ML19332E169

Forwards NRC Initial FY90 Base Table,For Info

ML19332E169
Person / Time
Issue date:	11/16/1989
From:	Rathbun D NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA)
To:	Breaux J, Jeanne Johnston, Sharp P, Udall M HOUSE OF REP., ENERGY & COMMERCE, HOUSE OF REP., INTERIOR & INSULAR AFFAIRS, SENATE, APPROPRIATIONS, SENATE, ENVIRONMENT & PUBLIC WORKS
References
CCS, NUDOCS 8912060323
Download: ML19332E169 (15)

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UNITED STATES :-

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The Honorable J; Bennett Johnston, Chairman-I Sub:o mittee on Energy =and Water Development' g

Cormictee on Appropriations A

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DeariMr;' Chairman:

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' Enclosed for your' information. is a copy of the Nuclear Regulatory Consission's < initial Fiscal Year-1990 Base Table..

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. Dennis K. Rathbun, Director ll '

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. The Honorable Horris K. Udall, Chairman

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Subcommittee on Energy and the Environment-Comittee on Interior.and Insular Affairs United States House of Representatives

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Dear Mr. Chairman:

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. Enclosed for your information is a copy of the Nuclear Regulatory Jj N

Commission.'s initial Fiscal Year 1990 Base Table.-

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Dennis K. Rethbun, Director Congressional Affairs h-Office of Governmental and m

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The Honorable John Breaux,: Chairman i

Subconnittee on Nuclear Regulation Comnittee on Environment and Public Works United States Senate Washington,-D.~ C.

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Dear Mr. Chairman:

Enclosed for your information is a copy of the Nuclear Regulatory Connission's initial Fiscal Year 1990 Base Table.

Sincerely, Dennis K. Rsthbun, Director Congressional Affairs-Office of Governmental and Public Affairs L

Enclosure:

As' Stated cc: The Honorable Alan K. Simpson L

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iThe Honorable Philip R. Sharp. Chairman Subcomunittee on Energy'and~ Power

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Dear Mr. Chairman:

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. Enclosed for your information is aj copy of the Nuclear Regulatory Comisiion's11nitial Fiscal Year 1990 Base Table.

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1 LDennis K. Rathbun, Director Congressional. Affairs l'

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Enclosure:

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cc:s Ths Honorable Carlos 6. Moorhead

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October 31,:1989' 2,

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Enclosure

'U.S. NUCLEAR REGULATORY C0fellSSION

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FY 1990 BASE. TABLE

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FY 1990 1 r e -

' na Actiust==ts' i

President's Comparability Appropriation ~ 10/1/89.

Budaet Ad.iust = at Reduction Estimates Program I.

Reactor Safety and Safeguards a

j Regulation

.5175,664 156

$ -6,048

.$169,772.

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Nuclear Safety Research 124,041 -19,838 104,203 Nuclear Naterial and Low-Level Waste Safety and Safeguards Regulation 40,887 42

-1,451 39,478'.

High-Level Nuclear Waste Regulation 23,195 a

-904.

22,291 Special and Independent Reviews, Investigations, and Enforcement 36,636

-105

-971 35,560-1 Nuclear Safety Nanagement j

and Support 71.677

-93

-788 70.7 %

k TOTAL

$472,100

$-30,000

$442,100 NRC Inspector General 2.900 0 2.900

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TOTAL NRC

'$475,000

$ ~

$-30,000

$445,000 4

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'These changes are discussed on the following-pages.

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COMPARABILITY ADJUSTMENTS f

.The-methodology' has changed for allocating regional travel funding among ~ the

-NRC mission areas. In the FY-1989 NRC budget submission to Congress in January 1989,' region travel was allocated to each NRC mission area based on the number

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'of region-FTE's in the mission area.

To sinalify the calculations, the region E

. travel funding allocationtis now determined- )y allocating'rogion travel to the

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.two mission areas for which the travel primarily occurs (i.e., Reactor Safety-

-and Safeguards Regulation, and Nuclear Material and. Low-Level Waste Safety and W

Safeguards Regulation.)

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DISTRIBUTION OF APPROPRIATION REDUCTION The NRC's FY '990 appropriation of $445,000,000 is $30,000,000 less than.the President's Budget request. The reduction has been allocated as shown below.

(Dollars in Thousands) i-Frogram Administrative Net l

Suonort Suonort Chanae Nission Area p

. Reactor Safety and Safeguards Regulation'

$ -4,500

$-1,548

$ -6,048-Nuclear Safety Research'

-19,600

-238

-19,838 E

Nuclear Material and l-Low-Level Waste Safety and Safeguards Regulation

-1,100

-351

-1,451 High-Level Nuclear Waste -

Regulation'

-800

-104

-904 i

Special'and Independent Reviews, Investigations and Enforcement 700

-271

-971 Nuclear Safety Management and Support -788

-788

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TOTAL'

$-26,700

$-3,300

$-30,000 _

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Program Sunnart The impacts' of the reduction in program support funding are delineated below.

Reactor Safety and Safeauards Reaulation'

-$4,500K

+

o Eliminates contractor support that may be needed for 8 of the 30 maintenance A;

team inspections scheduled-for FY 1990.

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o Delays:campletion of the analysis of the sensitivity of nuclear power plant

.r*st e 'iations in human performar.a ' ntM FY 199'..

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,'a one or t..# of the 'planns to 12 safety system functional

s safety system outage moo..) cation inspections, or operational eam insputions.

Also reduces the level of probabilistic risk L'

u nt quidance_provided.to resident and tra '. T,pectors.

l iuces techt Mai. ssistance fc myieving operat

. autor licensing actions about 20 This wil' delay completva of about 200 licersing s '.io's.-

c Continuek nro funding for contractor assistance for topical reports in L

FY 1990 M.fety impvements that may have baan derived from new or advanced; L

methds will be delay'd util FY 1991.

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- o Eliminates contractor support in applying potential probabilistic risk i-assessment insights and precursor information to regulation activities.

L o Reduces by about 18 percent,. the contractor support for the region based E

emergency preparedness exercise inspections.

4 Hug)sar Safety Research

-$19,600K o Delays.for at least a year, the two pressurized thermal shock experiments (PTSE-3 and -4) which are in preparation.

This may effectively eliminate performing these tests due to facility decay and loss of essential personnel.

The - PTSE-3 experiment was intended to determine the effect of claddir.g on mitigation of crack extension under PTS accidents. The industry may attempt to tah' credit for cladding's ability to inhibit crack extension to obtain relier from the requirements of the PTS Rule when they reach the screening criterier. Without adequate experimental proof, the staff may, on an interim basis, adopt excessively conservative positions regarding operation at or beyond the screening criterion.

The PTSE-4 experiment was to measure the

^f'4ty of low upper shelf energy weld metal to resist fracture under PTS 3

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w conditions.. The 'NRC will now have to rely on analyses. provided by the

~ industry and'may have to adopt excessively conservative positions to assure-

, safety = at: this time.. " Additionally, the number of tests' and microscopic examinations; that will be conducted to-determine the-radiation. damage e

mechanisms will also be reduced. This will reduce our ability to effectively.

. predict when plants reach the PTS rule screening criteria. It will also delay-revision of' Regulatory Guide 1.99, Effects of Residuel Elements:in-Predicted Radiation Damage to Reactor Vessel Materials.

4

~ o Defers the restart of work:on the cyclic crack growth. rate of vessel and 1

piping steels under reactor environmental conditions and delays initiation

= of studies of short cracks in pipes and elbows. E This work tells how fast t

cracks can grow between operating cycles-or if a short crack can actually be critical for failure. The Office of Nuclear Reactor Regulation is dependent' upon.these crack growth. rates for their decisions of whether or not to allow plans-to go back on line, or if cracks must be repaired or replaced. Current a:

decisions will be based on available data which was validated for long cracks 1

.and are thought to be not conservative for short cracks.

I' o Eliminates.about 70 percent of the funds for. determining the initial flaw 4

distribution in a pressure vessel. This will effectively eliminate the start

.of the program.

The plar, was to use an existing pressure vessel salvaged from a cancelled nuclear plant for very detailed examination using the most advanced nondestructive techniques, and then to do such metallographic 1

. examination as necessary to verify defects. This initial flaw distribution data is - needed for probabilistic risk assessment. accuracy.

The present

-" standard" init'ial flaw distribution was set forth in the Marshall Report of-n nearly ten years ago. This distribution is no longer accepted as realistic, L

and is strongly believed to be unconservative. However, there is no credible j

alternative.

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o Reduces 50 percent of the funding for evaluation of components and materials l

removed from the Shippingport reactor.

This will preclude work to begin j

removal and study of pressure vessel steel material from the vessel. The loss Hm of data for the Shippingport vessel will eliminate tests of such material to validate accelerated laboratory irradiation tests. Duplicate materials cannot be produced in the lab.

The in-situ as-irradiated properties of reactors which have operated for long times are essential to ragulate older plants and

-then relicense them for continued service. Will'only be able to complete the work on shield tank embrittlement, and will have to stretch out or abandon

- work on materials already removed, o The work in the area of Aging of Reactor Components will be reduced about 20

' percent. This work consists of the aging assessment, impact on safety, aging detection and the development of aging degradation mitigation methodology for over 30 electrical-mechanical components and 20 systems found in U.S. nuclear power plani.s. The reduction means that some of the identified components and systems will never receive an aging degradation assessment and much of the confirmatory work required to assure the prevention of common mode failure for classes of safety systems in commercial nuclear power plants will not be carried out.

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For a significant number of safety systems and ' safety related components,.

i the. NRC willEnot have ~ established the increasing; risk. engendered by Lpossible' failure: of aged - components-and ~ systems.

Some of.these

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. components and systems are: compressors, heat exchanges, surge arresters, fans and chillers, main stean isolation valves, nuclear instrumentation,-

main steam system, and-reactor. core isolation cooling' system.

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' For. approximately 50 percant of the identified components and systems, i

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the.NRC will not.have the -technical-bases-for evaluating the effectiveness of the utilities'= maintenance' programs.

Development of the technical bases for reactor license renewal fo most of the components identified above'as being impacted by the reduction:

p, will not be completed in a timely nianner.

1 o': Eliminates-about three staff-years of contractor assistance to the NRC in H

engineering-standards development and-transfer to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III,

" Rules for' Construction of Nuclear Power Plant Components," and Section XI,,

o

" Rules for Inservice Inspection of Nuclear Power Plants." This will reduce l:

NRC' representation at all code and committee meetings-pertaining to nuclear L

power standards' and delay studies for the regulatory impact and cost analyses.

c that.usually :are ~ needed before. the NRC endorses professional society.

standards.

In addition, reductions will also be made in the NRC testing i

L orogram on the operability of certain types of motor operated valves. This work is in support of-the resolution of Generic Safety Issue 87 and the-implementation 'of the resolution of Generic Safety Issue II.E.6.1.

.o Delays by at least one year, findings about earthcuake causal mechanisms and

. prehistoric earthquake occurrence that could help close the Eastern U.S.

-seismicity issue and would potentially reduce the large uncertainties L

associated with seismic hazard estimates. Seismic hazard estimates provide the dominant uncertainty in seismic probabilistic risk assessment studies.

Thus, the major uncertalaty addressed in Individual Plant Examination seismic

' plant reviews cannot be reduce until studies are completed to demonstrate whether or not the likely recurrences of earthquakes (i.e., similar to the Charleston-earthquake) are tied to specific geographical areas.

o ' Virtually eliminates research support of the review of upcoming American

.'Suciety of Mechanical Engineers piping design criteria changes for pipe damping, pipo stress allowables, piping analysis, and pipe support design.

It is expected that several such proposals will be presented to the NRC for approval in FY 1990, o Delays for one year, possible cooperative effort with Japan on seismic response of structures on soil sites. Assessment of realistic seismic margins for U.S. plants on soil sites requires test results that are available only from Japanese test programs..

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- o: This) reduction sin :structurali aging research requires ~ concentration of all

~ remaining resources on attempts to keep pace with the license renewal program.-

.This will > preclude-any att~ts to begin L the formulation: of a basis for g[<

restructuring the leak ratt

.ing program..

L

-oiTerminates experiments needed to' confirm once-through-steam-generator (OTSG).

facility scaling assumptions ~ used;to simulate the following? transients:

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' accident / management strategy of secondary -feed and bleed; main steam line break; inadvertent.. valve opening; 'and. other' transients leading to 0TSG-

. secondary-side depressurizatior.. ' As a result of terminating experiments, the-NRC will-not have a data base for thermal-hydraulic code development with OTSG l

performance equivalent-to that which exists for Westinghouse, Combustion

. Engineering and General. Electric plants.

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- o:' Terminates technical analysis for suggested tests on accident management in

. ROSA-IV, effectively eliminating. participation in ROSA-IV test decision on 1

primary depressurization,E primary feed : and ~ bleed, and - secondary ' feed and -

bleed. This impacts accident' manages. ant research in that code validation for c

specific.. accident sequences would be lacking.

ROSA-IV would pass from a i

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US/ Japan program to' a Japan / France / Germany program. Also, new work will not

~ be initiated on' experimental facilities at universities.

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o Eliminates half of the baseline activities at the thermal hydraulics Technical.

Support Center. The activities include code applicability studies for a small L

break loss-of-coolant accioent in a Combustion Engineering plant and for a L

loss-of-feedwater accident in a Westinghouse,-plant.

Also, development of two~ plant input decks (PWR and BWR)'will be delayed until FY 1991.

o: : Terminates-work on thermal-hydraulic analysis of CANDU' reactors from the point of view of NRC licensing criteria.

Reduces work on review of 600MW BWR advanced light water proposals submitted to DOE for purpose of determining if existing NRC computer codes can accurately simulato safety systemt of these new designs.

o Delays by about six months, research on the role of the shift technical advisor. Also delays about one year, research to integrate human and hardware reliability into assessments of sdvanced reactor designs.

o. Delays development of an objective basis for regulatory requirements to monitor performance rather than design margins.

Development of criteria to improve operational safety using defenses against common-cause failure would be delayed.

o Cancels the planned confirmation of predicted natural circulation induced surge line failure for a station blackout accident and investigation of the reactor coolant system resporse to similar accidents at PWRs. It is important to confirm that the principal reason that direct containment heating is not the dominant threat ta large dry containments in Severe Accident Riskt: An Assessment for Five U.S. Nuclear Power Plants (NUREG-ll50) because of expected

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depressurization of the reactor coolant system by natural circulation-induced ^

' hot leq failure. - As a consequence of the reduction, the.NRC will not be able g^ '

to fu'ly. confirc-the' NUREG-ll50 conclusions nor provide best. estimate technical' bues' for estimating the effects of natural circulation on' the o

K courte of severe accidents.

o Slows work on fission product behavior within the reactor coolant system and within containments.

Plannea validation of-fission product release-- and

-transport models will be delayed, and models for predicting the impact 'on accident source terms from resuspention and revaporization of fission products N

will not be evaluated until. FY 1991, and then on a stretched out schedule.

the NRC will not bec ablez to improved - best; estimate technical bases for 7

estimating severe accident source terms and as a consequence, the containmen* -

improvements-program will'not be as effective as it is now anticipated.

1 o' Slows furt.vir. !.velopment.of core / concrete interaction analysis tools and curtails tus "o^ct of core / concrete experiments.

As:a result,.the NRC's ability to answe accident management questions and detailed questions about

~

melt behavior and:the generation of fission product aerosols in containment will.be delayed about 12 to 18 months. Therefore, NRC's ability to provide the best ' estimate technical bases for estimating containment response and source terms froni severs accidents will be impacted.

oi Cancels plans for construction-of the experimental facility to study high temperature hydrogen combustion and detonation in containments. This study D

was planned to address the dominant uncertainties with respect to the question is

.of steam invertingLin the presence of high temperature hydrogen for BWR Mark II-and III containments and in PWR condenser containments. As a consequence, the_NRC will not be able to provide improved estimatas of the effects of high

temperatures,'high pressures an high steam content on containment loadings from hydrogen combustion and detonation in severe accidents.

o. Delays ' the extension of results to prestressed concrete containments and

. defers activities on structural response to hydrogen-related loadings.

It will be necessary to reduce the scope of the penetration project by dropping p

cae of the two bellow tests.

This will necessitate extrapolating from one H

test -to numerous bellows types, thus leaving large. uncertainties.

It will L

also be necessary to reduce the scope of the post-test analysis and separate i

effects testings for prestressed concrete cont:inment.

The technical basis for some Individual Plant Examination revi tws may be delayed.

l o Delays the development and use of advanced probabilistic risk assessment methods including improved models of human behavior and severe accident physical processes in the review cf advanced light water reactor risk analyses (required for design approval of such advanced plants), in the review of risk analyses or licensed plants, and other regulatory uses of risk analysis

methods,

o. Risk analysis models cf power plants are used by the staff in a variety of ways, including the cost-benefit analysis of generic issues, the analysis of the importance of events in operating plants, assessing the overall !

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performance of operating plants, etet The number of plant risk studies which -

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can be put into a~ form for use by the staff in these w of such analyses.

01 Defers about 20l percent of 'the planned research for confirming the safety o o

low-le' vel waste disposal. This 'will impose conservative constraints on the.

- technical bases for some licensing decisions'and may effect the licensabili of specific sites due to the abserce -of adequate supporting-technical

.b information.~

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'o1 A draft regulatory guide on control room habitability previously planned for

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FY 1990 will:not be issued.

' document and referenced:via a generic letter.. Technical results will-be publis o?Rulemaking: or petition-evaluation suoport will be' raduce in the fuel cycle

and' transportation areas, and. safeguards support will be terminated.

reduction in the: fuel: cycle support will - delay research to assess the The radiological impact of the recycle of equipment and material with residual radioactive contamination.

will further: extend; the joint NRC-DOT. program to evaluate t D

economic significance of NRC's continuing to allcw fissile material and Type-B quantities of other radioactive material to be shipped in DOT Spectification Packages.1The lack of safeguards support will eliminate validation of the psychological. testing portion of t,he access author z. tion rule.

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c Limits. the extent of the systematic review.and subsequent modification of-regulations that are marginally important to safety.

o :The systematic - review.of. the risk importance and effectiveness of NRC-regulations and regulatory pract= ices identified in the Safety Goal Policy implementation plan will be substantially reduced in scope for FY 1990 and deferred.to-later years.

+

Program to $500K, the same level as FY MaReduces NRC particip o

Value-impact analyses that would be required for backfitting any additional o

regulatory requirements identified under the Containment Performance Improvement program for containments other than BWR Mark I's will not be carried out in FY 1990.

The implementation of any recommended improvements will' either be delayed until FY 1991 or will be implemented by including the insights in the Individual Plant Examinations.

Staff findings on other containments will not be impacted, Studies of potential changes to NRC policy and regulations as a result of o

Technical Information Document-14844 source term. severe eccident Efforts to modify other appiteations of source term and severe accident research will be delayed until FY 1991.,

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o Continuing reevaluation on the Hiroshima and thqasaki health effects data provides new information on tne function of sex and age at exposure. NRC risk estimates needed to establish current dose limits do not address these issues.

The NRC will soon need to respond to the Iriternational Commission on Radiological Protection and the National Council on Radiation Protection and Measurements recommendations for reduction in the dose limits.

Without analysis of the new data on age and sex dependency of risk, the technical base for rulemaking will be weak.

o Terminates work on radiation protection issues that are unique to advanced reactor designs.

Initiation of this work has been delayed several times as funding for development of advanced reac:frs has been reduced.

Hgthar Material and Low-Level Waste Safety and Safeauards Reaulation -$1,100K o Defers initiation of surveys of previously decommissioned materials and fuel cycle facilities until FY 1991, o The development of the Regulatory Guide, " Criticality Safety of Shipping Casks", will be delayed until FY 1991.

The delay will result in continued conservaticn uncertainties in cask criticality calculations, including burn-up calculations.

Hiah-Level Nucleaf Waste eteaulation

-$800K o Rulemakings on (1) Design Basis Accident Dose Limit, (2) Criteria for Containment of " Greater-than-Class C" Waste, and (3) License Application Content and Acceptance '."riteria will be deferred by about one year.

This will delay publication of the final rule for (1) and (2) until about October 1992 and for (3) until about September 1993.

Special and Indeoendent Reviews. Investiaations. and Enforcement

-$700K o Delays implementation of new initiatives in the reactor and materials health physics trairling areas and the specialized technical training area. Extensive curriculum modifications are known to be required in the reactor and nuclear material / fuel cycle health physics areas.

o Reduces NRC support for the DOE Aerial Measurements Program. Number of sites scheduled for over-flights would be reduced to four per year which is a marginally acceptable level of funding to maintain emergency support service from DOE... _.....

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o? Delays further development an -implementation of Reactor Safety Assessment a

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System as an analytical ~ tool for the Retetor Safety Team and thereby reduces the_NRC's capability tc rcspond b and assess a reactor accident.

o,-Reduces the tapability to conduct BWR drills using the Nuclear Plant Analyzer

. and ~ contractor technical support.

k' o o Reduces the ability to respohd co newly identified reactor technology training

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This Lwould c result in a reduction of' about two course weeks of i

C training.

Reduces the ' bility to procure hi

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.of technical training programs, gh techrology training aids in direct' support a

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Eliminates'some technicalLexpertise in' specialized fields in support of AE00 n-

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studies ' and, in turn, limits the number, scopo and depth _ of studies.

Detailed evaluations of one or more aspects of AE00 studies will increase the J

credibility and utility of!these studies. Studies which could benefit from -

such assistance include equipment taken out of' service during plant shutdown,

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fast bus transfer, diesei fuel-oil contamination problems, and common mode

. diesel 1 failures.

Potential safety benefits can be obtained from' improved technical dets.il in AE00 reports to feedback the lessons of experience.

' Administra'tive 'Suonort

-$3,300K r

-The impacts of the administrative support funding reduction are. delineated below.

The allocation of tiis reduction to NRC mission areas is shown on page 2 of this

. enclosure:.

1, o Defers 1 the acquisition of new system development tools, ir.cluding computer-aided software engineering tools, database related systems software, and PC-based user software needed for cooperative processing.

o Only essential installation or relocation of telephone instruments and associated - equipment, modems, and-telecommu1(cations lines will be made

.throughout headquarters during FY 1990.~

-o ' Reduces usage of the videocenferencing system in FY 1990.

o - This reduction will:- (1) Limit NUDOCS full text processing to Licensee Event Reports and to documents submitted in electronic format. Full-text processing will not exceed ter, percent of the other documents submitted to NVDOCS during

.FY 1990. This wiH restrict the growth of the full-text databases. (2) Limit 3.

the extent of document indexing by reducing descriptions, eliminating abstreets, eliminating FOIA indexing, eliminating special project indexing, and eliminating linking document packages.

(3) Eliminate the processing of "s

any new document types into the system. (4) Defer development of the oatical

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'diskAub-systemuntil: FY 1992..<This would defer any image access until that time. --(5) Defer consolidation into NUDOCS of other NRC automatad document-s

,-E' control systems (i.e., ASLBP/ INQUIRE, PDR/8RS, OGC/HCPE) until FY 1c92. This

will delay attaining the cost avoidance that would come from the e'.imination--

of.duplicative, systems.

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'o' Redacesithe planned incriase in ADP timesharinglcast by-about 50- percent.~

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Should requirements exceed the planned budget allocation, actions to restrict

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use of the timeshared' computer facilities would be required.. Also,. reduces 1

the number of multiple subscriptions +o various. periodicals.

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-o Delays in proceeding with the second building to consolidate NRC beadquarters 0

' employees result-in tha deferral of certain.onsolidation costs.

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