ML19269D027
| ML19269D027 | |
| Person / Time | |
|---|---|
| Issue date: | 08/28/1978 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| ACRS-CT-0817, ACRS-CT-817, NUDOCS 7902260599 | |
| Download: ML19269D027 (4) | |
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y f10 CLEAR REGULATORY COMMISSION L. *( '}; 'y ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
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WASWNGTON D. C. 20555
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August 28, 1978
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i E. G. Care, D2puty hirector Office of 1:uclear bgulation STATUS OF ACES RECOT'ENDATIONS As a folle.1 up to yr.ur memorandum of April 21, 1978 on the above sub-ject, the AciG StafI and Co.T.mittee tiembers have reviewed the comments of the 1;nC Staff relative to the reco.Taendations made by the Comit-tee during the perital January 1,1977 through September 30, 1977.
A suamary of the CGunittee's thoughts on significant items is attached for your appropriate action.
In the future, in cihlition to citing references to SER's, letters, etc.,
it would to helpful t o the Committee if you would state the action taken in resp;mco to the various recomendations.
i R. P. Fraley Executive Director
Attachment:
Coments on Staff Recomendations 790226057M
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00PREN'IS CN STAFF RECOV21f2;DATICk1S APPENDIX A 201st Meeting, January 6-8, 1977 1.
%e Ccanittee looks forward to receiving the Staff evaluation of the feedwater monitoring program. Feedwater piping vibra-tionc will be discussed at a future meeting of the Fluid Rjdraulics Subcomittee.
3.
W e resolution is acceptable for North Anna.
It is not clear how the North Anna resolution is to be translated into a generic reso-lution. Clarification is requested.
202nd Meeting, February 10--12, 1977 1.
We document referenced by Dr. Pbeller should have been proposed AtlSI Standard N13/42, " Performance Specifications for Reactor Ehergency Radiological Monitoring Instrumentation," (Tables 1, 2 and 3).
3.
It is not clear from the response what final action the NRC Staff has taken. Clarification is requested.
204th Meeting, April 7-9, 1977 la. %e response relative to pump flywheels is acceptable for the pres-ent, but there is no indication of the schedule for ultimate resolu-tion of this matter. 'Ibe Corraittee recommends that the Staff make quarterly reports until a technological solution to this problem is identified.
Ib. He Committee would like to be kept inforned regardire the develop cent and application of this probabilistic methodology to this subject.
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, APPENDIX A (Continued) 205th Meetirn, hay 5-6, 1977 1.
We St4ff reply is not responsive to the inquiry that addressed the procedures for identifying drawings and descriptive material that should be withheld from public disclosure. Apparently, the decision to withhold has been turned over to the Commission.
For the present information is being withheld on a proprietary basis. 'Ihe Committee is interested in the ground rules for estab-lishing what information should be withheld assuming that the pro-prietary alternative can be implemented. Se memorandum from Goller cuggests that the licensee will make judgements concerning informa-tion to be safeguarded.
It is not clear whether the NRC Staff has a basic for testing the licensees' judgement. Clarification is re-quested.
2.
Formation of a damage control team should receive consideration.
A fairly modest investment might lead to a considerable improve-rrent in response time and capability. An ACRS Subcommittee will follow up this response with a meeting to discuss the subject.
206th Meeting, June 9-10, 1977 2.
See response to 205th Meeting, item 2 (above) 208th Meeting, Aucust 11-13, 1977 2.
Se intent of this request was to be sure that open items identified for the PDA are addressed when the PDA is used in a construction permit application. he response is not clear on this matter; clari-fication is requested.
T 3.
According to our records we have not received a Staff response on this item.
209th Meeting, September 8-10, 1977 3.
It is at clear whether the premises described by Portland G. E.
with respect to failure to isolate containment is representative of the case in question. Se intent of the inquiry was to obtain an assess:r.ent concerning the habitability of a control room with degraded containment capability subsequent to an accident where radiation re-leases are a variable. For example, the intent was to determine whether a large number of fuel cladding failures coincident with a IDCA and par-tially ineffective containment closure could influence the habitability of control rooms. One approach might be to consider the effects of 14 fuel clad perforation, 5% fuel clad perforation, and 50% fuel clad perfor-ation as possible conditions conincident with a IOCA and incomplete con-tainment as a way of assessing control room habitability contingencies.
Ihc Cos11ttee woulo appreciate a responso on this matter.
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NRC FORM 318 (9 76) NRCM 0240 N u. s. ooVERNMENT PRINTING OFFICE: 3 978 = G28-824
I 3-APPENDIX B 201st Meeting, January 6-8, 1977 2b. h Committee recon:aends that the Staff provide guidance and a echedule for implementation of Reg. Guide 1.97.
2d. De Coc:riittee wishes to be kept informed regarding the results of the Licensee's reliability study, the Staff's evaluation of it, the final fix required and its generic implications, if any.
3a. We Comittee desires information regarding stress levela for various ctructures and components required for safe shutdown and long-term cooling presented in such a manner that the mar-gin against an increase in scismic stress can te determined.
203rd Meetir>g, March 10-12, 1977 2.
'Ibe approach suggested by the Staff concerning auxiliary system reliability might be a5 equate, but there is insufficient descrip-tive information to provide a basis for judgment.
It would be useful for the Staff to provide an illustrative example with ficti-tious data if no meaningful statistics are available as a way of displaying their approach to answering the question.
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NRC FORM 318 (9 76) NRCM 0240 W u. s. GOVE RN M ENT PRIN.
OFFICES 1978 - 826424