regarding NRC - I&E Bulletins No. 79-05 and 79-05A,79-05B; NRC orders to operating nuclear stations which make use of Babcock and Wilcox nuclear steam supply systems; and ACRS recom-mendations resulting from the March 28, 1C79 accident which oc-curred at 'IMI-2.
Portions of this session will be closed as required to discuss Proprietary Information related to this matter.
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. 2:00 P.M. - 5:30 P.M.
Meeting with NRC Staff (Open) - The Commit-tee will hear presentations by and hold discussions with members of the NRC Staff regarding recent operating experience and licens-ing actions including a failure c,f the condenser steam dump control valves to close following a load rejection at the Beaver Valley Nuclear Plant Unit No.1, replacement of reactor pressure vessel nozzles in the Duane Arnold Nuclear Plant, and cracking in the feedwater piping at the D. C. Cook Nuclear Station.
% e Committee will also hear a brief report from the NRC Staff re-garding inadequacies in the design of the piping of several nu-clear plants related to their ability to withstand seismic disturbances.
%e NRC Staff will also report to the Committee on NUREG-0531
" Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants" dated February 1979, and NUREG-0396, "A Modified Basis for the Developnent of State and Iocal Govern-ment Radiological Response Plans In Support of Light Water Nuclear Power Plants."
%e future schedule for ACRS activities will also be discussed.
5:30 P.M. - 6:30 P.M.
Executive Session (Open) - Discuss proposed ACRS connents and recomendations regarding 'IMI-2; implications of 1184 304
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. the accident at mI-2 on the design of nuclaar facilities, and the proposed power level increase for the Millstone Point Nuclear Pbwer Station Unit 2.
Saturday, June 16, 1979 8:30 A.M. - 4:00 P.M.:
Executive Session (Open) - The Comittee will discuss proposed ACRS coments and recommendations regarding MI-2; the implications of the accident which occurred at 'IMI-2 on March 28, 1979; and the requested power level increase for the Millstone Nuclear Power Station Unit 2.
'Ihe Committee will discuss proposed ACRS reports to NRC regarding the request for a Construction Permit for the Palo Verde Nuclear Generating Station Units 4 and 5, and an Operating License for the Sequoyah Nuclear Plant Units 1 and 2.
'Ihe Comittee will discuss proposed ACRS comments / positions regard-ing use of stainless steel fuel element cladding, stress corrosion cracking in nuclear power plant piping and a modified basis for development of radiological emergency response plans in support of light-water nuclear power plants.
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s s 'lhe Committee will continue discussion of other items considered during this meeting including regulatory and other deficiencies identified as a result of the March 28, 1979 accident at 'IMI-2.
Portions of this session will be closed as necessary to discuss Proprietary Information, provisions for physical security of the facilities involved, classified Information and matters involved i on adjudicatory proceeding.
Procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 4,1978 (44 FR 45926).
In accordance with these procedures, oral or written statements may be presented by members of the public, recordings will be permitted only during those portions of the meeting when a transcript is being kept, and questions may be asked,nly by members of the Committee, its con-sultants, and Staff. Persons desiring to make oral statements should notify the ACRS Executive Director as far in advance as practicable so that appropriate arrangements can be made to allow the necessary time during the meeting for such statements.
Use of still, motion picture and television cameras during this meeting may be limited to selected l
portions of the meeting as determined by the Chairman.
Information regarding the time to be set aside for this purpose may be obtained by a telephone call to the ACRS Executive Director (R. F. Fraley) prior to the meeting.
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. I have determined in accordance with Subsection 10(d) P.L.92-463 that it is necessary to close portions of this meeting as noted above to protect Proprietary Information (5 U.S.C. 552 b(c)(4)), to preserve the confidentiality of classified information and the arrangements for physi-cal protection of the Palo Verde, Sequoyah and Millstone nuclear plants (5 U.S.C. 552b(c)(1)) and to permit discussion of matters involved in an adjudicatory proceeding (5 U.S.C. 552 b(c)(10)).
Ebrther information regarding topics to be discussed, whether the meeting has been cancelled or rescheduled, the Chairman's ruling on re-quests for the opportunity to present oral stateraents and the time allotted therefor can be obtained by a prepaid telephone call to the ACRS Execu-tive Director, Mr. Raymond F. Fraley (telephone 202/634-1371), between 8:15 A.M. and 5:00 P.M. EDr.
(Date)
John C. Hoyle i
Advisory Committee Management Officer i
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