ML19260G291
| ML19260G291 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/03/1979 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-MS-0577, ACRS-MS-577, NUDOCS 7910170313 | |
| Download: ML19260G291 (2) | |
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231ST ACRS MEETING la# Un
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TABLE OF CONTENTS g
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JULY 12-14, 1979 I.
Ch a i rma n ' s R e p o rt...........................................
1 A.
R e v i e we rs...............................................
1 B.
Outstanding Follow-Up Items for ACRS' Consideration.....
1 C.
Assignment of ACRS Staff Member to Kemeny Commission Investigation.........................................
1 II.
Meeting on Bailly Generating Station Nuclear 1..............
2 A.
Sub c ommi t t ee R e p o rt.....................................
2 I
B.
Appl i ca nt 's Pres ent ati ons...............................
3 1.
Introduction........................................
3 2.
Pi l i ng De sc ri pt i on..................................
3 3.
Foundation Load Analysis............................ 4 C.
Status of NRC Staff Review..............................
4 III. Meeting on TMI-2 Implications...............................
5 A.
NRC Staff Presentation..................................
5 B.
Committee Action........................................
5 IV. Meeting on the NRC Research Program Budget..................
5 V.
Executive Session...........................................
6 A.
Activities of Members...................................
6 1.
Mr. L e w i s...........................................
6 2.
Mr. Okrent..........................................
6 B.
Future Schedule.........................................
7 1.
Agenda..............................................
7 2.
Subcommi ttee Acti vi ti es.............................
7 M/M 703/.3 9
Table of Contents s.
231st ACRS Meeting July 12-14, 1979 C.
Act i vi ti es of ACRS Consul ta nts.......................,...
8 8
- 1. (
4 m 3.o..................................
- 2. ~
J...........................................
8 4
D.
Subcommittee Reports....................................
9 1.
Evaluation of Licensee Event Reports........... ~....
9 E.
Hi story of Regul atory Requi rements......................
9 F.
EPRI Activities.........................................
9 G.
ACRS Reports and Letters................................
9 1.
Comments on the NRC Safety Research Program Budget..
9 2.
Research to Improve Reactor Safety..................
9 3.
Resea rch Request Requi reme nts....................... 9 4.
Bailly Generating Station, Nuclear 1................
10 5.
Response to Request from NRC/TMI Special Inquiry Group.............................................
10 11 9
c TABLE OF CONTENTS--APPENDIXES 231ST ACRS MEETING JULY 12-14, 1979 Appendix I - Attendees.......................................... A-1 Appendix II - Future Agenda..................................... A-8 Appendix III - Schedule of ACRS Subcommittee Meetings and Tours A-9 Appendix IV - Outstanding Follow-Up Items for ACRS Consideration A.11 Appendix V - Bailly 1:
Background for Investig: tion into Safety of use of Shorter Foundation Piles...............
A-21 Appendix VI - Bailly 1: Minutes of July 9,1979 Subcommittee Meeting.........................................
A-170 Appendix VII - Bailly 1: Written Statements from Members of the A-172 Pub 1'-
Appendix VIII - Bailly 1:
Foundation Criteria and Subsurface Soil Conditions...............................
A-186 Appendix IX - Piling Description and Subsoil Corrective Program A-191 Appendix X - Bailly 1:
Mat Pile Load Analysis..................
A-213 Appendix XI - Status Report on THI-2 Recommendations by ACRS... A-218 Appendix XII - TMI-2 Lessons Learned:
Short-Term Recommendations A-248 Appendix XIII - Small Leaks Experiments........................
A-251 Appendix XIV - Review of LERs by ACRS Fellows..................
A-252 Appendix XV - Comments on the Safety REsearch Program Budget...
A-265 Appendix XVI - Research to Improve Reactor Safety..............
A-310 Appendix XVII - Research Request Requirements..................
A-315 Appendix XVIII - Bailly Generating Station, Nuclear 1..........
A-316 Appendix XIX - Significant ACRS Recommendations, in Selected Areas, Made for Non-B & W Plants Prior to March 28, 1979................................
A-319 Appendix XX - Additional Documents for ACRS' Use...............
A-498 iii
i.
373!,0 Federal Register,'
A. 44. No.124 / Tuesday June 26,1976 Notices
~
De Committee will discuss its De agende for subject meeting shall ' discuss its proposed. annual report be as follows:
regarding the adequacy of this program, proposed annual report regarding the adequacy of the NRC Safety Research 2:N P.M-(# P.M.: Executive Session Program.
Wednesday.]uly 11.1s79 (Open) -he Committee will hear and De Cornmlun wiH discun no AJO o.m. untilthe conclusion of discuss the reports of its Subcommittees schedule for future activities.
business on the NRC Safety Research Program Portions of this sessior will be closed
%e Subcommittee m j meet in and discuss its propaed enrxa! report as necessary to discuss Proprietary Executive Session, with any of its regarding the adequacy of this program, Inf mauon.
d5nsultants who may be present, to ne Committee will hear and discuss Procedures for the conduct of and explore and exchange their preliminary the report ofits Subcommittee on the participation in ACRS meetings were opinions regarding matters which should Implications of the March 28,1979 published in the Federal Register on be considered durmg the meeting and to accident at the %ree Mile Island October 4.1978 (44 FR 45926). In formulate a report and Nuclear Plant Unit 2.
. acc rdance with these procedures oral recommendations to the full Committee.
He Committe? will hear and discuss or written statements may be presented At the conclusion of the Executive the report ofits Subcommittee on the by membere of the public, tecordings Session. the Subcommittee will bear BaiUy Genersting Station Nuclear 1 will be perm.ttted cnly dunng those I
pre entations by and hold discussions regarding proposed changes in the piling p rti ne f d.e meeting when a with representatives of the NRC Staff, configuration at this plant.
transcript is being kept, and questions and their consultants, pertinent to the as necusan to &, session will be closed may be asked only by members of the Pordons oms above topics. The Subcommittee may scuss PmprietarY Committee,its consultants, and Stef!.
then caucus to determine whether the Inf rmation related to this matter.
Persons desiring to make oral matters identified in the initf gl session A30P.M-7NP.MrBailly Generating. statements should notify the ACRS have been adequately covered and whether the project is ready for review Station Nuclear 1(Open)-The Executive Director as far in advance as Committee will hear and discuss practicable so that appropriate l
by the full Committee.
presentations by members of the NRC arrangements can be made to ellow the -
Further information regarding topics to be discussed, whether the meetmg Staff and the applicant re8edmg the neessary time during the meeting for has been cancelled or rescheduled, the request for a change in the piling design auch statements.Use of still, motion Chairman's ruling on requests for the for this plant.
picture and television cameras during opportunity to present oral statements Portions of this session will be closed this meeting may be limited to selected and the time allotted therefore can be if required to discvu Proprietary portions of the meethg as detemined by obtained by a prepaid tefephone call to information related to this matter, the Chairman. Information regarding the time to be set aside for dus purpose may the Designated Federal Employee for Friday, July 13,1979 be obtained by a telephone call to the this meeting. Dr. Richard P. Savio ACRS Executive Director (R.F. Fraley)
(telephone 202/634-3267) between 8:15 A30 A.M-12:30 P.M. Executive a.m. and 5:00 p.m. EDT.
Session (OpenJ-ne Committee will prior to the meeting.
I have determined in accordan e with discuss its proposed annual report Subsection 10(d) p.1.92-463 that it is Dated. june 21.tir?9.
regarding the adequacy of the NRC necessary to close portions of this Joh2 C Hoyle, Safety Research Program.
snecting as noted above to protect Admory Committee Management Officer.
2:30 P.M-d.30 P.M: Executive Session Pmprietary Infomation (5 U.S.C.
pnon.,,.s,uru m sine. 4 (O en)--The Committee will discun the 552b(c)(4)).
P sumo coor riew-m views of its members and consultants Further information regarding topics regarding the basic causes contributing to be discussed, whether the meeting Adytaory Committee on Reactor to the March 28.1979 accident at the has been cancelled or rescheduled, tie Safeguards Nuclear Regulatory Three Mile Island Nuclear Plant Unit 2.
a nnade ruhng on mqunts for the Commisalon; Westin9 De Committee will hear and discuss op u y to pent oral statements in accordance with the purposes of the report ofits Subcommittee and e ime a otted therefor can be a( *[CRS discuss a proposed ACRS report to the
'd p pa d * 'p call to Sections 29 and 182b. of the Atomic NRC regarding its esvalus tion of u
D t
Energy Act (42 U.S C. 2039. 2232 b.). the Licensee Event Reports resulting from Raymond F. Fraley (telephone 202/834-Advisory Committee on Reactor nuclear power plant operations.
Safeguards will hold a meeting on July h*), between 8:15 A.M. and 5:00 P.M.
12-14.1979. In Room 1046.1717 H Street.
The Committee will discuss a NW. Washington. DC. Notice of this proposed reper' to the NRC regarding Dsted: June 21.1979.
meeting was published on May 24.1g79 reevaluation of pnmary system integnty (44 FR 30177).
based on operating experience at John C Hoytw The agenda for the subject meeting nuclear facihties.
Advisory Committee Management Officer.
ps on. vo.ie sa md S.ason au w Will be as follows:
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Thursdey. july 12,1979 8:30 A.M-HO P.M: Enecutive A30 A.M-12:30 P.M: Enecutive Session (Open)-The Committee will Advisory Committee on Reactor Session (Open)-The Committee will discuss proposed ACRS commenta and Safe 9uards Subcommittee on Fr" and discuss the report of the ACRS recommendations regarding sne Advanced Reactora; Meeting Chairman regardmg miecellaneous implications of the accident which metters relating to ACHS activities.
occurred at TMl-2 on March 28,197R The ACRS Subcommittee on he Committee will hear and discuss and the proposed change in piling Advanced Reactors will hold an en the reports of its Subcommittees on the configuration at the Bailly Generating meeting on July 11.1979 in Room 4203'.,
NRC Safety Resesich Program and Station Unit 1.
New Executive Office Building.17th St 2%XAMS
km #E0p9 e
UNITED FIATES l
- g NUCLEAR REGULATORY COMMISSION j
I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS z
WASHINGTON, D. C. 20555 e$
gj July 3,1979 SCHE:DUII AND OlfrLINE FOR DISCI'SSION 231ST ACRS Meeting July 12-14, 1979
- SHIR~ ION, DC Wursday, July 12, 1979, Room 1046, 1717 H Street, NW, Washirnton, DC 1) 8:30 A.M. - 12:30 P.M.
Executive Session (Open) 1.1) 8:30 A.M. - 9:00 A.M.- Chair-man's Reprt 1.2) 9:00 A.M. - 12:30 P.M.:
Dis-t cuss proposed ACRS report on the NRC Safety Research Pro-gram 12:30 P.M. - 1:30 P.M.
IUNCH 2) 1:30 P.M. - 6:30 P.M.
Executive Session (Open) 2.1) 1:30 P.M. - 4:00 P.M.:
Dis-cuss proposed ACRS Annual Repart on the NRC Safety Research Program 2.2) 4:00 P.M. - 6:00 P.M.:
Dis-cuss proposed ACRS report to NRC on implications of the March 28, 1979 accident at the %ree Mile Island Nu-clear Plant Unit 2 2.3) 6:00 P.M. - 6:30 P.M.:
Re-port of ACRS Subete. on Bailly Generating Station Nuclear 1 (Portions of this session may be closed if necessary to discuss Proprietary Information related to this matter.)
3) 6:30 P.M. - 7:30 P.K.
Bailly Generating Station Nu-clear 1 (Open)
(Portions of this session may be closed if necessary to discuss Proprietary Information related to this matter.)
9
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Friday, July 13,1979, Rcom 1046,1717 H Street, NW, Washington, DC Executive Session (Open)
- 4) 8:30 A.M. - 12:30 P.M.
4.1) Discuss proposed ACRS an-nual report on the NRC Safety Research Program UJNCH 12:30 P.M. - 1:30 P.M.
Executive Session (Open) 5)
1:30 P.M. - 6:30 P.M.
5.1) 1:30 P.M.-4:00 P.M.:
Dis-cuss underlyiry causes con-tributing to the 'IMI-2 ac-cident 5.2) 4:00 P.M. - 6:00 P.M.:
Discuss proposed ACRS report en Licensee Event Reports 5.3) 6:00 P.M. - 6:20 P.M.:
Dis-cuss proposed ACRS report to NRC regarding pipe cracking in Boiling Water React. ors Saturday, July 14, 1979 Room 1046, 1717 H Street, NW, Washington, DC Executive Session (Open) 6)
8:30 A.M. - 4:00 P.M.
6.1)
Discuss proposed ACRS re-ports on:
NRC Safety Research Pro-gram
'INI-2 Accident Implica-tions Bailly Generating Sta-tion Nuclear 1 Pipe Cracks in BWR's (Portions of this session may be closed if necessary to discuss Proprietary Information related to the Bailly Generating Station.)
6.2)
Future schedule for ACRS activities 6.2-1) Anticipated Sub-committee activity 6.2-2) Anticipated full Com-mittee activity
t Issue Date: SEP 101979 MINUTES OF THE
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j[3 i
231st ACRS MEETING l
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July 12-14, 1979 i
[
(( gh The 231st meeting of' the Advisory Committee on Reactor Safeguards, held at 1717 H Street N.W., Washington, DC, was convened at 8:30 a.m., Thursday, July 12, 1979.
[ Note:
For a list of attendees, see Appendix I.
Mr. Lawroski was not present on Saturday.]
The Chairman noted the existence of the published agenda for this meeting, and the items to be discussed.
He noted that the meeting )was being held in confonnance with the Federal Advisory Committee,Act (FACA and the Govern-ment ir. the Sunshine Act (GISA), Public Laws92-463 and 94-409, respectively.
He notea that no requests had been received from members of the public to l
He also noted that copies of the transcript of some pre 3ent orcl statements.
of the publir portions of the meeting would be available in the NRC's Public Document Room at 1717 H Street N.W., Washington, DC, within approxnmately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
[ Note:
Copies of the transcript taken at this meeting are also available for purchase from Ace Federal Reporters, Inc., 444 North Capitol Screet N.W.,
Washington, DC 20001.]
1.
Chairman's Report (0 pen to Public)
[ Note:
Ravmond F. Fraley was the Designated Federal Employee for this portion of the meeting.]
A.
Reviewers The Chairman named Messrs. Kerr and Shewmon as reviewers for the 231st ACRS Meeting.
B.
Outstanding Follow-Up Items for ACRS' Consideration The Chairman r.oted that R. F. Fraley's memorandum of June 28, 1979, Outstanding Follow-Up Items for ACRS Consideration (see Appendi x IV) contains changes of priorities that reflect Member's comments.
C.
Assignment of ACRS Staff Member to Kemeny Coninission Investigation The Chairman noted that a request was received from W. R. Stratton, who is serving as a consultant to the Kemeny Commission investigat-accident and its implications, for assignment of a Ing the TMI senior ACRS Staff member to compile information regarding the significance of major nuclear accidents for transmission to the
. 9
MINUTES OF THE 231ST ACRS MEETING July 12-14,1979 Kemeny Commission.
The Committee declined to approve
- such assign
- ment, and suggested that this infonnation could better be obtained I
from a national laboratory.
II. Meeting on Bailly Generating Station Nuclear 1 (Safety Issues Relating to Use of Shorter Piles) (0 pen to Public)
[ Note:
Ragnwald Muller was the Designated Federal Employee for this portion of the meeting.]
A.
Subcommittee Report Mr. Lawroski, Subcommittee Chairman, discussed the background for this particular review (see Appendix V).
He reported on the findings of the subcommittee meeting held on July 9, 1979 (see Appendix VI).
He concluded that the issues revolve about whether subsoils disturbed by jetting of several piles can be restored to a compact state.
He noted receipt at the subcommittee meeting of written statements from 5 members of the public (see Appendix VII),
and 1 oral statement.
F. E. Richart, ACRS Consultant, noted that the NRC Staff has not completed its review.
He commented that e
The soft spots observed in the 6reas where piles have been jetted, are disturbed zones.
The use of 10" diameter compac-tion piles seems appropriate to remedy the ccndition.
He recommended rapid field monitoring, using a Dutch Cone Penetrometer,be carried out both before and after piles are set.
Dynamic earthvlrke stresses in the piles nee 6 to be compared e
with the ultimate bearing capacity of the piles, e
Load tests should be carried out to failure The Chairman noted that a telephone call was received from Mr. G.
M. Wilson, United Steel Workers, asking the Committee to compare the foundations of the near-by Bethlehem Steel Plant with the proposed foundations of the safety-related structures of Bailly.
In discussing the question of settlement of builidings at the near-by Bethlehem Steel Plant, F. E. Richart said that the steel plant is founded on spread footings, not pilings.
This type of foundation has no relationship to nuclear plant design.
On that basis, the settlement history of the steel plant may be discounted. e
MINUTES OF THE 231ST ACRS MEETING July 12-14,1979 R. E. Scott, ACRS Consultant, noted that he has made cciculation>
of settlement for the proposed reactor buildings.
He suggested that the applicant, or the applicant's consultants, meet with him to discuss his calculations.
B.
Applicant's Presentations 1.
Introduction R. Bohn, Northern Indiana Public Service Company (NIPSCO) discussed the design criteria as stated in the Bailly Prelimi-nary Safety Analysis Report (PSAR) and discussed sub-surface soil conditions (see Appendix VIII).
He noted that the fossil fuel plants located on the Baily site are founded on concrete mats, rather than piles, and have shcwn only 2" of settlement.
2.
Piling Description M. Kiefer, Dames and Moore, applicant's consultant, discussed the pile design, focused on subsoil conditions and studies performed to demonstrate that high-capacity non-displacement piles founded in the interbedded glacial lacustrine deposits located at tne Bailly site are a viable foundation system, and described a generic corrective program for disturbed subsoils (see Appendix IX).
T. McKenna, Sargent and Lundy, said that no change of building design will be required because of the substitution of the shorter piles for the longer piles.
He said that the building response will be analyzed for the short pile system.
J. Paulsea, Sargent and Lundy, sa.d tnat 21 points on Cate-gory-I s cructures will be monitored.
The criteria for this monitor'ng have not been identified yet.
With rsgard to the effects of settlement, T. McKenna said that by the time the piping is attached to the buildings, the major porticn of the settlement will have taken place.
The connec-tion of the essential service water piping to the main building complex is not needed until construction is well advanced. The piping design allows for up to 3" of settlement.
The Cate-gory-I buildings will be constructed on an inter-connected-mat system, and therefore there should not be differential settle-ment between buildings.
MINUTES OF THE 231ST ACRS MEETING July 1E-14, 1979 In answer to a question, M. D. Lynch, NRC Staff, said that the Bailly Technical Specifications will include settlement crite-ria.
3.
Foundation Load Analysis A.
K.
Singh, NIPSCO, discussed the details of the proposed mat-pile load analysis (see Appendix X).
C.
Status of NRC Staff Review M. D. Lynch reported on the NRC Staff review of settlement damage to Bethlehem Steel Company's buildings at their Burns Harbor plant, adjacent to the Bailly site, and noted that the foundation methods were different and unrelated to those proposed for Bailly.
There-fore, there would be no basis for comparison of the settlement at Bethlehem.
M. D. Lynch said that the NRC Staff believes that the proposed densification piles would have a high probability of redensifying the disturbed subsoils.
Further, the NRC Staff does not believe that the shorter pilings represent a significant safety issue.
M. D. Lynch said that he had a recent conversation with G. Wilson, United Steel Workers, regarding the damage to Bethlehem Steel's buildings, and Wilson's fears of similar settlement damage at Bailly.
He said that Wilson admitted to not being familiar either with the requirements for foundations, or with the method used to provide foundations for the Bethlehem Steel plant.
In answer to a question, M. D. Lynch said that the NRC Staff will require load testing of the piles.
R. Bohn said that the applicant has already committed to load testing the piles in the disturbed zones.
G. H. Cunningham, NRC Staff, noted that the next step in this proceeding, following receipt of the' Committee's report, will be for the NRC Commissioners to determine whether or not a public hearing will be held regarding this matter.
4-
MINUTES OF THE 231ST ACRS MEETING July 12-14, 1979 III. Meeting on TMI-2 Implications (0 pen to Pubif c)
[ Note:
Richard K. Major was the Designated Federal Employee for this portion of the meeting.]
A.
NRC Staff Presentation R. Mattson provided a status report regarding NRC Staff actions relating to TMI-2 follow-up recommendations made by the Committee (see Appendix XI), and discussed the short-term recommendations regarding operations and design ard analysis (see Appendix XII).
These recommendations are intended to apply to operating plants and those plants nearing construction completion.
B.
Committee Action l
The Committee considered a proposed draft of an interim report on the implications of the TMI-2 accident, and transferred a number of items from this proposed report to the Committee's report comment-ing on the NRC Safety Research Program budget (NUREG-0603).
The Committee agreed to defer further action on the interim TMI-2 accident implications report in order to provide adequate time for the completion of NUREG-0603.
IV. Meeting on the NRC Research Program Budget (0 pen to Public)
[ Note:
Thomas G. McCreless was the Designated Federal Employee for this portion of the meeting.]
The Committee met with members of the Office of Reactor Reguletory Research to further discuss matters relating to the proposed supplemen-tary research budget for FY 1980 and the proposed budget for FY 1981, prior to the Committee's preparation of its Comments on the NRC Safety Research Program Budget (N9 REG-0603) (see Appendix XV).
S. Levine, NRC Staff, noted that some of the projects included in these budgets are not fully defined, therefore information on them may be scanty. He suggested that the Committee can update its comments cn the projects relating to 1981 during the preparation of the Committee's annual report to Congress on the NRC Research Program.
He also stres-sed that many of the current programs also included in the 1981 budget have been developed for a number of years, even before the existence of the NRC.
Currently, necessary and useful data from these programs are being obtained, and he recommended that these programs be continued.
He also said that the NRC Staff has learned of some gaps in the re-search program as a result of the studies of the TMI-2 accident, and that additional work to fill these gaps is being proposed.
This is
.s.
MINUTES OF THE 231ST ACRS MEETING July 12-14, 1979 especially true of the accident spectrum between anticipated transients, and core melt.
The NRC Staff is working to develop new codes, and these codes will have to be evaluated and verified.
Additional re-sources have been requested to do this.
L. S. Tong, NRC Staff, identified the planned experiments on small.
break LOCAs (see Appendix XIII).
S. Levine noted that a meeting is scheduled in the near future between the Office of Management and Budget, Department of Energy, and the NRC to resolve the current dichotomies in safety research.
He agreed with the Committee opinion that not enough effort has been expended in this area.
With respect to fast breeder reactors, S. Levine noted an increase in the FY 1981 budget.
He said that not only is the research needed, but that the program is begining to lose capable people because of poor morale resulting from reduced work.
He noted that foreign countries are going ahead with fast breeder reactors, and offered the opinion that the United States must follow suit. Areas of current interest are in trcnsients and 'small-break LOCA analysis, enhancement of operating capabiiity, and post-accident and plant recovery.
Mr. Siess recommended procedures for a sequential approach for the preparation of the report.
The Committee accepted these recommenda-tions.
V.
Executive Session (0 pen to Public)
[ Note:
James M. Jacobs was the Designated Federal Employee for this portion of the meeting.]
A.
Activities of Members 1.
Mr. Lewis The Committee offered no objection to Mr. Lewis' testifying before a legislative committee of the Arizona legislature on the subject of the role of nuclear energy in society.
2.
Mr. Okrent The Committee offered no objection to Mr. Okrent's testifying before the House Committee on Science and Technology, Subcom-mittee on Science, Research, and Technology, on the subject of risk-benefit analysis in the legislative process..
C~
MINUTES OF THE 231ST ACRS MEETING July 12-14, 1979 B.
Future Schedule 1.
Agenda The Committee agreed on a general future schedule (see Appendix II) and also on the following tentative agenda for the 232nd ACRS Meeting (August):
Relationship of the ACRS Annual Report to Congress on the NRC Safety Research Program vis-a-vis the ACRS report to the NRC regarding the NRC Research budget TMI-2, Interim Report 4 ACRS Report on the Evaluation of LERs Lacrosse BWR Subcommittee Report Salem 2 Nuclear Generating Station / Westinghouse Nuclear Plants -- OL NUREG-0396, Emergency Response Plans TMI-2 -- Underlying Causes Generic Items -- Evaluation and Prioritization ATWS Pipe Cracking in BWRs -- Proposed Report The Committee agreed to defer its review of the molten core retention ladle proposed for the Floating Nuclear Plant pending consideration of additional items to be identified by Dr.
Okrent.
The Committee agreed that it be briefed on NUREG-0396, Modified Basis for Development of Emergency Plans by State and Local Governments in Support of Light-Water Reactors.
2.
Subcommittee Activities A schedule of future subcommittee activities was provided to the members (see Appendix II).
The Chairman noted that he would chair the next TMI-2 Implica-tions Subcommittee Meeting to be held on Wednesday, August 8,
,v'
MINUTES OF THE 231ST'ACRS HEETING July 12-14, 1979 in Washington, DC, at 1:00 p.m.
He proposed the following*
subjects for discussion:
0 the scope of review in the regulatory process, e
the ACRS role, e
the role of NRC inspectors, e
the NRC role with respect to operator training and qualifi-
- cations, e
procedures for evaluation and application of operating experience, e
depth of knowledge in the NRC Staff (e.g., materials chemistry, hardware, plant behavior, etc.),
e NRC responsibilities / procedures during emergencies, and e
NRC-state government relations for emergencies.
The Committee agreed that lessons learned from the TMI-2 accident relating to Wsstinghouse plants should be considered on a generic basis by the Salem Subcommittee during its review of the Salem 2 Operating License application.
Chairmen of the TMI-2 Accident Implications and Westinghouse Plant subcommit-tees that may be affected by the " lessons learned", were specificaly invited to attend the Salem Subcommittee on July 27, 1979.
C.
Activities of ACRS Consultants
- 1. f
+
7 It was noted that the ACRS Consultant /
- 1 l has accepted a contract to consult with f 4, on lessons learned from TMI-2.
He is not consulting with the Committee wit'n respect to TMI-2.
It was the consensus of the Committee that no problem exists.
- 2. f 1+
/
Itwasnotedthatthe[
u
/is bidding on NRC contracts regarding studies of containment buckling and of evaluation of 1500 outstanding LERs.
The Office of the General Counsel has indicated that currently no conflicts exist.
e
MINUTES OF THE 231ST ACRS MEETING July 12-14,1979 However, the Committee recognized that conflicts coald develop,'
and recommended tht the ACRS Staff consider engaging additional consultants with/
4
' skills.
D.
Subcommittee Reports 1.
Evaluation of Licensee Event Reports Mr. Moeller briefly reviewed the status of the subcommittee's review of Licensee Event Reports for the years 1976-1978.
He recommended that the Committee prepare its report on this matter at the 232nd ACRS Meeting (August).
I Several members commented on the proposed plan for ACRS Fellows to review current Licensee Event Reports (see Appendix XIV).
Implementation was deferred.
E.
History of Regulatory Requirements The Committee authorized the ACRS Executive Secretary to arrange for copies of Mr. Okrer.t's paper on the history of selected regula-tory requirements to be printed for distribution to Members, ACRS Staff, and others.
F.
EPRI Activities The ACRS Staff was requested to provide Members inform:: tion regard-ing EPRI plans to establish a Nuclear Safety Analysis Center (NUSAC) ind a Nuclear Operations Institute.
G.
ACRS Reports and Letters 1.
Comments on the NRC Safety Research Program Pzfget The Committee completed its report, Comments on the NRC Safety Research Program Budget (NUREG-0603) (see Appendix IV).
2.
Research to Improve Reactor Safety The Committee prepared a report, Research to Improve Reactor Safety (see Appendix XVI).
3.
Research Request Requiremer.ts The Committee prepared a letter to the Commissioners regarding research request requirements (see Appendix XVII). 9
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MINUTES OF THE 231ST ACRS MEETING July 12-14, 1979
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4.
Bailly Generating Station, Nuclear 1 e
Tne Committee prepared a report regarding the use of shorter piles under certain structures at the Bailly Generating Sta-
.Y tion, Nuclear 1 (see Appendix XVIII).
5.
Response to Request from NRC/TMI Special Inquiry Group The Committee authorized a response to a request from M.
Rogovin, NRC/TM1 Special Inquiry Group, regading significant ACRS recommendations made on non-B & W plants prior to March 28, 1979 (see Appendix XIX).
The 231st ACRS Meeting was adjourned at 4:00 p.m., Saturoey, July 14, 1979.
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