ML19260B455
| ML19260B455 | |
| Person / Time | |
|---|---|
| Issue date: | 09/18/1979 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1666, NUDOCS 7912100195 | |
| Download: ML19260B455 (11) | |
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$&/S-H, u, DATE ISSUED: 9/18/79 l
MINUTES OF THE 1/ /y9 ACRS SUBCOMMITTEE MEETING ON REGULATORY ACTIVITIES AUGUST 8, 1979 WASHINGTON, D.C.
The ACRS Subcommittee on Regulatory Activities held a meeting on August 8, 1979, at 1717 H Street, N.W., Washington, D.C.
The purpose of this meeting was to review:
1.
proposed Regulatory Guides and Standards, 2.
revisions to existing Regulatory Guides and Standards, and 3.
other matters pertinent to activities that affeet the current-1Icensing process or reactor operations.
Notice of this meeting was published on Tuesday, July 24, 1979, in the Federal Register, Volume 44, Number 143; a copy is included as Attachment A.
Mr. Gary Quittschreiber was the Designated Federal Employee for the meeting.
A list of meeting attendees is included as Attachment B.
INTRODUCT0r" STATEMENT BY THE CHAIRMAN Dr. Siess, the Subconmittee Chairman, convened the meeting at 8:45 a.m.,
reviewed briefly the schedule for the meeting, Indicating that the Sub-ccmmittee will hold discussions with the EC Staff pertinent to the following:
1.
Proposed Limited Revision of Appendix J to 10 CFR Part 50, "Alr Locks".
2.
Proposed Regulatory Guide 1.136, Revision 2,
" Materials, Construction and Testing of Concrete Containments".
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Reg Ac:t Mtg 8/8/79 He noted that the Subcommittee had received neither wri den conments nor requests for time to make oral statements fran members of the public.
PROPOSED LIMITED REVISION OF APPENDIX J TO 10 CFR PART 50, " AIR LOCKS" Mr. Arndt reviewed briefly the need for the proposed revision to Appendix J, Indicating that the requirements delineated in Appendix J for leakage testing of containment building air locks are too narrowly and -lgidly defined for variety of air lock designs and operational situations. As a result, the NRC Staff has been granting exemptions to these requirements on a case-by-case basis in the licensing process since the implementation of Appendix J (February 14, 1973). The proposed re-visions to Appendix J reflect the current position of the NRC Staff on testing of air locks and these are expected to minimize er preclude granting of exemptions to Appendix J requirements.
In response to a question from Dr. Sless regarding the differences in the air-lock designs, Mr. Arndt stated that the design pressure at which the air lock could be tested will vary among various designs; some of the air lock designs Incorporate double seals at the doors and, in such designs, the tests could be conducted on the seals as compared to other designs where the test should be conducted on the chamber, in response to another question fran Dr. Sless as to what kind of penetrations employ continuous leakage monitoring system, Mr. Arndt stated that there are cer+3In penetrations which employ continuous leakage monitoring system; however, he is not sure of the exact type of penetrations which ase such systems He added further that the NRC Staff is giving further thought on the subject of continuous leakage monitoring system and they Intend to provide further clarification and guldance on this subject in the general revision of Appendix J.
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Reg Act Mtg 8/8/79 Stating that several of the Licensee Event Reports indicate that the failure and subsequent leakage of the air-lock seals were attributable to some foreign objects sticking at the seals, Dr. Sless asked whether there are any Technical Specifications or operating procedures to pre-vent such occurrences.
Mr. Arndt stated that tho"e is no information provided in the Regulations with regard to this issue ard they intend to discuss this with the group responsible for writing Technical Specifications and find a solution.
With regard to the Integrated leak rate test, Dr. Sless cernmented that since this test is conducted after f*ixing all the leaks prior to the test, he does not have much confidence in the results of this test and also he does not have a feel for the significance of this test. He asked whether any probabilistic study has been made to determine the probability, at a given time, that the leakage rate would be below the maximum permissible Iimit.
Mr. Arndt stated that he is not aware of any probabilistic study performed in this area. He believes that by performing Type B and Type C tests at frequent intervals, as required by the Appendix J requirements, and also by performing other tests in be+ ween the integrated leak rate tests, they may be able to telI whether the leakage rate le maintained within the maximum permissible vrlua.
In response to a question frcrn Dr. Siess as to whether any study of the Type S and Type C tests has been made to determine wnether the probability of the failure of Type C test on Isciation valves is much higher than that of the Type B test on penetrations or vice versa, Mr. Arndt stated that no such studies have been performed.
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Reg Act Mtg 8/8/79 In view of the fact that failure of the Tyoe B and Type C tests does not necessarily mean that there would have been leakage in the Integrated leak rate tests, coupled with the fact that the integrated leak rate test is required to be conducted once every 5 year period, Dr. Sless asked what function the integrated leak rate test serves.
Mr. Arndt stated that the Integrated leak rate test could detect gross degradation in some portion of the leakage barrier, such as the containment liner, that was not subjected to Type B or Type C tests; it could also detect leakage through penetrations 2nat had not been subjected to a Type B or Type C test. Overall, the integrated leak rate test gives the assurance that. things that were not covered by the Installed leakage testing methods have been covered.
Dr. Siess commented that, in view of the fact that the integrated leak rate test is to look at things tha't have not been subjected to a Type B er Type C test, it does not seem appropriate to fix the leaks through penetratI0ns or ' solation valves prior to making the Integrated leak rate
- test, it seems that either we are putting too much enphasis on the inte-grated leak rate test or we are not much concerned about how good it is.
There must be enough data from Type B or Type C tests to look at the Integrated leak rate test so that scraone could do somo kind of reliability-type study to say what the leak rate would be in betwoen Tests and with what confidence we can say it.
Mr. Arndt stated that the NRC Staff wculd compile data from existing test results and from Licensee Event Report: on failures so as to predict the frequency and magnitude of failures and the reasons for their failures.
They would also give considerstion to the suggestion by Dr. Sless during the general revision of Appendix J.
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Reg Act Mtg 8/8/79 Or. Sless stated that he believes that in the past few years the leak rate requirements changed significantly the structural design of the containments. He feels that sometimes the regulations have led to design changes that are not necessarily Improvements in real safety; they may be improvements in calculations which may or may not contri-bute to real safety. He stated that the ACRS may be Interested in hearing more about where we stand on leak rate tests and why, In one of the future ACRS meetings.
With regard to the pressure at which the integrated leak rate test is conducted, Mr. Arndt stated that there are some differences of opinion; one group believes that it should be conducted at the full calculated accident pressure and other group orefers conducting it at half the calculated accident pressure. Even though such controversy still exists, for the time being they prefer to conduct the Integrated leak rate test at full pressure.
Indicating that, during the discussion of the intag'O+ed leak rate testing at the ACRS-German meeting held t t Washinnton, D.C., the Germans pointed out + hat they do not havt-much confidence in the results of the tests onducted at low pressure, Dr. Sless suggested that the NRC Staf f take a look at the resort made at that meeting on the Integrated leak rate testing.
Indicating that the Integrated leak rata test conduc'ed at North Anna Unit I gave a negative leakage rate, Mr. Etherington asked about the NRC Staf f's opinion on that test.
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Reg Act Mtg 8/8/79 Mr. Arndt stated that he is not f amillar with the test conducted at North Anna Unit I.
He added that In the general revision of Appendix J,
- hey Intend to include only the criteria for the leakage testing; the technical aspects and procedures of conducting a test will be required to be in accordance with the procedures outlined in the applicable Industry standards.
Af ter further discussion, the Subcommittee Indicated that the NRC Staf f could issue this Guide for public comment.
PROPOSED REGULATORY GUIDE I.136, REVISION 2, " MATERIAL, CONSTRUCTION, AND TESTING OF. CONCRETE CONTAINMENTS" Regulatory Guide 1.136, Revision 2 describes soma bases acceptable to the NRC Staff for implementing its requirements with regard to the materials, construction, and testing of concrete containments. This Guide endorses with certain exceptions the " Code for Concrete Reactor Vessels and Con-tainments" (ASME Section 111, O! vision 2, 1977 or ACI Standard 359-1977).
This Guide is an expanded version of Regulatory Guide 1.136, Revision I whIch dealt with only Article CC-2000, " Material," of the Code. Revision 2 of this Guide provides Information regarding the NRC Statf's position on the acceptabilit / for licensing actions of the following Articles of the Code:
CC-1000, introduction CC-2000, Material CC-4000, Fabrication and Construction CC-5000, Construction Testing and Exaaination CC-6000, Structural Integrity Tests of Concrete Containment Structures CC-7000, Protection Against Overpressure.
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Reg Act Mtg 8/8/79 Witn regard +o Regulatory Position C-3, Dr. Sless asked whether it would be convenien* for the user of this Guide if the chemical requirements delineated II; Regulatory Guide 1.107 are conpletely spelled out here instigd of cross referencing Regulatory Guide 1.107 Mr. Arndt stated that the Contents of Regulatory Guide 1.107 being considered by the Code Committee may be included in a future addendum to the Code.
If in case the Code Committee makes some modifications and if they are acceptable to the NRC Staf f, the NRC Staf f will make changes to the Regulatory Guide 1.107; if the chemical requirements de-lineated in Regulatory Guide 1.107 are spelled out in Regulatory Guide 1.136, the NRC Staff has to make changes to both Regulatory Guides; thus, cross referencing of Regulatory Guide 1.107 for ensnical requirements precludes the possibility of making changes to Regulatory Guide 1.136.
With regard to the rock anchor problem (water intrusion into rocks),
Mr. Bender asked whether the Integrity of the rock anchors br: Deen properly controlled by regulations.
Mr. Arndt stated that the rock anchor issue is not covered in this Guide; he believes that some activities are currently going on, on this issue; but, he is not aware of all the details.
The Subconimittee suggested some editorial changes and Indicated that the NoC Staff could issue this Guide for pubile conment.
POSSIBLE CHANGES IN THE REGULATORY ACTIVITIES SUBCOMMITTEE'S PROCEDURES IN THE REVIEW OF ORAFT REGULATORY GUIDES in an attempt to reduce the Succommittee's and the NRC Staff's ef forts, Dr. Sless proposed the following procedures for the review of Regulatory Guides, especially those that are going out for public comment:
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Reg Act Mtg 8/8/79 1.
The Subcommittee Chairman will review the appropriate Regulatory Guides in advance and decide whether they are substantive enough to discuss in a meeting; while making the decision he will give consideration to several factors such as: are they controversial items 7; do they include matters of safety concern?; 1s there any public Interest (request for time to make oral statements or request to submit written comments for Subcommittee consideration) in a Subcommittee meeting?
If the Chairman decides not to have a meeting, copies of the appropriate Items will be distributed to the Subcommittee members and written conments, if any, will be solicited; thc e comments will be transmitted to the NRC Staf f for consideration.
2.
Itans that consist of controversial matters will be d!scussed in a Subcommittee meeting.
3.
If public participation (oral statements or written conments) is expected on certain items, they may be included for discussion in a meeting.
4 Items of safety concern will be discussed in a meeting.
These procedures will be tried on certa!n occasions on a case-by-case basis.
The NRC Staf f did not raise any objection to these proposed procedures.
FUTURC MEETING The NRC Staf f Ir.ulcated that they do not have any items for the Subcommittee's review at the September 5,1979 meeting.
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Reg Act Mtg 8/8/79 The meeting was adjourned at 10:10 a.m.
' NOTE: For additional details, a completo transcript of the meeting i s ava i l ab l e i n the NRC Pub l i c Document Room, 1717 H St., N.W.,
Washington, D.C. 20555, or from Ace-Fedaral Reporters, Inc.,
444 North Capital Street, N.W., Washington, D.C.
1519.._3.12..
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Federal Register / Vol 44. No.143 / Tuesday. July 24.19P9 f W 43375 Advisory Committee on Reactor
[, don licens.g acti
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,g, ses n SafeguardsMa.mee on Regulatory Activities; Meeting Persons wishing to submit written statements may do so by providing a ne ACRS Subcommittee on readily reproducible copy to the Regulatory Activities will hold an open Subcommittee at the begmning of the meeting on August 8.1979 in Room 1048, meeting. However, to insure thet in7 H St N.W Washington.DC E.
adequate time is available for full Notice of this meeting was published in consideration of these comments at the the Federal Register on June 27.1979 (44 meeting. It is desirable to send a readily FR 37568).
reproducible copy of the comments as in accordance with the procedures farin advance of the meeting as out!'ned in the Federal Register on practicable to Mr. Gary R.
October 4.1978 (43 FR 45926) oral or Quittschreiber, the Designated Federal written statements may be presented by Employee for the meeting in care of members of the public recordings will ACRS. Nuclear Regulatory Co:nmission.
be permitted only during those portions Washington, DC 20555 or telecopy them of the meeting when a transcnpt is being to the Designated Federal Employee kept and questions may be asked only (202-634-3319) as far in advance of the by members of the Subcommittee.its meeting as practicable. Such comments consultants. and Staff. Persons desiring shall be based upon documents ou file to make oral statements should notify and ave'lable for public inspect!:,n at the Designated Federal Employee as far the NRC Public Document Room. In7 H in advance as practicable so that Street. NW. Washington. DC 20555.
appropriate arrangements can be made Further information regW Mpics to allow the necessary time during the to be discussed, whether the meeting meeting for such statements.
,has been cancelled or rescheduled. the The agenda for subject meeting shall Chaien's ruling on requests for the be as follows: Wednesdoy. August 8.
opportunity to present oral statements 1979. The meeting willcommence at 8:45 and the time allotted therefor can be o.m.
obtair.ed by a prepaid telephone call to ne subcommittee will hear the Designated Federal Employee for presentations from the NRC Staff and this meeting. Mr. Gary R. Quittschttiber.
will hold discussions with this group (telephone 202/834-3267) between 8:15 pertinent to the following: (1) Proposed a.m. and 5:00 p.m EDT.
Regulatory Guide 1.136, Revision 2.
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" Materials. Construction,and Testias of Jeha C. Hop.,
Concrete Containn ents.
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Other matters which may be of a pedecisional nature relevant to reactor ATTACHMENT A 1519 313
ACRS SUBCOMMITTEE MEETING ON REGULATORY ACTIVITIES AUGUST 8,1979 WASHINGTON, D.C.
ATTENDEES LIST ACRS NRC C. P. Siess, Chairman S. Brown H. Etherington, Member J. Pulsipher W. M. Morrison W. Ker? Member W. F. Anderson M. Bender, Member G. Quittschreiber, Staff
- J. S. Ma S. Duraiswamy, Staff G. Arndt
- Designated Federal Employee EPRI ACRS CONSULTANT Leyse W. C. Lipinski BECHTEL POWER CORP D. Smehtz ATTACHMENT B 1519 314
.