ML20003F520
| ML20003F520 | |
| Person / Time | |
|---|---|
| Issue date: | 04/10/1981 |
| From: | Zech G Office of Nuclear Reactor Regulation |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20003F521 | List: |
| References | |
| ACRS-GENERAL, NUDOCS 8104220242 | |
| Download: ML20003F520 (2) | |
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2 APR1'3 M b 2Co MEMORANDUM FOR: Raymond F. Fraley, Executive Director Advisory Committee on Reactor Safeguards
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Gary G. Zech, Chief Technical Support Branch 9
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Planning & Program Analysis Staff
SUBJECT:
NRR RESPONSES TO ACRS RECOMMENDATIONS FOLLOWING THE 246TH, 247TH, 248TH, a 249TH MEETINGS In response to your memoranda dated February 17, 1981, which sumarized Actions, Agreements, Assignments and Requests following the 246th, 247th, 248th, & 249th ACRS meetings, the following is provided on those items assigned to NRR.
246th Meeting 1.
Seismic Oualification of Auxiliary Feedwater Systems As discussed in our November 21, 1980 memo, the ACRS recommendations have been incorporated into the scope of the staff's review program in this areas.
2.
ACRS Coments on ATWS In a memo dated November 17, 1980, the staff provided its views regarding the reliability of the GE BWR/6 nuclear power plant high pressure injection system, as requested by the ACRS.
3.
Bingham Amendment By memo dated November 7,1980, the staff responded to the Committee's comments regarding the staff's plans for addressing the requirements i
of the Bingham Amendment.
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247th Meeting 1.
Diablo Canyon The list of items still outstanding regarding the issuance of an OL for Diablo Canyon and the status of each are provided in SER supplements 13 and 14 dated April 2,1981.
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2.
Indian Point 3 The staff met with the Indian Point 3 licensee on April 2,1981 to discuss the initial draft of its proposed systems interaction study.
A final version is expected from the licensee in mid-May 1981 after which an ACRS subcommittee meeting will be scheduled to discuss the plan along with an estimate of the man-rem doses that will result from the planned " walk through".
248th Meeting No follow-up action requested.
249th Meeting 2.
Sequoyah Containment Vacuum Breaker Valves The staff has not yet completed its review comparing the reliability of the Sequoyah containment vacuum breaker values with that of safety grade values.
It is intended that the review be completed sometime in June and prior to the next Sequoyah subcommittee meeting.
Gary G. Zech, Chief "echnical Support Branch Planning & Program Analysis Staff
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