ML20038A577
| ML20038A577 | |
| Person / Time | |
|---|---|
| Issue date: | 01/28/1980 |
| From: | NRC COMMISSION (OCM) |
| To: | |
| References | |
| NUREG-0629, NUREG-629, NUDOCS 8111130366 | |
| Download: ML20038A577 (72) | |
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I U.S. NUCLEAR REGULATORY COMMISSION BUDGET ESTIMATES 07d '9' / p'g I
FISCAL YEAR 1981 N
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. i BUDGET ESTIMATE FOR U. S. NUCLEAR REGULATORY COMMISSION FISCAL YEAR 1981 I EEX Genera l S ta teme n t............................................................................... Page s 1-12 Nucl ea r Reactor Regul a ti on ( NRR )................................................................Pa ge s 13-22 S ta nda rds Deve l opme n t ( SD)...................................................................... P a ge s 2 3 28 In spec ti on and En f orceme nt ( 18E )................................................................Pages 2 3-39 Nuc l ea r Ma teri al Sa fe ty a nd Sa f egua rds ( NMSS)...................................................Page s 40-49 Nuc l ea r Regul a tory Resea rch ( R ES)...............................................................Pages 50-62 Program Techni cal Support ( PTS).................................................................Page s 63-65 Program D i rect ion and Admi n i s tra ti on ( PDA).......................................................Pa ge s 66-69 i
S pec i al Su ppo r t i ng Tabl e s....................................................................... P a ge s 7 0-7 2 l
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O U. S. NUCLEAR REGULATORY COMMIS$10N FY 1981 Dudget Estimates GENERAL STATEMENT FOR SALARIES AND EXPENSES (Dollars in thousands, except whole dollars in narrative material)
Estimate of Appropriation The summaries which address obligations include the NRC's Reimbur-The budget estimates for Salaries and Expenses for FY 1981 provide for sable program. It should be noted that the obligations related to obligations of $468,490 to be funded in total by a new appropriation.
this program are not financed by NRC's appropriated tunas, but solely through reimbursable agreements with other Federal agencies.
Estimates of Obligations and Outlays This section provides for the summary of obligations by program on page '
The NRC will deposit revenues derived from the Itcenstre fee 2; the summary of fin 2ncing these obligations on page 3; the analysis of program and indemnification fees to Miscellaneous Receipts of outlays on page 4; obligations by function on page 5; the proposed the Treasury. FY 1981 and 1980 revenues from this source are appropriation language and analysis of the appropriation language on estimated at $13,000,000.
pages 6 through 8; and the narrative summary of NRC programs beginning on page 9.
The following table summarizes the total obligations for NRC's Direct and Reimbursable Programs for FY 1979. FY 1980 and FY 1981.
The detailed justifications for direct program activities are presented in the same order as they appear in this summary table.
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$UMMARY OF DBLIGATIONS BY PROGRAM 4
(Dollars in thousands, except wnose collars in narrative noterial)-
Obligations by Activity:
Direct Program 5
-Actual Estima;e Estimate-
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FY 1979 FY 1980 FY 1981_
Nucl ea r R eactor R egul a t i on...................................................
$ 49.823
$ 74,217
$ 69,385 S t a nda rds D eve l opme n t........................................................
13,440 15,565 16,390 I ns pe c t i on a nd E nfo rc eme nt...................................................
34,353 44,996 53,889 Nuc lear Ma t eri al Sa f ety a nd Sa f egu a rds.......................................
29.232 31,791
' 43,680 Nuc l ea r R egu l a t o ry R es ea rc h..................................................
157,384 204,062 2?B.228 Program Technical Support....................................................
13,131 17.372-18.861 Program D i rect i on a nd Admi ni s t ra t i on.........................................
28,483-34.974 38,057 Total Obligations - Direct Program......................................
$325,846
$422,977
$468,490 Reimbursable Program.........................................................
136 500 500 Total Obilgations.......................................................
$326,042
$423,477
$468,990-Unob11 ga t ed bal a nce, s ta rt of yea r...........................................
-4,805
-5,627 0
Unob11 ga t ed bal a nce, e nd of yea r.............................................
5,627 0
0 O rde rs recei ved f rom. ot her Federa l agenc i es..................................
-263
-500
__ -500-B ud ge t Au t ho r i ty........................................................
$326,601
$417,350 1/
$468.490 1/ Includes M,810,000 for the proposed FY 1980 pay raise supplemental and $49,200,000 for the proposed program supplement.
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s (Dollars in thousands, except whole dollars in narrative material)
Financing of Obligations The financing of the estimated total obligations of $468.490 proposed in the budget estimate for FY 1981 is summarized in the following table:
SUPNARY OF FINANCING Actual Estimate Estimate FY 1979 FY 1980 FY 1981 Source s of Funds Ava il abl e fo r Obli ga ti ons:..................................
Unobi l ga ted bal a nce, begi nni ng o f ye a r.......................................
5 4.805 5 5.627 5
0 Appropriated to NRC..........................................................
326.601 417,350 1/
468,490 Orders received from Federal sources.........................................
263 500 500 Total Funds Available for Obligations...................................
$331.669 IE'U7
$468,990 Less: Unobi l ga ted bal a nce, end of yea r......................................
-5 627 0
0 To ta l Ob l i ga t i on s.......................................................
$326,042 6
5468.990 1/ Includes $4,810,000 for the proposed FY 1980 pay raise supplemental and $49,200,000 for ti:e proposed program supplement, 3
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Outlays for Salaries and Expenses Outlays for 1981 are estimated at $432.830,000. The following analysis This amount less the unexpended balance at the end of the identifies funds available for outlays for each of *he budget periods.
period equals the outlay:;.
DUTLAY ANALYSIS Actual Estimate Estimate FY 1979 FY 1980 kt 1981 Unexpended M1ance, beginning of year:
$124.344-5140,630
$212,927 W! i n ed.................................
9 4.805 5.627 0
" %41 5sted..................................
32__,601 417,350 1/
468,490 6
Appropn etton to NRC.........................................................
Total Funds Ava i l abl e for Ou tl ay s.......................................
T45F,75D T5eT507 -
$681,417 Unexpended balance, end of year:
Obligated...............................................................
$140.630 5-212,927 6-248.587 Unob11 gated.............................................................
5,627 0
0 T o t a l Ou tl ay s........................................................
T369.497 M50.660
$432.836 IT Includes $4,810,000 for the proposed FY 1980 pay raise supplemental and $49,200,000 for the proposed program supplement.
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y (Dollars in thousands, except whole dollars in narrative siiaterial)
' SUPNARY OF BUDGET I
OBLIGATIONS BY FUNCTION i
Actual Estimate Estimate FY 1979 FY 1980 FY 1981 i
Direct Prograr,.
I Pe rs onne l C omp ens at t or;.......................................................
$ 85,362
$ 99.692
$112,730 Personnel Benefits...........................................................
7,526
. 9,4 34 10,820 Program Support..............................................................
186,592 250,969 274,094 Administrative S*pport.......................................................
31,208 46,089 47,366 Travel......................................................................
6.123 7,819 9,200 Equipment....................................................................
9,035 8.974, 11.280 Total Ob11 0 tion. - Direct Program......................................
$325,846
$422,917 1/
$468,490 R e i mbu rs a b l e P rogra m.........................................................
1%
500 500 TOTAL TL GATIONS.......................................................
$326,042
$423,4_77
$468.990 i
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1/ Includes 54,810,000 for the proposed FY 1980 pay raise supplenental and $49,200,000 for the proposed program supplenent.
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O U. S. NUCLEAR REGULATORY COMMISSION PROPOSED LANGUAGE - SALARIES AND EXPENSES (Dollars in Thousands, except whole dollars in narrative material)
The proposed language is as follows:
Salaries and Expenses For necessary expenses of the Commission in carrying out the purposes of performance of the work for which this appropriation is made, and the Energy Reorganization Act of 1974, as amended, including the in such cases the sums so transferred may be merged with the employment of aliens; services authorized by 5 U.S.C. 3109; publication appropriation to which transferred: Provided further, That moneys an1 dissemination of atomic information; purchase, repair, and cleaning received by the Commission for the cooperative nuclear safety of uniforms; official entertainment expenses (not to exceed $15,000);
research programs may be retained and used for salaries and reimbursement of the Ceneral Services Administration for security guard expenses associated with those programs, notwithstanding the pro-services; hire of passenger motor vehicles and aircraf t; $468,490,000 to visions of section 3617 of the Revised Statutes (31 U.S.C. 484),
remain available until expended: Provided, That from this appropriation, and shall remain available until expended.
transfer of sums may be made to other agencies of +.he Government for the 6
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O U. S. NUCLEAR REGULATORY COMMISSION Analysis of Proposed FY 1981 Appropriation Language 1.
For necessary expenses of the Commission in carrying out the purposes 4.
Pubitcation and dissemination of atomic infomation; of the Energy Reorganization Act of 1974, as amended; 42 U.S.C. 2161b 42 U.S.C. 5841 et. seq.
42 U.S.C. 2161b directs the Commt ssion that they shall be 42 U.S.C. 5841 et. seq. the Energy Reorganization Act of 1974, guided by the principle that the dissemination of scientific established the Nuclear Regulatcry Commission to perfom all the and technical infomation relating to atomic energy should licensing and related regt.latory functions of the Atomic Safety and be pemitted and encouraged so as to provide that inter-Licensing Board Panel, the Atomsc Safety and Licensing Appeal Board, change of ideas and criticism which is essential to and the Advisory Committee on Reactor Safeguards, and to carry out scientific and industrial progress and public understanding the perfomance of other functions including research, for the and to enl3rge the fund of technical information.
purpose of confirwatory assessment relating to licensing and other regulation, other activities, including research related to nuclear 5.
Purchase, repair and cleaning of uniforms; material safety and regulation under the provisions of the Atomic Energ/ Act of 1954, as amended (42 U.S.C. 2011 et seq.) and the 5 U.S.C. 5901 Energy Recrganization Act of 1974, as amended (42 U.S.C. 5801 et seq.).
5 U S.C. 5901 authorizes the annual appropriation of funds 2.
Employment of aliens; to each agency of the Government as a unifom allowance.
42 U.S.C. 2201 (d) of the Atomic Energy Act of 1954, as amended 6.
Official entertainment expenses; authorizes the Commission to employ persons and fix their compensation without regard to civil service laws.
47 Comp. Gen. 657 43 Comp. Gen. 305 3.
Services authorized by 5 U.S.C. 3109; This language is required because of the established rule 5 U.S.C. 3109 restricting an agency from charging appropriations with the cost of of ficial entertalruent unless the appropriations 5 U.S.C. 3109 provides in part that the head of an agency may procure involved are specifically available therefor. Congress has by contract the temporary or intemittent services of experts or appropriated funds for of ficial entertairmenc expenses to consultants when authorized by an appropriation.
the NRC and NRC's predecessor AEC each year since FY 195u.
7.
Reimbursement of the General Services Administration for security guard services; 34 Comp. Gen. 42 This language is required because under the provisions of the Federal Froperty and Aduinistrative Services Act of 7
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O Analysis of Proposed Language - continued 1949, specific approprition is made to GSA P-
.rrying out the
- 10. That from this appropriation, transfers of sums may be maoe function of protecting public bui' dings and property, and to other agencies of the Government fcr the perfonnance therefore, NRC appropriations not specifically made available of the work for which this appropriation is made, and in such therefore may not be used to reimburse GSA for security guard cases the sums so transferred may be merged with the
- services, appropriation to which transferred; 8.
Hire of passengar motor vehicles and aircraf t; 64 5 tat 765, Sec.1210 31 U.S.C. 638a 64 Stat 765, Sec.1210 prohibits the transfer of appropriated funds from one account to another or working fund except as 31 U.S.C. 6384 provides in part
- (a) Unless specifically authorized by law.
authorized by the appropriation concerned or other law, no appropriatoin shall be expended to purchase or Fire
- 11. Moneys received by the Commission for the cooperative nuclear passenger motor vehicles for any branch of the Govern-safety research programs may be retained and used for ment..."
salaries end expenses associated with those programs, ano shall remain available untti expended.
9.
To remain available until expended; 26 Comp. Gen. 43 31 U.S.C. 718 2 Comp. Gen. 775 31 U.S.C. 718 provides in part that no specific or indefinite appropriation shall be construed to be available continuously Appropriated funds may not be augmented with funds from other without reference to a fiscal year unless it is made in tenns sources unless specifically authorized by law. These are expressly providing that it shall continue available beyond funds received from foreign governments which in turn will the fiscal year for which the appropriation Act in which it is participate in NRC's reactor safety research experiments.
contained makes provision.
These funds will be used to pay for any costs incioental to their participation.
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U. S. NUCLEAR REGULATORY COPNISSION PROGRAM STATEMENT The NRC was estab11shed by the Energy Reorganization Act of 1974. The Our request for budget authority in FY 1961 amounts to $468 million agency is responsible for assuring that the possession, 'ise and disposal with outlays estimated at $433 million. As previously noted, the of radioactive materials and the construction and operation of reactors funding increase over our revised FY 1980 estimate is primarily and other nuclear facilities are con 6scted in a manner consistent with influenced by TMI considerations, but it also reflects the need public health and safety and the common defense and security, and with for resources in waste management. It will also pemit the NRC proper regard for environmental quality.
to pursue an Improved Reactor Safety program requested by the Congress. This program provides for tne performance of relevant The NRC 1981 Budget Highlights - The accident at the Three Mile Island small-scale experiments to provide data to support development of Unit 2 f acility on March 28, 1979 has had a major impact on NRC program new safety innovations and criteria. The major objectives of this areas. In the days, weeks and months following the accident, the NRC program will be to examine a spectrum of suggestions for improving had to redirect significant resources away from on-going essential pro-reactor safety, to develop tunctional requirements and conceptual grams % respond to the safety issues associated with the TMI accident-designs, and to assess the value/ impact of developing, licensing In late FY 1979, much of this redirected effort required reprogramming and implementation of these concepts, requests which were provided to and approved by Congress. Congress also provided NRC with additional resources to preclude unnecessary In risk assessment, the accident at INI clearly indicateo the delay to the reactor licensing ef fort and to provide for additional need for NRC to address safety isst;es involving accidents beyond resident inspectors at operating reactor sites.
those previously treated extensively. Consequently, the FY 1961 risk assessment. program 1s being redirected and expandeo to cover Resource estimates for FY 1981 contained in this budget request, as well an increasing range of accident sequences, as for the FY 1980 Supplemental Request previously provided to the Con-gress, are predominantly influenced by the TM1 accident. In this regard, The subject of waste management continues to be a national issue, the FY 1980 column of our FY 1981 request assumes enactment of supple-Significant regulatory and research ettorts are required to:
mental legislation. Fundamental changes to nuclear regulation are address the 1mbalance in regional capacity for low-level waste necessary. The NRC is currently developing a Lessons Learned action plan disposal and to develop alternative disposal options; abate the in s 7 port of its own investigations and the President's recommendations emissions from uranium mill tallings; and to provide technical Enumerated in his response to the Kemeny Commission investigation. The assistance to Agreement States for their licensing activities.
resources requested in this budget are essential if regulatory changes are to be made and the President's recommendations implemented on a timely Also, NRC's current level of ef fort to develop a regulatory and basis to ensure a safe nuclear option. We recognize that these resources licensing capability for high-level waste repositories must be may not be adequate to carry out both the current tasks as well as those augmented. In this regard, NRC expects to receive High-Level tasks anticipated as the results of all TMI investigations when they are Waste site characterization plans on two sites by the end of fully evaluated. Additional FY 1981 personnel may be necessary.
1982. This will require additional ettort by NRC to provide early character 12ation guidance and to develop its capability to in response to the President's recommendations, the NRC 15 accelerating review and act on the plan with a tralned, competent statt.
i the resolution of generic and specific safety issues as well as expanding inspection and enforcement functions, particularly through the addition of The highlights addressed above are described in more detail in more resident inspectors to the program. Specific actions imposed upon subsequent pages. The NRC is actively pursuing the Implemen-the utilities will require substantial NRC oversight to evaluate and tation of necessary regulatory changes that have been clearly accredit industry ef 50rts to assure that prompt and ef fective attention indicated as a result of the TMI accident. In this context is being given to needed safety questions. Improvements in reactor there follows a briet description of each of NRC's muor programs; operator perfomance ne.essitate the development of more rigorous criteria fcc operator and supervisor qualifications, expanded and im-Nuclear Reactor Regulation - The assurance of adequate safety and proved use of simulators, and NRC examination and recertification at environmental protection for nuclear power plants will continue to licensed operators. Since the IMI investigations have indicated tnat be the primary objective of this ottice. Since the FY 1961 budget human error was a significant contributing f actor to the TMI accident, request was developed, NRR has been evaluating tne reconmiendations operational safety and reliability of nuclear power plants must be of the various Three Mile Island (1MI) investigative groups and improved through better control and instrumentation system design, implementing the lessons learned. A comprehensive NRC task action infomation display techniques, and advanced training methods. All plan is being developed for coordinated and phased implementation c:f these actions are resource dependent.'
of IMI recommentiations, including the prerequisites for resumption 9
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O U. 5. NUCLE AR REGULATORY COPNISSION of nuclear power plant licensing activities. It is likely that this 1980). Under this expanded program, sites with operating and action plan will require additional resources beyond those in the present preoperational reactors will have as many resident inspectors FY 1981 request. Our highest priority continues to be in the area of assigned as there are reactors in these phases, with a etn1 mum of operating plants, since they represent the more immediate and potential two residents at each scch site. Resident inspector coverage at safety and environmental concerns as compared to reactors under con-reactor construction sites will also be Increased by the beginning struction or construction pemit review. Major objectives associated of FY 1981 to include assignment of 24 residents to construction with this activity are the efforts directed toward the elimination of sites. At all reactor sites with resident inspectors, more direct the excess backlog of operating reactor actions (defined as more than observations of licensee work performance will be conducted.
ten unresolved licensing actions per reactor) by the end of FY 1984 Also, region based inspectors will provide increased independent and the completion of 21 of 22 generic tasks addressing the " Unresolved measurements such as envirormental sampling, non-destructive Safety Issues" identified in the 1978 NRC annual report by the and of testing, and verification of equipment calibrations at all reactor FY 1981. This involves the continuation of NRR's program to improve the sites. Finally, the Revised Inspection Program will be expanoed current Itcensing methodology and approach for amendment / actions and to include increased Program Appraisal inspections at fuel thereby minimizing the number to be reviewed by the statt. Also NRR facilities, material licensees and vendors, and management has established an interim organization specifically assigned to continue appratsal inspections of licensees having reactors in con-work on " Unresolved Safety issues" in an ef fort to minimize the impact struction, startup, and preoperational testing. New intstatives of the resource drain the TMI-2 accident has had. NRR will continue will be undertaken in the Fuel Fac111 ties and Materials Safety to apply increased efforts to improve the competency of nuclear power program to allow inspection of new materials Itcensees within plant operators.
six months of Itcense issuance; more frequent contact witn low-risk matertals Itcensees; and expanded radiation protection.
Standards Development - During FY 1981, the standards development radioactive waste processing and environmental monitoring effort will be directed at: developing detailed supporting stand-capabilttles. The Safeguards program will provide adatttonal ards to complement the broad performance requirements that are in support to the timely implementation of tne joint US/lAEA place; developing new standards to reflect needs identitled in the Sateguards Agreement. One lesson learned as a result of the licensing and inspection and enforcement processes; and updattn?
TMI accident was that the NRC incident Response Center f acility standards to reflect expertence from plant operation, research re-15 inadequate as a command post for dealing with events sucn sults, feedback from users of standards, advances in technology and as IMI. Accordingly, the NRC Incident Response Center will be improved regulatory practices. Engineering standards will include improved to increase its capability for dealing with possible work in the areas of qualification of equipment, inservice inspec-future nuclear accidents or safeguards threats.
tions and testing, decommissioning, transportation of radioactive materials in urban areas, and consumer and industrial products con-Nuclear Matertal Safety and Satesuards - During FY 1981, the High-talning radioactive materials. Site and health standards work will Level Waste Management Program will continue to work on tulttiling include a major revision to reactor siting criteria, development of NRC's respons10 tittles pertaining to the national program of effective regulations for the licensing of high-level waste repost-developing a high-level waste management Capability by promul-tories and low-level waste burial f acilities, issuance of guidance gating the final regulation, on tne geological disposal of sucn for maintaining radiation worker exposures as low as reasonably waste (10 f,FR 60) and providing detailed guidance to the Department achievable, continuing review of the data base on biological of Energy on acceptable procedures to charactertze and finally effects of low-level radiation exposure, safeguards standards for select a site in bedded or domed salt. In Low-Level Weste, work physical protection and material control, and emergency planning.
will continue on: (1)the development of a regulation for the cis-There will be a continuing review and assessment of NRC's positions posal of low-level waste (10 CFR 61); (2) the licensing casework in a number of regulations and guides as a result of the events at consisting of applications for new sites or amendments for existing Three Mlle Island. The Office of Standards Development will cor.-
licenses; and (3) requests true tne Agreement States for assistance tinue to coordinate the NRC involvement with the U.S. national for their 11 censing activity. Urantum Recovery Licenstng ef fort standards program and to manage U.S. technical activities in the will increase as a result of additional assistance to Agreement International Atomic Energy Agency's development of regulatory States and requests for Itcensing actions to bring operating mills standards for nuclear power plant safety.
Into compliance with EPA radiation standards. Fuel Cycle and Material Saf ety Licenstng requirements will be broaoened to include Inspection and Enforcement - In FY 1981, the Of fice of Inspection "as low as reasonably achievable" (ALARA) occupational exposure and Enforcement will continue to implement the Revised Inspection levels for radiotsotopes 11censees. Other new radioactivity limits Program (Initiated in FY 1978 and expanded significantly in FY and personnel exposure requirements such as the Clean Air Act will 10
U. S. NUCLEAR REGULATORY C0ktt!SSION broaden licensing requirements for fuel cycle plants and f ac111ttes.
help provide timely regulatory guidance to potenttal Itcensees, and Wortt will continue on performing detailed accident assessments and to turnish the technical bases for licensing, regulation and developing radiological contingency plans for fuel cycle and materials inspection of waste disposal sites. The advanced reactor saf ety plants and factlttles. Radiological surveys of potentially contaminated research program (Fast Breeder Reactors and Advanced Converters) former licensee sites will continue. Work will continue on the evaluation will be phased out by the end of FY 1981, of regulations, procedures and measures of analysis with regard to severe accidents in the air, road, rail and water modes for the transportation Program Technical Suppo_rt - The organizations in this category of radioactive materials. Safeguards emphasis will concentrate on W RS. Boards and Panels. Ezecuttve Legal Otrector. International improving the timeliness, sensttivity and dependability of Itcensees' and State Programs and the newly created Ottice for Analysis and matertal control and accounting systems to detect the <11 version of Evaluation of Operational Data) directly support the safety and material. Licensees' physical security safeguards will be assessed to safeguard mission of the Commission. In FY 1981 increased ettorts assure compItance with the upgrade requirements established in FY 1980.
w111 De directed toward expanded saf ety review acttwity and in-In FY 1980, NRC has consolidated within NMSS the reactor and fuel cycle proving the review and analysis of operational data received tros safeguards licensing functions that had been divided between NRR and NRC licensees as well as legal support to accomodate growtn in the NMSS. This consolidation was based on an NRC review that considered waste management program and in international export and sateguards the current and projected levels of saf eguards activities and the matters. Within the Otttce of State Programs the major requirement maturity of the programs, and has enabled the NRC safeguards effort to continues to be the need to obtain rapid and thorough reviews of be more ef ficiently managed under a centralized program and also allow state emergency response plans. Discusstons are currently underway a savings in resources.
between NRC and FEMA on the possible transfer of the emergency preparedness function, Based upon those discussions and innal Nuclear Regulatory Research - The FY 1981 research program for NRC will disposttion, resources between the two agencies will be adjusted.
continue to be responstve to the issues raised or reemphastzed by the Three Mile Island accident. Implementation of this program will be Program Direction and Administration - The ottices under this accomplished by both short-term additional effort and long-term category indirectly support the utssions of the Comission and reortentation primarily in the large Loss-of-Coolant Accidents (LOCA) provide financial, administrative and logistic support. In FY and related programs to emphasize work on small LOCA and transients 1981 NRC is requesting $500,000 in program support in this area events. In connection with the Loss-of-Fluid-Test (LOFT) f acility to intttate a ptiot intervenor tunding program to alleviate some program, which NRC assumed full responsibility for funding in FY 1980, of the financial burden of Intervenors who otherwise would not be increased emphasis is being placed on small break LOCA's and operational able to make constructive contributions to safety hearings.
transients which have been highlighted in the lessons learned from the Additional resources are also directed toward expanding tne TM1 accident and recomended in the President's Commission Report.
Equal Employment Opportunity function, accomodating expanded During FY 1981, research to improve reactor safety will be devoted legal workload within the Ottice of the General Counsel and primarily to critical studies to imprc.e in-plant accident response increased contractual workload as a result of greater empnasts and to evaluate alternate containment concepts and decay heat removal on competittve procurements.
systems to support development of relevant safety requirements and criteria. In FY 1981 the risk assessment program will be Personnel Overview - The administratton has agreed tnat 146 tull-expanded to evaluate accident sequences which may lead to severely time temporary positions, provided to NRC over the past several famaged Cores and to examine operating reactors using quantitative years, should be Converted to full-ttee permanent positions. ints i
risk assessment methods to assess the integrated safety of overall action, whicn is reflected in our FY 1961 request, recognizes that reactors. This ef fort will also include analysts of equipment in the split of the Atomic Energy Comission, NRC was not treated fatlure data, waste isolation studies and research to enable NRC equitably in terms of transfer of administrative and logistic to better dettne acceptable risk criterta. Research in primary support personnel, thereby severely impacting the agency's admints-system integrity, seismi: and reactor environment areas will be trative support function. To provide tne required support, we conducted to provide rational bases for NRC dectstons regarding the have used, witn OMB's approval, temporary employees, some of whom vulnerability of nuclear f actlttles to earthquakes, tornadoes, have been with NRC since its inception. This situation has floods and other internal phenomend under normal or plant accident resulted in a gross inequity for these temporary employees, conditions. Further research will be carried out on the structural l'rtmarily women, who are not eligible f or employee benett ts.
f ntegrity of Light Water Reactors (LWR) primary system pressure For comparabilt ty purposes, the F Y 1979 and FY 1960 personnel boundary, including pressure vessels, piping and steam generators.
levels shown in our request have been revised to reflect this NRC will increase its waste management research on a broad scale to change.
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O U. S. NUCLEAR REGULATORY COMMIS510N Af ter adjusting for the conversion of full-time temporary personnel dis-cussed above, the NRC is requesting an increase over FY 1980 of 150 positions, approximately half of which are for inspection and enforcement for a new ceiling of 3,390. This increase, addressed in detail in the individual program justifications, is required to handle increases in fuel f acility caseload; to provide increased oversight in the areas of emergency planning, in-plant radiation protection and environmental monitoring; to permit increased ef fort on the inspection of licensees of industrial applications, medical factittles, and academic applications; to provide additional region based inspectors for reactor construction inspection; to provide support to an expanded Waste Management Program; to address t
safety issues raised as a result of the TMI incident; and to reflect increased workload in import / export licensing matters.
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(Dollars in Thousands, except whole dollars in narrative material)
I'JCLEAR REGULATORY C06911SS10N - continued
$69,385 Nuclear Reactor Regulation............
Summary of Nuclear Reactor Regulation Estimates by Function Estimatgj Estimate Actual FY 1980 FY 1981 FY 1979
$20,615
$24,348
$27,230 Parsonnel Compensation....
1.817 2,301 2,614 Personnel Benefits.
17,0573f 30,413 26,073 Program Support.........
9,237 15,850 12,238 Administrative Support...
Equipment....................
1,053 1,305 1,230 Travel........
44 0
0 Total Obligations.......
$6
$6
$6 (605)
(722)3/
(722)
Parsonnel..........
The Nuclear Reactor Regulation personnel requirements and program support funding requirements (primarily contractual support with DOE Itboratories and private contractors), have been allocated to major programmatic functions as shown below. The narrative that follows
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provides justification in support of these requirements.
Ariual FY 1979 Estimate FY 1980 Estimate FY 1981 Dollars gPe Dollars Ae Dollars People P
le le
. Ope' rating Reactors...............
FG un I~B,873 229 N
252 Systernatic Evaluation of Operating Reactors....
1,265 32 1,300 32 950 32 4,856 211 11,185 170 6,888 182
[
Casework..............
5,622 126 7,740 226-7,415 187 Ttchnical Projects.
982 9
1,315 5
1.050 8
Advanced Reactors......
0 11 0
- 11 _
0 13 Standards Assistance.........
B 23 0
' 28 0.
'25 Training and Correspondence...
0 18 0
21 0
23 Management Direction..........
E M
M M
M Totals...........
77 o
1/includys 51,099,000 transferred to NHSS-Physical Sectrity Safeguards. s s-g
-y Includes $1,179,000 for FY 1980 pay raise supplemental and $16,299,000 fb,r EY 1980 program supporty pptveital.
}
3fincludes four positions tenp6rarily asslyted to the U.S. Army Corps c'f Ennineers.
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(D911 Ars in Tho'usands, exce,st whole dollars in narrative material)
NUCLEAR REAC10R REGULATION c continued TheOfficeofNuclearReactorRegukatioq(hRR)performsthesafety, Continue efforts to resolve generic technical issues in environmental, and antitrust reviews of nuclear reactors prior to direct support of the licensing process. A number of licensing. This office is charyd with the responsibility for generic tasks have t een designated as " Unresolved Safety reviewing applications fos constWction permits (CP's), operating Issues" by the Commission. These geneth tasks tvill licenses (OL's), changer to operating licenses for nuclear power receive priority in the NRC program.
plants, and the review enti licensing of research and test reactors and other reactor de$igns. Organizationally, the licensing effort is Conduct value/ impact analyses to assure) hat the impact divided among the office's tour major divisions to: (1)3eview of each regulatory action is (omnensurate with the value proposed changes in desi p and operaticn of operating reactors; (2) in t rotecting the public.miihe environent.
carry out the project management functions for safety reviews of CP.
and 01 appl! cations; (1) per form detailed safety reviews of reactor To meet,these objectives, NRR will continue to optimize its applications through the operating license stage; and (4) evaluW e resources by internal reallocations. ' Additional personnel saf=ty and environmental aspects of reactors and sites. Also, bdR will be allocated to Operating Reactors and Trenical Projects has respesibility for the antitrust and indemnification aspects of in ordar to reduce the unacceptatte backlog of operating reactor nuclear f acilities, amendment /lirensing actions consistent with our goal of elimination 3f the excess backlog (i.e., more than' ten Specific objectives of the program are:
unresolved licenstr.g actions / plant) by the end of FY 1984; to laplement needed changes to operator Mining and licensing Assure the safe operation of operating reactors.
and requalifications consistent with the reconmendations of the Three Hile Island (TMI) accident investigations; to provide Assure that operatir.g reactors are adequately protected against for the development, maintenance and revision of Standard industrial sabotage.
Review Plans to address the increased depth and scope of staff technical review during licensing, as needed for implementation Assure that reactors are designed, constructed and operated to of the THI short terin lessons learned; and to rnduce our assure the protection of the public health and safety and the dependence on vendor and licensee-submitted calculations environment.
consistent with attainment of a rapid response role in Continue progress toward the goal of expedited reviews for standardized applications. This includes reviews of reference designs for standard application, reviews of applications The necessary resources to implement the short tern lessons utilizing previously apptowed standard designs, and reviews of learned from the IMI accident are detailed in the following replicate and duplicate plants.
program summaries.
Conduct Early Site Reviews (ESR) to remove some or all site suitability issues from the critical path of CP reviews.
O erating Reactors..
FY 1979 = $4,332 Fi 1980 = $8,813 FY 1981 = $9,770 J'
' ' ~ -
(175)
(229)
(252)
In FY 1981 NRR will give the highest priority in resource allocation to operating plants, since they represent the more immediate poten-tial safety and environmental concerns as compared to reactors under construction or construction permit review. Continuing activities in this area included:
14
m.
g.-
y
-Y s
,f f.
s
.r
+
3 e
s (Dollars in Thousands, except whole dollars in n,.riative material)
NUCLEAR REACTOR REGULATION - continued j
Assuring plants continue to operate safely by evaluation of specification requirements on repor; ting, the use yf the operating experience, design information, inspection and enforce-Of fice of Inspection amt Enforceae.d for snee r4otine ment findings, and taking necessary action in the form of requests and implemented stwfardized t,echnical specifi-licensing orders and changes in allowable op' rating conditions.
cations for all older facilities.
.r Prevent unnecessary restrictions in plant operations by prompt By implementing program improvements, we' expect to reduce review and modification of licensee requests'for reactor fuel the number of routine new actic4.< from 15 per plant per reload appilcations.
year to 12 per plart per year by end cf FY 1981. We f.
also expect to cut the aversge napowr requirements s
Continue to re"lew and evaluate operating reactor problems and per action for both staff-and contractor processed, events and resolve each issue in a manner consistent with actions by the,end of FY 1981.
continued safe plant operaticn.
As a result;of the IMI actident, ther, will oe a large License " operators" and " senior operators" to assure facility increase in the operating reactors workload starting in i
personnel are adeque.ely trained to safely operate a nuclear FY 1980J This will b9 largely in the form of additional actions. Amandments/ actions will be' handled by a co6ina-plant under all con 6ftfons. Renew operator licenses
~
periodically after a verification of the individual's
.tien of-staff effort and technical assistance from contrac-qualifications.
t;.-s.
In FY 1981, about 1770 actions will be ccepleted.
Tnis will reduce excess backtrg to about 1560 actions by As a result of Three Mile Island investigations, a significant the end of FY 1981 and support the paal of reducing the increase-is being implemented in the scope of operator licensing excess backlog, including the large additional workload exams and related supporting activities. The increases are as due to IMI, to zero by the end of (Y 1984.
follows: (1) addition of simulator exams to cold and initial i
hot exams; (2) addition of simulator exams to power ficility With the transfer of most of NRR's Safeguards functions replacement exams; (3) auditing of requalification programs at in this area to MMS 3, a nominal effort is included in half of the operating sites each year; and (4) auditing half of operating raactors efforts in FY 1980 and Ff 1981 for the vendor and utility operated training centers each year. We safeguards-related transition and coordination efforts, expect to administer about 135 9perator licensing exams in FY 1980. In FY 1981 we anticipate completing 150 operator In addition to regular operating reactor ef forts, nonroutine licensing exams.
operating events require immediate attention. NRP is required to maintain a prompt response capability to review unexpected Continue to assure that operating experience is fed back into or unanticipated operating events to assure public safety.
the licensing process including amending licenses, as necessary, Resources for this effort are required to review and evaluate to reflect the results of the IMI accident lessons learned.
unanticipated operating reactor events and resolve each issue in a manner consistent with continued safe plant operation In FY 1981, NRR will continue its program to improve the current for the plant where the event occurs. Also, other similar licensing clethodology and approach for amendment / actions and facilities are evaluated to determine if they are affected.
thereby minimize the number of needed actions while increasing if safety margins are reduced, prompt action is taken to the efficiency of processing. Improvements to be considered reestablish those margins.
include reduced technical specification requirements on reporting, administrative handling of certain actions, and use The major objectives of the non-routine effort are:
of dedicated personnel or routine action processing. Included in this program will be the effect of reduced technical Evaluate unexpected safety and environmental problems at operating plants as they occur. Develop a regulatory position on each problem or event for the specific facility 15 4
O O
O (Dollars in Thousands, except whole dollars le narrative material)
NUCLEAR REACTOR REGULATION - continued where the event occurred, and determine necessary action There have been three major groups investigating the IMI-2 at all other operating reactors to assure that adequate accident (long Term lessons Learned-NRR, the Special TMI margins of safety are maintained and identified deficiencies Investination Group-NRC, and the Presidential Investigative
{
corrected.
Group) in addition to the Congressional investigative groups.
As these groups c wplete their investigations, it is antici-Factor lessons learred from each unexpected event back into the pated that their reconv ndations will generate a signiff-licensing process to assure that applications under licensing cant number of operating license actions. Presently, it is review (CP and OL) include consideration of this event and that not possible to accurately identify the number of actions necessary followup action is taken. Such action would then help
.that will result from the investigative groups. Therefore, to assure that such an event would not occur at a newly licensed a " planning wedge" is included to provide resources to complete plant. All facilities under licensing cognizance would be' a portion of the anticipated actions that will surface as the required to address this concern.
results of the investigative groups are cropleted. The contingency ($3,700.000 in program surpo n) will enable NRR Review and analyze operationM data as ociated with power reactors, to complete an additional 385 licensing actions in FY 1981.
I including evaluation of literste event reports, stanup test data, An additional major action that we plan to undertake is the and inspection reports. This effort will provide for improved implementation of emergency p2anning procedures for all tracking and documentation of operating expeaience, early identification operating a7d near tern OL plants in accordance with the of potential areas, improved and systematized review procedures, and lessons learned from TMI. The details of these procedures are efficient feedback of experience into the licensing process thrcugh the presently being developed as a part of the TKi-2 Action Plans.
standardized technical specifications ef fort and liaison with the 4
licensing groups.
FY 1979 = $1,265 rY 1980 = $1,300
'FY 1981 = $950-Systematic Evaluation of Operating Reictors.....
(32)
' (32) 02)
Because of the recognized deficiencies in documentation of the accept-Phase Ill, application of the SEP to the reoaining ability of older licensed plants and the increasing amount of staff operating facilities, will commence as Phase II is time being devoted to developing such dMusentation on an ad hoc basis, completed. Details of this phase are currently under a plan and program have been developed for performing a systematic development.
review of operating nuclear power facilities. This effort, designated the Systematic Evaluation Program (SEP), reviews operating power reactors Regulatory Requirements Review Committee (RRRC) decisions with respect to current licensing criteria and documents the results and which affect operating reactors will be implemented as part 1
identifies the need for plant changes. The program was initiated in of the SEP.
late FY 1977.nd has been developed into the follewing phases:
I The major objectives of this program are:
4 Phase I, the development of a list of topics to be used in per-The SEP will assess the safety adequacy of the design forming the systematic evaluations, has been completed. Examples of topics include seismicity, missile protection, and reactor and operation of currently licensed nuctrir power plants, 1
coolant boundary leak detection.-
and will provide the technical basis for the conversion..
of Provisional Operating Licenses to Full Ters Operating Phase !!, the actual evaluation of the 11 oldest facilities, has Licenses.
commenced and is scheduled for completion in FY 1982. This phase had been scheduled for completion in FY 1981, but slipped because The program will establish documentation which shows resources had to be transferred to THI-2 support activities.
how each operating plant reviewed compares with current criteria'on significant safety Issues, and will provide i
a rationale.for acceptable departure from these criteria.
i 16 4
O O
O (Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REACTOR REGULATION - continued The program will provide the capability to make integrated and Of 1500 review topics identified in Phase II, about 550 either balanced decisions with respect to any required backfitting, were completed or a course of action determined at the end of FY 1979. An additional 700 were under review. All of The program will incorporate procedures which assure early the remaining topics will be completed by FY 1982 and Phase til identification and resolution of any significant safety deficiencies.
will be implemented in FY 1982.
The work is carried out primarily by a dedicated staff group in a separate organizational component and is supported by contractors in specialized disciplines as needed. This assures consistent interpre-tation of the regulations and continuous access to those knowledgeable of prior licensing criteria.
FY 1979 = $4,856 FY 1980 = $11,185 FY 1981 = $6,888 Casework.
(211)
(i70)
(182)
Casework is that effort associated with the safety, environmental, additional internal audits of the staff's review of licensing and antitrust application reviews of Construction Permit (CP), Operating applications and to identify where further improvements can be License (OL), standard plant design, and early site applications.
made in implementing the standardization concepts of preliminary The CP covers the applicant's proposed site and preliminary design of design approval (PDA) extensions, standard design approvals a nuclear facility and also includes a detailed review of the site (SDA), and final design approvals (FDA),
selection process, and the safety and environmental aspects of the proposed site. This review must be completed prior to the start of The major objectives of the casework effort are:
major construction. A limited work authorization (LWA) may be issued prior to issuance of a CP if all environmental and site suitability CP's - Continue to recommend appropriate actions regarding considerations are satisfied. The OL review involves the review of CP's for auclear power plants af ter a satisfactory review the final design of the plar.t. This phase starts approximately three of safety, environmental, and antitrust matters. Continue years prior to the expected fuel load date. The standard plant design to work toward shorter average safety and environmental concept offers an opportunity for reactor designers and architect review schedules for new cases. Imp 1&nt a number of engineers to submit standard designs for review that can be referenced recommendations contained in a statf study (NUREG-0292) by future license applicants. Early Site Reviews (ESR) are conducted direrted toward development of early staff positions and to evaluate the environmental and site suitability aspects of sites issuances of safety evaluation reports (SER's) six months to be used in future CP appilcations. The issuance of approval from after docketing an application, New CP appilcations NRC following these standard plant and site reviews is an affirmation received in FY 1980 and beyond will have a target review tarly in the licensing process that the designs and the sites identified schedule of 24 months from docketing to preliminary by the applicants will provide the.necessary assurance for adequate decision date by the Atomic Safety and Licensing Board (ASLB).
protection of the public health and safety while the sites satisfy on CP issuance. Continue to perform antitrust reviews on a the National Environmantal Policy Act (NEPA) criteria for preserving schedule so thc' decisions resulting from these reviews are the quality of the environment. Efforts are being directed to improve reached in a tlw frame consistent with the prospective the licensing process by implementing new procedures aimed at increasing decision date for safety and environmental matters affecting CP's.
the efficiency and effectiveness of the staff in processing licensing applications. In addition, efforts are included in this-unit to perform OL's - Continue to grant operating licenses for nuclear power plants after satisfactory review of the final design of the application to assure the facility can operate 17
/"N O.
U ON (Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REACTOR REGULATION - continued without endangering the public health and safety and in New and/or ewpanded environmental qualification accordance with applicable environmental regulations. Continue requirements for safety grade equipment within to schedule OL reviews in a timely manner to assure the review containment, process will not be a critical path item that would delay the react r fuel load and startup testing.
Implementation of atmospheric transport models to forecast and hindcast release. impacts, Continue to perform selected early site reviews (ESR) to remove some or all site suitability issues from the critical path of CP Pump and valve operability and reliability assurance,.
reviews. These reviews can decrease portions of the site /
environmental reviews when the applicant subsequently submits a Revised criteria on hydrogen generation and requirements CP application. Such early reviews can also accelerate the on hydrogen recombiners, issuance of a Limited Work Authorization (LWA) which enables the applicant to start some construction prior to issuance of the New requirements for containment atmosphere sampling, CP.
Revised containment isolation criteria.
Standard Plant Designs - Continue to review and approve various standard plant designs that will provide impetus to the industry to utilize one of the various standardization concepts. This The following table summarf res new applications and planned will increase the predictability of the acceptability of plant licensing action completions in FY 1979 - FY 1981.
design from the licensing review standpoint. Pursue potential efficiencies of standardization in trying to achieve the goal of FY 1979 FY 1980 FY 1981 a shorter average CP safety review. The use of standard plant CP designs in concert with a previously approved site should result incoming
'2 1
0 in significant savings in time and money to the nuclear industry under review 19 18
.16 with no adverse impact on overall safety.
completed 2
0
.3 Continue to improve the stability and predictability of the OL licensing process by increased use of rulemaking and review of.
incoming 4
16 7
changing requirements by the Regulatory Requirements Review under review 37 53 52 Committee (RRRC).
completed 0
e 9
Significant impacts of the Three Mlle Island accident occur in Std Plant the reviews of OL's, CP's and Standard Plants. The effort applied incoming 1
0 3
to casework is not to resolve the problems identified by TMI, under review 10 10 9
but to implement the lessons learned into the actual reviews.
completed 0
4 4
This results in increased review scope and depth in certain of the review areas as listed below, for every licensing case.
ESR incoming 2
1 0
Enhanced e.aergency planning activities, under review 6
7 2
completed 0
5 2
Implementation of new and/or revised accident analysis requirements, 18
- -~
O O
O (Dollars in thousands, except whole dollars in narrative material)
NUCLEAR REACTOR REGULATION - continued FY 1979 = $5,622 FY 1980 = $7,740 FY 1981 = $7,415 Technical Projects.
(126)
(226)
(187)
The Technical Projects effort encompasses several different types of of Generic Issues Related to Nuclear Power Plants").
technical activities necessary to directly support licensing activities.
Seventeen issues in the NRC grogram have been identified The types of activities included in this program are described below.
as " Unresolved Safety issues by the Commission and their progress is discussed yearly in the NRC Annual Report a.
Topical Report Reviews - NRR reviews reports submitted by industry as required by Section 210 of the Energy Reorganization.
organizations (usually reactor vendors or architect / engineers)
Act of 1974, as amended. These generic tasks will receive on generic technical subjects. Efficiencies are derived by con-priority in the NRC program.
ducting these reviews independent of construction permit or operating license reviews. Generic technical positions result The objectives of the Technical Projects effort are:
f rom these reviews that are then incorporated by reference in the staff's evaluatice of individual license applications, and Topical Report Reviews - To review industry submitted need not be further considered in individual case reviews; thus, topical reports that are incorporated by reference in both staf f and applicar t resources are utilized more ef fectively.
license applications by providino the basis for staf f acceptance in particular review areas at a pace consis-b.
Contract Management - This effort involves the selection of tent with maintaining licensing schedules.
contractors and the review of the technical progress on NRR con-tracts for technical support on specific licensing applications Contract Management - To provide ef fective contract and generic activities. NRR responsibilities include the technical management to assure that the proper programs and con-direction of programs performed at DOE national labs, universities tractors are selected, that the scope of work is being and private firms, accomplished, and that the information needs are being met in the most efficient and effective manner.
c.
Non-NRR Support - This effort includes direct technical assistance to other NRC offices (with the exception of the Office of Standards Non-NRR Support - To provide direct technical assistance Development), principally the Of fice of Nuclear Material Safety and to cutside organizations (primarily to the Office of Safeguards, other Federal agencies, and support of international Nuclear Materials Safety and Safeguards to perform por-technical exchange prog ras.
tions of their reviews of fuel cycle facilities, such as reviews in the earth sciences area for the high and d.
Research Coordination - This ef fort invcives seural NRR activities low level waste disposal facilities) when the particular related to interfacing with the Office of Nuclear Regulatory technical expertise is available only in NRR.
Research (RES) including the development of NRR research needs Research Coordination - To maintain coordination with to support licensing activities, participation in research review groups, reviewing contract proposals, assisting in contractor the Of fice of Nuclear Regulatory Research to assure that selection, and providing technical guidance for research contracts.
research ef forts properly consider NRR's needs and that In addition, manpower is budgeted to assure that research results research results are fac'ored into NRR licensing are documented and introduced into the licensing decisionmaking.
activities.
process.
Generic Issues - To resolve genaric technical issues e.
Generic Issues - This effort involves the corduct of activities and thus provide added assurance of plant safety and to develop technical positions on issues that relate to the improve the perception of the public th9t NRC is safety, or enytrunmental aspects of nuclear power plent design, responsibly meeting its reoulatory obligations. In construction, or operation. These tasks are conducted in direct addition, to provide the NRC staf f with adequate calcir support of licensing activities and are analyzed within the frame-lational capabilities to perform independent analyses work of NRR's generic issues program (described in a report sub-and to update the Standard Review Plan to enhance the mitted to Congress as NUREG-0410. "NRC Program for the Resolution discipline and efficiency of the review process.
19
1 O
. O O
(Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REACTOR REGULATION - continued Substantial reprogrammina of NRR manpower resources into operating received from RES, and NRR personnel have participated in the reactors and casework was necessary in FY 1978 and FY 1919. In research review group meetings and RES program reviews. NRR addition, substantial further reprogramming has taken place in the personnel, in concert with RES and the Office of Management and second half of FY 1979 to address the high priority efforts associated Program Analysis, have established a sys'.ee to track and document with the Three Mile Island accident. This reprogramming resulted in the products of the RES programs and their subsequent use in the substantial manpower reductions in the Technical Projects area in FY licensing process. This system wi1* centinue to be used to increase 1978 and FY 1979. Further, several additional generic issues haea the quality and efficiency of the licensing process in FY 1981.
been identified from the TM1 lessons learned and are part of the Generic Issues - The NRC identified 17 " Unresolved Safety Issuef in workload starting in FY 1980. A number of Unresolved Safety issues.,
the 1973 NRC Annual Report, which are addressed by 22 high priority -
are likely to be identified as a result of further investigations of generic tasks in the NRR generic issues program. By the end of the Three Mile Island accident. Task Action Plans to address these FY 1980, 13 of these generic tasks are expected to be completed. Eight issues will be developed as these issues are identified (probably in of the nine remaining generic tasks are expected to be completed in
. The expected accomplishments in this decision unit are as FY 1981. Nine new " Unresolved Safety Issues" are expected to be :
identified during FY 1980 and FY 1981. Generic tasks to address these new issues will be initiated as they are identified. In addition, Topical Report Reviews - In FY 1979, the NRR staff completed special generic studies of low probability-higa consequence accident reviews of approximately 30 topical reports. However, about scenarios such as core melt, hydrogen generation and behavior and 30 topical reports have been submitted for review during steam explosion phenomena will be started.
this time frame and this rate of submission is expected to continue through FY 1983. Through increased allocations of Standard Review Plans - Significant revisions to. the Standard Review resources plus increases in efficiency in review procedures, Plans, delayed by the impact of the Three Mlle Island accident, will completion of 40 topical report reviews per year can be achieved be accomplished in FY 1980 and FY 1931.
beginning in FY 1981, thereby permitting NRR to reduce the Audit Calculations - Audit calculations were accomplished on a Timited backlog of unreviewed topical reports beginning in FY 1981.
scale because of the unavailability of adequate resources for this Contract Management - An information retrieval system has been purpose in FY 1979. The requested resources will permit this function to be carried out on a slightly larger scale in FY 1981.
established that summarizes the scope and anticipated use of the results from all recent Program Support contracts. A system has Licensing Improvements suring FY 1979, the improved CP review also been established for forwarding program briefs to provide procedures were implemented successfully'on the Palo Verde 4 & 5 guidance for the preparation of work statements by contractors.
application with the completion of the safety evaluation report in Due to resource limitations, technical direction of contracts six months. A major reassessment and revision of the standardiza-has been maintained at the minimum level that is acceptable for tion program was completed to increase its effectiveness. Develop-assuring that the work is responsive to NRN needs.
ment and implementation of improvements will continue, directed towards reducing the number of amendments and other actions for Non-NRR Support - NRR will continue to provide technical Operating Reactors.
assistance as needed to State and Federal agencies and other NRC offices, particularly to NMSS in the areas of waste management As a result of the short-tern TMI tessons learned, a number of issues have and siting reviews for fuel cycle facilities and high and low been identified for resolution. In FY 1980, NRR will begin the implemen-level waste disposal sites, thereby increasing the effectiveness tation of the lessons learned through a series of studies such as control of resource utilization within NRC.
room design with regard to human factors engineering, review of regulatory requirements for plant systems, emergency preparedness, hydrogen behavior, Research Coordination - Twenty-four research requests were monitoring and control, and radiolngical consequence accident models.
transmitted to RES in FY 1978 and 26 have been transmitted in FY 1979. Research Information letters have been_.
20
/7
/G p
(Dollar in Thousands, except whole dollars in narrative material)
NUCLEAR REACTOR REGULATION - continued FY 1981 = $1,050 FY 1980 = 11.(315 (8)
Advanced Reactors......
FY 1979 = $982 5)
(9)
The Advanced Reactor effort involves the NRC's review and evaluation Monitor the operation of the Fort St. Vrain reactor (HTGR) and of of proposed and operating reactors which utilize novel or develop-the FFTF to assure protection of the health and safety of the public.
mental concepts (including DOE sponsored advanced reactor concept studies). Within this program, amendments / actions are processed Perform licensability studies in support of DOE alternate fuel cycle relating to Fort St. Vrain, an operating High Temperature Gas Reactor efforts (Nonproliferation Alternative System Assessment Program, (HTGR), and to review the safety analyses for and operating conditions (NASAP)).
of DOE-owned reactors such as.the liquid metal cooled Fast Flux fest Facility (FFTF). As needed, criteria that have been developed for The accomplishments in the Advanced Reactor area are:
light water reactors are modified or new design criteria are developed to provide guidance in these reviews.
Completed three years of monitoring the safety of operation of Fort St. Vrain and one year of FFIF operation.
The major objectives of the Advanced Reactor effort are:
Completed most of the NASAP Preliminary Safety and Environmental Provide licensing review capability for NRC for advanced reactors Information Document (PSEID) review and follow-on effort; in analyzing and evaluating characteristics and processes unique to these reactors.
Completed review of the modifications to the Brookhaven National Laboratory High flux Beam Reactor; Provide adequate support to other Federal agencies for advanced reattor technologies that will exchange the long-range goals of Completed review of some portions of the Gas Cooled Fast Reactor the nation's energy needs.
(GCFR) PSEID amendments and the HIGR preapplication.
FY 1979 = $0 FY 1980 = $0 FY 1981 = $0 Standards Assistance........
(11)
(11)
(13)
Regulatory Guides and standards describe and make publicly available members of industry code committees providing staff technical input to, methods acceptable to the NRC staff for implementing specific parts the development of industry codes and standards.
of the Commission's regulations and provide guidance for applicants concerning information needed by the staff in its review of applica-The major objective of the Standards program is to provide NRR support tions for CP's and OL's.
Internally, NRR participates in the pre-needed for standards development consistent with resources allocated to paration of NRC Regulatory Guides and standards. The NRR effort is assure that guides and standards that are developed can and will be mainly one of technical assistance to the Office of Standards Develop-utilized by NRR in the disc;iarge of its regulatory responsibilities.
ment to assure NRR's experience is factored into the standards This effort will enhance the stability and predictability of the development process. Externally, NRR staff members participate as licensing process through published Regulatory Guides, codes and standards.
FY 1979 = $0 FY 1980 = $0 FY 1981 = $0 Training and Correspondence.
(23)
(28)
(25)
Training - Resources are required to provide formal and informal included are the normal training requirements for the achinistrative and training to the NRR staff to assure the staff remains knowledgeable supervisory staff, in the technical fields associated with nuclear reactors. Also 21
r
(%
O (Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REACTOR REGULATION - continued Correspondence - Resources are required to respond to Freedom of Correspondence:
Information Act (FOIA) requests and to outside inquiries from the Administration, Congress, other Federal Agencies and the general Respond in a timely manner to FOIA requests and inquiries from the public.
Administration, Congress, and the general public.
The major objectives of these programs are:
The major accomplishments of these programs are:
Training:
Training - During FY 1979, NRR sent about 250 individuals to technical courses, and about 30 individuals to management, supervisory, admin-To assure employees are kept abreast of new technological develop-istrative, and clerical coursas, ments, new NRC and Governmental regulations, new office requirements and policies, and to be responsive to GA0 recommendations that the Additionally, 173 individuals took part in the reactor systems and staf f should receive more training so that their ef fectiveness is simulator courses conducted by the Office of Inspection and Enforcement.
maximized.
Courses of this nature provide the staff with "0N THE JOB" experience which enhances their capabilities as technical reviewers to increase Maintain a high degree of professional competence within the their abilities to perform better analyses, staff by authorizing personnel to attend formal and informal training. This is especially necessary for the technical staff Correspondence - In addition to the large volume of routine correspondence since many of the technical requirements and innovations in the processed during FY 1979, NRR responded to approximately 143 FO!A technical fields require periodic updating, requests requiring 581 professional, technical and clerical staff hours.
Management Direction..
FY 1979 = $0 FY 1980 = $0 FY 1981 = $0 (18)
(21)
(23)
The resources for this effort include the Director's Office and the Assure that operating reactors continue to operate in a safe and Program Support staff. The Director provides overall management and environmentally acceptable manner, guidance on major program objectives and goals. The Program Support staff provide technical assistance and support to the Director.in Assure that the Systematic Evaluation Program progresses satisfactorily.
svaluating proposed Office activities or positions and in the admini-stration of highly technical and diversified licensing projects. This Assure that appropriate safeguards requirements are implemented on function is responsible for: the planning, coordination, direction reactors.
(nd execution of the administrative affairs of the Office which includes rssource management, the budget formulation and execution; the develop-Assure that casework reviews are thorough and carried out in an ment, planning and implementation of programs to assess and improve expeditious manner.
the ef fectiveness and ef ficiency of the licensing process; the coordination of confirmatory research programs and the assessment of Assure that the generic issue program is given proper policy the effectiveness of such programs, and the development, planning and direction and resources, coordination and implementation of generic technical assessments of existing and prop
- sed Office safety and environmental criteria and Assure that research results are widely distributed within NRR and requirements.
utilized in the licensing proceu Czntinue to provide necessary support to the Director and Divisions Assure that appropriate planning, coordination, and direction of the and develop more effective ways to carry out the mission of the office affairs of the Director's Office are carried out by the staff in a to achieve the following objectives:
cost effective, expeditious and ef ficient manner.
22
p i-m k
(Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REGULATORY C00NISS10N - continued
$16,390 Standards Develoosent.
Summary of Standards Development Estimates by Function Actual Estimatg/
Estimate FY 1979 FY 1980-FY 1981 Personnel Compensation
$ 4,655
$ 5,723
$ 6,070 Personnel Benefits..............
410 544 583 Program Support.................
6,673 7,012 7,150 Administrative Support........
1,529 2,036 2,347 Travel..........
Equipment......
173 250 240 0
0 0
$1E4TO
$15 555
$ F TJD Total Obligations........
(134)1/
(160)
(161)
Personnel.
The Standards Development personnel and program support funding requirements (primarily contractual support with CGE laboratories and private contractors) have been allocated to major programmatic functions as shown below. -The narrative that follows provides justification in support of these requirements:
Actual FY 1979 Estimate FY 1980 Estimate FY 1981 Dollars People Dollars People Dollars People Power Facility Standards..............
$ 1,284 36
$ 1,365 45
$ 995 46 Fuel Facility and Materials Standards..
773 34 1,555 42 1,350 40 Operation and Utilization Standards........
2,130 37 1,785 42 2,805 46 Safeguards Standards.............
2,486 12 2,307 14 2,000 13 International Standards.....
0 4
0 5
0 4
Management Direction and Scpport..............
0 11 0
12 0
12 Totau......
55 573 1141/
5T012 150 5ET50 T5I F ncludes four full-time permanent positions actually filled by six part-time employees in an experimental part-time employment program with SD that 1
was authorized by OMB.
2/ ncludes $277,000 for FY1980 pay raise supplemental and $1,595,000 for FY1980 program supplemental.
-I 23 n
O O
O-(Dollars in Thousands, except whole dollars in narrative material)
STAhDARDS DEVELOPMENT - continued 1.
Introduction technical specialties is used where it would not be practical or ef ficient to recruit permanent NRC staf f for start ters, one-of-a-kind.
The primary function of the Office of Standards Development (50) is projects. (llalf of 50's budget is for staff, half is for technical the development of standards, i.e., technical regulations and regula-assistance.) Contractual program support is often used to analyze tory guides, that NRC needs to regulate nuclear facilities and commer-existing data to form a technical basis for the development or revi-cial uses of nuclear materials.
sion of a guide or regulation. It is also used to help prepare envi-ronmental impact statements for some rulemaking actions and, in some Standards improve the effectiveness and efficiency of regulation by cases, to provide input to the staff analyses for regulations and defining enforceable requirements and providing supplementary detailed guides.
guidance to achieve acceptable levels of safety, safeguards, and envi-ronmental protection; by addressing issues in a systematic way to Another function of the Offic( of Standards Development is to coordi-ensure uniformity of consideration and review; and by using acceptable nate NRC participation in both national and international standards consensus-development processes to assure a broad technical review of development activities. This involvement is prov, ding direct benefits engineering and reputatory practices proposed for standardization.
to NRC since about half of NRC's regulatory guides refer to or endorse Standards help NRC s efficiency by reducing uncertainties in the areas national (consensus) standards. NRC technical staff members from all addressed, stabilizing requirements, improving predictability of the offices p7rticipate in standards development committees to provide a regulatory process, shortening review times for licensing decisions-regulatory safety perspective to professional societies developing and providing bases for inspection.
national standards and to encourage the development of standards that will enhance safety and be useful in the regulatory process. NRC's The NRC's process for developing standards enhances openness and pub-decision on how or whether to use a national standard in the regula-lic confidence in the regulatory process by making the bases for regu-tory program involves independent review by the staff and pubile latory requirements available for public scrutiny and providing for comment on NRC's consideration of endorsing the national standard.
public participation in their development. Proposed NRC standards are issued initially for public comment. Comments received and staff NRC participation in international standards development activities experience are considered when revising and issuing a final standard.
is principally associated with management of U.S. technical activities associated with the Internatienal Atomic Energy Agency (IAEA) develop-The staff performs a value/ impact analysis of each new and revised ment of internationally acceptable regulatory standards for nuclear standard with respect to such questions as: What is the need for this power plant safety for use by developing nations. While the NRC man-standard? What alternative solutions exist for this particular safety, power required for this activity is small,-it is important because it safeguards, or environmental problem? What will be the impact of the enables us to assure that U.S. nuclear safety and other interests are standard on safety, safeguards, or environmental protection? What appropriately considered in these standards, will be the impact on NRC's workload, on other Government agencies, on industry, and on the public? This value/ impact analysis is proving The accident at the Three Mile Island power plant has required 50, to be a valuable tool in improving safety, the quality of NRC standards, along with the rest of NRC, to revise its ongoing program to take into in establishing priorities, and in eliminating unnecessary regulatory account health and safety needs that became apparent at that time and requirements.
during subsequent staff review of the event. This budget reflects only SD's initial response ta the THI accident and the short tern In addition to the work done directly by the NRC staff in developing recommendations of NRC's " Lessons learned" task force.
standards, program support in the form of contractual. expertise in FY 1979 = $1,284 FY 1980 = $1,365 FY 1%1 = $995 2.
Power Facility Standards..
(36)
(45)
(46)'
Power facility standards are prepared to assist applicants for, or The overall objective is to codify and m M ain the primary criteria holders of, nuclear power plant licenses, and license reviewers in and detailed engineering, siting and health standards. These standards ensuring protection of the health and safety of the public, including are the cornerstone of the regulation of f.uclear power facilities and workers, and of the environment. These standards establish the are the bases against which license applications are reviewed.
criteria for siting, design, construction, and decommissioning of nuclear power plants.
24
O O.
(Dollars in Thousands, except whole dollars in narrative material)
STANDARDS DEVELOPMENT - continued 2.
Power Facility Standards (continued)
NRC has already issued regulations that provide general design criteria,
. preparedness planning. Site safety standards in geology / seismology, quality assurance criteria,'and siting criteria for nuclear power facil-and meteorology are being developed to codify licensing experiences, ities..Now its principal activity is to develop more detailed standards and in hydrology.to maintain existing standards. SD also supported (principally by involvement with the national standards program and regional workshops with State and local government on proposed eser-development of regulatory guides) that describe and make available to gency planning rule changes and developed the bases for issuance of the public one or more methods acceptable to the staf f for implementing effective regulation amendments revising 10 CFR Part 50 emergency these broad criteria (regulations)
These detailed standards (guides)'
planning requirements, accelerate the licensing review and decision-making process by making clear to the applicant and to the public what the NRC staff expects During FY 1981, planned accomplishments include issuing new or updated of applicant / licensees with respect to site safety, environmental standards in many areas covered by our present regulations and regula.
protection, safety engineering, and quality assurance for nuclear tory guides including design and fabrication of fluid system components power facilities. In addition, the Office of Standards Development and supports; design and construction of structures and containments; (50) responds to petitions for rulemaking flied by the public on qualification for operab(11ty of electrical and mechanical equipment; matters relating to the siting and safety of nuclear plants.
design criteria for electrical systees; quality assurance (QA), including personnel selection, qualification and training, simulator design and Majnr accomplishments anticipated during FY 1980 in the power facil-use, handling of records, guidance on QA for specific aspects of ities area include a rule to require that nuclear power licensees nuclear power plant construction, and application of QA criteria to-maintain an updated Final Safety Analysis Report (FSAR), a rule to all structures, systems and components important to safety;-reporting specify fire protection requirements-for all ulear power plants, requirements for specific design and construction deficiencies; pro-a guide specifying instruments to follow tt-se of an accident tection from natural and man-made hazards'such as earthquakes, fires, and design criteria for such instruments, a Je on design require-and tornadoes; radweste processes; decontamination and decommissioning ments for residual heat removat systems; dratt guides on criteria of nuclear power plants; emergency core cooling systems (ECCS); and for operator qualification including requirements for operator educa-accident analysis, accident monitoring instrumentation, and shielding.
tion, experience, and training; and assessment of the need.to change Work will be completed on one Task Action Plan directed toward generic,
NRC's regulations and guides to assure consistent. treatment of fission solution of the problem of flaw detection, Petitions for rulemaking product release resulting from fuel clad failure.
will be dealt with as appropriate.
More than half of SD's effort in the Power Facility Standards area is Additional accomplishments in FY 1981 will be the issuance of proposed being applied to maintenance of existing standards to assure that they changes to the emergency protection rule (Part 50 Appendix E) and asso-are current. As part of the maintenance effort, steps are being taken ciated guides and reports; a major revision of reactor site criteria to refine and clarify existing standards, and to make changes that will (10 CFR Part 100), particularly relative to desegraphic requirements; reduce the regulatory burden on the pubile where this can be done without and pub 11 cation of NUREG reports in evaluation of reactor site selec-sacrifice to safety.
tion procedures, early site review, alternate site review, and meteorology.
Additional accomplishments expected in FY 1980 are the issuance of proposed rules. relative to alternate site reviews and emergency 3.
Fuel Facility and Materials Standards.....
FY 1979 = $ 773 FY 1980 =.$1,555 FY 1981 = $1.350 (34)
(42)
(40)
Fuel facility and materials standards are prepared to assist'appli-criteria are met to maintain the health and safety of the public and cants for fuel cycle facility licenses and for licenses to possess to protect the environment. Fuel facility standards establish the source material, special nuclear material, and byproduct material.
criteria for design, procurement, and construction of fuel cycle These standards also assist ifcense reviewers to assure the basic faclittles, including facilities for the storage c ' spent fuel and 25 L_
'_/
G) i a
t
%)
(Dollars in Thousands, except whole dollars in narrative material)
SfANDARDS DEVELOPMENT - continued 3.
Fuel Facility and Materials Standards (Continued) storage of wastes. Materials licensing standards establish reguia-Environmental Impact Statement (EIS) for the HLW technical regula-tions, guides, and procedures for: (a) packaging, transporting, and tions; development of a standard format and content for DOE's Site storage in transit of all types of licensed materials; and (b) safety Characterization Report; development of the standard review plan for and environmental control in the design, manufacture, and distribution the review of the Site Characterization ReporL; development of proposed of industrial, medical, and consumer products that contain radioactive regulations for the licensing of fow-level waste (LLW) disposal facil-material.
itles; development of the supporting [IS for these LLW regulations and the holding of public meetings to obtain public input concerning the Performance standards are still needed for some classes of industrial regulation of nuclear wastes, products and for uranium allis. Also needed are standards for waste management including facliities for away-from-reactor stcrage of spent In FY 1981, new or updated standards will be issued dealing with fuel and standards for decommissioning activities at all types of nuclear quality assurance, licensing guidance and packaging for transportation facilities. NRC transportation regulations need continued coordination of radioactive materials; li" nsing for manufacturing medical devices; with the U.S. Department of Transoortation and the International Atomic use of radioactive materials in consumer and industrial products; Energy Agency. In most of these areas, the primary standards in place decommissioning of fuel cycle facilities; design of independent spent are simply the basic rules for safety and environmental protection.
fuel storage installations; uranium solution mining; and uranium ox de 8
The detailed standards needed are those which would cover matters such fuel fabrication. Several petitions for rulemaking will be dealt with; as controlling radioactive releases, nuclear material criticality con-the priority assigned to each will be consistent with the importance trols, design of facilities for decommissioning, quality assurance, of the issue. We also plan to develop needed changes to international and training of personnel. For high-level waste management, EPA is transportation standards and t) study the shipping environmerb asso-promulgating generally applicable environmental radiation protection ciated with various transportation modes.
standards being developed for the licensing of geologic repositories.
Other planned accomplishments for FY 1981 include the issuance of In FY 1980, new or updated standards are anticipated to include an effective rules, supporting guides, and technical positions for the updated environmental impact statement on transportation of radioactive IIcensing of high-level waste repositories and low-level waste burial material to and from nuclear reactors, a final rule and environmental facilities, continued effort on the implementation of the Clean Air impact statemant implementing present IAEA transportation standards Act; the issuance of a rule change specifying the environmental impact in our regulations; guidance on licensing for manuf acturing medicM of the fuel cycle for National Environmental Policy Act (NEPA) review; products and on qualification of paramedical personnel administering publication of reports on fuel cycle site suitability and on st.sndard-or using radioisotopes; and reports on decommissioning of uranium fuel ized environmental impact of the fuel cycle for NEPA review; and on fabrication plants and of facilities used for manufacturing products standardized environmental dose assessment.
containing radioactive materials.
Additional accomplishments include:
the publication of ef fective pro-cedural regulations and proposed technical regulations for the licensing of high-level waste (HLW) repositories; the development of the supporting 4.
Operation and Utilization Standards.
FY 1979 = $2,130 FY 1980 = $1,785 FY 1981 = $2,805 (37)
(42)
(46)
Operation and utilization standards are prepared to provide licensing ultimate disposal by industry and the pubile of industrial, medical, conditions and regulatory guidar.ce on health, safety, and environmental and consumer produ,:ts that contain radluactive material.
protection for operation of nuclear power plants and fuel cycle facil-ities and for utilization of nuclear materials by NRC licensees and The overall objective is to codify and ma!ntain the primary and detailed the public. Operation standards establish criteria for startup, opera-standards against which the operation and decommissioning of reactors, tion, testing, maintenance, repairs, modification, and decommissioning
- P' tycle facilities, and waste management facilities, the transporta-operations for nuclear reactors and fuel cycle facilities. Utilization tion production, and use of licensed ma brials and products containing standards establish criteria for the transportation, utilization and
0 O
O (Dollars in Thousands, except whole dollars in narrative material)
STANDARDS DEVEL0 MENT - continued 4.
Operation and Utilization Standards (Continued) licensed materials are reviewed and inspected to assure continued pro-it also includes coordination with EPA and ether Federal agenc'es on tection of the health and safety of the public, including workers, implementation of the Clean Air Act and the Toxic substances Control and environmental protection.
act.
Accomplishments during FY 1980 in this area are anticipated to include:
The development and rnintenance of ALARA guidance for occupational (1) for nucivar power plants, revised rules on pressure vessel material exposures and other w)rker and environmental radiation protection fracture toughness to reflect changes in the American Society of standards for licensed nuclear facilities and activities will continue Mechanical Engineers (ASME) Boiler and Pressure Vesse! Code; revision in FY 1981. The maintenance of effluent and environmental monitoring of the rule on containment leakage testing to reflect actual experience standards will also continue. Guidance to license applicants and with containment airlock leakage testing; several guides on initial licensees is ptanned in the areas of: radiation protectica training, startup and periodic testing programs, quality assurance for operations, radiation personnel qualifications, techniques to minimize occupational and worker training in radiation protection; (2) a draf t generic envi-exposure at medical institutions, bicassays, radiation protection ronmental impact statement and policy statement on decommissi aing surveys, instrument calibration, dosimeters with audible alaces, nreA+c-operating reactors and fuel cycle facilities; (3) for transportation, tion against neutron radiation, occupational radiation risks, and (ne an environmental impact statement on transportation of radioactive use of respirator 5 uder both routine and emergency conostions. The materials in urban areas; (4) for radioactive products, guidance on review of the data base on biological effects of low-level radiation j
medical applications, industrial uses, and laboratory testing and exposure, including reexamination and evaluation of epidemiology studies I'
instrumentation measurements; (5) a policy statement concernira the performed by others, will continue.
protection of individuals who supply information to NRC; and (6) a review of NRC enforcement policy on licensee violations of safety in In FY 1981, other planned accomplishments include (1) for nuclear power l
nuclear power plant operations due to human or procedural er or, plants, development of new and updated standards dealing with inservice Criteria was also developed for the design of nuclear powtc plant inspection end preoperational and initial startup testing and periodic simulators for use in operator training.
test programs; (2) a proposed rule on decommissioning operating reac-tors and fuel cycle facilities; (3) for transportation, guidance on In addition during 1980, an epidemiology feasibility / planning study on emergency response to transportation accidents, and guidance on State low-level radiation effects will be completed and recommendations made and local initiatives in regulating the transportation of radioactive to the Congress to assist in the planning for epidemiologic studies materials; (4) for material utilization, guidance on radioactive of low-level radiation effects. The findings of these efforts will products; guidance on medical applications; and standards for indus-j be used to support the scientific basis for NRC health related regu-trial uses. Effort on regulations for protection of individuals latory activities. New regulations to further protect the radiation supplying information to NRC will be confined to review of comments safety of patients will be issued to implement NRC's medical policy and related maintenance, statement. New regulations are under development in the areas of occu-pational dose limits, survey instrument calibration, and performance SD also plans to continue tN* development and maintenance of standards testing of personnel dosimetry processors, bloassay laboratories, and related to medical licensing, and radiological health (with emphasis on survey instruments. SD responded to requests from the Office of Nuclear low-level radiation ef fects), and issuance of guidance on decommissioning Reactor Regulation (NRR) and the Office of Inspection and Enforcement of uranium mills.
(IE) for assistance with occupational retpiratory protection activities as recovery operations at Three Mile Island proceed.
In the radiation protection area, efforts in FY 1980 'nclude cooperat-ing with EPA on basic radiation policy guidance and participating in a joint hearing on standards to limit radiation exposures to workers.
27
p R
R k
U FY 1979 = $2,486 FY 1980 = $2.307 IY 1981 - $2,000 5.
Safeguards Standards.
(12)
(14)
(13)
The Safeguards Standards program is directed toward developing a body safeguards standards. In addition, there is substantial participation of regulations for licensee safeguards systems and supplementing these in national standards writing efforts to encourage the development of regulations with guides and technical reports to assist in their imple-consensus standards for safeguards. A number of standards have been mentation.
Issued in this area and several are in progress with an anticipated FY 1980 pubilcation date.
Accomplishments in FY 1980 are anticipated to include the issuance of generic standards for: strengthened physical protection requirements Planned Safeguards Standards development accomplishments in FY 1981 for fuel cycle facilities; strengthened material control and accounting are to provide generic standards for: definition of protection and requirements; rules for personnel access controls at nuclear power response requirements for alternative fuel cycle facilities; security plants; rules for reporting of safeguards events; issuance of a general system designs and operational procedures to implement the strengthened license for carriers of irradiated reactor fuel; transportation require-physical protection requirements published in FY 1930; issuance of an ments for Category Il and Ill special nuclear material; an access effective rule for upgraded material control and accounting systems; authorization program for fuel cycle f acilities; implementation of the publication of the guidance documents needed to support the material US/IAEA Safeguards Agreement; a rieasurement quality assurance program; control and accounting upgrade rule; continued work with national and maintenance of consistent, comprehensible and technically current standards writing organizations; and maintenance of consistent, com-prehensible and technically current safeguards standards.
FY 1979 = $0 FY 1980 = $0 FY 1981 = $0 6.
International Standards.
(4)
(5)
(4)
The SD activities with the International Atomic Energy Agency (IAEA) expert groups to develop safety standards for transport of radioactive provide U.S. input and solicit pubile comment on the IAEA development materials.
of internationally acceptable standards on reactor safety for use by developing nations embarking on a nuclear power program. These stand-A senior SD staff member participated, with State Department support, ards are intended to draw on the reactor safety and regulatory expe-in preparation of updated United Nations Scientific Committee on the rience of industrial nations such as the United States, the Federal Effects of Atomic Radiation reports o6, the assessment of world-wide Republic of Germany, France, Japan, Great Britain, Canada, and the and regional radiological impacts and the risks from radiation and Soviet Union. 50 is the focal point for U.S. participation in this radioactive materials.
program. Maximum use is made of public and industry participation in order to minimize NRC resource needs. NRC manpower for this activity NRC staff members have participated on expert groups to: (1) assess is small from a budget standpoint, but it does include a significant the radiological impact of effluents from the nuclear fuel cycle; (2) involvement by key NRC staff.
develop a general standard related to consumer products; (3) develop a standard for radioluminous time pieces; and (4) develop a standard In addition, NRC staf f members have participated in Advisory Groups for ionization type smoke detectors.
to the IAEA that prepared guidance for IAEA member states on (1) monitor-ing airborne and liquid effluents from nuclear facilities and (2) the The resources requested for FY 1981 are needed to continue to ensure principles and procedures for establishing Ilmits for releases of that safety considerations and other U.S. interests are adequately con-radioactive materials into the environment, and has worked with IAEA sidered in the IAEA development of internationally acceptable nuclear power plant safety standards for use by developing countries that are embarking on a nuclear power program.
7.
Management Direction and Support..
FY 1979 = $0 FY 1980 = $0 FY 1981 = $0 (11)
(12)
(12)
This activity provides the central management and coordination of the overall Office of Standards Development. It also provides the central administrative support necessary to manage SD activities which includes' support in preparation of the budget, contracts control, financial reports, 28 personnel matters, facility and logistics administration, mail control.
Freedom of Information Act requests, and other administrative matters.
A A
~
,)
Y (Dollars in thousands, except whole dollars in narrative material)
NUCLEAR REGULATORY CODNISSION (Continued)
..........$53,889 Inspection and Enforcement...
Summary of Inspection and Enforcement ist. mates by function Actual Estimate 1/
Estimate FY 1979 FY 1980 ~~
FY 1981 Personnel Compensation......
$20,731
$24,681
$?9,640 Personeel Benefits.............
1,828 2,336 2.844 3,876 5,660 6.691 Program Support..
Administrative Support....
4 346 7,627 6,214 3,s93 3,455 4,520 Travel......
379 1.237 3,980 Equipment..............
$34,353 544.996
$53,889 Total Obligations.......
( 727)y (874)2/
(947}2/
Personnel....
The Inspection and Enforcement personnel requirements and program support funding requirements (primarily contractual support with DOE laboratories and private contractors) have been allocated to major program elenients as shown below. The narrative that follows provides justification to support these requirements.
.'.ctual FY 1979 Estimate FY 1980 Estimate Ff 1981 Dollars People Dollars gd Dollars People Reactor Construction Program...
$ 146 149
$ 540 153
$ 605 183-Reactor Operations Program.......
-415 1%
615 327 600 327 0
26 180 29 0
32 Vendor and Contractor Program..........
Fuel Facilities and Materials Safety Program...........
1,387 152 1,590 153 2,165 184 925 90 1,000 90 1,166 93 Safeguards Program...............
Specialized Technical Training Program.
346 17 790 25 1,268 25 657 97 945 97 887 103 Management Direction and Support.............
E 376 727 p
8 74 m
W Total..
1/ Includes 51,193,000 for the FY 1980 pay raise supplemental and $2.720,000 FY 1980 program supplemental.
ff Includes two personnel in FY 1981 converted to full-time permanent with corresponding comparability adjustment in FY 1979 and FY 1980.
29
O O
O (Dollars in Thousands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMENT (Continued)
The mission of the Office of Inspection and Enforcement is to insure the public and/or the environment. To insure uniformity of inspection, this through field inspection, lowestigation, and enforcement that facilities program is documented by written guidance, which provides a consistent and materials under NRC jurisdiction are constructed, operated and used path for assurance of Ilcensee performance and problem identification in a manner which protects the public and the environment. The functions and generally involves three basic types of inspection activity:
of the Office are: to inspect, investigate, enforce, evaluate and inform.
Revlwing the licensee's basic systems and procedures to be certain The inspection, investigation, enforcement, evaluation and information they conform with requirements, are technically sound and are pro-activities are primarily concerned with: (1) reactor facilities - nuclear perly implemented.
power plants (under construction, testing or in commercial operation), test reactors, and research reactors; (2) fuel facilities and nuclear materials Analyzing the licensee's records of operation and interviewing licensees; and (3) vendors - nuclear steam system suppliers, nuclear licensee personnel to confirm that actions called for by the pre-architect / engineers and other major nuclear system components suppliers.
scribed systems and procedures are routinely followed.
Activities performed by the Office include: (a) inspecting licensees and Directly verifying licensee and system performance by means o' their contractors to ascertain compliance with Commission regulations, direct observation and independent measurement, rules, orders and license provisions; (b) inspecting license appilcants as a basis for recommending issuance or denial of an authorization, permit, The reactive component is the response or " reaction" to some influence or license; (c) inspecting suppliers of safety-related services, compo-outside the above described program. The reactive component often nents, and equipment to determine if these suppliers have established consists of an in-depth investigation in response to an event or allega-systems to assure the quality of their services and products; (d) investi-tion which may arise from routine. inspections, required licensee contrat. tor gating incidents, accidents, allegations, and other unusual circumstances or vendor reports, or allegations made by licensee employees, members of to ascertain the facts and to take or recommend appropriate action; (e) the puolic, and/or public interest groups. The objective of the NRC's enforring Commission regulations, rules, orders, and license provisions; reactive program is to establish the facts, determine the significance of (f) evaluating the results of inspections, investigations, inquiries and the particular condition, and take appropriate corrective action.
reports to determine the effectiveness of the Commission's programs and, where necessary, recommending corrective regulatory action; (g) evaluating Enforcement information con
- rning incidents and accidents to assure adequacy of the The enforcement program is aimed at achieving public safety by (a) assur-overall response and to provide continued response by appropriate NRC ing operation within requirements, (b) correcting areas of noncompliance staff; and (h) informing the Commission, other NRC offices, other govern-or poor practice and (c) deterring further noncompliance. The enforce-ment agencies, licensees, and the public through notices or reports of ment program includes a clearly delineated and evenly applied series of occurrences.
deterrents that escalate according to the nature of the offense and the past history of licensee performance. Sanctions available to the NRC Inspection and Investfoation include Notices of Violation, Civil Monetary Penalties, Orders to Cease The NRC inspection program includes two components: routine (scheduled) and Desist, and Orders to Suspend, Modify, or Revoke Licenses. Enforce-inspection and reactive (unscheduled) inspection / investigation. Both ment actions are taken to insure compilance with NRC rules, regulations, are based on the premise that during the conduct of regulated activities orders, and license provisions.
the licensee is responsible for complying with NRC requirements for safe-guarding nuclear facilities and materials and protecting both the
.To strengthen the enforcement process, the NRC has requested environment and the health and safety of the pubilc..The NRC inspection increased civil penalty authority from Congress and approval is expected.
program is designed to provide assurance that the licensee is properly This request proposes substantial civil penalties of up to $100,000 for discharging these responsibilities.
each safety violation (including Ilcensee's failure to submit regtaired reports of safety related information) with no upper limit on combined The routire component is a carefully constructed program of inspection violations. Furthermore, the NRC is revising its enforcement policy and performed on a continuing basis to evaluate the licen,ee's activities criteria including identification of the types of safety violations that within the context of his ultimate respontibility for public protection.
require escalated enforcement.
The thrust of this effort is to critically examine, by systematic selec-tion, licensee controls designed to prevent conditions that might threaten 3C
g3 A
)
O (Dc11ars in Thousands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMENT (Continued)
Revised _!nspection Program The Revised Program also increases the degree of emphasis placed on in FY 1978, the Comission initiated a modified approach for inspecting direct verification of licensee activities, prineily at reactor sites nuclear reactors and major fuel plants designed to improve the effective-This is achieveM expanding both direct observation and independent ness of the IE inspection program. This Revised Inspection Program has measurement activities. Direct observation consists of an NRC three coriponents: the Resident inspector Program, increased direct inspector observing either wort-in-progress, licensee measurenents, or verification, and the Performance Appraisal Team.
that work has been properly completed. Independent measurements are technical measurements, equipment calibrations, and environmental The original Pestdent Inspector Program plan called fcr one resi-sample analyses performed either by !E inspectors. contractors. 00E dent inspector at each power reactor operating site, one resident laboratories or state personnel, at selected late stage ennstruction sites and one resident at each of two major fuel facilities. The plan was to achieve thi; coverage Increased direct observation will be achieved through the assignrent by phasing in resident assignments over a four year period ending of additional resident inspectors. While region-based inspectors will in FY 1981. It was decided to expand the program after the Three continue to provide a minimal amount of direct observation, resident Mlle Island accident and Congress apprcpriated an additional 146 inspectors will spend a great deal of their time observing licensee positions (98 inspectors and 48 support) and about $4.5 million for activities. In fact, the additional residents assigned in FY 1980 will FY 1980. With these additional resources, more resident inspectors spend virtually all their time directly observing plant olerations will now be assigned to reactor sites having one or more units in and checking safety equipment operability.
pre-operation, startup, or operation. Reactor sites with either one or two of these units will have two resident inspectors, whereas Independent measurements will also be expanded at both operating all sites having three or more units will have residents equal to reactor and construction sites. At operating sites independent number of units at these sites. In all cases, each site will measurements will be conducted by:
continue to have a senior resident inspector with the balance of the residents being less experienced personnel whose primary using NRC environmental monitoring vans, facus will be direct observation of plant operations and safety equipment operability. In addition to expanding the program, IE obtaining contractor laboratory analyses of environmental is also accelerating the assignment of resident inspectors and
- samples, expects to have all operating sites fully staffed with residents by the end of FY 1980.
and expanding the use of state contracts for the analysis of environmental samples, as well as in the deployment and for reactor construction sites, the original plan called for the retrieval of radiation measuring devices at these sites.
assignment of fifteen (15) resident inspectors at construction sites by the end of FY 1980 and twenty (20) by the end of FY 198!. That At construction sites, independent measurements will be expanded in plan has now been accelerated so that IE will have twenty (20) the area of both destructive and non-destructive testing of contractor residents assigned to construction sites by the end of FY 1980.
work products. Non-destructive examinations will be performed by hRC Furthennore, it has been expanded to include the assignment of inspectors, normally at the site, whereas destructive examinations four (4) additional residents at problem construction sites to will be performed in contractor laboratories.
bring the FY 1980 total of construction resident inspectors assigned to twenty-four (24).
It is believed that by increasing the amount of direct verification at reactor sites a direct positive effect on how the if censee In the safeguards area, the current plan calls for keeping one conducts his activities will result and tFus improve the safety of resident at each of two major fuel facilities.
reactor facilities.
Throughout the implementation period of the expanded / accelerated A more detailed discussion of initiatives being undertaken to expand program. IE will maintain a balanced program that will increase the direct observation and independent measurements is outlined below in number of resident inspectors and concurrently maintain the region each of the related program areas.
based inspection effort. A sufficient number of region based inspectors must and will be maintained to provide necessary Finally the Revised Inspection Program indudes a centrallred level of specialized technical support.
Performance Appraisal Team that will evaluate licensees from a 31
J O
O O
(Dollars in Thousands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMENT (Continued) national perspective, evaluate the effectiveness of the IE inspec-In evalwting the performance of licensees, IE will seek to identify tion program, and confirm inspector objectivity. During FY 1981 those qualities that determine better performance thus enabling IE this Team will be expanding its activities to include program to better allocate its inspection work force and to make available appraisal inspections at fuel facilities, materials licensees and to industry the qualities that lead to better performance.
vendors and management appraisal inspections of licensees having reactors in construction, startup, or pre operational testing.
Specific program descriptions are provided below for eacn of the seven program elements.
Reactor Construction Program.
..FY 1979 = $146 FY 1980 = $540 FY 1981 = $605 (149)
(153)
(181)
NRC rules and regulations require licensees to construct nuclear. reactors Reactor construction inspections are performed by both region-based and in such a manner that when they become operational they will pose no resident inspectors. Construction residents assume a small portion of threat to the public and the environment. The resources reflected in the inspection activity previously conducted by region based inspectors this Program are required to: (a) adequa'ely inspect, enforce, and and provide a substantial increase in direct verification of Ticensee evaluate the construction of nuclear power plants thereby assuring the performance through direct observation and independent measurements. The public that licensees are fulfulling this aspect of their responsibil-region based support ronsists of in-depth, specialized technical inspections, ities; and (b) carry out the functions of a national Performance Appraisal Team focusing on licensee performance, inspection program The Performance Appraisal Team provides the capability to assess regula-effectiveness, and inspector objectivity.
tory performance of nuclear power plant licensees on a national basis.
It also provides the NRC with a capability to obtain additional assurance The reactor construction inspection program consists of conducting both of inspection program consistency and inspector objectivity, routine inspections (scheduled) and reactive (unscheduled) inspections /
investigations. The routine component consists of a series of preplanned The reactor construction enforcement program consists of a clearly audit type inspections designed to assure that licensees have the required delineated series of deterrents that escalate according to the severity controls in place to prevent adverse situations from occurring. It is of the noncompliance (s) found and the Nst histnry of licensee perfom-comprised of multidisciplinary inspections conducted on a schedule con-ance. Enforcement actions are taken both to correct situations and to sistent with the licensee's construction activities plus inspections of assure future compliance with NRC regulations and license provisions.
reactors that have progressed beyond the construction phase. For these reactors, the inspections are conducted during baseline and in-service The reactor construction evaluation program consists of reviews of examinations as well as during periods of major modification. The Ilcensee performance, inspection and enforcement experience, and data reactive component consists of both inspections and investigations relating to the licensee's compliance with NRC rules and regulations, to conducted in response to events and conditions that generally emanate improve both licensee performance and regulatory effectiveness.
from either licensee reported events, allegations of licensee noncom-pliance, or generic problems.
Activities include developing and administering inspection programs and policies, conducting inspections; investigating incidents, accidents, Nuclear reactors inspected are those in the stage prior to receiving a allegations and unusual circumstances; enforcing NRC orders, rules, construction permit but authorized to proceed with construction work regulations and license provisions; recommending changes in licenses and under a limited work authorization (LWA), those in early construction standards; evaluating licensee performance nationally; and notifying (first two years), mid-construction (third and fourth years), late licensees of generic problems. This Program includes all field ruourtes construction (fif th and sixth years), and those in pre-operational test-applied to construction and Performance Appraisal ir.spections/
a ing as well as those with operating licenses.
investigations -- inspectors, branch and section chiefs, direct clerical support personnel and technical equipment funds. It also includes head-quarters personnel in the Reactor Construction Inspection Division and Program Support funds dedicated to this program.
32
O O
O (Dollars in Thousands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMENT (Continued)
The workload of nuclear reactor units inspected is displayed below:
FY 1979 FY 1980 FY 1981 Construction residen's assigned by E0Y -
10 24 7F Workload Volume In addition to region based and resident inspections, licensee problems /
Phase FY 19795/
FY 19802/
FY 1981 /
corrective actions and performance will be routinely evaluated. Other 2
Pre-construction Permit Units 7F
- 5. W
~TW activities such as improved field feedback to Headquarters, licensee Early Stage Units 19 25.50 21.00 performance evaluation from a natloaal perspective, and evaluation of Mid Stage Units 30 28.00 20.50 inspection program implementation will be accomplished. Program Support Late Stage Units 21 22.75 25.50 and technical equipment funds will be used to conduct additional Pre-operation Test Units 12 15.50 15.75 independent measurements such as: ultrasonic testing of welds and joints; Units with Operating 1.icenses 75 86.75 100.00 radiography analysis; testing of environmentally sensitive equipment; chemical, metallurgical and physical tests of concrete, steel, and safety 1/ Workload for FY.1979 reflects plant status as of the end of the fiscal related piping; composition, strength, and fracture toughness of materials year.
used in construction; sensitization tests of stainless steel material 2Norkload for these fiscal years is determined on a quarterly basis to samples to determine if they are susceptible to intergranular attacks; incorporate any phase changes that are projected within each year.
and weld metal tests for typical lots and heats of welding materials.
For example, a teactor unit projected to be in the pre operation test The increases in this funding area are primarily due to increases in.the phase in the first quarter is counted as.25 units against that phase scope of ongoing projects. An additional thirty (30) positions are with the remaining.75 counted against reactor units with an OL.
This requested for FY 1981. Twenty (20) will be used to adequately conduct method of workload identification makes manpower planning more precise.
the resident inspection program and support the increase in reactive inspection / investigation effort required since the Three Mile Island A critical element of IE's Revised Inspection Program is and will con-accident. Ten (10) positions will be used to expand the Performance tinue to be to increase direct observation and independent measurement Appraisal Team (PAT) to include program appraisal inspections at fuel of construction work as it is being performed at the site. A major facilities, material licensees, and vendors and einagement appraisal portion of this increased effort will be achieved through the assignment inspections of licensees having reactors in construction, startup, of resident inspectors. FY 1979 resident assignments and the plan for or pre-operational testing.
FY 1980 and FY 1981 are as follows:
FY 1979 = $415 FY 1980 = $615 FY 1981 = 1600 Reactor Operations Program..
(196)
(327)
(327)
HRC rules and regulations require licensees to operate their facilities Reactor operational safety inspections are being performed by both region and use nuclear material in a safe manner. The resources reflected in based and resident inspectors. Resident inspectors not only assume a this Program are required to adequately inspect, enforce, and evaluate portion of the inspection activity previously conducted by region-based the operational safety of nuclear reactors thereby assuring the public inspectors, but also provide increased verification of licensee per-that licensees are fulfilling this aspect of their responsibilities.
formance through direct observation. The region based support consists The reactor operations inspection program consists of conducting both routine (scheduled) and reactive (unscheduled) inspections / investigations.
The operational inspections performed at power reactors are " phase" The routine component consists of a series of pre planned, audit type oriented. During the pre-operational and startup testing phases, inspec-inspections designed to assure that licensees have the required controls tion emphasis is placed on test management, procedures and results.
in place to prevent adverse situations from occurring. The reactive Licensee tests are witnessed, test results are independently evaluated component consists of both inspections and investigations conducted in and licensee evaluations of test results are reviewed. During the com-response to events and conditions that generally emanate from either mercial power operation phase,' the inspection program focuses on:
licensee reported events, allegations of Ilcensee noncompliance, or reviewt of basic systems and procedures that licensees follow to be generic problems.
Nuclear reactors inspected are: power reactors ir, pre-operational test-ing, startup testing, and commercial power operation and non power reactors.
33
%./
Q (Dollars in 'housands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMtNT (Continued) certain that they conform with requirements and are technically sound incorporate any phase changes that are projected within each year. For and properly implemented; analyses of records of licensee operations and example, a reactor unit projected to be in the pre-operation test phase-interviews of licensee personnel to confirm that prescribed procedures in the first quarter is counted as.25 units agalest that phase with the are routinely followed; periodic verifications of licensee and system remaining.75 counted against reactor units with an OL.
This method of performance by means of direct NRC observations; and examinations of workload identification makes manpower planning more precise.
licensee review and audit committee actions, changes to the quality assurance program and personnel / organization changes.
A critical element of IE's Revised Inspection Pmgram is and will continue to be to increase direct observation of Ilcensee plant operations at each Efforts to improve both licensee performance and regulatory effectiveness nuclear reactor unit. The majority of this increased effort will be through the reactor operations enforcement program consist of a clearly accomplished through the assignment of additional resident inspectors delineated series of deterrents that escalate according to the severity who.;ill provide added inspection coverage in seven main areas:
of the noncompliance (s) found and the past history of licensee performance.
Enforcement actions are taken botn to correct situations and to encourage (1) Engineered Safety Feature Observation and Independent Assessment future compliance with NRC regulations and license provisions.
(2) Surveillance Test Observation (3) technical Specification and Operating Parameter Check The reactor operations evaluation program consists of reviews of licensee (4) Maintenance Overview performance, licersee event reports, inspection and enforcement experience, (5) Jumper and Bypass Control and data relating to the licensee's compliance with NRC rules and regula-(6) Operating Procedure Adherence tions to improve both Ilcensee performance and regulatory effectiveness.
(7) Startup and Pre-operational Testing Activities include developing and administering inspection programs and By conducting these types of inspection activities, it is believed that policies; conducting inspections; investigating incidents, accidents.
the assurance of safety equipment operability will be significantly allegations and unusual circumstances; enforcing NRC orders, rules, improved.
regulations and license provisions; recommending changes in licenses and standards; evaluating licensee performance nationally; and notifying FY 1979 resident assignments and the plan for FY 1980 and FY 1981 are as licensees of generic problems. This Program includes all field resources follows:
applied to reactor operational safety inspections / investigations --
inspectors, branch and section chiefs, direct clerical support personnel FY 1979 FY 1980 FY 1981 and technical equipment funds. It also includes headquarters personnel Operations residents assigned by E0Y -
28 7C 7C in the Reactor Operations Inspection Division and Program Support funds dedicated to this program.
In addition to the region based and resident inspections described above, Program Support funding in FY 1980 is being directed toward a determina-The workload of nuclear reactor units inspected is displayed below:
tion of the direct verification roles of the resident inspector and a revision of the reactor operations inspecticn program with more emphasis Phase FY 19791/
FY 1980 FY 1981 /
on direct observation. Tnese projects will be completed in FY 1980 and 2/
2 Pre-operation Test Units 7F
~I5 50-T5~7F the results incorporated into the inspection modules in FY 1981. Also, Startup Units 4
6.25 9.25 in FY 1981, an evaluation of accident response procedures for nuclear-Operating Units 71 80.50 90.75 power plant operation will be completed and a checklist for identifica-Non power reactor Units 86 84.00 84.00 tion of accident response procedural deficiencies for use by IE inspectors will be issued.
1/ Workload for FY 1979 reflects plant status as of the end of the fiscal year.
2/ Workload for these fiscal years is determined on a quarterly basis to
..FY 1979 = $0 FY 1980 = $180 FY 1981 = $0 Vendors & Contractors.....
(26)
(29)
(32)
NRC rules and regulations require licensees to construct nuclear power
.this Program are required to adequately inspect certain licensee vendors plants in such a manner that when they become operational they will pose and rontractors to assure that they maintain adequate controls to produce no threat to the public and the environment. The resources reflected in nuclear products and services of suf ficient quality to assure public health and safety.
34
r r
n (Dollars in ihnusands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMENT (Continued)
This aspect of NRC's inspection program is known as the Licensee Contrac-Activities include developing and administering inspection programs and tor and Vendor Inspection Program (LCVIP). This program was established policies; conducting inspections; investigating incidents, accidents, 14 FY 1974 because a significant number of problems at licensee facili-allegations and unusual circumstances; enforcing NRC orders, rules, ties were traced to faulty work by contractors and vendors utilized by the regulations and license provisions; recommending changes in licenses and licensee in facility design, construction and testing. Inspectors review standards; evaluating licensee performance nationally; and notifying documented procedures, interview personnel, and examine both desions and licensees of generic problems. This Program includes all field resources hardware to determine if adequate quality control procedures have been directly applied to the inspection of Ilcensee contractor and vendor prepared and are being followed. Licensees remain responsible for product activities that are not conducted at the construction site -- inspectors, acceptance.
branch and section chiefs and direct clerical support personnel. It also includes a small portion of the Reactor Construction Inspection Division The LCVIP consists of conducting both routine inspections (scheduled) and responsible for policy and program development, implementation and evalu-reactive (unscheduled) inspections / investigations. The routine ;omponent ation of the LCVIP.
consists of a series of preplanned audit type inspections to assure that Ilcensees have the required controls in place to assure quality products The workload of NRC licensee vendors and contractors inspected is and services. The reactive component consists of both inspections and displayed below:
investigations conducted in response to events and conditions that generally emanate either from licensee raported events, allegations of FY 1979 FY 1980 FY 1981 licensee noncompliance, or generic problems. NRC presently conoucts a Nuclear Steam Suppliers and minimal program of inspection of vendors. architect engineers and nuclear Architect Engineers 15 15 15 steam system suppliers. Approximately 25u inspections are conducted Fuel Suppliers 5
5 5
annually by NRC inspectors. Emphasis is placed on allocating inspection Component Suppliers 135 150 175 resources in response to feedback on licensee problems wth added emphasis placed on the inspections of architect engineers and nuclear The NRC relles heavily on the LCVIP program to attest to the quality of steam system suppliers.
safety related components manufactured offsite. Approximately 50% of the safety related equipment problems that are reported can be attributed In FY 1977, NRC initiated a two year trial program with the American to vendor activities. Utility licensees have not proven effective in Society of Mechanical Engineers (ASME) to test the use of third party dealing with many generic problems primarily because they do not have inspection systems as a means of supplementing the LCVIP. Adoption of the broad perspective needed to recognize and deal with these issues.
the third party inspection systems would expand and strengthen NRC inspec-Recent events indicate that many component failures are oriented toward tion of mechanical component manufacturers with only limited additional early design and not fabrication. Consequently, three additional NRC resources. The ASME trial program was not concluded in FY 1979 as positions are needed in FY 1981 to increase the scope and depth of the initially anticipated but will be continued until program acceptance is inspection program at Architect Engineers and Nuclear Steam System deemed appropriate. Anticipating ultimate success, this program will be Suppliers and to conduct inspections focusing on increased technical established on a routine basis and serve as a model for exploring the reviews during the design and specification development stage.
possible use of other third party inspection systems.
......FY 1979 = $1,307 FY 1980 = $1,590 FY 1981 = $2,165 Fuel Facilities & Naterials Safety Program....
(152)
(153)
(184)
NRC rules and regulations require licensees to operate their facilities inspections which examine licensee's radiation / environmental protection, and use nuclear materials in a safe manner. The programs and resources environmental monitoring, and radwaste processing and control progrank reflected in this Program are required to adequately inspect, enforce.
The routine component consists of a series of pre planned audit type and evaluate the use of nuclear materials at fuel cycle facilities, inspections designed to assure that licensees have the required controls.
materials licensees, and nuclear reactors, thereby assuring the public in place to prevent adverse situations from occurring. The reactive that licensees are fulfilling this aspect of their responsibilities.
component consists of both inspections and investigations conducted in response to events and conditions that generally emanate either from The Fuel Facilities and Materials Safety inspection program consists of licensee-reported events, noncompliance findings, allegations of conducting two types of inspections; (1) safety inspections at fuel licensee noncompliance, unsafe operations, and generic problems.
facilities and materials licensees and (2) reactor health physics 35
~
O lO O
(Dollars in Thousands, except whole dollars in narrative material)
INSPECTION AND ENFORCEMENT (Continued)
Fuel facilities inspected are: uranium mills; uranium hexafluoride allegations and unusual circumstances; enforcing NRC orders, rules, facilities; fuel processing and fabrication (uranium and plutonium) regulations and license provisions; recommending changes in licenses and facilities; spent fuel reprocessing facilities; short-term fuel storage standards; evaluating licensee perfermance nationally; and notifying facilities; and facilities for storage and disposal of high level radio-licensees of generic problems. This Ptogram includes all field resources active wastes. The inspection program for fuel facilities presently applied to fuel facilities and materials safety inspections / investigations requires, in frequency of inspection, four inspections per year of
-- inspectors, branch and section chief s, direct cluical support personnel, reprocessing, plutonium processing and fuel fabrication plants; three and technical equipment funds. It also includes headquarters personnel inspections per year of uranium processing and fuel fabrication plants; in the Fuel Facilities and Materials Safety Inspection Division and Program and one inspection each year of uranium hexafluoride conversion plants, Support funds dedicated to this program.
uranium allis, reactor fuel storage sites, R&D facilities, and decommis-stoned facilities.
The workload of fuel facilities, materials licensees and reactors inspected is displayed below:
j Materials licensees are those authorized by the NRC to possess and use byproduct, source and special nuclear materials in radiography, medical, Facilities FY 1979 FY 1980 FY 1981 tcademic, and industrial applications as well as to operate low-level Fuel Reprocessing 3
2 2
nuclear waste disposal facilities. Inspection frequency and depth for Plutonium Processing 6
6 6
these licensees are based on risk potential The highest risk category, Uranium Processing 18 17 17 priority 1 (about 25 licensees), is inspected twice per year; priority 2 UF-6 Processing 2
2 2
(about 350. licensees) is. inspected once per year; priority 3 (abnut 200 Uranium Mills 18 35 47 4
j licensees), is inspected every two years; priority 4 (about 3500 licens-R&D Facilities 5
7 7
ces), every three years; priority 5 (about 100 licensees), every five Fuel Storage Facilities 2
2 2
years; priority 6 (about 1200 licensees), esery 10 years. The remaining Decommissioned Facilities 1
2 2
licensees (about 3500) in the lowest frequency grouping priority 7 are not routinely inspected but 5% are inspected on a sample basis each year.
Materials Licensees.
Nuclear reactors inspected are power reactors in pre operational testing, Manufacturing &
startup testing, and in commercial power operation, as well as non power
-Distribution 23 23 24 test and research reactors. Annual reactor health physics inspections Medical 3,002-2,998 3,081 are conducted to assure that licensees have adequate radiation protection.
Academic 808 808
. 831
]
emergency planning, radioactive waste management, and environmental Indust fal 1,811' 1,821 1,872 4
monitoring programs. All power reactor facilities receive the same level Radiography 367 367 377
{
of routine inspection. whereas the effort for non power and research Waste Disposal 11 11
. - 11 reactors varies by type, based on risk potential.
Other 2,847 2.922-3,004 The enforcement program consists of.a clearly defined, evenly applied ReactorsY'E j
series of deterrents that escalate according to the severity of inspec-i tion findings and the past history of licensee performance. Enforcement Pre-op Test Units 12 15.50 15.75 actions are taken both to correct situations that require immediate Startup Units 4
6,25 9.25 i
j action and to assure future compliance with NRC requirements. The Operating Units 71 80.50 90.75 ability of the NRC to take these actions to enforce its rules and regu-Non-Power Units 86 84.00 84.00 lations.is an incentive for licensees to perform in a safe manner.
u The evaluation program consists of reviews of licensee performance,
-1/ Workload for FY 1979 reflects plant status as of the end of the fiscal year.
Inspection and enforcement experience, and data relating to the licens-2/ Workload for FY 1980 and FY 1981 is determined on a quarterly basis to
- ee's compliance with NRC rules and regulations, to improve both licensee
~ incorporate any phase changes that are projected within each year. For performance and regulatory effectiveness.
example, a reactor unit projected to be in the pre-operation test phase in the first quarter is counted as.25 units against that phase with the i.
Activities include developing and administering inspection programs and remaining.75 counted against reactor units with an OL. This method of policies; conducting inspections; investigating incidents, accidents, workload identification makes manpower planning more precise.
36 i
4
/M R
Y J
Continue the support of aerial radiological surveys of reactor and An additional thirty-one (31) positions are needed in FY 1981.
Eight (8) positions will be used to support caseload growth and six fuel facility sites.
(6) for anticipated increases in work from Three Mile Island Lessons Increase the support of State contracts and the on and offsite Learned and increased reactive inspections / investigations. Six (6) more positions will be useu to conduct a mail / telephone program with low radiation measurement program.
Inspection priority materials licensees to increase the frequency of NRC Continue the support of the Measurement Assurance Program.
contact with these low risk licensees. Six (6) additional positions will be used to inspect all new materials licensees within six months of Continue to maintain and calibrate region based environmental monitor-license issuance. Five (5) more positions will be used to expand IE Headquarters expertise in emergency planning, radiation protection, ing vans, radwaste processing, and environmental protection.
Increase the use of contractor laboratories to support expanded Program Support funds will be used in the following areas:
independent measurements of licensee activities.
Technical equipment funds will be used to maintain and upgrade region based equipment.
.....FY 1979 = $925 FY 1980 = $1,000 FY 1981 = $1,166 Safeguards Program...
(90)
(90)
(93)
NRC rules and regulations require licensees to control and account for licensees who transport special nuclear material both within and outside certain types of special nuclear materials; to protect nuclear materials, the Uatted States and licensees who transport irradiated reactor fuel, reactor facilities and fuel facilities against theft, sabotage, or unauthorized entry; and to ensure that special nuclear material and The enforcement program consists of a clearly defined, evenly applied irradiated fuel are transported safely. The resources reflected in this series of deterrents that escalate according to the severity of inspec-Program are required to adequately inspect, enforce, and evaluate the tion findings and the past history of licensee performance. Enforcement safeguarding of nuclear facilities and materials thereby assuring the actions are taken both to correct situations that require immediate action public that licensees are fulfilling this aspect of their responsibilities.
and to assure future compliance with NRC requirements. The ability of the NRC to take these actions to enforce its rules and regulations is an The Safeguards inspection program consists of conducting two types of incentive for licensees to perform in a manner both safe and consistent inspections: (1) material accountability inspections designed to assure 4th public interest, thereby assuring public safety.
that the licensees are adequately controlling and accounting for special nuclear material; and (2) physical security inspections designed to assure The evaluation program consists of reviews of licensee performance, that licensees are adequately protecting facilities and shipments and inspection and enforcement experience, and data relating to the their contents against theft, diversion and sabotage. Both types of licensee's compliance with NRC rules and regulations to improve both inspections can be routine (scheduled) or reactive (unscheduled). The licensae performance and regulatory effectiveness.
routine component consists of a series of pre planned audit type inspec-tions designed to assure that licensees have the required controls in Activities include developing and administering inspection programs and place to permit adverse situations from occuring. The reactive component policies; conducting inspections; investigating incidents, accidents, consists of both inspections and investigations conducted in response to allegations and unusual circumstances, enforcing NRC orders, rules regula-events and conditions that generally emanate either f rom licensee-reported tions and license provisions; recommending changes in licenses and events, noncompliance findings, allegations of licensee noncompliance or standards; evaluating Ilcensee safeguards performance nationally; and unsafe operations and generic prcblems.
notifying licensees of generic problems. This Program includes all fleid resources applied to safeguards inspections / investigations - inspectors, Facilities inspected include: power reactors in the pre-operational test branch and section chiefs, direct clerical support personnel, and technical phase, power reactors with operating licenses, non power reactors (test equipment funds. It also includes headquarters personnel in the Safeguards and research), spent fuel storage facilities, certain materials licensees, Inspectior. Division and program support funds dedicated to this program.
37
u v
v (Dollars in Thousands, except whole dollars in narrative material)
INSPECil0N AND ENFORCEMENT (Continued)
The workload of the Safeguards Inspection program is displayed below.
2Norkload for these fiscal years is determined on a quarterly basis to incorporate any phase changes that are projected within each year.
27 y
FY 1979y TY 1980 FY 1981-For example, a reactor unit projected to be in the pre-operation test Pre-Operational Test Reactors 12 13 50
" W75 phase in the first quarter is counted as.25 units against the phase Reactors with 0perating Licenses 75 86.75 100.00 with the remaining.75 counted against reactor units with aa OL.
This Non power Reactors 71 70 70 method of workioad identification makes manpower planning more precise.
High Enriched Uranium fuel Facilities 14 14 14 Program Support funding will be principly directed toward independent Low Enriched Uranium measurement of licensee special nuclear material measurements by the New Fuel facilities 5
5 5
Brunswick Laboratory. Additional Program Support funding is needed to Materials and Spent continue the effort begun in FY 1980 to upgrade inspection strategies fuel Storage Facilities 14 17 17 and methodology.
Shipments 70 240 241 fechnical equipment funds will be used to provide spare and replacement
-INorkload for FY 1979 reflects plant status as of the end of the fiscal parts for the regional laboratories and for new portable equipment.
year.
Three (3) additional positions are requested in FY 1981 for the prepara-tion of an inspection program and appropriate facility attachments associ-ated with the joint US/XAEA agreement.
....FY 1979 = $346 FY 1980 = $790 ff 1981 = $1,268 Specialized Technical Training Program............
(17)
(25)
(25)
Newly hired and existing inspector personnel, as well as other NRC per-skills training in the classroom by NRC instructors; technology and codes sonnel, must be sufficiently knowledgeable of the facilities, processes, courses developed and taught by contractors specifically for NRC personnel, and activities within their technical purview. Most personnel, hired to technical training by NRC instructors at Tennessee Valley Authority simu-be future inspectors, do not possess all the technical and regulatory lator facilities which enable NRC personnel to obtain " hands on" experience; qualifications required to properly perform their duties and existing programmed self-study training and "off-the-shelf" type courses related personnel must be kept abreast of current industry state-of-the-art.
to various aspects of the develogment and implementation of'the NRC Therefore, training must be provided to assure that necessary levels of ins;,ection and enforcement program.
knowledge are developed and maintained. This Program contains the resources required to administer and conduct specialized training - e.g.,
Program Support funding is for the development and conduct of selected instructor and support personnel plus program support funds for developing specialized technical courses. The FY 1981 increase of $478,000 is used tnd conducting courses under contract.
to provide technology and code courses for new NRC resident inspectors recruited in FY 1980 against the expanded program. No additional Specialized technical training provides IE personnel with performance positions are needed in FY 1981.
..FY 1979 = $E57 FY 1980 = $945-FY 1981 = $887 Management Direction & support.
(97)
(97)
(103)
The resources reflected in this Program provide support to IE's other studies, management studies, incident response capability analy is, and functions. Management direction and support is provided in NRC head-effectiveness measurement studies.
quarters by the Of fice of the Director, the Executive Of ficer for Management and Analysis, and the Executive Of ficer for Operations Support.
The regional administrative support personnel included in this Program are In the regions, management direction and support is provided by the for secretarial support for regional office management personnel, clerical offices of the Regional Directors and the regional administrative staffs-support for personnel assigned to regional of fices from other NRC of fices, Program Support funds included in this Program are for information system receptionists in each region, and management information coordination.
38
m.
O O
O (Dollars in Thousands, except whole dollars in narrative material)
INSPECTION AND ENFORCfMENT (Continued)
The Administrative Support funds for regional of fices are for: rent Plan, budget, evaluate and control resource uti;iration-and utilities; telephone and non-telephone communications; purchase lease, and maintenance of office equipment; general office equipment; general Administer contracts office supplies and materials; space alterations; and health services.
Operate an office-wide manigement information system The Director of I&E is responsible for overall program management.
The two headquarters Executive Of ficers provide necessary technical and Operate the NRC Operations Center for incident response administrative services. They:
Conduct studies on alternative policies and programs Develop policy for and assist in investigations, incident iesponse, event reporting and enforcement actions.
.The Offices of the Regional Directors are responsible for executing the inspection and enforcement programs and for managing assigned rescurces.
Provide technical liaison with NRC's Office of Research and with The Regional Directors also serve as the NRC's senior official in their other agencies (e.g., EPA, DOT) respective geographical areas.
Respond to Freedom of Information Act (FOIA) requests in FY-1981, six (6) additional positions are needed to staff the NRC Operations Center on a permanent, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day, 7 day / week basis. Program Maintain and distribute the IE Inspection Manual Support funding is primarily directed toward the conduct of studies of alternative policies and programs and toward the support of onooing -
Provide centralized headquarters administrative support (e.g., file management information systems. Technical equipment funds ($3,000,000) are room, mail distribution, word processing) needed to implement the results of a FY 1980 System Engineering /
Architecture Study on modifications needed to improve the NRC Operations Center response capability during emergencies.
39
O O
C (Dollars in Thousands, except whole dollars in narrative material)
AUCLEAR REGULAT0dY CG441SS10N - continued J
~
Nuclear itaterial Safety and Safegua:..................................................................................... 543,680 Summary of Nuclear Material Safety and Safeguards Estimates by Function Actual Estimate Estimate FY 1979 FY 1980 If FY 1981 Personnel Compensation.......................................................... $ 8,282
$10,006
$11,430 Personnel Benefits............
730 944 1,097 P ro g r am S u p po r t............................................................
15,787 14,865 21,745 4,081 5.482 8,778 Admini s tra tive Support.................
Travel..........................
352 494 630 Equipmenc...............
0 0
0 4
TOTAL OdLIGAT1045
$29,232
$31,791
$43,680 Personne1..........................................................................
(263)
(313)
(335)
The duclear Material Safety and Safeguards personnel requirements and program support funding requireraents (primarily contractual support with DOE laboratories and private contractors), have been allocated to major programmatic functions as shown below. The narrative that follows provides 4
justification in support of these requirements.
Actual FY 1979 Estimate FY 1930 Estimate FY 19J1 i
Dollars People 5611ars Peggie 6611ars People Fu e l Cyc l e a nd Ha te r i a l Sa fe ty....................................................
$ 2.890 90
'$ 2,199 1 06
$ 4,250 -
108 Saftguards.......................................................................
3,080 90 1,800 98 2,51 0 96 Was te slanagenen t...............................................................
9,817 67
_10,706 90 '
14,885
'112 Ha nagewn c u t rec t ion a nd Su ppor t................................................
0 16
'160 19 100 19 Tota 1........................................................................
$15,787 263
$14,P65 313
$21,745 335 i
If includes $479,000 for the FY 1980 pay raise supplemental and $2,610,000 FY 1980 program supplemental.
i i
4 40.
1 4
,a O
p (Dollars in Thousands, except whole dollars in narrative material) dVCLEAR MATERIAL SAFETY AND SAFEGUARDS - continued The Energy Reorganization Act of 1974 as amended, established the Office of developing contingency plans for dealing with threats, thef ts, and Huclear Hacerial Safety and Safeguards (NMSS). The Act charges the Director sabotage; and recommending research.
of NASS to perform two principal functions: a) license and regulate all facilities and materials associated with the processing, transport and To carry out these responsibilities and other statutory requirements, handling of nuclear materials, including provisions for maintenance of TNSS has established and manages three major programs: Fuel Cycle and safeguards against threats, thef ts, and sabotage; and b) review safety and Material Safety, Safeguards, and Waste Management. These programs are safeguards of all such facilities and materials, including: monitoring, managed and supported by the Management Direction and Support Program, testing and upgrading internal accounting systems for nuclear materials; Each major program consists of program elements.
SurrrLary_of Fuel Cycle and Material Safety Program Actual FY 1979 Estimate FY 1930 Estimate FY 19d1 Program Elements ETlars People ETUirs Peopy ETlars Peopl_e
~
$ 2,164 39
$ 1,754 45
$ 3,595 44 Fuel Cycle Licensing.........
509 12 195 15 305 18 Transporta tion Certification.............
217 39 250 46 350 46 Radioisotopes Licensing......
To tal
$ 2,890 90
$ 2,199 106 5 4,250 lod FY 1979 = $2.164 FY 1%0 = $1,754 FY 1931 = $3,595 Fuel Cycle Licensing.......................
(39)
(45)
(44)
Ine goals are to license fuel cycle plants and improve the ef fectiveness support and improve the efficiency and effectiveness of the licensing and efficiency uf the licensing process. This includes: performing process; and 7) deveirp radiological contingency plans for coping with safety and enviromental reviews en new, existing, and formerly licensed accidents and incidents at licensed fuel cycle plants, and coordinate these facilities and former AEC contractor sites to ensure the health and plans within NRC with other affected Federal, State, and local agencies, safety of toe public; revising guidance used in fuel cycle facility and with licensees.
licensing actions and implementing requirements resulting from new rules and stand.irds;.formlating and coordinating standards and confirmatory The significant accompitshments for FY 1979 were to: 1) complete 24 major P researcn reqoirennts for resolving fuel cycle problems; and developing and 95 minor fuel cycle licensing actions within established review times, radiolod cal conting acy plans for coping with accidents and incidents.
progress will be made toward resolution of long-tem casework projects to be conpleted beynnd FY 1980, and complete two of the natural phenomena reviews Tne major objectives are to: s)) perform safety ard environmental evalua-for Advanced fuel Processing Plants, initiated in FY 1977; 2) contribute to cions required for licensing dechions for fuel cycle plants and facilities; the NRC Report to Congress on Alternative fuel Cycles and provide limited
- 2) perform studies in support of rulemaking proceedings and other required reviews of broad nuclear fuel cycle environmental studies and statements; fumission activities, to resolve generic and specific fuel cycle problems;
- 3) complete ttw review cf docket flies of former licensees who possessed J) survey former licensee sitet, unlicensed burial grounds and burial source or special nuclear materials, and begin the review of docket files grounds at selected licensed plants that may nave potentially undesirable of former byproduct licensees; 4) tegin the review of proposed ^ remedial nealtn, safety, or enyironmental impacts, and evaluate proposed remediei actions for one former AEC site (Cannonsburg, PA); 5) complete Division aci.lons wJ related epvironmental assessments; 4) review DOE proposed participti,n on revised rule loplementing must of EPA's environmenta L reatedhi action 3 for fomer AEC industrial contractor sites and evaluate radiation protection $tandaids for nuclear pour 5peradons; 6) fornlate,,, g nd coordinate requirements for con,firmatory researd and standards in' suppurt of fuel cycle licegsing, revied v61ue-impact analyses and respono,( -
tns propused plans; 3) develop, with other NRC organizations, regulations fur new environwatal, radioactivity limits and personnel, exposure require-ments, and impitkent the new limits and requirements brougn' the lkensing to hifomation requests; and 7) inhiete the developnent of radiologicci' contingency plans.
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The significa[it anompliWents planned during Ff 1981 are to: 1)
- /,
c M ete 23 major,an.1 95 minor licensing actions f P uranium fuel cycle complete 24 major, and 95 mirar licensing actions for uraniwa fuel cycle plants and faci 14tl s; 2) complote the Uranium Fuel Cycle Survev U.d.5,-3 p <
, plants and facilit'les and complete the remainder of the natural, phenomena A
a-reviews for Adv&ced Fuel Processing Plants, initiated.in FY M77; 2)
Table update ht?10 CFR.?1 to be used in.readtor licens!*gy and ZontiGu 4 A
pelish a radon rule and a draf t updata of the Environmental Survey of the reviews of br4ad ev%ar) fuel cy:le p;tudies and statments; 3) complete' the Uranium Fuel Cycle, continue to contrf oute to the NRC Report to Congiess i: review of fonner tiprodot licen;ees 4) ' survey former licensee sites and d
- Wernative Fuel Cycles, and contitue limited reviews ofproa? nuclear
- burial grounds v.d cvaluate propem! remedial a$tions; 5) review bf-five DOE x
1 ifuel cycle envirornnental, studies; 3) c'ontinue the refit-w of falser prryosed remedial actions; 6)xtQinp nd.e environmmtal radioactivity lialts 4
A t>yproduct licensees and begin radiological surveys of sites wnic'n may and rersonnel oposure requirements and impicment ttira through the ifcensing i
I contain radioactive contanination;1 ) begin the rev}ew of pr-
- actions pmcess; 7) continue to fonnulate ard coordinate stindards and regulatory 4
foradditionalsitEsidentifiedin'Cne00ERemekialAdion researcy requiraments for fuel cycit licensing, assess research results and u
s) parcicipate in an NE Task Force to develop implementing tions
.%1ement fhemlnto the licedng process r begin review of Parts C, ara 'O ot\\td CFR, reviN value-impact analyse @nd respond to information r& quests; fu tne Clean Air Act;'fr) continue to formulate and coordinat.
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ments for confirmatory research and standards, review valu:-ir.
- t and 8) cortinue the' development of radioiJgicii contingency plans.
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m ar31yses, and respond to infonnation requests; and 7) continue the
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development of radichgical contingency plaqsy
.Theincreaseinfrogramsupportismainlytosupportsafetystudiesofthh s
NFS high-leve) waste systems at West Valley, New YorP 7
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FY 1979 * $509 FY_1980 = $195 FY 1931 = $305 (12. )
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Tho goal is to p9fform safety reviews for package designs and operations
_.Thesignificaniaccomplishmentsplanned4orFY1980areto: 1) completel for shipnent of-radioactive mathiafs in quantitles exceeding certain 50 Safety reviews; 2) continue 1to maintain and. improve heat transfer, limiM, as specifiedsin 10 CFR Part 71; to review package licensing
,, shielding, and criticality codes; 3),contir.ue'the devel nt of radio; proceriures and the standards which packages muf t met; to develop,.
logical contingency plans.
maintain, and improve package analysis mthods te usure quality and-i f timely reviews; and to develap radiologicalisid.!ngency' plans.
The significant accomplishnents planned for FY 1981 are to: 1) complete
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56 reviews of the estimated 84 cases awaiting action, and reduce the s
Ine major objectives are to:- fl)~corduct(safety ' reviews of ma)or package caseload backlog;.2) maintale criticality, shielding, and heat transfer (e.g., spent fusi cask, plutonium par.kage, high-lovel waste, etc.) designs,
programs and data base on a continuing basis; provide technical input within one year and of other designs within four months, reduce the and develop policy decisions for the Office of Nuclear Regulatory f oreiast backlog of app'lications, and maintain a registry of package users; Research to conduct the Modal Study; evaluate the results of the Modal
- 2) prpvide technical: expertise on a continuing basis for structural, thermal, Study; and develop appropriate action plans for possible rulemaking; and criticality.,and shielding analysis for Itcensing requests; review licensee
- 3) continue the development of radiological contingency plans, quality assurance programs; maintain and improve standardized analysis methods on a continuing basis; and evaluate the safety effectiveness of The increase in manpower is for increased work on package certification regulations, procedures and methods of analysis with regard tu severe and for support of the Modal Study. The increase in funding is for the accidents in the various transportation modes; and 3) develop radiological ongoing program to develop and raa entain standardized methods of analysis.
contingency plans for coping with transportation accidents and incidents.
The significant accomplishments for FY 1979 were to: 1) complete 64 safety reviews; 2) maintain and improve heat transfer, shielding, and criticality codes; and 3) initiate the developnent of radiological contingency plans.
42
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NUCLEAR MATERIAL WUY add WEGMD5 - coNttn.ed
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FY 1!09 = $217 FY 1930 = $250 FY 19d1 = $ n0 Rad io i so topes IJcensi rg.........................
(3Q (46)
(46)
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The goal is to assure protection of public health and safety by prevent-
.The significant accomplishnents picued dudng FY 1930 ar ~ to: 1) process ing excessive raJiation exposure through a cystem of licensing for the 5,600 licensing appitcations, s edere the turnarceid ttne to 30 to 45 days, possession, use, transfer, and disposal of radioactive ~ mterial (typroduct; and evaluate 200 sealed sources %-d devices; 2) continue to provide assistance and training to Agrement States; 3)' continue revied 'attr!
source, and special nuclear material).
s revision of current licensing guides and develop the most urgently needed
.The major objectives are to: 1) perform safety evaluations required for new gulde n 4) complete studies to reexamine the apnitcation of ALARA for materials licensing so that licensing decisions wil,1 be completed on all occupational exposures and effluent releases at radiophrmaceutical manu-cous within an average time of 30 to 45 days, and. evaluate 200 sealed facturers and to improve mett'ods for evaluating and Itcensing sealed sources and devices per year on a continuing basts; 2) pro <ije technical sources and devices, and continin the study to declop NRC policy on assistance and training as requested by Agreement States; 3) review and consumer products containtreg radioactive material; 5) con.tuct approvi-urdat?' existing radioisotope licensing guides, regulations, and standards mately 70 post-licensir.g evaluatinns; 6) comr ete evaluation of the pilot on a c:atinuing basis and develop new oner relative to current safety needs; regionalization program; 7) initiata an infonnatten program for Itcensees
- 4) conduct generic studies to improva. the licensing process; 5) condJCt -
concerning licensing requirenents and the licensing process; and 8) Continue pu n-licensing evaluations on a continuing basis (approximately 70 per year) the development of radiological contingency plans, to confirm tne validity of licensing actions; 6) co~%ct the existing Itcensing regionalization program in NRC Region Iliz, /) complete and the significant accomplistnents planned for FY 1931 are to: 1) review all maintain a licensing information program to supplement the license appli-new, renewal, avi amenenent applications and issue licerises within 39 to 45 cation guides with instructional materials, quarterly bulle. ins, and days, and evaluate 200 sealed sources and devices; 2) continue to provioe regional seminars; 3) develop and maintain standard license review plans; assistance and training to Agreement States; 3) develop new licensing and 9) develor radiological contingency plans for coping with accideats guides; 4) inittate a study of general licer.ses and the development of and incidents at major materials licensees.
techniques for radioisotopes acccuntabi'itty, and complete the study to develop.JRC policy for exempt consur=r products; 5) conduct approximately The significant accumplissments for FY 1979 were to: 1) procass 5,150 70 post-licensing evaluations; 6) cos. duct the licensing regionalization licensing appilcations witn an average turnaround time of 35-50 days for program in NRC Region I'l; 7) complete development of a licensing infoma-Itcense amendments and new applications, and 120 days for a license renewal, tion program; 8) develop standard Itcense review plans; and 9) continue and evaluate 100 sealed sources and devices; 2) continue to furnish technical the development of radiological contingency plans.
assistance to Agreement States; 3) develop and publish three new licensing goldes and seven amendments to regulations; 4) initiate studies to The increase in fundfng is to initiate and maintain a licensing information reexamine how operations at radiopharinaceutical facilities can be carried program to supplement the Itcense appilcation guides and to initiate a study out to maintain occupational exposures and effluent releases et as low at to evaluate and certify sealed sources and devices.
reasonably acnievable (ALARA) level, improve the evaluation of sealed sources and devices, and develop NRC policy on consumer products 5) conduct approximately 47 post-ilcensing evaluations to confirm the validity of licensing actions; 6) continue the evaluation of the pilot Ilcensing regionalization pragram; and 7) initiate the development of radiological contingency plans.
43
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V (Dollars in Thousands, except whole dollars in narrative material) t~JCLEAR MATERIAL SAFETY AND SAFEGUARDS - continued Summary of Safeguards Program Actual FY 1979 Estimate FY 1980 Estimate FY 1991 PROGRAM ELEMENTS D3Tiars people M11ars teople Do11ars People Material Control and k counting.
1,133 44 1.035 38 135 44 Physical Security.......
1,947 46 765 60 1,775 M
Total....
3,080 90 1,800 98 2,510 96 Material Control and Accounting.............
FY 1979 =$1,133 FY 1980 = 51,035 FY 1961 =$735 (44)
( 38)
(44)
The goal is to assure the protection of the public health and safety and safeguards information system; 4) provide user planning and management of promote the common defense and security throuch the development, imple-the MC&A research program. Generate approximately 4 new HC&A regulatory mentation, and maintenance of effective MC&A programs at licensed fuel research requirements. Develop methodoingy to assist field assessors, cycle facilities and support international safeguards and nonproliferation Perform 1 user suitability test. Direct 25 agencywide MC&A research and objectives through participation with other U.S. agencies in programs to technical assistance project reviews. Publish the integrated safeguards strengthen international safeguards.
program plan. Review approximately 48 NASAP and 180 INFCE documents for SG adequacy; and 5) complete a m*jor generic regulatory issue paper on MC&A fhe major objectives are to: 1) perform timely licensing casework upgrade for SSPN and complete material cantrol guidance in the Part 73 Upgrade reviews. This includes the review and approval of licensee MC&A plan Rule Guidance Compendium.
submittals, revisions to existing plans and the institution of remedial licensing actions based on the results of inspection and evaluation activi-The significant accomplishments planned for FY 1980 are to: 1) review ties; 2) perform MC&A reviews of export / import license applications, 8 major and 80 minor MC&A plan changes; conduct 15 reviews of licensee timely implementation and maintenance of the provisions of the US/XAEA procedures for calculating measurement uncertaintles; 2) review 200 export /
Sifeguards Agreement and development and implementation of programs to import applications. Implement the US/IAEA Safeguards Agreement. Provide strengthen IAEA safeguards, support international safeguards and contribute expert safeguards consultatfor. to IAEA and foreign countries in support n
i to the achievement of U.S. nonproliferation objectives; 3) perform reviews, of U.S. nonproliferation goals; 3) evaluate MC&A programs at 3 fuel Edequacy assessments, and analysis of accoenting data for existing MC&A cycle facilities. Improve inventory difference simulation models. Develoo a programs at licensed facilities to form the basis of remedial licensing method synthesizing MC&A assessment data. Carry out the system design work actions and the refinement of regulatory requirements which improve the for an integrated safeguards information system; 4) generate approximately licensing process; 4) formulate HMSS safeguards research requirements, plan 4 new MCAA regulatory research requirements. Perform 3 facility application and manage research projects, insure user-utility of results, direct analyses. Direct 25 agencywide HC&A research and technical assistance contract activities, maintain NRC integrated safeguards program plan, and project reviews; update the integrated safeguards program plan. Provide perform interagency planning in order to anticipate MC&A requirements, and Biannual Safeguards NRC, NASAP report to the President; 5) complete a minor
- 5) develop improved regulations, value impact stateirents, and associated generic regulatory issue paper on MC&A requirements aor low-enriched uranium.
puidance documents.
Complete two minor regulatory issue papers. Complete a proposed MCM upgrade rule with a draft value/ impact analysis and implementation guidance documents.
The significant accomplishments for FY 1979 were to: 1) complete the review of 15 measurement control plans: 6 other major MC&A plan changes, The significant accompIlshments planned for FY 1981 are to: 1) review 75 minor plan revisions and major licensing actions were completed at approximately 10 major amendment cases, 80 minor amendmett cases, an<t 20 3 facilities; 2) review approximately 200 export / import arplications.
remedial licensing amendments and correction of generic and site-specific Provided calysis which prompted a Commission decision requiring substantive deficiencies; 2) extend the implementation of the US/XAfA Safeguards Agree-MC&A export licensing reviews. Flan and initiate implemantation of US/XAEA ment to assist in preparation of facility attachments in all eligible reactor Sifeguards Agreement. Contribute to the development of U.S. action plan and nonreactor licensed facilities ami to implement requirements in 10 CFR for strengthening international safeguards. Initiate analysis of IAEA Part 75 through licensing cases for ebout 90 facilities and modification for technical objectives and provide consultation to IAEA and foreign countries about 15 facilities. Assess, evaluate and formulate policy alternatives in support of nonproliferation goals; 3) evaluate MC&A programs at 11 for 220 MC&A reviews for esport/ import licensing cases. 3) conduct MC&A facilities. Develop procedures for tracking foregin origin material and assessments at two facilities. Analyze MC&A inventory dif ference and other facility' reporting of IAEA data. Formulate the development of an integrated accounting data at three facilities. Improve HMSS information system for
m n
m (Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR MATERIAL SAFETY AND SAFEGUARDS - continued domestic and international safeguards; 4) formulate approximately 6 NMSS and licensees; and 5) cceplete MCAA upgrade rule with value impact analyses.
MC&A research requirements and plan and maeage an HCAA research program of Complete four minor generic issue papers on MC&A. Complete two minor MC&A approximately $1.1 H.
Conduct 25 project reviews of NRC Safeguards Research regulatory amendments with value impact analysis and implementation guidance.
and Technical Assistance Programs. Meet changing safeguards needs caused by changing technology. Ensure dissemination of MC&A technology for NRC The increase of six positions in ff 1981 is to catend the IAEA agreement to additional facilities.
rhysical Security.
FY 1979 =$1,947 FY 1980 r$165 FY 1981 =$1.775 (46)
(60)
(52)
The goal is to assure the protection of the public health and safety axi management of the physical security research program involving approxi-promote the national security through the development, implementation mately $1.3 M.
Perform 6 user suitability tests. Direct agencywide and maintenance of ef fective physical security programs at power and non-activities for approximately 25 physical security research and technical power reactors, licensed fuel facilities and during the shipments of SNM.
assistance projects. Publish the integrated safeguards program plare; and Support nonproliferation objectives and physical protection of nuclear
- 6) complete the upgrade rule for SSNM, the tule for protecting Category material by other countries through participation with other U.S. agencies II/Ill materials, major guidance documents for each rule, 6 minor generic in programs to S W ngthen interaational safeguards.
regulatory issue papers, and testimony concerning spent fuel shipments.
The major objectives are to: 1) develop and monitor programs to protect licensed SNM from loss or diversion and reactors from radiological sabotage.
The significant accomplishments planned for FY 1980 are to: 1) review and Parform licensing reviews that include approval of physical security plans, approve: 32 transportation and fuel cycle facility plans, 46 remedial contingency plans, guard training plans and remedial licensing actions; amendments, 2 cor.tingency plan review, transportation security arrangements
- 2) conduct physical protection reviews of export Ilcense applications and for 76 domestic and export shipments of Category I and II material. Review in-country evaluations of foreign physical protection programs to assure the 35 spent fuel plans to include monitoring of 300 shipnents. Complete for adequacy of the protection of exported m,aterial and facilities; 3) interface reactor facilities: six 10 CFI' 73.55 reviews for power reactor;, complete with licensees, transportation agents, and local law enforcement agencies 50 remedial licensing actions, 20 vital area analyses, complete review of and negotiate supporting interagency agreements in order to provide a threat 35 contingency olans and 18 quard training plans, and complete reviews of assessment basis for NRC safeguards and incident response activities for 16 nonpower reactor security plans; 2) review and approve 195 export appli-response against threats and attempted thef t or sabotage; 4) perfom ade-cations and conduct four in-country foreign evaluations; 3) complete an quacy assessments of existing safeguards at Ilcensed f aciMties md
- tans-insider threat study. Continue contingency planning related to transport portation activities; 5) formulate, plan and manage safeguards research of nuclear materials; 4) complete vulnerability assessments of actual SSNM requirements to provide agencywide coordination of al' contractual physical shipments. Conduct unscheduled safeguards evaluations at three nuclear security projects and determine the need for new policy initiatives; coordi-facilities; 5) perform 7 facility appilcation analyses. Direct agencywide nite with other government agencies for physical protection technology Safeguards Technical Assistance and Research (STAR) activities for approxi-changes; and 6) review generic regulatory issue > and develop new and revised mately 25 physical security research and technical assistance projects.
regulations with associated guidance documents and corresponding valve impact Update the integrated safeguards program plan; and 6) complete a rule for statements.
protecting Transient Shipments and related value/ impact analyses and guidance documents. Complete a major regulatory issue paper on Spent Iuel Shipments.
The significant accomplishments for FY 1979 were to: 1) review and approve:
Complete 12 minor generic issue papers and 5 minor regulatory amendments.
17 transportation and fuel cycle facility plans, 47 minor amendments, I licensability reviews of DOE facilities; 39 contingency and guard training plans, review transportation security arrangeoents for 20 Category I export The significant accomplishments planned for FY 1981 are to: 1) complete shipments; 2) review and approve 181 export applications, ronduct three 46 rajor Itcense amendments,105 minor license amer"iments, and 35 amendments foreign in-country evaluations; 3) complete a generic adversary character-resulting from vulnerability assessments for protection plans for Category istics study based on over 650 data sources. Continue to maintain a data II/III materials, Coatingency Plans and Guard Training Plans. Review 200 btse of threat information. Complete NRC Headquarters contingency plan nuclear material shipments. Complete six IC CFR 73.55 operating reactor ef fort and complete an interagency agreement with the FBl; 4) complete 8 reviews and three reactor contingency plan reviews. Complete 60 security plan comprehensive evaluation reports on safeguards at SSNM facilities and evalu-ste the vulnerability of 15 SSNM vault dasigns; 5) provide user planning and 45
G
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(Dollars in Thousands, except whole dollars in narrative material) f"JCLEAR MATERI Al SAFETY AND SAFEGUARDS - continued license amendments and the analysis of 8 wital components and systems.
research requirements and plan and manage an approximate $1.3 M annual Implement the upgrade rule for 22 nonpower facilities, 8 Contingency Plans research program to assure the relevance of overall NRC physical security and 8 Guard Training Plans, and implement the Category II/Ill Rule at research and technical assistance program thrnugh agencywide reviews, update 26 facilities. Remedial licensing actions, identification of generic issues the integrated safeguards program plan, meet changing saft;uards needs caused and participation in nonproliferation activities will continue; 2) complete by a changing technology; and 6) draft a final regulation for physical protec-four foreign visits and 12 country analyses reports, and 22p physical protec-tion of spent fuel shipments, complete one minor generic regulatory issue tion reviews of export / import applications; 3) assess the implications of paper, complete four minor regulatory amendments, value/ impact analyses, and 300 safeguards events and maintain the threat data base. Accomplish contin-implementation guidance packages, complete two self-test guidance packages gency planning with an estimated 180 local law enforcement egencies distri-for physical protection subsystems. labe over development of generic issue buted alor.g 3000 road miles relative to in-transit protection over five papers, guidance and new regulations for power and nonpower reactors.
nuclear shipment routes; 4) based upon the requirements in 10 CFR Par
- 73 conduct vulnerability assessments of four nuclear fuel facilities and three The increase of $1,010,000 is primarily for add 4fonal technical assistance sptnt fuel /high level waste shipments resulting in approximately 35 remedial required to review reactor safeguards, licensing actions; 5) formulate approximately six NM55 physical security Summary of Waste Management Program Actual FY 1979 Estimate FY 1980 Estimate If 1981 Program Element Dollars Peoole Dollars People Dollars People
$ 6,636 27
$ 7,275 42
$10,640 50 High Level Waste Management....
I,203 17 2,425 25 1,975 27 Low Level Waste Management.
Uranium Recovery L'censity.
1,978 23 1,006 23 2,270
,3fg Total....
$ 9,817 67
$10,706 90
$14,885 112 FY 1979 = $6,636 FY 1980 = 7,275 FY 1981 = $10,640 High-level Waste Management.
(27)
(42)
(50)
The goals are to provide assurance to the public that all Department of The significant accomplishments for FY 1979 were: 1) issued for public Energy (DOE) repositories accepting high-level waste material are comment a proposed policy statement on the procedures for licensing properly designed, constructed, operated and terminated so as to have geologic high-level waste repositories, which has been developed into the no adverse effect on health and safety and the environment. DOE has been procedural portion of the high-level waste regulation; 2) developed given sole authority to dispose of high-level waste, consequently, NRC guidance on the format and content of reports submitted prior to site must develop a capability to indepene ntly assess DOE proposals in all characterization, and as part of a license application; 3) continued critical areas. NRC must also provide guidance and direction to the the development of models for assessing radionuclide transport in bedded DOE R&D Program.
salt; 4) reviewed DOE site characterization programs, and schedules; directed the NRC review of the DOE's draft GEIS on the management of The major objectives are to: 1) develop critical technical and scientific rommercially generated high-level waste and on the draft EIS for WIPP; information required for and publish generic regulations; 2) develop regu-
- 5) initiated an in-depth review of DOE's entire high-level waste manage-latory guidance (technical directives, review plans, format and content ment program.
guides) a minimum of two years before receiving a DOE license application;
- 3) develop a capability to perform reviews of DOE applications for the The significant accomplishments planned for FY 1980 are to: 1) publish for construction and operation of high-level radioactive waste disposal facil-public comment the proposed procedural and technical portions of the high-ities; 4) conduct site characterization reviews and safety and environ-level waste disposal regulation (10 CFR 60) with supporting EIS; 2) issue mental licensing reviews; and 5) evaluate the content and possible NRC draf t guidance on the format and content of site characterization, environ-use of results from DOE R&D efforts, provide guidance for DOE preappli-mental, and safety analysis reports, publish technical directives on site cition efforts, and evaluate overdil DOE program content and progress.
selection and characterization for bedded and domed salt; 3) complete development of models for assessing radionuclide transport in bedded salt;46
O O
O (Dollars in thousands, except whole dollars in narrative material)
NUCLEAR MATERIAL SAFETY AND SAFFCUARDS - continued
- 4) develop plans for conducting site characterization reviews, and guides, publish technical directives on waste form and repository design construction authorization revi?ws; begin onsite review of DOE site char-for bedded and domed salt; 3) complete the development of models for acterization activities at bedded and domed salt candidate sites; and 5) assessing radionuclide transport in domed salt and basalt; 4) expand assess the extent to which DOE's high-level wast
- program is directed at review of DOE site characterization activities to include the onsite developing the information necessary to comply with the proposed 10 CFR 60 review of candidate basalt and granite sites; and 5) continue the and provide the results to DOE.
critical review and overall surveillance of DOE's high-level waste R&D The significant accomplishments planned for FY 1981 are to: 1) complete resolution of comments on the proce6ral portion of 10 CFR 60 and publish The increase in resources in FY 1981 is to continue development of reguia-as final; complete resolution of comments on the technical portion of Lions and regulatory guidance for geologic disposal of high-level waste.
10 CFR 60; 2) pub 11sh the format and content guides as final regulatory Low-level Waste Management..........
FY 1979 = $1,203 FY 1980 = 52,425 FY 1981 = $1,975 (17)
(25)
(21)
The goal is to assure that low-level waste dispo.al facilities are con-Tha significant accomplishments planned for FY 1980 are to: 1) complete structed, operated, and terminated in a manner which wi d protect the the saf ety reviews for tenewal of the Richland, WA and Barnwell, SC public health and safety and the environment.
licenses, and complete the environmental assessment for the Sheffield, il decommissioning, and continue technical assistance to Agreement States; The major objectives are to: 1) perform thorough, yet expeditious, safety
- 2) issue a draf t regulation as an advanced notice of proposed rulemaking and environmental assessments required for low-level waste disposal opera-for low-level waste disposal; 3) prepare proposed guides for the prepar-tions licensed t*y the NRC, and provide assistance to Agreement States to ation of license applications and environmental reports for low-level help them discharge their regulatory responsibilities; 2) publish final waste disposal by shallow land burial; and 4) continue to provide technical regulations governing low 'evel waste disposal by shallow land burial assistance for disposing of IMI decontamination wastes.
(FY 1982) and by alternative methods (FY 1984); 3) upgrade the technical basis, including regulatory guides, and prepsre standardized review proce-The significant accomplishments planned for FY 1981 are to: 1) complete 50%
dures for licensing shallow land burial sites (FY 1982) and alternative of licensing review of an application for a new cosmercial LLW disposal low-level waste disposal methods (FY 1984); and 4) provide assistance to site, and continue to provide technical assistance to Agreement States; other NP.C offices in developing regulations and solving problems associated
- 2) continue wuk on final low-level waste disposal regulation (10 CFR 61) with the decontamination and decommissioning of nuclear nacilities.
and associated EIS; 3) continue work on regulatory guides and standardized review procedures for shallow land burial; and 4) provide technical assis-The significant accomplishments for FY 1979 were: 1) completed licensing tance for developing decommissioning and decontamination regulations for action on six applications for license amendments, and provided technical fue'6 cycle facilities, continue to assess special low-level waste disposal assistance to the Agreement States of Washington and Kansas; 2) published problems associated with the TMI cleanup, and evaluate onsite disposal reports on alternative LLW disposal methods and classification e, tem for activities of facilities being decommissioned.
10w-level waste; 3) completed development of a model for making low-level waste projections; and 4) provided technical assistance for disposing of The increase in personnel in FY 1931 is to permit more timely development 7hree Mile bland (TMI) decontamination wastes, of regulations and Ilcensing review procedures especially for alternative methods of low-level waste disposal.
FY 1979 = $1.978 FY 1980 = $1,006 FY 1981 = $2,270 Uranium Recovery Licensing.......................
(23)
(23)
(35)
The goal is to aswre that uranium recovery facilities are constructed, Specific activities are to: 1) issue license amendments to bring operating operated, and terminated in a manner that protects the public health and mills into compliance with new El'A radiation standards and regulations safety and the environment.
resulting from the CLIS on Uranium Milling; 2) perform environmental and safety reviews of applications for proposed f acility modifications; 3)
The single major objective of this decision unit is to make licensing issue license amendments supporting new requirements resulting from review and regulatory decisions to assure that the preceding goal is achieved, of facility operating data and NRC inspection reports; 4) perform safety 47
n n
,m (Dollars in Thousands, except whole dollars in narrative material) f40 CLEAR MATERIAL SAFETY AND SAFEGUARDS - continued cnd environmental reviews of If cense renewal applications; b) evaluate DOE inspection reports; 4) complete regulatory action on four uranium mill f eaedial accion plans, as mandated by PL 95-604; 6) perform safety and license renewal applications and four RAD facility license renewal appilca-environmental reviews of applications for new urcnium recovery operations; tions; 5) complete the review of proposed remedial action plans for one DOE and 7) provide tecanical assistance to Agreement States, facility; 6) issue licenses for five new uranium recovery facilities; and
- 7) provide technical assistance to Agreement States in completing ten The significant accomplishments for FY 1979 were: 1) initiated action to project reviews.
establish tne basis for determining whether operating mills are in compli-ance witn the new EPA radiation standards; 2) completed regulatory action The significant accomplishments planned for FY 1981 are to: 1) complete on five applications for proposed facility modifications; 3) continued to nine license amendments implementing new EPA radiation standards and review facility operating data and f4RC inspection reports to identify any regulations resulti?g from the GEIS on Uranium Stilling; 2) complete required license amendments; 4) completed regulatory action on one uranium regulatory action on 16 applications for proposed facility modifications;
.nt11 license renewal application; 5) prepared to review DOE remedial action
- 3) complete ten license amendments resulting from review of factitty plens; 6) issued licenses for twelve new uranium recovery facililities; operating data and NRC inspection reports; 4) complete regulatory action and 7) provided tecnnical assistance to Agreement States in completing six on three uranium recovery license renewal applications; 5) complete the project reviews.
review of proposed remedial action plans for six DOE facilities; 6) issue licenses for 14 acw uranium recovery facilities; and 7) provide technical The significant accomplistuents planned for FY 1980 are to: 1) complete assistance to Agreement States in completing 13 project reviews.
the final GEIS on Uranium Milling and completa four Ilcense amendments implementing new requirements; 2) complete regulatory action on ten The increase in resources in FY 19di is to pemit the licensing staf f to aplications for proposed facility modifications; 3) complete ten Itcense reduce the casework backlog for uranium recovery activities, amendments resulting from review of facility operating data and NRC Ha na gemen t D i rec t i on a nd Su ppor t.........................................
FY 1979 = 0 FY 1980 = $160 FY 1931 = $100 (16)
(19)
(19)
The goal is to ensure ef fective and efficient management of PMSS programs.
The following items were the significant accomplishments of FY 1979:
The director provides overall management direction and policy guidance on
- 1) NMSS realigned the organizational structure of the Division of Safeguards major program goals and objectives. The Program Support staff assists the to allow more effective use of available resources, recognize shif ting MSS Director by evaluating and assessing the effectiveness with which priorities, and more clearly delineate functional responsibilities and alhcated resources are managed in NMSS programs. In addit'e, the Program established the Division of Waste !ianagement to provide increased manage-Support staff provides resource management, contractual, auniinistrative, ment enphasis on this important area of iMSS responsibilities; 2) the and other direct support to the Division program staff, as well as PMSS Director was provided, at his request, with independent technical coordination with the ED0 staff.
and management assessments of selected technical programs, proposals, and other issues, which included the proposed annual budget.utuission, The major objectives are to: 1) provide overall management direction proposed mid-year financial reprograrning, executive program analysis and policy guidance as necessary to achieve NHSS program goals and reports, Congressional budget testimony, and responses to Congressional objectives; 2) conduct special independent technical and management inquiries; 3) the PPSAS manpower reporting subsystem for noncase activities evalaations of program resource utilization to ensure that programs are became operational; 4) approximately 80 procurement actions were executed planned and executed in an efficient manner; 3) manage the IMSS Program with private contractors, and the same number with DOE laboratories; and Planning and Status Assessment System (PPSAS) which provides fMSS program
- 5) necessary administrative and personnel services which include responding resource planning, status assessment and reporting, and financial control to F0IA requests, centro 11tng suspense items, controlling classified documents, information, enabling program managers to monitor decision unit accomplish-evaluating resumes, and processing personnel action requests were provided ments; 4) apport NHSS programs by the placement of technical assistance to the fMSS Director and Divisiens.
projects with private contractors. Department of Energy (DOE) laboratories, and other government agencies; and 5) provide administrative and personnel The significant accomplistments planned in FY 1980 are as follow:
services reqdred to operate NMSS programs.
- 1) policy guidance and management direction will continue to be provided to 48
___._..m
_ _ _ _ _ _.~_.-
O O
O.
(Dollars in Thousands, except whole dollars in narrative material)
NOCLEAR AATERIAL SAFETY Arid SAFEGUARDS - continued resolve issues and restructure programs, as necessary, to accomplish the The significant planned accomplishments planned for FY 1981 are as follow:
major objeccives of NMSS Decision Units within allocated resources; 2) the
- 1) policy guidance and management direction will continue to be pmvided
' rHSS director will continue to be provided, at his request, with independent to resolve issues and structure prograins, as necessary, to accomplish the technical and management assessments of se1Nted technical programs, major objectives of NMSS prograras within allocated resources; 2) indepen-proposals, and other issues; 3) the PPSAS manpower reporting system is dent technical and management assessments of selected technical programs, scheduled to be fully operational, with the integration of the budget sub-proposals, and other issues will continue to be provided; 3) the letSS systen, the casework subsystem, and the implementation of the reporting PPSAS will continue to be managed, and appropriate management information subsystem; 4) approximately 80 procurement actions will be executed with reports will be provided to NMSS prograta managers and the EDO staff; private contractors and the same number with DOE laboratories; and
- 4) approximately 80 procurement actions will be accomplished with private
- 5) neces u ry administrative and personnel services will continue to be contractors and 75 with DOE laboratories; and 5) necessary adialnistrative provided to the NHSS Director and divisions.
and personnel services will be provided to the NMSS Director and Divisions, to support the efficient operation of the Office.
49
= _ _.. _ _
_m
___..m.___
1 4
a
,)
J (Dollars in Thousands, except whole dollars in narrative material) t i
NUCLEAR REGULATORY'C0petSSION - Continued Nu cl ea r Re gu l a to ry Res ea rc h.................................................................................
1 i
4 Summary of Nuclear Regulatory Research Estimates by function Estir. ate (1)
Estimate i
t Actual FY 1979 FY 1980 FY 1981 t
1 I
j Nuclear Regulatory Research:
$ 5,593
$ 6,272
$ 6,900 t
4 Personnel Compen sa t i o n................................................
493 593 662 4
Pe rsonne l Be ne f i t s..........................,.........................
140,465 186,821 207.100 i
Program Support.......................................................
1.891 2,159 2,686 j
Administrative Support................................................
330 480 580 Trave1................................................................
8,612-7,737 10,300 Equipment.............................................................
1 J
$157,384
$204.062
$228,228 Personne1...........................................................'
(1 54)
(164)
(178)
TOT AL OBL I GAT I ONS................................................
j The fluclear Regulatory Research personnel and program support funding requirements have been allocated to major programatic function The narrative that follows provides justification in support of these requirements:
j Actual FY 1979 Estimate FY 1980 Estimate FY 1981 -
1 D611ars Penple '
Hollars People Dollars People i
$117,847 78
$157,721 83
$159,300 82
..ea c to r S a f e ty Re se a rch...............................................
7,999 12 7.000 12 12,200 14-Env i ronmental Ef fects and Fuel Cycle Sa fe ty...........................
4,450 8
8,600.
11 13,600 15 Waste Management......................................................
4,997 10 4,000 8
4,900 8
Sa f egua rd s Re sea rch...................................................
4,372 21 8,500 25 12,600 30 i
Risk Assessment.....................................................
B00 1
1,000 1
4,500 3
l I mp roved Re ac to r Sa fe ty...............................................
0 24 -
0 24 0
2f.
Management Di rection and Program Support.............................
I
+
$140,465 154
$126,821 1 64
>?07.100 178 4
TOT AL P ROGRAM SUPP0RT...........................................
i for the FY 1980 pay raise supplemental and $24,035,000 FY 1980 prooram* supplemental.
IIIIncludes $302,000 t
9 5
i 1
i i
]
50 4
T 4
5 t
a
,,)
I l
u-)
i iV (Dollars in Thousands, except whole dollars in narrative material)
N'JCLEAR REGULATORY CO'HISSION - Continued The Office of Nuclear Regulatory Research has the responsibility and
!icensing process. Such accidents, similar to TMI, can occur as a result authority under the Energy Reorganizat;on Act of 1974 to perform research of partial failure and intermittent operation of velous systems and may in support of the nuclear regulatory process. A major part of this respon-lead to extensi r core damage, without fuel meltinf. It is clear that the sibility is to develop an independently verified source of safety, health, TMI accident was not a unique sequence; one can pmtulate other similar environmental and safeguards information to be used together with the accidents starting from a variety of operational transients or other infomation furnished by the applicant or licensee in support of his causes that could ultimately lead b e@nsive fuel damage. For this proposal, as a basis for licensing and regulatory activities. Thus, a reason, we b311 eve the work requested belJw needs urgent attentim.
basic objective of the RES program is to provide objectively verified safety data and analytical methods which meet the needs of licensing and Soon after the TMI accident, RES moved to reorient its research program to increase emphasis on small loss-of-coolant accidents (trCA) and anomalous regulatory activities and the need for public confidence.
transient events, enhanted operator capability, plant response under accident The FY 1981 request provides resources to continue the research program on conditions and post mortem examination and plant recovery.
understanding reactor accidents from small loss of-coolant accidents, reactor transients and human error.
- n general terms, the TMI accident This FY 1981 request will enable NRC to continue vitally needed programs can be thought of as emphasizing the need for additional safety research begun in FY 1980 to address safety issues raised by the TMI accident, and infomation and understanding as indicated in the figure below:
assumes the FY 1980 supplemental request recently submitted to Congress and included in the FY 1980 column of the budget request is a: proved. In par-ticular, better coguter codes will be developed (I) to enhance our under-standing of small LOCAs and transients, (2) to allow multitudinous plant studies to be made of these types of events and the mny variations that can occur in them, and then (3) to predict, with greater precision than now possible, the behavior of nucitar power plants in response to such events.
Design Basis Accidents Studies will be made of simulator requirements to enhance the capability for training plant operators. Analyses will be made of the instrumentation Increasing Accidents Leading to needed by operators to understand and react properly to the full spectrum Consequences Extensive Core Damage of potential reactor accidents, and studies will be conducted of the control room display and diagnostic equipment needed to assist the plant operators u
Core Melt Accidents in effecting proper responses and insuring that limiting conditions of operation are met. Risk assessment tasks to construct event trees (proba-Design basis accidents (DBAs) have been studied extensively in NRC's bility models) are needed to define accident sequences covering severe core licensing process. A prime example of a DBA is a large loss-of-coolant damage, which the codes must calculate, and to guide the research tasks accfJent (LOCA). Theee analyses and supporting research are perfomed to needed to assess the potential impacts of human errors on the course of ensure that plant safety equipment (emergency core cooling systems, etc.)
these types of accidents.
have adequately defined safety margins to prevent significant fuel damage Also, the need exists to understand better the reaction and response of in the event of a DBA. While NRC has known for some time that more atten-tion is required for small LOCA and transient events, the TMI accident plants to the type of accident that occurred at TMI. Research pmgrams have been started in FY 1980 to obtain a better understanding of primary coolant clearly calls for much more action than has so far been taken to examine chemistry af ter severe fuel damage; hydrogen evolution and behavior in the these areas.
primary coolant system and in the containment; behavior of important compo-The area which lies in between the design basis accident and the Core Melt nents under long-term, severe accident environments', equipment qualification Accident has received less emphasis in both our research program and the and testing requirements; and structural analysis of important plant compo-nents and safety features under accident conditions. These programs will be continued and expanded under the proposed FY 1981 budget.
51
IG J
(Dollars in Thousands, except whole dollars in narrative material)
CJCLEAR REGULATORY RESEARCH - Continued I.
Reactor Safety Research Actual Estimate Estimate FY 1979 FY 1980 FY 1981 Dollars Peo gle Dollars Peop_le Dollars gPeo le A.
Light Water heactor (LWR) Safety Research.
HTM5 46
$T3FM5
~51
$ TEM 53 8,402 19 10,476 19 16,900 23 B.
Seismic, Engineering and Site Safety..
C.
Advanced Reactor Safety Research Program..
15,400 13 15.400 13 5,000 6
Total Reactor Safety Research Program..
$117,847 78
$157,721 83
$159,300 82 A.
Light Water Reactor Safety Research 32,187 17 41,345 19 38,000 19 (1) Systems Engineering....
(3) Code Development....
23,300 7
42,300 8
43,000 8
(2)
LOFT.......
9,330 7
12,000 8
14,200 8
20,828 8
27.600 9
27,900 9
(4) Fuel Behavior...........
8,400 7
8,600 7
14,300 9
(5) Primary Systems Integrity..
94,045 46 131,845 51 137,400 53 Total Light Water Reactor Safety Research.
....FY 1979 = $32,187 FY 1980 = $41,345 FY 1981 = $38,000 (1) Systems Engineering...
The Systems Engineering research program has been modified to emphasize Semiscale is a test facility designed to simulate PWR transient behavior improved understanding of accidents less severe (but more likely) than under loss-of-coolant accident (LOCA) conditions. The facility is a scale design basis accidents and to increase research on reactor operational model of the LOFI system and utilizes electrical heater rods to simulate safety. Systems Engineering otjectives are (1) to provide an experimental nuclear fuel rods. The Semiscale facility has been reconfigured to simu-data base from separate effects and integral-system testing for use in-late upper head injection of emergency core coolant, and THi-accident-developing and assessing analytical models and codes and in assessing support experiments were conducted in FY 1979. Within a few days after regulatory practices and requirements, and (2) to provide operational the THI accident started, Semiscale test.ed ways to remove gas from the safety research results for use in assessing and improving reactor opera-primary coolant loop and provided the results to the TMI recovery team, tional programs.
Subsequent TMI transient simulation tests at Semiscale confirmed that pressurizer " full" level readings did not preclude core uncovering. In The Systems Engineering research programs fall into four categories: (1)
FY 1980, small-break testing and upper-head-injection testing will be Integral systems tests (such as the Semiscale facility and the Two Loop c neluded. The Semiscale facility will then be upgraded in FYs 1980 and Test Apparatus) which will simulate reactor system performance during 1981 for better transient simulation of a pressurized water reactor plant.
(nomalous transients, small-break loss-of coolant accidents, or during Upgrading will simulate a.two-loop plant with two pumps in each loop, natural circulation conditions after an accident (2) Separate-effects sealed steam generators, and active secondary loops. This will provide tests which investigate different components or regions of the reactor realistic experimental simulation of reactor transients over a wide range system (e.g., simulated fuel bundles, pumps, etc.) under controlled tran, of accident conditions and operator responses.
slects for purpose of investigating behavior under accident conditions, (3) Very small scale (i.e., " bench-type") experleents designed to investi-The PWR blowdown heat transfer (BDHT) program, a separate research program t
gate fundamental two phase flow phenomena for model development, and (4) at the Oak Ridge National Laboratory, has been reoriented to emphasize Operational safety research to test relief / safety valves, fire protection small-break conditions. This program is concluding its experiments on systems, and qualificat h n-testing methods for safety-related equipment large loss of-coolant accidents, and in FY 1980 will conduct bundle uncovery that must withstand reactor accident conditions, studies on human factors, tests. These experiments will provide data for evaluating possible conse-and development of methods to improve NRC capabilities for inspection and quences of slow loss of PWR coolant over a range of conditions.
emergency response. These research programs and facilities are described 52 below.
m
{
D U
V (Dollars in Inousands, excent whole dollars in narrative material)
CCLEAR REGULATORY RESEARCH - Continued Srparate effects and systems effects experiments on the reflood phase of a design of instrumentation for the SCif Core I has been initiated and PWR loss-of-coolant accident are conducted under the FLECHT-SEASET project.
fabrication is to be completed in FY 1981. The IRAC code will be used to This project is jointly funded by NRC, Westinghouse and the Electric Power perform post-test analyses of the CCTF test results and design calculations Research Institute (EPRI). The project has obtained separate effects data for the SCIF and UPTF facilities, on reflood heat transfer in a simulated core and in a full height U-tube steam generator during a large-break loss-of-coolant accident (LOCA). In Model development activities (supported by small scale tests) will continue FY 1981. FLECHT SEASET will study modes of post-accident core cooling during FY 1980 to provide basic data for developing models and correlations following a small-break LOCA, including natural circulation, and will needed by advanrad safety codes. Validity of these models is then assessed study reflood heat transfer with flow blockage.
by comparisons with data from the larger scale separate effects and integral tests. In FY 1981 this work will include testing models for liquid / gas A BWR research program, jointly funded with GE and EPRI, has obtained data separation and thermal stratification within containment subcompartments on BWR blowdown heat transfer. In addition, a BWR integral system loop, following an accident and also will include basic research on steam / water the Two Loop Test Apparatus (TLTA), will conduct small break tests to interactions.
assess analysis methods in FY 1980. Plans are underway to upgrade the TLTA facility to improve small break and transient simulation.
A major lesson from the TMI accident is the importance of operational safety. Operational safety research will continue to evaluate the effec-Another separate effects program is the international cooperative 2D/3D tiveness of both fire prevention measures being utilfred in nuclear power research program which NRC is jointly funding with Japan and the Federal plants and qualification testing methods utilized for nuclear power plant Republic of Germany. This cooperative program will obtain experimental safety related equipment. Results to date from these tests, have generally information on ECCS behavior during the refill and reflood phases of a confirmed the acceptability of current practices and have led to the LOCA in full-scale PWR geometry. These experimental results will be used modification of the technical reviews of such related electrical equipment.
to confirm the physical models in the multidimensional system code, TRAC.
Large-scale replication fire testing will be started in FY 1980 and contin-G2rmany (FRG) is planning to construct a nonnuclear full-scale PWR upper ued in FY 1981. In FY 1981 operational safety research will also include plenum test facility (UPIF) mockup to study the behavior of water aad testing pressurizer safety / relief valves and other safety-related components, steam in the upper plenum and in the downconer during reflood. The Japanese providing research support for the Of fice of Inspection and Enforcement (IE)
Atomic Energy Research Institute (JAERI) completed the construction and and helping IE develop a rapid communication link between operating reactors initiated testing in a large (2,000 rod) electrically heated cylindrical-and the NRC response center, developing noise analysis techniques to core test facility (CClf) to study the refill and reflood phase during a monitor reactor behavior, and providing research support to develop human-PWR LOCA and is fabricating an electrically heated slab-core test facility factor guidelines for reactor operation and maintenance.
(SCTF) to study the multidimensional flow behavior of steam and water within the core, upper plenum, and downcomer during reflood. The NRC is In addition to the above activities, technical support will continue to providing the analyses, integration, and evaluation of the JAERI experimen-make NRC codes and research information available to the public through tal efforts through the advanced analysis code (TRAC), and is in addition the National Energy Sof tware Center and the Nuclear Safety Information fabricating instrumentation fnr installation on loan to these facilities Center, and will continue to develop instruments tu monitor such things as to provide for measuring steam and water flow patterns and behavior. The post-accident reactor water level and leakage through relief / safety valves.
experimental data and analysis will be used to evaluate computer codes and to assess margins of safety. The JAERI CCIF Core I commenced testing in The shif t of NRC's Systems Engineering research to emphasize small breaks raid FY 1979, the SCTF Core I is scheduled to begin testing in FY 1981, and and anomalous transients has been accompanied by a similar shif t in emphasis FRG is projecting a start-of-testing in the UPIF in FY 1983. NRC contrac-of reactor safety research in other countries. NRC has coordinated plans tors have already Aelie red a large complement of two phase flow, liquid in this area with other countries (particularly Japan and the Federal level and mo w t u flux measurement instrumentation to Japan which has Republic of Germany) so that this rasearch in the U.S. and other countries been installed and is in use in the vessel and loops of CCIF Core 1.
The is complementary.
...FY 1979 = $23,300 FY 1980 = $42,300 FY 1981 = $43,000 (2) Loss-of-Fluid Test.
The loss-of-Fluid Test (LOFT) facility is a nuclear reactor designed to the adequacy of analytical techniques for assessing performance of engi-investigate the behavior of a nuclear plant and its engineered safety neered safety systems; to evaluate the actual performance of integral features under accident conditions. The test results are used to evaluate reactor systems including safety systems under off-normal and accident 53
I V
V v
(Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REGULATORY RESEARCH - Continued conditions; to identify any unanticipated behavior not presently accounted being planned and these should provide infomation on natural circulation for in evaluating the performance of safety systems; and to evaluate the and plant recovery from anomalous conditions. In FY 1981, test planning information available to the operator, and its display, during off-normal includes three operational transients, a large LOCA at 100% of the power and accident conditions.
density in a commercial PWR and assuming a loss of offsite power, one small-break test, and one intermediate break test. This program will The nuclear LOCA testing began in early FY 1979, approximately 12 weeks in provide impo. tant information concerning the safe operation of today's advance of the schedule committed in October 1976. The first and second commercial plants, and the plants expected to come on line in the future, nuclear loss-of-coolant experiments in the power ascension series with full sized double-ended cold-leg breaks and with cold leg ECC injection The LOFT is also serving as a test bed for improved instrumentation to were done in FY 1979. In.1ight of the THI-2 accident, plans for small monitor the status of a plant during recovery from an accident and for break tests, off normal transient tests and natural circulation tests were computer-assisted graphics to display this information clearly for the advanced, the first zero power small break test was performed in FY 1979 operators. This will be helpful in testing the feasibility and effective-and the first full power test was performed in early FY 1980. For FY 1980, ness of proposed improvements in reactor control rooms.
a total of five small break tests and one operational transient test are (3) Code Development and Applications.
..FY 1979 = $9,330 FY 1980 = $12,000 FY 1981 = $14,200 The development of computer codes for analysis of nuclear power plant plant behavior for small-break LOCA and transients that may require operator brhavior under accident conditions is of central importance to the safety actions. Developent of this advanced simulator, if undertaken, would take research program. The objective of code development is to provide a f amily several years, of widely applicable computer codes for the analysis of the safety of the various light water reactor systems and components currently in operation The advanced code for PWR containment analysis (BEACON) has been completed, and in the design phases (CP and OL reviews). Experimental results from and its accuracy is being tested through comparisons with experiments.
the research program provide information used in code development and Final assessment, starting in FY 1981, will include comparisons with data the data for assessment of code accuracy. This research includes develop-from the containment intercompartment flow tests (described under Systems ing the codes, assessing the accuracy of these codes by comparison to Engineering). This code is to be used by the NRC staff to evaluate the experiments, and applying the codes to specific safety issues, ef fects of various accidents on the integrity of reactor containment buildings.
The major ef fort in code development has shif ted from improvement of existing codes (primarily RELAP) to development of advanced codes (primarily IRAC).
As advanced codes are completed, effort will increase to assess the codes The RELAP code has been improved periodically over several years and is in by comparison with experiments and to apply the codes. Application of these wide use, both in the United States and abroad. The first version of the codes to evaluation of plant response transients and small breaks will be advanced systems analysis code (TRAC) has been completed and released for made in a systematic manner in conjunction with the development (under Risk general use. In FY 1980, improved versions of TRAC to analyze a broader Assessment) of event and fault trees that include multiple equipment failures range of pnssib?e abnormal reactor conditions and accidents are being comple-and specified operator actions.
ttd.
In FY 1981, a fast running version of TRAC will be completed for PWRs and initiated for BWRs. Codes will be extended to analyze conditions lead-A plant data bank to store and rapidly retrieve design data from each ing to severely damaged cores.
operating reactor power plant is being studied in FY 1980. In FY 1981, it will be developed and applied to a few plants on a trial basis. Such a data Also in FY 1981, a study will be performed to evaluate the feasibility of bank will, in the event of an accident, allow NRC to promptly analyze the developing an engineering simulator that realistically models PWR and BWR accident and calculate results of alternative recovery actions. This capability will be greatly enhanced through an engineering simulator.
..... FY 1979 = $20,828 FY 1980 = $27,600 FY 1981 = $27,900 (4) Fuel Behavior..
Fuel Behavier research provides experimental data for independent assessment quantify fission product release and transport from fuel under accident con-of reactor fuel behavior during accidents. The approach used is to develop-ditions. The research includes fuel / clad model development experiments,
~
analytical models through basic experiments on fuel rods conducted out-of-fuel irradiation tests including the Power Burst Facility (PBF) experimental reactor, to assess these models with in-reactor tests, and to better program, fuel-behavior code development and testing, and molten fuel behavior 54
O O
O (Dollars in Ihousands, except whole dollars in narrative material)
NUCLEAR REGULATORY RESEARCH - Continued and fission product release and transport. Increased priority is results may cause some revisions in methods of calculating fuel pin distor-placed on research on the behavior of severely degraded fuel because tion in such accidents. Also PBF tests were conducted on prototype LOFT of the IMI accident.
fuel rods to assure that their design would withstand LOFT test conditions.
In the area of fuel / clad model development experiments, electrically heated Another PBF experiment provided data to help resolve the uncertainty in single and multirod bundle tests have provided information on the signitude measured cladding temperatures caused by placing thermocouples on the LOFT of cladding strain associeted with burst due to depressurization accidents cladding. Other PFB research has shown that the fuel pin cladding embrittle-as a function of temperature, pressure, and heating rate. Experiments on ment which follows film boiling during an accident does not necessarily the mechanical properties of zirconium cladding containing oxygen provided weaken the structure beyond its ability to retain fission products (current information used in the revision of licensing LOCA audit curves and, in licensing practice assumes fission product release if film boiling occurs).
addition, will provide the basis for consideration of a new embrittlement Reactivity initiated accident (RIA) tests in P8F have identified additional criterion for a future revision of 10CFR50 Appendix K.
In FY 1981, the failure mechanisms to be factored into proposed revisions of RIA licensing large bundle (8 x 8) experiments in the Multi-Rod Burst Test Program will criteria. During FY 1980, PBF testing will continue in the areas of simu-be completed. The out-of pile experiments on stress rupture properties of lated overpower accidents, simulated loss-of-coolant accidents, and possible irradiated Zircaloy will be completed. Production of flammable gas on fuel rod failure due to fuel pellet-cladding mechanical interaction during contact of metal coatings and organic coating systems by steam will be reactor transients. In FY 1981. PBF will perform two operational-transient underway and studies of radiation effects will start. Data on factors experiments, two reactivity initiated accident experiments, and one severe-which affect fuel temperatures during accidents will be obtained from fuel damage scoping test.
three experimental assemblies in the Halden (Norway) reactor. Prepara-l tions will be made for the obtaining of fuel samples from the TMI-2 To complament the PBF testing of three-foot-long fuel rods (during the reactor to mesh with the site schedule for access to the reactor vessel.
blowdown phase only), full-length (twelve-foot-long) fuel rods will be Investigations will continue on the possibility of generating explosive tested (during the heatup phase only) in the NRU reactor in Canada in hydrogen / oxygen mixtures in containment during accidents.
FY 1981. Also in FY 1981, experiment planning and design will be performed fer the ESSOR program. This program will test six-foot long rod bundles Codes for detailed analysis of fuel behavior during steady state (FRAPCON) during a complete LOCA sequence (blowdown, heatup, and reflood). Membership and during transients (FRAP-T) have been developed and are in wide use in in the Halden Reactor Group will continue.
the U.S. and abroad. Ongoing upgrading of these codes gives the licensing staff a more complete and accurate prediction of possible fuel assembly As a result of the THI accident, higher priority is now placed on fuel-melt temperatures during accident situations. In FY 1981, these fuel-analysis behavior and fission product transport. By the end of FY 1980, 270 experi-codes will be brought to a maintenance level, although upgrading will ments on vapor explosion triggering phenomena will be completed. Also, in continue by incorporating improved models and more ef ficient running the 48 larger scale tests to determine the thermal to mechanical energy methods. Linkage to systems codes will continue. Assessment of FRAP-T6 conversion efficiency, the largest observed ef ficiency was 1.5L This is and FRAPCON-2, by comparisons with data, will be completed in FY 1981.
about a factor of 20 less than the maximum theoretical efficiency. In FY 1981, small-scale steam-explosion tests will be completed in the fully Irradiation experiments are conducted to measure fuel response under instrumented test facility, and large-scale steam-explosion ef ficiency rcalistic accident conditions and to assess the accuracy of fuel codes.
tests will begin. Modeling of containment fission product transport for The Power Burst facility (PBF), located at the Idaho National Engineering the TRAF-MELT, code and fission product source-terms will be performed.
Laboratory, is the principal facility for this research.
betermination of fission product release on two PBF tests will be performed.
Means of making real-time estimates of core damage from fission product A loss-of-coolant test was performed in PBF using pressurized fuel rods in measurements in the coolant will be investigated, in addition to studies on which unexpected ballooning of the fuel cladding occurred. These test remote sampling of coolant chemistry during accidents.
.......FY 1979 = $8,400 FY 1980 = $8,600 FY 1981 = $14,300 (5) Primary System Integrity...
The objective of primary system integrity research is to provide information the results of large vessel tests have demonstrated the design conservatism to help assure the integrity of the reactor vessel, other primary system in reactor pressure vessels, and thus have helped validate the American components, and piping systems. The scope includes vessel, steam generator, Society of Mechanical Engineers (ASME) Code for reactor pressure vessels.
and piping integrity, irradiation embrittlement, corrosion, and flaw detec-In addition, results of fracture mechanics research in FY 1980 have greatly tion and evaluation.
55
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O (Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REGULATORY RESEARCH - Continued clarified the conditions for the extent and limitation of crack extension against the environmental effects causing corrosion and stress corrosion under nonpressurized thermal shock accident conditions. In FY 1980, this cracking in BWR and PWR piping.
research provided the first significant data on the fracture toughness cf irradiated thick steel weld metal exhibiting minimum acceptable fracture
'tesearch is being conducted on a series of nondestructive examination (NDE) toughness in its unirradiated state as defined by present federal regula-methods for pressure vessel, piping and steam generator tubes in order to tions. Data to be developed in FY 1981 will complete this evaluation and define the current limits of in-service inspection techniques and to improve help establish correlations between small test specimens and reactor the capability for both detection and evaluation of flaws. Based on develop-vessel material conditions. This work will help to determine the need ment of the SAFI-VI ultrasonic test method in previous years, the method for redefining federal regulations to assure a continuing safe level of will be transferred to industrial practice in FY 1981 to field usable equip-reactor pressure vessel material toughness, and determine the possible ment for vastly improved characterization of flaws periodically found need for in-service annealing of pressure vessels. Data collection in especially in large diameter piping. Other ultrasonic test work is aimed FY 1980 on the rate of crack growth in vessel and piping steels has at defining the test parameters and improved methods for performing more progressed such that a draft revision of the ASME Code Section XI curves accurate in service examinations. In FY 1981, the initial tests will be for evaluation of crack growth in operating plants is expected in FY 1981.
complete from many inspection teams examining a series of standard flawed The TMI accident revealed accident conditions for which the pressure specimens. Without the corroborating evidence of such multiple-team tests, vessel can undergo thermal shock at high pressures, and it is therefore the newer methods and ranges of test parameters to be used cannot be pro-necessary to investigate vessel integrity under pressurized thermal posed and enforced. Studies on improved eddy current NOE equipment for shock conditions. Design and construction of a facility for such steam generator tube inspection resulted in field tritis in FY 1980 in an pressurized thermal shock will begin in FY 1981. Studies which have operating reactor steam generator for detection of crevice cracking. This continued through FY 1980 will result, in FY 1981, in an analytical program is expected to be complete in FY 1981 with further field data -
code for the prediction of jet loads ad forces from broken pipes establishing the improvement in detection and characterization of a wide' and the consequences of the resulting pipe impact loads. New methods rang.e of flaws, dents and degradation in steam generator tubing. In developed to evaluate vessel and piping materials in the elastic plastic addition to the periodic NDE methods noted above, continuous monitoring range will be val; dated in FY 1981 by testing large diameter piping for cracking is also pursued. The acoustic emission method detects the removed from operating power plants.
location and growth of cracks during operation. In FY 1981, tests will be underway in operating reactor environments to validate the criteria, pro-Based upon the receipt of a retired steam generator in FY 1980, studies in posed in FY 1980, for the potential severity of a growing flaw, established FY 1981 will be concentrated on validating nondestructive examination methods through lab tests and in prototype component tests, the other continuous for detection and characterization of steam generator tube cracks and dents.
method under study employs internal friction to detect the incipient Construction of the facility for conducting the extended research program on formation of a crack. Following successful laboratory proof of incipient the patterns of degradation and corrosion will continue. Based on the crack detection in previous years, work in FY 1981 will be focused on completion in Fi 1980 of a comprehensive survey, studies will be initiated providing the ability to monitor in an operating reactor environment and in FY 1981 to establish a licensing basis for evaluating and mitigating on proving the capability of the method to predict stress corrosion crack initiation in BWR stainless steel lines.
FY 1981 = $16,900 FY 1979 = $8,402 FY1980=$10(476 B.
Seismic, Engineering, and Site Safety..
(19) 19)-
(23)
Tha Seismic, Engineering and Site Safety (formerly Site Technology and The Seismic, Engineering and Site Safety program is using the principles Engineering) program provides safety information for nuclear power and methods of probabilistic risk assessment in its research. The most plant sites, structures, components and equipment subjected to normal noteworthy example of this is the Seismic Safety Margins Research Program operating, extreme environmental and accident events such as earthquakes, (SSMP). This is a multidiscipline effort involving seismology, structural tornadoes and floods. The program also assists in the development engineering and mechanical engineering. The objective of the SSMRP is and confirmation of regulations, standards and 9uldes which dtfine the to develop mathematical models that can more realistically define elements safety design basis for nuclear facilities to withstand these phenomena.
that effect the probabilities of radioactive release due to large earth-These objectives are achieved through advanced analysis, experiments, quakes. These models will be used to gain engineering insights which field tests and observations. In addition, the Seismic, Engineering can be applied to develop improved design methods and criteria. Application and Site Safety program seeks to evaluate concepts which mitigate the of probabilistic techniques, along with conventional methods, will be used effects of extreme environmental and accidents events. Novel nuclear to study the effects of loads from the combination of simultaneous laroe facility siting designs, such as underground facilities or floating earthquakes and system transients such as large and small loss-of coolant power plants, fall within the interests of this program.
accidents (LOCA)-
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NUCLEAR REGULATORY RESEARCH - Continued The structural and mechanical engineering programs have been reoriented as component response. Investigations of the behavior of mechanical and a result of Three Mile Island and the five plant shutdown resulting from hydraulic snubbers under accident and environmental conditions will continue.
potential seismic design deficiencies. The studies should be continued A program to assess the adeouacy and validity of the ASME Boller and Pressure and accelerated to provide information to the user offices in a timely Vessel Code, as it applies to nuclear power plant components, will be started canner. Of particular importance are programs that provide damage assess-in FY 1981.
ment and requalification of structures and components subjected to accident conditions, evaluate effects of explosion inside the containment structure.
During FY 1981, current effort on regional seismological and meteorological assess the qualification standards for pumps and valves, and verify investigations will be continued, including expansion of the seismic computer codes used to predict the behavior of structures and components monitoring network near We Indian Point, New York, reactor site. Estima-under normal and accident conditions.
tion of potential earthquale hazards at dif ferent reactor sites, development of methods for interpreting earth stress measurements, reevaluation of During F) 1981, the structural engineering program will continue to support reactor site seismic instrumentation requirements, evaluation of real-time the 55MRP in the areas of soil-structure interaction and structural response.
meteorological modeling and site network requirements, analysis of ultimate Programs that support the licensing review of operating plants to determine heat sink performance tests, and completion of regional lightning hazard their capacity to withstand additional and new loads not required during assessment for U.S. are the projected accomplishments for the year in initial design, as well as assessing methods to define seismic input, Site Safety Research.
and develop technical positions relating to water hammer effects will be continued or initiated during FY 1981.
The increase in FY 1981 provides for structural and mechanical engineering programs, including initiation of experimental verification in ef forts The mechanical engineering program will concinue investigations in the such as the 55MRP, computer codes and snubber qualification. Also, other area of systems behavior in support of the SSMRP, component and equipment seismic activities are evolving from initial scoping to detailed analytical failure, nonlinear modeling and scaling of components, and mechanical and experimental ef forts which are necessary to cope with the issues related to the seismic safety of nuclear plants.
C.
Advanced Reactor _ Safety Research Actual Estimate Estimate FY 1979 FY 1980 FY 1981
$12,500
$13,700-
$5,000
(') Fast Breeder Reacurs...
2,900 1,700 0
(2) Advanced Converter Reactors..
$5,000
$15(400
$15(400 (6)
Total Advanced Reactor Safety Research..
13) 13)
Tha objective of this program is to provide the NRC with an independent Ongoing activities that involve projected empenditures in FY 1981 will be capability for safety assessment and for the development of licensing slowed down and no new commitments will be made starting in third quarter standards for advanced reactors. Two types of reactors have been the FY 1980 (April 1980) to allow orderly termination in FY 1981. At the focus of this program - Fast Breeder Reactors (FBR) and Advanced Converter indicated level of $5.0 million, it will not be possible to mothball facil-Raactors (High Temperature Gas-Cooled Reactors). These research programs ities or to finish current safety calculations. The primary ef fort in will be terminated in FY 1981.
FY 1981 will be to close down facilities and to document the current status This is in concert with Administration policy on Advanced Reactor develop-ment and is consistent with the DOE plan for FY 1981.
FY 1981 = $12.200
$7{999 FY1980=$7{000 (14)
FY 1979 =
II. Environmental Effects and Fuel Cycle Safety....
l2) l2)
This research program provides technical methods and data to predict and There are two general categories of research activity under Environmental assess the impacts and effects vpon the public and the environment of and Fuel Cycle research.
nuclear power plant operations and to assess the safety and environmental impacts of other licensed nuclear facilities.
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NUCLEAR REGULATORY RESEARCH - Continued 1.
Environmental Ef fects research is responsive to the needs identified effects mainly reflect increased emphasis on advanced research in acute by the licensing process for assessing and limiting the impact of morbidity and mortality studies and in early effects of inhale <1 radionuclides, ifcensed nuclear activities upon the environment.
plus increased emphasis on internal dosimetry of nuclear power plant workers and neutron dosimetry evaluation.
2.
Systems Performance research focuses on the performance of effluent control, occupational protection and safety systems other than reactor Systems Performance Research safety systems.
Environmental Effects Research In 1981, ongoing research will provide measured data and validated analy-tical models for evaluating radioactive aerosol production and release for In FY 19'1 environmental effects research will assess impacts of nuclear a range of fuel cycle facility accidents. Work will continue on the develop-8 power plants on oceans, rivers, lakes and ponds and associated fisheries.
ment and testing of codes and data to assess the response of shipping packages Computer codes for simulating entrainment and impingement phenomena and to the structural, thermal and radiation environments and to assess the resulting fish mortality will be tested using independently observed field adequacy of shielding and criticality controls as required by NRC's current measurements. A mathematical model of radionuclide transport in water regulations. Improvement of current codes being used routinely in NRC and sediments based on movement of radionuclides from the West Valley, licensing actions can shorten the time required for Ilcensing reviews and New York site to Lake Erie will be tested by field measurement data at improve their technical bases. A modal transportation study, initiated in all states of flow of Cattaraugus Creek. Research efforts will be FY 1980, is being accelerated in 1981 with the objective of developing an increased in FY 1981 in the areas of assessing of the feasibility of a improved technical base for NRC's transportation regulations, thereby further real time environmental monitoring data acquisition system for normal and enhancing the safety of radioactive materials transport. During FY 1981,-
emergency conditions, determination of entrainment effects on Zoo and package acceptance standards will be established for extremely severe trans-phyto-Plankton. Tests of methods used to establish bioaccumulation portation accident environments. Based upon the results, alternative regu-of P-32 in fish will be evaluated.
latory methods to limit potential exposures of the public will be developed.
A model for forecasting baseload and peakload needs for electrical power lhe measurements of radionuclide concentrations and relecses being taken on state and utility service bases will be developed and verified, in operating nuclear power plants will continue and the report on results and research will be initiated to evaluate the effect of power plant s tained from the first four plants will be published.
construction and operation on the local economy. Land use and value, population growth, need for public services, taxes and living costs will Studies will also continue to evaluate degradation of fodine trapping be among the factors studied. Development of a capability for predicting ability of charcoal filters under simulated accident conditions and exposure the need for electrical generating capacity on a regional basis will be to atmospheric pollutants during nomal plant operations. Werk will be continued with the participJtion of the New England states. Reflecting initiated to reflect increased emphasis on the evaluation of advanced THI concerns, additional research will be initiated in FY 1981 on assessing ef fluent treatment concepts which could significantly reduce normal plant emergency preparedness capability at the Federal, State, and local level.
radionuclide releases and waste volumas.
Research related to occupational radiation exposure and radiation health Reactor decommissioning projects initiated in FY 1979 will be expanded effects will be continued with no new initiatives. Methods for assessing to reflect current needs to establish decommissioning source terms based occupational exposures to radiation and alternative means of reducing work on assessment of samples fres reactor stations. The quantitles and distribu-exposure will be further analyzed in support of the as low as reasonably tion of long-lived activation products and radionuclide contamination as well achievable exposure control concept. Radiobiological research will be as the effectiveness of decontamination methods for reducing waste volumes done to determine the radiation dose patterns resulting from inhalation and occupational exposures in operating plants will be determined.
and ingestion of particulate fuel materials. Independently developed and verified information on the biological half-life of uranium in yellow-Additional research will be initiated to determine radionuclide inventories cake will be available to support bioassay requirements for uranium mill.
and distribution in fuel cycle facilities to assist the development of workers. Measurements of radionuclides in tissue relating the internal source terms for guidance of MRC policy for fuel cycle facility decommissioning.
deposition of thorium to measurements made by whole body counting and thoron breath analyses will be continued. Codes for calculating radiation Assessment of ef fects of decontamination on reactor ef fluent control systems dose to critical organs of the human body from internal depositions of will continue. A study will be initiated on the effects of decontamination radionuclides will be developed to improve assessments of radiation effects and decommissioning on the ability to solidify wastes. Research will also required for safety and environmental impact analyses. Increased research be initiated to evaluate the reduction in occupational exposure that could ef fort in FY 1981 over FY 1980 in occupational exposure and radiation health be effected by using decontamination processes during the plant lifetime, particularly during maintenance operations.
58
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(G G
(V
)
i 1
i (Dollars in Thousands, except whole dollars in narrative material)
NUCLEAR REGULATORY RESEARCH - Continued 111. Waste Management,...
FY 1979 = $4,450 FY 1980 = $8,600 FY 1981 = $13,600 (8) 11)
(15) experimentstoevaluateremotetechn(iquesfordeterminingthemorphologyof t'aste management research is providing tested analytical and predictive methods and confirmed data to support or improve engineering and scientific unerposed geologic structures; assessments of geophysical responses to assumptions and judgments used as bases for regulatory standards, impact thermal and other stresses from stored wastes; evaluation of the safety assesssments, licensing decisions and monitaring methods for processing and aspects of retrieving wastes or spent fuel f rom repository stor>A and hindling wastes, and for siting, designing, constructing, operating and assessments of the structural response and safety of repositories with terminating waste management facilities. This includes methods and data respect to accidents and natural geologic and cliraatic phenomena. The for evaluating radiation protection and safety systems; for predicting entire program of High Level Waste research will be broidened to develop and assessing environmental impacts from the processing. packaging, and verify methods for predicting, monitoring and assessing occupational transport, handling and isolation of wastes; and for assuring that safety, public exposure to radiation and environmental impacts, deleterious impacts are irept as low as reasonably achievable. The program is expanding and accelerating in order to develop technical information Low Level Waste to support and improve regulation of higS-level waste processing and isolation, low-level waste facilities and uranium mill tailings in response A major increased effort of this program will be to expedite the develop-to major DOF and industrial demands for licensing and regulation of waste ment of the technical bases for site selection criteria needed for canagement "acilities.
additional shallow land burial facilities, for evaluating and ensuring improvement of the operation of facil! ties in current use, and for decom-High Level Wastes missioning terminated facilities. Ihis includes intensive laboratory testing and field experiments at existing shallow land burial sites to Th2 high-level waste program provides technical bases for regulating the determine the effectiveness and reliability of methods used to site and processing and isolation of wastes that contain high levels of radioactivity construct the existing facilities, and to support regulatory requirements and for providing timely guidance to the DOE regarding information that for the engineering design and operation of burial facilities and for will be needed to meet licensing requirements. The program will improve monitoring the effectiveness and safety of these facilities. A study of understanding of the mechanisms important to the durability and stability the characteristics of radioactive wastes from medical and research insti-of the waste and provide methods for predicting the degradation of pro-tutions will be completed. Research will be initiated to define the charac-cessed and packaged wastes. This includes increased testing of matrices teristics of volume reduced wastes for shallow land burial and to assess and initiation of container testing for wastes and new projects to determine other disposal methods such as medium depth burial.
the combined ef fects of multiple processes that can decompose solidified wastes and their containers. Additional tests will be initiated to confire Tailings the effectiveness of overpack materials, and engineered multi-barrier systems which are designed to assure retention of any radionuclides for field sampling and analyses of radioactive gaseous emissions from mill at least 1000 years. The main natural mechanisms which can affect the tallings will be completed. Models for predicting atmospheric resuspension long term migration of radionuclides released from decomposing stored and transport of particulates and the seepage into groundwater of radio-waste are geochemical and hydrological processes. To develop an under-nuclides and other tonicants from mill tailings will be developed and standing of these processes, studies of the interactions between high level tested. Research will be initiated to (a) support. criteria for regulating wastes and various host rorts will be expanded, and methods will be the stabilization and decommissioning of tailings (b) measure the rated developed for predicting the long term migration and fate of these radio-of natural compaction of tailing piles, (c) test the ef fectiveness of nuclides. Systems analyses will include an intensified and accelerated erosion control methods (d) assess methods, costs and benefits of disposing development and refinemer.t of models for predicting radionuclide migration of tailings in mines, and (e) evaluate methods for reducing the volume pathways, transport rates and consequences. Repository engineering safety or radinactive content of tailing wastes. This program will provide studies to be carried out will include tests of the reliability of bore-technical information needed to support scheduled licensing actions and hole and fractured rock sealing techniques for repository requirements; provide guidance to mill operators for stabilizing mill tailings, and for minimizing the emanation of radon from inactive tailings piles.
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NUCLEAR REGULAf0RY RESEARCH - Continued IV.
Safeguards Research..
FY 1979 = $4,997 FY 1980 = $4,000 FY 1981 = $4,900 (10)
(8)
(8)
Safeguards research continues to stress the development of systematic Work will continue on the development of an improved national system for methods for uniform, equitable and repeatable evaluations of the effective-nuclear material inventory tracking and control. Data will be collected nass of safeguards systems, and to provide confirmed data and tested and analyzed to determine the significant factors which contribute to methods to improve the technical judgments and assumptions used in license in process holdup.
review, field evaluation and inspection, and the development of new regu-lations and regulatory strategy. This research covers physical protection Theresearchprojecttodevelopimprovedtechniquesandinspection and material control and accounting at fixed facilities and the protection procedures for field evaluations and inspection will be completed during of special nuclear material and spent fuel in transit.
FY 1981, and the 24 delivered modules will serve as the basis for strategy and implementation of the regional inspection program. These In FY 1981, research in physical protection will stress transfer of three inspection modules are being developed by a two year cooperative program evaluation codes to NRC for user application. These will include the involving the contractor, the Of fice of Inspection and Enforcement and completion of vital area identification using fault tree methodology at the regional inspection force, and will be transferred directly to all operating power reactors, and the preliminary application of two operational use. Some elements of the modules will be made available to other methods, SAFE (Safeguards Automated Facility Evaluation) and SNAP licensees for use in self test and evaluation of contingency response (Safeguards Network Analyses Procedure), to evaluate safequards at and guard training.
licensed fuel cycle facilities and power reactors. All three of these methods will be employed by the NRC staff to assist in licensing reviews.
The two year program of research to identify source terms for potential The contractor will support the initial ef forts involved in this transfer rad'oact7ee material releases resulting from explosive attack and deforma-and will incorporate the results and lessons learned from limited test tion of spent fuel shipping casks will be about two-thirds completed during applications during FY 1980 to increase the efficiency and effectiveness 1981. Interim results will be published to assist in reconsideration of of the codes, the current interim rule and to support environmental impact assessments.
Research on optimum defensive tactics during safeguards incidents will Methods previously developed for evaluating fixed site material control stress field experimentation on the instrumented Miles test range and accounting (MC&A) procedures will be fully incorporated into the (Sandia - Albuquerque) to provide data and methods for adversary neutral-coordinated research and applications program following prblication of the iration and to validate safeguards encounter models. Research to develop MC&A requirements as an effective rule. The codes developed in the research concepts and methods for previously developed evaluation of safeguards program will be extensively used in FY 1980 to support the development of for AFR (Away from Reactor) and Sng-term spent fuel storage will be these new rules, initiated.
FY1979=$4(21)
FY 1980 = $8(25)
FY1981=$12[30) 372 500 600 V.
Risk Assessment.
Risk assessment research entails the development of new or improved Each of these groups has recommended expanded development and application methods to predict the sequence of events in nuclear accidents, estimate of these nuclear safety analysis techniques.
their likelihood, and evaluate their consequences. The current scope of this research embraces light water reactor plants and radioactive waste Major efforts underway in the risk assessment program are:
repositories. The principal focus cf the reactor risk assessment research program lies in the development and initial application of safety analysis An Integrated Reliability Evaluttion Program (IREP) has been techniques that can address accidents that go beyond design basis eventr, initiated to apply existing risk assessment techniques to each of particularly those entailing multiple failures, human errors, and/or the operating commercial light water reactor plants in the U.S.
common-cause failures and that lead to core damage or meltdown.
The objectives are to identify particularly high-risk accident sequences at individual plants to develop a cadre of experienced Considerable growth in the risk assessment research program is required practitioners of these safety analysis techniques.
in FY 1980 and 'Y 1981 to accommodate the secommendations of the President's Commission on the Accident at Three Mile Island (Kemeny Improved collection and analysis of statistical data on component Commission), the Risk Assessment Review Group (Lewis Committee failure rates and human error rates applicable to reactor operators NUREG/CR-0400) and the Advisory Committee on Reactor Safeguards (ACRS).
and maintenance personnel.
60
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NUCLEAR REGULATORY RESEARCH - Continued Continue to apply the core melt consequence prediction models in Development of improved methods to classify, model, and predict human errors by reactor operators.
research to improve emergency planning and to improve nuclear plant
~
site selection and evaluation criteria.
Development of improved methods to predict the risk posed by in plant l
fires, in plant and external floods, and transportation accidents Continue research to develop a quantitative criterion of acceptable in the vicinity of nuclear power plants.
risk.
Development of improved methods to predict the risk posed by high-Continue research to resolve selected generic safety issues and level radioactive waste repositories.
identify improvements to the " single f ailure" criterion.
Continue research to improve core melt consequence prediction models, Continue the development of waste repository risk assessment models.
particularly atmospheric dispersion, liquid pathways, and biological-effects of released radioactive materials.
i FY 1979 = $800 FY 1980 = $1,000.
FY 1981 = $4,500 VI.
INPROVED REACf0R SAFETY.
(1)
(1)
(3)
Implementation of NRC's " Plan for Research to Improve the Safety of alternatives for achieving the same or greater increases in reliability Light-Water Nuclear Power Plants" (NUREG-0438, April 1978) was begun in of shutdown heat removal will also be emplored.
FY 1979 and continued in FY 1980. The research examines a spectrum of suggestions for improving reactor safety, develops functional requirements The objective of research on improved in plant accident response is to.
and conceptual designs, and assesses the value/ impact of developing, enhance the capability of reactor operators in preventing, recognizing licensing and implementing these conceptsJ The objectives are to determine and controlling accidents. In FY 1980 studies are being performed to tha feasibility of achieving particular safety improvements, to evaluate provide the operator with the necessary and sufficient information to the safety significance of proposed concepts and to propose regulatory indicate unambiguously the physical status of the plant and its engineered requirements where implementation is determined to be desirable, without safety features. Preliminary functional requirements for computerized preparing detailed designs. To date three concepts have been emphasized:
disturbance analysis and survillance systems are being developed. In (1) vented, filtered containment systems; (2) add on decay heat removal FY 1981 these studies will pr duce guidance for improving the quality of systems; and (3) improved in plant accident response.
the operator / machine interface. There will also be a significant expansion into other aspects of ope ator capability. Among them are The objective of vented containment systems is to reduce the probability studies to evaluate the technical ajequacy of approaches (e.g., noise of large airborne releases of radioactivity in the event of a core melt diagnostics, logic modeling, pattern recognition) to disturbarme or other severe accident, in FY 1980 preliminary design requirements, analysis; to assest the performance of prototype systems; to determine conceptual designs for several containment types, and computer models to the feasibility of new concepts for instrumentation and their appilca-analyze the performance of the system are being developed. In FY 1981 bility to commercial facilities; to improve the ways that plant data are the systems will be analyzed in detail, the design requirements will be collected, stored and presented to the operator; to develop requirements refined, and a Research Information Letter (RIL) assessing'the values that plant simulators must meet in order to serve as more effective and impacts of incorporating vented filtered containment into nuclear-training tools; and to gather data on operator performance under power plant designs will be prepared. Needs for additional information, simulated and actual plant conditions. Some of these studies will including experimental data, to reduo the uncertainty in the assessment utilize the improved information displays and diagnostic system being will be identified.
Installed on LGFT in FY 1980.
The objective of add-on decay heat removal systems is to reduce the In addition to the concepts emphasized to date, studies will be performed
[
probability of severe core damage through increased reliablity of shut-in FY 1981 which identify the risk reduction pote W M and feasibility down heat removal. In FY 1980 preliminary design requirements an' of other concepts such as innovative approaches to the protection against conceptual designs for a PWR and a BWR are being developed N NE and sabotage, molten core retention devices, improved monitoring and control the development and analysis of down heat removal system a?f.ributebie to systems, and others. Also the metimdology to assess quantitatively the the add-on system will be determined, the design requ bements wl;l be values and impacts of proposed safety improvements will be developed and refined, and a RIL assessing the values and impacts of the add-on system-applied to guide the implementation of concepts and to set priorities will be prepared for use in developing regulatory position 9ther for further research.
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I'JCLEAR REGULATORY RESEARCH - Continued VII. Management Direction and Program Support (Personnel)....
FY 1979 = (24)
FY 1980 = (24)
FY 1981 = (26)
The personnel requirements for this area consists of the Director's Of fice, other programatic functions within RES. These relationships involve both tdministration support staff and the resource control and contract execu-providing information to and receiving information from these other tion staff. This staf f provides the Director of RES with technical assist-offices, organizations, and groups, the workload within this area is ance and support to direct and evaluate complex technical research directly related to the workload within the other RES organizational projects; and plans, coordinates, directs, and executes the business elements, by the demand for RES action by other NRC offices and organi-matters of the Office, including contractual agreements, budget formula-2ations and by the interaction with those groups external to NRC. The tion, fiscal management, personnel administration, travel assistance, aquested increase in fY 1981 will pruvide stronger administrative and research coordination, assistance required by the expanding competitive contractor selection process and the implementation and execution of the agency-wide By the nature of its function, this area is interrelated with all other management performance system.
NRC offices and organizations, related groups external to NRC, and the Equipment..
FY 1979 = $8,612 fY 1980 = $7,737 FY 1981 = $10,300 Equipment requirements are needed for the varied research and development calibration certification facility, and in the new fault-diagnostic unit programs described above under Program Support. A major portion of the being installed to study operator / reactor interaction and information equipment is required in order to productively utilize major research display.
facilities such as LOFT, PBF, Semiscale, and thermal-hydraulic heat transfer experiments. Equipment will also be required to support:
In Fuel Behavior research, equipment is needed to upgrade the Power Burst environment, fuel cycle, and waste management programs.
Facility for testing at conditions beyond design basis accidents in order to better define the threshold of conditions leading to severe fuel Equipment is requested in Systems Engineering research to modify test damage. Also, equipment is needed for research on large-scale steam-facilities to allow more accurate simulation of reactor small-break explosion testing, fission product release at high temperatures, and LOCAs and operational transients. In addition, equipment is needed for hydrogen generation and behavior in containment. Equipment for Primary operational safety tests of fire protection and safety equipment System Integrity is requested for the examination of a steam generator qualification and also for containment intercompartment flow tests. New removed from service. Also, equipment is needed for research on inspec-equipment is needed to r@re aging equipment used in the continuing LOFT tion techniques and on environmental effects on piping and pressure program and facility support activities. Further, as the t0F1 project is vessel materials. Waste management equipment will also be procured.
expanded to its full scope, new equipment needs are being identified.
This will include sampling and measuring devices, analytical and test in particular, equipment is needed in the new fuel inspection and exam-instruments for high-level waste activities.
ination facility (the hot shop and hot cells), the new steady state flow 62
v v
v (Dollars in Thousands, except wnole dollars in narrative matertal)
NUCLEAR REGULATORY C06NISS10N - continued Program Technical Support
$18,861 Sunnary of Program Technical Support Estimates by Function Actual Estimate Estimate FY 1979 FY 1980 1/
FY 19e!
5 7,622 5 8,464 5 9,8v0 Personnel Compensation Personnel Benefits....................................................................
672 803 941 Progrca Support.......................................................................
1,312 3,595 2.790 Adm i n i s t ra t i v e Su p po r t................................................................
2,888 3,590 4,167 Travel................................................................................
637 920 1 13S Total Program Costs..............................................................
$13.13I TTQ72 ilu,.ebl Personnel............................................................................
(250)2/
(267)2/
(294)2/
This budget activity includes salaries and other costs for the staf f over the FY 1980 level of 40 represents an initial response offices trat provide direct program technical support. These are the to this goal and will be used to provice increased analytical Advisory Committee on Reactor Safeguards, the Atomic Safety and capability for the ACRS of ttce to do independent analysts of Licensing Board Panel, the Atomic Safety and Licensirg Appeal Panel, reactor safety matters.
the Office of the Executive Legal Director, the Of fice of State Programs, the Office of International Programs, and the newly b.
Atomic Safety Licensing Board Panel ( ASLBP) conducts statutory created Office for Analysis and Evaluation of Operational Data.
adjudicatory hearings through its hearing boards which issue decisions with respect to granting, suspending, revoking, or a.
The Advisory Connittee on Reactor Safeguards ( ACRS) estab-amending licenses or authorizations under the provisions of 11shed in 1957 by Statute, reviews and reports on safety app 11 cable laws or regulations. These decisions cover both studies and facility license applications referred to it; the construction and operation of nuclear power plants, and advises the Commission on potential hazards of proposed or antitrust issues relating to the operation of such plants.
existing reactor facilities and the adequacy of proposed Three-person boards, appointed from members of the Panel, con-safety standards; and performs such other duties as the duct the hearings which deal with environmental issues as well Commission may request. The ACRS reviews each application as matters of health and safety, national defense, financial for a construction permit or an operating license for power qualtitcations and economic considerations. Boards are also and test reactors and spent fuel reprocessing plants, any appointed to resolve issues that may arise as a result of application for an amendment to an operating license interventions by members of the public or any other party, referred to it by the Commission and any matter related Accordingly, the Panel has authority to rule on Petitions for to nuclear f ac111ttes specifically requested by the Intervention and to conduct rulenaking hearings as oesignated Department of Energy. The Committee's report on applications by the Commission. The Boards are required to initiate most for fac111ty Itcenses becomes a part of the record of the of the hearings in the vicinity of the plant site. The FY application and is made available to the public, except for 1980 staff totals 37 and remains unchanged in FY 1961.
privileged or security material. Section 29 of the Atomic From the Momic Safety and Licensing Appeal Panel ( ASLAP)
Energy Act of 1954 also requires the that the ACRS advise the c.
Commission with respect to the safety of operating reactors.
are drawn three-member tribunals which review decisons of The Fresident, in his response to the Kemeny Commission administrative law judges and atomtc safety and Itcensing Report, supported the concept of an expanded ACRS safety boards, and perf orm other appellate f unctions in (a) pro-review role. The requested increase of 2 technical positions ceedings on appitcations for Itcensing of production and 1/ Includes $403.000 for the FY 1980 pay raise supplemental and $1,425,000 for the FY 1980 program supplemental.
J/ Includes 8 personnel in FY 1981 converted to full time permanent with corresponding comparantitty adjustments in FY 1979 & FY 1980.
63
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O (Dollars in Thousands, except whole dollars in narrative material)
PROGRAM TECHNICAL SUPPORT - continued utilization facilities (under 10 CFR Part 50), and (b) such e.
The Of fice of State Programs (OS_PJ was established in 1976 to other licensing proceedings as the Commission may specify.
develop and direct a program of cooperation and llatson with In addition, these Appeal Boards perfonn such other regulatory States, local governments and interstate organizations; ammin-functions as may be delegated to them by the Commission.
1 ster the State Agreements Program under section 274 of the Atomic Energy Act of 1954, as amended; provide guidance, Members of an Appeal Board for a particular proceeding are training and assistance to State and local governments in assigned from the Atomic Safety and Licensing Appeal Panel, radiation control and radiological emergency response planning the members of which are designated by the Commission.
and operations; coordinate the development of an NRC national The Panel is organizationally separate from the Atomic emergency action plan; and cooperate with other NRC of ttces and Safety and Licensing Board Panel. The Appeal Panel's U. S. Government agencies having State and interstate activities and the assignment of Panel members to serve in responsibilities.
particular proceedings are responsibilities of the permanent Chairman and, in his absence, of the permanent Vice Chatman.
The functions of the ottice f all into three program areas:
The FY 1980 Appeal Panel staff totals 15 and remains unchanged (1) State Program Development. Assist the Comentssion in formulating policies involviiig NRC/ State cooperation and in FY 1981.
11alson; conduct national conferences, workshops and aantnis-d.
The Of fice of the Executive Legal Director (ELD) is responsible trative and contractual programs for coordinating and inte-for providing advice and services to the Executive Director for grating Federal and State regulatory responsibilttles Operations and the NRC programmatic and support offices which involving the streamlining of the licensing process, the report to that official. ELD responsib111ttes tuclude pro-transport of radioactive materials, safeguarding public viding legal representation for the NRC staff in administrative health and safety, the decommissioning of nuclear f actitttes, proceedings involving the licensing of nuclear facilities and the storage and disposal of radioactive waste materials and materials, enforcement actions and rulemaking. In addition, the identification and resolution of technical problems ELD is responsible for providing legal advice and services with involving urantum mills and mill tallings; maintain Itatson respect to such matters as health and safety, environmental with and provide guidance and support to State, interstate impact and antitrust aspects of licensini and regulation; regional and quest-goverrunental organizations, NRC ottices research programs; general agency admi11stration, including and other U. S. Government agencies on nuclear regulatory contracts, patents, personnel, security and labor relations; matters; and monitor nuclear-related State legislation.
Gafeguards and waste management programs; and the export /
import licensing program.
(2) State Agreements. Administer the State Agreements program in whRh 26 States are exercising regulatory responsibility for The diserse responsibilities of ELD are performed by five certain classes of radioactive materials; conduct annual re-divisions: Hearing Division Antitrust Division, Regulation views of State radiation control programs, provide annual Division, Rulemaking and Enforcement Division and the Operations training for State radiation control personnel, and render and Administration Division. In FY 1981, the ELD staffing level te:hnical assistance to the Agreement States to ensure adequacy reflects a net increase of eight positions over the FY 1980 ard compatibility with NRC standards; negotiate with and assist staffing level of 98. Two of these positions will be assigned is qualifying other States to enter into agreements with NRC to the Regulations Division to deal with growth in high and administer the Uranium hill Tallings Radiation Control Act and low level waste management and international export of 1978.
and safeguards matters. Two positions will be assigned to Rulemakirg and Enforcement to accommodate a projected (3) Emergency Preparedness. Carry out NRC's lead agency increase in enforcement and civil penalty matters, petitions responsibtIIttes in providing leadership and management for for actions against licensees and rulemaking matters. Three the Federal Interagency Radiological Emergency Response positions will go to Operations and Administration to Plannino and Preparedness Assistance Program for State and accommodate workload increase in personnel, labor and EE0 Local Governments; pubitsh technical guidance in many areas matters and related hearing activity. One position will be of radiological emergency response planning, incluetng assigned to the Program Support Branch to cover new support instrumentation guidance, accident scenarlos to test emergency plans, protecttve action guides, reatoprotective activities, 64
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PROGRAM TECHNICAL SUPPORT - continued prophylaxis, and radioactive materials transportation deter, and prevent diversion and thef t of nuclear material emergency planning; train State and local government personnel, exported from the United States. DIP is also responsible including emergency medical services personnel, to establish an for NRC's interagency 11atson en the implementation of adequate radiological emergency response posture in suppora, of the US/X AE A Safeguards Agreement, which was submitted to fixed nuclear f acilities and the transportation of radioactive the Senate for consideration in February 1978.
materials.
The FY 1981 staf f request reflects an increase of tour The FY 1981 request reflects an increase of 11 positions over the FY positions above the FY 1980 level of 31. This increase is 80 level of 28. Three of these positions will be uttitzed to assist largely due to the expanded export licensing respons10titttes in the expanding Agreement State program and in the administration which the NRC was required to assume with passage of the of the Uranium Mill Tailings Radiation Control Act of 1978; two Nuclear Nonprolif erattan Act. This Act required NRC to positions will provide State liaison officers for two additional NRC assume a greatly expanded Itcensing function for a wide regional offices, bring the total to four; the remaining sin positions variety of exported nuclear components some of which were will be applied to the emergency preparedness function to assist in previously licensed under authority of the Department of the review and approval of State emergency response plans. It should Commerce and the Department of Energy and to consult formally be noted that discussions are currently underway between NRC and FEMA on exports licensed by other U. S. Lovernment agenctes. In on the possible transfer of some NRC resources to FEMA in order to con-f urther support of NRC's export licensing responsiblit ties, solidate the emergency preparedness function in one federal agency.
OIP is expanding efforts in the areas of International sate-guards and physical security, and in health and safety f.
The Office of International Programs (OIP) is responsible for cooperation with developing countries which import U. S.
negotiation and implementation of regulatory and safety infonnation nuclear materials and equipntent. OIP is also taking exchange agreements with other countries, licensing the import and additional steps to help ensure that data on toreign export of nuclear materials and nuclear facilities, NRC nonpro-abnormal reactor operattng occurrences are available to liferation and international safeguards policy planning, analysis be factored into NRC's domestic safety program.
and coordination, and providing direct program support for all NRC international activities.
g.
Of fice for Analysis and Evaluation of _ Operation Data ( AEOD).
Largely in response to IMI and the (,AU and Kemeny Conantssion Major objectives of OIP are to improve public health and safety recommendations NRC has created a new Of fice f or Analysts by assuring timely U. S. access to operating data and safety and Evaluation of Operational Data ( AE00) and is expanding research information from foreign nuclear activ: ties, especially its operating data analysis function f or all licensees. The that which concerns foreign nuclear facilities of U. S. design function of this new of fice will be to gather, collate, or bears on current regulatory decisions in the U.
S., to provide analyze, and disseminate information received from all to other countries on a reciprocal basis the benefit of NRC licensed fac111ttes with particular emphasis on operating nuclear aafety experience, including, in particular, information reactors and to assess the safety implications such data has pertaining to the design and operation of exported U. S.
for regulatory poltetes and procedures. Both the amount of reactors; to comprehensively and carefully review export and data received and the complexity of the analyses and import license applications for nuclear materials and equipment evaluations are increasing significantly. The FY 1960 revised to ensure that such exports and imports will not adversely affect base (including supplemental) of 18 positions for this ottice U. S. national security; and to develop and implement NRC policy is increasing by 2 positions in FY 1981 to accommodate the in support of U. S. goals concerning nonproliferatton, the expanding workload.
strengthening of international safeguards and other controls against misuse of exported U. S. nuclear materials and equipment.
OIP, with technical support from and in coordination with NMSS, will develop NRC's contributions to U. S. government international safeguards and physical security policy on measures to detect.
65
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(Dollars in Thousands, except whole dollars in narrative material) l NUCLEAR REGULATORY CCMMISSION - continued l
(
P rogra m D i rect i on a nd Admi n i s t ra t 1 or........................................................................................................... $38,057 i
l SUP91ARY OF PROGRAM DIRECTION AND ADMINISTRATION ESTIMATE BY FUNCTION
(
Actual Estimate Estimate t
FY 1979 FY 1980 1/
FY 19%
$17,864
$20.198
$21.660 Personnel Coppensation P e rs on ne l B e ne f i t s....................................................................
1,576 1,913 2,079 Program Support.......................................................................
1,422 2,603 2.537 l
Administrative Support................................................................
7,236 9,345 10,916 865 l
Travel................................................................................
385 915
. $38.057 Total Program Costs..............................................................
$28,483
$ 34,9M I
Personnel.............................................................................
(708)2/
(740) y (753)ff f
Program Direction and Administration offices provide overall policy procedures for complete secretariat services for the con-duct of Comission business and inplementation of Coassission i
direction.. resource management, administration and logistic l
support, and includes the staff offices of the Comissioners decisions; advises and assists the Comission and staff and the Executive Director for Operations as shown below:
on the planning, scheduling and conduct of Comission business; prepares for and records Comission meetings in accordance with requirements of the Sunshine Act; provides
_The Commission:
ED0_:
senior-level management and administrative guidance on Consnission EDO preparation and submission of Comission staff papers to l
Secretary Equal Employment Opportunity include monitoring the status of all items requiring General Counsel Controller action; malrtains a forecast of matters for future Comunission Policy Evaluation Management and Program Analysis consideration; processes and controls institutional correspon '
l Inspector and Auditor Administration dence; maintains the Comission's official records; controls l
Congressional Affairs the handling and service of documents issued and received in all adjudicatory matters and public proceedings; Public Affairs coordinates protocol activities at the Comission level; a.
The Office of the Comissioners (OCM) is the governing body malr.tains liaison with and support for the Atomic Safety which must exercise the overall NRC responsibilities of the and Licensing Board Panel, Atomic Safety and Licensing Energy Reorganization Act of 1974 and the Atomic Energy Acts Appeal Panel and the Advisory Comittee on Reactor Safeguards;.
of 1946 and 1954, as amended. This body provides fundamental.
performs services of the Federal Advisory Connaittee policy guidance end administration and management direction Management Officer; operates a reproduction facility; necessary to assure that the civilian use of nuclear energy is administers the NRC Historical Program; operates the.
developed in a manner consistent with the public health and classified document control fystem for the Consnissioners; safety, environmental quality, national security and antitrust provides personnel, administrative and logistical support services to the Cnnunission and other NRC offices located in J
1aws. No staff increases are requested above the FY 1980 1evel of 31 people, however, OCM is requesting a $500,000 in.
Washington, D. C.; and supervises and administers the NRC Pubite Document Room, which is organized to maintain and crease in program support to initiate a pliot intervenor provide to the pub 11c regulatory information, reference funding program in FY 1981.
services and access to docket material pertaining to NRC l
b.
The Office of the Secretary (SECY) ' develops policies and regulatory and adjudicatory activities.
1/ Includes $977,000 for the FY 1980 pay raise supplemental and $525,000 for the FY 1980 program supplemental.
[
- 7) Includes 136 personnel in FY 1981 converted to full-time permanent with corresponding comparability adjustment in FY 1979 and FY 1980.
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PROGRAM DIRECTION ANJ ADMINISTRATION - continued The FY 1981 staffing level for the Of fice of the Secretary with GAO, the Department of Justice and other audit and law shows no increase above the FY 1980 level of 42 positions.
enforcement agencies.
c.
Of fice of the General Counsel (0GC) is the chief legal advisor to the The objective of OIA is to provide the Comission with an Commission. The General T.ounse170vides legal opinion, advice, and independent review and appraisal of programs and operattons consultation to the Conaission in connection with the quasi-judicial to assure that responsibilities are discharged with ettective-responsibilities of the Cammission and in the development of sub-ness and ef ficiency, and to provide a capability to verity stantive policy matters. It represents the Commission in matters re-facts to assure continued maintenance of the highest standards lating to litigation and, in cooperation with the Department of of integrity of all NRC organizations, programs and Justice, represents the Commission in court proceedings af fecting the activities.
the NRC program in the Federal District Courts. It represents the Commission, unassisted by the Department of Justice, in Courts of OIA is involved in a wide variety of activittes leadtng to the Appeal proceedings to review Commission orders. The office also pro-issuance of audit reports and memoranda related to NRC vides legal advice with respect to legislative matters of concern to operations and activities. Typically these activities involve NRC, including draf ting of legislation, preparation and review of coordination with the General Accounting Office, interviews testimony, and preparation and transat ssion of statements of views with NRC and industry otticials, visits to uttittles (reactor requested on proposed legislation.
licensees), steam supply system vendors, architect engineers, reactor sites, and fuel f abrication f acilities. In addition, ponse to a significant increase in workload related to the of fice is responsible for conducting a significant nober
,sts for regulatoO sctions from the public, expan& d of investigations and referring items, when appropriate, to 31slative review, re.olution of numerous unresolved legal the Department of Justice. In all of DIA's activttles, a ssues, and a variety of other legal matters, OGC is requesting continuous ef fort is made to eltsinate waste, traud, and one position increase over the FY 1980 staf fing level of 26.
error. The FY 1981 statt reflects no increase above the FY 1980 level of 28 postttons, d.
Office of Policy Evaluation (OF E) advises the Commission on a broad range of substantive policy matters to enhance the f.
The Of fice of Congressional Af f airs (OCA) assists and advises information base on which Commission decisions are made. The the Comission and senior statt on Congressional matters, office provides the Commission with an independent evaluation coordinates interagency Congressional relations activities of program policy objectives; reviews staff papers, provides and is the principal liaison for the Com15ston with independent technical evaluation of issues presented to the Congressional comittees and members oi Congress.
Commission, including cases under adjudication, and contributes technical and policy advice for projects being conducted and The primary objective of the ottice is to assure that the managed by other NRC of fices for outside agucles. The FY Congress is kept fully and currently informed of NRC 1981 staffing level remains unchanged from the FY 1980 level of activities as required by Section 202 of the Atomic Energy 18.
Act of 1954, as amended. The ottice seeks to assure that individual members of Congress are kept turrently and e.
Of fice of Inspector and Auditor (OIA) functions as the Agency adequately informed of significant NRC licensing Inspector General and 15 responsib W for developing policies activities that impact on their respective states and and standards that govern the financial and management audit districts. Additiona 'ly, the ot tice provides the Comission program, including planning and directing the long-range compre-and senior NRC staff with relevant and current information hensive audit program, as well as conducting day-to-day internal as to major legislative activities Itkely to ettect NRC.
audit activities; conducting investigations and inspections, as necessary, to ascertain and verify the facts with regard to the The FY 1981 staffing level readins unchanged from the FY 1900 integrity of all operations, employees, organizations, programs level of 9 people.
and activities; referring suspected or alleged criminal violations to the Department of Justice; administering the 9 Office of Public Af fairs (OPA) activities can be broken down Commission's "Open Door" policy; serving as point of contact into three broad categories. These categortes are: (1) with the General Accounting Of fice (GAO) and maintaining liaison issuance of pubitc announcements both from headquarters and 67
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O O
(Dollars in Thousands, except whole dollars in narrative matertal)
PROGRAM D*RECTION AND ADMINISTRATION - continued the regional offices; (2) responding to telephone inquiries from subject to NRC regulation, the news media and the public; and (3) responding to letters f rom the media and the public, including the bulk of the NRC referrals
- j. The Of fice of the Controller (CONJ provides the budgetary from the White House. In addition OPA arranges press conferences and liscal management organization for the NRC, including in the Washington area and in the vicinity of nuclear facilities, the development and maintenance of 4 financial control l
and coordinates requests for Commission speakers before civic groups system and a system of accounting designed to conform to and other organizations interested in the role of the NRC. The the standards prescribed by the Comptroller General. It office also assists the Itcensing boards, the appeal boards and the provides resource planning and evaluations to assess the i
ACRS at the hearings and meetings in which a high degree of public relationship between program workload and resource and press interest is evidenced.
allocation, develops manpower standards, evaluates over-r head ratios, and provides work measurement analyses.
In light of the unparalleled growth in of fice workload as a result of increased pubile concern over nuclear power, OPA is In FY 1979 and FY 1980 the computer 1 red multi-y4 ar Zero Base requesting a one position increase over the FY 1980 staffing Budgeting system was moditted to enable greater tiexibility level of 18 positions.
for generating ZBB data. Productivity increases continue to accommodate the increasing workload within the Division of h.
The Executive Director for Operations (EDO) is responsible for Accounting, although some backlogs are still anttcipated.
supervision and coordination of policy development and operational Nonetheless, the FY 1981 statftng level of 68 remains unchanged.
activities of both line and staf f of fices and for implementation of the Commission's policy directives pertaining to these of fices.
k.
The Of fice of Management and Program Analysts (MPA) provides The office consists of the EDO and his immediate staff and the management data and analyses for a variety of users within Administrative and Correspondence Branch which is responsible for the NRC and is the office responsible for developing and main-the EDO correspondence system including the assignment, review, tatning most of the agency's key management information sys-and coordination of all correspondence. The FY 1980 staffing tems. Organizationally, W A is divided into two divisions:
level of 13 remains unchanged in FY 1981.
(1) the Division of Information, Analysis and Planning which consists of the Internal Information Systems Branch; the 1.
The Office of Equal Employment Opportunity (EEO) is responsible Analysis and Planning Branch; and the Special Projects branch for defining the procedures and practices necessary to attain and (2) the Division of Technical Support which is made up of and maintain equal employment opportunity within the NRC.
the Automated Systems Branch; the Licensee Operations Evalu-The office develops and prepares the agency's Af firmative atton Branch; and the Applied Statistics Branch. MPA provides Action Plan, advises and assists on recruitment plans and analyses and management intornation f or the EDO and other provides investigation of discrimination complaints when office 4 through studies and evaluations on a wide variety of necessary.
subjects of interest to NRC management.
Major objectives of the office are to emphasize a program that Much of the analytical ef fort within MPA involves program will increase employment of minorities and women in the agency; and management issues, and long and short-range planning -
provide interaction with community groups concerned with equal studies. Additionally, MPA is a central source for opportunities for minorities and women; promote continued statistical analysis. The office also produces Congres-growth of the Upward Mobility Programs; provide training in sionally mandated reports such as: the NRC Annual Report Equal Employment Opportunity awareness for NRC managers and including the Report on Domestic Safeguards and Abnorwal supervisors; and assure a climate for improved employee morale Occurrence Reports. The FY 1980 statting level of 76 by promoting and maintain 6g EE0 counseling activities and sup-remains unchanged in FY 1981.
porting advisory commiittees made up of special emphasis groups.
1.
The Of fice of Administration ( ADJM 15 responsible for The FY 1981 staffing level of six reflects an increase of two personnel administration; security and classification; positions over FY 1980. This increase is necessitated by growth in document control; agency-wide training; f ac111ttes and EED workload internally and by increased efforts with respect to materials license fees; contracting and procurement; compliance activities pertaining to Title VI recipients and others transportation services; telecommun*:ations; amministration 66
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FROGRAM DIRECTION AND ADMINISTRATION - continued of Freedom of Information requests; centralized automatic data processing; printing and reproduction; records Nnagement; Privacy Act requests; and a variety of other housekeeping functions as well as support for 152 local pubitc document rooms.
The substantive work of ADM is performed by the Management Development and Training Staff, the License Fee Management Branch and seven divisions: Organization and Personnel, Security Facilities and Operations Support, Technical Information and Document Control. Automatic Data Pro-cessing, Rules and Records, and Contracts.
Nine additional positions abeve the FY 1980 staffing level of 407 positions are requested for FY 1981. In a recent report, the General Accounting Of fice criticized the agancy for over-reliance upon sole source contracting. The GA0 concluded that NRC's historical level of 65% sole source contracts could and should be improved. It is estimated that an average competitive procurement consumes four times -
the amount of time a contract specialist would need to J
complete a non-competitive action. Six positions are requested for the Division of Contracts to enable the Commission to increase the percentage of competitive procurecaents. This additional staffing will also permit ?
more effective contract eeninistritam and reduction
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1 Two Personnel Management 5dacialist positions see requested s
to provide accelerated staffing and placement services as well as concentrated implementation of the Civil Se-vice' ,-
s Reform Act. Also, one permanent position is requested tc-t heidle (i.e., receive, account for, process, disseminste
'and otherwise safeguard) tDe Continuously growing volume f
of agency intelligence-l'oternal security documents;'
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benefits by programs are shown in the tables below.
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Actual FY 1979-Estimate FY.1980 Estimate FY 1981 End A7.'EuT l End
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~.
Er.d Av 3 ull Program Stre-gth Time Obligationg. Strengtt _ Time Obligations. Strength Time _
Obitgat M
. - 122 722 29,844 Nuclear Reactor itegulation '
6r'.5 605
,22,432 722 3/
6b3 26,649 l 161 160 b bS3 Standards Development 134 2/
136 5,065 160 145 6,267 Inspection and Enforcement 727 710 22,559 874 800 27,017
'947 910 32,464 Nuclear Material Safety
,313 288 10,950 335 324 12.527 and Safeguards 263 268 9,012 Nuclear Regulatory Research 154 153 6,086 154 159 6,865 17o 171 1,562 Program Technical Support 250 243 8.294 267 258 9,'267 294 480 li),741 1 rt 708 636 19,440 740 724
_2(111 753
' 746' 23 73 2
TOTAL NUCLEAR REGULATORY COMMIS$10N 2.841 4/
2.751 92,803 3,240 4/
3.017 109.126 1/,.
3,390 4/
3,313 123,550 1/ Includes 54,810,000 for the proposed FY 1980 pay raise supplemental and $49,200,000 for the proposed program supplement.
f/ Includes equivalent 4 full-time personnel accomplished by 6 part-time personnel.
3/ Includes 4 personnel temporarily assigned to the U.S. Army Ccrps of Engineers.
]/ Includes 146 personnel in FY 1981 converted to full-time permanent with corresponding comparability adjustments in FY 1979 and FY 198U.
70
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FY 1981 Budget Estimates kT (Dollars in Thousands, except whole dollars in narrative material)
NRC DIRECT TRAVEL Actual Estimate Estimate FY 1979 FY 19h0 FY 1981 N uc l ea r R ea c tor R egul a ti on...................................................
.$ 1,053 5 1.105 5 1.230 Standards Development........................................................
173 250 240 Inspection and Enforcement...................................................
3,193 3,455 4.520 Nuc l ea r Materi al Sa fety and Sa fegua rds.......................................
352 494 6 30 N uc l e a r R egul a to ry R e s e a rc h..................................................
330 480 580 P rog r em Tec h ni c al S u p po r t....................................................
637 920 1.135 4
P rogram D i rec ti on and Admi ni s tra ti on.........................................
385 915 665 4
Total...................................................................
$ 6.123 5 7.619 5 9,20u l
The NRC estimate for travel covers the cost of official travel for examination and oversight of all commercial reactor and fuel Government employees while discharging assigned duties away from cycle facilities; coordination with DOC of fices and contractors their official duty stations. TP* travel costs reflect the travel and travel associated with the health, safety and compliance of NRC permanent full-time employees, NRC intermittent employees such function of the Advisory Committee on Reactor Safeguarcs and as members of advisory groups, members of boards and panels, individual the Atomic Safety and Licensing Board Panel.
consultants, and NRC trainees.
A signifle. ant portion of the planned travel is required to 4 majority of the travel is required in connection with inspection maintain technical and administrative supervision of Commission responsibilities of licensee facilities by IE personnel working programs, and to provide for attendance of NRC personnel at l
cut of five regional of fices; by NRR and NMS$ licensing of fices in necessary domestic and foreign meetings.
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FY 1981 Budget Estimates (Dollars in Thousands, except whole dollars in narrative material)
LEGISLATIVE PROGRAM PROJECTIONS Actual Estimate Estimate Estimate Estimate Estimate Estimate FY 1979 FY 1980 FY 1981 FY 1982 FY 1983 FY 1984 FY 1985 NRC Total Budget Authority 326 5
417 1/
468 481 5
477 480 40 Budget Outlays 309 351 1/
433 445 441 444 444 T/ Budget Authority includes $4,810,000 for the proposed pay raise supplemental. Budget Outlays associated with this supplemental total $4,680,000. Also, related to the program supplement, includes $49,200,000 Budget Authority and
$6,000,000 Budget Outlays.
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