ML19351D154
| ML19351D154 | |
| Person / Time | |
|---|---|
| Issue date: | 06/16/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1750, NUDOCS 8010090100 | |
| Download: ML19351D154 (18) | |
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MINUTES OF THE
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MAY 20< 1950 ACRS REACTOR OPERATIONS SU3CCMMITTEL MEETING, WASHINGTON, D. C.
The ACRS Reactor Operations Subcomittee held an open meeting on May 20, 1980 in Room 1046, 1717 H St., N.W. Washington, D. C..
The purposa of this meeting was to review the pragrams and FY-82 budget of the Research Support Branch (RSB) of the Office of Nuclear Regulatory Research (RES) in the areas of operational safety and technical support in preparation for the ACR5 annual reports to the Nuclear Regulatory Comission and Congress. Notice of this meeting was published in the Federal Register on May 20, 1980.
A copy of this notice is included as Attachment A.
A list of attendees for this meeting is included as Attachment B, and schedule for this meeting is included as Attachment C.
A complete set of i
handouts has been included in the ACRS Files. The Designated Federal Employee for this meeting was M'. Richard Major, j
r Ooeninc Remarks - W. M. Matnis Mr. William Mathis, Chairman of the ACRS Reactor Operations Subcommittee began the meeting at 8:45 A. M.
He introduced the other ACRS members present and noted that the purpose of the meeting was to review the programs and FY-82 budget of the Research Support Branch (RSB) of the Office of Nuclear Regulatory Research 16 the areas of operational safety and technical support in preparation for the ACRS annual reports to the Nuclear Regulatory Comission and Congress.
Introduction - William Farmer, Chief Research Support Branch Mr. Farmer introduced the topics to be covered by the presentations on operational safety research and technical support activities.
Included in the area of oper-ational rafety research programs are: fire protection research, qualiff-cation testing evaluation, human factors research, noise diagnostics, and safety valve research. Technical support programs include the Nuclear Safety Information l
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at ORNL and the Argonne National Energy Software Center.
Center Farmer mentioned that there are six people in the Research Support Branch (RSB).
i Mr.
i Their responsibility is not only to monitor the research but to develop program i
concepts and planning.
I Qualifications Testing Evaluations (QT_E) Procram_ - R. Feit The objectives of the QTE program are to w ;,rovide an independent assess:nent of LOCA (and other) testing methodologies, determine the nuclear source tem signature for the design-basis LOCA and evaluate the adequacy of radiation simulators, and provide a model that can be used to simulate the natural aging process of repre-sentatives Class IE materials by accelerated aging methods'.
Among the accomplishments of the program reviewed for the Subcommittee were quali-The test inclu-fication tests performed on Browns Ferry Unit 3 electrical connectors.
I d;d a nuclear radiation test which exposed the connectors to a uniform dose of 6.9x10 RADS (ATR) at an average dose rate.77x10 RADS / AIR for approximately '90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, a f
0 temperature aging test of 217 F for 60 hrs. in air and 217 F for 180 hrs in 0
0 The tests duplicated nitrogen and a steam exposure of 157 c, at 58 PSIG for 24 hrs.
those already perfomed by TVA. All aspects of the utilities test program were An additional program that has been completed is a leakage path verified.
A leakage path was investigatrd between the conductors and the experiment.
insulation material of a cable that could break the integrity of a supposedly sealed As a result of their work, there have been a number of motor or an instrument.
changes that have been made at plants to block that leakage path.
Current test facilities are capable of performing experiments to test synergistic To date and on a limited basis, no significant synergistic effect has effects.
Some minor differences such as discoloration were noted, but nothing been noted.
However, other generic pieces of l
l that would result in a functional difference.
equipment will be tested to judge the effects of a simulataneous exposure to steam,
. pressure, anc radiation.
Pressure transmitters will be the next devices tested.
Among topics for future tests will be tests designed to overcome the oxygen decletion effect of previous LOCA tests.
In a postulated loss of coolant acci-dent in a typical containment oxygen would be present. When qualification tests I
are conducted in the laboratory, there's usually a steam flooding condition and a de-pletion of oxygen. There is a strong indication that those are not conservative tests, since much of the degradation is a function of oxidation.
In the area of long-term QTE program goals, several areas stand out. The develoo-ment of requalification tests for naturally-aged equipment is one such goal. The aim is to develop procedures for requalifying equipment after a given amount of service rather th6n requiring replacement. Another area of research will be to evaluate
" statistical" qualification methods. This would be a tie-in between the quality assurance program and the qualification program. The aim is to develop a statisti-I cal basis for saying equipment will survive. Tests will also be conducted on addf-tional generic safety-related equipment such as limit switches, cabling connectors, etc. Plans are also being made for U.S./ French Cooperative Programs using some very unique facilities to study oxygen depletion.
There have been a number of accomplishments in the QTE accelerated aging study.
These include the completion of a low-level radiation, aging facility; continued aging experiments, and model verification for typical electric cable insulation jackets; and the performance of extensive evaluation of old-style polyethylene /
polyvinyl chloride cable. A fire-retaro nt' aging study has also been initiated.
The tests expose equipment to both radiation and thermal environments. These are long-term tests which require years to complete. The current program is
'.imited to cable insulation and specimens have been in test chambers for three years. Some naturally aged samples have also been examined. Samples of poly-ethylene. cable insulation from Savannah River have been obtained, along with 1
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ex:glier.: re:Or:i of thair service life. One of tne reasons the cable aging oro-grar v.as started wa3 due to severe degradation in the polyethylene cable that was used at Savannah River.
En the long term aging studies will focus on new methods and alternate damage indicators as a method of looking for cable degradation. The aging program will t
also be extended to seals and gaskets. Causes for aging" in addition to radiation and thermal effects, such as stress, will be explored.
It is hoped that nacurally 8
aged cable samples will become available from a number of plants along with some samples from TM!-2.
The QTE program dealing with radiation qualification source evaluation objectives will have several long-term objectives including: develop dose and dose-rate estimates for a generic containment structure, and develop a quantitative simulator specification to duplicate the damage from a realistic release.
As alluded to before, there will be a program to evaluate the performance of TMI safety-related equipment. The purpose will be to collect data on exposure and performance of safety-related equipment. The program will establish and implement a systematic post-mortem examination of this equipment.
The final area of review under qualification testing is a design adequacy study.
The objective of this program is to review generic safety-related instrumentation and elect
- al equipment to identify areas of vulnerability and failure modes.
Review areas include: the identification of generic safety-related equipment, material compatability problems, fabrication problems, maintainability problens and interface problems. No work is scheduled to begin in this area until 1982.
5-Fire P-c:e.';or. Resaarch Drecra - Rcr Fe't ing oojective of the fire protection research program is to provide an improved (and independent) data base for the evaluation of fire protection testing metho-t Mr. Feit dology and for regulatory guides, standards, and licensing decisions.
i This includes an evaluation of Reg.
discusse" work that has been done to date.
Guide 1.75, where findings were that the Reg. Guide was adequate for electri-cally initiated fires, but was not adequate for an exposure fire.
Research has also been concerned with the following additional protective mea-In fire retardant coatings, shields, and barriers of various types.
sures:
all cases, these measures seemed to be effective aghinst'
- reventing the spread p
Work has also been done with sprinkler cf fire through a series of cable trays.
Preliminary work has also been done for penetration fire stops and systems.
halon suppression systems.
Tne long range objectives of fire suppression research will be to provide fire i
I suppression test data for confirmation or modification of NRC fire protection re-In the near term the objective will be to determine minimum gas qui rements.
concentrations and interaction (SOAK) times for suppression of horizontal cable i
Mr. Feit also went over the design of the test chamber for the fire 2 ray fires.
suppression tests.
Mr. Feit explained the theory behind the application of halon is to catch the fire A con:entration of 6% halon is recomended at an early stage and suppress the flame.
to extinguish a fire; this concentration is also safe from a health effect stand-Mr. Ebersole questioned the Staff on the desirability of pre-point to workers.
The Staff replied it could be done inerting the cable spreading room with halon.
l but would be very expensive.
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1 Tests are planned with halon to see how well it dist ioutes itself in a parti-cular volume that contains a fire. How well halon diffuses into the atmosphere will be studied.
The fire protection research has also done an evaluation of the IEEE Standard flame test and developrant of improved small-scale cable system quali-i 383-1974 The test objectives were to test the repeatcbility and para-fication tests.
meter sensitivity and a comparison of results with cable performance in a full-f Some A second objective is to develop an improved test procedure.
scale systec.
of the test results were that a comparison of flame propagation tests on similar cables showed distinct differences in different tests and cables that resisted flame propanation in an IEEE-383 flame test did not resist flame propagation in a full-scale test. Parameters tested included: test cell size and configurations, cable size and material, mixing cable sizes and materials, air flow require-ments for the test cell, etc.
The objective of this Research is also conducting tests on penetration fire stops.
test is to confirm that current qualification test nethodology guarantees per-formance during a design basis fire and to reconmend changes to current quali-The failure mode of the penetration fication test methodology where necessary.
b3ing examined, is hot combustible gas which leaks through the cracks in the Smail scale tests tall during a fire and carries the fire to the cold side.
conduct 0d show that differential pressures and excess fuel are important test parameters.
Research has Another area of fire protection research is on replication tests.
been asked by NRR to perform confirmatory fire testing of detailed mock-ups of selected operating plant configurations with fire protection measures designed in accordance with NRC fire protection guidelines and found acceptable by the NRR The purpose of the test will be to confirm whether these fire protection Staff.
. In a sense, figurations.
nfigvatitns are valid for operatinJ plant con Possible' candidate configurations
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its will be a full scale croof test.The kind of testing to be performed woul ancho Seco, and Arkansas One.
Research would like to tm nelude a full scale te'.t with a suppression sys e. stem doesn't work, wit i
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, epeat the test, assuming the suppress on sy a fire brigade.
Laboratory, a consultant Dr. Hunter of Johns Hopkins. University, Applied physics r
tation. The pres-in fire protection for NRC Research, made a brief presen i
l models of the sentation described work being developed on mathemat ca bles or air channeis, firo resistance of walls that are penetrated by electric ca f
temoerature be-A wall exposed to ' fire on one side can fail when its back ace heat'conbustion in cables, or excessive heat
.comes too high, due to excessive A wall with channels can transfer from hot gas forced through air channels.
ignites on the unexposed l
i also fail when unburned flammable gas from the fire side.
Noise Diacnostics for Safety Assessment _ - W. Farmer techniques to the under-i Noise diagnostics is the application of various no se The objectives stems.
standing and analysis of the behavior of various plant sy l to support independent of the program are to develop technology and personne f noise diagnostic assessments of reactor operating prob'lems, development o t including: loose parts techniques and data, and diagnostic systems assessmenand functiona monitoring, leak detection, pattern recognition,
i modeling. A The first area of noise diagnostics research is in stochast c spectral density ex-time cependent neutroti code is used to derive the power-in the physical geometry pected at a detector-location for various changesThe obje within the reactor system.
be achieved using noise the degree of detectability and ' sensitivity that can
. diagnostics. Applications of stochastic modeling include predicting PWR neutron f
i noise for in core vibration, flow blockage, coolant boiling, etc. Predictions of BWR neutron noise will be used to detect boiling and in-core vibrations.
The loose parts, monitoring detection studies are using the EGCR pressure vessel to study techniques for locating impacts and characterizing loose parts.
Ex-perimental work is expected to be com:leted in FY-80. Reporting is expected to be complete in FY-81.
Baseline signature measurements are being made. These baseline neutron signature field measurements started in 1979 on some PWRs. A libra,ry of these signatures is being compiled for assessment of anomalous behavior in operating plants. A collection of the Output from neutron chambers for specified operating conditions I
will be kept on file for operating reactors. Such information would S ve been l
helpful in analyzing conditions such as the loose core barrel at Palisades, and vibrating instrument tubes in BWRs. Baseline neutron noise data has been obtained for five PWRs to date.
Dr. Moeller noted that all of the research being conducted was using neutron noise and asked if there were any research programs designed to look at audio noise?
Mr. Fanner said that only in loose parts monitoring through the use of accelero-meters is mechanical noise used. Mr. Ebersole also noted that there has been little research done on monitoring a ' plant in a post-trip condition. Mechanical noise detection may be one such method of monitoring.
Baseline signature measurements in FY-81 will be to get neutron noise measure-ments from Saquoyah. The program will also be extended to measurements which taill include core exit thermocouples and process signals (pressure, temperature, and flow) from Sequoyah.
In FY-82 the signature measurement program vill be expanded to include more process signal data, and component signature information.
This will expand diagnostic capability to cover systems behavior, and component
as well as, the current neutron noise cata case for in vessel phenomena.
- e e ier, be y
The BER stability momitoring progra~ is designed to see if neutron noise can Neutron noise measurements offer the advantage used to monitor BWR stability.
of continous or intermittent stability measurement quickly, without perturbing L
the plant.
By FY-81 To date, SWR stability measurements by neutron noise looks promising.
In FY-82 it is it is hoped that analytical investigations would be complete.
l for hoped to verify investigation using field data fron several BWR power p ants several refueling cycles.
The last item in noise diagnostics is work on the use of Californium 252 to d This method allows a measure of suberiticality termine reactor suberiticality.
l Reactivity is obtained from measure-without actually taking the reactor critical.
Interpretation does not depend on ments performed only at the subcritical state.
knowing the absolute value of the reactor's inherent source or detection ef It involves the use The method has been demonstrated on small pool-type reactor.
of three fission chambers, one of which will contain Californium 252 as a source, by cross-correlating the signals, it's possible to derive directly the sub-criticality measurement for the reactor core.
Safety and Relief Valve Testing Procram - M. Stolzenburg The safety and relief valve testing program requirements were generated from EPRI is conducting TMZ-2 lessons learned recomendations and the ATWS revicw.
The BWR program will be the safety and relief valve testing but only for PWRs.
The requirement from lessons learned was that pressurized water re-separate.
actor and boiling water reactor licensees and applicants conduct testing 2o qualify the reactor coolant system relief and safety valves under expected As a result of operating conditions for design basis transients and accidents.
TMI, these valves which were designed for steam operation will be examined
. Not all valves will be ditions.
under twc-phase flow as well as water solid dis:harge con A description of the Testing will be done on a prototypic'al basis.
tested.
d PWRs) should be test program and the scSedule for testing (for both BWRs an Testing shall be completed by July 1, 1981.
submitted by January 1, 1980.
am. How-E i NRR has requested that ATWS conditions be included in the test progr hich testing ever, the industry (EPRI's) position is that ATWS conditions to w In addition, some of the currently specified must be conducted are not firm.
d date. Currently, test requirements could not be accomplished by the require industry has been asked to perfom the ATWS tests, but they have not been Currently, the industry position' is that they will not quired to do the tests.
do ATWS tests.
be the Mr. Stoirepburg said that INEL will act as a systems integrator to infor-focal point for the collection of all data that would contribute to the INEL will review the industry programs, including a de-mation need of NRR.
d test tailed review of the test facility instrumentation test procedures an ility of conditions, to ensure that the test will adequately demonstrate operab In addition, INEL will review methods of analysis used by the indus the valves, Independent to interpolate test results to other valves and pipe configurations.
ided.
analysis using existing critical flow models and system codes will be prov PWRs) will focus on relief and safety The EPRI program (which deals only with In-relief and safety valves will be tested.
valve operability.
Proto tyoical
'd down-cluded in the test will be the principal hydraulic effects of upstream an Valve test facilities include those at stream piping on valve operability.
d Combustion Engineering with potential secondary contractors at Duke P Wyle laboratories.
. Meacc i on Human Factors
'4. Farmer Farmer noted that only part of the man-machine interface work is carried Mr.
on within the Research Support Branch. A very large and significant amount of this work, in terms of dollar value and effort is conducted within the Probabilistic Assessment Branch, under the improved safety program.
Huran factors deals in part with plant monitoring. One area of plant monitoring is instru-v.tation to provide for better infomation display and greater surveillance of f
the plant during the course of an accident. This effort includes developing the instrumentation and displaying the system status.
A second effort under plant moni-toring includes diagnostics which is aimed at giving an o'perator the capability to Also quickly determine the cause of malfunction or other difficulty and respond to it.
included is continuous on-line surveillance (pattern recognition).
4 Man-machine interface deals with the interrelationship of man to his controls and his procedures. Control room design work (largely going on within NRR) is aimed at evaluating existing designs and supporting examination of designs on a generic basis and developing guidelines and criteria for later implementation in the re-view of control rooms now in operation. There is some advanced research going on to examine the use of CRTs and other display devices to enhance operator infor-mation display and controls over more conventional systems that are now in existance.
This Research into operator behavior deals with safety related operator action.
area deals with operator performance under stress and simulator training.
Human errors research is being conducted by PAS. This effort includes data evalu-ation and risk assessment.
Mr. Mathis asked if there was any " people" oriented type research as opposed to the more equipment and process research described. He was interested in knowing
- if there was an effort to set criteria that could be usec for licensing or He was told that the operator licensing hiring people as potential licensees.
branch is addressing the licensing and training requirements for operatcrs and has been upgrading those requirements. In terms of screening potential operators, both educational requirements and emotional stability are being investigated.
Ultimately, this research will end up as changes in the licensing requirements and guidance that the agency endorses.
f Mr. Farmer described the continous on-line reactor surveillance program at ORNL in conjunction with the TVA Sequeyah-1 plant. The objective of the program is The aim is to monitor selected reactor signals for indications of an'omalies.
The system to provide early detection of impending component or system failure.
will provide a record of plant operational behavior when bounds are exceeded.
The system will provide an alert capability to the operators.
A second area in human factors research handled by the RSB (Research Support Branch) f is safety related operator action. Contractors are ORNL, General Physics Corp.,
and Center for Nuclear Studies at Memphis State University.
The objective of this program is to evaluate the operators time response to a range It will develop a quantitative basis for assigning safety of abnormal occurrences.
functions for operator action. It is hoped to develop some information on the effort of stress on operator actions. A final aim is to develop correlation factors so that operator responses during simulator tests can be related to field behavior.
The expected products are a quantitative and c>alitative data base on opbrator response for use in standards, design, and licensing.
A second phase of safety related operator actions involves the use of simulator l
PWR and BWR simulator experiments will be carried out using real experiments.
operating crews in training. Additional work will collect field data from records, logs,.and LERs.
. Ine final report on worx regarding scfcty related operator actions is expected in the a
spring of 1982.
A survey of nuclear power plant simulators and their use in operator training and requalification was performed to assess capabilities for training in abnormal /
Further objectives were to assess current use in training and g,
emergency events.
The result of the recommendations for improvement in light of the TMI accident.
study was that the use of simulators, characterized in the report as, one of potential the most powerful training tools and probably the only viable approach for training A recom-for abnormal / emergency events, has been less than optimum in the past.
mendation was made that NRC should support, encourage, participate in, cooperate the comprehensive programs which are necessary; and iricorporate results into a co regulator, policy for training on abnermal events which recognizes the complete One of the specific problems called out regarding scope of a training program.
simulators is the lack of a site specific simulator in some cases.
I Dr. Moeller wanted to be sure that -he research staff was familiar with Chapter 6 in the ACRS report, NUREG-0542, "A Review of NRC Regulatory Processes and Functions."
f l
On pages 6-6 and 6-7 there are four recommendations that deal with man-machine interactions.
The four recommendations were:
"There may be advantages to expanding the automated plant features 1.
to reduce the need for operator action during transient operating periods, but how and whether this should be done deserves c'onsid-etable thought. The Committee pointed out that the real concern is whether the diagnostic burden on operating personnel is excessive.
w e
r
. There is a need to improve the infor ation displays in control
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Specifically, we need to draw operator attention to the rooms.
The alam systems crucial instrumentation needed in emergencies.
may be excessively confusing, and some information displays could k.
be better located.
5 Attention will have to be concentrated on integrating infonnation 3.
from diverse sensors and combining the information in such a way that the accide'nt systems lead the operators to initiate correct f
Symptom correlation with instrument' sig-safety control actions.
nals to direct operator action to the appropriate safety pro-cedures could eliminate wch of the concern about man-machine Not enough attention has been addressed to interfacial response.
this matter.
Operating personnel must have some emergency instrumentation pro-4.
i visions to maintain cognizance o.f accidents that do not proceed An example is instruments that show along anticipated lines.
whether fuel has failed and what type of failure may have occurred.
Without such provisions, the operating personnel are less able to correct unforeseen events that may have been overlooked during accident analysis, even though the corrective action mignt be easily performed."
Technical Sueoort procram - H. Scott Mr. Scott made a brief presentation on the Nuclear Safety Information Center at The center is designed to collect, evaluate, abstract and disseminate ORNL.
Also discussed was the National Energy Software relevant safety information.
The Software Center collects, packages, I
Center at Argonne National Laboratory.
distributes FRC contractor-developed programs and data.
maintains and 1
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Inforrat on Throuch FY W. Farmer c
i Closed Sessian en Bud:etary 1
Mr. Farner presented the continuing Research Support Branch,0perational Research Programs for FY-81/82. The slides used are being treated as Official Use Only
- Jacuments based on exemption 9(B) of PL 94-409, the Sunshine Act, frustration of agency action. In addition, Mr. Farmer presented nrm' initiatives in the areas 6 l of man-machine interface, plant systems behavior, and Instrumentatien and Electri-cal. It was noted that the new initiatives had received no formal approval and were tentative.
The meeting was adjourned at 2:25 P.M.
I A complete transcript of the meeting is on file at the NRC Public Document Rooom at 1717 H St., N.W'., Washington, D. C. or can be obtained from Alderson Reporting Company, Inc., 300 7th St., S.W., Rep 6rters Building, Washington, D. C. 20024, (202) 554-2345.
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1960 / N:tfess Federal Regist M {g/Upg4 2E30
'o make oral statements should notdy CFFICE OF MANAC4 MENT AND LEGAL. 5ERVICES CORPOR ATION de Desip.ated FederalE=plo>ee as far suDGET.
in adsance as practicable so that Agency Forma under Review Granta and Contracts appropnata arrangementa can be made to allow the necessary time durgthe g 3,,g Apnl a reso-The Legal Service 6 Corporation was
=uting for such statements.
Background
est0bhshed pursuant to the The Legal ne agenda for subject meeting shan When executive departments and Serv. es Corporation Act of1974. Pub. f.
be as follows: Lesay MeyE.1980, s
93-353a. Se Stat. 378. 42 U.S.C. 2996 Mm unQ concluamn of agencies propose public use forms.
reporting orrecordkreptag 4
2996.'. as amended. Pub. L 95-=2 N8/"'88-requirements, the Omce of Management (December 28,1977). Section 100*(f)
The Subcommittee may meet in and Budget (OMB) reviews and acts on provides: "At least thirty days pner to E.xecutive Session, with any ofits sose requirements under the Federal the approval of any grant apphcation or consultants who may be preserd to Reports Act (44 USC. Chapter 35).
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- be considered during the meeting.
to consult with the pubbe on significant
- such grant. contract. or psoiect. * * **
At the conclusion of the Executive reporting requirements before seeking The Legal Services Corporation hereby announces publicly that it is Session the Subcommittee will bear OMB approval CMB in carrying out its considenes the grant apphcation presentations by tad hold discunions responsibJiry u: der the Act also l
with representenves of the NRC Staff.
considers comments on the forms and submitted by:
Leyal Aid B"teau for Kalamazoo and Geir consultanta, and other interested recordkeeping requirements that wi!!
Van Butt t Cc.mties. !nc., in Kalamazoo=
persona.
affect the public.
Michigan..r.erve Cass County.
'I1se ACR$ is required by Section 5 of Interesteo ;,ersons are hereby invited the1978 NRC Au6erization Act to list of Fonna Under Review 12 subr.it wntten comments or review the NRC research program and Efery Mondy and Thursday OMB recommendations concernma the abovebudget and to report the results of the pulbishes a het of the agency forms applicanon to the Regional Office of the review to Congress. In order to perform received for review since the last list Legal Services Corporation at Th'e Lega this review, the ACRS must be able to was published.The het has a!! the Services Corporattort Northern Virtuus engage in frank discussion with entries for one egency together and Regional Omce.1730 N. Lynn Strut.
members of the NRC Staff and such grouped into new forms, revisions.
l Arimgfon. Va. 2209.
discussions would rot be possible if extensions, or reinstatements. Some Dasl Bredley, held in public sessions. In addition.11 fonns listed as revisions may only have Avervent.
may be necessary for the Subcommitee a change in the number of respondents tra on mar,s rn.m
-i to hold one or more rJosed sessions for or a msurnaw o e tune nuded m fiU aos caos een.n*
the purpose of explanes matters Gem at rather dan any dange 2 de involving proprietary information. I have e atent of the form.The agency NUCt. EAR REGULATORY determined, therefore. in accordance I"
with Subsection 10(d) of the Federal
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Advisory Committu Act (Pub. L. 92,=
Advisory Committee on Reactor 463), that, should such sessions be Safeguards Subcommittee on Reector required. itis necessary to close na name and ta'ephone number of the
, Operations; Meeting portions of this meeting to prevent agency clearina omcer(from whom a frustration of the above stated aspect of copy of the form and s.pportmg documents The ACRS Subcommittne on Reactor the ACRS' statutory responsibilities and is n ede m Operations will hold a meeting on to protect proprietary inforroation. See 5 e omce of the agucy tuuing is fann:
Tuesday. May 20.1980 in room 1048, U.S.C. 552b(c)(9)(B) and 552b[c)(4).
1717 H St. NW. Washingtort. DC 20535 to Further informat:on regarding topics umber.If applicable-review NRC research prog-ems in the How often the form must be filled out[
en area of operational safety, including fire to be disc.;ssed. whether the a reting who will be required or asked to report pictection. noise diagnostics, and man
- has bc en cancelled or rescheduled. the An esumate of the number of forms that wi!!
machine interfaces for the ACRS annual Chairman's ruling on requests for the be ft::ad euc reports to NRC and Congress. Notice of opportunity to present oral statements An astimate of the total number of houre this meeting was published Apnl 25.
and the time a!!otted therefor can be needed to fill out the form: and obtained by a pre;> aid telephone call to
,he name and telephone number of the accordance with the procedures tst cognizant Designated Federal Person or omca responatble for CMB outlined in the Federal Register on Employee Mr. Richard K. Major
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October 1.1979 (44 FR 564cs), oral or (telephone 202/634-1414) between 8:15 written statements may be presented by a.m. and 5 p.m EDT.
Rerotting or recordkeeping members of the public, recordmas will requ;tements that appear to raise no Deted. Apnt :s. teso.
s gnDeantissues are approsed be permitted only dunns those portions I'**P Y' O*' "'**IP'**'5**i* "*'
- I af the meetmg when a transcriptit being John C. Ho>le, U
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kept, and questions may be esked on y Adnsory Commit n Management Officer.
ake any action on proposed reporting requirements until at least ten working by members of the Subcommitee.its consultants, and Staff. Persons destnns w w.~
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LJ ATTACHMENT B MAY 20,1980 ACRS REACTOR OPERATIONS SUBCOMMITTEE MEETING, WASHINGTON, D. C.
6 ATTENDE25:
NRC STAFF _
ACRS W. Mathis, Chairman G. Knighton R. Silver J. Ebersole R. Ireland D. Moeller
- 5. Hudson J. Ray R. Major, Designated Federal Employee D. Notley L. Tong W. Farmer R. Feit H. Scott OTHER L. Hunter, Consultant Shirley Wolf, Alderson Reporting Co.
ML Stolzenberg L. W. Hunter, Applied Physics Lab.
R. J. Ross. Doub & Muntzing R. W. Whitesel, EPRI l
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TENTATIVE SCHEDULE ACRS DEACTOR OPERATIONS SU3 COMMITTEE ROOM.1046,1717 H St., N.W. Washington, D.C.
May 20, 1980
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Times are Approximate 1.
Executive Session (OPEN)
,i 8:30 A.M.
Introductory Statement - W. Mathis, Subcommittee Chairman i
Discussion of Agenda Meeting With NRC Staff from Research Succort Branch II.
TRE S )*
Evaluation of Qualification Testing (45 Min.)
A.
8:45 A.M.
B.
Fire Protection (45 Min.)
9:30 A. M.
i Nois'e Diagnostics (45 Min.)
C.
10:15 Program to Monitor EPRI Safety-Relief Valve Testing D.
11:00 A.M.
Effort (15 Min.)
r Man-Machine Interfaces (2 Hrs.)
E.
11:15 A.M.
III. Final Executive Session _
1:15 P.M.
- decide if information is sufficient to write appropriate sections of ACRS annual reports to the Commission and Congress on RES budget.
ADJOURN
' :30 P.M.
It may be necessary to close portions of this meeting to discuss pertinent portions of the NRC FY-82 budget for research programs, and, if necessary to protect proprietary information.
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