ML20041D175
| ML20041D175 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1982 |
| From: | NRC OFFICE OF THE CONTROLLER |
| To: | |
| References | |
| NUREG-0870, NUREG-870, NUDOCS 8203040436 | |
| Download: ML20041D175 (100) | |
Text
O NUREG-0870 O
BUDGET ESTIMATES FISCAL YEAR
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1983 u
j Appropriation:
l Salaries and Expenses
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U.S. Nuclear Regulatory Commission j
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Available from GPO Sales Program Division of Technical Information and Document Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Printed copy price: $5.00 and National Technical information Service Springfield, Virginia 22161 A
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O NUREG-0870 BUDGET ESTIMATES FISCAL YEAR
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1983 Appropriation:
Salaries and Expenses O
January 1982 U.S. Nuclear Regulatory Commission O
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i BUDGET ESTIf1ATES FOR i
l U. S. fiUCLEAR REGULATORY C0fiMISSICil l
FISCAL YEAR 1983 I
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General Statenent..................................
Pages 1 - 11 fluclear Reactor Regulation (fiRR)...................
Pages 12 - 24 j
Inspection and Enforcement (ISE)..................
Pages 25 - 43 6*
Nuclea r flaterial Safety and Safeguards (f! MSS)......
Pages 44 - 61 Nuclear Regulatory Research (RES)..................
Pages 67 - 78 Program Technical Support (PTS)...................
Pages 79 - 81 Progran Direction ar.d Administration (PDA).........
Pages 82 - 86 Special Supporting Tables..........................
Pages 87 - 90 I
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NUCLEAR R[bulATORY C0lTISS10f!
j' FY 1983 Budget Estimates GENERAL STATff'ENT F0P SALARIES AND E.YPENSES 1
(Dollcrs in thousards, except whole dollars in narrative material) i Estinate of Appropriation The budget estimates for Salaries and Expenses for FY 1983 provide for obligations of $4/9,500,000 to be furded in total by a new appropriation.
Estimatee of Obligations and Outlays This section provides fer the surnEy of oblige +. ions by program on page 2; the surmry of financing these oblications on page 3; the analysis of outlc.ys on page 4; obligttions by function on pace 5; the proposed appropriation language s
i crd analysis of the appropriation language or tage 6 through 9, the gereral program statement on pages 10 and 11, and the torrative sumrary of NRC prcgrans beginning on page 17.
i The sucr. aries which address obligations include the NRC's Reimbursable progrom.
It should be ncted that the obligations related to this progran are not financed by NRC's appropriated
- funds, but solely through reinbursable agreements with other Federal agercies.
The f.RC will & pcsit revenues derived from the licensee fee precram and indennification fees to flircellaneous Receipts of the Treasury.
The following table summarizes the total cbligations for NRC's Direct and 1
Reimbursable Programs fer FY 1981, FY 1982 and FY 1982.
The detailed justifications for direct program activities are presented in the same order as i
they appear in this summary table.
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l SUf't'ARY OF ff> LIGATIONS [Y PROGRA!1 I.
(Dollars in thousands, racept whole (ToTlars ir narrative naterial) 9 Cbligations by Activity:
4 Direct Prograri Actual Fstimate Estimate l
FY 1981 FY 198?
FY 1983 1
huclea r Peac tor Rcgulatier........
! EU,6?7 5 67,015
$ 93,12C Inspectior and Enforcement........
52,668 66,234 69,850
!!uclear f*aterial Saf ety and
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Safeguaras.....................
33,936 38,917 37,385 f;uclea r f<egul a t or y P.esea rch.......
227,326
??7,663 219,725 Program Techr.icr1 Support.........
18,696 22,61F 23,400 Program Direction & Acriinistration.
35,441 37,359 36,020 Total Obligations -
Direct Progran.............
$448,694
$474,800
$479,500 Peimbursable Progran..............
413 500 500 Total Obligations.............
$449,107
$475,300
$480,000 Unobligated balarce, start of year.
-11,996
-6,100 0
Unobligated balance transferred to other accounts..............
660 0
0 Unobligated balance, end of yeer..
6,100 0
0 Pecovery of prior year obligations
-2,966
-3,000 ll 0
Orders received from other Federal agencies.......................
-344
-500
-500 Budget Authority.............
$440,561
$465,700
$479,500 l/- Estimate to fund a portion of the FY 1982 pay raise; if recovery is not i
realized, programs will have to be reduced accordingly.
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(Dollars in thcusands, except vihole dcllars in ncrrative raterial) 9 Financing 01 Cbligations j
The financing of the estimatml total obligatiers of $479,500,000 proposed in the budget estirate for FY 1983 is suP1rlarized in the fellowing table:
_Su_llt'ARY OF FIriA!!C 9!G i
Actual Estimate Estirate FY 1981 FY 1982 FY 1983 l
Sources of Furds Available for Obligations:
3/ $
0 Recovery of prior year obligaticris.......
S 2,966
$ 3,000 l
Uncbligated balance, start of year.......
11.996 6,100 0
l App rop ri ated to NRC......................
442,570 465,700 479,500 l
Orders received from Federal sources.....
344 500 500 l
Transferred to other accounts:
i Unoblig?.teo Balance..................
-660 0
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FY 1981 Appropriation................
-1,959 0
0 Total Funds Avcilable for Cbligations
$455,207
$475,300
$480,000 l
Less: Urchligated balance, end of year..
-6,100 0
0 Total Obligations..............
$449,107
$475,300
$480.000 4
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Estiriate to fund a portion of the FY 1987 pey raises; if recovery is r.ot j
realized, programs will have to be reduced accordingly.
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l (Dollars in thousands, except whole dollars in narrative traterial)
Outlays for Salaries and Expenses Outlays for FY 1983 are estimatec at 5450,500,000.
The following analysis
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identifies funds available for cutlays for each of the budget periods.
This amount less the unexpended balance at the end of the period equels the outlays.
l OUTLAY AtlALYSIS Actual Estimate Estimate FY 1981 FY 1982 FY 1983 Unexpended balance, beginning of year:
Obligated......................
$ 156,477
$ 185,403
$ 210,703 Unobligated....................
11,996 E,100 0
Appropriatioii to NRC..............
442,520 465,700 479,500 Total Funds Available for Outleys $ 610,988 5 657,703
$ 690,203 Unexpended balance, end of year:
l Obligated......................
5-185,403
$-210.703
$-239,703 Unobligated....................
-6,100 0
0 Transferred to other accounts.....
-2,619 0
0 Total Outlays................
'$ 416,866
$ 446,500
$ 450,500 0
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(Dollers ir thousands, except whole dollars in narrative raterial)
O St'f T.AP,Y OF BUDGET 08LIGATIOfc5 BY FufiCT!0f!
Actual Estimate Estinate FY 1981 FY 1982 FY 1983 Direct Progran Sale ries and Benet its........
$123,423
$138,700
$137,900 Program Support..............
255,513 270,350 274,000 Adn'nistrative Support.......
43,422 47,677 50,900 Travel.......................
7,883 10,250 10,100 Equipment....................
8.453 7,823 6,600 Total Obligations -
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$479,500 Direct Progr6n........
$448,694
$474,F00 Peinburseble Progran.........
413
_500 500 TOTAL OBLIGATIONS...........
5449,107
$475,300 5480,000 O
l ll Includes $6,100,000 unobligntcc balance carried fcrward and on estimate of
$3,000,000 in recovery of prior year cbligations to fund a portion of the FY 1982 pay raises.
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- l.. c. NUCLEAR REGLLATORY CN'f11SSION i
PRPPOSED LANGUAGE - SALARIES A!;0 EXPENSES (Deliars in Thourands, except whole dallers in narrative material) l i
l The proucsed languacc is as fellcws:
Salaries and Expenses i
For necessary experses of the Cer.nission ir. carrying cut the purpoc.es of the l
Enercy Reorganization Tct cf 1974, as amended, and tFe Atonic Energy Act, es arended, including the enploymerit of aliens; services authorized by 5 U.S.C.
3109; publication and dissemination of atomic energy information; purchase, repairs, and cleanino of ut.iforms; official representation expenses (not to exceed $3,000); reiribursement to the General Services Administration for security guard services; hire of passenger m.otor vehicles and aircraf t; S479,500,000 to remain available until expended:
Provided, That from this appropriation, transfer of suas may be made to other agencies of the Government for the performance of the v.ork for which this appropriation is made, and ir, such cases the suns so tranc.ferred may be nerged with the appropriation to which transferred: Provided further, that moneys received by the Conmission f or the cooperative nuclear safety research program and the material access authorization pregran may be retained and used for salaries and expenses associated with those programs, notwithstanding the provisions of 31 U.S.C.
484, ar.d shall remain available until expended.
(Energy and Water Development Appropriation Act, 1982.)
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L. S. i;UCLE/,F REGULATOKY C0i' HISS:G!:
/>nalysir. of Proposed FY 1983 Apfropriation Lerquage 1.
Ier necessary expenses cf the Comniuien in carrying out um rurposes of the Energy Recrger.izatior Act of 1974, an amendec; 42 U.S.C. 5841 et. scq.
42 U.S.C. SM1 et. Seq. the Energy Reorgari7ction Act of 1974, estabiished the fluclear Regulatory Comnission to perform ell the licensing and related reculatory functions of the Atonic Safety and Licensing Ecard Panel the Atcr.iic Safety cnd Licensirg Appeal Board, and the /cvisory Connittce on Reactor Saf eguards, and to carry cut the performance of other functions including research, for the purpose of confirratory assessment reibt ira to licensing and ether regulation, other activitics, includine research related to nuclear material safety art regulatier, under the provisions of the Atonic Energy Act of 1954, as arended (42 U.S.C. 2011 et. seq.) ar.d the Energy Reorgani7ation Act of 1974, as amended (42 U.S.C. 5801 et. seq.).
2.
Enployment of eliens; 42 U.S.C. 2201 (d) of the Aton c Energy Act of 1954, as arended authorizes i
the Commission to employ persons and fix their ccrpensation without regard to civil service laws.
3.
Services authorized by 5 U.S.C. 3109; 5 U.S.C. 3109 5 U.S.C. 3109 prevides in part that the head of an agency may procure by contract the temporary or interriittent services of experts or consultants when authorized by appropriation.
4.
Publication anc dissemiration of atomic infornation; 42 U.S.C. 2161b 42 U.S.C. 2161b directs the Commissico that they shall be guided by the principle that the dissenication of scientific and technical infomation relating te atoraic energy should be permitted erd encouraged so as to provide that interchar.ge of ideas and criticism which is essential to scientific ar.d industrial progress ena public urderstanding and to enlcree thc fund of technical inforuation.
5.
Purchase, repair and cleaning cf uniforns; 5 U.S.C. 5901 5 U.S.C. 5901 authorizes the annual appropriation of funds to each agency of the Government as a uni'orm allowance.
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Tnalysis of Proposed I.ancu3ge - continued 6.
Official representetion expcoses; 47 Con p. Gen. 657 43 Cor p. Gen. 305 This larcuage is required because of the established rule restricting an agency from charging appropriations with thc cest of official representation unless the appropriations involved are specifically available therefor.
Congress Fas appropriated funds for official representaticr. expenses to the NRC and NPC's predecessor AEC each year since FY 1950.
7.
Reimburser ent of the Gereral Services Administration for security guard services; 34 Comp. Gen. 42 This language is recuired because under the provisions of the Federal Property and Administrative Services Act of 1949, specific appropriation is made to GSA for carrying out the function cf protecting public buildings and property, and therefore, NRC appropriations not specifically made available therefore niay not be used to reinburse GSA for security guard services.
8.
Hire of passenger notcr vehicles and aircraf t; 31 U.S.C. 638a 31 U.S.C. 638a provides in part
"(a) Unless specifically authorized by the appropriation concerned or other law, no appropriation shall be expended to purchase or hire passenger notor vehicles for any branch of the Governrrent..."
9.
To remain available until expended; 31 U.S.C. 718 31 U.S.C. 718 provides in part that no specific or indefinite appropriation shall be construed to be available continuously without reference to a fiscal year unless it is mede in terms expressly providing that it shall continue available beyond the fiscal year for which the appropriation /.ct in which it is contained makes provision.
- 10. That from this appropriation, transfers of sums may be made to other agencies of the Government for the performance of the work for which this appropriation is trade, and in such cases the sums so transferred nay be merged with the appropriation to which transferred; 64 Stat 765, Sec. 1210 64 State 765, Sec.1210 prohibits the transfer of appropriated funds from one account to another or working fund except as authorized by law.
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Anclysis of Proposed t.anguage - contir.ced l'oneys received by the Ccnnission for the cocperative nuclear safety G
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research progrcns art the material access authorization progran nay be retained ar.d used for salaries and expenses as%ciated with those pregrams, er.c shall remain availcble until experded.
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C Ccep. Gen. 775 Approprinted funds nay not be augmented with funds from other sources unless specifically authorized by law. The cooperative nuclear safety research progran consists of fur.ds received from foreign governments that will participate in NRC's reactor safety research experiments.
These funds will be uded to pay for any costs incidental to their participation.
The paterial access authorization program consists of funds received from licensees for the cost of security investigations asreciated with access to fernula quantities of special nuclear naterial. These funds will be used to pay the agency performing the security investigations.
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U. S. fWCLEAR RFG"LATORY COMMISSION Progran Statement The LFC budget estimate for FY 1983 is $479.5 nillio.
It reflects a decrease in prograri, primarily in Nuclear Pegulatory Research, as ccmpared to FY 1982 when the effects of inflatien are considered.
The budget provides resourccs f or both contiruation of reactor licensing activity comensurate with caseload schedules er.c increased efforts toward resolution of reacter safety issues.
Resources are included for ccrtinued oversight of Three Mile Ish nd cleanup activities.
Incrmised ef fort will lie devoted
'0 ward the licensing of the Clinch Piver Breeder Reactor.
A significant focus of regulatory research ef fort in FY 1983 will continue to be on prevention and nitigation cf snall break loss-of-coolant accidents such as that which cccurred 6t Three Mile Island. Additional research will t.e directed teward obtaining better understanding of severe accident phenomena, human-machine interfaces and probabilistic risk analysis.
The NRC will contir.ue its progrcm of utilizing the cperating experience of reactors for safety analysis.
In this regard, data are extracted from reports provided by the nuclear industry, analyzed by the NRC staff and entered into e centrcl data bank that provides the capability to riatch and compare like occurrences at different operating plants. This procran effectively incorporates cperating experience into the regulctory process.
NRC will assign resident inspectors tc reactor sites with new operating licenses and maintain sufficient resident coverage at existing sites. NRC will continue to pursue a vigcrous enforcenent program.
To improve efficiency with both its licer. sees and the people affected by licensed facilities, NRC will continue tc expand its regionalization program. NRC is also planning to initiate construction of a neu facility for its inspecter and technical training program to be co-located with the existing TVA simulator training site near Chattanooga, Tennessee.
The FY 1983 budget results in some reduction in programs.
The NRC plans to corplete a schedule of tests at the loss-of-Fluid Test facility during FY 1983, thus allowing the facility to be placed in stardby status in FY 1984.
The Nuclear Data Link progran is being limited in FY 1983 to the testing and evaluation of a protctype systen for subsequent decision on its potential contribution to emergency response.
To eliminate overlap and unnecessary expenditure of funds, the NRC is actively pursuing a policy to take advantage of werk being done by other government agencies and the private sector.
NRC intends to use Department of Energy research in the arcas of high-level waste disposal and breeder reactor technology. NRC will cantinue to work closely with the Federal Energency Management Agency on developing and implementing effective emergency planning requirements for licensed facilities. The NPC is pursuing with the private sector third party certification of qcality control. The commission is utilizing work done by the Institute on Power Operations (INP0) on the development and operation of Nuclear Plant Reliability Data System as well as on the operation of an industry-wide screening service to identify Licensee Event Reports and other operating experience of significance to the licensees to augment NRC data. NRC will also evaluate the INP0 program for the development of standards and requirements in the human factors area.
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U. S. NUCLEAR REGULATCRf C0f4f11SSI0fi Program Statement - continued In parallel with the progran actions identified above, the Nuclear Regulatcry Commission is reviewing current policies to determine if changes could be
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made to improve the regulatery process without compromising safety.
The flRC intends that its regulatory processes be efficient and cost effective.
Unnecessary regulatory burdens are to be avoided and flRC regulations sFeuld allow licensees to select the most cost effective ways te satisfy NRC safety cbjectives.
In summary, the fiRC has taken positive steps to nininire the resources necessary to effectively regulate the nuclear industry. A critical review of the f!RC's procedures and organizational structure has led to changes that limit our resource requests while simultaneously improving the quality of regulation. We have looked to other sources for information and research that er.able the NRC to eliminate overlap while ensuring the pub 1 health and safety. The estimates for the NRC are based on the premise of effective and efficient managerent that has as its goal the s.afety of the public ard the regulation of a highly technical industry at minimum cost.
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(Dollars in Thousands, except whole dollars in narrative material) 3 t
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Nuclear Regulatory Commission - continued v
Nuclear Reactor Regulation.
............................. $93,120
SUMMARY
OF NUCLEAR REACTOR REGULATION ESTIMATES BY FUNCTION Actual Estimate Estimate FY 1981 FY 1982 FY 1983 Salaries and Benefits.....
$29,741
$32,580
$34,210 37,913 41,285 44,600 Program Support.........
Administrative Support..
11,927 11,750 12,810 Trave 1.........................
1,046 1,400 1,500 Total Obligations........
$80,627
$87,015
$93,120 People.........
(700)
(702)
(738)
In accordance with the Atomic Energy Act of 1954, the Energy Reorganization Act of 1974, and the National Environmental Policy Act of 1969, the Office of Nuclear Reactor Regulation's (NRR) primary objective continues to be the assurance of adequate protection of public health and safety and the environ-ment in the design, siting, construction, and operation of nuclear reactors.
[V-)
NRR is responsible for performing the safety, environmental and antitrust reviews for applicants for construction permits and operating licenses; changes to operating licenses for power and non power reactors; and the licensing of reactor operators.
Organizationally, the regulatory and licensing effort is divided principally among the office's five divisions to (1) carry out project management functions (2) perform detailed safety engineering and environmental reviews; (3) perform detailed performance-oriented evaluations for nuclear plant systems; (4) perform operational, administrative, and people-oriented reviews for human factors safety; and (5) assure that basic safety and environ-mental policies, goals, and requirements are achieved by the regulatory and licensing process.
The Nuclear Reactor Regulation personnel and program support funding require-18 ants to meet NRR's responsibilities have been allocated to the major program-matic areas shown below.
The narrative that follows provides justification for,the resources associated with each program, o
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Nuclear Reactor Regulation - continued 3
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Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Dollars People Dollars People Dollars People Operating Reactors
$10,733
.60
$10,310 201
$10,245 264 Systematic Safety Evaluation of Operating Reactors 3,390 31 1,436 26 3,200 42 Operator Licensing 1,643 11 4,040 23 3,590 33 Casework 15,752 297 17,272 309 14,660 246 Safety Technology 5,735 131 7,642 76 12,490 91 TMI-2 Cleanup 660 23 335 20 315 17 Management Direction and Support 0
47 250 47 100
_45 TOTAL
$37,913 700
$41,285 702
$44,600 738 In the aftermath of the Three Mile Island accident, the NRC redirected a signi-ficant portion of its resources to ef fertively analyze and evaluate the accicent and determine the generic lessons that apply to licensing and regulating nuclear power.
As a rhult, NRC slowed its licensing process f or more than one year while the applicants continued construction of nuclear power plants.
NRC was then faced with a b tuation in which a numner of plants could be ready to operate p
before an opc ating license would be issued.
In order to minimize the impact of j
j the licensing oelays, NRC instituted a recovery plan in FY 1981 designed to
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reduce the delays in issuing operating licenses for plants scheduled to be completed in FY 1981 and 1982, and to eliminate the delays in issuing 1icenses for plants scheduled to be completed in FY 1983 and beyond.
The FY 1983 budget will continue to concentrate on avoiding unnecessary delays in licensing power v
- reactors and on implementing the safety requirements developed from the TMI-2 Action Plan and the Unresolved Safet
'n ses.
Phase III of the Systematic Evaluation Program will begin and 1.
Je integrateri with the National Reliability Evaluation Program N
'll continue to place special emphasis on the regulatory activities ne, n.
t he decontamination of TMI-2, defueling the reactor, and disposition - t m.
wioacti /e waste.
Also, NRR will resume the study and resolutiun~of those generic safety issues which were partially deferred in FY 1982 pending re prioritization of the safety issues.
s Operating Reactors..
..FY 1981 = $10,733 FY 1982 = $10,310 FY 1983 = $10,245 (160)
(201)
(264) x The regulatory activities associated with operating power reactors which are 4
'necessary to protect the public health and safety will continue to be NRR's first priority.
To assure that operating facilities achieve and maintain the adequate levels of protection of public health and safety and the environment, NRR will take the necessary action to correct identified inadequacies in plant V) 13
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued design and operation; to review and act upon licensees' requests for amendments to operating licenses; and to implement new or revised regulations and criteria for all operating facilities.
Accordingly, NRR will conduct the technical review necessary to accomplish licensing actions (e.g., amendments, orders, petitions, hearings, fuel reloads, and multiplant issues) and manage the overall technical and procedural aspects of safety and environmental reviews.
In doing so, NRR will continue to:
assure that plants operate safely by using operational data, design information, results of resolved safety and environmental issues, and inspection and enforcement findings, as the basis for taking necessary action in the form of licensing orders and changes in allcwable operating conditions.
prevent unnecessary restrictions in plant operations by prompt review and modification of license conditions based on licensee requests to modify plant systems and reactor fuel load configurations.
review and evaluate operating reactor events and resolve each issue in a manner consistent with continued safe plant operation.
assimilate lessons learned from each unexpected operating event into the licensing process to ensure consideration of the event in the review of construction permit and operating license applications.
The resource requirements for reviewing operating reactors licensing actions and f or the project management workload are based on the NRC Caseload Forecast.
The following table summarizes the projected number of licensed operating reactors during the planning period.
Licensed Operating Reactors FY 1981 FY 1982 FY 1983 Reactor units 75 85 103 Reactor sites 50 58 70 lo enhance the overall safety and environmental project management of operating reactors, NRR will assign by the end of FY 1983 one project manager per site with similarly designed facilities and two project managers per three unit site.
In the few cases where multi unit sites have power reactors of significantly different designs, NRR will assign one project manager per unit.
Although NRR has continued to improve the current methodology and approach for reviewing and.prioritizing operating reactor licensing actions, the licensing action workload continues to increase.
This increase is primarily a result of additional facilities being licensed and an increase in the number of actions per plant, especially during the first two years of operation.
The number of actions per plant is increasing as a result of implementing many of the TMI-related requirements,' resolving several Unresolved Safety Issues, more formalized generic technical specifications, and startup problems experienced 14
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued during plant shakedown.
The licensing actions identified in NUREG-0737,
" Clarification of the TMI Action Plan Requirements" are being and will l
continue to be reviewed and implemented.
The implementation schedule for l
Unresolved Safety Issues (USI) and the remaining items from NUREG-0660, l
"TMI-2 Action Plan" is compatible with their resolution.
The projected licensing action workload including implementation of the TMI Action Plan and resolved USI's as well as other multiplant and plant specific actions is:
I Licensing Actions FY 1981 FY 1982 FY 1983 Carryover from previous year 3,008 4,882 3,424 Incoming 3,887 1,086 1,366 Reviewed and completed 2,013 2,544 2,358 NRR is also required to conduct iapid initial safety assessments of unanticipated events at operating facilities and develop generic technical positions on safety or environmental aspects of nuclear power plant design, construction and operation directly related to operating facilities.
NRR has evaluated and resolved many unanticipated operating events which have occurred during FY 1981.
J Examples of operating reactor events which required significant resources in
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FY 1981 include the Indian Point-2 containment flooding, boiling water reactor scram system problems, pressurized water reactor thermal shock, and emergency core cooling system actuation and recirculation problems, recurring loss of-control room annunciators, and transformer failures.
The resource increase in FY 1983 results from fully implementing the assignment of project managers per site, as previously discussed; the increased number of operating reactors; and the more resource consuming licensing actions scheduled to be reviewed.
Systematic Safety
- Evaluation of Operating Reactors...... FY 1981 = $3,390 FY 1982 = $1,436 FY 1983 = $3,200 (31)
(26)
(42)
The NRC is conducting an ongoing comprehensive systematic review of operating; nuclear _ power reactors with respect to current licensing requirements.
The program documents the results of the review and identifies the need for plant.
changes.
This effort-includes two assessment programs-_the Systematic Evaluation Program (SEP), a deterministic review of specific safety issues and the National Reliability Evaluation Program (NREP), a probabilistic analysis of systems reliability under accident sequences.
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The SEP, initiated late in FY 1977, assesses the adequacy of design and operation
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of reactors, compares them with current safety criteria and provides the basis V
- for integrated 'and balanced equipment backfit decisions.
Phase I of the program, the establishment of guidelines, techniques and review areas for conducting the evaluation, has been completed.
Phase II, the actual _ review of 15 w
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(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued 10 older operating plants,U has commenced and approximately 70% of the overall topic evaluations have been completed.
The remaining SEP Phase II topic reviews are scheduled for completion by the end of 1982.
Following completion of each plant's topic reviews, an integrated plant safety assessment will be performed.
The integrated safety assessment for the lead plant is expected to be completed by July 1982 with the remaining assessments to be completed by June 1983.
The SEP Phase 11 program was redirected in early 1981 to require that licensees participate more actively, resulting in reduced NRC resource requirements for this program.
This approach will also be applied to Phase III of the SEP.
In addition, for the SEP Phase Il plants, the program will provide the technical basis for the conversion of Provisional Operating Licenses to Full-Tero Operating Licenses.
SEP Phase III is planned to begin in FY 1983 and be completed in FY 1989.
This phase will provide documentation on how each of the next 60 operating reactors c.ompare to the current safety criteria.
To ensure that issues of significant safety benefit are considered for each group of Phase III plants, an annual review of significant safety issues will be conducted.
The issues for the first group of Phase III plants will be determined from experience with SEP Phase II.
As experience is gained from the SEP Phase III reviews and knowledge is gained from the NREP reviews, safety issues of particular significance may be added and safety issues of lesser significance may be deleted from the list.
The first revised set of safety issues will be completed in late FY 1982 and subsequent revisions will be completed at the end of each succeeding fiscal year until all groups of plants have been addressed.
The first group of SEP Phase III plants will be identified in late FY 1982 and will be coordisioted to the extent possible with the NREP program.
NRR expects to identify approximately 70 issues and 5 licensees for the first group Phase III SEP plants.
The licensee will be allowed approximately 12 months to conduct their review.
Resource requirements are based upon grouping plants of similar age and with similar design features to permit maximum use of a generic review approach and improve the efficiency of the review.
The NREP program will be used to assess the safety (design, and operational deficiencies, etc.) of all commercial operating power reactors.
NREP will be coordinated with the SEP and may assist with assessments on safety significance of deviations from safety criteria; backfitting decisions; and the identifica-tion of significant safety issues.
In FY 1982, a program pin will be developed to select sites, establish schedules, and determine the scope of the probabi-listic risk assessment studies.
Implementation of the NREP program plan is planned to begin in late FY 1982.
The duration of each plant review is estimated to be 1-2 years.
Beginning in FY 1984, ten plant reviews are scheduled to be completed per year.
The additional resources in FY 1983 are required to begin implementation of SEP Phase III and provide for the first full year of NREP.
.1/ Originally 11 plants were in SEP Phase II.
Dresden 1 is shutdown indefinitely and will not restart before 1986.
NRR has accepted the licensee's proposal to defer the SEP review.
16
(Dollars in Thousands, except whole dollars in narrative material)
I
)
!q j Nuclear Reactor Regulation - continued Operator Licensing.
FY 1981 = $1,643 FY 1982 = $4,040 FY 1983 = $3,590 (11)
(23)
(33)
The activities associated with operator licensing include the preparation, administration, and grading of examinations for the licensing of Reactor Operators (R0s) and Senior Reactor Operators (SR0s), the annual requalifica-tion of R0s and SR0s, and the certification of training facility instructors.
Other activities include operator examinations for non power reactors, training program audits, and a study to determine licensing requirements for plant maintenance and management personnel.
As the studies of the TMI-2 accident indicated, the ability of reactor operators to fully perform their duties under both normal and abnormal conditions is important to the safe operation of nuclear reactors.
The NRC, as a part of its effort to verify the competence and ability of reactor operators, has expanded the scope of the R0 and SR0 examinations, and has increased the overall passing score from 70 percent to 80 percent.
In FY 1981, NRR administered licensing examination to 725 R0s and SR0s and currently anticipates administering examinations to approximately 1200 R0s and e~3 SR0s in FY 1982 and 1400 in FY 1983.
Additionally, in FY 1982, NRR will
(
j begin an annual requalification program which will include simulator requali-N' fication examinations to all R0s and SR0s and written and oral examinations to 20 percent of the R0s and SR0s.
Previously, the NRR only audited the licensee requalification exams.
Also in FY 1982, NRR will begin to certify training facility instructors.
The operator licensing workload is shown below:
Examinations Site Visits FY 1981 FY 1982 FY 1983 Power Facility 3
23 31 Replacement /Requalification 200 232 Certification 48 52 60 Non power Facility 51 51 51 The overall resource requirements for this program remain essentially the same in FY 1983.
However, the NRC Staff will be conducting more of the R0 and SRO examinations, resulting in a need for less program support.
Casework........ FY 1981 = $15,752 FY 1982 = $17,272 FY 1983 = $14,660 m
(297)
(309)
(246)
(
)
i
/
' /
17
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued The Casework program includes the effort associatea with the safety, environ-mental, and antitrust reviews including the public hearing process, for appli-cations for a Construction Permit (CP), Operating License (0L), standard plant design approval, and early site approval.
Casework also includes topical report reviews and the necessary effort for the review and evaluation of the characteristics and processes unique to advanced reactors.
The CP review includes the review of an applicant's preliminary design of a nuclear facility and a detailed review of the site selection process as well as the safety and environmental aspects of the proposed site.
This review must be completed prior to the start of any construction.
A Limited Work Authorization may be issued prior to issuance of a CP if all environmental and site suitability considerations are satisfied.
The OL review involves the review of the final
~
design of the plant.
This phase starts approximately three years prior to the expected fuel load date.
The standard plant design concept offers an oppor-tunity for reactor designers and architect / engineers to submit standard designs for review that can be referenced by future license applications.
Early Site Reviews are conducted to evaluate the environmental and site suitability aspects of sites to be used in future CP applications.
Topical Report reviews are conducted on technical reports submitted by industry organizations (usually reactor vendors or architect / engineers) on subjects related to nuclear reactors, and their associated systems or operation.
For all casework activities, the staff performs independent detailed audit calculations to verify applicant results in certain selected review areas critical to safety.
NRR will continue to:
review license applications to ensure that safety and environmental reviews are conducted in a manner consistent with the protection of the public health and safety, the environment and in accordance with anti-trust regulations; and schedule reviews te ensure the review process will not unnecessarily be a critical path item that would delay the reactor fuel load and startup testing.
The major effort in the operating 1icense review area has been to ensure that the TMI related requirements and new safety requirements have been met prior to issuing new operating licenses and to minimize delays in the review and hearing processes for near-term OL applications.
The NRR has also been working to adapt the TMI-2 Action Plan to the pending construction permit (CP) and manufacturing license (ML) applications.
This has resulted in issuing to all applicants the guidelines (NUREG-0718, " Proposed Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License" and the proposed CP/ML Rule) the staff will apply in the review of applications for cps and MLs.
l The NP,C Caseload Forecast was used to project the number of applications docketed and under review.
The number of licenses expected to be issued during the planning period is based on the December 1981, Monthly Status Report to the House Appropriations Subcommittee on Energy and Water Development.
In developing the case review resource requirements for OL applications, NRR 18
l l
(Dollars-in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued l
used plant specific milestone dates for facilities scheduled for completion in FY 1981-1983.
For plants scheduled for completion in FY 1984 and beyond, a standard 31 month schedule to conduct the review and hearing process was assumed.
Also, the applicant's construction completion date was used as the NRC decision date.
The OL resource requirements were based'on 20 professional staff years / review.
This is an increase of 6 professional staff years above the previous budget estimate but less than the manpower expenditures NRR has.
been experiencing on cases currently under review.
The increase is primarily a result of implementing the TMI-2 Action Plan and increased depth and scope of the reviews.
Technical areas which have had an increase in the scope and-depth of review include control room designs; management and organization; operating procedures (normal and emergency) and startup test; qualification of safety-related equipment; chemical analysis; fire protection; accident evalua-tion; radiological assessment; systems reliability and systems interaction.
The resource estimates for the CP and ML applications in-house were determined on a case specific basis, dependent on the number of non-TMI open issues and the staff's TMI-related requirements (described in NUREG-0718 and the new proposed CP/ML rule) and the expected CP or ML decision date.
The only-new CP application forecast for the planning period is the resumption of the review for the Clinch River Breeder Reactor (CRBR).
Resource estimates for the CRBR S
review include the necessary effort tc resume the review begun in 1974 and J
terminated in 1977 and are based on the assumptions that the open issues identified from the previous review, the applicable TMI-related requirements and any other NRC requirements adopted since 1977 would have to be resolved.
The following table summarizes the OL and CP/ML applications under review and the planned licensing action completions in FY 1981-1983.
Types of Reviews FY 19813/
FY 19821/
FY 1983 /l OL Applications:
under review 31(48) 32(52) 31(46) completed (4)
(10)
(18)
CP/ML Applications:
under review 5(15) 6(16) 3(5) completed 2(9) 2(4)
Non power reactor renewal applications:
l.
under review 26 25 21 completed 2
6 10 1/ Numbers in parenthesis represent the number of units.
The resource decrease in FY 1983 is primarily a result of. fewer units under review for operating licenses and construction permits.
Also, for those plants O
scheduled to receive an OL for.FY 1983, the major portion of the NRR resources
, Q required for the review will have been expended'in FY 1981 and FY 1982.
19
.-3
---,..-y-,,_..v-,-,
--,.c
,.-y 3_,.
-e-,,,,.,
-y,
,,rm-
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued Safety Technology.
FY 1981 = $5,735 FY 1982 = $7,642 FY 1983 = $12,490 (131)
(76)
(91)
The Safety Technology program is directed at developing independent agency positions on significant issues that relate to the safety aspects of reactor design, construction and operation and to establish an integrated program to develop, review and maintain licensing and regulatory requirements.
The activities encompassed in this program include:
Unresolved Safety Issues (USIs) - An Unresolved Safety Issue is a matter which affects a number of nuclear power plants and poses important questions concerning the adequacy of existing safety requirements for which a final resolution has
~
not yet been developed.
The issues involve conditions not likely to be acceptable over the lifetime of the plants it affects and thus must be analyzed on a case by case basis pending generic technical resolution.
During FY 1981, the staff developed final technical resolution for five USIs.
The expected resolution of seven USIs during FY 1982 will bring the total number of USIs technically resolved to 18.
In FY 1983, NRR will continue to develop resolutions for nine USIs (comprised of four remaining from the original group, four new USIs identified during FY 1981, and one new USI identified so far in FY 1982) plus any additional USIs that may be added during the remainder of FY 1982.
Four USIs will be resolved during FY 1983.
And two new issues are projected to be identified in FY 1983 and in each fiscal year thereafter.
Generic Issues - Includes the development of technical positions on issues that relate to the safety or environmental aspects of nuclear power plant design, construction, or operation.
These tasks are conducted in support of iicensing activities.
The generic issues programs are described in NUREG-0410 "NRC Program for the Resolution of Generic Issues Related to Nuclear Power Plants" and NUREG-0660 "NRC Action Plan Developed as a Result of the TMI-2 Accident" During FY 1980 and FY 1981, NRR developed technical positions for generic tasks identified in NUREG-0660.
During FY 1981, 135 of these TMI tasks were approved for implementation by the Commission and are specified in NUREG-0737,
" Clarification of TMI Action Plan Requirements" There are approximately 90 TMI Action Plan Issues in the areas of engineering, systems integration and human factors requiring further technical development.
During FY 1982, NRR will apply resources to the resolution of all remaining priority 1, most priority 2, and a few priority 3 items.
NRR will complete its effort to reprioritize all generic safety issues identified in NUREG-0410, others which have arisen since publication of NUREG-0410 (other than those identified as USls) and unresolved TMI Action Plan items.
These issues will be reprioritized in terms of significance to health and safety based on potential risk reduction and cost.
The results of this reprioritization will form the basis for the NRR plan and schedule for the resolution of the remaining generic safety issues.
Based on the reprioritization conducted during FY 1982, NRR will develop or modify Task 20
(Dollars in Thousands, except whole dollars in narrative material)
G )
Nuclear Reactor Regulation - continued Action Plans for the resolution of the highest priority generic safety issues during FY 1983.
NRR will also review, analyze, and develop NRR positions on the basis of the results of these generic studies and incorporate the findings into regular staff practices and the regulatory process.
,l Risk Assessment - Includes the performance of reliability and risk assessments of nuclear power plants and their systems important to safety, with principal emphasis on new or potential safety issues; and the identification of high risk accident sequences for consideration in developing new regulatory and safety requirements or in evaluation of existing requirements.
During FY 1981, generic activities included an assessment of the risk of reactor coolant pumps seal failure, evaluation of the risks associated with emergency core cooling system switchover, evaluation of the reliability of lightning protection and evaluation of a postulated scram discharge volume loss of coolant accident.
In addition, considerable effort was directed toward including risk analysis techniques into the near term construction permit rule to identify changes to core and containment heat removal systems that would enhance safety at reasonable cost.
During FY 1983, NRR will perform c
studies of generic systems to assess potential improvement in reliability; perform risk studies of serious accidents to provide licensing guidance in rulemaking and research functions; factor degraded core / core melt analysis
(
experience into risk related aspects of rulemaking; perform short reviews of b
the conclusions of risk studies of various operating reactors.
Research and Standards Coordination - Includes NRR activities involving the i
Office of Nuclear Regulatory Research (RES), including developing NRR research needs to support licensing activities, participation in research review groups, providing technical guidance for each research contract and participating in j
the review and development of standards (e.g., rules, regulatory guides, j
industry standards).
1 During FY 1981, NRR completed over 1300 actions related to research and standards coordination.
The research related actions included the review of approximately 20 user need letters, 50 research endorsements, 40 Research Information Letters, 610 research reports and the NRC Five Year Research Plan.
The standards related actions included processing 105 Regulatory Guides, 48 rule changes and reviewing 29 industry standards and 56 NUREGs.
Similiar levels of effort are expected in FY 1982 and FY 1983.
Operating Experience Evaluation - Provides for systematic assessments of reactor operating experience and interface with the Office for Analysis and Evaluation of Operational Data.
During FY 1981 and FY 1982, NRR's resources for operating experience evaluation have been applied to the licensing recovery effort.
NRR has increased its dependence on the Office of Inspection and Enforcement for routine reviews and O
on the Office for Analysis and Evaluation of Operational Data for more compre-V hensive evaluations of events for possible significance to safety.
During-FY 1983, NRR will perform systematic assessments of reactor operating experience with respect to facility performance and operational safety to detect 21
i (Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued patterns in abnormal occurrences, to identify precursors of possible hazardous events and to evaluate the adequacy of existing safety factors in design and operation of the present operating units and new ones as they go on line.
Regulatory Requirements - Maintain and update the standard technical specifica-tions for operating light water power reactors based on new regulatory require-ments, new technical considerations and operating experience.
Perform a continuing systematic evaluation of the adequacy of regulatory requirements for licensing and operation, including updates to the Standard Format and Content Guide.
During FY 1981, NRR completed revisions to about 200 sections of the Standard Review Plan to reflect the TMI lessons leained and to correlate with 10 CFR.
Three new staf f technical positions developed in NUREG-0651 " Evaluation of Steam Generation Tube Rupture Events", NUREG-0588 Revision 1 " Interim Position on Environmental Quality of Safety Related Electrical Equipment" and NUREG-0577 "Potentiai for Low Fracture Toughness and Lamellar Tearing on Pressurized Water Reactor Steam Generators and Reactor Cooling Pump" were reviewed in terms of regulatory requirements and recommendations concerning implementation were prepared.
During FY 1982 and FY 1983, NRR will manage and coordinate the Standard Technical Specifications program and all needed revisions to the Standard Review Plan; prioritize previously identified and new regulatory requirements on the basis of safety significance; review revisions to the Standard Review Plan and other proposed requirements in terms of value impact; audit new licensing actions and backfitting of new requirements; and provide technical engineering, systems integration and human factors support for these activities.
Code Analysis and Maintenance - Evaluate, modify, verify, and maintain analytical tools, such as computer codes, for the performance of audit calculations.
NRR continued review of vendor thermal-hydraulic analytical methods in FY 1981.
This included an assessment of operator guidelines, the review and evaluation
~
of transient events at operating reactors, TMI Action Plan items, and severe accident analysis.
During FY 1983, NRR will continue to evaluate licensee analytical codes relevant tc demonstrating compliance with licensing requirements; review anticipated submittals of advanced analytical techniques by industry; and provide an independent capability to use these codes for assuring' applicant /
licensee compliance with licensing requirements.
The resource increase in FY 1983 are primarily a result of the additional workload to review the highest priority generic safety issues identified by the FY 1982 prioritization effort.
These issues are being partially deferred in FY 1982 pending prioritization.
TMI-2 Cleanup.
..FY 1981 = $660 FY 1982 = $335 FY 1983 = $315 (23)
(20)
(17)
This activity, initiated in April 1980, provides the regulatory review, direc-l tion and oversight of the TMI-2 cleanup operations including the technical and l
management supervision of the related NRC inspection, licensing, analysis, 22
l l
(Dollars in Thousands, except whole dollars in narrative material)
~
Nuclear Reactor Regulation - continued public information, and government relations actions onsite, in the Middletown, PA office and in the Washington, DC area.
NRC will continue to ensure the maintenance of. protection of public health and safety and the environment during decontamination and disposal of radioactive waste from TMI-2.
In FY 1981, reviews and determinations were prepared for the environmental l
assessment related to the use of EPICOR-II for decontaminating water in the l
containment building and the Final Programmatic Environmental Impact Statement related to " Decontamination and Disposal of Radioactive Waste from the March 28, 1979 accident at TMI-2" was issued.
During FY 1982 NRC will, in cooperation l
with the Department of Energy (DOE), develop and implement plans for the safe disposal of radiologically contaminated materials resulting from TMI-2 cleanup activities.
In FY 1983, the NRC will continue to maintain coverage by the NRC technical staff at the site to review and approve licensee cleanup activities, to oversee implementation of these activities so as to ensure adequate protection of public health and safety, to verify that NRC rules and regulations are being followed, to prepare necessary environmental assessments for the various phases of the TMI-2 cleanup process and to revise technical specifications as needed to assure adequate protection of the public health and safety.
Conduct special evaluations of problems that arise during the course of facility decontamination and of fuel removal and disposal.
Also, in cooperation with
(
the Department of Energy, Electric Power Research Institute, and General Public utilities, plan and conduct an investigation of the TMI-2 cleanup process on decontamination technology, radioactive waste handling, and fission product release, transport, and disposition.
Information obtained will be used te ensure that cleanup activities are conducted in a manner that will minimize risk to public health and safety.
Assess the er.vironmental impact of each phase of the TMI-2 cleanup effort.
Supplements to the Programmatic Environmental Impact Statement will be prepared and issued as needed.
Management Direction and Support............FY 1981 = $0 FY 1982 = $250 FY 1983 = $100 (47)
(47)
(45) l Tais effort includes the three major functions necessary to support the NRR regulatory and licensing activities.
Director's Office - Consists of the Director, Deputy Director, and the Planning and Program Analysis Staff.
The Director develops and administers regulations, policies, and procedures required for regulating nuclear reactors; provides overall management and~ guidance on major program goals and objectives; and performs other functions necessary to execute the NRC reactor licensing program.
The Planning and Program Analysis Staff provides administrative support for managing and coordinating NRR programs and resources.
The staff establishes priorities, schedules, and resource l y/
allocations; forecasts resource needs; and performs long-and short-term program planning.
The staff also manages all personnel administration l
matters and prepares, reviews, and recommends administrative operating l
procedures, policies, and directives.
In addition, the staff provides technical coordination and oversight for resolution of special technical t
problems.
23
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Reactor Regulation - continued Support to Others - Direct technical assistance to other NRC offices (except the Office of Nuclear Regulatory Research), other Federal agencies, and support of international technical exchange programs.
Corrtspondence - Respond to Freedom of Information Act and Privacy Act req ests and to other inquiries from the Administration, Congress, other Federal and State agencies, and the general public.
In FY 1983, NRR will continue to provide the policy management, direction, technical and administrative assistance to ensure that the functions of the office are carried out efficiently and effectively; provide on a limited basis NRR technical staffing support as requested; and continue to respond, in a timely manner, to correspondence.
O e
l l
O 24
t (Dollart in Thousar es, excep' whole dollars in narrat've material) 9 f!UCLEAR FECULATORY C0f f1ISSION - centinued i
I n s p e c t i o n a r d E n fo rc ene r.t............................................
569,850 l
EUfiNARY OF II.SPECTIC.E lND ENFORCEf:EUT ESTIMATES BY Fb%i10N l
Actual FY 1981 Estimate FY 1981 Estinate FY 1983 l
Salarios a Benefits
$13.9EE S41,470 541,810 Program Support
' 1P4 9,?91 11,400 Administretive Support 6,837 c.360 10,910 1
1 revel 3,895 5.190 5,330 Equipment 794 923 400 Total Obligations L,668 SSE 23T 369,850 People (873)
(985)
(995) i The Iespectier and Enforcer.cnt persernel requirer;.ents and prcgram support funding requirements (primarily contractual support with DOE !abcratories l
and private contractors) have been allcceted as shcun below.
The narrativc that follows provides.iustification to support these requireme.tc.
Actual FY 1981 Est'nate FY 1982 Estinate FY 1983 Doliars People Dollars People Dollars People t
i Reactor Engineering and
{
Ccnstruct ion Progran S 461 161 5 1,0)G 1c2 S 1,810 188 j
%acter Operations i
j Prtg ram 524 E50 563 280
?,1C0 304 l
Radiological Safety l
Prograr:
?,062 160 2,594 167 2,460 170 Safeguards Program 1,135 75 753 84 1,410 81 Eriergency Pt eparedncss Proqran 1,951 60 3,050 73 2,330 72 Enforcement, Invest. &
Special Programs 1,038 c4 1,288 107 1.200 107 Managerent Direction S Support 13 73 33 81 30 73 j
57,184 UI 3 9,291 W
S11,400 99b i
l.
The tr.ission of the Office of Inspection and Enforcenent is to ensure through inspectier., investication, and enforcement that f acilities and materials under NPC jurisdiction are constructed, cperated and used in a manner which prctects the public and the environment.
The functions of the Office are:
to inspect, i
investigate, enforce, participate in the liccnsing process, evaluate and inforn.
Workloads primarily ccnsist of:
(1) reactor f acilities - nuclear power plants (under construction. being tested or in commerciel operation), non-power (test i
and research) reactors; (2) fuel facilities and nuclear materials licensecs; l
and (3) vendors - nuclear steam system suppliers, nuclear architect / engineers dnd other major nuc1 car system cer:ponent suppliers.
!' S 25 l
l
(Dollars in Thousands, en ept whole dollars in r,arrative material)
Inspection and Enforcement - continued Scheduled Activities Routine Inspections:
a carefully constructed program of inspection performed on a continuing basis to evaluate the licensee's activities within the context of his ultimate responsibility for public protection.
The thrust of this effort is to critically examine, by systematic selection, samples of licensee controls de-signed to prevent conditions that might threaten the public and/or the environ-ment.
To ensure uniformity of inspection, this program is documented by written guidance, which provides a consistent path for assurance of licensee performance and problem identification and generally involves four basic types of inspection activity:
Confirming the management effectiveness of the quality assurance and quality control (QA/QC) program for the design, fabrication, construction, testing and operation of facilities.
Directly verifying licensee and system performance by means of direct observation and independent measurement.
Reviewing the licensee's basic systems and procedures to be certain toey conform with requirements, are technically sound and are properly imple-mented.
Analyzing the licensee's records of operation and interviewing licensee personnel to confirm that actions called for by the prescribed systems a.id procedures are routinely followed.
Emergency Prepaiedness Safety Evaluation Reviews:
an appraisal of a licensee's capability to properly respond to any emergency at his nuclear facility which serves as an input to the licensing process.
Performance Appraisal Inspections:
comprehensive examinations that focus on licensee performance; inspection program effectiveness; and inspector objectivity from a national perspective.
Systematic Assessment of Licensee Performance (SALP):
a comprehensive annual appraisal of power reactor licensees designed to improve licensee performance; improve the NRC regulatory program; identify other than average licensee per-formance; and provide a basis for management allocation of NRC resources.
Information Dissemination:
IE disseminates information on regulatory actions taken by IE and on operational problems / events that occur at licensed facilities.
Information is distributed through various sources such as notices, bulletins, circulars and press releases.
As appropriate, information is provided to the Commission, other NRC offices, other government agencies, licensees, and the public.
Unscheduled Activities Reactive Inspections:
inspections to either assure the adequacy of licensee response to incidents and accidents or to assess licensee compliance with special requirements imposed through bulletins, orders, etc.
26
(Dollars in Thousands, except whole dollars in narrative material) m inspection and Enforcement - continued
(
)
\\._j Investigations:
in-depth evaluations conducted in response to an event or alle-gation which may arise from inspections, required licensee reports, or allega-tions made by licensee employees, rambers of the public, and/or public interest groups.
The objective is to esta'lish the facts, determine the significance of the particular condition, and take appropriate corrective action.
Enforcement:
a program aimed at achieving public safety by (a) assuring opera-tion within requirements; (b) correcting areas of noncompliance or poor practice; and (c) deterring further noncompliance.
The enforcement program includes a clearly delineated and evenly applied series of deterrents that escalate accord-ing to the nature of the offense and the past history of licensee performance.
Sanctions available to the NRC include Notices of Violation, Civil Monetary Penalties, Orders to Cease and Desist, and Orders to Suspend, Modify, or Revoke Licenses.
To strengthen the enforcement process, the NRC has been granted increased civil penalty authority from Congress.
This provides substantial civil penalties of up to $100,000 for each safety violation (including licensee's failure to submit required reports of safety-related information) with no upper limit on combined violations.
In dealing with licensees who do not comply with NRC requirements, NRC emphasizes prompt and vigorous enforcement.
In any case, licensees who are unable or unwilling to comply or whose operations represent a threat to the public health and safety will not be permitted to operate.
Incident / Accident Response:
when necessary the NRC Operations Center is activated and an Emergency Response Team is dispatched to the site to CN (a) monitor and evaluate the situation; and (b) provide advice /information
(
/
to the licensee, state / local government of ficials, other federal agencies and the public.
Reactor Engineering and Construction Program FY 1981 = $461 FY 1982 = $1,010 FY 1983 = $1,810 (161)
(193)
(188)
The Reactor Engineering and Construction Program includes administering inspection programs and policies, conducting inspections, recommending changes in licenses and standards, and notifying licensees of generic problems.
This program includes all field resources applied to engineering inspections at power reactor sites and inspection of licensee contractor and vendor activities including the quality control and assurance program--inspectors, branch and section chiefs and direct clerical support personnel.
It also includes headquarters management personnel plus program support and technical equipment funds dedicated to this program.
The Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1975 charge the NRC to regulate the production and use of nuclear materials and to promulgate regulations to protect the health and safety of the public.
NRC rules and regulations require licensees to construct nuclear reactors in such a manner that when they become operational they will pose no threat to the public and the environment.
The resources reflected in this program are required to:
(a) inspect and evaluate the construction of nuclear power plants, thereby assuring the public that licensees are fulfilling this aspect of their responsi-
, p/
g bilities; and (b) adequately inspect certain licensee vendors and contractars to assure that they maintain adequate controls to inspect reactors in commercial i
V operation to assure that systems and/or plant modifications are in accordance with applicable codes and standards.
27
y c
w
--a
-._---.n.---
-s
.m (Dollers in Thousars. except whole dollars in narretise materiall Inspection and Enfrrcement - continued At Pcwer Reactor tites This portion cf the program consists ci conductinci both routine (scheduled) ard reactive (unscN duled) inspections.
The routine cu:.penent crrsists of a series of preplanned accit type inspections designed to astere that licensees havr He required ccr.trols in place to preven + adverse situations f rom occurring.
It is comprised of cultidisciplinary inspections conducted on a schedule cor.sistent with the licensee's constructior activitics plus insrections of rccctors the+
hcve progressed bevond the ccnstructior phaso into commercis cperation.
For these reactcrs, the insrcctions art cenducted du ing baseline and in-service examinations as well as during perioos of major modification.
The reactive component consiets of inspections conducted in respense to events and conditions that gcrerally cri6nate fron either licensee reported events or generic problems.
Nuclear reactors inspected are those in the stagc prior to receiving a construc-tion prmit (CP), but authori::ed tc proceed with construction work under a lim'ted work authoriation (Lh'A); those ir early construction (first two years); mid-construction (third erd fourth yeers); late construction (fifth and sixth years):
[
those in pre-crerational testing; and those with cperating licenses.
l Inspections are perferred by both region-based and resident inspectrrs.
Residents f
assume a portion of the inspecticn activity previously conducted by recien-based inspectors and provide a substantial incrr.ase of direct verification of licer.see perfcroance thrcugh direct F servation end independent measurements.
The region-based support consists of in-depth, specialized technical inspections.
In addition to region-based and resident inspecticns, licensee problems / corrective actions anc perfornt.rce are routinely evaluated.
Reactor worklcad is displayec below:
1/
1/
FY 1983_/
1 FY 1981 FY 1982 Pre-censtruction Permit Units 7.00 7.00 0
Early Stege Construction Units 27.25 21.00 F. 00 Mid Stage Construction Units 19.50 15.50 7.25 Late Stage Constructior Units 21.00 17.25 18.00 Pte-operatien Test Units 17.75 23.00 13.50 Units with 0perating Licenses 73.5C 82.25 100.25 Breeder Reactor 0
1.00 1.00
-1/ Power reactor worklcads are calculated on a cuarterly t, asis to incorporate any phase changes that are projected within each year.
For example, a reactor unit projected to be in the pre-operational test phase in the first quarter is ccunted as.25 units against that phase with the remaining.75 counted against reactor units with an OL.
This method of worklcad identification r?akes staff-year planning more precise.
In FY 1981, five (5) additional resident inspectors were assigned to con-
{
struction sites bringing the total number of residents assigned to construction sites to 24, 28
(Dollars in Thousanas, except whole dollars in narrative materiai)
Inspecticn and Enforcement - continued Also during FY 1981, inprcvements were made to the construction inspection prog ram.
One such improvement was the establishment of a trial progran for team inspections cf construction reactors.
Inspections utilizing a "tean" epproach were ccmpleted at eight (8) reactor sites.
The team inspection apprcach will be used at selected constructier sites in FY 1982-FY 1983.
Program support and technical equirnent funds were used tc ccnduct independent measurement efforts in compositior, strength and fracture toughness of material samples in FY 1981.
A ncr-destructive examinction (NDE) van was purchased and delivered in late FY 1980. During FY 1981, van equiptrent was purchased. calibrated and installed.
The van is used to perfora ultrasonic examinations of welds, metallic surf aces, concrete samples, piping, etc.
Primary attention includes verificaticn of technical accuracy of construction work at sites where significant ellegaticos have been received and where the rcutine inspection program identifies a break-down in the licensees quality assurance progran.
During FY 1981, the van was used at Beaver Valley and Three Mile Island.
In FY 1982 ard FY 1983 planned site visits include WNPS e2, Zim,er and several plants in Regions II and IV.
In FY 1982, eleven (11) additicnal residents will bc assigned to constructicn sites achieving 100% coverage by resident inspectors at construction sites having 15% or more of the construction work completed.
(A)
Program support and technical equipment funds in FY 1982 will be used to conduct increased independent measurement efforts in:
ccmposition, strength and 'racture v
toughness of material samples; and ultrasonic, radiographic anc retallurgical tests of welds and ioints used in reactor construction.
s l
l Also in FY 1982, the NRC is initiating efforts in support of construction permit and licensing reviews of the Clinch River Breeder Reector (CPEP.).
The CRBR with its ligeid metal technology poses a significant new workload for IE as it cur-rently has no inspcction staff or headquarters engirecring expertise for this type plant.
Because it is a prototype plant the inspection activity will need to be more intense than icr a pressurized water reactor or boilina water reactor (PWR/BWR).
Staff effort will be needed initially to assess the status of the CRBR in terms of components already manufactured and in storage, those in the manufacturing process, those in the design stage, and to orient the inspection program to focus on the most critical areas.
Existing inspection procedures for PWRs and BWRs have only limited application.
Headquarters staff with specialized knowledge in the area of liquic cetal technology will need to be hired during the FY 1982-FY 1983 timeframc to plan the inspection program, write new inspec-tion procedures, modify portions of the existing vendor inspection program, and resolve technical problems with the field inspectors es well as the licensing and research staffs. Also during FY 1982-FY 1983 e litated inspection staff will be needed which will initially focus its entire attention on equipment that has been procured, tested, and stored at the site and other components that are in some stage of Iaanuf acture/ design.
At this stage, the inspection program will also focus on the quality assurance program at vendor facilities.
(a)
After CP issuance (FY 1984), additional inspection staff will start the on-site
'ul construction inspection program with mest of the early effort cencentrating on the quality assurance (QA) program.
29
(Collars 4r Thousands, except whole dollars in carrative material)
Inspection and Enforcement - con t i r:uM In FY 1%3 fewer resident inspectors wil' be reauired tc maintair. !00^ coverace at constructicn sites due te the declirn #n the nurber of sites (20} having reactors under construction.
The reductior, in staffi.c requested in FY 1983 cccpared to FY 1982, primarily r
resu'ts fror a cecline in the number of rtcctors urpr-construction.
Progra surport furts requc.sted in FY 1983 escr the FY 1982 level wil' provide highly specialized contracter assistarce beyond the capebility of the IE staff for the CPM?. and ccrcontrated non-dest ructive exrninations (l:DE) at selected ccnstruction sitri using the I:rF van.
FY 19P? technicei equipme"' funds will be used to sonrert the imE van.
At Vcodors and Contractors Inspections at venerrs and cortractors stcrted in FY 19 M because o# a signifi-cant number of orrblens at licensee facilities traced to faultv uork by con-tractors and vendors utilizcd by the licensee in facility design, constructirn and testing.
The I;RC relies Fcevily on this program tc attest to the quality of safety-related componenu. Approximetely 50' cf the safety-related equipment orchlens that are reported can be attributed to vendor activities.
In cortrast to individual utility licensees,flRC has the across-industry perspective of thesc equipment problems, which is needed to recognize and deal with tt'se that are gcreric in nature.
Inspectors review cocumented procedures, interview personnel, and exanine bott designs ano hardware to determine if adequate quality control precedures have been prepared and are being followed.
Licensees remain responsible for final product acceptance.
fiRC presently conducts a procrarr of inspection for vendors, architect engineers anc nuclear ster.n systen suppliers. Approximately 300 inspections will be con-ducted anrually by f7C inspectors. Action has been taken to increase enphasis on the inspection o# architect engineers and nuclear stean systen suppliers.
flany ir.spections are conducted in response to feedback of licersr.e problens.
f;RC initiated a trial prcqram with the American Society of t'echanical Engineers (ASf'E) to test the use of third-party inspection systens as a neans of supple-menting NRC inspections. Adoption of the third-party inspection systems would expand and strengthen NRC inspection of nechanical component nanufacturers. ?!RC has recommendcd that ASME incorporate changes to their auality assurance require-ments, so + hat they are compatible with the NRC, as a prereauisite for acceptance.
Acceptance is anticipated in late FY 1982 ; subscquently, this progran will be established or a routine basis.
Durinc FY 1981,f;FC inspectors conducted inspections / investigations at power reactors, reactor component vendors and contractors, and at independent testinq l abora tories. The vendor inspection program has been restructured to place nore emphasis on technicel evaluations of vendor products and services in addition to existing hardware quality assurance verifications.
O 30
(Dollars in Thousends, except whole dollers in narrative cateriell Inspection and Enforcement - continued Planned vendor and contractor inspecticns are as follows:
Inspections FY 1982 FY 1983 Reactor System 30 30 Component 100 100 Reactive 120 120 Equipment Qualification 20 20 Curing FY 1981, NRC (IE) and the Institute of Electrical and Electronic Engineers (IEEE) reached agreement on the need for establishing a laboratory cccreditetier program for the environmental qualification of safety-related equipment.
The IEEE agreed to develop the accreditation program and authorized funds to support the development and initial implementation of the precran.
The NRC also indepen-dently tests selected components to assess their ability to withstand environ-mental conditions.
In FY 1981, the NRC began conducting three (3) independent tests (at Landia Labs) en electrical components that the NRC suspects may not be environmentelly qualified. These tests should be completed in late FY 1982 or early FY 1933.
By early FY 1982, it will be required that ell safety-related equipment requiring environmental qualification be qualified in accredited testing laboratories.
FY 1982 program support funds will provide contractual assistance for inspection (3
of laboratory testing programs and to witness testing of selected safety sensi-(v) tive electrical equipment.
In FY 1983, additional pregram support funds requested over the FY 1982 level are to provide increased contractual support commensurate with the proiected peak workload, to inspect laboratory equipment qualificetion testing programs and to witness testing of selected safety sensitive electrical equipment.
Reactor Operations Program FY 1981 = $524 FY 1982 = $563 FY 1983 = $2,160 (250)
(280)
(304) 1he Reactor Operations Program includes adninistering inspection programs and policies, conducting inspections, recommending changes in licenses and standards, and notifying licensees of generic problems.
This program includes all field resources applied to reactor operational safety inspecticns--inspectors, branch and section chiefs, and direct clerical suppcrt personnel.
It also includes headquarters mar.egement personnel plus program support funds dedicated to this prog ram.
The Atonic Energy Act cf 1954, as amended, and the Energy Reorganization Act of 1975 charge the NRC to regulate the production and use of nuclear materials and to promulgate regulations to protect the health and safety of the public.
NRC rules and regulations require licensees to operate their facilities and use nuclear material in a safe manrer. The rescurces reflected in this program are required to inspect, and evaluate the operational safety of nuclear reactors p) thereby assuring the public that licensees are fulfilling this aspect of their
' ;V responsibilities.
31
(Dollars in Thousands, except whole dollars in rarrative material)
Inspection and Enforcement - continued The reactor operations inspection program consists of conoucting both routine (scheduled) and reactive (unscheduled) inspections.
The routine component consists of a series of preplanned, audit type inspections designed to assure that licensees have the required controls in place to prevent adverse situaticr.s f rom occurring. The reactive ccmponent consists of inspections conaucted in response to events and conditions that generally emanate from either licensee reported events or generic problems.
Nuclear reactors inspected are:
power reactors in pre-operational testing; startup testino; commercici power operation; and non-power (test and research) reactors.
The operational inspections performed at pcwer reactors are " phase" oriented.
During the pre-operational and startup testing phases, inspection emphasis is placed on test management, procedures and results.
Licensee tests are witnessed, test results are independently evaluated and licensee evaluaticns of test re-sults are reviewea.
During the commercici power operation phase, the inspection program focuses on:
periodic verifications of licensee and system performance by means cf direct NRC observations; reviews of basic systems and procedures that licensees follow to be certain that they conform v;ith requirements and are technically sound and properly implemented; analyses of re:ords of licensee operations and interviev:s of licensee personnel to confir that prescribed proce-dures are routinely fellowed; examinations of licensee review and audit committee actions; changes to the cuality assurance progran; and personnel /orcanization changes.
In addition to region-basea and resident inspections, licensee problems /cor-rective actions and performance are routinely evaluated.
The inspection program will continut to place emphasis on direct observation of plant operations at each nuclear reactor unit.
The majority of this effort will be performed by resident inspectors.
Inspection program emphasis fer the resi-dent inspectors is placed on operational safety verification.
Activities range from independently confirming the operability cf a selected engineerina safety system to observing control room operations.
By conductino these types of inspection activities and providing some limited inspection coverage on each shift, it is believed that the assurance of safe operations car, be improved.
Reactor workload is displayed below:
FY 19811/
FY 1982 /
FY 19831/
1 Pre-operation Test Units 17.75 23.00 13.50 Startup Units 2.25 9.00 18.00 Operating Units 71.25 73.25 8?.25 Non-power Units 84.00 84.00 84.00 1/These workloads we calculated on a quarterly basis to incorporate any phase changes that are projected within each year.
For example, a reactor unit projected to be in the pre-operational test phase in the first quarter is counted as.25 units against that phase with the renaining.75 counted against reactor units with an OL.
This method of workload identificetion makes staffyear planning more precise.
32
(Dellars in Thousands, cxcept whole dollars in narrative material)
[')
, Inspection and Enforcement - continued By the end of FY 1981, 117 resider.t inspectors had been assigned to sites having One or more reactor units in oper6 tion or in pre-operational testing.
procram suppert runds were used to provide contractual assistance in the ncchan-l ical, electrical, civil and structural engineering fields to Ossist IE in event evalu0 tion and bulletin followup.
Approximately 62 bulletins and other notices were issued in FY 1981, to notify licensees of specific potential operating safety problems and to ask for or reconvend actions to resolve these problems.
The number of resident inspectors assigned to sites having one or more reactor units in operation or pre-operational testing in FY 1982 remains unchanged from rY 1981. All new reactor units in pre-operational testing or in operation in FY 1982 crr at sites where one or more residents are already assigned.
program support funds in FY 1982 will bt used to provide the same contractual assistarce as was provided in fY 1981.
In FY 1983, twelve (12) additional positions are requested to assign resident inspectors to operating reactor sites as reactor units advance from the con-struction phase to the pre-operational test phase.
Regional inspector growth can be attributed to an increase in the number of reactors in startup and in operation compared to FY 1982.
\\
U In FY 1983, Odditional program support funds will be used to assist the IE staff in performing evaluations of licensee response and compliance with operating safety bulletins. Contractor assistance is required to support the IE staff in areas of electrical, mechanical, metallurgical and civil engineering.
These evaluations are performed for each licensee who receives a bulletin.
Due to significant safety concerns, it is important that thorough and timely bulletin response evaluations be perforued to assure an adequate response frora cach licensee and to determine if regulatory changes are needed.
Each of these eval-uations represents a peak workload, not only in tenns of ef fort, but also in terms of the highly specialized skills required.
The increase in f Y 1983 program support fun'is over FY 1982 will also be used to conduct a one-time intensive inspection of licensee compliance with 10 CFR 50.48 and Appendix R - Fire protection, to establish a firm baseline which will then be followed by the traditional audit inspection approach.
This type of intensive examinatien has proven very valuable in both the health physics appraisals at reactors as well as the ongoing emergency preparedness appraisal activity.
Radiological Safety Togram FY 1981 u $2,062 FY 1982 = $2,594 FY 1983 = $2,460 (160)
(167)
(170)
The Radiological Safety Program includes administering inspection programs and p) policies, conducting inspections, reconenending changes in licenses and standards, and notifying licensees of generic problems.
This program includes all field gL/
resources applied to radiological safety inspections--inspectors, branch and 33
(Dcllars in Thousands, except whole ccllars in rarrative material)
Inspectior, ar.d Enforcenent - continued section chiefs and direct clerical support personnel.
It also includes head-quarters program management perscnrel plus program support and technical equip-r.:e r t funds dedicated to this program.
The Atomic Ercrqy Act of 1954, as amcoded, and the Energy Reorganization Act of 1975 charge the flRC te regulate the production and use of nuclear materials and to promulgate regulations to protect the health and safety of the public.
NRC rules and regulations require licensees to operate their facilities and use nuclear naterials in a safe manner.
The programs and resources reflected in this progran are recuired to inspect and evaluate the use of ruclear materials at fuel cycle facilitics, materials licensces, and nuclear reactors, thereby assuring thc public that licensees are fulfillirg this aspect of their responsibilities.
The radiological safety inspection program consists of conducting two types of inspections:
(1) Safety inspections (incluoing transportation) at fuel facilities er.d materials licensees; enc (2) reactor health physics inspections which examine liccnsee's radiation / environmental protection, environnental monitoring, and radwaste processing and control prcerams.
The routine component consists of a series of preplanned et.dit type inspections designed to assure that licensces have the required controls in place to prevent adverse situations from occurring.
The reactive component consists of inspections conducted in response to events and conditions that gererally emanate from either licensee reported events, rcocompliance findings, unsafe operations, and generic problems.
Fuel facilities inspected are:
uranium oills, uranium hexafluoride facilities, fuel processing and fabrication (uranium and plutonium) facilities, spent fuel reprocessing facilities, short-term fuel storage facilities, and facilities for storage and disposal of high level radicactive wastes.
The inspection program for fuel facilities presently requires, in frequency of inspection, four inspections per year of reprocessirg, plutonium processing and fuel fabrication plants; thrca inspections per year of uranium processing and fuel f abrication plents; and one inspection each year of uranium hexafluoride conversion plants, uranium mills, reactor fuel storage sites, R&D f acilities, and decommissioned facilities.
Liaterials licensecs inspected are those authorized by tne flRC to possess and use byproduct, source and special nuclear materials in radiography, medical, academic, and industrial applications as well as to operate low-level nuclear
~
waste disposal facilities.
Inspection frequency and depth for these licensees is based on rist potential. The highest risk category, priority 1 (about 25 licensees) is inspected twice each year; priority 2 (about 350 licensees) is inspected once each year; priority 3 (about 200 licensees) is inspected once every two years; priority 4 (about 3500 licensees) once every three years; priority 5 (about 100 licensees) once every five years; and priority 6 (about 1200 licensees) once every 10 years.
The remaining licensees about (3300) in the lowest frequency grouping (priority 7) are not routinely inspected, but 5%
are inspected on a sample basis each year.
34
(Dollars in Thousards, except whole dollars in narrative material)
/9 Inspection and Enforccment - continued
(
)
U fluclear reactors inspected are power reactors in pre-operational testing, startup testing, and in commcrcial operation, as well as non-pcwer (test and research) reactors.
Workload for the radiological safety inspection program is displayed beicw:
Fuel Facilities FY 19811 1/
1/
FY 1982 FY 1983 Fuel Reprocessing 4
a 4
Plutonium Processing 7
7 7
Uranium Processing 16 16 16 UF-6 Processing 2
2 2
Uraniun Mills 13 13 13 R&D Fecilities 4
4 4
Fuel Storage Facilities 2
2 2
Deconmiissioned Fecilities 2
2 2
fiaterial Licensees Manufacturino & Distribution, Academic, Other 3,373 3,474 3,491 Industrial / Medical 4,906 5,053 5,150 Radiography / Waste Disposal 379 379 379 Pcwer Reactors Pre-operatioT Test Units 17.75 23.00 13.25 A)
(
Startup Units 2.25 9.00 18.00 V
Operating Units 71.25 73.25 S2.25 Non-power Units 84.00 84.00 84.00
-1/ Power reactor workloads are calculated on a quarterly basis to incorporate any phase chances that are projected within each year.
For example, a reactor unit projected to be in the pre-operational test phase in the first cuarter is counted as.25 units against that phase with the remaining.75 counted against reactor units with an OL.
This method of workload identification makes staff-year planning more precise.
In FY 1981, a reactor health physics appraisal effert was completed. This appraisal program was a team effort to judge the overall adequacy and ef fective-ness of radiation protection programs.
Based on appraisal program findings the inspection program was changed to emphasize more direct observation of licensee performance with less reliance en written records.
Also, in FY 1981 a health physics appraisal program for uranium mills was begun. This program is basically an extension of (in terms of application of new inspection methode-logies) the appraisal program at reactors.
Initial feedback from inspections already completed are promising. This program will be completed in FY 1982.
Program support funds were also used to perform aerial radiclogical surveys at reactor sites and fuel facilities; continue the confirmatory independent mea-surements program utilizing contractor laboratories and region-based radio-
[m) logical measurements vans; continue and expand state contracts; and continue (j
the off-site radiation measurement program - thermoluminescent dosimeter (TLD) network.
35
(Dollars in Thousands, except whole dollars in narrative materiali Inspection and Enforcement - contiaued FY 1981, technical equipment funds wre used to purchase porteble radiatier, survey eqcipment, fixed radiation survey equipment and replacer,ents for personnel dosi-meter radiation badges and TLD badges for the TLD retworks at reactor sites.
Two additional radiological measurcuent vans were purchased and equipped.
Three more states were addcd to the TLD/environtenal progran.
Fight information notices, seven circulars and three bulletins were issued resulting from TFI followup investigatien reports, in FY 1982, proaram support funds v.ill r rovide for completien of the uranium mills health physics apprcisal prograr.. Also, new radiological protection plans fcr orcrating power reactors will be process (d.
These plans will form the basis for review and revision of the health physics inspection program at nills and opera-ting powcr reactors.
In FY 1982, independent measurement tests of environmental and effluent sanples will be increased by 101 and then maintained at that level through FY 1983.
State contracts and TLD network prcorans will be continued at essentially FY 1981 levels.
FY 1982, technical equipment funds will be used to purchase portable and fixed radiation survey equipment, essentially equippire all regions with the necessary technical equipment to fully carry out the health physics inspection progran.
Additional inspector staffing required in FY 1983 is based on an increase in the number of reactors in startup and in operation corpared to FY 1982.
In FY 1983, progran support funds will continue the independent rceasurements pro-gram, the TLD network, the state contracts program and aerial surveys at essen-tially FY 1981 levels.
The slight reduction in program support funds is due to the corrpletion of the uraniem mills health physics appraisal study in FY 1982.
FY 1983 technical equipment runds will provide the regienal offices with pertable radiation survey equipment, a fully equipped radiation measurement van (replace-ment), fixed laboratory equipment, and personnel monitoring equipment enabling them to independently measure and verify licensee sanpling results.
Technical equipment furds will provide replacement personnel dosimeter radiation badges, rad-survey meters and TLD badges.
As a continued response to the Three Mile Island accident, five (5) health physicists have been assigned to the TMI-NRC team to work directly on cleanup activities.
Safeguards Program FY 1981 = $1,135 FY 1982 = $753 FY 1983 = $1,410 (75)
(84)
(81)
The Safeguards Program includes administering inspection programs and policies, conducting inspections, recommending changes in licenses and standards, and notifying licensees of generic problems. This program includes all field resources applied to safeguards inspections--inspectors, branch and section chiefs, and direct clerical support personnel.
It also includes headquarters program management personnel plus program support and technh.al equipment funds dedicatcd to this program.
36
(Dollars in Thousands, except whole dollars in narrative material)
(']
Inspection and Enforcement - centinuea The Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1975 charge the NRC to regulate the production and use of nuclear materials and to promulgate regulations to protect the health and safety of the public.
NRC rules and reetlations require licensees to control and accecnt for certcin types of special ruclear materials; tc protect nuclear matericls, reactor f acilities end fuel facilities against thef t. sabotage, or unauthorized entry; and to ensure that special nuclear naterial anc irradiated fuel is transported safely.
The resources reflected in this program are required to inspect, and evaluate the safeguaroing of nuclear facilities and n.aterials thereby assuring the public that licensees are fulfilling this aspect of their respensibilities.
The safeguards inspection progran consists cf conducting two types of inspections:
(1) naterial accountability inspections designed to assure that the licensees are adequately controliing and accounting for special nuclear material; and
(?) physical security inspections designed to assure that licensees are ade-auately protecting facilities ar,a shipments and their contents against theft, diversion and sabotage.
Both types of inspections can be routine (scheduled) or reactive (urscheduled).
The routine component consists of a series of pre-plannec audit type inspecticns designed to assure that licensees have the required controls in place to prevent adverse situations from occurring.
The reactive cor.penent consists of inspections conducted in response to events and conditions that generally emanate either fron licensee reported events. noncom-pliance findings, unsafe operaticns and generic problems.
(m)
Facilities inspected include:
power reactors in the pre-operational test phase; V
power reactcrs with operating licenses; non-power (test and research) reactors; spent fuel storage facilities; certain materials licensees; licensees who trans-port special nuclear material both within and outside the United States; and licensees who transport irradiated reactor fuel.
Workload for the safeguards inspection program is displayed below:
FY 19811/
1/
FY 1983 I 1
FY 1982 Pre-operation Reactor Test Units 0
23.00 13.50 Reactors with Opciating Licenses 73.50 82.25 100.25 Non-power Reactor Units 84.00 84.00 84.00 Enriched Uraniun Fuel Facilities 13.00 13.00 13.00 Decommissioning Facilities 6.00 6.00 6.00 Materials and Spent Fuel Storage Facilities 37.00 36.00 37.00 Shipnents 68.00 10.00 10.00
~1/Pcwer reactor workloads ere calculated on a quarterly basis to incorporate any phase changes that are projected within each year.
For example, a reactor unit projected to be in the pre-operational test phase in the first quarter is counted as.25 units against that phase with the remaining.75 counted against reactor units with an OL.
This method cf workload identification makes staff-(p) year planning more precise.
v
l (DcIlars in Tbcusands, except whole t'cIlars in narrative material)
J_nspection and Enforcement - continued During FY 1981, the safeguards inspectiun progran nodules underwent a thoreugh review.
The prrerm was recuted in scope and prioritized in terrs of safety significance.
Also during FY 1981, a semi-annual revirv> ef the physical ecurity end naterial control and accounting inspection programs was begun.
Thi' sched-uled review will allev, headquarters personnel to update revise or ireplemen t new programs to neet changing cperational requirerents.
Some of these reouire-nents cre new rules. fluctuations in operating reactor caseload, and availatrility of inepectors.
The inspector training prcgram was restructured to place greater emphasis on certificatien ci reinimum qualificaticos through riessroom treining
'nd on-the-job experience.
In FY 1981, prcgram support funds were used to provide contractual assistence to perform cerf irmatory independent measurements of licensee initiated measureiient procrans. Alsc, these fords providea contractual support to assist NRC personnel ir reviewing and revisinc t he safeguards inspection program.
FY 1981 technical equipment funds provided irtependent ceasureme it equipment for regional fixed laboratories and portable equirr:ent for use at the site cnd in the nobile var,s.
FY 198? ptceram suppert runds will be used to continue FY 1981 contractual ef fert <, at a reduced level of ef fort.
FY 1982 technical couipmen+ funds wili be used to purchase independent measure-nent equipment for recicnal of fice laboratories and for on-site use in mobile wns.
The staf fing reduction in FY 1983 is based on a reduced requirement for program development /apprais al ef fort.
The requested increase in FY 1983 program support funds will provide contractual support for a one-tine in-depth inspectier of licensee compliance with new rules.
Thic. will also include uncovering any generic problems, establishing inspection parameters for new rules, and recommending additions to the inspection program.
FY 1983 technical equipment fcnds are needed for replacement equipment and spare pa rt s.
-Progran FY 1981 = $1,951 FY 1982 = $3,050 FY 1983 = $2,330 (60)
(73)
(72)
The Emergency Preparedness Progran includes activities designed to determine that the state of on-site and off-site energency preparedness provides reasonable assurance that adequate protective neasures can and will be taken in the event of rediolceical emergencies.
The staff accomplishes this by conducting an on-site emergency preparedness implementation appraisal that evaluates the adequacy of the licensees emergency plans and procedures for compliance with the recula-tions and the effective implementation of the plans and procedures through the i
38 I
(Dollars in Thousands, except whole dollers in narrative materirl',
Inspection ard Enforcement - continued observation and evalertion of annual exercises.
In performing this evaluation, the NRC takes into consideration fincings submitted to it by the Federal Emergency flanagemcrt Agency (FEMA), from FEf!A's evaluations of the state of preparedness of State and local governments.
The program also includes activities designed to assure that the NRC develops and maintains an adequate ircident response capability.
This program includes all fiel resources applied to licer. sing and appraisal activities--inspectors, branch and sectior. chiefs, and direct clerical support personnel.
It also includcs the headquarters staff plus program support and technical equipment funds dedicated to this program.
The Atomic Enercy Act of 1954, as amended, and the Energy Reorgarization Act of 1975 charge the NRC to regulate the productior and use of nuclear materials and to promulgate regulaticrs to protect the health and safety of the public.
NRC rules and regulations require all nuclear power reactor licensees, beginning on April 1,1981, to have upgraded emergency plans and procedures implemented, and to exercise these plans arnually.
The resources contaired in this program are required to:
(a) evaluate the state of emergency preparedness at nuclear power facilities to determine that on-site and off-site personnel, plans, procedures, and equipment are adequate to take protective measures in the event of a radio-logical emergency; (b) provide sections of Safety Evaluation Reports (SERs) as an input to the licensing process; (c) cevelop guidelines and criteria fcr use by licensees and NRC personnel to upgrade response capabilities; and (d) develop NRC emergency response capabilities.
O f
)
For existing operating reactor licensees and near-term operating license appli-U cants, an initial license review is conducted.
This initial review is an in-depth / comprehensive evaluation which licensees and applicants must pass to keep or receive an operating license.
Subsequent reviews (perforred annually) are less comprehensive (approximately 1/3 of the elements of the initial review are evaluated annually).
If a licensee is not in compliance with Federal rules, the licensee is cited and may receive no more than 4 months to correct deficiencies.
Failure to comply with NRC rules and regulations can result in enforcement actions and can eventually lead to plant shutdown.
Emergency preparedness plans for construction permit applicants are also reviewed for conformance to rules and regulations and an SER input is prepared.
These reviews, evaluations, SERs and any resulting testimony are prepared by inspection teams consisting of regional and resident inspectors, contractors and heacquarters staff members.
The present program is effective in providing for increased emergency prepared-ness capabilities.
During FY 1981, approxinately 405 of the nuclear power plant sites were visited for initial implementation reviews and evaluations and in almost all cases, some deficiencies were found in the state of emergency prepared-ness.
Licensees were notified of the deficiencies and are correcting them. Also during FY 1981, excicises were observed at about 50% of the nuclear power plants.
The NRC's emergency preparedness program is related to the emergency preparedness progran of FEMA which is responsible for upgraded emergency ren'nse capabilities of State and local governments in support of nuclear power pl v t?.
FEMA and the NRC have entered into a Memorandum of Understanding to coordinde the two agency's (o) respcnsibilities and efforts in this area.
There is no duplication of effort
'd because FEMA is responsible for all State and local planning and NRC is responsi-ble for all licensee planning.
39
(Pellars in Thousards, except whole collars in narrative material)
I_nspectien and Enforcement - continued Also during FY 1981, DOE (Sandic Laboratory) conpleted their work on the con-ceptual design of the Nuclear Data Link (NDL).
This work is contained in a six volume report which was publishea curing FY 1981.
In addition, an NDL prototype program is being developed to allow the NRC tc determine whether the NDL approach is the best way for the NRC to accomplish its emergency roles.
The first phase of an NDL program will be initiated with the developmcnt of a test and evalua-tion plan by an outside contractor and the lease of one cr more comnercially developed data systems for evaluation.
During Fi 1981, a reouest for proposal (RFP) was issued to have a systens integrator available in FY 1982 cnc FY 1983 to assist in the development of the NDL prototype.
FY 1981 program support funds were used to provide contractual support of the eval-uation of energency response plans and to participate in the conduct of licensee excrcises and drills.
FY 1982 progran support funds will be used to provide ccrtractual support of the evaluaticn of erergency response plans, to participate in exercises ano drills, to upgrade the NRC operations center and to develop a prototype Nuclear Data Link (NDL).
Evaluation of connercially available data and display systems ir FY 1982 and FY 1983 will enhance the NDL prototype development, testino, and evaluation and provide pertinent technical informaticn, cost dLta and a better understanding of system applicability to the NRC emergency response role.
This information will assist the Commission and the Congress in making a decision on the final implementation of an NDL system presently scheduled to begin in FY 1984.
It is anticipated that all initial appraisal visits and all first year exerciscs will be completed by April 1982.
The prcgram will then move into the second phase where upgraded emergency response facilities, communications systems and proce-dures are verified to be installed.
'n FY 1982, technical equipment funds are to be used for purchase of equipment for the NDL prototype.
The reduction of one (1) pcsition in FY 1983 is due to a reduced level of effort associated with the NDL prototype program.
~
FY 1983 program support funds will provide for a reduced level of effort for emergency response plans, exercises and drill observatiens.
The NDL prototype will be completed in late FY 198? or early FY 1984.
Enforcement, Investigations
& Special Programs FY 1981
$1,038 FY 1982 = $1,286 FY 1983 = $1,200 (94)
[107)
(107)
Most of the programs and resources described here complement the programs of inspection described above in the Reactor Engineerina and Construction, Reactor Operations, Radiological Safety, Safeguards, and Emergency Preparedness programs.
It includes the NRC's enforcement program through which notices of violation, civil penalties, and orders are issued when it is deemed that these sanctions are necessary to assure safety and compliance with NRC requirements.
Also in-cluded is the staff dedicated to the investigation function, which augments the 40
4 x
(DcIlars in' Thousands, except whole dollers in narrative material)
Inspection and Enforcement - continued inspection 8ctivity.
It has been organized to systematically collect ard examine
~ evidence or other relevant information to uncover the facts and establish the truth concerning matters of interest to the NRC.
Both headquarters and regional effices have staffs who manage and cor.c'uct enforcenent and investigation activ-ities at their respective levels, with technical assistance being provided from each of the major programs as needed. Most investigations are conducted in the regions.
Enforcement actions emanate from the regions with the headquarters becoming involved in escalated actions referred to headquarters by regional offices.
During FY 1981, approxinately 50 eleveted enforcement actions were issued (re-sulting in civil penalties, orders, or headquarters notices of violation).
The average elapsed tir.e frem issuance of the inspection report to initiation of the enforcement action was 18.2 calendar days.
In aadition, this prograu also contains the Performance Appraisal Team whose purpme is to focus on licensee performance, inspection progran effectiveness and inspector objectivity frem a national perspective.
The Perfornance Appraisal Team provides the capability to assess management control systems of ruclear power plant licensees on a national basis.
It also provides the NRC with a capability to obtain additional assurance of inspection prcgram consistency and inspector cbjectivity by conductiro comprehensive inspections and comparing their resuits to those documented in earlier regional / resident inspections.
The n
Performance Appraisal Team completed ten (10) program and maragement appraisal (V
)
inspections in FY 1981. Approximately the same number of appraisal inspectichs will be completed in FY 1982 ano FY 1983.
This program contains the IE specialized technical training function.
Newly hired and existing inspector personnel, as well as other NRC personrel, must be sufficiently knowledccable of the facilities, processes and activities within their technical purview.
Training must be provided to assure that necessary levels of knowledge are developed and maintained. Most perscnnel hired to be f uture inspectors do not possess all the technical and regulatory qualifications required to properly perform their duties. Moreover, existing personnel must be kept abreast of current industry state-of-the-art.
Students receive this train-ing thrcuch classroom instruction by NRC instructors, on-the-job training con-ducted by senior resident inspectors. technology and codes courses developed and taught by contractors, simulator training by NRC instructors at TVA simulator facilities to enable NRC personnel to obtain " hands on" experience, and program self-study training and "off-the-shelf" courses related to the NRC inspection and enforcement program.
J in FY 1981, all of IE S specialized technical training function had been consoli-dated in Chattanooga, Tennessee. Approximately 2,200 student-weeks of technology, codes, simulator, etc., training for IE inspectors ano NRC personnel were con-ducted during FY 1981.
In FY 1982, approxinately 2,700 student-weeks will be cceducted, and 3,200 student-weeks are planned for FY 1983.
In FY 1983, IE plans to initiate construction of its own technical training facility at the Tennessee Valley Authority (TVA) site to be co-located with t*!e TVA simulators.
41 s
(Dollars in Thousands, except whole dollars in norrative material)
, Inspection and Enforcement - contirued In FY 1981, procran support funds werr used to provido specialized technical training to IE inspectors and other NRC personnel using reactor simulator fccilities and contracted courses in reactor design, techmology, codes, con-structico practices, and operation.
Progran suoport funds in FY 1982 and FY 1983 will be used for the same purpose as in FY 1981.
Funding fluctuations correspond to variations in inspector training workload, primarily reduced resident inspecter training requirements.
The Office of Inspecticn and Enf orcen.ent underwent a reorganization in FY 1981.
A key element rf that reorcanization was to place all prograr development acti-vities in one organization.
The objective of centrclizing this activity was to f ocus concentrated attention to the task of maintaining a dynamic inspection pro-gra. that reflects changes in regulatory requiren:cnts, priorities, and resources availatle.
During FY 1981, an interim routine inspection progran structure for reactors under censtruction and in operation was draf ted.
This structure uses a prioritiiing concept which concentrates inspection efforts on activities most inportant to nuclear safety.
In addition, the vendor inspection program has been restructured to place more emphasis en technical evaluations of vendor products and services in addition te cristing hardware quality assurance verifications.
In FY 1982 and FY 1983 more work will be done to streamline and prioritize the inspection prer;ran, to assure that it is designed tc provide the maximum payoff in terms of snf ety assurance.
Management. Direction &
~Suppoe FY 1981 = $13 FY 1982 = $33 FY 1983 - $30 (73)
(81)
(73)
The resources reflectcc above are used to provide overall support to IE's main function.
For IE Headauarters it includes the Office of the Director and the headquarters administrative staf f.
For the regions, it includes the otiices of tne Administrators, Division Directors and the indirect portion of the admin-istrctive staff.
The Of fices of the Regional Administrators arc responsible for executing the inspection and enforcement programs and for managing assigned resources.
The Regional Administrators also serve as the NPC's senior of ficial in their respec-tive geographical areas.
The regional administrative support persennel included in this program provide clerical / administrative support to all regional staff members (except direct support which is included in each of the major programs).
The headquarters administrative staf f performs the following activities:
Plans, budgets, evaluates, ano controls resaurce utilization.
Administers contracts.
Operates and maintains office-wide management information systems.
42
(Dollars in Thousands, except whole dollars in carrative material) inspection and Enforcement - continued Provides centralized headouarters administrative support (e.g., file rooms, nail distributufon, word processing).
Pest nds to Freedom of Information Act (F0IA) requests.
Conducts studies on alternative policies and programs.
l Program support funds included in this program are for information system studies, udnagement studies, and organization effectiveness studies.
The administrative support funds are for the regional offices and provide for:
rent and utilities; telephone and non-telephone communications; purchase, lease, l
and maintenance of office equipment; general office supplies and materials; space alterations; and health servi es.
O 1
1 s
l i
l 43 1
1 1
b..
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Commission - continued Nuclear Material Safety and Safeguards.................................$37,385 Summary of Nuclear Material Safety and Safeguards Estimates by Function Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Salaries and Benefits
$11,524
$12,860
$12,330 Program Support 15,812 18,692 17,300 Administrative Support 6,191 6,830 7,220 Travel 409 535 535 Equipment 0
0 0
Total Obligations
$33,936
$38,917
$37,385 People (293)
(320)
(308)
The Office of Nuclear Material Safety and Safeguards is responsible, under the Energy Reorganization Act of 1974, for the health and safety licensing of all NRC-regulated activities except reactor operations and for the total safeguards licensing for all licensees including reactors.
In addition, it exercises lead NRC responsibility for the transportation of nuclear materials.
The licensing and regulating responsibilities include such cases as the licensing
(
of the national high-level waste repository, away-from-reactor storage
{
facilities, uranium mills, storage of fresh fuel at reactors, and fuel I
O manufacturing plants, as well as a wide range of radioisotope uses.
Safeguards responsibilities include the review and assessment of safeguards against potential threats, thefts and sabotage involving licensed facilities and materials.
To carry out these responsibilities and other statutory requirements, NMSS has established and manages three, major programs:
Fuel Cycle and Material Safety, Safeguards, and Waste Management.
These programs are managed and supported by the Management Direction and Support Program.
The narrative that follows provides justification for the personnel and program support funding for these programs.
Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Dollars People Dollars People Dollars People Fuel Cycle and Material Safety
$ 4,097 92
$ 3,482 102
$ 3,580 100 Safeguards 2,510 90 2,735 94 2,440 86 l
Waste Management 9,205 93 12,375 105 11,180 103 Management Direction and Support 0
18 100 19 100 19 Total
$15,812 293
$18,692 320
$17,300 308 J
44
(Dollars in Thousands, except whole dollars in narrative material)
O Nuclear Material Safety and Safeguards - continued V
Summary of Fuel Cycle and Material Safety Program Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Dollars People Dollars People Dollars People Fuel Cycle Licensing
$2,765 35
$2,177 39
$2,130 38 Transportation Safety 345 12 305 17 450 17 Materials Licensing 987 45 1,000 46 1,000 45 Total
$4,097 92
$3,482 102
$3,580 100 Fual Cycle Licensing FY 1981 = $2,765 FY 1982 = $2,177 FY 1983 = $2,130 (35)
(39)
(38)
The goal is to protect the health and safety of workers and of the public and to protect the environment through the administration of an effective licensing program for fuel cycle plants and the review and approval of remedial actions for formerly licensed and known contaminated sites.
This includes:
performing safety and environmental reviews on new, existing, and formerly licensed facilities; performing radiological assessments of formerly licensed sites and DOE sites as required by law; upgrading radiological contingency plans for coping with accidents; improving the efficiency and effectiveness of the licensing process; and formulating and coordinating standards and confirmatory p
research requirements for resolving fuel cycle issues.
i\\
The major objectives are:
(1) Perform safety and environmental assessments for fuel cycle facility licensing decisions and remedial actions for contaminated formerly licensed sites, develop and implement improved radiological contingency planning requirements and coordinate the review of operational data and licensee event reports, (2) Develop regulations, regulatory guides, and technical positions for fuel cycle facilities which includes the periodic and systematic reevasuation of existing regulations, and (3) Formulate and coordinate requirements for standards and confirmatory research, review proposed and ongoing research projects, and assess other ongoing fuel cycle activities for changes in the licensing process.
The segnificant accomplishments during FY 1981 were:
(1) Completed 115 licensing actions for uranium fuel cycle plants and facilities; completed the review of former byproduct, source, and special nuclear material licensee docket files; conducted radiological surveys of selected formerly licensed sites to evaluate radioactive contamination; conducted reviews of proposed actions for sites identified in the 00E n\\
Remedial Action Program; began review of radiological contingency planning
/
information submitted by licensees needing such plans; coordinated and expedited the review of operational data and licensee event reports; 45
(Dollars in Thousands, except whole dollars in narrative material)
Ih! clear Material Safety and Safeguards - continued developed and negotiated a Memorandum of Understanding with 00E for the West Valley Demonstration Project as specified in P.L.96-368, West Valley Demanstration Project Act; (2) Developed alternatives for waste handling within waste generating institutions and initiated a systematic review of the licensing program for fuel cycle facilities, and (3) Formulated and coordinated requirements for confirmatory research and standards in support of fuel cycle licensing; provided input, as appro-priate, to NRC's quarterly Abnormal Occurrence Report and incident reports; and evaluated Congressional acts and other mandates for incorporation of changes into the licensing process.
The significant accomplishments planned during FY 1982 are:
(1) Complete approximately 115 licensing actions for uranium fuel cycle plants and facilities; continue to conduct radiological surveys of formerly licensed sites, evaluate remedial actions for these sites which are known to be contaminated, to enable completion of this work in FY 1985; review remedial actions planned by DOE for DOE sites as required by law; consult with DOE and review its activities for the West Valley high-level waste solidification project, in accordance with P.L.96-368; and continue development and implementation of improved radiological contingency planning with emphasis on formalizing requirements, implementing require-nents, and testing licensee plans; (2) Systematically review regulations for licensing fuel cycle facilities and develop waste handling alternatives for waste generating institutions, and (3) Continue to formulate and coordinate research and standards requirements, evaluate ongoing research projects and review proposed new work; continue providing input to NRC's quarterly Abnormal Occu?rence Report and any incident reports; and continue to evaluate Congressional acts and other mandates for incorporation into the licensing process.
The significant accomplishments planned during FY 1983 are:
(1) Complete approximately 115 licensing actions for uranium fuel cycle plants and facilities; continue to conduct radiological surveys of formerly licensed sites, evaluate remedial actions for those which are known to be contaminated to enable completion of this work in FY 1985, and review remedial actions planned by 00E for their sites; continue consulting with 00E and reviewing its plan for the West Valley high-level waste solidifica-tion project including the waste removal system; and implement, as license conditions, onsite radiological contingency plans and emergency prepared-ness plans for licensees exhibiting potential for significant impact due to accidents; 46
1 (Dollars in Thousands, except whole dollars in narrative material)
T Nuclear Material Safety and Safeguards - continued (2) Continue the development of waste handling alternatives at waste generating institutions, and (3) Continue to provide input to NRC's quarterly Abnormal Occurrence Report i
{
and any incident reports.
1 i
The staf f year decrease results from reduced effort in reviewing regulations.
Transportation Safety FY 1981 = $345 FY 1982 = $305 FY 1983 = $450 l
(12)
(17)
(17) r The goals are to perform safety reviews for package designs and operations for j
shipment of radioactive materials as required by 10 CFR Part 71 to assure that they meet established NRC standards; to review package certification procedures and package standards; and to develop, maintain, and improve package analysis methods to assure quality and timely reviews.
i The major objectives are:
(1) Perform safety reviews of transportation package designs, maintain and improve standardized analysis methods, review licensee quality assurance programs, and maintain a registry of package users; (2) Develop regulations, regulatory guides, and technical positions for transportation activities; and 4
(3) Assess ongoing transportation activities.
The significant accomplishments during FY 1981 were:
(1) Completed 99 safety reviews of transportation package designs; maintained and improved heat transfer, shielding, and criticality computer programs with various input simplifications for more efficient analysis; performed 90 quality assurance reviews; and maintained a registry of package users; (2) Provided technical support for a systematic review of existing regulations i
for transportation of radioactive materials, and (3) Provided technical and policy input for the Office of Nuclear Regulatory-Research's conduct of the Modal Study.
The significant accomplishments planned during FY 1982 are:
3 (1) Complete approximately 108 safety reviews of package designs and maintain I.
a registry of users; maintain and improve heat transfer, shielding, and 2
criticality computer programs; and continue to perform approximately 45 quality assurance reviews; t
(2) Continue to provide technical support for the review and evaluation of
)
existing regulations, and 47 l
-mn n;-
g
,em---
,v
...n,--
,re-
.m e
w
-e ye
,~,,
-xre-g-a+
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and Safeguards - continued (3) Continue to provide technical and policy input for the conduct of the Modal Study and develop appropriate action plans for possible rulemaking or suggested changes to International Atomic Energy Agency (IAEA) rules.
The significant accomplishments planned during FY 1983 are:
(1) Complete approximately 115 reviews, including new designs, modifications of existing designs, renewals and administrative amendments; continue to maintain a registry of package users; maintain criticality, shielding and heat transfer computer programs and data base required to evaluate package designs; and continue to perform approximately 45 licensee quality assurance reviews; (2) Provide technical support for development of all NRC regulatory guides in the transportation area, and (3) Provide input to and assess results of modal-dependent package performance tests, and review the proposed revisions to the IAEA transportation regulations scheduled for issue in 1983.
The program support increase will be used to update and improve computer programs utilized for package analyses.
Materials Licensing FY 1981 = $987 FY 1982 = $1,000 FY 1983 = $1,000 (45)
(46)
(45)
The goal is to assure protection of worker and public health and safety through a system of licensing for the possession, use, transfer, and disposal of radioactive material (byproduct, source, and special nuclear material).
The major objectives are:
(1) Perform safety evaluations required for radioactive materials licensing in a timely manner so as to ensure safety and prevent delays in essential services, evaluate approximately 100 sealed sources and devices per year on a continuing basis, conduct licensing site visits on a continuing basis to confirm the validity of licensing actions, and provide technical assistance and training as requested by Agreement States; (2) Provide technical support for the development of regulations, regulatory guides, and technical positions for materials licensing, and (3) Assess ongoing materials licensing activities.
The significant accomplishments during FY 1981 were:
(1) Processed 5,151 new, amendment, and renewal licensing applications; evaluated 125 sealed sources and devices; established an NMSS licensing section in Region I to complement the existing NMSS licensing section in Region III; conducted 45 licensing site visits to confirm the validity of licensing actions; and furnished technical assistance and training to Agreement States; 48
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and Safeguards - continued (2) Continued a study to examine how operations at radiopharmaceutical facilities can be carried out to maintain occupational exposures and effluent releases at an "as low as reasonably achievable" (ALARA) level, completed a study on consumer products containing radioactive material, continued a study to improve the evaluation of sealed sources and devices.
initiated a study of the general license concept, initiated a study to analyze and improve the materials licensing process, and developed new licensing guides and amendments to regulations, and 4
(3) Coordinated license reviews with the Advisory Committee on the Medical j
Uses of Isotopes.
The significant accomplishments planned during FY 1982 are:
(1) Process approximately 5,100 licensing applications in a timely manner, evaluate approximately 100 sealed sources and devices, conduct licensing site visits to confirm the validity of licensing actions, continue to provide assistance and training to Agreement States, and initiate develop-ment of a prototype computerized Licensing Management System to provide a i
support system for materials licensing and to provide information to management regarding the performance of the licensing system ;
(2) Complete the study on maintaining occupational exposures and effluent releases at radiopharmaceutical facilities at ALARA level, complete a s
)
program to improve methods for evaluating and licensing sealed sources.
/
and devices, continue the study on the effectiveness of the general license concept, continue the analysis of the materials licensing process, and continue to develop new licensing guides and amendments to regulations; and (3) Continue to coordinate license reviews with the Advisory Committee on the Medical Uses of Isotopes.
The significant accomplishments planned during FY 1983 are:
(1) Review approximately 5,530 applications and take licensing actions in a timely manner so as to prevent delays in essential services, evaluate approximately 100 sealed sources and devices, conduct licensing site visits to confirm the validity of licensing actions and to determine whether current licensing practices are necessary and sufficient to adequately protect public health and safety with minimum government i
regulation, provide assistance and training to Agreement States, initiate a program which will result in the examination and certification of individuals to perform industrial radiography, and continue development of the prototype computerized Licensing Management System; (2) Complete a study on the effectiveness of current general license regula-
+
tions for controlling distribution, use, and disposal of devices containing ps byproduct material; complete the analysis of the materials licensing i
process; utilize the data base developed in the consumer products study r\\s_ /
to redefine N9C policy on consumer products and revise appropriate 49
l (Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and Safeguar_ds - continued regulations, as required; and develop standard licensing review plans to ensure uniformity of review and application of NRC regulations to all licensees; (3) Continue to coordinate license reviews with the Advisory Committee on the Medical Uses of Isotcpes.
The decrease in staff years results from reduced regulatory guidance development and reduced evaluation of existing regulations.
Summary of Safeguards Program Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Do l l a r:.
People Dollars People Dollars People Reactor Safeguards Licensing
$1,607 34
$1,445 37
$ 940 37 fuel Cycle facilities Safeguards Licensing 829 36 1,140 36 1,200 30 Safeguards Transporta-tion and Export Licensing 74 20 150 21 300 19 Total
$2,510 90
$2,735 94
$2,440 86 Reactor Safeguards Liconsing FY 1981 = $1,607 FY 1982 = $1,445 FY 1983 = $ 940 (34)
(37)
(37)
The goals are to assure the protection of the public health and safety and promote the common defense and security through licensing reactor safeguards.
The major objectives are:
(1) Perform safeguards licensing case reviews for reactor facilities; and (2) Develop safeguards regulatory policy and practices for reactor facilities.
The significant accomplishments during FY 1981 were:
(1) Completed 414 safeguards licensing actions required to issue or amend the licenses of power and nonpower reactors, performed licensing actions to implement IAEA safeguards at selected U.S.
reactors in accordance with the requirements of the US/IAEA agreement, completed field tests of reactor regulatory effectiveness review techniques of two reactor f acilities ;
(2) Provided policy guidance and technical support to develop, prepare and improve regulations affecting safeguards at power and nonpower reactor facilities such as publishing proposed amendments to 10 CFR Part 73 for Physical Protection of Formula Quantities of Strategic Special Nuclear Material at Nonpower Reactors; continued participation in i-teragency technical activities to strengthen IAEA Safeguards and the i.iplementation of the US/IAEA Safeguards Agreement.
50
.. _. _.. _ ~.,..
1 W
(Collars in Thousands, except whole dollars in narrative material)
/
Nuclear Material Safety and Safeguards - continued t
The significant accomplishments planned during FY 1982 are:
(1) Complete approximately 315 safeguards licensing actions which will include f.he review of contingency, guard training and 10 CFR Part 73.55 security j
plans; complete approximately ten licensing actions to implement IAEA i
safeguards at selected U.S. reactors; evaluate and assess the regulatory d'
ef fectiveness of safeguards rules and programs at about ten reactor i
facilities; develop review plans for use in licensing of reactor facilities; and 1
1 j
(2) Continue to provide policy guidance and technical support to develop,
{
prepare and improve reactor safeguards regulations; and ptovide consulta-tion to the IAEA in support of U.S. efforts to strengthen IAEA safeguards and to implement the US/IAEA Safeguards Agreement.
l The significant accomplishments planned during FY 1983 are:
(1) Complete approximately 400 safeguards licensing actions for reactor facilities, complete approximately ten safeguards licensing actions to implement IAEA safeguards at selected U.S. reactors, evaluate and assess the regulatory effectiveness of safeguards rules and programs at about six reactor facilities, and (2) Resolve generic policy and technical issues precipitated by Congressional, h
public and staff involving safeguards concerns; incorporate required
,_s/
changes in the regulatory base and review rules for appropriate cost effective modifications;.and provide consultation in support of U.S. efforts to strengthen and implement IAEA safeguards.
The FY 1983 program support decrease is the result of reduced technical support for the assessment of effectiveness of safeguards rules / program at reactors.
4 Fuel Cycle Facilities Safeguards Licensing FY 1981 = $829 FY 1982 = $1,140- FY 1983 = $1,200 (36)
(36)
(30) l The goals are to assure the protection of the public health and safety and promote the common defense and security through licensing fuel cycle facility i
safeguards.
l The major objectives are:
^
(1) Perform safeguards licensing case reviews for fuel cycle facilities, and (2) Develop safeguards regulatory policy and practices for fuel cycle facilities.
t The significant accomplishments during FY 1981 were:
O
'(1) Completed 195 licensing actions for fuel cycle facilities which included physical security plan reviews and material control and accounting (MC&A) plan reviews, completed safeguards licensing' actions to implement IAEA 51 i
r.
-. +
_ _,. - -, ~ _. -. - - _ _ ~ _ - - -, -.
(Dollars in Thousands, except whole dollars in narrative material) puclear Material Safety and Safeguards _- continued safeguards at selected U.S.
fuel cycle facilities, develooed review plans for use in licensing cf fuel cycle facilities, and (2) Provided policy guidance and technical support to develop, prepare and improve regulations affecting safeguards at fuel cycle facilities, such as the publication of advanced notification of rulemaking for the MC&A Reform Amendment; participated in interagency technical activities to strengthen IAEA Safeguards and the U.S. program to Provide Technical Assistance to IAEA Safeguards.
The significant accomplishments planned during FY 1982 are:
(1) Complete approximately 220 licensing actions for fuel cycle facilities; complete approximately five safeguards licensing actions to implement IAEA safeguards at selected U.S. fuel cycle facilities; evaluate and assess the regulatory effectiveness of safeguards rules and programs at about four fuel cycle facilities and reflect the results into the regulatory ba30, if required; perform MC&A data analysis of several fuel cycle facilities; update and develop licensing review criteria; and (2) Continue to provide policy guidance and technical support to develop, prepare and improve Safeguards fuel cycie facilities regulations, such as policy efforts which may include deregulation of low-enriched uranium and regulatory reform of nuclear material control and accounting for high enriched uranium; and provide consultation in support of U.S. ef forts to strengthen IAEA safeguards.
The significant accomplishments planned during FY 1983 are:
(1) Complete approximately 250 licensing actions for fuel cycle facilities; complete approximately five safeguards licensing actions to implement IAEA safeguards at selected U.S. fuel cycle facilities; evaluate and assess the regulatory effectiveness of safeguards rules and programs at about four fuel cycle facilities and incorporate the results into the regulatory base, if required; perform material control and accounting (MC&A) data analysis of fuel cycle facilities; and (2) Resolve generic safeguards issues and incorporate the results into the regulatory base, and support the IAEA Agreement.
l The decrease in staff years results from reduced scope of technical support for regulation development, reduced number of assessments at fuel cycle facilities, and reduced scope of analyses of inventory dif ference and shipper /
receiver data.
Safeguards Transportation and Export Licensing FY 1981 = $74 FY 1982 = $150 FY 1983 = $300 (20)
(21)
(19) l The goals are to assure the protection of the public health and safety and promote the common defense and security through licensing the transportation and export of nuclear materials.
52
._.~.
l (Dollars in Thousands, except whole dollars in narrative material) i Nuclear Material Safety and Safeguards - continued The major objectives are:
I (1) Perform safeguards licensing case reviews for transportation and export of nuclear materials, and (2) Develop safeguards regulatory policy and practices for transporation of
{
nuclear materials.
i The significant accomplishments during FY 1981 were:
(1) Completed 187 1icensing actions which included strategic special nuclear materials and spent fuel shipment route plan reviews, special nuclear material of moderate and low strategic significance reviews, physical 4
i security plan maintenance reviews, and nuclear material shipment monitoring; j
completed reviews of 208 applications for export / retransfer of nuclear materials; completed four country analyses describing the status of IAEA i
safeguards implementation; evaluated the regulatory effectiveness of contingency plans for transportation of spent fuel and strategic special i
nuclear materials; and (2) Provided policy guidance and technical support to develop, prepare and improve regulations such as publishing final amendments to 10 CFR Part 70, domestic Licensing of Special Nuclear Material, requiring physical protection for transient shipments, implementing documents and technical positions affe. ting safeguards for transportation and support of nuclear materials.
]
The significant accomplishments planned during FY 1982 are:
(1) Complete approximately 270 licensing actions which include spent fuel route reviews, special nuclear material of moderate and low strategic significance reviews, plan maintenance reviews, and shipment monitoring; complete reviews of approximately 220 applications for export of nuclear materials; complete approximately ten country analyses describing the status of IAEA safeguards; evaluate and assess the regulatory effectiveness l
of safeguards contingency plans for transportation of spent fuel and strategic special nuclear materials; and 1
(2) Provide policy guidance and technical support to develop, prepare and improve regulations; and develop implementing documentation and technical positions for export reviews.
The significant accomplishments planned during FY 1983 are:
(1) Complete approximately 320 licensing actions which include spent fuel route reviews, special nuclear material of moderate and low s Pategic significance reviews, plan maintenance reviews, and shipment monitoring; complete reviews for approximately 220 export applications;. complete
.approximately 15 country analyses describing the status of IAEA safeguards; i
evaluate and assess the regulatory ef fectiveness of safeguards contingency j'
plans for transportation of spent fuel and strategic special nuclear -
\\,/
materials;-and j
53
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and Safeguards - continued (2) Review rules and modify them to achieve increased cost effectiveness, analyze generic policy and technical issues related to safeguards transportation, and develop implementing documentation and technical positions for export reviews.
The FY 1983 program support increase will provide technical assistance to support the development of NRC export license application review criteria to fulfill NRC mandates in the 1978 Nuclear Non-Proliferation Act.
The decrease in staff years reflects a reduction in projected caseload of licensing reviews to be received in FY 1983 for reactor fuel shipments.
Summary of Waste Management Program Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Dollars. Peop_l e Doll a rs People Dollars People
~
High-Level Waste Management
$6,146 34 5 8,109 41 5 6,730 41 Low-Level Waste Management 2,077 28 2,400 30 2,350 29 Uranium Recovery Licensing 982 31 1,866 34 2,100 33 Total
$9,205 93
$12,375 105
$11,180 103 High-level Waste Management F Y 1981 = $6,146 FY 1982 = $8,109 FY 1983 = $6,730 (34)
(41)
(41)
The goal is to p. ovide reasonable assurance that high-level wastes (HLW) are disposed of without unreasonable risk to the health and safety of the public.
The major objectives are:
(1) Conduct the initial NRC activities associated with licensing a high level waste repository:
the on-site review of DOE's site screening activities, and the detailed technical reviews of DOE's site characterization reports, which are to be per formed on a schedule that will not delay implementation of DOE's program ;
(2) Develop technical and scientific information required for and publish generic regulations and regulatory guidance (technical positions and regulatory guides); and (3) Evaluate the overall DOE program content and progress and part;cipate in interagency activities and NRC high-level waste management related rule making and licensing proceedings.
The significant accomplishments during FY 1981 were:
(1) Began to apply models to assess groundwater flow in basalt; prepared a draft review plan for Site Charatterization Reports; expanded the initial assessments of DOE's screening activities in salt, basalt, and welded tuff; completed the review of DOE Site Screening reports for basalt; 54
(Dollars in Thousands, except whole dollars in narrative material) m Nuclear Material Safety and Safeguards - continued (2) Published the procedural portion of the high-level waste disposal regulation (10 CFR Part 60) as a final rule, and published the technical portion for public review and comment as a proposed rule, along with the supporting environmental assessment; issued the draft regulatory guide on the Format and Content of Site Characterization Reports for comment; issued one draf t technical position; and (3) Continued the review of the National Plan for Radioactive Waste Management; continued the assessment of the extent to which DOE's HLW programs are directed at developing the information necessary to comply with 10 CFR Part 60, and provided NRC evaluations to 00E; reviewed the draft EPA standard for the disposal of high-level waste.
The significant accomplishments planned during FY 1982 are:
(1) For basalt:
continue to review the DOE site screening investigations, and prepare for public comment a report on the NRC staff's analysis of the DOE Site Characterization Report.
For domed / bedded salt and volcanic tuff: continue to review the DOE site screening investigations and review site screening documents, and begin the development of models for assessing radionuclide transport in welded tuff.
Begin consultation with DOE on activities related to the solidification of liquid waste at West Valley, and provide comments on the West Valley environmental impact statement; (2) Complete preparation of the final technical rule and begin public hearings if required, begin development of support for preparation of format and content guides for the license application preliminary safety analysis report (PSAR) and the environmental report, issue three draft technical positions, and (3) Continue the assessment of the extent to which DOE's HLW programs are directed at developing the information necessary to comply with 10 CFR Part 60, and continue to provide the results to DOE; update NRC portions of the National Plan for radioactive waste management; and conduct a formal review of the EPA standard for the disposal of high-level waste.
The significant accomplishments planned during FY 1983 are:
(1) Continue review of DOE site screening reports; continue review of DOE site characterization reports and preparation of NRC analysis reports and advisory opinions for a basalt, a tuff and a salt site; continue review and consultation with DOE on activities related to the solidification of liquid waste at West Valley; develop a review plan for construction authorization; (2) Provide technical support for public hearings on technical rule; develop technical information for format and content guides; develop technical information for and publish technical positions to provide timely guidance to DOE on areas such as waste form integrity, waste / rock interaction,
/']
performance of shaft and borehole seals and radionuclide migration; and 55
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety a.d Safeguards - continued (3) Maintain an overview of the DOE research and development program and their generic field testing activities, review DOE waste management environmental impact statements, and provide high-level waste program area management.
The decrease in funds reflects increased reliance on DOE high-level waste management efforts.
Low-Level Waste Management FY 1981 = $2,077 FY 1982 = $2,400 FY 1983 = $2,350 (28)
(30)
(29)
The goal is to ensure that low-level waste (LLW) disposal facilities are constructed, operated, and closed in a manner which will protect the public health and safety and the environment.
The major objectives are:
(1) On a continuing basis, perform thorough, yet expeditious, safety and environmental assessments to provide the basis for licensing and regulatory decisions for LLW operations; as requested by the Agreement States, provide technical support to such States to assist them in carrying out their responsibilities; develop a capability for performance assessment; (2) Publish final regulations governing the disposal of low-level wastes by near surface disposal, and publish final amendments to the regulation governing the disposal of low-level waste by alternative methods, complete regulatory guides to support the regulation and to support amendments to the regulation; (3) Assess ongoing LLW management activities, such as the cleanup of Three Mile Island (TMI) waste generation, processing and storage; and LLW program area management, including participation in interagency LLW activities.
The significant accomplishments during FY 1981 were:
(1) Completed the licensing review of the NRC Barnwell special nuclear material license renewal; completed one minor license amendment; completed the draft Sheffield environmental assessment fo'r decommissioning; continued the developmant of license review procedures and performance assessment capability to be used for health, safety and environmental assessments; (2) Published a draft low-level waste regulation and completed the draft environmental impact statement (EIS) specifically addressing near surface disposal, began the analysis of comments on the drafts, and developed regulatory guidance in support of the regulation; and (3) Continued characterization and analysis of decontamination of waste resulting from the TMI accident; continued to evaluate waste generation, processing, and storage; continued assessing licensees generating signifi-cant low-level waste; completed a volume reduction policy Commission Paper.
56
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and SafeguarJs - continued The significant accomplishments planned during FY 1982 are:
(1) Complete approximately three licensing decisions (renewals, and/or amendments) for LLW disposal facilities; provide technical assistance to Agreement States supporting states' licensing decisions for LLW disposal facilities; complete final environmental assessment for Sheffield decommissioning; assist other NRC branches on licensing actions involving low-level waste; continue development of licensing review procedures and performance assessment capability to be used for health, safety, and environmental assessments; i
(2) Determine the scope, extent and initiate development of amendments to the regulation specifically addressing other than near surface disposal, publish regulatory guides to support the regulation, and I
(3) Continue characterization and analysis of decontamination of waste resulting from the TMI accident; continue to evaluate waste generation, processing and storage; provide LLW program area management.
The significant accomplishments planned during FY 1983 are:
(1)
Initiate the review of two applications for new commercial sites, complete j
two amendment reviews for commercial special nuclear material disposal, provide technical assistance to Agreement States that request technical
[
assistance, develop licensing review procedures and performance assessment
.\\
\\
capability, assist other NRC branches on licensing actions involving LLW; (2) Publish a final LLW regulation and final EIS specifically addressing near surface disposal, develop and publish draft amendments to 10 CFR Part 61 and a supplement to the environmental impact statement specifically I
addressing other than near surface disposal, publish regulatory guides, and (3) Continue to evaluate unique and significant waste; identify sources of low-level waste to assess characteristics and properties of as generated low-level waste, and to assess the effects of processing and storage on LLW disposal; and provide LLW program area management.
The decrease of one staff year is due to reduced support for regulatory guide development.
l.
Uranium Recovery Licensing FY 1931 = $982 FY 1982
$1,866 FY 1983 = $2,100 (31)
(34)
(33)
The goal is to ensure that uranium recovery facilities are constructed, operated, and decommissioned in a manner that protects the public health and safety and the environment, v
57
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and Safeguards - continued The major objectives are:
(1) Make licensing and regulatory decisions to assure that the preceding goal is achieved which includes activities to perform safety and environmental assessments required to provide the basis for licensing decisions for new uranium recovery operations; perform safety and environmental reviews of license renewal applications; perform safety and environmental reviews of license amendment requests for proposed facility modifications; issue license amendments to bring operating mills into compliance with new EPA radiation standards (40 CFR 190, Environmental Radiation Protection Standards for Nuclear Fuel Cycle Facilities, effective December 1, 1980 for milling facilities); review operating facilities' safety and environ-mental monitoring data and NRC inspection reports and issue license amendments where appropriate action is necessary; evaluate DOE remedial action plans, as mandated by Public Law 95-604, Uranium Mill Tailings Radiation Control Act of 1978; and provide technical assistance, as requested by Agreement States with respect to uranium recovery facilities, to assure technically satisfactory Agreement States licensing actions; and (2)
Improve the regulatory basis upon which licensing decisions are made.
The significant accomplishments during FY 1981 were:
(1) Completed decisions on four new applications for uranium recovery operations, issued three license renewals, issued 23 license amendments in response to requests for proposed facility modifications, issued 22 license amendments to bring operating uranium mills b,'o compliance with EPA radiation standards and with regulations from the Generic Environmental Impact S'atement (GEIS) on Uranium Milling reviewed 136 monitoring and inspection reports and took appropriate action when necessary; continued review of DOE plans for remedial action on 25 abandoned tailing sites, and provided technical assistance for 17 Agreement State licensing actions; (2)
Initiated and supported work on regulatory guides to properly support the l
uranium recovery program, provided technical support for research needed to wpport the licensing program and provided technical support to upgrade Agreement States regulatory programs as required by the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA).
The significant accomplishments planned during FY 1982 are:
(1) Complete decisions on approximately eight new facilities, issue approx-i imately six license renewals, issue approximately ten license amendments in response to requests for proposed facility modifications, review over 100 monitoring and inspection reports and issue license amendments where appropriate action is necessary, continue analysis and licensing of 00E remedial action sites, and provide technical assistance for approximately five Agreement State licensing actions, and O
58
I l
(Dollars in Thousands, except whole dollars in narrative material) r~s (v)
Nuclear Material Safety and Safeguards - continued (2) Continue support for regulatory guide development, provide technical support for research needed to support the licensing program, and assist in finalizing Agreement State agreements as required by UMTRCA.
The significant accomplishments planned during FY 1983 are:
(1) Complete approximately 12 decisions on new applications for uranium recovery operations, issue approximately eight license renewals, issue approximately 14 license amendments in FY 1983 in response'to requests for proposed facility modifications, review over 100 monitoring and inspection reports and issue license amendments where appropriate action is necessary, continue analysis and licensing of 00E remedial action sites, and provide technical assistance for approximately three Agreement State licensing actions, (2) Continue support for regulatory guide development, and provide technical support for research needed to support the licensing program.
The increase in funds is for safety and environmental reviews at NRC licensed facilities.
The decrease of one staff year is due to reduced support for regulatory guide development.
Summary of Management Direction and Support Program N
)
Management Direction and Support FY 1981 = 0 FY 1982 = $100 FY 1983 = $100 (18)
(19)
(19)
The goal is to ensure effective and efficient management of NMSS programs.
The director provioos overall management direction and policy guidance on major program goals and objectives.
The Program Support staff assists the NMSS Director by evaluating and assessing the effectiveness with which allocated resources are managed in NMSS programs.
In addition, the Program Support staff provides resource management, contractual, administrative, and other i
direct support to the Division program staff, as well as coordination with the EDO staff.
The major objectives are:
l (1) Provide overall managemer.; direction and policy guidance as necessary to l
achieve NMSS program goa's and objectives, (2) Conduct special independent technical and management evaluations of program resource utilization to ensure that programs are planned and executed in an efficient manner, (3) Manage the NMSS Program Planning and Status Assessment System (PPSAS) which provides NMSS managers with program and resource planning and p
status assessment information, 59 I-
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Material Safety and Safeguards - continued (4) Support NMSS programs by the placement of technical assistance projects with private contractors, DOE laboratories, and other government agencies, and (5) Provide administrative and personnel services required to operate NMSS programs.
The significant accomplishments during FY 1981 were:
(1) Provided policy guidance and management direction to resolve issues and restructured programs as necessary to accomplish the major objectives of NMSS within allocated resources, (2) Provided the NMSS Director, at his request, independent technical and
~
management assessments of selected technical programs, proposals and other issues which included the proposed annual budget submission, proposed mid year financial reprogramming, executive program analysis reports, Congressional budget testimony, and responses to Congressional inquiries, (3)
Implemented the full operational capability of the PPSAS budget subsystem, (4) Executed 99 procurement actions with private contractors and 123 procurement actions with DOE laboratories, and (5) Provided required administrative and perss.inel services which included responding to FOIA requests, controiling suspense items, controlling classified documents, evaluating resumes, and processing personnel action requests to the NMSS Director and Divisions.
The significant accomplishments planned during FY 1982 are:
(1) Continue to provide policy guidance and management direction to resolve issues and restructure programs as necessary to accomplish the major objectives of NMSS within allocated resources, (2) Continue to provide the NMSS Director, at his request, independent technical and management assessments of selected technical programs, proposals and other issues, (3) Continue to manage PPSAS and provide appropriate management information reports to NMSS program managers and the EDO staff, (4) Execute approximately 100 procurement actions with private contractors and the same number with DOE laboratories, and (5) Continue to provide required adnanistrative and personnel services.
O 60
(. collars in Thousands, except whole dollars in narrative material)
O Nuclear Material Safety and Safeguards - continued i
Q The significant accomplishments planned during FY 1983 are:
(1) Continue to provide policy guidance and management direction to resolve issues and restructure programs as necessary to accomplish the major objectives of NMSS within allocated resources, (2) Continue to provide the NMSS Director, at his request, independent technical and management assessments of selected technical programs, proposals and other issues, (3) Continue to manage PPSAS and provide appropriate management information reports to NMSS program managers and the E00 staff, (4) Execute approximately 100 procurement actions with private contractors and the same number with DOE laboratories, and (5) Continue to provide required administrative and personnel services.
\\
O 61 I
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Commission - continued i
Nuclear Regulatory Research...........................................$219,725 Summary of Nuclear Regulatory Research Estimates by Function Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Salaries and Benefits
$ 12,814 5 13,560
$ 13,000 Program Support 201,812 196,578 195,200 Administrative Support 4,496 4,900 4,600 Travel 545 725 725 Equipment 7,659 6,900 6,200 Total Obligations
$227,326
$222,663
$219,725 People (292)
(295)
(283)
~
The Nuclear Regulatory Resea,ch personnel requirements and program support funding requirements (primarily contractual support), have been allocated to major programmatic functions as shown below.
The narrative that follows provides justification in support of these requirements.
Actual FY 1981 Estimate FY 1982 Estimate FY 1983 Dollars People Dollars People Dollars People d
$ 46,182 20
$ 30,900 19
$ 30,000 17 LOFT 41,550 6
42,000 6
15,000 4
Accident Evaluation and Mitigation 26,324 23 33,100 25 47,200 25 Advanced Reactors 9,703 4
7,500 3
13,000 4
Reactor & Facility Engineering 28,405 56 33.800 57 38,000 56 Facility Operations and Safeguards 12,618 55 13,028 55 13,500 55 Waste Management 10,202 28 12,200 28 13,600 26 Siting & Environment 12,927 31 9,000 31 9,000 26 Systems & Reliability Analysis 13,901 44 15,050 46 15,900 46 Program Direction and j
Support 0
25 0
25 0
24 i
Total
$201,812 292
$196,578 295
$195,200 283 The Office of Nuclear Regulatory Research (RES) has the responsibility and autho-rity under the Energy Reorganization Act of 1974 to perform research in support of the nuclear regulatory process.
A basic objective of the research program is to develop a sound and complete base of technical information on safety i
issues for the Commission to consider, and an independently verified source of l
safety, health, environmental and safeguards information to be used together with information furnished by applicants or licensees as a basis for Commission licensing and regulatory decisions.
An important part of this activity includes the development of safety data and analytical methods to support Commission 62
- _ _ - _ _ _ _ =
m (Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research - continued l
rulemaking activities and policy determinations, and formulation of rules and regulatnry renuirements for commissinn cnnsideration.
This office also provides the principal interface between the NRC and other organizations involved in the national standards effort.
The following narrative provides justification for i
the resources requested for each program.
LOCA and Transient FY 1981 = $46,182 FY 1982 = $30,900 FY 1983 = $30,000 l
(20)
(19)
(17) l This research provides experimental data and analytical methods to assess the behavior of nuclear power plants during anomalous transients and loss-of-coolant accidents (LOCA).
The accident at Three Mile Island focused attention on the need for better understanding of the course of anomalous transients and small-j break LOCAs.
The program will also give support to licensing and regulatory l
action regarding severe accidents by providing an understanding of system transient response and defining those conditions under which severe fuel damage may occur.
The program includes testing of engineering models of i
j reactors systems and components to better understand and confirm how nuclear 2
power plants behave during accidents and to measure emergency core coolant 1
(ECCS) flow distribution, and incorporating the resulting experimental data into analytical models and computer codes to improve capabilities for predicting the behavior of nuclear power plants during accidents.
l The LOCA and Transient program is described in greater detail below.
I j
Semiscale is an electrically heated test loop which simulates a pressurized j
water reactor (PWR) and its coolant system.
It is located at the Idaho National Engineering Laboratory (INEL).
The semiscale program provides transient experi-ments and backup analyses for PWRs.
Support is provided for NRR licensing j
actions, investigation of safety concerns, code development, and code assessment.
Recent test series have addressed TMI behavior, small-breaks. anticipated Loss-J of-Fluid-Test (LOFT) tests, resolution of the reactor coolant pumps on/off issue, 4
j upper head injection, station blackout, typicality of Semiscale with respect to PWRs, and natural circulation.
~!
FY 1983 Semiscale test and analysis work will include transients that involve steam generator tube breaks, including complicating factors such as other mal-functions and breaks, licensing and code assessment support, and evaluation of l
PWR instrumentation.
Tests in support of acti'tities related to severe acci-dents will also be planned where data for code development and assessment can be economically obtained in Semiscale.
The Two-Loop Test Apparatus has completed its original mission of studying the boiling water reactor (BWR) large-break LOCAs and will be upgraded in a coopera-tive venture with Electric Power Research Institute (EPRI) and the General Electric Company to address small-break and transient testing.
The facility will be renamed the BWR Full Integral Simulation Test (FIST) to reflect the new mission.
FIST Phase I testing of small-break LOCAs will be conducted in early FY 1983, and will be followed by Phase II testing of other transients, e.g., loss of feedwater, anticipated transients without scram (ATWS).
s 63
~
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued Separate effects experiments utilizing both intermediate and small scale facili-ties provide insight into phenomena which affect plant behavior during abnormal operation and LOCAs.
Thermal hydraulic event sequences resulting from opera-tional transients will be analyzed to determine optimum modes of recovery and to identify any need for improvement in monitoring and surveillance systems.
This program will provide reflood heat transfer data in rod bundles with flow blockage that will be applicable to Westinghouse, Combustion Engineering and Babcock & Wilcox reactor designs.
In addition, information on the modes of natural circulation to provide an effective heat sink will be investigated.
Use will be made of separate effects experimental data to verify correlations employed in best estimate codes and to develop refined phenomenological models for code improvement.
The international cooperative 2D/3D program (involving the U'nited States (NRC) and the German and Japanese governments) will provide information on blocked core bundle behavior and ECCS behavior during the refill and reflood phases of large and medium break LOCAs.
NRC's responsibility as specified in the Inter-national Agreement is to provide advanced instrumentation and computer code analysis capabilities to the experimental facilities located in Germany and Japan.
The 2D/3D program consists of two test facilities located in Japan:
the Cylindrical Core Test Facility and Slab Core Test Facility; and one test facility yet to be constructed in Germany, the Upper Plenum Test Facility (UPTF).
The Japanese test program has been on schedule, established early in the 2D/3D program, and NRC code analysis and instrumentation have been supplied on schedule.
However, the UPTF facility has incurred several schedule delays and total cost is anticipated to increase because of design changes made early in the program.
Delays in UPTF schedules are now estimated to be two years.
These program delays coupled with several revisions in instrumentation needs and increased development costs have caused projected NRC costs to exceed earlier estimates.
NRC, in consultation with Germany and Japan, is developing a number of options that would allow more predictable program costs and sche-dules.
The main emphasis in these discussions is to freeze the UPTF design which would allow NRC's supply responsibilities to that facility to be fixed in terms of workscope and schedules, thereby producing predictable program costs and providing a basis for limiting cost of U.S. participation in the out years.
In order to improve NRC's capability to analyze transients and small-break LOCAs, including ef fects of equipment failure, operator actions, and recovery procedures, codes for computer analysis must be improved and assessed against experimental data.
Code improvement and maintenance activity will complete and maintain the fast running versions of the TRAC codes for analysis of light water reactor (LWR) operational transients, complete the subchannel code, COBRA-TF, and maintain the FRAP-T and FRAPCON codes for analysis of fuel behavior under operational transients.
The SOLA-3D component code for detailed multidimensional analysis of hydrc4en transport within containment will be completed and assessed with use of applicable data.
In addition, we will complete the independent assessment of the detailed safety analysis codes, TRAC-PD 2, TRAC-PF 1, and RELAP 5 for PWRs and TRAC-BD 1 for BWRs and will apply the advanced' codes to help in resolution of safety issues.
Study of 64
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued the feasibility of an engineering analyzer will continue with the goal of pro-viding faster-than-real-time operator interactive analysis of LWR accident situations.
Loss-of-Fluid Test FY 1981 = $41,550 FY 1982 = $42,000 FY 1983 = $15,000 (6)
(6)
(4) 1 The Loss-of-Fluid Test (LOFT) facility has provided a unique, nuclear test facility to assess the accuracy of computer codes developed by the NRC (such as RELAP and TRAC) and by the reactor manufacturers which are used to analyze accidents in PWRs; to better understand the behavior of PWRs and engineered safety features under accident conditions; and the operator actions needed to stabilize and recover the plant; to evaluate improved instrumentation and advanced display systems to assist the operator in identifying the accident conditions and tak Sg the best actions to assure public safety and plant recovery.
The LO/T test program has included anomalous transients and loss-of-coolant accident with large, intermediate and small pipe breaks, and anticipated transients without scram.
A LOFT Special Review Group (LSRG) appointed at the direction of the Commission, completed a review of the LOFT program in early 1981 and recommended a priori-tized test matrix to complete the program.
The test program was also reviewed i
by the Commission and the Office of Nuclear Regulatory Research considering l (
the recommendations of the LSRG.
The final test matrix covers the high priority tests recommended by the LSRG and special needs for reactor regulation.
In 4
FY 1982 and FY 1983, the final two tests in the large-break loss-of-coolant accident series will be performed.
Both tests will use prepressurized fuel for the first time, and will simulate a loss of offsite power.
These tests will impose the most severe conditions required for consideration by NRC regulations (Appendix K of 10 CFR 50).11 In support of these tests, the reactor must be refueled:
the central fuel bundle will be replaced twice; and the irradiated fuel will be examined.
The remaining tests in FY 1982 and FY 1983 will comprise two ATWS tests, a set 1
of four operational transients, and a boron dilution transient requested by the licensing staff.
The ATWS test will be the first such test performed at LOFT, the results of which are needed to assess the predictive capabilities of the nuclear industry computer codes.
In FY 1983, the LOFT test program will be completed.
The final test, to be performed in FY 1983 is planned to investigate ballooning and burst of fuel rod cladding in a pressurized fuel assembly under large break conditions.
This test is specifically needed to evaluate the safety margins in the Appendix K fuel model specifications.
Additional funding to permit more intensive post-irradiation examination and analysis is being sought from foreign governments and EPRI.
Analyses of the test results will be completed and reported during
'the last half of FY 1983 and early FY 1984.
1 J
If Emergency Core Cooling Evaluation Models 65
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued Accident Evaluation and Mitigation FY 1981 = $26,324 FY 1982 = $33,100 FY 1983 = $47,200 (23)
(25)
(25)
The objectives of this program are to provide the NRC with the technical bases for:
(1) policy determinations concerning operational capabilities required to mitigate the consequences of severe accidents; (2) reducing uncertainties associated with present risk assessment methodology and data so they can be used more effectively in the regulatory process; and (3) evaluating engineered features to improve LWR safety.
To obtain these objectives, research will be conducted:
(1) to provide data and analysis methods covering the progression and consequences of accidents involving damage to fuel or cladding; (2) to describe behavior of the core
~
during degraded cooling conditions and its interactions with the primary system and the containment; (3) to characterize a possible radioactive source term resulting from an accident, and (4) to develop and evaluate guidelines for management of severe accidents including provisions for improved plant operat-ing flexibility as well as engineered systems intended to optimize capabilities for managing plant recovery from accident stituations.
These investigations will also be supported by post-accident data from TMI-2 which will be obtained in conjunction with the NRC, Department of Energy, Electric Power Research Institute, and General Public Utilities cleanup efforts.
An increase is reouested for this program in FY 1983 to provide experimental data on accident control and mitigation and establish a quantitative evalua-tion of accident threats to containment.
This effort will investigate - first a survivable primary system and second - containment survivability based on quantitative analysis in contrast to bounding analysis used previously.
- Thus, in FY 1983 the in pile fuel test, fission product release and transport, the hydrogen generation and control work, as well as out-of pile fuel tests will all be in the experimental or active physical examination state requiring significantly increased funding.
In addition, the severe accident sequence analysis analytical ef fort will increase as valid data from the experimental program become available. As the major accident threats to the primary system and containment become better evaluated, increased emphasis on material defects and other possible accident initiators will also be required.
Experimental information and analytical capability is required for the study of the progression and consequences of severe accidents to provide the basis for appropriate licensing actions and Commission policy determinations.
Severe accident sequence analysis will be performed to guide experimental investigc-tions by characterizing accidents and to assist development of operational tech-niques for managing accident recovery.
Data will be obtained on the formation, kinetics, character, size, extent, and coolability of damaged fuel.
Important information to be extracted from these tests include fission product release rates, hydrogen generation and release, and the chemical composition of the fuel.
Other experiments in this program are concentrated on the coolability of ballooned and burst cladding.
This work includes both in pile tests (i.e.,
PBF', ACRR, and completion of NRU-test reactor experiments) and ex pile work on electrical heated rods including providing state-of-the-art instrumented test trains frr prototypical tests.
66 I
(Dollars in Thousands, except wholt dollars in narrative material)
Nuclear Regulatory Research
- continued
-~s
(-
Key information to be obtained within this activity includes the threat to con-tainment from (1) pressure excursions from rapid quenching of core materials, (2) the burning of hydrogen and other combustible gases, and (3) containment basemat interactions.
Tests of concrete interaction, the effectiveness of retention materials and development and verification of appropriate computer models will continue in FY 1983.
Research on fission product release and transport will provide for experimenta-tion and development of analytical methods for defining the radiological source term released from containment under accident conditions.
This research is necessary for assessing the health effects and property damage that may result from such a release.
It encompasses the release of fission products from damaged fuel, their subsequent transport through the primary reactor coolant system and containment; as well as the release of fission products and nonradioactive aerosols from interactions of core materials and their surroundings and the transport behavior of multispecie aerosols.
Information from this program also would characterize the radiation environment for equipment qualification, and fission product and aerosol loads for design of Engineered Safety Features pro-vided to facilitate accident recovery.
This activity also provides for the development and evaluation of operational strategies for limiting plant damage and recovering from accidents as well as consideration of engineered features that may be incorporated into nuclear plants for the mitigation of the consequences of severe accidents, including i
analysis and supporting experiments to examine the feasibility, value, and s,,)
impact of such safety features.
The evaluations will ccver improved plant instrumentation, more flexible control of plant operation, hydrogen control systems, alternative containments, filtered vented containment, and containment heat removal systems.
The evaluation will include value/ impact assessment, engineering feasibility, and cost estimates.
Tests of vent filter components, retention materials, and equipment survivability under severe accident condi-tions will support these evaluations in FY 1983.
Advanced Reactors FY 1981 = $ 9,703 FY 1982 = $ 7,500 FY 1983 =. $ 13,000 (4)
(3)
(4)
The objective of this program is to provide surport for the NRClicensing review process for the Clinch River Breeder Reactor (CRBR), and to maintain a baseline oroaram within NRC for use in possible future high temperature gas reactor (HTGR) application review. The increased funding for this activity is related to research support for the CRBR effort.
4 Fast Breeder Reactors All research efforts will be addressed tn CRBR licensing considerations.
Research is being conducted to assess accident prevention features and accident sequences which may lead to core damage or threaten containment integrity.
4 Further effort to understand phenomena related to accident energetics, system
{'N integrity and aerosol release and transport will also be continued.
Accident g~
prevention research will be initiated in FY 1983 on in-service inspection and testing, mechanical / structural design, fuel handling and equipment surviva-bility.
The response of primary and secondary containment systems to severe 67
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Reseg ch
- continued accident sequences will be analyzed, and release categories for various acci-dents will be estimated.
This research will lead to preliminary identifica-tion of important accident sequences and major uncertainties, and will identify the area on which to focus NRC's independent risk analysis and core safety research.
The purpose of the accident energetics research is to provide a data base for the development and verification of analytical models for assessing the threat to the integrity of the reactor primary systems and eventually the containment of the energy released in a core disruptivc accident.
The program includes experiments with LMFBR fuel in the Annolar Core Research Reactor (ACRR) and laboratory experiments on key thermophysical phenomena.
Research on systems integrity will continue using the Large-Melt Facility, that has the capability of providing 500 kg of reactor fuel (U0 ) for test of the effects of large 2
melts.
The majority of the work on the aerosol release and transport program should be essentially completed during FY 1983 to allow assessment of the pro-posed filtered vent system in CRBR.
Gas-Cooled Reactors Current planning is predicated on being ready for an HTGR licensing application in FY 1983.
Generic work carried out in previous years will be reviewed and compiled to form a basis for a preapplication review of key regulatory issues starting during FY 1982.
Needed improvements in the data base revealed by the review will be factored into FY 1983 and subsequent future program plans.
Ongoing research efforts have continued to support NRC's Ft. St. Vrain plant responsibilities.
The industry HIGR risk assessment evaluation developed in the earlier Accident Initiation and Progression for HTGRs will be reviewed and supplemented as necessary with latest probabilistic risk assessment techniques, and plant infor-mation for the current proposed HTGR design in order to obtain move accurate assessments of reliability, identification of predicted risks, and development of safety research needs.
Materials studies will continue investigation of graphite corrosion methodology and testing.
Containment liner cooling and engineered safety systems will be evaluated for reliability and failure mode characterizations.
Reactor and Facility Engineering FY 1981 = $28,405 FY 1982 = $33,800 FY 1983 = $38,000 (56)
(57)
(56) l As more nuclear power plants have begun operating and as these plants achieve l
- n. ore years of operation, understanding of the effects of aging on the capability of systems and components to function when needed is required to provide inde-pendently generated safety information relating to ways to reduce the probabil-ity of,,echanical, electrical, and structural failures and provide a technical basis for regulations and licensing decisions.
A further goal is to provide safety information,in the areas of fire protection, effluent treatment, and controlling normally produced and accidentally released radioisotopes.
- Further, the nuclear industry has reached a degree of maturity where decommissioning of older or obsolete facilities will be required.
Research is needed to provide 68
(Dollars in Thousands, except whole dollars in narrative material)
-(]
Nuclear Regulatory Research
- continued t
i V
a basis for evaluating licensee requests for shutdown and decommissioning of such facilities in a manner that protects the public health and safety.
Each of the programs is described below in more detail.
t Research in mechanical and structural engineering is designed to provide infor-mation en structures, systems, components, and equipment of LWRs.
The mech-anical engineering program will emphasize component structural reliability and qualification of mechanical equipment.
Emphasis in structural engineering will be directed toward evaluating and assuring containment integrity.
The Seismic Safety Margins Research Program is a multidiscipline effort that is developing mathematical models to realistically define elements that affect the probabilities of radioactive release due to earthquakes.
During FY 1983, an assessment will be completed of the sensitivity of seismic risk to uncertainties in soil-structure interaction and structural, mechanical component, and system response.
Further, a preliminary validation of techniques to estimate con-servatisms in seismic safety licensing requirements will be completad.
The mechanical equipment qualification program is being undertaken to evaluate and validate methods of qualifying ihe operability of mechanical components and to develop procedures for obtaining failure data from existing qualification methods.
Ongoing evaluation and monitoring of related industry-sponsored work will be continued and several standards will be developed on the qualification s
m (v-p and inspection of snubbers and valves and on qualification methods for a variety of mechanical-components.
The program on behavior of piping systems is devel-oping methodology for assessing the consequences of pipe rupture and will also develop a model to assist in redefining the criteria for the location and number of pipe restraints to achieve maximum safety.
Results in FY 1983 will include preliminary definition of' loads for pipe breaks, including effects of pipe whip and pipe-to pipe impact..The program on containment structural integrity is being performed to obtain test data needed to predict failure modes and to determine margins of safety needed to estimate risks from existing plants for use by the licensing staff in evaluating the safety of proposed designs.
During FY 1983 an increase is requested to provide for steel and concrete containment experiments with large penetrations (typical of real systems) to determine structural capacities and failure modes.
The researcl/ programs on LWR primary system integrity will include a test in FY 1983 to validate the pressurized thermal shock analysis method to be completed in FY 1982.
This method will be used by NRC in evaluating plant performance, especially for the 20 PWR plants with vessels built to older mater-ials specifications.
This program will also provide the methods for' analyzing actual and postulated overcooling transients such as steam-line break accidents and wil.1. help formulate the corresponding regulation on material toughness to insurp system integrity during accidents.
Following emplacement of a steam genetator removed from service into the Steam Generator Examination Facility, nondestructive evaluation baseline and experimental measurements will be started in FY 1982 for correlation with tube integrity test results beginning in FY 1983.
O Such data can be used by the licensing staff for early prediction of steam
()
generator tube failures based on inspection results and will provide a basis 69
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued for updating standards on tube plugging and inspection.
Increased funding in this area will pro /ide resources for the large scale tests of degraded and cracked pipes, an expanded program of corrosion studies to establish impurity limits in steam generator water, and to evaluate the safety significance of observed degradation of cast stainless steel reactor components.
Research in nondestructive examination (NDE) in FY 1983 will utilize round-robin test results for pressure vessel inspection to update ASME Code rules for improved detection and characterization of near-surface pressure vessel flaws.
Also in FY 1983, the program will evaluate the level of improvement obtainable by using advanced NDE techniques that may be proposed for incorporation into the ASME Code in f Y 1984.
Following laboratory development of an improved real-time ultrasonic test method in FY 1982, this method will be used and optimized on an operating reactor to assure that accurate monitoring can be accomplished.
Many electrical systems and components in nuclear power plants must function during and after an accident in order to assure that the plant can be shut down and then maintained in a safe condition.
The qualification testing research program is being performed to develop test methods and procedures for qualify-inq electrical equipment and components used in systems for accident preven-tion and mitigation and for safe shutdown in nuclear power plants.
Specific objectives include completion of an independent assessment of test methodologies under LOCA and main steam-line break (MSLB) conditions, determination of the nuclear source term composition and its effects on electric equipment, and development of validated accelerated aging techniques.
The FY 1983 program will include completion of tests to determine whether ex-reactor gamma radiation (i.e., from source irradiation facilities) can effectively simulate the more complex radiation source actually present in the reactor environment.
The requirements for electric equipment qualification will be revised to incorporate these results and the results of other ongoing research such as the cooperative research program with France concerning the effects of oxygen-simulated aging on electrical components as it affects their survival in a LOCA or MSLB environment.
Studies of accelerated aging techniques will be continued and aging guidelines for electrical equipment will be issued for use by the licensing staff.
In FY 1983 effort will continue on testing to evaluate the ability of fire detection systems to function properly over the wide range of conditions.
The adequacy of current standards used for testing barrier penetration fire stops will also be evaluated.
The program in fuel cycle facility safety research is directed toward providing the staff with the capabilities needed to assess the safety of design of fuel cycle and materials facilities.
The specific objectives are to obtain experi-mental data and to develop realistic validated models for evaluating, among others, criticality safety systems, spent fuel storage capability, and facil-ity response to major accidents.
Effort during FY 1983 will include continua-tion of studies to determine source terms at operating LWR fuel cycle facil-ities and initiation of an evaluation of the applicability of LWR fuel cycle facility accident data and analysis models to materials facilities.
Effluent control and chemical systems research is being performed to provide the licensing staff with capabilities to verify procedures and analytical models for effluent treatment systems for controlling normally produced and accidentally released radioisotopes in nuclear power plants.
70
(Dollars in Thousands, except whole dollars in narrative material)
{
Nuclear Regulatory Research
- continued During FY 1982 and FY 1983 the program plan for studying facilities undergoing decommissioning will be completed, initial sites will be selected, and a report on LWR decommissioning source terms will be issued.
Several tasks on the technology and costs of decommissioning various facilities will be completed and the final Generic Environmental Impact Study related to a major rulemaking will be issued.
Facility Operations FY 1981 = $12,618 FY 1982 = $13,028 FY 1983 = $13,500 and Safeguards (55)
(55)
(55)
Since the TMI accident, greater emphasis has been placed on facility operational safety.
The increasing number of operating nuclear power plants and the consequently increasing potential for hardware failures and human-error-related incidents occurring in these facilities have accelerated the need to provide the NRC licensing staff with independently generated safety information as a technical basis for decisions and rules that will result in fewer and less severe accidents that might affect public health and safety.
A minimal increase is requested in FY 1983 to strengthen the human engineering and plant instrumentation and control efforts explained below.
Current instrumentation and control efforts include a program to evaluate the safety implications of control systems on plant dynamics and safety:
an anal-ysis of the feasibility of developing plant electric system models using com-puter analysis; evaluations of the feasibility of reactor surveillance tech-niques using noise analysis, microprocessor based control, and protection 5(,
systems; and instrumentation performance under accident conditions.
FY 1983 efforts include evaluation and testing of instrumentation available for use in accident monitoring and possible revisions of the regulatory guide on "Instru-mentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident;" ano the performance of instrumentation, control, protection, and other electric equipment important to safety to identify deficiencies that could lead to common cause or common mode failures.
The objective of the human factors program is to provide the technical basis to support current and anticipated regulatory needs in the application of human factors engineering to nuclear facilities.
Components of this basis include:
human performance data and analytical methods, assessment of new concepts and design and evaluation criteria.
Data to support the implementation of modifi-cations in the operator-machine interface are particularly needed to ensure that such modifications actually improve safety.
Improved quantitative esti-mates of human reliability are needed to help reduce the large uncertainties in risk analyses.
Methods of quantifying and reducing the human contribution to risk to an acceptably low level must be developed and evaluated.
The FY 1983 human factors program will include conduct of task analyses for opera-tions and support personnel at reactors and other fuel cycle facilities; con-duct of controlled experiments on human performance as affected by information display content and format; identification and application of techniques to measure human performance capabilities; validation of the licensing examina-
[_h tions and proposed education and training requirements and conduct of simulator
/
experiments to validate human performance models.
l 71 1
1
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued The quality assurance research program will continue in FY 1983 to provide the technical basis for developing criteria to determine the plant structures, systems, and components that should be included in the quality assurance program and for implementing the quality assurance program requirements Commensurate with importance to safety.
Regulations for guidance on quality assurance requirements for the operation of high-level waste repositories will also be developed.
Final guidance in these areas will be issued in FY 1984.
The objectives of the safeguards research program have been to improve the protective systems employed at nuclear facilities to prevent radiological sabotage, improve the system for the control, accounting, and protection of special nuclear material, facility, and transportation links that could constitute a threat to the health and safety of the public or to national defense.
The FY 1983 safeguards program continues to be based on the assump-tion that nuclear fuel reprocessing will not be proposed by the industry.
Emphasis is being given to use of safeguards resources for implementation of previously developed programs.
Development of new standards for the training of safeguards personnel and the evaluation of shipper-receiver dif ferences will continue.
The basic objective of the occupational radiation protection program is the development of a comprehensive body of regulations, guidance and information which would assure an adequate degree of radiation protection for workers in NRC-licensed activities.
The program consists of six elements:
(1) occupa-tional ALARA, (2) health physics measurements improvement, (3) internal dose contro!, (4) personnel performance improvement, (5) dose rate / working time reduction, and (6) licensing improvement.
The FY 1983 plan includes:
evaluation of various techniques for the safe removal (decontamination)of radioactive corrosion products in an effort to reduce ambient radiation levels in the working environment; an evaluation of occupational dose reduction opportunities at LWRs through the use of low-maintenance equipment; an evaluation of extensive use of remote in plant handling methods for packaged LWR radioactive waste; a study of incentives for reducing the collective occupational dose at LWRs; and the identification of specific high-dose maintenar.ce tasks at LWRs and recommendations for dose reduction.
Revision of regulatory guidance on Emergency Planning for Fuel Cycle Facilities is planned in FY 1983 as well as the development of a proposed regulation to revise nuclear power reactor emergency preparedness requirements and development of appropriate accident scenarios for exercising emergency plans.
Waste Management FY 1981 = $10,202 FY 1982 = $12,200 FY 1983 = $13,600 (28)
(28)
(26)
The nuclear waste management research program will provide technical information and develop standards essential for regulating commercial high-level and low-level radioactive waste and wastes from uranium recovery operations such as mill tailings.
Th6 technical information developed by the research program will provide reliable bases for NRC regulations, criteria, codes, and regula-tory guides; for the support of licensing decisions and for enforcement of 72
(Dollars in Thousands, except whole dollars in narrative material)
[
Nuclear Regulatory Research
- continued i
v regulations.
In addition to supportiny NRC regulatory activities, this program will provide technical information to the Agreement States.
The high-level waste research program provides information and analytical capa-bility required to evaluate DOE's proposed methods for waste treatment and facility design, and sites for the storage of high-level radioactive waste.
To predict the long-term performance of both the natural and engineered compo-nents of a geologic repository, the NRC evaluation requires an improved under-standing of natural phenomena and geologic processes over long periods of time.
Research will continue on the evaluation of site characterization methods used to evaluate the physical, chemical, and hydrologic properties of rocks in a high-level waste repository.
Research to assess predicting the effectiveness and reliability of methods for plugging and sealing boreholes will be continued and will include consideration of large diameter shafts and tunnels.
Properties of waste forms, containers, and backfill materials will be studied to evaluate l
potential long-term containment and controlled release capabilities offered by these materials.
The consequences of shaft seal failure on water movement and radionuclide migration under the relatively high temperature condition in a f
repository will be assessed.
The assessment of the geochemical interactions between waste packages, waste products, groundwater and rock will continue, including evaluation of techniques employed to simulate long-term corrosion of l
waste packages, and studies of natural analogies to predict long-term migra-l tion of radionuclides from the repository.
Research will continue to assess l [N methods for predicting long-term groundwater flow through both saturated and
(
)
unsaturated rock.
Laboratory-scale tests to predict radionuclide migration l
v through integrated systems including waste form, breached canister, backfill, and rock will be continued.
Research on risk methodology will be continued to l
extend the risk methodology developed for bedded salt to include consideration of basalt and welded tuff.
l The major efforts of the low-level waste research program will emphasize testing of solidified wastes arising from reactor accident clean-up and from the routine decontamination of operating reactors.
This program will include an assessment of the effects of chelating agents found in decontamination agents on the potential for enhanced radionuclide migration from shallow land burial sites.
Work will be initiated to compare past test results obtained from simu-lated waste forms with real full-size forms to evaluate the effectiveness of proposed standard tests of waste forms.
Research will be continued to define the characteristics of volume-reduced wastes produced by DOE and industry.
High integrity containers will be evaluated for long-term confinement capa-l bility.
The design, construction, and operating practices of shallow land burial facilities will be continued.
Ongoing studies of existing shallow land burial sites will be continued to assess the reliability and deficiencies of l
measurement methods that have been in use.
This study of existing facilities l
will examine the accuracy of methods for measuring, analyzing, and predicting waste transport in soils.
A major part of this study involving cooperative studies with the state of Kentucky, will provide technical information needed to assist the state in decommissioning the Maxey Flats site.
In FY 1983, work
,o will provide for completion of tests of solidified wastes generated from two
(
)
nuclear power plants (one PWR, one BWR) with respect to leachability and com-kl pressive strength.
Studies initiated in FY 1982 to assess risks associated with the performance of low-level waste facilities will be continued.
Guides 73 L
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued will be published on waste form, site closure, stabilization and post-operational care, facility design, operation, and monitoring.
The uranium recovery research program will evaluate engineering designs and methods for managing tailings of operating uranium mills and waste from in-situ mines.
Research on the properties of covers for attenuating radon emanation from uranium tailings piles will be completed.
Study of liquid radioactive wastes seeping from tailings ponds into surface and groundwaters and in control-ling such seepage methods will continue, including assessment of the effective-ness of various neutralization alternatives to limit the mobility of potential groundwater contaminants.
New work will be undertaken to assess methods of segregating different sized tailings particles, (known as " sands" and " slimes")
for the purpose of reducing seepage.
Work will also continue on assessment of methods for stabilizing active operational tailings and to assess engineering methods for disposal of tailings in contact with groundwater.
Efforts include completing assessment and issuing a report on the scope, feasibility, and design of experimental studies on tailings stabilization of rock resistance to weather-ing and optimum placement of erosion prevention covers and barriers.
Field tests to determine accuracy of flow mndels for determining impact of tailings f
on groundwater will be initiated.
Efturts also include completing measurements of tailings and soil consolidation characteristics and evaluation of materials and installation procedures for effective dewatering of tailings.
Siting and Environment FY 1981 = $12,927 FY 1982 = $ 9,000 FY 1983 = $ 9,000 (31)
( 31)
(26)
The Siting and Er.vironment research program is concerned with developing and implementing research and standards-setting activities for the siting of nuclear facilities, the assessment of environmental impacts from siting and operation of nuclear facilities, and protection of health and safety of the public from harmful effects of ionizing radiation in licensed activities.
This program includes:
(1) assuring systematic analysis of sites from the perspective of public health and safety and protection of the environment; (2) providing data for the development of regulatory requirements for siting of nuclear facilities relating to seismology, geology, geotechnical engineering, hydrology, and mete-orology; and (3) developing information and standards for the protection of public health and safety and workers from potentially harmful effects of ioniz-ing radiation and of the use of radioactive materials in licensed nuclear activities.
The siting program will develop regulatory requirements for siting fuel cycle facilities, including implementation of guidance for nuclear power plants.
Models will be developed for evaluating alternative sites and facility designs that will reduce the need for detailed site-specific time-dependent information for future sites.
This will include single and multi-unit sites.
A cost-effectiveness analysis will be made of alternatives to controlling land-use patterns near reactor sites.
The siting program focuses on development and publication of final regulations for the review of alternative sites and con-tinuing research on the socioeconomic impacts of constructing and operating nuclear reactors.
74
(Dollars in Thousands, except whole dollars in narrative material)
Huclear Regulatory Research
- continued v
The geology, seismology, hydrology, and meteorology programs provide informa-tion for use in the development and confirmation of regulations, standards, and guides which define the safety design bases for nuclear facility structures, components, and systems to withstand the effccts c' severe and extreme natural phenomena such as earthquakes, floods, and severe eather events (e.g., torna-does, lightning).
In FY 1983, the seismology and geology program will continue to develop methodologies for analyzing digital and analog seismic data, to evaluate the tectonic characteristics of the Northeastern and Northwestern United States, to study the Charleston, SC and New Madrid, M0 seismogenic zones, and to perform initial studies of predictive methodology for soil liquefaction.
The hydrology program is developing design base events and conditions for severe hydrometecrological phenomena such as floods in the area of nuclear facility siting.
Also, criteria for hydrological dispersion in surface-water bodies and hydrodynamic dispersion in groundwater media are developed.
The meteorology program provides information for emergency preparedness and consequence analyses concerning the dispersion of airborne effluents from nuclear power plants.
The FY 1983 meteorology program will complete initial field studies of atmos-pheric dispersion at coastal sites and perform verification studies,0f the Atmospheric Release Advisory Capability accident dispersion prediction model.
The health effects program will continue research ano standards programs neces-sary to ensure that NRC regulations adequately protect the health and safety of the public and workers from potentially harmful effects that might result O(,
from the use of ionizing radiation and radioactive materials in licensed nuclear activities.
Ef forts will be continued to simplify and clarify regulations per-taining to medical uses of byproduct materials, and to exempt from licensing certain medical products with low levels of radioactive material.
The revision of 10 CFR Part 20, Standards for Protection Against Radiation, will continue through FY 1983 and be implemented by FY 1984.
Efforts to improve estimates of the risk from neutron exposures at occupational dose levels will continue, Studies will continue to provide verified information and models predicting metabolic pathways end mechanisms of radiation injury.
Long-term studies of the offects of low-level irradiation on thorium workers will continue to improve the understanding of health effects of low-level radiation.
Systems and Reliability Analysis FY 1981 = $13,901 FY 1982 = $15.050 FY 1983 =
15,900 (44)
(46)
(46)
The objective of Systems and Reliability Analysis research is to develop systems analysis and reliability engineering techniques, including risk assess-ment methodology for application to regulating the safety of nuclear facilities and materials.
This research supports the licensing and inspection staff in prioritizing and resolving safety issues, supports major rulemaking, and helps to systematize and stabilize regulatory practices.
Studies in support of regu-latory reform will be undertaken on (1) risk assessment perspectives on issues important to safety, (2) operations research applied to licensee safety assur-ance practices in design and operation, (3) analyses of the regulatory struc-ture and safety evaluation practices, and (4) research into alternative tech-v/
niques of system safety assurance drawn from other industries (aerospace,-
defense, electronics, etc.).
75
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Rewarch
- continued Some accomplishments to date in developing and applying risk assessment tech-niques to regulate nuclear safety are as follows.
In 1978, this research ranked the risk-importance of 133 generic safety issues; only 15 issues were found to be important to reactor safety.
In 1979, several of the inquiries into the TMI-2 accident employed methods developed in risk assessment research.
In 1980, risk analysis techniques led to recommended improvement for auxiliary feedwater systems at Babcock & Wilcox plants.
Also, the Commission review of the Zion and Indian Point plants used risk assessment results, in part, to decide on continued operation and fixes required.
In 1981, NRC staff positions on control room designs, emergency procedures, and operator qualification were based, in part, on research in human reliability developed for risk assessment.
Now, risk assessment methods are being applied to support application of decision theory to help systematize regulatory practices and to support policy determina-tions related to siting, emergency planning, and severe accident issues.
Planned research accomplishments in FY 1983 are described below.
The research on risk methodology development will provide NRC with analytic tools, procedures, and statistical data with which to predict the course of nuclear accident sequences and their likelihood, and to resolve the combina-tions of equipment and numan failures that might lead to accidents in nuclear facilities.
Such research is needed to help improve and stabilize NRC regula-tions of nuclear safety as recommended by inquiries into the accident at Three Mile Island.
Improved procedures and user's guide will be developed for licensee performed reactor risk assessments within the National Reliability Evaluation Program (NREP) for standardizing the scope, methods, data, and assumptions of NREP studies, for maintaining NREP models for continuing appli-cations in reactor safety regulation, for quality control, and for efficient agency review of NREP submittals.
Continuing research to overcome the limita-tions of NREP-like risk, reliability, and data evaluation methods is scheduled in the following areas:
(1) common cause failures, (2) systems interactions, (3) time-dependent, partial, and progressive failures, (4) accident sequence analysis, (5) automated evaluation of raw event data to obtain failure rates, and (6) modeling of design deficiencies or failures that are not revealed in surveillance tests.
In addition, a regulatory guide will be prepared on the failure rate data base for use in NREP studies with which to screen accident sequences by likelihood.
The resulting data are needed for NRC and licensee risk analyses to help resolve safety issues.
Virtually all of the inquiries into the accident at Three Mile Island urged the use of probabilistic risk assessment techniques to analyse the course, likelihood, and consequences of reactor accidents.
Risk assessment research to lay a coherent foundation for evaluating severe accident sequences will be continued in FY 1983.
Value impact analyses will be developed for policy determinations; i.e., a variety of options for improved containment and for improved prevention of core damage will be analyzed for risk-limitation and cost effectiveness.
A selected set of published reactor risk assessments will be subject to reanalysis by multidisciplinary teams.
Each accident sequence will be examined in turn to identify and catalog the features of plant design or operation that might make the sequence the dominant contributor to risk.
This catalog of possible risk-dominant safety defects will be published in FY 1983 for NRC use in systematizing regulatory requirements for industry use 76
(Dollars in Thousands, except whole dollars in narrative material) j Nuclear Regulatory Research
- continued V
in improving accident diagnosis procedures.
Trial applications will be made of improved methods of risk and reliability analysis to evaluate their regula-tory utility and potential use by licensees.
Improved methods are expected to address fires and other common-cause failures.
The transportation and matarials r4k research program is developing analyses 4
of licensed activities in the fuel cycle (other than reactors) and in the pro-duction, transportation, and use of products containing radioactive materials.
In addition, this activity develops standards for radioactive material trans-portation and the production and use of products containirq radioactive mate-rial.
Comparison of the risk from nuclear fuel cycle facilities and operations i
with the risk of reactors on a consistent basis, and development procedures for conducting systematic risk assessments of selected elements of the nuclear fuel cycle will be accomplished in FY 1983.
This research on Systems and Reliability Analysis in FY 1983 will help bring nuclear safety regulation into better congruence with the risks; that is, to identify and help to close loopholes in regulatory requirements in risk-significant areas, to identify of f-target or unnecessary regulations, and ultimately to help t.tabilize the regulatory process.
Program Direction and Support (Personnel)
FY 1981 = (25)
FY 1982 = (25)
FY 1983 = (24)
The personnel requirements for this area consist of the Director's office, U
admir.istrative support staf f, and the resource control and contract execution staff.
This staff provides the Director of RES with technical and administra-tive assistance and support for direction and evaluation of complex technical research projects; and plans, coordinates, directs, and executes the business matters of the office, including contractual agreements, budget formulation, riscal management, personnel administration, travel assistance, and research coordination with other organizations.
This area is interrelated with all other NRC offices and organizations, groups external to NRC, and the other programmatic functions within RES.
These rela-tionships involve both providing information to and receiving information from these other offices, organizations, and groups.
The workload within this area is directly related to the workload within the other RES organizational elements, by the demand for RES action by other NRC offices and organizations, and by the interaction with those groups external to NRC.
e The requested level of 24 staff in FY 1983 is required to support the workload in the RES organizational elements and the interaction with NRC offices and other external groups to the NRC.
The staff will manage and run RES's computer-ized action item standards tracking system and systems that track research projects, user requests, and research information letters.
The staff will also provide needed contract and budgeting analysis assistance.
s
\\v/
77
(Dollars in Thousands, except whole dollars in narrative material)
Nuclear Regulatory Research
- continued Equipment FY 1981 = $ 7,659 FY 1982 = $ 6,900 FY 1983 = $ 6,200 In FY 1983 equipment will be required to support the research programs as discussed above.
In particular, accident evaluation and mitigation, advanced reactors, and the reactor and facility engineering programs will require test facility modifications and expansions in order to productively utilize these engineered experiments.
Data gathering and analysis systems for these facil-ities must be upgraded to provide for new and expanded instrumentation to properly describe experimental results.
The requested FY 1983 equipment requirements reflect the completion of the LOFT testing program.
Equipment is requested to modify experimental facilities to allow more accurate simulation of reactor small-break LOCAs and operational transients, and for operational safety tests of fire protection and safety equipment qualification.
Requirements for equipment in the expanding areas of severe accident behavior and aerosol transport will also place new demands on this resource.
The high temperature characteristics of the fast breeder reactor will require new equip-ment as this research effort is strengthened in FY 1983.
Equipment is needed to upgrade the Power Burst Facility for testing at extreme conditions to better define fuel damage.
Expanded research on large scale steam-explosion testing, fission product release at high temperatures, and hydrogen generation and behavior in containment will require new equipment.
Further, equipment is needed for research on inspection techniques and environ-mental effects of piping and pressure vessel materials.
Within the waste management program equipment will be required foi sampling devices and analytical measuring instruments.
O O
78
(Dollars in Thousands, except whole dollars in narrative material) flVCLEAR REGULATORY COMi1ISSION - continued Program Technical Support........................................
523,400
SUMMARY
OF PROGRAM TECHNICAL SUPPORT ESTIMATE BY FuriCTION FY 1981 FY 1982 FY 1983
]
Actual Estimate Estimate Salaries and Benefits 512,005 513,960
$13,810 Program Support 1,683 2,462 3,300 Administrative Support 4,036 5,010 5,000 l
Travel 972 1,180 1,290 TOTAL
$18,696 522,612 523,400 4
l' Personnel (276)
(308)
(305) l The Program Technical Support offices are integral to the agency's process of regulating nuclear facilities and materials for the protection of j
public health, safety and environment.
These staff offices are the i
Advisory Committee on Reactor Safeguards, the Atomic-Safety and Licensing Board Panel, the Atomic Safety and Licensing Appeal Panel, the Office of the Executive Legal Director, the Office of State Programs, the Office of International Programs, and the Office for Analysis and Evaluation of Operational Data.
These offices will continue the conduct of and the legal representation at hearings to license the operation of nuclear power
~,
plants, while increasing the emphasis on analyses and evaluation studies of potentially significant nuclear related operational events and situations.
The increase in Program Support is due to additional technical assistance in the licensing of reactors and an increased number of studies of data from operating reactors. The decrease in Personnel is related to further refinement of both the' export licensing of nuclear i
materials and financial qualifications casework.
The increase in travel reflects the prcgrams of the individual offices with co m Meration given to the inflation in the price of transportation services. The following narrative addresses the individual functions of the Program Technical Support offices.
a.
The Advisory Committee on Reactor Safeguards (ACRS) established in l
1957 by Statute, advises the Commission on potential hazards of proposed or existing reactor facilities and the adequacy of proposed safety l
standards.
Section 29 of the Atomic Energy Act of 1954 also requires that j
the ACRS advise the Commission with respect to the safety of operating reactors, and Public Law 95-209 requires an annual report to the Congress on the NRC Safety Research Program.
The ACRS reviews requests for preapplication site and standard plant approvals; applications-for construction permits or operating licenses for power reactors, ~ test j
reactors, spent fuel reprocessing plants 'and waste disposal facilities; and assists in matters related to 00E nuclear facilities as outlined in the Memorandum of Understanding dated February 24, 1978.
Because the ACRS O
is a statutory body of advisors to the Commissioners, their advice impacts b
on the federal responsibilities of the NRC including the licensing of operating reactors. There is no similar group which would provide both the'. independence and expertise of this. Committee.
79
(Dollars in Thousands, except whole dollars in narrative material)
Program Technical Support - continued b.
The Atomic Safety Licensing Board Panel ( ASLBP) conducts statutory adjudicatory hearings in accordance with applicable provisions of the Administrative Procedure Act, the Atcmic Energy Act, and the National Environmental Policy Act. The ASLBP through its hearing boards issues decisions with respect to granting, suspending, revoking, or amending licenses. These decisions cover both the construction and operation of nuclear power plants andantitrust issues relating to the operation of such plants. The ASLBP on-site board hearings deal with environmental issues as well as matters of health and safety, financial qualifications and economic considerations.
The activities of the licensing boards are directly related to granting licenses to the utilities for the operation of nuclear power plants.
Boards activity has increased in conjunction with the agency's increased emphasis of licensing power plants.
c.
The Atomic Safety and Licensing Appeal Panel (ASLAP) is admini-stratively established and requires Congressional notification of any revision to the organizational structure of the panel.
The ASLAP reviews decisions of administrative law judges and the Atomic Safety and Licensing Boards and performs other appellate functions in proceedings on applications for licensing of production and utilization facilities (under 10 CFR part 50) and such other licensing proceedings as the Commission may specify.
The ASLAP holds appellate reviews according to the applicable provisions of the Administrative Procedure Act.
d.
The Office of the Executive Legal Director (ELD) is responsible for providing legal advice and services to the Executive Director for Opera-tions and to the NRC programmatic and support offices which report to that official. The diverse responsibilities of ELD are performed by four divisions: Hearing Divisior., Regulations Division, Rulemaking and Enforcement Divicion and the Operations and Administrative Division.
ELD provides legal representation of the NRC staff in administrative proceedings involving the licensing of nuclear facilities and materials, enforcement actions and rulemaking.
In addition ELD provides legal advice and services with respect to such matters as health and safety, environmental impact and antitrust aspects of licensing and regulations; research programs; general agency administration, including contracts, patents, personnel, security and labor regulations; safeguards and waste management programs; and the export / import licensing program. This office plays a major role in the licensing of nuclear power plants by representing the agency at the licensing hearings, an activity that has increased with the agency's emphasis on licensing nuclear power plants.
e.
The Office of International Programs (0IP) was established in 1976 to develop and direct a program of cooperation with foreign regulatory agencies and to administer the Commission's re ponsibilities in the areas of non-proliferation, international safeguards and nuclear exports and imports. OIP provides informational support to the Commission and staff on international matters and maintains liaison with other U.S. agencies.
OIP performs a key function in facilitating the exchange of nuclear health and safety related information between the U.S. and foreign countries.
OIP also reviews, processes, and issues as appropriate licenses for export of such items as nuclear reactors, fuel and components; assists in the development of improved international safeguards and physical security arrangements; and participates in implementation of the U.S./IAEA safeguards agreemer.t.
80
(Dollars in Thousands, except whole dollars in narrative traterial)
(N Program Technical Support - continued f.
The Office of State Programs (OSP) was established in 1976 to develop and direct a program of cooperation and liaison with states, local governments, and interstate organizations.
The office administers the State Agreements program established under the provisions of Section 274 of the Atomic Energy Act of 1954, as amended. OSP provides liaison to states and state-related organizations; training and assistance to state and local governments in radiation control; and coordinates these efforts with other NRC offices and U.S. Government agencies having state and interstate responsibilities.
The office performs reviews of Agreement State programs including regulation of uranium milling and icw level waste; administers the Price-Anderson indemnity program for nuclear facilities; performs financial qualifications reviews and decommissioning studies of nuclear facilities. Twenty-six Agreement States now administer about 12,000 licenses involving the regulation of certain classes of radioactive materials.
g.
The Office for Analysis and Evaluation of Operational Data (AE00) collects, stores, analyzes, evaluates, and feeds back information on operational experience to identify significant events and situations that warrant detailed evaluation, and studies these events and situations to determine what problems should be corrected.
In addition, the office has the lead responsibility for coordinating the NRC operatirinal data analysis program, developing reporting requirements for operational events and computerized systems for the storage and retrieval of operational c)
(G experience reports.
4 0
\\
\\m/
81
(Dollars in Thousands, except whole dollars in narrative material) p MUCLEAR REGULATORY COMt11SSION - continued Program Di rection and Admini stra tion..................................$36,020 SURIARY OF PROGRAM DIRECTION AND ADMINISTRATION ESTIf1 ATE BY FUNCTION Actual Estimate Estimate FY 1981 FY 1982 FY 1983 I
Salaries and Benefits.......
$23,381
$24,270
$22,740 Program Support.............
1,109 2,042 2,200 Administrative Support......
10,529 10,332 10,360 Travel......................
422 715 720 Total Program Costs...
$35,441
$37,359
$36,020 Personnel...................
(705)
(715)
(674)
Program Direction and Administration (PDA) offices collectively provide overall policy direction, resource nanagement, administration and logistic support for the agency. These functions undergo a continual management review for improvement in efficiency and effectiveness.
The program reductions are in keeping with the Administration's efforts to reduce agency administrative support and travel costs as well as personnel expenses. Total Headquarters Administrative Support, after absorbing costs of inflation, increases modestly due to the higher rents, alteration costs and moves of offices and equipment
'h associated with the consolidation of headquarters staff in the District of
(,/
Columbia and Bethesda, MD; the integration of new sites into the Emergency Notification System and Health Physics Network; implementation of cost amortization provisions in OMB Circular A-121, " Computer Depreciation"; and the purchase of library materials for resident inspectors. Travel programs remain essentially unchanged from FY 1982 to FY 1983. Program support increases because court reporting services for licensing hearing and meeting activity expands from 200 days in FY 1982 to 360 days in FY 1983, because of additional contracting for investigations of discrimination complaints and for agency-wide
}
statistical assistance in technical and administrative programs.
The following l
staff offices of the Commission and the Executive Diretor for Operations (ED0)
~
are included:
The Commission:
EDO:
Commission EDTi Secretary Equal Employment Opportunity General Counsel Controller Policy Evaluation Management and Program Analysis Inspector and Auditor Small & Disadvantaged Business Congressional Affairs Utilization Public Affairs Administration a.
The Office of the Co- 'ssioners (0CM) is the governing body which must exercise the overall NRC asponsibilities of the Energy Reorganization Act of 1974 and the Atomic Energy Acts of 1946 and 1954, as amended. This body provides fundamental policy guidance and administration and management y",
direction necessary to assure that the civilian use of nuclear energy is developed in a manner consistent with the public health and safety, environmental quality, national security and antitrust laws.
82
(Dollars in Thousands, except whole dollars in narrative material)
^
Program Direction and Administration - continued d
b.
The Office of the Secretary (SECY) develops policies and procedures for complete secretariat services for the conduct of Commission business and implementation of Commission decisions; advises and assists the Comnission and staff on the planning, scheduling and conduct of Commission business; prepares for and records Commission meetings in accordance with requirements of the Sunshine Act; provides senior-level management and administrative guidance on preparation and submission of decision papers to the Commission to include monitoring the status of all items requiring action; maintains a forecast of matters for future Commission considerat'on; processes and controls institutional correspondence; maintains the Commission's official records; controls the handling and service of documents issued and received in all adjudicatory matters and public proceedings; administers the NRC Historical Program; provides personnel, administrative and logistical support services to the Conrnission and other NRC offices located in Washingtor. D.C.; and supervises and administers the NRC Public Document Room (PDR) 10 maintain and provide to the public regulatory information, reference services and access to docket material pertaining to NRC regulatory and adjudicatory activities.
c.
The Office of the General Counsel (0GC) is the chief legal advisor to the Commission. Tlie Counsel provides legal opinion, advice and consultation to the Conmission in connection with the quasi-judicial responsibilities of the Conmission and in the development of substantive policy matters.
It represents the Commission in matters r21ating to litigation, in Courts of Appeal n
proceedings to review Commission orders and, in cooperatior. with the Department
(
)
of Justice, represents the Commission in court proceedings affecting the NRC tj program in the Federal District Courts.
The office also provides legal advice with respect to legislative matters of concern to NRC, including drafting of legislation, preparation and review of testimony and preparation and transmission of statements of views requested on proposed legislation.
d.
The Office of Policy Evaluation (opt:) advises the Commission on a broad range of substantive policy matters to enhance the information base on which Commission decisions are made. The offi'ce provides the Commission with an independent evaluation of program policy objectives; reviews staff papers, provides independent technical evaluation of issues presented to the Cannission, including cases under adjudication; and contributes technical and policy advice for projects being conducted and managed by other NRC offices or outside agencies.
e.
The Office of Inspector and Auditor (0IA) functions as the Agency Inspector General and is responsible for developing policies and standards that govern the financial and management audit program; planning, directing and executing the long-range, comprehensive audit program; conducting and reporting on investigations and inspections, as necessary, to ascertain and verify the facts with regard to the integrity of all agency operations, employees, organiza-tions, programs and activities; referring suspected or alleged criminal violations to the Department of Justice (D0J); administering the Commission's "open door" policy; serving as point of contact with the General Accounting Office (GAO); and maintaining liaison with GAO, the 00J and other audit and law
(
enforcement agencies.
83
(Dollars in Thousands, except whole dollars in narrative material)
P_rogram Direction and Administration - continued Office of Inspector and Auditor - continued The objective of OIA is to provide the Connission with an independent review and appraisal of programs and operations to assure that responsibilities are discharged with effectiveness and efficiency, and te provide a capability to verify facts to assure continued maintenance of the highest standards of integrity of Pll NRC organizations, programs and activities. A continuous effort is made to eliminate waste, fraud and inefficiency.
DIA activities lead to the issuance of audit reports and memoranda related to NRC operations.
These activities involve coordination with the GAO, interviews with NRC and industry officials, plus visits to utilities (reactor licensees),
steam supply s; stem vendors, architect engineers, reactor sites, and fuel fabrication facilities.
The office is also responsible for conducting a significant number of investigations and referring items, when appropriate, to 00J.
f.
TheOfficeofCongressionalAffairs(OCA1assistsandadvisesthe Conmission and senior staff on Congressional matters, coordinates interagency Congressional relations activities and is the principal liaison for the Conmission with Congressional committees and members of Congress.
The primary objective of the office is to assure that the Congress is kept fully and currently informed of NRC activities as required by Section 202 of the Atomic Energy Act of 19E4, as amended.
The office provides the Commission and senior NRC staff with relevant and current information as to major legislative activities likely to effect NRC. Additionally, the office seeks to assure that individual members of Congress are kept currently and adequately informed of significant NRC licensing activities that impact on their respective states and districts.
g.
The Office of Public Affairs (0PA) issues public announcements both from headquarters and the regional offices;-responds to telephone inquiries from the news media and the public; and responds to letters from the media and the public, including the bulk of the NRC referrals from the White House.
In addition, OPA arranges press conferences in the Washington area as well as in the regions in the vicinity of nuclear facilities, and coordinates requests for Commission speakers before civic groups and other organizations interested in the role of the NRC. The office also assists the licensing boards, the appeal boards and the ACRS wherever hearings and meetings are held in which a high d
degree of public and press interest is evidenced, and advises the Commission and senior NRC staff on public affairs impacts of planned programs and other activities. A Consumer Affairs Program initiated on a "tiial" basis in FY 1981 to advise and assist the Commission and the public on the conduct of public meetings and rulemaking hearings of broad general interest is continuing, h.
The Executive Director for Operations (EDO) supervises and ccLedinates operational activities and policy development of both line and staff offices and implements the Consission's policy directives pertaining to these offices The office consists of the EDO, his immediate staff and the Administrative and Correspondence Branch which is responsible for the ED0 correspondence system including the assignment, review, and coordination of all correspondence.
84
1 (Dollars in Thcusands, except whole dollars in narrative material)
Program Direction and Administration - continued
- i. The Office of Equal Employment Opportunity (EEO) defines the procedures and practices necessary to attain and maintain equal employment opportunity within the NRC. The office develops and prepares the agency's Affirmative Action Plan; advises and assists on recruitment plans; and provides investigation of
- discrimination complaints both individual and class when necessary.
ficjor objectives are to increase employment of minorities and women in the agency; provide interaction with community groups concerned wth equal opportunities for minorities and women; promote continued growth of Upward j
Mobility Programs; provide training in Equal Employment Opportunity awareness for NRC managers and supervisors; and assure a climate for improved employee j
norale by promoting and maintaining EE0 counseling activities and supporting advisory committees made up of special emphasis groups.
- j. The Office of the Controller (C0N) provides the budgetary and fiscal management organization for the NRC, including the development and maintenance of a financial control system and a system of accounting designed to conform to the standards prescribed by the Comptro;1er General.
It provides analyses to assess the relationship between program workload and resource allocation, staff year utilization, overhead ratios and work measurement.
Proc'activi ty I
increases continue to accommodate the increasing workload within the Division of Accounting, although some backlogs are still anticipated.
- pi k.
The Office of Management and Program Analysis (MPA) provides management information and analyses for a variety of users within the NRC and is the
!gd office responsible for developing and maintaining the agency's key management 1.
information systems and centralized automatic data processing.
This office I'
designs and maintains a comprehensive management information capability for the l
NRC policy makers and operating officials to use in program management and planning.
It collects, reviews and issues various periodic and special reports on radiation exposure data reported by licensees for use by NRC 1
offices, Congress, other parts of the government and the public at large. The office provides the Commissioners and the ED0 with the current status of NRC 4
programs and relevant issues of major significance; manages and coordinates special projects including Congressionally mandated reports such as the NRC Annual Report; and assists other offices in applying statistical methods and theory to nuclear regulation through agency technical administrative and i
management programs.
1.
The Office of Small and Disadvantated Business Utilization (0SDBU) was created in response to Public Law 95-507 (an Amendment to the Small Business Act and Small Business Investment Act of 1958). Major objectives of the office are to locate small businesses capable of performing NRC contractual requirements, conduct outreach efforts designed to stimulate greater small business interest in NRC programs, and to provide information to small businesses interested in agency contracting procedures.
n\\.J l
85 l
l I
(Dollars in Thousands, except whole dollars in narrative naterial) l Program Direction and Administration - continued m.
The Office of Administratit- (ADM) is responsible for personnel
~
administration; security and classification of sensitive information; document control; agency-wide training; facilities and materials license fees; contracting and procurement; transportation services; telecommunications; rental, maintenance and security of leased buildings, administration of Freedom of Information Act requests; printing and reproduction; records management; Privacy Act requests; support for 152 local public docurent rooms; managing the Headquarters Administrative Support funds; agency-wide interviewee and change-of-duty-station travel as well as a variety of other housekeeping functions.
~
The substantive work of ADM is perforned by the Management Development and Training Staf f, the License Fee Management Branch and the following six operating divisions:
Organization and Personnel, Security, Facilities and Operations Support, Technical Information and Document Control, Rules and Records, and Contracts.
O
+I l
4 l
l l
e!
86 1
l l
U. S. NUCLEAR REGULATORY COMMISSION FY 1983 Budget Estimates (Dollars in Thousands, except whole dollars in narrative material)
LEGISLATIVE PROGRAM PROJECTIONS Actual Estimate FY 81 FY 82 FY 83 FY 84 FY 85 FY 86 FY 87 NRC Total Budget Authority
$ 441 5 466
$ 480
$ 499 5 450
$ 430
$ 430 Budget Outlays
$ 417
$ 447
$ 451
$ 469
$ 423
$ 405
$ 405 i
I e-l 9
87
(Dollars in Thousands, except whole dollars in narrative material) flUCLEAR REGULATORY COMillSS10fl - continued Consulting Services Obligations (in thousands)
Account Title Type FY 1981 FY 1982 FY 1983 fluclear Reactor Regulation Contractual Services 11
$ 160
$ 150 Personnel Appts.
2 60 60 Advisory Committee Consultants Total 13
$ 220
$ 210 Inspection and Enforcement Contractual Services Personnel Appts.
19 15 15 Advisory Committee Consultants Total 5
19 15 15 fluclear Material Safety Contractual Services and Safeguards Personnel Appts.
67 118 120 Advisory Committee Consultants 40 40 40 Total 5 107
$ 158
$ 160 fluclear Regulatory Research Contractual Services Personnel Appts.
2 9
9 Advisory Committee Consultants Total 5
2 9
9 Program Technical Support Contractual Services Personnel Appts.
Advisory Committee Consultants
$ 135 5 145
$ 161 Total
$ 135
$ 145 S 161 Program Direction and Contractual Services
$ 316
$ 200
$ 215 Administration Personnel Appts.
78 166 149 Advisory Committee Consultants Total
$ 394 F366 3 T6T Total Nuclear Reaulatory Contractual Services
$ 327
$ 360
$ 365 Conmission Personnel Appts.
168 368 353 Advisory Connittee Consultants 175 185 201 Total 3 676 5 913
$ 919 0
88
Consulti_ng Services - continued
'3 fiAJOR PROGRAli AREAS flVCLEAR REACTOR Consulting services provide technical advice on plGULAT10fl highly complex and controversial areas on an intermittent buis for the regulation and licensing of nuclear power plants.
This advice is primarily on the methodology, phenomenology, and engineering applications related to core melt accident analysis, in particular, mechanistic analysis of accident sequences, containment loadings, and containment failure characteristics.
Consultants also provide advice on the relationship of geologic structures, selsnic related design mat.ters and earthquakes.
Ifl5pCCT10fl AllD Consulting services are used to f acilitate operations Ellf0RCLl1EtlT of the office, and accomplish a smooth transition of various IE headquarters functions to the regions.
They are also used to critique / evaluate technical training for flRC inspectors with respect to overall IE programs, syst. ems and policies and then reconvend changes where necessary to assure that the proper priorities are assigned to maximize the achievement of office objectives wit.hin the resource limitations, b
flVCt_ EAR MATERIAL Consultant services are used to provide advice on SAFETY & SAFEGUARDS review and analysis methodology for structural mechanical systems in fuel cycle plants (seismic and tornado designs); on fuel processing operations, including high level waste solidification activities; to support the Domestic Safeguards program staf f in conducting special policy studies in areas such as threat evaluation, people-related problems, and clandestine fission explosives; to assist staff in evaluating LLW generation, processing, and storage from disposal perspective to ascertain long term hurial ground performance. Advisory Conmittee consultants include the Advisory Committee on Medical Uses of Isotopes which considers medical questions referred to it by flRC staff and renders r
expert opinion regarding medical uses of radioisotopes and advises flRC staff on matters of
- policy, i
alV 89 P
t
Consulting Services - continued MAJOR PROGRAM AREAS - continued NUCLEAR REGULATORY Research uses the advice of consultants to supplement RESEARCH the expertise of its staff.
Such advice is required in a wide variety of technical areas associated with nuclear power research and standards development work, e.g., epidemiology, radiation health effects, etc. The employment of consultants on an ad hoc basis allows Research to obtain needed advice without increasing its permanent technical staff.
PROGRAM TECHNICAL Advisory Committee consultants assist with the SUPPORT membership of the Advisory Committee on Reactor Safeguards (ACRS) established by statute in 1957.
The ACRS advises the Commission on potential hazards of proposed or existing reactor facilities and prepares a report to Congress as required by Public Law 95-209 on the NRC Safety Program.
PROGRAM DIRECTION Consultants are used on a variety of primarily
- f. ADMINISTRATION technical issues when ad hoc Commission studies cannot be undertaken with the existing resources of our professional staff.
In FY 1981, the two major consulting projects were the NRC Safety Goal and Diablo Canyon proceedings.
Consultants also advise the agency on such issues as job evaluation standards, implementation and applicability of the civil service reform act, violation of selection procedures in defense of allegations under the uniform selection guidelines and evaluating the applicability of a data processing system for recruitment and selection records.
t e
O 90
N.,"2"" 335 1 RE PORT NUMBE R IAssfes o DDCI r
u s NuctEAn nEcut Atony couMissioN
'4UREG-0870 BIBLIOGRAPHIC DATA SHEET
< s n T t E An u Sun T s i t E ta as votum, no,o worno,...
2 ita.,eeres FY 1983 Budoet Estimates 3 nEC,P,e NT S ACCESSION NO 7 AU T HOHISI
$ D ATE HEPOR T CCVPLE TED l vf AR MONTH January 1982 9 Pt M OHMf NG OHGANI/A siON N AME AND MAILING ADOHE SS (/w/uw /.y Codef D ATE RE POH T ISSUE D U. S. Nuclear Reaulatorj Cormission VONTH lVtAR Office of the controller, Division of Budaet and January 1982 Resources Analyses Pashinqton. DC 20555 e a,,,,
o,,,,. ;
12 SPONSOH+NG OHGANI/ AfiON N AVE AND M AILING ADOHE SS trac /v* lip Codel 10 PROJE CT T ASA WOHN UNIT NO 11 CONT H ACT NO 13 T v Pt OF Ht POH T PE Ri O D C O V E Rf D //H lu s',f ddMf)
FY 83 Conoressional Budget Submission
' 10/01/82 thru 9/30/83 153 SUPPL E ML N T AH V NOTE S 14 (L eeve tw a t 16 AHS TH ACT UC0 w o on or /esst Fiscal Year 1983 Budoet Justifications to Congress. The budget estimates for Salaries and Expenses for FY 1983 provide for obligations of $479,500,000 to be funded in total by a new appropriation.
b 17 af Y WOHDS AND DOCUME NT AN ALYSis 1 74 DE SC hip T O HS 17ti iOE NTIFIE RS OPE N E N DE D TE RUS O
18 AV AIL ABILIT Y ST ATE YE NT 19 SE CU RIT Y C L ASS /TN ecoo rA 21 NO OfPA'ES linclassified Unlimited 23 SE CURT TY C L ASS ITN ospJ 22 N CE s
N RC F 0av JJS
- 7 775