ML20209H591
| ML20209H591 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1987 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-1100, NUREG-1100-V03, NUREG-1100-V3, NUDOCS 8702060083 | |
| Download: ML20209H591 (72) | |
Text
.
Uolu"$$i" BUDGEl ESTIMATES FISCAL YEARS 1988
- 1989 Appropriation:
Salaries and Expenses January 1987 U.S. Nuclear Regulatory Commission 8702060093 870131 00 R PDR l
t.
o 3
- n.
-3
- 2
+
e' Available from
~
Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, D.C. 20013-7082 Single copies of this publication are avePable from National Technical Information Service, Springfield, VA 22161 I
gwvmw'-
y r-.*
g 9i%,,
.m q
g,
- - - * -. + -,. -
-ew-,m
-..m9
.-+.,.-=--y
.---=g gyeg+9
.m%.ww.wiegw%
= -
-umi,y,eqp=d
- yye
- * --+
-r--a p
Uolu" ASP BUDGET ESTIMATES FISCAL YEARS 1988 - 1989 Appropriation:
Salaries and Expenses January 1987 U.S. Nuclear Regulatory Commission 8
BUDGET ESTIMATES FOR U.S. NUCLEAR REGULATORY COMMISSION 1
FISCAL YEARS 1988-1989 e
$ *h i
'3 57 Page(s) 8*
a Summary......................................
1-14 lEsi Nuclear Reactor Regulation Programs (NRR)....................
15-26 05 h_i Nuclear Material Safety and Safeguards Programs (NMSS)........
27-42 a
-1 Inspection and Enforcement Programs (IE).....................
43-58 SE 5'
Nuclear Regulatory Research Programs (RES)..................
59-88 i
5 ft RJ Program Technical Support (PTS).............
89-98 9
r Program Direction and Administration (PDA)..................99-110 o
5-t' Special Supporting Tables..................
111-114 r1 E
){
T 1
CONTENTS Page Summary...........................................................
1 Introduction.................................................
1 Salaries and Expenses Summary................................
3 Summary of Obligations.......................................
4 Financing of Obligations.....................................
5 Outlays for Salaries and Expenses............................
6 S umma ry o f B u d g e t............................................
7 Proposed Language - Salaries and Expenses....................
8 Analysis of Proposed Appropriation Language..................
9 Chart of FY 1988 Dollar Distribution.........................
12 Chart of FY 1988 Staff Distribution..........................
13 Nuclear Reactor Regulation Programs...............................
15 Chart of Program Support Funds and Staff Facing Page.........
15 Description of Programs......................................
16 Operating Reactors Program...................................
17 Safety Evaluation and License Maintenance...............
17 Response to Events and Assessment of Operational Problems..............................................
18 Project Management......................................
18 Systematic Safety Evaluation of Operating Reactors Program...
19 Operator Licensing Program...................................
20 License Reviews Program......................................
21 Reactor Operating License Reviews.......................
21 Standard Plants.........................................
21 Others Reviews..........................................
22 Safety Technology Program....................................
23 Resolve Safety Issues...................................
23 Human Factors Issues....................................
23 Regulatory Improvements.................................
24 Advance Reactor Concepts................................
24 TMI-2 Cleanup Program.......................................
25 Management Direction and Support Program.....................
26 Nuclear Material Safety and Safeguards Programs...................
27 Chart of Program Support Funds and Staff Facing Page.........
27 Description of Programs......................................
28 Fuel Cycle Facility and Nuclear Material Safety Programs.....
30 Fuel Cycle Facility and Nuclear Materials Licensing.....
31 General Licenses........................................
31 Licensing of Monitored Retrievable Storage Facility.....
31 Shipments of Spent Fuel and High-Level Radioactive Waste.
32 Dry Storage of Spent Fuel..............................
32 Demonstration of High-Level Waste Solidification........
32 Management of Low-Level Waste Prior to Ultimate Disposal.
33 ii
Pap Safeguards Program...........................................
34 Reviews of Safeguards at Operating Reactors.............
35 Safeguards of Licensed Facilities and Transportation....
35 Safeguards Support of the Nuclear Waste Policy Act......
35 IAEA Safeguards Program Participation...................
35 High-Level Waste Management Program..........................
36 Regulatory Guidance.....................................
37 Pre-Licensing Consultation..............................
37 Review of Site Characterization Plans...................
37 Low-Level Waste Management and Uranium Recovery Programs.....
38 Di sposal of Low-Level Radioactive Waste.................
38 Licensing Uranium Pecovery Facilities...................
39 Uranium Mill Tailings Remedial Action Program...........
40 Technical Assistance to States..........................
40 Management Direction and Support Program.....................
41 Inspection and Enforcement Programs...............................
43 Chart of Program Support Funds and Staff Facing Page.........
43 Description of Programs......................................
44 Reactor Inspections Program..................................
46 Power Reactor Workload Forecast Table...................
47 Resident Inspectors......................................
47 Region-Based Specialists................................
48 Safety Systems Functionality Inspections and Safety System Outage Modification Inspections................
48 Systematic Assessment of Licensee Performance...........
49 Vendor and Quality Assurance Programs........................
50 Vendor Program..........................................
50 Quality Assurance Program...............................
51 Enforcement, Technical Support, Incident Response and Li c e n s i n g P ro g ram s.........................................
52 Enforcement.............................................
52 Support for Problem Facilities, Allegations and Investigations........................................
53 Licensee Event Analysis and Generic Communications and Performance Indicators............................
53 Incident Response Program...............................
53 Emergency Preparedness Reviews..........................
53 Fuel Cycle and Materials Inspections Programs.................
55 Fuel Facilities Inspections.............................
55 Materials Inspections...................................
55 Decommissioning and Closeout Radiation Surveys..........
56 Specialized Technical Training Program.......................
57 Management Direction and Support Program.....................
58 Nuclear Regulatory Research Programs..............................
59 Chart of Program Support Funds and Staff Facing Page.........
59 Description of Programs......................................
60 iii
Page Reactor System Safety Program................................
64 Thermal Hydraulic Transients............................
64 Accident Evaluation.....................................
68 Risk and Reliability Research...........................
70 Engineering Safety Program...................................
73 Plant Safety............................................
73 Materials Aging.........................................
75 Waste Management Program.....................................
81 High-Level Waste........................................
81 Low-Level Waste.........................................
82 Regulatory Applications Program..............................
83 Regulatory Application..................................
83 Management of Rulemaking................................
84 Radiation Risk Assessment...............................
85 Radiation Risk Management...............................
85 Management Direction and Support Program.....................
87 Program Technical Support.........................................
89 Advisory Committee on Reactor Safeguards.....................
90 Atomic Safety and Licensing Board Panel......................
91 Atomic Safety and Licensing Appeal Panel.....................
91 Office of Investigations.....................................
92 Office of the General Counsel................................
93 Office of International Programs.............................
94 Office of State Programs.....................................
94 Office of Analysis and Evaluation of Operational Data........
95 Program Direction and Administration..............................
99 The Commissioners and Staff..................................
100 Office of the Secretary.....................................
100 Office of the Inspector and Auditor..........................
101 Office of Public Affairs.....................................
101 Office of Congressional Affairs..............................
102 Of fice of Executive Director for Operations..................
103 Office of Small and Disadvantaged Business Utilization and Civil Rights...........................................
103 Office of Information Resources Management...................
104 Computer and Telecommunication Services.................
105 Information Support Services............................
105 Office of Resource Management................................
105 Budget and Analysis.....................................
106 Accounting and Finance..................................
106 Office of Administration.....................................
107 Organization and Personnel..............................
107 Facilities and Operations Support.......................
108 Publication Services....................................
108 Rules and Records.......................................
108 Contracts..............................................
108 iv
faq.e Security................................................
108 Employee Development and Training.......................
109 Occupational Safety and Health..........................
109 Special Supporting Tables.........................................
111 Legislative Program Projections..............................
111 Consulting Services..........................................
112 Summary of Headquarters - Regional' Resources.................
114 v
m---+
J-1 s-~
e.
uA-----,,a-e a--.
w a-
}
l
SUMMARY
l l
I i
J I
m.-...4.---
=m--
M mm-a am--
--m-- - - -~s a
~1---maM-1-
G u
--A."--*=es--- - *---
-s m--
l E
E3 I
I n
,w
INTRODUCTION A.
The United States Congress has determined that the safe use of nuclear power for peaceful purposes, particularly in the production of electric-ity, is a legitimate and important national goal.
The Congress estab-lished the U.S.
Nuclear Regulatory Commission (NRC) to regulate those who commercially use or produce nuclear material so that the public health and safety, the common defense and security, and the environment are protected.
B.
To meet this Congressional mandate the Commission has adopted the fol-lowing broad goals as a basis for budgeting and future planning:
To assure the safe operation of licensed facilities and quality con-struction of those to be licensed.
To improve regulation of the nuclear industry.
To protect the public from risks associated with the wide-scale use of nuclear materials.
To ensure the safe transportation, storage and disposal of nuclear wastes.
To provide appropriate safeguards for facilities and materials.
To manage agency resources more effectively and efficiently.
C.
In furtherance of these goals, this budget for the NRC:
Places emphasis on safety first and foremost.
Continues the implementation of the Severe Accident Policy Statement initiated in FY 1986.
Continues the Integrated Safety Assessment Program based upon the results of the pilot program.
Places more emphasis on establishing a regulatory environment that will encourage nuclear power plant standardization.
Contains a long-term program to prepare the NRC to review licensee requests to extend nuclear power plant lifetimes beyond their current license conditions.
Develops improved guidelines and procedures for future decom-missioning of power reactors.
1
Provides for review of applications for reactor operating licenses and standard plant designs.
Proposes the construction of additional thermal hydraulic test facilities at the Idaho National Engineering Laboratory.
Expands the review, screening and analysis of operational data.
Provides for continuing analyses and proper regulatory response to the Chernobyl accident.
Provides for a stable research program essential for effective nuclear safety regulation, including continued NRC participation in major international safety research efforts.
Provides for maintaining resident inspectors el oil e eciutor-sites.
Maintains an effective emergency response capability for reactor, materials, and fuel cycle incidents.
Provides for regulatory review of the Department of Energy's waste management and advanced reactor programs.
Provides for the continued devalnnment of a framework for high level waste regulation and fulfillment of NRC's responsibilitics under the Nuclear Waste Policy Act of 1982.
Provides full regulatory support for the implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985.
Expands the regulatory oversight currently provided for nonreactor licensees.
Reflects significant staff savings associated with building con-solidation and other initiatives that increase productivity.
i
l t
f 4
SALARIES AND EXPENSES
SUMMARY
Estimates of Appropriation j
The budget estimates for Salarg and Expenses for FY 1988 provide for obligations of $427,800,000-to be funded in total by a new appropriation.
Estimates of Obligations and Outlays t
This section provides for the summary of obligations by program, the summary of financing these obligations, the analysis of outlays, obligations by function, the proposed appropriation language, and an i
analysis of the appropriation language.
The summaries of obligations include the Reimbursable prcgram.
_It should be noted that the obligations related to this program are not j
financed by NRC's appropriated funds, but solely through reimbursable agreements with other Federal agencies.
4 l
The agency.will deposit revenues derived from license, inspection and user fees and enforcement actions to Miscellaneous Receipts of the Treasury.
The Summary of Obligations by Program indicates the total obligations for Direct and Reimbursable Programs for FY 1986, FY 1987, FY 1988 '
and FY 1989.
The detailed justifications for direct program activi-ties are presented in the same order as they appear in this summary table.
i i
i t
I i
M Dollars in the text are whole dollars, dollars in the tables are in thousands; staff numbers are in full-time equivalents.
d 1
1 4
l 1,
t 3
l 1
SUMMARY
OF OBLIGATIONS FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Direct Program:
Nuclear Reactor Regulat!on.... $ 79,848
$ 80,810
$ 83,545
$ 81,030 Nuclear Material Safety and Safeguarda..............
38,532 40,423 41,180 39,985 Inspection and Enforcement....
94,398 100,571 104,880 98,925 Nuclear Regulatory Research... 123,785 111,685 119,675 125,260 Program Technical Support.....
31,286 33,644 34,082 33,700 Program Direction and Administration...........
42,054 43,141 44,438 43,700 Total Obligations -
Direct Prog ram............
$409,903
$410,274
$427,800
$422,600 Reimbursable Program.........
131 1,800 2,500 2,500 l otal Obligations...........
$410,034
$412,074
$430,300
$425,100 Offsetting collections from Federal Fund s...............
-189 1,800
-2,500
-2,500 Recovery of prior year oblig ation s.................
-5,781 Unobligated balance, start of year.....................
-13,312
-9,274 Unobligated balance, end of year.....................
9,274 Budget Authority............
$400,026
$401,000
$427,800
$422,600 4
FINANCING OF OBLIGATIONS The financing of the estimated total obligations of
$427,800,000 proposed in the budget estimate for FY 1988 is summarized in the following table:
Summary of Financing FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Sources of Funds Available for Obligations:
Recovery of prior year obligations.............
$ 5,781 0
0 0
Unobligated balance, start of year.................
13,312 9,274 0
.0 Appropriated to N RC.......
400,026 401,000 427,800 422,600 Subtotal
$419,119
$410,274
$427,800
$422,660 Less:
Unobligated balance, end of year..............
9,274 0
0 0
Total Obligations -
Direct Program
$409,845
$410,274
$427,800
$422,600 i
5
OUTLAYS FOR SALARIES AND EXPENSES Outlays for FY 1988 are estimated at $423,000,000. The fol-lowing analysis identifies funds available for outlays for each of the budget periods. This amount less the unex-pended balance at the end of the period equals the outiays.
Outlay Analysis FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Unexpended balance, beginning of year:
Obligated...............
$136,913
$120,020
$118,794
$123,594 U nobligated.............
13,312 9,274 0
0 Appropriation to N RC....
400,026 401,000 427,800 422,600 Total Funds Available for Outlays
$550,251
$530,294
$546,594
$546,194 Unexpected balance, end of year:
Obligated..............
-120,020
-118,794
-123,594
-123,194 Unobligated............
-9,274 0
0 0
Total Outlays..........
$420,957
$411,500
$423,000
$423,000 6
. =_..
SUMMARY
OF BUDGET OBLIGATIONS BY FUNCTION FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Direct Program:
Salaries and Benefits...........
$171,957
$175,823
$176,800
$163,200 Program Suppport..............
171,358 162,116 175,100 179,400 Administrative Support.........
56,868 61,835 65,800 69,500 T ra v e l.........................
9,720 10,500 10,100 10,500 Total Obligations -
Di rec t P rog ra m...............
$409,903
$410,274
$427,800
$422,600 l
Reimbursable Program..........
131 1,800 2,500 2,500 TOTAL OBLIGATIONS........
$410,034
$412,074
$430,300
$425,100 i
t 4
7
Proposed Language - Salaries and Expenses The proposed language is as follows:
Salaries and Expenses For necessary expenses of the Commission in carrying out the purposes of the Energy -Reorganization Act of 1974, as amended, and the Atomic Energy Act, as amended, including the employment of aliens; services authorized by sec-tion 3109 of Title 5, United States Code; publication and dissemination of atomic information;
- purchase, repair, and cleaning of uniforms; official representation expenses (not to exceed $20,000);
reimbursements to the General Services Administration for security guard services; hire of passen-ger motor vehicles and aircraft,
$427,800,000, to remain available until expended: Provided, That from this appropriation, transfers of sums may be made to other agencies of the Government for the performance of the work for which this appropriation is made, and in such cases the sums so trans-ferred may be merged with the appropriation to which transferred: Provided further, That money received by the Commission for the cooperative nuclear i
safety research program, services rendered to foreign governments and inter-national organizations, and the material and information access authorization i
programs including criminal history checks under Section 149 of the Atomic Energy Act, as amended, may be retained and used for salaries and expenses associated with those activities, notwithstanding the provisions of Sec-tion 3302 of Title 31, United States Code, and shall remain available until expended.
4 8
Analysis of Proposed FY 1988 U.S. Nuclear Regulatory Commission Appropriation Language 1.
FOR NECESSARY EXPENSES OF THE COMMISSION IN CARRYlNG OUT THE PURPOSES OF THE ENERGY REORGANIZATION ACT OF 1974, AS AMENDED, AND THE ATOMIC ENERGY ACT, AS AMENDED:
42 U.S.C. 5841 et. seq.
42 U.S.C. 5841 et. seq., the Energy Reorganization Act of 1974, estab-lished the Nuclear Regulatory Commission to perform all the licensing and related regulatory functions of the Atomic Safety and Licensing Board Panel, the Atomic Safety and Licensing Appeal Panel, and the Advisory Committee on Reactor Safeguards, and to carry out the per-formance of other functions including research, for the purpose of con-firmatory assessment related to licensing and other regulation, other activities, including research related to nuclear material safety and regulation under the provisions of the Atomic Energy Act of 1954, as amended (42 U.'S.C. 5801 et. seq. ).
2.
EMPLOYMENT OF ALIENS:
42 U.S.C. 2201 (d) 42 U.S.C.
2201 (d) of the Atomic Energy Act of 1954, as amended, authorizes the Commission to employ persons and fix their compensation without regard to civil service laws.
3.
SERVICES AUTHORIZED BY 5 U.S.C. 3109:
5 U.S.C. 3109 provides in part that the head of an agency may pro-cure by contract the temporary or intermittent services of experts or consultants when authorized by an appropriation.
4.
PUBLICATION AND DISSEMINATION OF ATOMIC INFORMATION:
42 U. S. C. 2161 b 42 U.S. C. 2161 b directs the Commission that they shall be guided by the principle that the dissemination of scientific and technical infor-mation related to atomic energy should be permitted and encouraged so l
as to provide that interchange of ideas and criticism which is essential l
to scientific and industrial progress and public understanding and to I
enlarge the fund of technical information.
1 5.
PURCHASE, REPAIR AND CLEANING OF UNIFORMS:
5 U. S. C. 5901 5
U.S.C.
5901 authorizes the annual appropriation of funds to each agency of the government as a uniform allowance.
9
6.
OFFICI AL REPRESENTATION EXPENSES:
47 Comp. Gen. 657 43 Comp. Gen. 305 This language is required because of the established rule restricting an agency from charging appropriations with the cost of official repre-sentation unless the appropriations involved are specifically available therefor. Congress has appropriated funds for official representation expenses to the NRC and N RC's predecessor AEC each year since FY 1950.
7.
REIMBURSEMENTS TO THE GENERAL SERVICES ADMINISTRATION FOR SECURITY GUARD SERVICES:
34 Comp Gen. 42 This language is required because, under the provisions of the Feder-al Property and Administrative Services Act of 1949, specific appro-priation is made to GSA for carrying out the function of protecting public buildings and property, and therefore, NRC appropriations not specifically made available therefor may not be used to reim-burse GSA for security guard services.
8.
HIRE OF PASSENGER MOTOR VEHICLES AND AIRCRAFT:
31 U.S.C.1343 and 1344 31 U.S.C.
1343 and 1344 provide in effect that unless specific-ally authorized by the appropriation concerned or other law, no appro-priation shall be expended to purchase or hire passenger motor vehicles for any branch of the Government...
9.
TO REMAIN AVAILABLE UNTIL EXPENDED:
31 U. S. C. 1301 31 U.S.C.
1301 provides in part that no specific or indefinite appro-priation shall be construed to be available continuously without reference to a fiscal year unless it is made in terms expressly provid-ing that it shall continue to be available beyond the fiscal year for which the appropriation Act in which it is contained makes provision.
10.
THAT FROM THIS APPROPRI ATION, TRANSFERS OF SUMS MAY BE MADE TO OTHER AGENCIES OF THE GOVERNMENT FOR THE PERFORMANCE OF THE WORK FOR WHICH THIS APPROPRIATION IS MADE, AND IN SUCH CASES, THE SUMS SO TRANSFERRED MAY BE MERGED WITH THE APPROPRI ATION TO WHICH TRANSFERRED:
64 Stat. 765, Sec.1210 64 Stat. 765, Sec. 1210 prohibits the transfer of appropriated funds account to another or working fund except as authorized by from one law.
10
- 11. THAT MONEY REECElVED BY THE COMMISSION FOR THE COOPERATIVE NUCLEAR SAFETY RESEARCH PROGRAM, SERVICES RENDERED TO FOREIGN GOVERNMENTS AND INTERNATIONAL ORGANIZATIONS, AND THE MATERI AL AND INFORMATION ACCESS AUTHORIZATION PRO-GRAMS INCLUDING CRIMINAL HISTORY CHECKS UNDER SECTION 149 OF THE ATOMIC ENERGY ACT, AS AMENDED, MAY BE RETAINED AND USED FOR SALARIES AND EXPENSES ASSOCIATED WITH THOSE ACTIVITIES, NOTWITHSTANDING THE PROVISIONS OF SECTION 3302 OF TITLE 31, UNITED STATES CODE, AND SHALL REMAIN AVAILABLE UNTIL EXPENDED:
26 Comp. Gen. 43 2 Comp. Gen. 775 Appropriated funds may not be augmented with funds from other sources unless specifically authorized by law. Under the cooperative nuclear safety research program, funds are received from foreign governments for their participation in N RC's reactor safety research experi-ments.
The NRC would also be authorized to receive directly com-pensation from foreign governments and international organizations for providing safety assistance and other services related to promoting the public health and safety. Funds are also received in the form of fees from licensees for the cost of security investigations and related processing associated with access to formula quantities of special nuclear material. These funds will be used to pay the related NRC processing costs and the agency performing the security investigations.
Pursuant to P.L.99-399, Section 606, funds will be received in the form of fees from licensees for the cost of fingerprint examinations and criminal history checks of each individual granted access to safeguards information or unescorted access to a nuclear power plant.
These funds will be used to pay for processing and performing the fingerprint examinations and criminal history checks. NRC will also use the money currently collected under 10 CFR Part 25, to pay the NRC processing costs and the Office of Personnel Management for conducting background investigations used as a basis for NRC security clearances for designated licensee representatives and other personnel requiring access to classified information.
11
FY 1988 DOLLAR DISTRIBUTION NMSS 9%
IE 25%
RR 19%
~
b d
.~
s PDA 11%
RES 28%
PTS 8%
l TOTAL = $427,800,000 12 l
FY 1988 STAFF DISTRI'BUTION NMSS 11%
s IE 34%
NRR 20%
RES 5%
PTS 10%
s PDA 20%
TOTAL = 3,250 13
1 THIS PAGE INTENTIONALLY LEFT BLANK I
I I
I
{
l l
l l
l I
l l
14 i
i
i l
I i
i NUCLEAR REACTOR REGULATION
NUCLEAR REACTOR REGULATION PROGRAM SUPPORT I
E 14.000 18.000 16.000 FY 1988 FY 1989 0 12.000 M
m 10.000 l
\\
6.000 4.000 wm A
fS6?/Z#'
STAFF 400 D
300 2.
100 0
' ! s /,4 ef h')I$ "
c'# #
NUCLEAR REACTOR REGULATION PROGRAMS i
(Dollars 'are in thousands, except in text, where whole dollars are used; staff numbers are in full-time equivalents.)
Tct31 FY 1988 est; bated obligations...............................
$83,545 4
l Total Funds and Staff FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Salaries and Benefits
$38,463
$39,410
$39,110
$36,080 Program Support 28,447 27,400 29,700 29,300 Administrative Support 11,420 12,390 13,220 14,050 Travel 1,518 1,610 1,515 1,600 q Total Cbligations
$79,848
$80,810
$83,545
$81,030 (Staff)
(697)
(686)
(655)
(635)
Program Support Funds and Staff The Nuclear Reactor Regulation staff and program support funds are allocated to the major programs shown below.
l The' program support funds are primarily for contractual work by the Department of Energy laboratories and commercial contractors. The narrative that follows de-scribes these programs and the reasons they are needed.
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds Staff Funds Staff Funds Staff Funds Staff Op rating Reactors
$ 9,650 306 $13,230 371 $14,994 362 $16,245 356 Systematic Safety Evaluation of Op:: rating Reactors 520 5
300 5
500 5
500 5
. Operator Licensing 3,275 66 2,305 77 2,760 81 2,120 81 l Licnnso ReOiews (7,479 138 4,460 86 3,688 67 3,627 67 Sr.fsty Technology
'7,353 133 6,885 99 7,708 97 6,808 87 TMI-2 Cleanup 170 8
220 7
50 3
0 0
Managtment Direction,
cnd Support 0
41 0
41 0
40 0
39 TOTALS
$28,447 697 $27,400 686 $29,700 655 $29,300 635 4
I t
15
Nuclear Reactor Regulation Programs DESCRIPTION OF PROGRAMS The Office of Nuclear Reactor Regulation (NRR) is responsi-ble for performing licensing activities associated with the con-struction and operation of nuclear reactors; reviewing applica-tions and issuing licenses for reactor facilities and designs as required by the Atomic Energy Act of 1954; and evaluating the health,
- safety, and environmental aspects of facilities j
and sites.
l This responsibility involves the following major functions: (1) performing detailed safety, environmental, and antitrust reviews of applications for nuclear power plant construction or operat-ing licenses and Standard Plant Designs; (2) conducting safety evaluations of licensees' implementation of requirements, or change.a to correct inadequacies, or effecting improvements in the design and operation of licensed reactors; (3) performing-the systematic safety evaluation of selected operating reactors; (4) examining and licensing reactor operators; (5) evaluating issues related to the safety and regulation of reactorr. to determine if regulatory requirements should be
- deleted, added, or modified to provide necessary safety improvements or to increase the predictability and stability of the regulatory process; and (6) providing for regulatory oversight of the Three Mile Island-2 (TMI-2) cleanup operations.
16
I Nuclear Reactor Regulation Programs OPERATING REACTORS PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 9,650
$13,230
$14,994
$16,245 (Staff)
(306)
(371)
(362)
(356)
The Operating Reactors Program ensures that operating facil-ities maintain adequate levels of protection of public health and safety by completing the regulatory actions necessary to correct inadequacies in plant design and operation that are identified from: operating experience, reviewing unanticipated
- events, resolving generic safety issues, inspection findings, and Nuclear Regulatory Commission (NRC) sponsored research.
These regulatory actions include safety evaluations necessary to complete specific amendments to operating licenses, requests for information on pending technical issues, and NRC Orders and hearings.
The program support increase and the staff decrease between FY 1987 and FY 1989 are due to a shift in the mix of contrac-tual support /in-house technical review for safety evalua-
- tions, with more reviews performed through contractual support by FY 1989 and an increase in the number of operating reactors.
The combined effort for contractual support and in-house reviews for each operating reactor remains relatively constant from FY 1987 through FY 1989.
SAFETY EVALUATION AND LICENSE MAINTENANCE Perform engineering and systems reviews and issue safety evaluations, including amendments to facility licenses necessitated by safety improvements or operating exigencies.
Such reviews are projected to total about 3,000 per year in FY 1987 and will increase slightly in FY 1988 and FY 1989 as the number of operating reactors increases. These reviews include the safety evaluations necessary to review and approve the licensee's proposed implementation of safety requirements such as resolution of reactor vessel overpressure p rotection,
the remaining TMI Action Plan items, such as containment hydrogen
- monitor, and other requirements applicable to a group of plants.
- Develop, in conjunction with the licensees, priority-based schedules for the completion of changes specified by new or revised NRC requirements and changes proposed by licensees.
17
i Nuclear Reactor Regulation Programs Evaluate longer-term operational issues at facilities with safety problems and review and resolve allegations and employee concerns at operating plants.
Examples of these activities include the need to resolve major issues, such as equipment qualification, plant operations, design control and welding.
RESPONSE TO EVENTS AND ASSESSMENT OF OPERATIONAL PROBLEMS Conduct initial technical assessments of reactor events to determine the immediate safety implications for the facility and the applicability to other operating reactors and to determine the immediate regulatory actions that must be taken.
Approximately 4,000 events per year are screened for safety implications. About 1,000 require further review and of these, about 300 warrant detailed follow-up, and recommended action.
Examples include failure of the Integrated Control System and severe overcooling transient at Rancho Seco and the loss of control from failure in the Remote Shutdown Station at Catawba.
PROJECT MANAGEMENT Project managers provide the overall management / review of safety and environmental modifications to operating plants. These modifications include actions that are directed by the NRC as a result of safety and environmental assess-ments and actions that are initiated by the utilities. It is through these modifications that NRC ensures that operating facilities achieve and maintain adequate levels of protection for the public.
There are projected to be 110 operating reactors in FY 1987,114 in FY 1988 and 117 in FY 1989.
18
I Nuclear Reactor Regulation Programs SYSTEMATIC SAFETY EVALUATION OF OPERATING REACTORS PROGRAM FY 1966 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 520 300 500 500 (Staff)
(5)
(5)
(5)
(5)
The integrated Safety Assessment Program (ISAP) will be continued through FY 1989. This program is needed to provide for the comprehensive review of selected operating reactors; to analyze, in an integrated manner, all pertinent safety issues; and to provide an integrated cost-effective imple-mentation plan for making needed plant improvements. The two plant pilot program that was initiated in FY 1985 will be completed in late FY 1987. The results of the pilot pro-gram will be incorporated into the follow-on ISAP program for two additional plants scheduled to begin in FY 1987. This follow-on program is scheduled for completion in FY 1989, i
d e
19
..~ -_.
~ _ -
Nuclear Reactor Regulation Programs OPERATOR LICENSING PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 3,275
$ 2,305
$ 2,760
$ 2,120 (Staff)
(66)
(77)
(81)
(81)
The Operator Licensing Program consists of the preparation, administration, and grading of examinations of reactor oper-ators, issuance of operator licenses ard the requalification of operators.
Initial examinations are needed to ensure that each new power plant is staffed with qualified operators prior to issuance of the plant operating license. Replacement examinations are ad-ministered to new operators at existing facilities to ensure that qualified operators are available at operating plants. The requalification examinations are designed to verify the con-tinued proficiency of licensed operators through the adminis-tration of examinations to 20 percent of reactor operators at about half of all operating plants each fiscal year. Operators of nonpower reactors are also examined to ensure their qualifications.
The anticipated workload for operator licensing is shown below:
Examinations Exam Type FY 1987 FY 1988 FY 1989 initial 345 190 50 Replacement 1,525 1,325 1,230 Requalification 457 460 460 Nonpower reactor 90 90 90 This program also includes studies of generic operator licensing problems, maintenance of an examination question bank, and improvements in the proficiency of examiners through training in examination content and balance, and in the development and writing of exam questions.
The requested resources reflect a policy of continuing to in-crease the proportion of examinations conducted by in-house NRC staff.
20
Nuclear Reactor Regulation Programs LICENSE REVIEWS PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estima'te Estimate Funds
$ 7,479
$ 4,460
$ 3,688
$ 3,627 (Staff)
(138)
(86)
(67)
(67)
The License Reviews Program consists of the review of appli-cations for reactor construction permits, operating licenses, and standard plant designs. The reviews include all aspects of safety and environmental
- effects, as well as antitrust implications. Also evaluated as part of these reviews are tech-nical reports submitted by industry organizations (primarily vendors) on subjects related to classes of nuclear reactors and their associated systems or operation.
The resources for operating license reviews decline as the num-ber of existing power plant license applications under review declines. This decline is somewhat offset by the increase in resources needed to review projected standard plant design applications.
REACTOR OPERATING LICENSE REVIEWS The required operating license reviews will be conducted on a schedule that will not unnecessarily affect reactor startup and operation.
It is anticipated that in FY 1987 there will be applications for 19 plants under active review, 10 in FY 1988, and six in FY 1989.
Initial decisions on operating licenses are planned for nine power reactors in FY 1987, four in FY 1988, and three in FY 1989.
In addition, resources are provided to support the resolution of major problems similar to those for TVA's Watts Bar facility and Texas Utility Electric Company's Comanche Peak facility.
STANDARD PLANTS in support of the Commission's goals pertaining to standard-
- ization, it is anticipated that in addition to the continued review of the Electric Power Research Institute's advanced reactor
- criteria, the following design certification reviews will be scheduled beginning in FY 1987: Westinghouse's RESAR SP/90, Combustion Engineering's CESSAR design, and General Electric's advanced boiling water reactor.
The current schedule for the certification reviews extends into the 1990's.
21
Nuclear Reactor Regulation Programs j
OTHER REVIEWS l
Resources are required to conduct reviews for nonpower license applications, license renewals and license amendments, and for safety reviews of projects conducted by the Department of Defense and the Department of Energy.
f i
i i
i i
j e
e i
1 i
j i
+
4 l
i i
22 4
1 1
Nuclear Reactor Regulation Programs SAFETY TECHNOLOGY PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 7,353
$ 6,885
$ 7,708
$ 6,808 4
(Staff)
(133)
(99)
(97)
(87)
The Safety Technology Program addresses significant technical issues that relate to the safety of reactor design, construc-tion, operation and maintenance, and regulatory issues that relate to the reactor licensing process.
Resource fluctuations between FY 1987 and FY 1989 primarily reflect:
changes to the implementation timetable of the Severe Accident Policy Program; changes to the Advanced Reactor Concepts work; and completion of certain risk assess-ment activities.
RESOLVE SAFETY ISSUES Technical positions will be developed on safety issues that affect a number of nuclear power plants and that relate to the safety of nuclear power plant design, construction, or opera-tion. These issues involve conditions not likely to be accept-able over the lifetime of the plants they affect. Priorities will be established for resolution of potential safety issues based on their safety significance and cost.
Completion is expected on three existing Unresolved Safety issues (USI's) in FY 1987 and five in FY 1988. The one remaining USl is scheduled for resolution in FY 1989. Technical resolutions of 21 generic safety issues are planned for completion in FY 1987, 19 in FY 1988, and 14 during FY 1989 and beyond. During FY 1986 and FY 1987, the NRC has evaluated and will continue to evaluate the implication of the Chernobyl accident.
Any generic safety concerns resulting from this evaluation will be resolved beginning in FY 1987.
4 HUMAN FACTORS ISSUES The technical basis will be developed for regulatory positions, guidance, and regulations on human factors issues related to the design, operation, and maintenance of nuclear power reactors.
These issues include
- training, staffing and qualifications, licensing examinations, and maintenance. Ongoing cooperative efforts with industry groups, such as the Institute for Nuclear Power Operations (INPO) and the Nuclear Utilities Management and Human Resource Committee (NUMARC), will be continued and incorporated in resolving human factors issues. For FY 1987, four human factors issues are scheduled for completion, with i
one in FY 1988 and one in FY 1989.
23 r,,-ee-,-~~
e w..
,.c
._-,e,-
---.r-
+
-e
Nuclear Reactor Regulation Programs REGULATORY IMPROVEMENTS The Severe Accident Policy Statement will be implemented for operating reactors and reactors under licente review over a four-year period beginning in FY 1986.
Development of a systematic approach to implement the Commission's Safety Goal for current safety issues is planned to be completed in FY 1987. After a one-year trial implementation, a Final Safety Goal will be proposed to the Commission.
Technical positions and guidance will be developed for conduct-ing probabilistic risk assessments, including improving the capability for assessing risk from external events.
Safety analysis computer codes used to perform analytical calculations will be evaluated, modified, and verified. The Standard Review Plan for reactor license applications will be updated as neces-sary.
Resources also provide for identification of research needs to support licensing activities, participation in re-search review groups and other office coordination designed to ensure that research efforts are directed toward maintaining applicability to regulatory goals.
ADVANCED REACTOR CONCEPTS Resources are provided for the implementation of the Advanced Reactor Policy Statement and for interaction, coordination, and review of DOE's program to develop, in conjunction with in-dustry, potential advanced reactor concepts. Based on DOE's program, NRC plans to review one High Temperature Gas Reac-tar (HTGR) and two Liquid Metal Reactors (LMR) concepts in FY 1986-1988, and initiate the review of one application beginning in FY 1989.
24
Nuclear Reactor Regulation Programs TMl-2 CLEANUP PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 170 220 50 0
(Staff)
(8)
(7)
(3)
(0)
This program provides for the onsite oversight of the TMl-2 cleanup operations, including technical reviews and government relations onsite and in the Middletown, Pennsylvania office.
This work will continue through FY 1988 to ensure the protection of the public health and safety and the environment during decontamination and disposal of radioactive waste from TMI-2.
After FY 1988, regulatory oversight will be maintained through the routine inspection and licensing programs.
25
Nuclear Reactor Regulation Programs MANAGEMENT DIRECTION AND SUPPORT PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
0 0
0 i
(Staff)
(41)
(41)
(40)
(39)
The resources requested for Management Direction and Support j
provide for the overall policy guidance and management direction of the NRR programs by the Office Director and the Regional Administrators. Requested resources also provide for independent assessments of selected technical programs, proposals and other l
management issues, executive program analysis reports, staffing
- plans, Congressional testimony, responses to Congressional inquiries and required support services.
).
t i
t 4
Y l
i t
i 4
i 26
l i
{
c
$4ih
- 3 22 l'
l l
l NUCLEAR MATERIAL SAFETY AND SAFEGUARDS l
4 l
i I
I
.l t
i
NUCLEAR MATERIAL SAFETY AND SAFEGUARDS PROGRAM SUPPORT LEGEND:
FY 1986 8,000 E
E 7,000 6.000 n
2 5,000 N
E k'
3 4 4.000 i
5 I 3,000 2.000 i
4 x
0-
^
^
A
,f;
- ,jt8
.4 STAFF 100 80 we 60 N'
x
/b fV / 4,.92S 65(.49'
NUCLEAR MATERIAL SAFETY AND SAFEGUARDS PROGRAMS (Dollars are in thousands, except in text, where whole dollars are used; staff numbers are in full-time equivalents.)
Tet:1 FY 1988 estimated obligation s................................ $41,180 Total Funds and Staff FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Salaries and Benefits
$16,907
$18,113
$17,930
$16,690 Program Support 14,521 14,500 15,000 14,500 Administrative Support 6,368 6,990 7,490 8,000 Travel 736 820 760 795 Total Obligations
$38,532
$40,423
$41,180
$39,985 (Staff)
(355)
(363)
(344)
(337)
Program Support Funds and Staff The Nuclear Material Safety and Safeguards staff and pro-gram support funds are allocated to the major programs shown below. The program support funds are primarily for contractual work by the Department of Energy (DOE) laboratories and commercial contractors.
The narrative that follows describes these programs and the reasons they are needed.
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds Staff Funds Staff Funds Staff Funds Staff Funi Cycle Facility and Nuclear Material Safsty
$ 3,071 98 $ 2,275 105 $ 2,400 99 $ 2,650 97 Saftguards 3,470 78 2,725 81 2,595 76 2,595 75 High-Level Waste Management 5,835 86 6,600 94 7,435 88 7,435 88 Low-Level Waste Manage-msnt and Uranium Recovery 2,145 66 2,800 56 2,470 54 1,720 52 M! nag: ment Direction and support 0
27 100 27 100 27 100 25 TOTALS
$14,521 355 $14,500 363 $15,000 344 $14,500 337 27
Nuclear Material Safety and Safeguards Programs DESCRIPTION OF PROGRAMS The Office of Nuclear Material Safety and Safeguards (NMSS) is responsible for the health and safety, licensing and environ-mental protection reviews for all activities regulated by the Nuclear Regulatory Commission (NRC), except reactors, and for safeguards technical review of all licensing applications, in-cluding those for reactors and the export of special nuclear material.
These responsibilities include development and implementation of NRC policy for the regulation of activities involving the use and handling of nuclear and other radioactive materials, such as uranium milling; fuel fabrication and fuel development; medical, industrial, academic and commercial uses of radioactive isotopes; certification of containers for trans-port of large quantities of radioactive material; out-of-reactor spent fuel storage; and safe disposal of low-level and high-level radioactive wastes.
Safeguards responsibili-ties include those licensing and review activities appropriate to deter and protect against threats of radiological sabotage and threats of theft or diversion of special nuclear material, both 6t fixed facilities and during transport.
The safety and environmental regulatory programs are designed to assure that workers, the public health and safety, and the environment are protected during both normal and off-normal operations.
These programs regulate activities ranging from complex operations--such as disposal of high-level radioactive waste in deep geologic repositories, reactor fuel development and fabrication, and medical radiopharmaceutical production--to relatively simple operations--such as medical diagnostic use of small quantities of radioisotopes.
Implementation of these pro-grams provides appropriate assurances for adequate and safe facilities; trained and competent personnel; appropriate prac-tices to control personnel exposures and environmental releases; contingency planning; transport casks to withstand conditions of normal transport and of accidents; and appropriate handling of radioactive wastes.
The safeguards regulatory program is designed to deter, detect, and protect against threats both within and outside of facili-ties, and during transport. In addition to providing for appro-priate theft protection, the safeguards program includes appropriate planning to protect against and to respond to intentional plant damage by radiological sabotage sufficient to cause significant offsite releases.
All safeguards activities are designed to assure that safeguards protective measures do not interfere with the safe operation of a facility both during normal and off-normal situations.
I 28
Nuclear Material Safety and Safeguards Programs The NMSS prcgrams have been strongly affected by the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, the Low-Level Radioactive Waste Policy Act (LLRWPA) of 1980, as amended in 1985, and the Nuclear Waste Policy Act (NWPA) of 1982. The UMTRCA directed the NRC to develop regulations and to license the disposal of mill tailings from licensed uranium mills.
Congressional action has directed that NRC regulations be amended in recognition of the Environmental Protection Agency (EPA) standards both for radiation and groundwater protection. In addition to directing NRC to revise regulations for licensees and to approve licensee mill tail-l ings disposal plans, UMTRCA requires that NRC review and approve the site-by-site implementation of the Department of Energy (DOE) program for mill tailings remedial actions, and to eventually license possession of these sites by DOE.
l The LLRWPA placed the responsibility on the states to provide for disposal capacity for low-level waste generated within a l
state. The NRC must ensure that appropriate regulations exist for both NRC and state licensing of disposal sites and must be prepared to provide technical assistance to states in reaching decisions on disposal facilities.
The Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 set up an l
aggressive timetable for states and compacts to establish new l
disposal facilities and for NRC to implement its substantial j
regulatory role.
{
The NWPA Act lays out a detailed approach for high-level waste disposal--an extensive, long-range undertaking with the DOE l
having operational responsibility and NRC having regulatory l
responsibility.
This undertaking involves a complex, inte-l grated system of waste handling, transportation, interim and l
retrievable storage, and ultimate deep geologic disposal of l
high-level radioactive waste requiring a
high certainty of acceptable environmental and health impacts over thousands of years.
29
Nuclear Material Safety and Safeguards Programs FUEL CYCLE FACILITY AND NUCLEAR MATERIAL SAFETY PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 3,071
$ 2,275
$2,400
$2,650 (Staff)
(98)
(105)
(99)
(97)
The Fuel Cycle Facility and Nuclear Material Safety Program in-cludes all licensed activities for the "f ront-end" of the fuel cycle after the uranium ore has been mined and milled.
This includes the processing of ore concentrates (yellow cake) into a suitable form for fuel, the development and fabrication of the fuel, and the safe transport and storage of fresh fuel at reactor sites until the reactor core is initially loaded with fuel.
This program also includes regulating approximately 9,000 medical, academic, industrial, and commercial users of nuclear and other radioactive material for diagnostic and therapeutic treatments; medical and biological research; academic training and research; industrial gauging and nondestructive testing; production of radiopharmaceuticals; and fabrication of commercial products such as smoke detectors.
The Fuel Cycle Facility and Nuclear Material Safety Program also involves, for operations under NMSS purview, the safe handling of radioactive wastes by industrial licensees and the safe interim storage of both low-level and high-level wastes at facilities prior to disposal at commercial facilities or by the DOE. This includes storage of spent fuel outside of reac-tor facilities or at any monitored retrievable storage facil-ity that the DOE is authorized to construct. Also included are the safety overview of DOE's high-level waste solidifi-cation activities at the clowd-down West Valley, New York reprocessing facility; the safety assessment of containers used to transport large quo.. titles of radioactive material, such as spent fuel and high-level waste; and the packaging and transport activities associated with the radioactive wastes from the Three Mile Island Unit 2 (TMI-2) reactor, particularly the core debris.
Transportation activities are closely coordinated with the Department of Transportation (DOT) and, as appropriate, with DOE and the Federal Emergency Management Agency (FEMA).
The staffing decreases in FY 1988 and FY 1989 reflect reduced efforts in spent fuel storage and transport container licensing work, technical assistance to the Agreement States, and nuclear material safety rule development. The additional funding in 30
Nuclear Material Safety and Safeguards Programs FY 1989 is for increased prelicensing guidance to DOE in antici-pation of receiving an application for a monitored retrievable storage facility in FY 1990.
FUEL CYCLE FACILITY AND NUCLEAR MATERIALS LICENSING Licensing work includes safety and environmental reviews required for the licensing and regulation of byproduct, source and special nuclear material in applications other than operation of power, test, or research reactors. NMSS-regulated activ-itles specifically include but are not limited to uranium fuel fabrication facilities, advanced fuel R&D facilities, and uranium hexafluoride production facilities, as well as medical, academic, industrial, and commercial uses of radioactive mate-rial.
The NRC will complete regulatory review of approx-imately 6,100 applications for new licenses, license amendments, license renewals, and sealed sources and devices in FY 1987, and 5,900 in FY 1988 and in FY 1989.
GENERAL LICENSES General licenses granted under NRC regulations are effective without the filing of an application with the agency or the issuance of licensing documents to particular persons.
Such general licenses currently apply to such radioactive devices as gauges, light sources, gas chromatographs, x-ray fluor-escence units, and static eliminators.
During FY 1985, a study found that gauge users were not complying in all cases with transfer and disposal requirements. During FY 1986 and FY 1987, the agency will expand the FY 1985 study to address other general licenses and to determine whether modifications of the regulations are needed, in FY 1988 and FY 1989, regulations will be revised as required.
LICENSING OF MONITORED RETRIEVABLE STORAGE FACILITY Monitored retrievable storage (MRS) involves the receipt, hand-ling, packaging and storage of spent fuel and high-level waste in a facility that permits continuous monitoring and ready retrieval for subsequent shipment to a permanent repository. Under the Nuclear Waste Policy Act of 1982, NRC is responsible for licensing an MRS if Congress authorizes DOE to construct one.
Thus, regulations for the storage of spent fuel in an inde-pendent spent fuel storage installation (Part 72 of Title 10 of the Code of Federal Regulations) will be amended in FY 1987 to provide for licensing an MRS facility. Assuming Congres-slonal authorization to DOE for an MRS, the NRC will review topical reports on specific design featu res, as requested by DOE, and will continue to provide other prelicensing guidance to DOE during FY 1987-1989.
31
Nuclear Material Safety and Safeguards Programs SHIPMENTS OF SPENT FUEL AND HIGH-LEVEL RADIOACTIVE WASTE The NRC reviews and certifies the designs of containers for transporting large quantities of radioactive material to ensure that such containers can withstand conditions of normal trans-port and accidents. Such licensing work involves applications for new container
- designs, for modifications to existing designs, and for renewal of existing certifications.
Appli-cations are submitted by commercial vendors and, on a selected basis, by the DOE. Approximately 110 certifications will be completed in FY 1987, approximately 110 in FY 1988, and approx-imately 100 in FY 1989~..
In support of the NWPA, NRC will provide technical guidance to DOE, DOT, the states and industry on safety and environmental policies and regulations for the shipment of spent fuel and high-level radioactive waste to any monitored retrievable storage facility, the high-level waste repository, and any Federal interim storage facility.
NRC will also certify spent fuel shipping containers developed by DOE under the Act.
l DRY STORAGE OF SPENT FUEL Review and evaluation work will continue on applications for site-specific interim storage of spent fuel outside of reactor pools. Also, review work will continue on evaluation of topical reports for dry storage cask designs. As required by the NWPA, rulemaking will continue on generic approvals for the use of dry spent fuel storage casks. This will require continued close coordination with DOE on its development and demonstra-tions of dry cask and site storage systems, and validation of performance predictions.
DEMONSTRATION OF HIGH-LEVEL WASTE SOLIDIFICATION As required by the West Valley Demonstration Project Act, con-sultation with DOE will continue through FY 1989 regarding the planning and safety analyses for the West Valley, New York project for the solidification of high-level radioactive waste.
NRC safety evaluation reports in FY 1987-1988 will include review of the supernate treatment system, the sludge mobilization system, low-level waste treatment and disposal, high-level waste
- storage, and the vitrification facility.
Close consultation is important to ensure that the resulting solidified high-level waste will be acceptable for disposal in the high-level waste repository.
l 32
Nuclear Material Safety and -Safeguards Programs MANAGEMENT OF LOW-LEVEL WASTE PRIOR TO ULTIMATE DISPOSAL Under the terms of the LLRWPAA, the states have responsibility for providing disposal capacity for certain low-level wastes (LLW) after January 1, 1993.
In the interim, access to exist-ing LLW disposal sites is limited.
Thus, work will continue on potential rule changes and preparation of licensing guides for acceptable LLW storage and treatment options.
Options include combinations of additional onsite
- storage, volume reduction, and centralized storage, many of which will require amendments to existing licenses.
1 1
33
Nuclear Material Safety and Safeguards Programs SAFEGUARDS PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Dtimate Funds
$ 3,470
$ 2,725
$ 2,595
$ 2,595 (Staff)
(78)
(81)
(76)
(75)
The Safeguards Program is designed to deter, detect and protect against threats, radiological sabotage and theft, or diversion involving special nuclear material, both at licensed facil-ities and during transport. Program implementation involves a large degree of professional judgment and is influenced by security or terrorist-type activities within society. Failure of safeguards has the potential for unusually high impacts on society, including theft of special nuclear material for extor-tion purposes or.in quantities sufficient to make a nuclear explosive device, and intentional damage sufficient to cause significant offsite releases from licensed facilities.
Special care must be exercised to assure that licensee-implemented safe-guards programs do not affect the operation of a facility (in both normal and off-normal situations) to the extent that a sig-nificant safety problem results.
4 Safeguards requirements are applied to nuclear material licensees possessing enriched uranium or plutonium, to reactors, and to the transport of enriched uranium or plutonium and nuclear reac-tor spent fuel. The requirements involve detailed planning, procedures, and operational systems for maintaining account-ability of material, as well as for deterring and responding to suspected theft or diversion of nuclear material, acts of radiological
- sabotage, or illegal seizure of material or j
facilities.
Techniques used by licensees include sophis-ticated detection and alarm systems, barriers, material con-trol and accounting, contingency plans for timely responses to threatening situations, and safeguards organizations staffed with trained and competent personnel.
This pro-gram also includes agency implementation of the Safeguards Agreement between the United States and the International Atomic Energy Agency (I AEA).
The resource decrease in FY 1988-1989 reflects a reduction in the rate of power reactor regulatory effectiveness reviews from 18 per year in FY 1987 to 14 per year in FY 1988 and FY 1989, and reduced efforts for regulations and regulatory guidance governing the protection of reactors and fuel cycle facilities.
34
Nuclear Material Safety and Safeguards Programs REVIEWS OF SAFEGUARDS AT OPERATING REACTORS Safeguards regulatory effectiveness reviews at operating power reactors have the objective of assuring that the safeguards required by the regulations and implemented by the licensees provide adequate protection without compromising safe opera-tions at the licensees' facilities. Fourteen reviews per year are currently planned for FY 1988 and FY 1989. At that rate, reviews will be completed at all operating reactors by FY 1991.
SAFEGUARDS OF LICENSED FACILITIES AND TRANSPORTATION Licensee operational data will continue to be compiled and ana-lyzed to look for early warning patterns and trends in safe-guards events and data and to identify and resolve any related generic issues through rule and regulatory guidance revisions.
Approximately 700 licensing reviews should be completed in FY 1987, approximately 680 in FY 1988, and approximately 650 in FY 1989. These licensing reviews include technical evaluations of safeguards plans or revisions of those plans for power reac-
- tors, nonpower reactors, fuel cycle facilities, the transport of nuclear materials, and the export of nuclear materials.
SAFEGUARDS SUPPORT OF THE NUCLEAR WASTE POLICY ACT in support of the NWPA, the safeguards aspects of any monitored retrievable storage facility as proposed by the DOE and autho-rized by the Congress will be reviewed and prelicensing guid-ance will be provided consistent with DOE schedules. As re-quired by the NWPA, development work will continue on safe-guards requirements for generic licensing of dry cask spent fuel storage.
I AEA SAFEGUARDS PROGRAM PARTICIPATION Consistent with the objectives of Title ll of the Nuclear Non-proliferation Act, participation will continue in the interagency Action Plan Working Group to strengthen I AEA safeguards and support the U.S.
program to provide technical assistance to IAEA.
In support of the US/l AEA Safeguards Agreement, which places i
selected U.S.
nuclear facilities under I AEA safeguards, docu-mentation of facility descriptions and the formal specific arrangements for implementing IAEA safeguards at the facilities will be completed, nuclear materials transaction and inventory data will be compiled and reported to I AEA, and l AEA inspection activities at selected U.S. facilities will be assisted.
35
Nuclear Material Safety and Safeguards Programs HIGil-LEVEL WASTE MANAGEMENT PROGRAM FY.1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 5,835
$ 6,600
$ 7,435
$ 7,435 (Staff)
(86)
(94)
(88)
(88)
The NRC's high-level waste management program is directed to an effective and efficient discharge of N RC's responsibil-ities based on the premise that, in the absence of unresolved safety concerns, the NRC regulatory program will not delay implementation of the Executive Branch's program as reflected in the DOE Project Decision Schedule (NWPA Section 114(e)).
The resources identified are based on the schedules presented in the March 1986 Project Decision Schedule.
The N R C's principal responsibility in the high-level waste program is to license the high-level waste repository providing that an independent NRC determination shows that the pro-posed repository's expected performance meets regulatory requirements and is adequate to protect the public health and safety and the environment.
To fulfill this responsibility without causing costly delay or rework in the DOE program,
- early, ongoing interaction and prelicensing consultation is necessary between the NRC and the DOE. Licensing decisions will be based on independent analyses of programs now being planned and implemented by DOE. DOE must demonstrate and the NRC must assure with appropriate certainty in a
formal licensing proceeding that the appropriate regulatory standards for public health and safety and the environment are adequately met.
In order to provide for an effective and efficient licensing process for this first-of-a-kind undertaking, the NRC, in a timely manner, must develop the methods for demon-strating compliance with performance objectives to permit independent determination of the adequacy of the DOE program; provide guidance to assure that the DOE program provides essential and acceptable data without costly delay or rework; provide onsite overview of activities; identify and resolve issues; and provide appropriate and timely review and evalua-l tion of DOE submittals.
The staffing decrease in FY 1988 reflects the time-phased re-i source requirements for reviewing DOE site characterization l
plans; the completion of a licensing open-item tracking system l
in FY 1987; and a reduction in efforts for developing regulatory j
guidance and for early resolution of licensing issues. The funding increases in FY 1988-1989 are for additional effort I
for streamlining the licensing process.
I 36 l
l
Nuclear Material Safety and Safeguards Programs REGULATORY GUIDANCE To ensure that the DOE program provides the essential, accept-able, and timely data required by the NRC for licensing review and to ensure that licensing information needs are met and that licensing issues are resolved in a timely manner, the NRC must provide appropriate and timely regulatory guidance to DOE. Such guidance includes the agency's regulations, regula-tory guides, and staff generic technical positions.
Underlying such guidance and the preparation for NRC technical reviews is the development of an NRC review capability. This includes developing review plans and a complex set of system performance assessment models and computer codes which must be maintained and updated as the repository development program progresses.
In addition, the NRC is attempting to identify potential approaches and develop plans for streamlining the licensing process to ensure that the three-year licensing review time mandated by the NWPA can be met.
PRELICENSING CONSULTATION Close interaction will be maintained with DOE, the states, affected Indian
- Tribes, the technical community and other interested members of the public to identify and begin the resolution of licensing issues at the earliest possible date to minimize costly delays or reworks by the DOE. As part of this
- effort, extensive NRC prelicensing reviews of DO E's generic and site-specific investigations will continue.
These DOE investigations include field and laboratory testing to support waste package designs, field and laboratory testing of geologic properties, development of designs, construction of shafts, and other generic and site-specific technical activities.
NRC prelicensing consultation includes the preparation of media-l specific and site-specific technical positions and documented technical meetings. As DOE progresses into site characteriza-tion, and as identified generic issues are resolved, the focus of N R C's review will shift from being predominately generic j
to site specific.
REVIEW OF SITE CHARACTERIZATION PLANS DOE's site characterization plans (SCPs) for three potential sites for the first repository will be reviewed in the FY 1987-1988 period, and NRC will prepare a site characteri-zation analysis for each site. As required by the NWPA, the SCPs will be updated semiannually until a site is selected (1991).
37
Nuclear Material Safety and Safeguards Programs LOW-LEVEL WASTE MANAGEMENT AND URANIUM RECOVERY PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 2,145
$ 2,800
$ 2,470
$ 1,720 (Staff)
(66)
(56)
(54)
(52)
The Low-Level Waste Management Program includes development of regulatory guidance for implementing 10 CFR Part 61 regula-tory requirements at existing and new near-surface land disposal sites, and for alternatives to conventional shallow land disposal practices; providing assistance to states in their development of new waste disposal facilities; reviewing and processing licensing actions as necessary to ensure continued safe operation of cur-rently operating commercial disposal facilities; and other efforts to assist states and compacts in their implementation of the LLRWPAA.
The Uranium Recovery Prc. yam involves the licensing of those facilities under agency jurisdiction that are engaged in uranium extraction activities (other than conventional mining) and ore milling activities; the modification and development of rules that are consistent with the Environmental Protection Agency (EPA) rules for regulating mill tallings; and approval, on a site-by-site
- basis, of each licensee's plan for disposal of mill tailings to meet requirements for public and environmental protection. In addition, the NRC must review, for concurrence and licensing, the actions taken by the DOE in their Uranium Mill Tallings Remedial Action Program.
The decrease in resources between FY 1987 and FY 1989 is caused by the time phased resource requirements to implement actions directly or indirectly associated with the LLRWPAA.
DISPOSAL OF LOW-LEVEL RADIOACTIVE WASTE On January 15, 1986, the President signed into law the LLRWPAA.
Under this law, the NRC is given additional responsibilities in the following areas: defining low-level wastes; licensing the Federal disposal of commercial low-level waste greater than Class C; granting emergency access to regional disposal facill-ties; providing regulatory guidance on alternative disposal methods; reducing the license review time; and establishing regulatory standards for wastes below regulatory concern.
38
m Nuclear Material Safety and Safeguards Programs Regulatory guidance continues to be developed for existing Part 61 requirements, in particular those requirements per-talning to waste form and packaging, waste classification, siting, monitoring and closure. Alternative methods for LLW disposal are being identified in order to be able to provide guidance on licensing information requirements. The NRC is preparing detailed plans to ensure review of license applica-tions and the accompanying environmental reports within a 15-month period. Working with EPA, the NRC is exploring
~
approaches to disposal of wastes containing both radioactive and other hazardous constituents which meet the requirements of both agencies.
An amendment to Part 61 (Licensing Requirements for Land Dis-posal of Radioactive Waste) is being developed to establish financial arrangements for long-term care of disposal sites.
A proposed rule is to be published in FY 1987 and development j
of a final rule will continue in FY 1988. Criteria are also being developed for evaluating requests for transfer of sites to the jurisdiction of the Federal government, as provided for under the NWPA.
To ensure prompt and efficient implementation of 10 CFR 61 regulatory requirements applicable to low-level wastes currently being shipped to commercial low-level waste ' disposal sites, re-views of topical reports on waste solidification processes, waste classification systems and improved disposal containers.will continue at a rate of two per year.
LICENSING URANIUM RECOVERY FACILITIES Approximately 80 licensing reviews per year in FY 1987, FY 1988, and FY 1989 will be completed for uranium recovery facilities.
These licensing reviews include safety and environmental eval-uations of applications for new licenses, as well as applica-tions for amendments to or renewal of existing licenses for uranium mills, heap leaching facilities, ore-buying stations, commercial solution mining and uranium extraction research and development projects.
To ensure protection of the public health and safety it is neces-sary to review approximately 100 licensee monitoring and agency inspection reports per year and to assess the need for improve-ments in regulatory guidance and licensee performance.
Congress has mandated that the agency revise Part 40 of the re-gulations (Domestic Licensing of Source Material) to conform to final EPA standards (40 CFR 192).
This rulemaking is focusing 39
Nuclear Material Safety and Safeguards Programs on groundwater protection from radiological and chemical hazards at mill tailing sites. A proposed rule was published in FY 1986, and publication of a final rule is planned for FY 1987. A program to monitor implementation of the Part 40 revisions at mill tailings sites will be initiated in FY 1988.
URANIUM MILL TAILINGS REMEDI AL ACTION PROGRAM As required by the Uranium Mill Tailings Radiation Control Act, reviews will be conducted of the remedial actions that will be taken by DOE at 24 mill tailings sites and several thousand contaminated properties located near the sites.
Before the remedial actions can begin, the NRC must review and concur with the DOE plans for the long-term stabilization of mill tailings for inactive mills which generated mill tailings due to Atomic Energy Commission ( AEC) and/or DOE activities. The program of remedial action for these mill tailings sites in-volves approval of plans to assure adequate long-term control of radiation or radioactive releases from the sites, protec-tion of groundwater, and eventual licensing of completed sites for long-term custody and maintenance. The Act's provision for early NRC review and approval of DOE plans helps ensure that the custody and care of the site can be licensed by NRC, thereby precluding costly delay or rework by DOE.
The greatest NRC involvement is expected to occur during the 1986-1990 period.
TECHNICAL ASSISTANCE TO STATES Technical assistance on low-level waste disposal and licensing of uranium recovery facilities will continue in FY 1987-1989.
With respect to low-level waste, NRC provides licensing tech-nical assistance to the sited states of Nevada, South Carolina and Washington.
To ensure that the requirements of the LLRWPAA are met, technical assistance is being provided to several nonsited host states and the Compacts. This assistance concentrates on the regulation of siting and design aspects of disposal facility development. With regard to uranium recovery, technical assistance will be provided to Agreement States upon request on specific technical licensing matters. Two or three requests for such assistance are anticipated each year.
40
Nuclear Material Safety and Safeguards Programs MANAGEMENT DIRECTION AND SUPPORT PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual '
Estimate Estimap Estimate Funds 0
$ 100
$ 100
$ 100 (Staff)
(27)
(27)
(27)
(25) i The resources requested for the Management Direction and Support Program provide for the overall policy guidance and management direction of the NMSS Programs by the Office Director, and the Regional Administrators. Requested resources also provide for technical and administrative support to the Office Director and the Regional Administrators. The staffing decreate in FY 1989 reflects a reduction in that administra-tive support.
I i
l 41
Nuclear Material Safety and Safeguards Programs
\\
i This page intentionally left blank l
42
m
_.m..
m I
INSPECTION AND ENFORCEMENT
)
i l
.- m
--&w.-----
g-m-
.w-w--w-aw y-my--
eer
.,mmwwm,--y-w
-ww-y-way--awqw
INSPECTION AND ENFORCEMENT l,
PROGRAM SUPPORT LEGEND:
F 198 m
$ 7,000 oyn:/
STAFF 700 3
600 500 h 400 y
NN x
w k\\
^
^
0
'S $~.if$'
l0
~
INSPECTION AND ENFORCEMENT PROGRAMS (Dollars are in thousands, except in text, where whole dollars are used; staff numbers are in full-time equivalents.)
Total FY 1988 estimated obligations................................$104,880
-Total Funds and Staff FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Salaries and Benefits
$ 55,391
$ 58,220
$ 59,610
$ 54,530 Program Support 15,915 16,001 18,300 16,900 Administrative Support 17,866 20,565 21,320 21,570 Travel 5,226 5,785 5,650 5,925 Total Obligations
$ 94,398
$100,571
$104,880
$ 98,925 (Staff)
(1,131)
(1,136)
(1,114)
(1,088)
Program Support Funds and Staff The inspection and Enforcement staff and program support funds are allocated to the major programs shown below.
The program support funds are primarily for contractua!
work by the Department of Energy laboratories and com-mercial contractors. The narrative that follows describes the programs and the reasons they are needed.
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds Staff Funds Staff Funds Staff Funds Staff Reactor inspections $ 5,311 670 $ 5,725 682 $ 6,115 674 $ 5,575 657 Vendor and Quality Assurance 1,314 53 1,455 49 1,635 46 1,235 42 Enforcement, Tech-nical Support, incident Response and Licensing 6,103 157 5,315 143 6,330 136 5,800 133 Fus! Cycle and Mat-erials inspections 913 85 985 92 1,525 91 1,525 91 Specialized Tech-nical Training 2,274 19 2,521 23 2,695 24 2 765 24 Management Direc-tion and Support 0
147 0
147 0
143 0
141 TOTAL
$15,915 1,131 $16,001 1,136 $18,300 1,114 $16,900 1,088 43 l
., - - -.. - - _. - _ -.. ~, -.. ~
inspection and Enforcement Programs DESCRIPTION OF PROGRAMS Inspection and Enforcement (IE) Programs are conducted to en-sure that facilities and materials under agency jurisdiction are designed, constructed, and operated or used safely and in com-pliance with agency regulations. Prompt enforcement action is taken against licensees who do not comply.
The IE Programs are conducted by the Office of Inspection and Enforcement and the agency's five Regional Offices, which are located in King of Prussia, Pennsylvania (Region 1); Atlanta, Georgia (Region 11);
Glen
- Ellyn, Illinois (Region Ill);
Arlington, Texas (Region IV); and Walnut. Creek, California (Region V).
The headquarters staff has responsibility for: (1) inspection policy and program development; (2) assessment of inspection program content and implementation by Regional Offices; (3) appraisal inspections to determine licensee and regional per-formance; (4) enforcement actions referred by Regional Offices; (5) evaluation of licensee events and analysis of indicators of individual plant safety and regulatory performance; (6) response to incidents by managing the agency's Operations Center; (7) emergency preparedness, including coordination with the Federal Emergency Management Agency (FEMA) and emergency prepared-ness licensing of reactors; (8) development and licensing of quality assurance programs; (9) development and implementation of the vendor inspection program; (10) specialized technical training; (11) technical support to the Regional Offices, and (12) management and participation.in specialized Headquarters /
Regional team inspections.
l The majority of the program staff are located in the Regional Offices. The Regional inspection staff has responsibility for:
(1) conducting inspections at reactors, fuel facilities, and l
l materials licensees, for the transport and storage of radio-active waste; (2) initiating enforcement actions; (3) con-
~
ducting systematic assessments of licensee performance; i.
(4) performing emergency preparedness annual reviews; (5) responding to incidents by dispatching personnel to the l
site in question; and (6) providing technical support to the l
Office of Investigations.
Implementation of the reactor inspection program is conducted under two basic formats:
(1) prescribed scheduled routine inspections designed to evaluate the licensee's activities, recognizing that the licensee has primary responsibility for protection of the public health and safety; and (2) unscheduled, reactive inspections to follow up on problems or to assess licensee compliance with special requirements imposed as a result of the evaluation of events at other reactor plants.
l l
44 l
inspection and Enforcement Programs Response to incidents is carried out jointly by headquarters and the regions. At headquarters, the agency's Operations Center is continuously staffed to receive calls of reportable events; to determine the appropriate immediate action; and to pass appro-priate items to the regions for followup. When necessary, the Center is activated and an emergency response team from the region is dispatched to the site to monitor and evaluate the situation and provide advice and information to the licensee, the Federal Emergency Management Administration (FEMA), state and local government officials, other Federal agencies, and the public.
l 1
l 45
.~
Inspection and Enforcement Programs 1
REACTOR INSPECTIONS PROGRAM l
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 5,311
$ 5,725
$ 6,115
$ 5,575 (Staff)
(670)
(682)
(674)
(657)
The Reactor inspections Program consists of:
(1) developing, conducting and ' assessing inspection programs for nonpower and power reactors under construction and during the preoperational-testing, startup, and operational phases; (2) developing and t
coordinating third-party inspection programs and agreements; (3) reviewing emergency preparedness license applications and modifications; and (4) providing radiological monitoring support services to Agreement States and other states. The program is i
performed by resident, headquarters and region-based inspec-tors. Resident inspec: tors live near the reactor sites and their offices and duty stations are located on the site. They are assigned at reactors under construction and at operating reactor sites. While the resident inspectors serve in a variety -of inspection functions as Nuclear Regulatory Commission (NRC) representatives, their primary job is to observe, evaluate and i
report on the adequacy of licensee n'uclear safety activities on a day-to-day basis. The region-based inspectors supplement the basic activities carried out by resident inspectors through a variety of program and technical inspections which afford an indepth look at licensee programs. The FY 1988 program support increase will provide contractual assistance for Safety System Functionality inspections and Safety System Outage _ Modification Inspections. The FY 1989 resource decrease is due to work-load decreases in reactors in construction, preoperational
- testing, and start-up testing; and completion of fire p ro-tection inspections in FY 1988. Although the number of plants i'
in construction and preoperational testing is declining, the level of inspection effort per plant is not being reduced.
i i
l t
i l
i l
46 a
r
-.e.,
s rr..,,._.
,m,._.,,.
,.,_.,.,,_,p__m
,,,m, p,,
m.
_,,,7,
inspection and Enforcement Programs Power Reactor Workload Forecast End-of-Year FY 1986 FY 1987 FY 1988 FY 1989 4
Actual Estimate Estimate Estimate Reactors Under Construction 6
3 3
2 i
Reactors in Preoperational Testing 13 7
3 1
Subtotal Construction 19 10 6
3 Reactors Licensed or Ready i
for Low Power Operation 101 110 114 117 Totall/
120 120 120 120 1/ Excludes five deferred plants which require only minimal inspection resources.
RESIDENT INSPECTORS Resident inspectors at reactors under construction apply general l
experience in construction activities to assure that installa-tions of equipment ~and structures are in accordance with design requirements and quality assurance procedures. The resident in-spector at construction sites has frequent contact with manage-ment personnel from the utility. The work is accomplished through review of procedures, direct observation and audits of licensee quality control. The resident inspector may also parti-cipate in agency hearings, licensing meetings and public discus-sions. The agency assigns two resident inspectors at each active construction site.
Resident inspectors for operating sites are generalists who con-centrate on day-to-day licensee operations, event followup, and licensee management and staff performance. In addition, they coordinate on-site activities of the various agency offices and participate in emergency exercises. They also serve as the agency contact with local officials, the press and the public. A second resident inspector is assigned at plants in the preopera-tional testing phase to allow for additional coverage during the critical period when utility construction and associated quality assurance and quality control inspections are being completed, preoperational testing is in progress, hearings are being con-ducted and when last minute allegations may be introduced.
Each plant in preoperational testing has four resident inspectors, I
two construction and two operations. This increased onsite in-spection coverage provides additional support for identifying, evaluating and resolving issues, and will help reduce the pro-bability of licensing delays. Two residents are assigned to all multi-unit operating sites.
In FY 1988, the assignment of a second resident inspector to almost all single unit operating sites will be completed. This additional coverage will provide better continuity and increased direct inspection of important 47 1
i
.--n
-~
^ ' '
Inspection and Enforcement Programs areas such as licensee maintenance and surveillance activities.
The budget provides approximately 160 resident inspectors each year in FY 1987 through FY 1989.
REGION BASED SPECI ALISTS The majority of inspections are indepth, specialized technical inspections carried out by region-based specialists in the areas of civil, mechanical, and electrical engineering; instrumenta-tion; welding; nondestructive examination; quality assurance; plant operations; systems surveillance; maintenance; modifi-cations; inservice inspection; fire protection; training; refueling; radiation protection; emergency planning; environ-mental protection; management systems; security; and safeguards.
Region-based specialists are responsible for evaluating the corrective measures taken by the utilities to resolve certain types of identified problems. To augment these region-based specialists, highly specialized technical assistance is pro-vided through contractual assistance. These contracts include state environmental monitoring at reactor sites and other confirmatory independent measurements.
SAFETY SYSTEMS FUNCTIONALITY INSPECTIONS AND SAFETY SYSTEM OUTAGE MODIFICATION INSPECTIONS Safety System Functionality inspections and Safety System Outage Modification Inspections represent emerging operating reactor inspection approaches. As the result of the Davis-Besse and other significant operational events, it became evident that there was a need to address the functionality of reactor systems and components. A Safety System Functionality inspection is an indepth engineering review of the design, configuration, main-tenance, testing and operation of systems, their components, and their supporting systems. A Safety System Outage Modification Inspection is also an indepth engineering examination of system functionality, but it is oriented towards the safety impact of various modifications which are made to several systems during the course of a reactor outage. This review centers on how the I
modification has altered the original design considerations and safety margins, the quality of the modified systems, as-built, and the adequacy of full functional testing of the modified sys-tems. Safety Systems Functionality inspections and Safety System Outage Modification inspections will be conducted to provide information on the effectiveness of the institute of Nuclear l
Power Operations (INPO)
Evaluation
- Program, adequacy of implementation of regional inspections (including any needed changes to regional programs), and direct insight into licensee nuclear safety performance. These inspections are conducted by a team of specialists that include both operations and design-l t
48
inspection and Enforcement Programs oriented personnel. -Six or more - of these inspections will be conducted in FY 1987 and 10 to 15 in each of FYs 1988-1989.
The FY 1988 resource increase will provide additional con-tractual support for Safety System Functionality inspections and Safety System Outage Modification inspections.
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE A program for the systematic assessment of licensee perfor-mance is aimed at improving both NRC regulatory efforts and licensee performance in the construction and operation of nuclear - power plants. The program involves collecting infor-mation on a periodic basis regarding the overall performance of a licensee in a number of important areas (e.g., management involvement in assuring
- quality, enforcement history, and reporting and analysis of events).
Emphasis is placed on understanding the reasons for licensee performance in these areas, sharing the understanding with the licensee, and then focusing agency inspection accordingly.
e 49
inspection and Enforcement Programs VENDOR AND
-QUALITY ASSURANCE PROGRAM FY 1986
-FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 1,314
$ 1,455
$ 1,635
$ 1,235 (Staff)
(53)
(49)
(46)
(42)
The Vendor Program focuses on architect-engineering firms, nu-
-clear steam system suppliers and companies producing the piping, valves, pumps, electrical equipment, and instrumentation for re-actor safety-related systems. The Quality Assurance Program in-tegrates agency activities for quality assurance licensing, inspection, standards and research, recognizing that substan-tive improvements in quality must come from the nuclear industry itself, with NRC efforts oriented to the prevention and early detection of major quality problems.
VENDOR PROGRAM Some reactor operational safety issues have resulted over the past several years from the breakdown of vendor quality assur-ance programs, failure of vendors to adequately convey mainte-nance procedures to licensees, and improperly certified (and in some cases fraudulent) work and materials provided to major vendors by second-and third-level vendors. Specific examples include:
(1) the Davis-Besse loss of auxiliary feed water event, (2) San Onofre check valve and water hammer event, (3) deficient Telemecanique S-R circuit breakers, (4) falsifi-cation of documents regarding calibration of equipment used to test steam generator tubes, and (5) problems related to Westing-house's Engineering Safeguard Actuation System. Major problems throughout the industry can be avoided if these types of issues are properly considered and resolved.
The Vendor Program is conducted to improve reactor safety by focusing on operational reactor safety issues, assessing the potential generic implications of vendor deficiencies and emphasizing licensee responsibilities for their vendor suppliers. Approximately 120 inspections will be conducted each year in FYs 1987-1989.
The principal inspection categories are: (1) reactive inspections at vendor facilities and reactor sites in response to reports of defects and noncompliance with the regulations (submitted in accordance with Part 21 of Title 10 of the Code of Federal Regulations), adverse reports on conditions of construction (submitted in accordance with 50 l-
Inspection and Enforcement Programs Part 50.55 (e) of Title 10 of the Code of Federal Regula-tions) and allegations by workers and the public; (2) inspec-tion of equipment qualification to ensure compliance with 10 CFR 50.49; (3) reactive and routine inspections of the quality assurance programs of architect-engineers and nuclear steam system suppliers, technical information provided to reactor licensees on vendor-supplied equipment, and third party surveys such as those conducted by the American Society of Mechanical Engineers in accordance with the Boiler and Pressure Vessel Code; and (4) inspections to follow up on known technical issues.
Contractor assistance funds permit the agency to: conduct more detailed technical inspections at vendor facilities, concen-trating on safety impact and feedback of information directly to plant operations; and provide the capability to hire experts in specialized areas.
The FY 1988 program support increase will provide tec.hnical assistance to complete the equipment qualifi-cation inspections on schedule.
The staff decrease in FYs 1988-1989 reflects the expected completion of the initial equipment qualification inspections.
QUALITY ASSURANCE PROGRAM A revised program for quality assurance is being developed and carried out as recommended in "A Report to Congress on improv-ing Quality and the Assurance of Quality in the Design and Con-struction of Nuclear Power Plants," NRC Report N U R EG-1055.
The Report to Congress identified a number of areas in which current agency practices should be altered to increase the like-lihood of achieving quality and the assurance of quality in design and construction. While the focus of the report was on construction, many of the corrections will be applied to reactor operations. These changes include: (1) reductions in agency prescriptiveness and greater emphasis on quality program per-formance and end products; (2) reduction or alteration of requirements which have resulted in attempts to inspect quality into a plant rather than to place reliance on those responsible for a project or plant operations; and (3) methods to resolve quality assurance contentions earlier in the licensing process so as to avoid the necessity for considering a large number of l
allegations in the final stages of a project when the conse-l quences of delay are much greater. These changes will also make the nuclear licensing and regulatory process more predictable and stable. Revisions io the quality assurance inspection pro-g ram are being undertaken and will be completed in FY 1988.
Support will also be provided in FYs 1987-1989 to the Nuclear Material Safety and Safeguards Programs in the review and over-sight of the quality assurance programs for Department of Energy (DOE) site characterization activities.
In
51
i i
Inspection and Enforcement Programs ENFORCEMENT, TECHNICAL SUPPORT, INCIDENT RESPONSE AND LICENSING PROGRAM FY 1986 -
FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 6,103
$ 5,315
$ 6,330
$ 5,800 (Staff)
(157)
(143)
(136)
(133)
The purpose of the Enforcement Program is to protect the public health and safety by insuring that licensees comply with agency regulations. The Technical Support Program provides necessary assistance to the conduct investigations, inspect problem facilities, follow up on allegations, analyze licensee events for their safety significance and the appropriateness of corrective actions, communicate generic problems to staff and licensees, analyze indicators of individual plant safety and regulatory performance and maintain fixed and mobile laborator-ies (e.g., the Non-Destructive Examination van). The incident Response Program affords assurance that the agency is pre-pared to respond to incidents, including 24-hour staffing of the agency's Operations Center. The Licensing Program focuses on reviews of licensees' emergency preparedness activities.
The FY 1988 staff decrease is due to realignment of resources for technical support to investigations based on actual experi-ence and fewer initial emergency preparedness licensing reviews.
The FY 1988 program support increase will provide upgrades to the incident response capability and accomodate anticipated requirements for problem facilities, such as the Tennessee Valley Authority (TVA). The FY 1989 resource decrease is due to reduced TVA and emergency preparedness initial licensing requirements.
ENFORCEMENT The Enforcement Program is carried out to ensure compliance with regulations and license conditions; to obtain prompt cor-rection of noncompliance; to deter further noncompliance; and to encourage improvement of licensee performance. The en-forcement program employs a series of sanctions that are es-calated or mitigated according to the seriousness of the non-compliance and the past history of licensee performance.
Notices of violation, civil penalties and orders are issued, as necessary, to assure safety and compliance.
52
Inspection and Enforcement Programs SUPPORT FOR PROBLEM FACILITIES, ALLEGATIONS AND INVESTIGATIONS Expertise is needed to assist in inspections and investigations.
An investigation into the cause of the event at Davis-Besse and problems at the TVA sites have exemplified the need for re-sources in this area. Problems at material licensees have re-quired augmented effort. Special inspections are also required to assist in investigations responding to allegations of safety and safeguards violations at nuclear facilities.
LICENSEE EVENT ANALYSIS, GENERIC COMMUNICATIONS AND PERFORMANCE INDICATORS Licensee event reports are analyzed to identify problems with potential safety significance which may be common to specific types of plants.
Bulletins and information notices are then prepared to inform licensees, vendors and the agency staff of these problem areas, and to recommend or require corrective ac-tions. More than 10,000 event reports are reviewed and approxi-mately 100 communications are issued annually. Indicators of individual plant safety and regulatory performance are analyzed for trends. The trending results are input into a management decision process to determine what NRC actions are appropriate in response to lagging performance.
INCIDENT RESPONSE PROGRAM The new NRC Operations Center, which opened in FY 1985, pro-vides an improved environment for the agency's response to incidents. In FY 1988, systems and programs which support reactor safety assessment, protective measures, information management, response training, and communications are being upg raded.
Program Support funding will provide continued maintenance of the Center, improved response tools for en-hancing analytical capabilities and improved emergency communi-cations using data from the licensees emergency response facilities.
1 EMERGENCY PREPAREDNESS REVIEWS Nuclear power plant applicants and licensees are required by agency regulations (Part 50 of Title 10 of the Code of Federal Regulations) to develop and implement onsite and offsite plans for taking protective actions in the event of reactor accidents.
The plans for a given reactor site generally involve those pre-pared by the utility for application to onsite areas and those prepared by state and local governmental authorities for areas 53
_.e--.-,
--r y -
F
--. _ __~
inspection and Enforcement Programs beyond the plant boundary. Emergency preparedness activities for NRC include: (1) developing licensing policy and guidance; (2) reviewing and evaluating onsite emergency plans and proce-dures to. provide input for Safety Evaluation Reports on appli-cants' emergency preparedness capabilities; (3) reviewing modi-i fications -to existing licenses; and (4) coordinating with FEMA on findings and - determinations resulting from their review of offsite emergency preparedness of state and local governments as it affects licensed nuclear facilities.
1 l
t 1
f 54 w
~ ~ -
e w
+
.-,-,-v----
,-.n.,.,,-,,.-_.,,,,m-r,~.
,e
-~
n,-~~--,,.mn,---,---.
,.-,----,-,n,r e---.,,
+,s_-+,
inspection and Enforcement Programs FUEL CYCLE AND MATERI ALS INSPECTIONS PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 913 985
$ 1,525
$ 1,525 (Staff)
(85)
(92)
(91)
(91)
The Fuel Cycle and Materials Inspections Program provides in-spections for the processing of nuclear materials at fuel cycle facilities, the use of nuclear and radioactive material at medical, academic and industrial institutions, and the trans-port of such materials.
FUEL FACILITIES INSPECTIONS Health and safety inspections will be conducted at 68 fuel facilities each year in FYs 1987-1989. These facilities include uranium
- mills, fuel storage facilities, uranium conversion facilities, and fuel production plants.
In addition, physical
- security, emergency preparedness and material control and accounting inspections will be performed at 11 fuel facil-ities which currently process enriched uranium.
Inspections at fuel facilities help to ensure that unsafe conditions involving unnecessary and harmful radiation exposure to employees and the public do not develop, that materials are properly controlled to prevent a nuclear criticality accident, and that security and material control practices are adequate to prevent diversion or theft of fissionable materials.
l MATERI ALS INSPECTIONS Approximately 2600 onsite radiological safety inspections of ap-proximately 9000 materials licenses will be conducted each year in FYs 1987-1989 to help ensure that unsafe conditions involving unnecessary and harmful radiation exposure to employees and the l
public do not develop. Nuclear materials are used by firms deal-l ing with source, byproduct, or special nuclear materials in nuclear medicine, radiography, industrial testing, well-logging, and academic research. Inspections of transportation and the handling and storage of radioactive wastes are also required.
In addition to routine periodic inspections of licensees, the requested resources will provide for the evaluation and follow up on actions such as licensee-reported incidents and medical misadministrations.
55
Inspection and Enforcement Programs The FY 1988 funding increase will provide improvements to the effectiveness of the materials inspection program.
DECOMMISSIONING AND CLOSEOUT RADI ATION SURVEYS Decommissioning and closeout radiation surveys at materials licensees and fuel facilities will be conducted as needed to de-termine whether the property can be released for unrestricted use. These determinations are based on independent radiation surveys to ascertain whether the licensee has successfully de-contaminated its property as it has stated in its report to the NRC.
56
\\
- ~..
N Inspection and Enforcement Programs SPECI AllZED TECHNICAL TRAINING PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 2,274
$ 2,521
$ 2,695
$ 2,765 (Staff)
(19)
(23)
(24)
(24) 1 The Specialized Technical Training Program is managed by the i
' Office of Inspection and Enforcement and operated at the i
Technical Training Center near Chattanooga, Tennessee. This program provides training to region-based and resident inspec-tors, other agency technical staff, and state and foreign gov-ernment employees. Courses are offered in design, technology 1
and operation of pressurized and boiling water reactors, and in other specialized areas of reactor construction, health physics, quality assurance, and operator license examiner training.
Training is conducted in conventional classrooms, scientific laboratories, nuclear power plants, and reactor control room l
simulators. This specialized training provides added technical experience for the staff to perform inspections and safety re-views for
- reactors, fuel cycle facilities and materials-use activities.
j increases in resources are based on increased demands for courses in engineering and inspection fundamentals as well as the need to keep all NRC inspectors abreast of new developments in boiling water reactor and pressurized water reactor technol-j ogy, radwaste, health physics and quality assurance. Reactor simulator usage will be increased for inspector and operator license examiner training.
6 4
1
+
i j
57 i
~ - - -
Inspection and Enforcement Programs
.4 MANAGEMENT DIRECTION AND SUPPORT PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
0 0
0 (Staff)
(147)
(147)
(143)
(141)
The resources requested for management direction and support provide for the overall policy guidance and management direction of the IE programs by the Office Director and the Regional Administrators. Requested resources also provide for technical and ' administrative support to the Director and Regional Admin-istrators.
The FYs 1988-1989 staff decrease results from expected efficiences in operations.
58
i I
NUCLEAR REGULATORY RESEARCH l
3
NUCLEAR REGULATORY RESEARCH PROGRAM SUPPORT LEGEND:
F 198
'/ / FY 70.000 e
8 60.000 m
W,000
,7 k 40.000 b
I 30.000
\\
\\
m 000 10.000
^
M 0
++~ h d' s$Y STAFF 100 80 60 2
/ / / s,r
NUCLEAR REGULATORY RESEARCH PROGRAMS (Dollars are in thousands, except in text, where whole dollars are used; staff numbers are in full-time equivalents.)
Total FY 1988 estimated obligations.............................. $119,675 Total Funds and Staff FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Salaries and Benefits
$ 11,674
$ 11,070
$ 11,010
$ 10,300 Program Support 107,397 95,800 103,600 109,500 Administrative Support 4,188 4,240 4,550 4,930 Travel 526 575 515 530 Total Obligations
$123,785
$111,685
$119,675
$125,260 (Staff)
(198)
(180)
(172)
(172)
Program Support Funds and Staff The Nuclear Regulatory Research program support funds and staff are allocated for major programs, as shown below. The program support funds are primarily for con-tractual work by Department of Energy laboratories, priva te contractors, nonprofit organizations (universities, foundations, etc.),
and grantees.
The narrative that follows describes the programs and the reasons they are needed.
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds Staff Funds Staff Funds Staff Funds Staff Reactor System r
Safety
$ 58,962 66 $ 44,535 60 $ 49,850 57 $ 53,850 57 Engineering Safety 39,453 49 43,110 43 42,350 41 44,250 41 Waste Management 4,598 17 5,800 19 9,000 18 9,000 18 Regulatory Applications 4,384 44 2,355 36 2,400 34 2,400 34 Management Direction and Support 0 22 0 22 0 22 0 22 Totals
$107,397 198 $ 95,800 180 $103,600 172 $109,500 172 l
59
Nuclear Regulatory Research Programs DESCRIPTION OF PROGRAMS The programs of the Office of Nuclear Regulatory Research (RES) are an essential and integral part of the regulatory process.
Safety research supports nuclear regulation by providing defensible technical bases for regulatory action to ensure public health and safety. The program emphasizes early identification of potential problems with operating reactors, where problems continue to arise, and the development of criteria for the safe disposal of nuclear waste. The problems and corresponding topics of research are programatically grouped into six major areas:
1.
Aging and Degradation in Power Plants A large number of reactor plants have been operated for a significant fraction of their licensed life.
Corrosion, radiation embrittlement, thermal aging embrittlement, and fatigue have raised specific questions about the continued safety and viability of many of these plants; in particular, there are concerns about the integrity of the primary coolant pressure boundary and safety systems components.
Widespread and potentially serious problems have occurred.
These have included cracked piping at boiling water
- reactors, steam generator tube degradation, defective valves, relays and circuit breakers, and inadequate means for detecting and characterizing flaws in reactor vessels and piping. Although many of these questions are being re-solved by research and regulatory action, similar questions are likely to continue to arise. Further, as the operating plants advance in age, there may be other presently un-recognized degradation mechanisms occurring. Therefore, research needs to be done to identify latent problems and incipient failures before they occur.
2.
Complex Operational and Thermal-Hydraulic Transients Previous research on complex operational and thermal-hydraulic transients has been largely oriented toward large-break loss-of-coolant accident (LOCA) issues and has reflected an underlying assumption that thermal-hydraulic transients generally could be adequately characterized by a limiting case, the large-Dreak LOCA. Complex transients arising from equipment malfunctions and small-break LOCAs which have occurred have had serious safety implications for a
broad class of reactors.
Since reactors are not standardized, and because the events which have occurred so far may be precursors to much more serious events which could result in core damage, direct extrapolation of the safety significance of a given accident is not readily achievable.
Therefore, development and maintenance of complex thermal analysis codes, as well as experimental analysis of potential accident sequences and verification of computer codes, are required.
60
Nuclear Regulatory Research Programs 3.
Consequences and Risk from Severe Accidents The Three Mile Island 2 (TMI-2) accident alerted the Nu-clear Regulatory Commission (NRC) to the need to conduct severe accident research to provide information for the evaluation and possible modification of its rules on emer-gency
- planning, reactor siting,
and equipment qualification / survivability.
It is necessary to determine how containments respond to loads from hydrogen burning or detonation, and loads from core molten materials falling onto the concrete basemat resulting in possible basemat penetration, generation of combustible gases, and/or steam explosions. Initial requirements for a revised radioactive source term estimate have now been completed and an accom-panying severe accident risk and consequences document is being prepared.
The research supporting these documents has revealed several areas of significant uncertainty such as the chemical form of radioactive iodine which would re-sult from a severe accident and the potential for radionu-clide revaporization. Additional research is needed to re-solve these and other uncertainties.
4.
Risk And Reliability Research Assessment of the probability and consequences of severe accidents remains an important objective of NRC. Significant advances have been made in r scent years in the development and, to some degree, in the applications of probabilistic risk assessment (PRA) techniques, and in research on se-vere accidents. Much of the FY 1986-1987 effort has been devoted to research for the assessment of the risk of severe accidents and their consequences in six reference plants (NUREG-1150), the development of computer-based, user-friendly systems for use in licensing and inspection activities, the evaluation of a
lifecycle-oriented reli-ability program for use by utilities to enhance the re-liability of equipment and operations important to safety, and the initiation of a methodology development activity to provide quantitative risk-based plant performance indi-cators and alert levels. The FY 1988-1989 effort will be directed to (a) adding one Combustion Engineering and one Babcock & Wilcox plant to the list of reference plants and completing external events analyses on three of the refer-ence plants, (b) augmenting the NUREG-1150 information by incorporating results of current severe accident research into areas of uncertainty discussed in the previous sec-tion, and incorporating the risk from external events such as earthquakes, floods, and fires, and the insights gained from the Chernobyl accident, (c) adapting and field test-ing existing risk / reliability me+hodologies in plant in-spection, status, and operations management, and (d) aug-menting and testing risk / reliability methodologies to enable the agency to resolve unresolved and generic safety 61
~.. _.
Nuclear Regulatory Research Programs issues, and to assess advanced / standardized reactor designs based on state-of-the-art proven technologies.
i S.
Seismic Analysis With the continuing improvement 'in understanding geology and seismology, a number of older plants have been identi-fled as being designed for seismic hazard levels that are below current criteria. Although there are considerable seismic safety margins in present reactor designs, there
+
is an urgent need for improved bases and methods for pro-perly characterizing seismic hazard for plants, especially those in the Eastern U.S., and for well-validated methods and data bases for seismic analysis that can be used to reassess the older operating plants to determine whether 4
]
adequate safety margins do exist and to quantify these margins.
6.
Nuclear Waste Disposal The research programs in this area are required to develop the methods and data bases needed to evaluate the adequacy of applicants' submissions to meet regulatory requirements l
required by law for the disposal of both high-level waste (HLW) and-low-level waste (LLW). The issues faced here are at the forefront of science in that society has never before required that hazardous materials be safely isolated for the very long time periods involved. The basic information and analytic methods must be improved to allow the Commission to make the required independent assessments of safety that the law mandates.
4 i
The two principal' goals for HLW research are to provide regulatory guidance to the Department of Energy (DOE) so that its licensing application to construct a geologic repository will be complete, comprehensive, and of high quality when submitted to the NRC; and to provide the technical basis needed to perform site characterization /
license reviews of the HLW repository once DOE submits its 1
application.
g The goal of LLW research is to provide the technical bases and analytic tools needed for NRC to carry out its responsi-well as provide guidance to indi-bilities to regulate, as vidual states and -state compacts-under the Low Level Radio-active Waste Policy Amendments Act (LLRWPAA) of 1985, and to develop and support the requisite regulatory base, including facility design, waste form and package design, performance assessments, and long-term monitoring techniques.
The emergence of new technical issues and the existing wide 4
variety of plant designs require continuing research as described i
S2 L
=
Nuclear Regulatory Research Programs in the six major areas above. NRC must therefore maintain tech-nical expertise for future resolution of regulatory issues., in an effort to meet these needs and to maximize productivity,- the Office of Nuclear Regulatory Research is working towards inte-gration of specialized scientific and engineering areas of expertise at selected principal national laboratories. Identify-ing well-defined areas of technical cognizance for each of several laboratories will greatly facilitate the execution and interpretation of research results, and maintain a capability in required technical' areas to respond to anticipated technical operating problems having impacts on safety, t
]
63
Nuclear Regulatory Research Programs REACTOR SYSTEM SAFETY PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$58,962
$44,535
$49,850
$53,850 (Staff)
(66)
(60)
(57)
(57)
The Reactor System Safety Research Program provides the regulatory staff with safety analysis computer codes and reactor transient and accident response data and information on which to base their regulatory decisions allowing for continued safe reactor operations. The program consists of research in thermal-hydraulic transients covering the temperature, energy release or absorption and physical state of the reactor coolant (water);
accident evaluation covering the reactor system response to severe accidents; and risk and reliability methods for determining the probability of accidents and transient events, evaluation of accident consequences, and information on ways to improve safety system reliability. The increase from FY 1987 through FY 1989 reflects funding for the construction and testing of thermal-hydraulic test facilities at the Idaho National Engi-neering Laboratory (INEL) to gather data on the performance of Babcock & Wilcox (B&W) designed reactor safety systems under a wide range of accidents. These facilities will provide: (1) a test-ing capability that is not available in the B&W Multiloop Inte-gral System Test facility; and (2) mformation on which to base future regulatory actions for B&W reactors.
THERMAL-HYDRAULIC TRANSIENTS Continued occurrence of complex transients at operating reactors leads to the concern that there may be likely combinations of equipment malfunctions, operator errors, and system response such that safe shutdown cannot be achieved for some future event. Thus, the emphasis of thermal-hydraulic research is the prevention of severe accidents through understanding of plant behavior during accidents and transients. This information is used to ensure that plant equipment, operational procedures and training are adequate to deal with operating events and prevent serious accidents.
Diversity in plant design and operation and the diversity and complexity of possible accidents and transients make direct experimental testing of all important events impractical. One must depend on verified computer codes to analyze events of interest. Assessment of computer codes is complicated by scaling questions, complexity of systems and thermal-hydraulic processes and the periodic identification of phenomena which need to be simulated. A dual experimental / analytical approach is therefore 64
\\
Nuclear R$gulatory Research Programs used to test the validity of codes. Calculations are supported by comparison with experiments simulating the event aind phenomena of interest.
The Thermal-Hydraulic Transients Program provides verified com-puter codes to the licensing' staff for use in conducting safety evaluations of nuclear plants for a wide range of possible transients and accidents such as small-break and large-break loss-of-coolant accidents, feedwater-line and steam-line breaks, and overcooling and undercooling transients. These codes are developed and verified.using data from experiments conducted in integral and separate effects test facilities. t The licensing staff uses verified computer codes to independently evaluate plant designs to ensure they ne capable of safely responding to plant transients. This is done" to ensure that analyses performed by reactor vendors or utilitie for licensing submittals are ac-curate and will result irt cper.n ng procedures that ' will prevent serious accidents.
Integral Facilities Regulatory issues frequently arise which relate to the specific L
plant geometry of the major reactor vendors (Westinghouse, Com-bustion Engineering, General Electric, and Babcock & Wilcox).
In the past, many thermal-hydraulic-related issues involving Westinghouse, Combustion Engineering and General Electric reac-tors were resolved with the use of test data from the Semiscale, Loss of Fluid Test (LOFT) and Fully integral Simulation Test (FIST) integral facilities. All these facilities have been re-cently closed and reliance is being placed on foreign integral facilities to resolve issues involving recovery of Westinghouse and General Electric plants from loss-of-coolant accidents (LOCA's) and complex operational transients. Examples of some of these issues include:
plant safety system performance after shearing off several instrument tube lines in a seismic event; full-scale confirmation of cold-leg emergency core coolant injection penetration into ' the core through the downcomer; and full-scale conf;rmation of the capability of upper *-plenum injec-tion to penetrate and cool the core.
The Babcock & Wilcox (B&W) nuclear pla it c
- sic incorporates features which affect its safety performa.ne e 3ays that are significantly different from other pressurized water reactors.
As such, separate experiments must be conducted. Additionally, operational events concerning the B&W-designed reactors have caused a shift in thermal-hydraulic research emphasis to the resolution of regu.atory issues involving reactors of this vendor. These issues include: adequacy of B&W plant small-break LOCA models, based on concerns raised from the TMI-2 accident; evaluation of recent accidents and transients in Davis-Besse and Rancho-Seco; and technical review of the B&W Owners Group rec-ommendations as a result of the safety reassessment of their plants.
65
Nuclear Regulatory Research Programs To address some of these issues, NRC is completing a joint pro-gram with the nuclear industry to study small-break loss-of-coolant accidents, feedwater-line and steam-line breaks, and overcooling and undercooling transients for B&W type reactor plants. The joint experimental program with industry is being performed in FY 1986 through FY 1988 using the Multiloop Inte-gral System Test (MIST) facility in Ohio. During FY 1987, data from these joint program tests will be analyzed.
The regulatory staff has requested a research program to pro-vide additional safety information on accidents (e.g.,
those mentioned above) not being covered by the testing in MIST to help resolve these and other operational problems being experienced at B&W reactors. The budget request includes fund-ing for such a program. This program will involve fabrication of two additional test facilities which will permit NRC to gather data on the performance of B&W safety systems under a wide range of accidents. One of these test facilities will be an improved scale integral representation of a B&W reactor system. The other will be a large-scale sector of a B&W steam generator.
These facilities will be constructed at Idaho National Engineering Laboratory (INEL) as part of the integra-tion of thermal-hydraulic expertise at that laboratory under the recently established Thermal-Hydraulic Technical Inte-gration Center.
Domestic experimental programs studying potential accidents in Combustion Engineering and Westinghouse-designed reactors were completed with the conclusion of the Semiscale program in Idaho in FY 1986. Analysis of the Semiscale results will be completed in FY 1987 and a report issued. With the termination over the past few years of the Loss of Fluid Test (LOFT), Semiscale,.the General Electric and Westinghouse test facilities, there will only be the integral system test facilities for B&W-type reac-i tors remaining in the United States. Design of a Continuing Experimental Capability at the INEL Technical Integration Center will be completed in preparation for construction of an improved l
scale B&W integral facility in FY 1989.
The Upper Plenum Test Facility (UPTF) in Germany and the Slab Core Test Facility (SCTF) in Japan will provide data to help l
resolve thermal-hydraulic regulatory issues such as: the effec-tiveness of upper plenum injection in Westinghouse two-loop l
- plants, resolution, in ful! scale, of the concern that the emergency coolant will Dypass tne core and go out the break, and full scale data on mixing in the downcomer under pres-surized thermal shock conditions. Construction of UPTF was completed in 1985; the experimental program will take place in FY 1986 through FY 1988.
The Rig of Safety Assessment IV (ROSA-IV) program in Japan is studying small-break loss-of-coolant accidents, feedwater-line t
66 l
1 i
Nuclear Regulatory Research Programs and steam-line breaks, and overcooling and undercooling tran-sients at a very large scale with the ability to confirm the large quantity of safety test data from the smaller Semiscale Facility. The ROSA-IV experimental program began in FY 1985 and will continue until FY 1988. N R C's support is a small percentage of the total cost of these programs and is allow-ing us access to data from unique large scale test programs costing over $350 million.
The resulting test data will be used by NRC to assess the capability of its own computer codes as well as those of industry to simulate a wide range of transients and accidents.
Separate Effects Separate effects experiments supply data in areas where a better understanding of specific phenomena is still required to reduce uncertainties and to maintain and improve thermal-hydraulic expertise for use in responding to accidents.
Current issues focus on B&W steam generator performance under both low power (auxiliary feedwater) and full power (main feed-water) operation. Much of the work h currently being done at universities. The specific phenomena being studied include water hammer prevention at the Massachusetts Institute of Technology, B&W simulation at the University of Maryland, and boron mixing at the University of California. Additional work being formu-lated for universities include studies on scaling of phenomena and specialized analysis centers. Computational models will be derived from the results of these research efforts and will be incorporated into the NRC safety analysis codes in FY 1988.
Transient Models and Codes Computer codes are the regulatory tools used to analyze full-scale plant behavior for accident conditions. The major regula-tory issue surrounding the use of such computer codes relates to the codes' applicability, scalability and uncertainty when applied to plant analyses. To resolve this regulatory issue, experimental data most relevant to the geometry and scenario being analyzed are used to verify the computer codes and to improve the modeling of thermal-hydraulic phenomena.
The principal codes developed by NRC are T R AC-PWR and RELAP5 for use by the regulatory staff in the analysis of pressurized water reactor transients, and TRAC-BWR for the analysis of boiling water reactor transients. Major development of the codes is generally complete. Efforts are continuing in the areas of code maintenance, code assessment, and error cor-rections. The Nuclear Plant Analyzer (NPA) allows the licensing staff to perform direct hands-on analyses of regulatory / safety incidents. NRC followup and response to the June 1985 Davis-Besse accident were considerably enhanced and speeded up 67
i I
N_uclear Regulatory Research Programs through rapid analyses at NRC Headquarters of potential conse-quences and mitigative actions performed on the prototype ver-sion of the NPA through remote tie-in to the large computers at the national laboratories. Maintenance of NPA capability devel-oped in previous years will be continued in FY 1988. An intern-ational code assessment and application program was established in FY 1985 and will continue for approximately five years. This program consists of agreements between NRC and e even other countries. The participants have agreed to provide NRC with nuclear plant start-up test data not available from U.S. plants and data from their reactor test facilities in exchange for the use of NRC safety analysis computer codes. The results of this program and the review of DOE laboratory contractor code evaluations will form the basis for any code improvements to be performed in future code versions. Code improvements to NRC's two major thermal-hydraulic safety analysis codes, TRAC and RELAP, resulting from these assessments will be made dur-ing FY 1988.
ACCIDENT EVALUATION The Accident Evaluation Research Program is required to com-plete the technical basis for the closure of severe-accident issues in accordance with the provisions of the Commission's Severe Accident Policy Statement. The ability to predict how radioactive materials are transported and released during postulated reactor accidents lies at the very heart of the regulatory process. The need for and extent of protection of the public from undue risk are measured by careful assessment of possible accidents and the releases of radioactive mate-rials from such accidents. During 1986 the Reassessment of the Technical Bases for Estimating Source Terms (NUREG-0956) was published and the Reactor Risk Reference Document (NUREG-1150) will be issued in early 1987. Both documents together pro-vide the regulatory staff with a technical basis for examining N RC's rules and regulatory practices to determine the need for change. The research supporting NUREG-0956 has identi'ied eight areas of uncertainty for which additional research in-formation is needed. The research to provide this information consists of an integrated program of both in-reactor and laboratory experiments and the development and validation of accident-analysis models and ' codes will be completed in FY 1989. This program has attracted significant financial sup-port from foreign reactor safety programs to share program costs.
68 i
Nuclear Regulatory Research Programs Damaged Fuel This work is required to better characterize uncertainties in issues of core melt progression, in-vessel natural circulation and in-vessel phenomena needed by the Office of Nuclear Reactor Regulation in their Individual Plant Evaluation of all operating reactors for severe accidents.
The work on damaged fuel will continue to provide characteriza-tion of the reactor core during core-melt progression as input for determining the uncertainties in core hydrogen generation,-
fission-product release and behavior, steam explosions and the direct heating threat to containment integrity. In FY 1987 and FY 1988, the work includes one test each year in the Annular Core Research Reactor (ACRR) in New Mexico on melt progression to fuel-melt temperatures and studies of hydrogen generation in the dominant severe accident sequences. Analysis of the data from these experiments and the application of the new knowledge to regulation will continue in FY 1988 and FY 1989. A full-length coolant boildown severe fuel damage test will be per-formed in the Canadian NRU test reactor in FY 1987 to provide needed data on hydrogen generation in severe accidents. This data will be analyzed and reported in FY 1988. Validation of the melt progression (MELPROG) code and the severe core dam-age analysis package (SCDAP) code is required for use in severe fuel damage source term assessment and for benchmarking simpli-fied severe accident safety analysis codes such as the new MELCOR code. MELCOR will be used for future severe accident analyses and specifically to calculate source terms. This vali-dation uses results of German and NRC laboratory work, along with results of the DOE examination of the TMI-2 core and the Electric Power Research Institute (EPRI) tests in the tran-sient reactor test facility (TREAT) test reactor in Idaho.
3 Containment Building Loading i
The Regulatory staff in their Individual Plant Examination of Operating Plants for Severe Accidents require better quantitative estimates of containment building loading with respect to core /
concrete interactions, steam explosions, fission product behavior l
and chemical form, and hydrogen combustion. The work discussed l
below will reduce and better characterize uncertainties in these areas leading to more accurate decisionmaking.
Research on the effects of the damaged core on containment building loading will be used to provide the technical baus for closure of issues related to containment building performance under severe accident conditions. Probabilistic risk assessment has shown that the public health consequences of accident se-quences with early containment building failure are a major factor. By contrast, a delayed containment building failure is expected to greatly reduce the impact on public health. It is important that the current containment building performance criteria be revised to reflect recent research results so that 69
Nuclear Regulatory Research Programs regulatory practice will reflect our current knowledge of acci-cent phenomena. Uncertainty in the timing and magnitude of key containment building load phenomena that lead to uncertainties i
in evaluating containment performance will be resolved as exper-iments are completed. In FY 1988, the experimental program on key phenomena that govern containment building loading in se-vere accidents will be nearly completed. This work includes core / concrete interactions, fission-product release from the reactor cavity, energy transfer to the containment building atmosphere, and the natural processes that result in fission-product retention in the containment structure. Analysis of the data from these experiments and the application of the new knowledge to regulation will continue in FY 1989.
Some additional fission product research is needed to reduce unacceptably large uncertainties in the area of fission-product chemistry. The program includes completion of separate-effect experiments on fission-product chemistry, with analysis and reporting to be performed in FY 1987 and FY 1988. Confirmatory integral (multi-effect) validation tests with full-length test fuel bundles to determine fission product release and hydrogen generation rates will be performed in the Canadian NRU test reactor and are expected to be completed during FY 1987. Anal-ysis of the data from these experiments and the application of the new knowledge to regulation will continue in FY 1988. These results will be used to validate the current source-term com-puter codes.
RISK AND RELIABILITY RESEARCH Risk Methodology implementation of NRC's safety goal and severe accident policy will require that a reliable and credible technology, modeling, and data base be provided to answer the questions: what is the current and expected level of safety of operating nuclear power plants, and what are cost effective ways to either enhance or maintain acceptable levels of safety?
The ability to evaluate the risk contribution of important acci-dent initiators involving equipment malfunctions and human errors, including common cause or depenoent tailures, has been improved to the point of useful application in assessing risk.
- Also, risk methodology for estimating the contribution from external events, such as fires, floods, and earthquakes, is being developed. To assure consistency, accuracy, and credibil-ity of reliability ana risk analyses there is a need to perform a systematic validation and verification culminating in stand-ardized methods and procedural guidelines for their document r tion and use. The areas of continued or new effort inclJde methods and analysis of human interaction, and obtaining neces-sary data to perform human reliability analyses; evaluation and management of generic issues; evaluation of potential risks of specific issues, such as seismically induced fires and floods; 70
Nuclear Regulatory Research Programs and the need for methods to analyze the reliability of micro-processors and integrated control systems as the use of these is expected to increase rapidly in step with computer technology r
in general.
Risk Assessment
. Assessment of the risk associated with severe accidents is a high priority objective of NRC. The major FY 1986 and FY 1987 risk assessment program has been the preparation of an integrated -
reactor risk reference document that assembles and interprets themost recent information on severe accident frequencies. and risk for six reference plants. This document is designated NUREG-1150. Drafts in various stages of completion will be pub-lished throughout FY 1987. The final document is expected to be-Istued during FY 1988. External events analyses on three plants and the addition of one Combustion Engineering and one Babcock
& Wilcox-designed plant will becompleted during FY 1988-1989.
As new information on severe accident phenomena and accident frequencies becomes available, updates of NUREG-1150 will be made. An analysis of the available data from the Chernobyl reac-tor accident will be conducted in FY 1987 and FY 1988 using risk methodology to be applied to the eight NUREG-1150 refer-ence plants.
Risk Applications I
(
j Risk-based analyses of inspection and enforcement issues, reac-tor technical specifications, and other licensing issues can augment the safety of operating plants by identifying weaknesses i
in design and operations. Using the NUREG-1150 information, a reliability analysis and risk results data base will be assembled and updated to maintain a reliable source of standardized, readily available information for various regulatory applica-tions. Specific computer-based capabilities have been developed i
from research in FY 1986-1987 for use as inspection tools and as regulatory evaluation aids.
In FY 1988, Plant Risk Status information Management (PRISIM) systems will enter a production mode on the remaining five of the six reference plants analyzed for support of NUREG-1150. These will be field tested and pro-vided to the inspection staff.
A similar application of the underlying software, called N-PRISIM for risk analysis of techni-cal specifications and other licensing issues on the same plants, also will be field tested and provided to the regulatory staff.
l An operational safety assessment software technique will be i
developed from FY 1986-1987 research results for inclusion in PRISIM programs. This user-friendly computer program will allow both inspectors and regulators to obtain, within the limits of uncertainty, the risk significance of changes to design or to emergency operating, testing, or maintenance procedures.
71
Nuclear Regulatory Research Programs Risk Codes in FY 1988-1989, the MELCOR/MACCS code will be used to pro-vide safety analyses of important severe accident phenomenolo-gical issues of concern to the NRC. In addition to contribut-ing to ongoing and anticipated newly identified PRA studies, the code will address generic concerns such as equipment qual-ification, safety goal implementation, and ' emergency planning.
i Benchmarking the code against detailed codes will also continue and, as the longer-term results of the severe accident experi-i mental program are completed, they will be used to fu r-ther validate these detailed codes.
Operational Safety Reliability Events at operating plants (such as the loss of feedwater at Davis-Besse in 1985) show that during a plant's operating life-time, a plant's safety performance may degrade below the capa-bility inherent in the original design.
With its lifecycle orientation, a reliability program can be particularly effective in helping the NRC and the utility to prevent such degradation by recognizing potential problems early on, prioritizing them, taking actions to prevent them, and verifying that corrective measures were effective.
Research efforts through FY 1989 include trial applications of reliability technology to evaluate the effectiveness of reliability engineering techniques that licensees can use to help achieve and maintain satisfactory levels of safety per-formance. Also, this research is developing improved, risk-based plant performance indicators and alert levels to strengthen N R C's monitoring of safety. A technique for providing a risk perspective to the development of equipment testing / surveillance procedures and optimizing the frequency of these activities will also have been evaluated for regulatory applications.
This technique will be used to determine if the equipment is achieving its reliability target and assuring that plant per-sonnel will properly interpret off-normal performance in the particular area in which the equipment problem exists.
72
L Nuclear Regulatory Research Programs ENGINEERING SAFETY PROGRAM i
FY 1986 FY 1987 -
FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$39,453
$43,110
$42,350
$44,250 (Staff)
(49)
(43)
(41)
(41)
Design errors, construction defects, and degradation due to ag-ing and wear at some nuclear plants increase the probability of the initiation of accidents or the reduced capability to miti-gate the effects of accidents should they occur.
The Engineering Safety Research Program is directed to provid-ing the licensing staff with the basis for taking timely action regarding the safety of operating plants and determining whether to permit continued operation or require shutdown or modification of plants. Events that require such decisions are, for example, adverse experience with components in one or more operating 4
1 plants, problems uncovered by inspectors, changes in safety requirements from those for which a plant was approved, results of domestic and foreign research, and operating experience. The research involves assessing the suitability of structures and components for the intended service (including abnormal and anticipated accident conditions),
the effects of
- time, operational environment (e.g., temperature, humidity, radiation),
and conditions of operation on the continued safety of those structures and components, and the means for surveillance, inspection,
- testing, maintenance,
- repair, and replacement.
The changes in - the funding profile reflect the completion of steam generator research and equipment qualification along with increased work in plant aging research.
I PLANT SAFETY Containment Building integrity The containment building is the final barrier to the release of i
radioactive material to the environment after a severe accident.
It is important that we know at what pressure and temperature i
the containment building will have unacceptable leakage. NRC experimental research is being conducted on a scale model con-crete containment building to validate calculational methods used to predict the structural and leak behavior of contain-ments under severe accident conditions. Separate experiments are also being conducted on containment building penetrations such as airlocks, hatches, and valves to evaluate their leak behavior. This research supports the NRC Severe Accident Policy Statement.
In FY 1988 experimental and analytical efforts to determine the leak behavior under severe accident conditions for 73
Nuclear Regulatory Research Programs reinforced. concrete' containment buildings will be completed.
Also,.in FY 1988 tests and evaluation will continue on the ef-fectiveness of ice condensers in removing fission products and aerosols from the containment building atmosphere.
Effects of Earthquakes on Operating Plants Probabilistic risk studies of some U.S.
nuclear power. plants currently estimate that earthquakes are potentially significant causes of risk to the public from some pcwer plants.
During FY 1988, research will continue to better determine the seismic hazards (earthquake magnitude and occurrence intervals) for nuclear power plant sites and to predict the response of the site and the plant to earthquakes within the range of magnitudes appropriate to the site, especially for the Central and Eastern United States. This program is closely coordinated _with and provides input to the seismic program evaluating reactor design requirements.
For some of the older nuclear power plants, it is likely that reevaluation' using present knowledge of geology and seismicity i
could lead to substantially increased values for seismic loads.
Uncertainties in the data contribute to d;fficulties in assessing whether the present seismic safety margins continue to provide adequate protection of the public health and safety. Therefore, the primary objective of the earth sciences-research program is to obtain the improved understanding needed to reevaluate the ground accelerations used in establishing these safety margins and to revise Appendix A (seismic and geological siting criteria for nuclear power _ plants) to 10 CFR Part 100 appropriately for plants in the Central and Eastern U.S.
To accomplish this, the NRC has been funding the operation of seismographic networks in the Central and Eastern U.S.
and j
related geological and geophysical research in the seismically active locations. In FY 1987, the NRC anticipates finalizing an l
Interagency ' Agreement with the U.S. Geological Survey (USGS) l.
to replace the NRC-supported networks. In FY 1988, the NRC will continue to fund the purchase of the needed permanent equipment for a six-year period and the USGS will provide personnel sup-l port and assume responsibility for the new network. Research results defining Central and Eastern United States seismic hazards have been used in license reviews and will be needed to determine whether seismic margin assessments of licensed plants are advisable. Significant progress is being made with the validation of seismic energy propagation codes because of several sets of strong ground motion records from some 1986 California earthquakes.
Because of recent research data on earthquakes, new procedures l
for estimating the capacity of nuclear power plants to withstand 74
Nuclear Regulatory Research Programs earthquakes larger than their original design basis are being developed. These procedures will provide the basis for sound regulatory decisions without unnecessary modifications being l
required. These procedures must be validated by improved data l
bases from experience and experiments before they can be used with confidence.
Large-scale complex experimental facilities at overseas locations in Germany, Taiwan and Japan are being used or pursued as part of international cooperative programs to validate these procedures. NRC pays only a small part of the total cost of these overseas experimental programs. Addi-tionally, NRC research is being conducted to determine the failure level of concrete structures and such critical com-ponents as electrical equipment and piping to supplement the existing data base that is being gathered in cooperation with the Electric Power Research Institute.
In FY 1988, large-scale experiments in cooperation with Germany and Japan to validate predictive methods will be completed. Also, failure tests on selected components to fill in the existing data base will be completed.
Equipment Qualification Qualification tests which show that certain equipment will oper-ate under normal conditions may be insufficient by themselves to assure safety. Some valves must close against high flows in the event of a pipe break outside the containment building. Valve malfunction can cause other emergency equipment needed in the control of the reactor to malfunction (e.g.,
flooding). The standards used by industry to qualify valves for this condition need validation to confirm regulatory positions and identify improvement where needed. Research will continue to determine the adequacy of methods for the dynamic qualification of valves.
In FY 1988 experiments will be completed on typical isolation valves in high-energy piping to identify loading characteristics that should be considered in the qualification process for the pipe break condition. In addition, experiments will be completed on other containment building isolation valves that will be used to predict their leak behavior under postulated design basis and severe accident conditions.
MATERIALS AGING Nuclear Plant Aging Research l
l Aging and service wear of components could result in deteriora-tion to a point at which stresses from normal operation, tran-sients or accidents, in conjunction with flaws that might have developed during preoperation or from initial fabrication, could cause a " common mode" failure. Such a failure could result in an accident or in redundant safety systems needed to mitigate acci-dents being rendered inoperable. Research is being conducted to identify the effects of aging and service on structures, compo-nents, and materials that would have an impact on the safety of I
operating reactors and to evaluate fracture predictive analyses, 75
Nuclear Regulatory Research Programs surveillance, inspection, testing, maintenance, repair, and re-placement procedures that can be effective in evaluating and dealing with such effects. This research will provide a basis for assessing the safety of older plants and will serve as a basis for decisions to extend plant operation beyond that origi-nally anticipated in the operating license.
Research will determine the age-related deterioration of such equipment as pressure vessels, piping, cables, circuit breakers, valves, pumps, and motors in the anticipated environment and operating service conditions. Samples and components taken from the Shippingport Nuclear Power Plant at Shippingport, Penn-
- sylvania, during decommissioning will be examined.
The embrittlement of steel from the decommissioned German KRB-A reactor vessel (Gundremmingen) and cast stainless steel from a recirculation pump, which provide good representation of mate-rial, operating temperature and irradiation conditions of U.S.
reactors, will also be evaluated. The availability of the German reactor materials and the Shippingport materials and equipment combined provides a unique opportunity to check predicted deterioration of both materials and equipment during operation against actual deterioration.
The equipment and materials selected will be based on their safety significance and their applicability to those in currently operating nuclear plants, and the results will therefore contribute to regulatory decisions regarding the continued safety of operating reactors. Samples from Shippingport will also be analyzed for neutron-induced isotopes and transported fission products to obtain information on the type of wastes that must be disposed of during decommissioning of nuclear power facilities.
In FY 1988, tests will be performed on naturally aged e"quipment (i.e., removed from operating or decommissioned reactors) and naturally aged and laboratory-aged materials to determine how aging degradation affects material properties and the pe"formance 1
of safety functions. A data base will be developed for indepen-dent evaluation by NRC to assess degradation processes to sup-t port regulatory decisionmaking on applications for extended operation including that beyond the current 40 year license.
Selected safety systems will be monitored and the results eval-uated to determine the impacts of aging degradation. Also in FY 1988, reactor components that have been decontaminated sev-eral times will be examined and evaluated to determine the long-term effects of decontamination on aging and on aged com-ponents which would affect safety during extended life.
Reactor Pressure Vessel Safety Brittle failure of the pressure vessel, which could result in a i
core melt accident, must be prevented by ensuring adequate safety margins. Experimental research on the effects of temper-
[
ature, stresses, irradiation and flaws on the primary system l
76
Nuclear Regulatory Research Programs pressure boundary is necessary to confirm the current regula-tory position that pressure vessels will not fail by brittle fracture during service or'in the case of an accident.
One issue that has been of very high interest is that of a potential accident called pressurized thermal shock (PTS). Here, sudden cooling and depressurization of the reactor vessel brought on by an anomalous transient followed by inadvertent repressurization of the reactor could lead to failure of the vessel. Studies of this accident sequence will be completed in FY 1988 through evaluation of the influence of vessel cladding on a crack started by the PTS incident; it will provide the final verification of the accuracy and margins involved in the PTS Rule. The effect of neutron radiation on reactor vessels has continued to be very important because the vessel can become brittle and could fail in an accident such as PTS noted above. Embrittlement is monitored through material surveillance programs, the results of which are evaluated using a reference fracture toughness curve in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Because ra-diation will adversely alter the material properties, it is neces-sary to assure that the Code reference curve accurately repre-sents behavior of the materials. Thus, in FY 1988, NRC will complete tests of 4-inch thick irradiated specimens to assure that the Code curve accurately represents the changes in prop-erty characteristics of the steels in most operating reactors.
Some older reactors have welds fabricated from materials that exhibit an anomalous behavior as regards fracture toughness.
This material is characterized as having " low-upper-shelf tough-ness en e rgy. "
Thus, in FY 1988, plans will be finalized and material will be procured for an irradiated fracture toughness testing program for these materials. The results from this pro-gram, due for completion in FY 1990, when coupled with previ-ously developed data, should confirm prediction methods and requirements specified in 10 CFR 50, Appendices G and H, for vessel toughness.
The integrity and safety of reactor vessels are analyzed and predicted by analytical methods called fracture mechanics. Ves-sels, however, exhibit characteristics ranging from brittle at low temperatures to very ductile and tough at normal operating temperatures. It has been necessary to develop and experimen-tally vallaate fracture mechanics methods for the different types of material behavior of vessels. In FY 1988, NRC will complete efforts to combine these methods into a single, unified methodology with the addition of the part on ductile fracture.
This unified methodology will enhance safety and reduce conser-vatisms.
Issues related to plant life extension will be under detailed study in FY 1988 to be sure that the necessary basis information is ready in the future when regulators are faced with decisions on plant life extension applications. Some of the important areas will be in comparing material property data i
i 77
Nuclear Regulatory Research Programs from decommissioned reactors such as Gundremmingen and Ship-pingport to current accepted trends for such properties and in assuring that the ASME Boiler and Pressure Vessel Code ref-erence curves for initiation of cracks by fatigue realisti-cally represent the conditions that exist in operating plants rather than just room temperature laboratory conditions.
Pipe Cracking and the Leak-Before-Break Principle There have been numerous instances of cracked piping in nuclear power plants.
Piping in most operating nuclear plants was designed on the basis that a double-ended guillotine break is the major accident against which the plant must be protected. This conclusion led to the installation of numerous pipe whip restraints and jet impingement barriers, and affected the plant design in many other areas. Past and ongoing research efforts have shown that, for many piping systems, the double-ended guillotine break is a very low probability event and further, that the steps taken to implement the requirement to postulate this break can actually reduce, rather than enhance, safety.
These results led to a rule change, accepting the leak-before-break principle to the extent that dynamic effects from the t
double-ended guillotine break need not be considered for piping lines that meet rigorous acceptance criteria. This rule change has introduced an inconsistency in the design criteria in that the double-ended guillotine break is still the design criteria for all but the dynamic effects consideration.
+
There are benefits that can be derived if a replacement to the double-ended guillotine break can be justified. The FY 1988 research begins to address definition of a replacement to the double-ended break and further defines and refines the criteria for eliminating break locations for dynamic effects considera-
- tion, i.e., defining when the leak-before-break principle can be applied. The FY 1988 research will include testing of piping systems under simulated seismic loading to validate the predic-tive methodologies currently being used and to define the limits i
of applicability of those methodologies. Because the rule is intended to include all high energy piping in the plant, the focus of the research has also been broadened to include the applicable materials and service conditions for both the primary l
[
system and the balance-of-plant piping. Research on cracking in stainless steel pipes of boiling water reactors will focus on the potential beneficial effects of improved water chemistry control, improved materials and other fixes for stress corrosion cracking.
The FY 1988 work will examine the effects of upsets in the nomi-nal water chemistry on the cracking benavlor of the improved materials. It will also continue to examine the causes and degree of degradation of cast austenitic steels due to long-term thermal I
aging. The FY 1988 work will evaluate the leak detection methods that may be useful outside the containment building to provide an independent assessment of these methods for use in the reg-ulatory process.
78
Nuclear Regulatory Research Programs Finally, a multi-disciplinary effort will continue to investigate the material, thermal-hydraulic, and design parameters respon-sible for erosion / corrosion of carbon steel pipe components.
The above research will contribute to confirming the technology based on the leak-before-break principle and to defining a replacement for the double-ended guillotine break as the design basis for many aspects of nuclear power plants.
Nondestructive Examination and Evaluation Methods currently in use for flaw detection and characterization are not always consistent, reproducible, or interpretable. Never-theless, preservice and inservice inspections are counted upon to reveal. and characterize flaws in reactor pressure boundary components such as vessels, pipes and steam generator tubes.
For safety evaluations, such as for PTS, it is very important to know if the very small flaws capable of crack initiation under PTS accident conditions are present. Pressure boundary piping must be reliably inspected to ensure leak-before-break.
Excessive degradation in steam generator tubing must be pro-perly detected and characterized so that tubes can be plugged to avoid unacceptable releases of radiation or loss of cool-ant. Thus, methods currently in use must be quantified with respect to their reliability.
In cooperation with the Organization for Economic Cooperation and Development (OECD), techniques and procedures will be evaluated in FY 1988-1989 for the inspection of nozzles and pressure vessels using realistic components and flaws. Also in FY 1988 international round robin testing will be initiated for evalu-ating techniques for inservice inspection of piping, including difficult-to-inspect cast stainless steel pipes. This cooperation with OECD will allow the U.S. to evaluate and benefit from cur-rent and advanced international technology for inservice in-spection of nozzles, vessels and pipes. A unified set of inspec-tion and acceptance requirements will be developed in FY 1988 for inservice inspection of pipes and vessels. These require-ments will be developed for consideration by the ASME Code or for Regulatory Guide preparation and will be based on non-destructive examination (NDE), flaw detection and characteriza-tion reliability, component material properties and function, and service conditions / environment.
The requirements will encompass all types of cracks, flaws and wall-thinning by envi-ronmental and thermal-hydraulic erosion / corrosion processes.
Locations exist in plants where conventional inspection tech-niques are inadequate for proper examinations for flaws. Thus, alternative techniques are very useful. One such technique is acoustic emission. This technique has the advantage that com-ponents can be monitored on line so that their integrity can be assessed on a continuous basis rather than periodically, on a 79
Nuclear Regulatory Research Programs limited sample, as is the case with current inservice inspec-tions which generally use ultrasonic testing techniques. Growing cracks produce acoustic signals that can be monitored to allow the detection, location and evaluation of flaw severity for active cracks growing during reactor operation. Leaks also produce acoustic signals that allow for the location, sizing and discrimination (i.e., cracks vs valves, pump seals, etc.) of leak sources. The acoustic emission information can therefore be used for enhancing the reliability and safety of operating reactors on a continuous basis. Although such methods are desirable, no formal criteria currently exist for acceptance by NRC or for application of the techniques in service, nor are the monitoring procedu res, techniques and crack evaluation criteria yet fully j
validated by inservice monitoring. In FY 1988, using funds from the Tennessee Valley Authority (TVA) derived under an NRC/
TVA cooperative agreement for validation and implementation of the technology, final field validation will be accomplished by completion of inservice monitoring of the Watts Bar Unit 1 reactor. A code case will be submitted for acceptance of the acoustic emission technology for crack growth monitoring by ASME, the industry and NRC. Also in FY 1988 advanced acoustic emission leak detection technology for inservice monitoring of pressure boundary components will be completed and field tested.
To make licensing decisions related to extension of service for nuclear power reactors beyond their first licensing period, evaluations of the integrity of the primary system reactor components and safety systems and their fitness for continued use must be performed to ensure continued safety. To perform these evaluations, the condition of the components with re-spect to flaws initiated during prior service and the extent of any degradation in material toughness and other mechanical properties must be accurately known. Nondestructive techniques for these assessments need to be developed and validated. Re-search will be initiated in FY 1988 to begin evaluation of such nondestructive testing techniques.
80
Nuclear Regulatory Research Programs WASTE MANAGEMENT PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 4,598
$ 5,800
$ 9,000
$ 9,000 (Staff)
(17)
(19)
(18)
(18)
The Waste Management Research Program provides the technical basis for regulations and licensing decisions (1) to evaluate DOE submittals and ultimately license high-level waste (HLW) disposal facilities and (2) to evaluate conventional and alternative low-level waste (LLW) disposal methods to facilitate licensing by Agreement States as well as the NRC. The increase between FY 1987 and FY 1988 is substantially due to the initiation of an increased emphasis on the field validation of performance models which will take into account the processes and phenomena important to HLW storage. Additionally, a part of the increase results from activities necessary to meet NRC responsibilities under the Low Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 relative to alternatives to shallow land burial.
HIGH-LEVEL WASTE in response to the Nuclear Waste Policy Act (NWPA) of 1982, the NRC is developing the capability to independently evaluate the adequacy of programs and information being developed by DOE for the licensed disposal of high-level waste in geologic re-positories. The HLW research and standards development program is contributing to the technical basis for this independent evaluation consistent with the milestones for repository development set forth in DO E's project decision schedule. If these schedules are to be met for this first-of-a-kind undertak-ing, it is essential that a competent methodology for evaluating the adequacy of DOE's activities related to site screening, selection, and characterization and facility design is developed.
Specifically, the NRC's HLW research is providing ongoing sup-port to N R C's prelicensing consultation with DOE to provide timely guidance to DOE on technical points and issues to be addressed during site characterization, and is developing in-formation specific to N R C's review of DOE's site characteriza-tion activities.
At present, the technical basis for NRC's HLW management review capability contains large uncertainties due to the lack of any previous experience with HLW disposal and the very long periods of time involved. In FY 1988, uncertainties will be reduced in selected areas through a program of selective experimentation and 81
- Nuclear Regulatory Research Programs testing of performance assessment models for the various components of a HLW repository. These models must be adequate-ly tested prior to use in licensing evaluation. The validation effort will increase as the license review approaches. The research needed to support the day-to-day activities of the licensing office will continue by identifying critical regulatory issues and helping to ensure that technical problems associated with these issues are understood sufficiently to support licensing decisions.
FY 1988 efforts will address waste package performance and likely i
failure mechanisms; performance of key features of an under-
)
ground facility, such as borehole and shaft seals; performance of backfill and packing materials; the groundwater hydrology l
In and around the repository; radionuclide transport; perform-ance assessment methodologies; and interaction between the engineered and material components of HLW repositories.
LOW-LEVEL WASTE NRC LLW research and standards development is directed at providing the technical basis for implementing requirements of the LLRWPAA of 1985. NRC LLW research is critical to establishing a sound technical basis for regulation of and advice to the states on all aspects of LLW disposal, includ-ing engineered enhancement and alternatives to shallow land burial.
This research effort will maintain both a national safety perspective and a uniform technical basis for efforts by the states to se'ely dispose of low-level waste.
Specific efforts to be continued or planned for in FY 1988 include research to provide information relative to site suitability, facility design, LLW source term, waste form and packaging performance, operational monitoring and postoperational care, and the performance of LLW disposal facilities over long periods of time. A key element of the FY 1988 research will be obtaining validation of performance assessment models and com-puter programs. Such validation is needed to increase confidence in the management of LLW, to minimize the need to apply conser-vatisms in the regulation of LLW disposal to compensate for uncertainties in the performance of various LLW disposal tech-niques, and to provide the technical bases against which to evaluate the performance of engineered enhancements or alter-natives to conventional shallow land burial. This will allow NRC or state licensing authorities to give appropriate consider-ation for the presence of engineered systems and to minimize licensing delays.
82
Nuclear Regulatory Research Programs REGULATORY APPLICATIONS PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 4,384
$ 2,355
$ 2,400
$ 2,400 (Staff)
(44)
(36)
(34)
(34) in the management of a successful research prog ram, it is necessary to ensure that existing and potential safety problems in NRC-licensed activities are recognized and understood, particularly those that are subject to mitigation or resolution through research.
Available resources must be directed to ensure that the problems of greatest safety significance are selected for the research effort, and that the research conducted is of high quality. To ensure that research results are utilized in the licensing, inspection and standards development processes, each research project must be an integral part of an agency-wide strategy adopted to deal with the related safety problem. It is also necessary to ensure that key personnel have ready access to information about NRC research and how results are used in the NRC regulatory program. These are the primary objectives of the Regulatory Applications Program. This program also includes the managernent of NRC rulemakings and the research and standards development activities for radiation protection and health effects.
REGULATORY APPLICATION in the design, operation, and decommissioning of complex nuclear facilities, safety-related problems arise which require regula-tory attention. For some of these problems, available technical information is inadequate for making balanced regulatory decisions. Since the principal objective of the research program is to provide such information, the effectiveness of the research program depends first upon problem-identification.
l Since it is not possible to fund research for all of the problems that are identified, a prioritization system is used to ensure optimum use of available resources. Prior to the preparation of t
l budget requests, the NRC technical staff ranks projects proposed through the problem-identification process, taking into consider-ation such key factors as: risk magnitude and uncertainty, the potential for uncertainty reduction, regulatory significance, and cost. This prioritization system provides for technical input from the staff which is then considered by NRC management in formulating the budget request. During FY 1988 safety-related problems that have been identified will be subjected to the prioritization process in preparation for the next budget cycle.
83 l
Nuclear Regulatory Research Programs A long-range research plan (5-year) will be developed describing the agency's research needs and presenting the relative priority assigned to each problem requiring research. In addition, a report will be prepared which will detail how research results have been and are being used in the NRC regulatory program.
MANAGEMENT OF RULEMAKING In addition to the execution of research to provide improved understanding of nuclear safety for resolution of complex technical issues important to regulation, the Office of Nuclear Regulatory Research (RES) performs standards development and assists in the management of rulemaking activities. Agency rule-makings are independently reviewed by RES to ensure that:
1.
NRC rulemaking resources are focused on issues important to public safety, and the common defense, and security; 2.
All ongoing rulemakings are coordinated and consistent with agency policy; 3.
Necessary rulemakings are properly developed and docu-mented and are completed in a timely manner; and 4.
Unnecessary rulemakings are weeded out before substantial staff time and resources are spent on them.
Initial efforts have been focused on purging ongoing rulemaking actions that are of marginal safety significance from the NRC Regulatory Agenda. Over 88 rulemakings have been independently reviewed to date; and, as a result, 27 rulemaking actions have been terminated.
In addition, during FY 1988, RES will continue its program to re-evaluate the effectiveness of existing regulatory requirements through the application of probabilistic risk assessment (PRA) and value-impact analysis tools. Contractual technical assistance to support these evaluations (e.g., developing improved methuds for performing value-impact assessments) will be required in this activity. The objective of this continuing program is to identify those requirements that are clearly not effective in enhancing public health and safety and which should be revised or withdrawn. Such a program permits limited agency and industry resources to be focused more on matters of highest safety significance, in FY 1988 and FY 1989, more detailed analyses will be performed using, for example, existing PRA and value-impact tools on approximately ten regulatory requirements which may support possible future regulatory actions. Contractual technical assistance in FY 1988 and FY 1989 will also provide support for the development of complex standards and rulemakings such as revising the siting and emergency preparedness regulations and the preparation of related guidance documents.
84
Nuclear Regulatory Research Programs RADI ATION RISK ASSESSMENT The degree of radiation risk associated with NRC-licensed activities influences decisions that are made in the standards development, licensing and inspection programs. To the extent
- possible, agency personnel need to understand risks to the public that arise from routine nuclear facility effluents, accidents, radioactive material shipments, products containing radioactivity, and residual radioactivity on or in decommissioned lands and structures, materials and equipment, and radioactive waste. It is also necessary to understand occupational risks from exposure to radiation and airborne radioactive material. The information needed includes the number of people exposed, the exposure magnitude, and the number and nature of associated health effects. Data regarding the number of workers exposed l
and the magnitude of the doses received is reported to the NRC l
by licensees in accordance with regulatory requirements. An l
annual report is issued on occupational radiation doses received.
Health effects information is obtained primarily through the analysis of published literature and participation in related conferences and governmental activities. The staff also has an active role in the international harmonization of risk models and coefficients currently in use.
During FY
- 1988, this risk assessment effort will be continued with emphasis on the impact of new scientific information on NRC regulatory standards, e.g.,
revised dosimetry for atomic bomb survivors and animal studies on the toxicity of soluble uranium.
It is anticipated that radiobiological (and other) information made available regarding the Chernobyl accident will identify research needs for the NRC regulatory program, particularly concerning the early effects of high radiation doses, and appro-priate research projects will be planned during FY 1988-1989 as these needs are identified.
R ADI ATION RISK MANAGEMENT There is a continuing need to maintain and update radiation protection standards for the protection of workers and the general public which are based upon the latest scientific information.
To meet this need, the radiation risk manage-ment effort consists primarily of standards development work published in Regulatory Guides and regulations. Use is made of consensus standards and the recommendations of authorita-tive bodies such as the International Commission on Radiological Protection, the International Commission on Radiation Units and Measurements, the National Council on Radiation Protection and Measurements, and the National Academy of Sciences.
Information published by various research organizations and by the United Nations is also used.
NRC radiation protection personnel participate actively in 85
~
Nuclear Regulatory Research Programs national and international standards development activities, analyze publications in this field, and keep NRC radiation risk management activities technically up-to-date. It is anticipated that a complete revision of the NRC standard on radiation protection (10 CFR Part 20) will be published in final form early in FY 1988, and that guidance on acceptable methods of compli-ance will be published soon thereafter.
i l
l I
I 86 l
Nuclear Regulatory Research Programs MANAGEMENT DIRECTION AND SUPPORT PROGRAM FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
0 0
0 (Staff)
(22)
(22)
(22)
(22)
The staffing requirements for this area consist of the Director's Office and the Research Planning and Policy Branch of the Division of Regulatory Applications. This branch provides the Director of RES with assistance and support in the direction and evaluation of complex technical research projects and program
- plans, and coordinates,
- directs, and carries out the administrative and fiscal matters of the Office, including coordinating the placement of contractual agreements, budget formulation, financial management, personnel administration, management information systems and travel assistance. Among the staff's most important functions are coordination with the licensing and regulatory groups within NRC to identify their needs and to assure that the research program is responsive to the maximum extent practicable, and coordination with industry and foreign agencies to develop and execute multiparty agree-ments on safety research.
l l
87
Nuclear Regulatory Research Programs THIS PAGE INTENTIONALLY LEFT BLANK 88
ws,-
i l
1 I
i PROGRAM TECHNICAL SUPPORT
r_
4 aa.-
m 2.C-_
A-e 1
l 4
l l
l l
l l
l l
r I
I l
I 1
4 t
4 i
l l
l i
I 1
PROGRAM TECHNICAL SUPPORT (Dollars are in thousands, except in text, where whole dollars are used; staff numbers are in full-time equivalents.)
Totcl FY 1988 estimated obligations............................ $34,082 Total Funds and Staff FY 1986 FY 1937 FY 1988 FY 1989 Actual Estimate Estimate Estimate Salaries and Benefits
$ 19,921 $ 19,830
$ 19,320
$ 17,700 Program Support 4,168 6,229 6,882 7,660 Administrative Support 6,059 6,470 6,810 7,280 Travel 1,138 1,115 1,070 1,060 Total Obligations
$ 31,286 $ 33,644
$ 34,082
$ 33,700 (Staff)
(375)
(357)
(334)
(323)
Program Support Funds and Staff The Program Technical Support program provides direct technical support to agency programs. At headquarters this Program is supported by the Advisory Committee on Reactor Safeguards (ACRS), the Atomic: Safety and Licens-ing Board Panel ( ASLBP), the Atomic Safety and Licensing Appeal Panel (ASLAP), the Office of International Pro-grams (IP), and the Office for Analysis and Evaluation of Operational Data ( AEOD). Technical support is provided at both headquarters and the regions by the Office of Investigations (01), the Office of State Programs (SP) and the Office of the General Counsel (GC).
The Office of the Executive Legal Director was unified with the GC in FY 1986.
The allocation of program support funds and j
staff to each office follows with narrative describing the programs and their needs.
I FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds Staff Funds Staff Funds Staff Funds Staff ACRS
$ 207 49
$ 320 42
$ 320 39
$ 320 38 ASLBP 152 45 820 38 816 30 816 30 ASLAP 0
15 10 14 7
10 5
8 01 0
41 0
44 0
44 0
44 GC 92 125 89 118 89 108 89 103 IP 2
26 50 26 50 24 50 23 SP 622 34 700 32 710 31 740 30 AEOD 3,093 40 4,240 43 4,890 48 5,640 47 TOTALS $4,168 375 $6,229 357 $6,882 334 $7,660 323 89
Program Technical Support ADVISORY COMMITTEE ON REACTOR SAFEGUARDS FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 207 320 320 320 (Staff)
(49)
(42)
(39)
(38)
The Advisory Committee on Reactor Safeguards (ACRS),
established in 1957 by statute, advises the Commission on potential hazards of proposed or existing reactor facilities and the adequacy of proposed safety standards. Section 29 of the Atomic Energy Act of 1954 also requires that the ACRS advise the Commission with respect to the safety of operating reactors, and perform other duties as the Commission may request. Public Law 95-209 requires the ACRS to provide an annual report to the Congress on the NRC Safety Research Program.
The ACRS reviews requests for preapplication site and standard plant approvals; applications for operating licenses for production and utilization facilities; amendments to oper-ating licenses for power reactors, test reactors, spent fuel reprocessing plants and waste disposal facilities; and assists in matters related to nuclear facilities as outlined in a Memorandum of Understanding with the Department of Energy.
The staffing changes reflect a reduced power reactor licens-ing workload.
The ACRS also recommends and comments on proposed Regula-tory Guides and standards being considered and/or promulgated as the basis for NRC regulatory activities. Since the imple-mentation of the Nuclear Waste Policy Act of
- 1982, the ACRS has participated in the establishment of related stan-dards and licensing activities on the handling and disposal of radioactive waste, including the interim storage arrange-ments for this material.
90
Program Technical Support i
ATOMIC SAFETY AND LICENSING BOARD PANEL FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 152 820 816 816 (Staff)
(45)
(38)
(30)
(30) i The Atomic Safety and Licensing Board Panel (ASLBP) is the statutory adjudicatory office of the agency.
Adminis-trative Judges sitting alone and in three-member Boards conduct adjudicatory hearings pursuant to the Administrative Procedure
- Act, the Atomic Energy Act and the National Environmental Policy Act.
Boards hear and-decide cases concerning: (1) licenses and license amendments to construct and operate nuclear plants and other nuclear facilities; (2) nuclear materials; (3) enforcement; and (4) other matters assigned by the Commission. Hearings address matters such as health,
safety and the environment.
Single Administrative Law Judges decide cases in enforcement, civil penalties and antitrust.
The resource decreases in FY 1988-1989 result from a decreasing number of applications for power reactor operating licenses offset by an increasing number of license amendments and other proceedings which the Commission may direct or the regulations of the agency may require.
ATOMIC SAFETY AND LICENSING APPEAL PANEL FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate i
t Funds 0
10 7
5 l
(Staff)
(15)
(14)
(10)
(8) l l
l The Atomic Safety and Licensing Appeal Panel's (ASLAP) l three-member tribunals review decisions of administrative law l
judges and the Atomic Safety and Licensing Boards rendered in (1) proceedings on applications under 10 CFR Part 50; and i*
(2) such other licensing proceedings as the Commission may specify.
In discharging this review function, the Panel is governed by the applicable provisions of the Administrative 91
Program Technical Support Pror.edure Act and the agency's Rules of Practice. The staff-ing changes reflect a reduced power reactor licensing workload.
OFFICE OF INVESTIGATIONS FY 1986 FY 1987 FY 1988 FY 1989 Actual _
Estimate Estimate Estimate Funds 0
0 0
0 (Staff)
(41)
(44)
(44)
(44) l The Office of Investigations (01) is an independent office which conducts and supervises agency investigations of all allegations of wrongdoing by other than NRC employees and its contractors, including reactor licensees, fuel cycle licensees, and materials safety and safeguards and facilities licensees. As operating licenses are issued and the number of applications decreases, the complexity of 01 cases is changing. The cases necessarily are becoming more complex because they relate to operating reactors rather than con-struction.
Each case must be thoroughly and completely examined and subsequent findings must be evaluated and disseminated so as to assure prompt attention to safety concerns and to avoid undue delay to licensing activities.
Quality control standards are being developed, administered, and maintained to oversee the conduct of investigations. The Commission and appropriate agency offices are apprised of matters under investigation which may affect public health and safety or other aspects of the agency's mission.
The 01 maintains liaison with other agencies and organizations to ensure the timely exchange of information of mutual interest and makes appropriate referrals to the Department of Justice on criminal matters.
l
(
92
.. =
l Program Technical Support i
OFFICE OF THE GENERAL COUNSEL l
FY 1986 FY 1987 FY 1988 FY 1989
)
Actual Estimate Estimate Estimate 1
l Funds 92 89 89 89 (Staff)
(125)
(118)
(108)
(103) i During FY
- 1986, the Commission decided to combine the Offices of the General Counsel and the Executive Legal Director. The new Office of the General Counsel (GC) re-porting to the Commission provides legal advice and services to the Commission and staff on all issues before the agency including the discharge of the Commission's quasi-judicial responsibilities, development of substantive policy matters, and the conduct of administrative proceedings involving the licensing of nuclear facilities and materials.
The GC also provides legal _ advice and assistance to the Commission and staff on enforcement actions and rulemaking and represents the Commission in the Courts of Appeal and, in cooperation with the Department of Justice, the District Courts and the t
Supreme Court.
J The office also provides legal advice on legislative matters of concern to the agency, including drafting of legislation, preparation and review of testimony, and preparation and j.
transmission of statements of views on proposed legislation.
J Additionally, legal advice and services are provided by the GC 1
attorneys in the areas of health and safety, environmental impact, antitrust, and general agency administration including research, contracts, intellectual property, personnel, budget, security, and labor relations; safeguards and waste management j
programs; Freedom of Information Act and Privacy Act matters, and the export / import licensing program. Staff reduc-tions reflect the expected efficiencies to be gained as a l
result of combining the two legal offices and a re+eced power reactor licensing workload.
i s
93
Program Technical Support OFFICE OF INTERNATIONAL PROGRAMS FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 2
50 50 50 (Staff)
(26)
(26)
(24)
(23)
The Office of International Programs (IP) develops and directs a program of cooperation with foreign regulatory agen-cies and international organizations on nuclear safety and administers the Commission's responsibilities in the areas of nonproliferation, international safeguards and nuclear exports and imports.
The staff on international matters, maintains liaison with other federal agencies, and performs a key func-tion in faciliating the flow of nuclear health and safety-related information between the United States and foreign countries.
It also administers the Commission's export / import licensing procedures, assists in the development of improved international safeguards and physical sc.curity arrangements, and participates in the ongoing implementation of the Commission's regulations in support of the U.S./ International Atomic Energy Agency safeguard's agreement.
OFFICE OF STATE PROGRAMS FY 1986 FY 1987 FY 1988 FY 1989 A_ctual Estimate Estimate Estimate Funds 622 700
$ 710
$ 740 (Staff)
(34)
(32)
(31)
(30)
The Office of State Programs (SP) manages a program of coop-eration and liaison with
- states, local governments, Indian tribes and interstate organizations.
The office coordinates regulatory issues with states concerning high-level waste Policy Act),, low-1evel waste (under (under the Nuclear Waste 94
Program Technical Support the Low-Level Radioactive Waste ' Policy - Act),- and transporta-tion of radioactive materials.
The SP also administers the NRC program with' 28 Agreement States, which in turn admin-ister about 13,000 licenses involving the regulation of certain classes of radioactive materials, including uranium milling and low-level radioactive waste disposal.
The office also administers the Price-Anderson Act, which provides liability insurance and government indemnity for nuclear accidents, and administers activities relating to nuclear property insurance, financing decommissioning, tracking state-regulatory incentives for nuclear
- plants, and monitoring Three Mile t
Island-2 ' cleanup financing. It provides guidance, training and assistance to state and local governments in radiation control and coordinates with other NRC offices and agencies having state and interstate responsibilities.
The office supports, along with. states and other agencies, the Conference of Radiation Control Program Directors, Inc. (an association of State Radiation Control Program Directors).
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA I
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 3,093
$ 4,240
$ 4,890
$ 5,640 (Staff)
(40)
(43)
(48)
(47) t The Office -for Analysis and Evaluation of Operational Data (AEOD) collects, analyzes, and disseminates information about operating experience from all agency licensed activities. This
)
office reviews operating experience to identify significant events or situations that warrant detailed evaluation and then studies those significant events or situations to determine the lessons of experience and safety concerns that warrant regula-tory attention.
j Specific tasks and activities of the office are the following:
Collect, screen, analyze, and feed back operating experi-
[
ence to agency staff, the nuclear industry, and the public on all agency licensed activities.
f h
l 95
Program Technical Support Screen U.S.
and foreign operational events for signifi-cance and systematically and independently analyze those events.
Analyze operational experience data to identify trends and patterns that indicate potential safety problems.
Make recommendations for agency action for resolution of safety issues detected through these activities.
Analyze all Licensee Event Reports, recommend to the Com-mission which events constitute Abnormal Occurrences, and document those occurrences on a quarterly basis to Con-gress and the public.
Maintain operational and reliability data storage and re-trieval systems, including: (1) development and operation of several data bases of selected operational experience data, and (2) coordination with the Institute of Nuclear Power Operations (a nuclear-industry-funded organization) which supports and manages the Nuclear Plant Reliability Data System.
Report appropriate U.S.
events to the international Nuclear Energy Agency's incident Reporting System.
Serve as contact point for data collection in relation to the agency staff, the ACRS, and industry groups.
Administer the incident Investigation Program for signifi-cant operational
- events, maintain personnel
- rosters, provide training programs, and provide necessary support to the incident investigation Teams.
The screening work requires the review of 3,500 reactor Li-censee Event Reports per year, as well as the review of exten-sive documentation of events involving foreign reactors, inspec-tion reports, and U.S.
industry reports.
In the evaluation of nonreactor events associated with the use, transportation, safeguarding and disposal of nuclear materials, about 6,000 reports are reviewed each year that are received from approxi-mately 9,000 licensees.
These reports involve operational events such as overexposures to radioactive materials or medical misadministrations.
The improved data bases associated with this activity are now sizeable and collection mechanisms are in place, it is now in-cumbent on the Nuclear Regulatory Commission to analyze trends and patterns based on these data. The lessons of oper-ating experience often cannot be derived from viewing a single event; they must be developed by associating events. Through trends and patterns an evolving picture can be developed that 96
Program Technical Support lead to appropriate corrective actions being identified and can taken before the situation becomes a serious incident. It is toward this end that the data bases have been established.
Analyses are now possible to identify the trends and patterns and to develop the risk perspective associated with operational experience. Resource increases in FY 1988 and FY 1989 are to account for the increased number of operating power reactors and to provide increased trends and patterns analysis capability.
97
Prograrn Technical Support THIS PAGE INTENTIONALLY LEFT BLANK i
i 1
e l
98
w
-w 1
PROGRAM DIRECTION AND ADMINISTRATION t
si o?
54 Y
r1 m
--r--.--------e-
.,,,--e,ew
-,e
-wwn,.we,----3--
m,,-
,,-y-.-,
,y
,--,-g,
- -. -wr,-my
.a-4 a-l l
l l
l l
l l
l i
l l
l l
1 1
1
-z M.-
=
O k'
P'c1
PROGRAM DIRECTION AND ADMINISTRATION (Dollars are in thousands, except in text, where whole dollars are used; staff numbers are in full-time equivalents.)
Total FY 1988 estimated obligations.................................$44,438 Program Total Funds and Staff FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Salaries and Benefits
$ 29,601 $ 29,180
$ 29,820
$ 27,900 Program Support 910 2,186 1,618 1,540 Administrative Support 10,967 11,180 12,410 13,670 Travel 576 595 590 590 Total Obligations
$ 42,054 $ 43,141
$ 44,438
$ 43,700 (Staff)
(689)
(647)
(631)
(625)
Program Support Funds and Staff The Program Direction and Administration program collec-tively provides overall policy direction, resource manage-ment, administration and logistic support for the agency.
The staff offices are the Commission (OCM), Secretary (SECY),
insoector and Auditor (I A),
Public Affairs (PA),
Congressic..r.i Affairs (CA),
Executive Director for Operations (EDO), Small and Disadvantaged Business Utilization and Civil Rights (SBDU/CR),
information Resources Management (IRM), Resource Management (RM),
and Administration (ADM).
The Commission has decided to eliminate its separate Office of Policy Evaluation (PE) effective September 30, 1986.
The allocation of program support funds and staff to each office follows with narrative describing the programs and their needs.
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds Staff Funds Staff Funds Staff Funds Staff r
OCM
$ 0 38
$ 285 43
$160
$ 43
$ 160
$ 43 l
SECY 110 30 385 30 350 28 350 27 lA 0
27 0
26 0
26 0
26 l
PA 13 17 15 17 10 17 10 17 PE 46 13 0
0 0
0 0
0 CA 0
9 1
8 1
8 1
7 EDO 0
22 50 23 50 23 50 23 SDBU/CR 286 9
150 7
150 7
150 7
IRM 0
112 0
117 0
114 0
114 RM 455 92 1,300 87 897 85 819 84 ADM 0
320 0
289 0
280 0
277 TOTALS
$910 689 $2,186 647 $1,618 631 $1,540 625 99 l
Program Direction and Administration THE COMMISSIONERS AND STAFF FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
$ 285
$ 160
$ 160 (Staff)
(38)
(43)
(43)
(43) l The Office of the Commissioners (OCM) is the governing body which must exercise the overall Nuclear Regulatory Commission (NRC) responsibilities. The Commissioners provide fundamental policy guidance ten assure that the civilian use of nuclear energy is regulated in a manner consistent with the put-lic health and safety, environmental quality, national security and antitrust laws.
OFFICE OF THE SECRETARY FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds
$ 110
$ 385
$ 350
$ 350 (Staff)
(30)
(30)
(28)
(27)
The Office of the Secretary (SECY) provides general manage-ment services to support the Commission and to implement Commission decisions; advises and assists the Commission and staff on the planning, scheduling and conduct of Commission business; prepares for and records Commission meetings; man-ages the Commission staff paper system and monitors the status of all items requiring action; integrates automated data processing and office automation initiatives into the Commission's administrative system; maintains a forecast of matters for future Commission consideration; processes and controls Commission correspondence; maintains the Commis-sion's official records; maintains the official Commission adjudicatory and rulemaking dockets, and serves Commission issuances in all adjudicatory matters and public proceedings; administers the historical program; and directs and admin-isters agency's Public Document Room.
100
Program Direction and Administration OFFICE OF INSPECTOR AND AUDITOR FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
0
$ 0
$ 0 (Staff)
(27)
(26)
(26)
(26) l i
The Office of Inspector and Auditor (IA) functions as the agency l
Inspector General, providing the Commission with an independent review and appraisal of programs and operations.
The office is responsible for developing policies and standards that govern the financial and management audit program; planning, directing and executing
.the long-range, comprehensive audit program; conducting and reporting on investigations and inspections, as necessary, to ascertain and verify the facts with regard to the integrity of internal agency operations, employees, contractors, organization's programs and activities; and referring suspected or alleged criminal violations concerning NRC employees or con-tractors to the Department of Justice.
It also administers the Commission's "open door" policy; serves as point of contact with the General Accounting Office (GAO);
and maintains liaison with GAO and government audit and law enforcement agencies.
OFFICE OF PUBLIC AFFAIRS FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 13 15
$ 10
$ 10 (Staff)
(17)
(17)
(17)
(17)
The Office of Public Affairs (PA) issues public announcements from both headquarters and the regional offices; responds to telephone inquiries from the news media and the public; and responds to letters from the media and the public, including the bulk of the NRC referrals from the White House. In addi-tion, the staff arranges press conferences in the Washington area, as well as in the regions in the vicinity of nuclear
=
101
Program Direction and Administration facilities, and coordinates requests for Commission speakers before civic groups and other organizations interested in the role of the agency.
The office also assists the licensing boards, the appeal boards
-and the Advisory Committee on Reactor Safeguards whenever hearings and meetings are held in which a high degree of public and press interest is evidenced; advises. the Commission and senior staff on public affairs impacts of planned programs and other activities; and advises and assists the Commission and the public on the conduct of public meetings and rulemaking hearings of broad general interest.
OFFICE OF CONGRESSIONAL AFFAIRS FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
1 1
1 (Staff)
(9)
(8)
(8)
(7)
The - Office of Congressional Affairs (CA) assists and advises the Commission and senior staff on Congressional matters, coor-dinates agency Congressional relations activities and is the principal liaison for the Commission with Congressional com-mittees and members of Congress.
The primary objective is to assure that the Congress, through its designated oversight committees, is kept fully and currently informed of agency activities and that Congressional requests responded to promptly. The Office provides and inquiries are the Commission and - senior staff with relevant and current information as to major legislative activities likely to affect the agency.
Additionally, the office seeks to assure that individual members of Congress are kept currently and adequate-ly informed of significant licensing activities that impact their respective states and districts.
l 102 l
l
Program Direction and Administration OFFICE OF THE EXECUTIVE DIRECTOR p
E FOR OPERATIONS I
FY 1986 FY 1987 FY 1988 FY 1989 l
Actual Estimate.
Estimate Estimate l-Funds 0
50
$ 50
$ 50 (Staff)
(22)
(23)
(23)
(23)
The Office of the Executive Director. for Operations (EDO) l-supervises and coordinates operational activities and policy i
development of both line and staff offices and implements the Commission's policy directives pertaining to these offices.
i OFFICE OF SMALL AND DISADVANTAGED I
BUSINESS UTILIZATION AND CIVIL RIGHTS i-FY 1986 FY-1987 FY 1988 FY 1989 L
Actual Estimate Estimate Estimate Funds 286 150
$ 150
$ 150 (Staff)
(9)
(7)
(7)
(7) i The Office of Small and Disadvantaged Business Utilization / Civil Rights (SDBU/CR) is responsible for implementing and execut-i ing functions and duties under three program authorities:
l Small and Disadvantaged Business Utilization Program -
P.L.95-507, Section 8 and 15 of the Small Business Act of 1958, as amended. This function requires: the identification of small businesses capable of performing NRC contractual requirements; the conduct of outreach efforts designed to stimulate greater small business interest in NRC programs; and the dissemination of information to senall businesses interested in agency con-l tracting procedures.
i e
103 l
i
Procam Direction and Administration Civil Rights Act of 1964, as amended, Civil Rights Program implemented by 29 CFR Part 1613 of the Equal Employment Opportunity Commission regulations. This function requires:
obtaining and maintaining equal opportunity within the NRC; developing and preparing the agency's Affirmative Action Plan; advising and assisting in recruitment plans and activities; providing counseling and investigations of discrimination com-plaints; providing Equal Employment Opportunity training for all agency employees; coordinating activities associated with all agency civil rights matters; interacting with community groups concerned with equal opportunity and human rights in the workplace; and monitoring compliance to Title 6 of the Civil Rights Act by those benefitting from the Agency's Federal Financial Assistance Program (Agreement States and grant recipients).
Federal Women's Program - This function expands and enhances opportunities for NRC women employees, and reforms policies and practices which serve as barriers; identifies underrepre-sentation and underutilization of women in the workforce, and recommends corrective action; participates in internal per-sonnel management evaluation and recruitment actions; and maintains communication between women's organizations and agency management.
OFFICE OF INFORMATION RESOURCES MANAGEMENT i
FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
0 0
0 (Staff)
(112)
(117)
(114)
(114)
The Office of Information Resources Management (IRM) manages and directs all information resources programs at the NRC including automatic data processing, telecommunications, docu-ment control, records management, records services, and the library; advises the Executive Director for Operations and the Commission on the use and application of automated systems to meet N R C's needs for the processing, distribution, and control of information; and develops policies, programs, and procedures in support of these responsibilities.
104
m Program Direction and Administration The office includes the following functions:
Computer and Telecommunication Services Provides all _ information technology-related product evaluation and acquisition, and all systems development to assure the most effective delivery of services to NRC management and staff.
Major activities associated with Computer and Telecommunications Services include information systems, automatic data processing hardware and software acquisition, telecommunications, and data administration.
Information Support Services l
l Provides computer and telephone support enhancing NRC's oper-l ation of advanced information technology and control of the information flow throughout NRC.
Activities associated with information Support Services include information technology i
support, library support, computer and telephone operations, document control system, records management, and records services.
OFFICE OF RESOURCE MANAGEMENT FY 1986 FY 1987 FY 1988 F'/ 1989 Actual Estimate Estimate Estimate Funds
$ 455
$ 1,300 897 819 (Staff)
(92)
(87)
(85)
(84) l The Office of Resource Management (RM) provides budgetary and fiscal management for the agency, including the development and maintenance of a financial control system and a system of
(
accounting designed to conform to the standards prescribed by l
the Comptroller General; management information and analyses for a variety of users within the agency.
i it provides analyses to assess the relationship between program l
workload and resource allocation; is the agency focal point for cost analyses; issues various periodic and special reports for use by agency offices, Congress, other parts of the government and the public; and manages and coordinates special projects, i
105
~
Program Direction and Administration including Congressionally mandated reports.
The office includes the following functions:
BUDGET AND ANALYSIS Provides agency senior management with analyses of policy, program and resource issues. Develops and maintains policies, procedures, and operations to formulate and execute approved NRC budgets; develops and administers NRC authorization and appropriation legislation; presents budget estimates to the EDO, Commission, OMB, and Congress; designs and develops systems and criteria for resource planning and control; performs cost analysis of NRC proposed rules; and assists NRC offices in use of sound statistical practices. Maintains liaison with OMB and Congressional Committees.
ACCOUNTING AND FINANCE Prosides for carrying out the agency's financial management responsibilities by developing and administering
- policies, principles, standards, and procedures for financial and cost accounting, financial management,'
- pricing, and license fee management; maintaining accounting and internal controls over agency appropriations; maintaining centralized payroll and travel accounting and reporting functions; maintaining central-ized government and commercial accounting and reporting; developing and maintaining the agency's financial management information systems; authorizing all foreign and change-of-station travel as well as headquarters domestic
- travel, coordinating relocation services and headquarters issuance of airline tickets; preparing fee regulations, fee schedules, analyzing licensing costs for determining fee base, and assuring fee payments; maintaining liaison with the General Accounting
- Office, the Treasury Department, and other agencies on financial procedures and related matters; and developing policies, standards, and practices governing cost principles and other financial arrangements under agency contracts.
106
Program Direction and Administration OFFICE OF ADMINISTRATION FY 1986 FY 1987 FY 1988 FY 1989 Actual Estimate Estimate Estimate Funds 0
0 0
0 (Staff)
(320)
(289)
(280)
(277)
The Office of Administration (ADM) provides the administrative and logistical support services for headquarters and some serv-ices for the regional offices. The services provided to all segments of the agency include: administration of the NRC Personnel Management Program; contracting and purchasing activities for the agency; transportation; space acquisition and utilization, including NRC headquarters consolidation; providing for the security of facilities and safeguarding of classified and sensitive unclassified documents; administration of the Free-dom of Information Act (FOIA) and Privacy Act activities; and administration of a system of 112 local public document rooms throughout the United States.
It provides printing and reproduction services for the agency; coordinates activities in support of headquarters consolidation into the White Flint complex; manages headquarters administrative support funds; Employee Development and Training Support; direction of the Occupational Health and Safety Program and the agency's Alcohol and Drug Abuse Program; and other agency-wide services.
ADM also manages the NRC Management Directives System and t
coordinates the NRC Differing Professional Opinion (DPO) prog ram.
The decreases in staffing are based on increased efficiencies in providing support services expected to be achieved as NRC consolidates its headquarters operations.
The office includes the following functions:
ORGANIZATION AND PERSONNEL Provides for personnel management and organization activities, include staffing and placement services, recruitment, position classification ar.d evaluation, personnel policy and program development, Federal labor relations and employee relations
- services, organization and staffing
- analyses, management analyses, and the agency's position management program; and provides secretarial
- services, liaison, and support to the Executive Resources Board and its subgroups.
107
Program Direction and Administration FACILITIES AND OPERATIONS SUPPORT Provides mail and messenger services; develops and administers programs for space acquisition and utilization, motor vehicle operation, building management, and transportation services; and develops and administers programs for property management, supply and warehouse operations, and office and equipment moves.
PUBLICATIONS SERVICES Provides centralized agencywide publication control and process-
- ing, technical writing and editing service, and translation service; publishes agency books, regulatory and technical reports, pamphlets and periodicals; orovides direction and co-ordination for agencywide provisio;. of document composition, printing, graphics, photography, and audiovisual and related services.
RULES AND RECORDS Develops policies, procedures and rules for implementing the
- FOIA, Privacy
- Act, and the Regulatory Flexibility Act; develops and reviews amendments to agency regulations and peti-tions for rulemaking; provides advice and assistance to offices and the public regarding regulations and procedures for filing petitions for rulemaking; and directs and coordinates Local Public Document Room activities near reactor sites throughout the United States.
CONTRACTS Develops and implements agencywide contracting and financial j
assistance policies and procedures; and directs and coordinates contracting and financial assistance activities, including selection, negotiation, administration and closecut of con-tracts. It provides advice and assistance to program officials on procurement regulations and requirements and methods of I
meeting program objectives consistent with such requirements; I
executes and modifies contracts, financial assistance relation-ships and interagency actions; settles claims and terminations; and performs other normal duties of a contracting office speci-fied in the Federal Acquisition Regulations.
SECURITY l
l l
Administers the agency's overall security program, including the l
safeguarding of Restricted Data and National Security information documents or material (e.g.,
classified matter) at NRC l
108
Program Direction and Administration Headquarters and Regional Offices, and at contractor, licensee and other facilities containing such matter; the safeguarding of sensitive unclassified information; the physical protection of NRC Headquarters, Regional Offices, and other agency locations; and the processing and maintenance of access authorizations (clearances) for agency employees, consultants, contractors, licensees and others.
EMPLOYEE DEVELOPMENT AND TRAINING Plans and develops policies and programs for the training and development of agency executives and Senior Executive Service candidates; provides management and supervisory training and development programs to improve managerial performance; administers the Intern and Upward Mobility programs; and develops training and education programs in response to Commission, statutory, and interagency requirements.
It also assists in identifying training needs and programs; develops and administers the agencywide training budget.(ex-cluding the Technical Training Center programs); and provides career development counseling.
OCCUPATIONAL SAFETY AND HEALTH Administers the agency-wide occupational health and safety program to provide a safe working environment for employees and the public using agency facilities.
l I
109
rogram Direction and Administration THIS PAGE INTENTIONALLY LEFT BLANK 110
a
-.-g
a A
4 l
l SPECIAL SUPPORTING TABLES l
l
--.A._
mA a _-. -
A 4__-
=a a
A i
i l
l l
I i
l l
\\
)
l J
l l
--vrew-em
LEGISLATIVE PROGRAM PROJECTIONS (Dollars in Millions) i FY 1986 FY 1987 FY 1988 FY 1989 FY 1990 FY 1991 FY 1992 Actual Estimate Estimate Estimate Estimate Estimate Estimate NRC Total Budget Authority
$410
$410
$428
$423
$423
$423
$423 Budget Outlays
$421
$412
$423
$423
$423
$423
$423 i
I,
{
111
, -, -,,. -, - - -. - ~, - - + - ---
,,-yem-
---~_e.,,%,----..--.-,--r.-%-w-.---,-.vw,,w-mw--,,
,-,r--,w
,-r--e
--=yr-
,-,-wwww w
P Consulting Services-Obligations Account Title Type FY 1986 FY 1987 FY 1988 FY 1989 Nuclear Reactor Contractual Services 0
0 0
0 l
Regulation Personnel Appointments 30 30 30 30 Advisory Committee l
Consultants 0
0 0
0
]
Total 30 30 30 30 Nuclear Material Contractual Services 0
0 0
0 Safety and Personnel Appointments 40 375 240 140 1
Safeguards Advisory Committee Consultants 5
10 10 10 Total 45
$ 385
$. 250
$ 150 f
i inspection and Contractual Services 0
0 0
0 Enforcement Personnel Appointments 0
0 0
0 Advisory Committee Consultants 0
0 0
0 i
Total 0
0 0
0 Nuclear Regulatory Contractual Services 0
0 0
0 Research Personnel Appointments 0
-0 0
0 Advisory Committee i
Consultants 0
0 0
0 Total 0
0 0
0 Program Technical Contractual Services 0
0 0
0 j
Support Personnel Appointments 0
0 0
0 Advisory Committee i
I Consultants 121 125 125 125 Total
$ 121
$ 125
$ 125
$ 125 i
Program Direction Contractual Services 56 75 75 75 and Administra-Personnel Appointments 53 31 31 31 j
l tion Advisory Committee l
Consultants 0
0 0
0 l
Total
$ 109
$ 106
$ 106
$ 106 g
i Total Nuclear Contractual Services 56 75 75 75 Regulatory Personnel Appointments 123 436 301 201 l
Commission Advisory Committee Consultants 126 135 135 135 l
Total
$ 305
$ 646
$ 511
$ 411 I
i 112
d Consulting Services MAJOR PROGRAM AREAS NUCLEAR REACTOR REGULATION Personnel appointments are used to provide engineering and scientific exper-tise not otherwise available to NRR to obtain advice / opinions on highly complex and controversial areas to enhance the quality and diversity of views and to provide outside independent viewpoints that lend greater credibility and technical support to agency licensing positions.
NUCLEAR MATERI AL SAFETY AND SAFEGUARDS Personnel appointments are used to provide (1) technical advice on fuel processing operations, including high-level waste solidification activities; (2) advice on review of critical technical plans and data resulting from these plans associated with repository site performance and evaluation; (3) technical advice between the time existing contracts expire and initiation of the NRC Federally Funded Research and Development Center; and (4) advice on staff implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985, resolving the mixed waste issue, and assessing financial responsibilities of NMSS licensees.
Advisory committee con-sultants include the Adviscry Committee on Medical Uses of isotopes which considers medical questions referred to it by NRC
- staff, renders expert opinion regarding medical uses of radioisotopes, and advises on matters of policy.
PROGRAM TECHNICAL SUPPORT Advisory committee consultants provide advice and expert opinions to the i
membership of the Advisory Committee on Reactor Safeguards (ACRS), in conducting project reviews, operating license reviews, generic reviews, and safety assessments for power reactors.
These consultants also advise the ACRS on matters pertaining to high-level radioactive waste management.
PROGRAM DIRECTION AND ADMINISTRATION Contractual services are used to provide advice to the agency on strategic long-range planning.
Personnel appointments provide the agency with advice and assistance (1) concerning the retrieval and maintenance of documents in the Local Public Document Rooms; (2) in evaluating current and proposed automated document control systems; (3) in maintaining and organizing reference technical
- codes, standards, and reports collection; (4) in reviewing certain security clearance applications; and (5) in evaluating proposed revisions for security-related standards, procedures, rules, and regulations.
113
l U.S. NUCLEM REGULATORY COMMISSION
SUMMARY
OF HEAD 0UARTER3 - REGIONAL RESOURCES i
(DOLLMS IN THOUSANDS, EXCEPT MOLE [0LLMS IN KARRATIVE MiERIAL.
I STMF IN FILL-ilNE EOL'! VALENT)
FY 1986 ACT'JAL
- FY 1967 ESil MTE : FY 1938 ESTISTE : FY 1989 ESTi mTE DOLLARS (STAFF) : DOLLMS (STEF) : IOJ.MS (STAFF) : ICLLARS (STAFF)
HEADGUARTERS PROGRAMS I
NUCLEAR REACTOR REGULATION $74.813 619 574.360 593 : $76.470 557 : $74,220 537 NUCLEAR MTERIAL SAFETY AND SAFEGUARDS 34.795 300 36,370 306 :
37.120 289 : 36,055 282 INSPECTION AND EhFORCEMENT 34.265 233 36,154 233 33,524 227 :
36.054 217
.NJCLEAR REGULATORY RESEARCH 123.785 198 : 111.655 150 119.675 172: 125.260 172 Fn00 RAM TECHNICAL SUPPORT 30.192 353 :
32.544 341 :
32.347 317 :
32,520 306 PROGRM DIRECTION AND ADMINISTRATION 42 054 689 :
43.141 647 :
44.433 631 :
43.700 625 Sl% TOTAL
$339.909 2,402 : $334.254 2.300 $34?.074 2.193 : $347.809 2.139 REGIONALPROGRAMS NUCLEAR REACTOR REGULATION
$5,030 78 :
$6,450 93 :
$7.075 98 :
$6.810 93 NUCLEAR MATERIAL SAFETY AND SAFEGUARDS 3,737 55 4.053 57 :
4.060 55 :
3.930 55 INSPECTION AND ET ORCEE NT 60,133 893 :
64,417 903 :
66 356 687 : 62.871 871 PROGRAM TECHNICAL SUPPORT 1,094 17 1,100 16 :
1.235 17 :
1.180 17 PROGRM DIRECTICN AND ADMINISTRAi!ON 0
0:
O 0:
0 0
0 0
s SLETOTAL
$69.994 1.043: $76.020 1,069 : $78.726 1 057 : $74.791 1.041 TOTAL PROCRAMS NUCLEAR REACTOR REGULATION $79.843 697 : $30.810 686 : $$3.545 655 : $31 030 635 MJCLEAR MATERIAL SAFETY AND SAFEGUARDS 38 532 355 :
40.423 363 :
41.180 344
- 39. % 5 337 INSPECTION AND ENFORCE 1NT 94.398 1.131 : 100.571 1,136 : 104.880 1,114 :
98,925 1,083 NUCLEAR REGULATORY RESEMCH 123.785 198 : 111.685 160 : 119.675 172 : 125,260 172 PROGRM TECHNICAL SUPPORT 31,266 375 8 33.644 357 :
34.032 334 :
33.700 523 PROGRM DIRECTION AND A[ MINISTRATION 42.054 689 :
43.141 647 :
44.438 631 :
43,700 625
-~
TOTAL
$409.903 3.445 : $410,274 3.369 : $427.800 3.250 : $422.600 3.130
=================:====================:====================:============r-=s
114
g PO====
u t uCua...out.Toa, c-...ON i aEPOa r Nu
.E a, A..-
r,oC.
, v., N..., ~,
'"',">' /'
818UOGRAPHIC DATA SHEET d
2 E N TauC.ON ON T...vi s.
NUREG-1100, Volume 3 2 TsVLE AND:suSieTLE 3 LE AVE BL ANK Budget Estimates Fiscal Years 1938-1989
/. oAre auOa7 Co PurEo juON,-
l
,aAn a cut Oa*
Janyhry 1987 f
. oAre auOar issuEo f
l
.ONr-vEA.
tWnua ry 1987 F PEW'ORMiNG ORGANA 2 AI10 AME AND M AILING ACOPESS tractosele C.*#
[ PROJECT /, ASKNWOAK UNsi NuwsER Division of Budg and Analysis
(
Office of Resourc -
nagement
- *'N oa oa AN' Nv==ca U.S. Nuclear Regula ry Commission Washington, DC 2055 10 $PON50 RING ORGANi2 AreON NAwE AND ING ADDRESS flac4smale Coes its YvPE OF REPORT Division of Budget and A ysis FY 1988-1989 Congressonal Office of Resource Managem t Budget Submission U.S. Nuclear Regulatory Co.
sion
,,,,,,,co,,,,,,,_e,,,,,
Washington, DC 20555 10/01/87 - 09/30/89 12 SUPPLEMENTARY NOTES 13 LOS TR ACT d200 wores er was This report contains the fiscal yea budge justifications to Congress. The budget provides estimates for salaries and pen s for fiscal years 1988-1989.
l l
- s i
10 DOcuwENT ANALvs#5 - e ut vWORDS-DESCniPTOMS IS A v AaL Asiksi y ST ATE MENT i
Unlimited
'6 SECURITv CL A55#F6 CATION
\\,
fre eeper
.,0,NTi...as,OP.N.No.o fiavs Unclassified a r n,
Uncla
,, v...s sified O,, Ages s 8 PA'CE C
i J
120555078877 1 1AN NOM DV 0F PUB SVCS POLICY & PUB MGT BR-PDR NtJREG W
HINGTON DC 20555
- i 1
e
~4 i
- a
.$ 1 l'
l i IS I
E 5