ML25168A068
| ML25168A068 | |
| Person / Time | |
|---|---|
| Issue date: | 06/20/1983 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Dircks W NRC/EDO |
| References | |
| Download: ML25168A068 (1) | |
Text
MEMORANDUM FOR:
FROM:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 June 20, 1983
- w. J. Oircks Executive Oirecto R. F. Fral
, Executive Di Advisory Committee on Rea ACRS COMMENTS ON THE PRIORITIZATION OF GENERIC ISSUES During November 1982, the NRC Staff requested that the ACRS review the following with regard to the prioritization of generic issues:
- Adequacy of the numerical methodology, described in Draft NUREG-0933, that was used in prioritizing generic issues.
- Adequacy of the application of the methodology to individual generic issues.
During its 273rd meeting, January 6-8, 1983, the ACRS completed its review of the adequacy of the numerical methodology and transmitted its comments to Chairman Palladino in a \
letter dated January 11, 1983.
During ;*ts 278th meeting, June 9-11, 1983, the ACRS performed a eartial review of the adequacy of the application of the methodology to individual generic issues. Results of this partial review are contained in the follow-ing attachments:
- Attachment l -lists those items for which the ACRS agrees with the priority rankings proposed by the NRC Staff.
- Attachment 2 includes a list of items for which the ACRS agrees with the priority rankings proposed by the NRC Staff, but has comments.
- Attachment 3 contains a list of items for which the ACRS disagrees with the NRC Staff's proposed priority rankings along with the reasons therefor.
2423
W. June 20, 1983 The ACRS will continue its review of the adequacy of the proposed priority rankings for the remaining generic issues and will provide additional comments as they become available.
It is requested that the NRC Staff provide written responses to the ACRS comments identified in Attachments 2 and 3.
The ACRS may review the ade-quacy of the NRC Staff's responses during one of its future meetings.
Attachments:
As Stated 2424
New Generic 2
3 5
6 11 12 14 15 16 19 20 June 20, 1983 ATTACHMENT 1 LIST OF ITEMS FOR WHICH THE ACRS AGREES WITH THE PRIORITY RANKINGS PROPOSED BY THE NRC STAFF Issues Title Failure of Protective Devices on Essential Equipment Set Point Drift in Instrumentation Design Check and Audit of Balance-of-Plant Equipment Separation of Control Rod from Its Drive and BWR High Rod Worth Events Turbine Disc Cracking BWR Jet Pump Integrity PWR Pipe Cracks Radiation Effects on Reactor Vessel Supports BWR Main Steam Isolation Valve Leakage Control Systems Safety Implications of Nonsafety Instrument and Control Power Supply Bus Effects of Electromagnetic Pulse on Nuclear Pl ant Systems 2425
New Generic Issues (Cont'd)
Task 26 28 29 Action Items A-14 A-15 A-19 A-20 A-22 A-25 A-28 A-32 A-33 A-34 Pl an June 20, 1983 ATTACHMENT 1 (Cont'd)
Title Diesel Generator Loading Problems Related to SIS Reset on Loss of Offsite Power Pressurized Thermal Shock Bolting Degradation or Failure in Nuclear Power Pl ants Title Flaw Detection Primary Coolant System Decontamination and Steam Generator Chemical Cleaning Digital Computer Protection System Impacts of the Coal Fuel Cycle PWR Main Steamline Break - Core, Reactor Vessel, and Containment Building Response Non-Safety Loads on Class IE Power Sources Increase in Spent Fuel Pool Storage Capacity Missile Effects NEPA Review of Accident Risks Instruments for Monitoring Radiation and Process Variables During Accidents 2426
Task Action Plan Items (Cont'd}
A-35 A-37 A-38 B-3 B-5(a)
B-7 B-9 B-14 B-21 B-22 B-23 B-24 B-25 8-28 B-29 B-31 B-33 8-34 8-35 June 20, 1983 ATTACHMENT 1 (Cont'd}
Title Adequacy of Offsite Power Systems Turbine Missiles Tornado Missiles Event Categorization Ductility of Two Way Slabs and Shells Secondary Accident Consequence Modeling Electrical Cable Penetrations of Containment Study of Hydrogen Mixing Capability in Contain-ment Post-LOCA Core Physics LWR Fuel LMFBR Fuel Seismic Qualification of Electrical Mechanical Components Piping Benchmark Problems Radionuclide/Sediment Transport Program Effectiveness of Ultimate Heat Sinks Dam Failure Model Dose Assessment Methodology Occupational Radiation Exposure Reduction Confirmation of Appendix I Models for Calcula-tions of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors 2427
Task Action Plan Items (Cont'd)
B-37 B-38 B-39 B-40 B-41 8-42 B-43 8-44 8-45 8-48 8-49 8-51 R-55 B-56 8-57 8-58 8-60 June 20, 1983 ATTACHMENT 1 (Cont'd)
Title Chemical Discharges to Receiving Waters Reconnaissance Level Investigations Transmission Lines Effects of Power Plant Entrainment on Plankton Impacts on Fisheries Socioeconomic Environmental Impacts Value of Aerial Photographs for Site Evaluation Forecasts of Generating Costs of Coal and Nuclear Plants Need for Power - Energy Conservation BWR CRD Mechanical Failure (Collet Housing)
Inservice Inspection Crite~ia and Corrosion Prevention Criteria for Containments Assessment of Inelastic Analysis Techniques for EquilJllent and Components Improved Reliability of Target Rock Safety-Relief Valves Diesel Reliability Station Blackout Passive Mechanical Failures Loose-Parts Monitoring System 2428
Task Action Plan Items (Cont'd) 8-62 8-64 8-67 8-68 B-70 8-71 8-72 8-73 C-2 C-8 C-11 C-12 C-13 C-14 C-15 June 20, 1983 ATTACHMENT 1 {Cont'd)
Title Reexamination of Technical Bases for Establishing SLs, LSSSs, and Reactor Protection System Trip Functions Decommissioning of Reactors Effluent and Process Monitoring Instrumentation Pump Overspeed During LOCA Power Grid Frequency Degradation and Effect on Primary Coolant Pumps Incident Response Health Effects and Life Shortening from Uranium and Coal Fuel Cycles Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel Study of Containment Depressurization by Inadvertent Spray Operation to Determine Adequacy of Containment External Design Pressure Main-Steamline Leakage Control Systems Assessment of Failure and Reliability of Pumps and Valves Primary System Vibration Assessment Non-Random Failures Storm Surge Model for Coastal Sites NUREG Report for Liquids Tank Failure Analysis 2429
Task Action Pl an Items (Cont'd)
C-16 C-17 0-3 TMI Action Plan Items I. F. l I.F.2(2)
I.F.2(3)
I.F.2(6)
I.F.2(7)
I.F.2(8)
I.F.2(9)
I.F.2(10)
I.F.2(11)
II.A. 2 11.8.5(1) 11.B.5(2} June 20, 1983 ATTACHMENT 1 (Cont'd)
Title Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection Interim Acceptance Criteria for Solidification Agents for Radioactive Solid Wastes Control Rod Drop Accident Expand QA Li st Include QA Personnel in Review and Approval of Plant Procedures Include QA Personnel in All Design, Construction, Installation, Testing, and Operation Activities Increase the Size of Licensees' QA Staff Clarify that the QA Program is a Condition of the Construction Permit and Operating License Compare NRC QA Requirements with Those of Other Agencies Clarify Organizational Reporting Levels for the QA Organization Clarify Requirements for Maintenance of "As-Built" Documentation Define Role of QA in Design and Analysis Activities Site Evaluation of Existing Facilities Behavior of Severely Damaged Fuel Behavior of Core Melt 2430
TMI Action Plan Items (Cont'd)
II.B.6 II.B.7 II.B.8 II.C. l II.C.2 II.C.3 II.C.4 I I. D. 2 II.E.1.3 II.E.3.2 II.E.3.3 II.E.3.4 II.E.3.5 II.E.4.3 II.E.4.4(1)
II.E.4.4(2)
II.E.4.4(3)
II.E.4.4(4)
II.E.4.4(5) June 20, 1983 ATTACHMENT 1 (Cont'd)
Title Risk Reduction for Operating Reactors at Sites with High Population Densities Analysis of Hydrogen Control Rulemaking Proceeding on Degraded-Core Accidents Interim Reliability Evaluation Program Continuation of Interim Reliability Evaluation Program Systems Interaction Reliability Engineering Research on Relief and Safety Valve Requirements Update Standard Review Plan and Develop Regulatory Guide Systems Reliability Coordinated Study of Shutdown Heat Removal Require-ments Alternate Concepts Research Regulatory Guide Integrity Check Issue Letter to Licensees Requesting Limited Purging Issue Letter to Licensees Requesting Information on Isolation Valve Issue Letter to Licensees on Valve Operability Evaluate Purging and Venting During Normal Operation Issue Modified Purging and Venting Requirement 2431
TMI Action Plan Items (Cont'd)
II.F.3 II.H.1 II.H.2 II.H.3 II.H.4 II.J.l.l II.J.1.2 II.J.1.3 II.J.l.4 II.J.2.1 II.J.2.2 II.J.2.3 II.J.3.1 II.J.3.2 II.J.4.1 II I. A. 1. 3 ( l )
III.A.l.3(2) June 20, 1983 ATTACHMENT 1 (Cont'd)
Title Instruments for Monitoring Accident Conditions Maintain Safety of TMI-2 and Minimize Environmental Impact Obtain Technical Data on the Conditions Inside the TMI-2 Containment Structure Evaluate and Feed Back Information Obtained from TMI-2 Determine Impact of TMI on Socioeconomic and Real Property Values Establish a Priority System for Conducting Vendor Inspections Modify Existing Vendor Inspection Program Increase Regulatory Control Over Present Non-Licensees Assign Resident Inspectors to Reactor Vendors and Architect-Engineers Reorient Construction Insp~ction Program Increase Emphasis on Independent Measurement in Construction Inspection Program Assign Resident Inspectors to All Co-nstruction Sites Organizat~on and Staffing to Oversee Design and Construction Issue Regulatory*Guide Revise Deficiency Reporting Requirements Workers Public 2432
TMI Action Pl an Items
{Cont'd)
III.A.3.1(1)
III.A.3.1 (2)
III.A.3.1(3)
III.A.3.1(4)
III.A.3.1(5)
III.A.3.2 III.A.3.3(1)
III.A.3.3(2)
III.A.3.4 III.A.3.5 III.A.3.6 III.B.l III.B.2(1)
III.B.2(2) 111.0.1.2 III.O. l.3(1) 111.D.l.3(2) 111.D.l.3(3) June 20, 1983 ATTACHMENT 1 (Cont'd)
Title Define NRC Role in Emergency Situations Revise and Upgrade Plans and Procedures for the NRC Emergency Operations Center Revise Manual Chapter 0502, Other Agency Procedures, and NUREG-0610 Prepare Commission Paper Revise Implementing Procedures and Instructions for Regional Offices Improve Operations Centers Install Direct Dedicated Telephone Lines Obtain Dedicated, Short-Range Radio Communication Systems Nuclear Data Link Training, Drills, and Tests Interaction of NRC and Other Agencies Transfer of Responsibilities to FEMA The Licensing Process Federal Guidance Radioactive Gas Management Decide Whether Licensees Should Perform Studies and Make Modifications Review and Revise SRP Require Licensees to Upgrade Filtration Systems 2433
TMI Action Pl an Items (Cont'd)
III.D.1.3{4)
III.D.2.4{1)
III.D.2.4(2)
III.D.2.6 III.D.3.1 III.D.3.2(1)
III.n.3.2(2)
III.0.3.2(3)
III.D.3.2{4)
III.0.3.5(1)
IIJ..D.3.5{2)
III.D.3.5(3)
IV.C.l IV.E.l IV.E.2 IV.E.3 IV.E.4 IV.E.5 IV.H.1 June 20, 1983 ATTACHMENT 1 {Cont'd)
Title Sponsor Studies to Evaluate Charcoal Adsorber Study Feasibility of Environmental Monitors Place 50 TLDs Around Each Site Independent Radiological Measurements Radiation Protection Plans Anend 10 CFR 20 Issue a Regulatory Guide Devel op Standard Perfonmrnce Criteria Develop Method for Testing and Certifying Air-Purifying Respirators Develop Format for Data to be Collected by Utilities Regarding Total Radiation Exposure to Workers Investigative Methods of Obtaining Employee Health-Data by Nonlegislative Means Revise 10 CFR 20 Extend Lessons Learned from TMI-2 to Other NRC Programs Expand Research on Quantification of Safety Decision-Making Plan for Early Resolution of Safety Issues Plan for Resolving Issues at the CP Stage Resolve Generic Issues by Rulemaking Assess Currently Operating Reactors NRC Participation in the Radiation Policy Council 2434
Issue No:
7 ATTACHMENT 2 LIST OF ITEMS FOR WHICH THE ACRS AGREES WITH THE PRIORITY RANKINGS PROPOSED BY THE NRC STAFF, BUT WITH COMMENTS
Title:
Failures Due to Flow-Induced Vibrations Proposed NRC Staff Priority:
DROP June 20, 1983 ACRS Comments:
The Staff makes an adequate case for the types of failures they consider. However, they do not appear to have con-sidered the problem of flow-induced breaking loose of flow deflectors of the sort that the Office for Analysis and Evaluation of Operational Data (AEOD) has brought out.
Issue No; 21
Title:
Vibration Qualification of Equipment Pro7osed NRC Sta f Priority: Covered in USI A-46 ACRS Comments:
The scope appears to be too narrow.
A review of the dynamic loads to be included should be performed.
Specifically, flow-induced vibrations should be evaluated and valve dynamic loads under faulted conditions (i.e.: rapid closure of main steam isolation valves under main steamline break) should be included.
It should be noted that the scope of USI A-46 does not appear to include this issue as indicated by NUREG-0933.
2435 June 20, 1983 ATTACHMENT 2 (Cont'd)
Issue No:
23
Title:
Reactor Coolant Pump Seal Failures Pro~osed NRC Sta f Priority:
HIGH ACRS Comments:
Coolant pump seal failure is a part of the small LOCA generic category.
The utilities need to improve their ability to forstall these by design, and by better failure symptoms to signal for corrective maintenance actions. This does not appear to be a matter for NRC Staff work other than surveillance of licensee progress. Seal failures are not of more concern than LOCAs from power operated relief valve leaks or small line failures.
The rate of coolant loss is the principal issue. Suggest that minor level of Staff effort be assigned.
Issue No:
A-13
Title:
Snubber Operability Assurance Proposed NRC Staff Priority:
RESOLVED ACRS Comments:
The Staff has imposed inspection requirements on the licensed plants. Effectiveness of these measures is npt yet known.
What frequency of snubber malfunction is tolerable? Does the test and inspection requirements satisfy the reliability requirements?
To resolve this issue would require a study of failure trends over a period of time.
Should be assigned to the Institute of Nuclear Power Operations (INPO) for reporting.
Does not need Staff resources. This is only resolved in the sense that the NRC Staff believes that their requirements will make the failure rates OK.
Should be listed as "resolved with qualifications".
2436 June 20, 1983 ATTACHMENT 2 {Cont'd)
Issue No:
A-18
Title:
Pipe Rupture Design Criteria Proposed NRC Staff Priority:
DROP ACRS Comments:
This was never on the ACRS generic list but, because of the concern for pipe whip restraint problems of reliability and inspection access, it deserves attention. The Staff is ready to take a position on Westinghouse PWR primary piping that would eliminate double-ended pipe breaks as a design basis.
To be useful, this action would have to extend to all PWRs and should address other piping systems which represent the bulk of the problem.
Not worthy of effort unless the results can be made available within a couple of years. Existing Westinghouse NRs would probably not be altered by a c~ange in criteria. The problem needs attention mainly because the case for reliable pipe whip restraints is weak and it would be better to build the safety argument on ductile inelastic response of piping systems.
{The matter of most importance is the mode of rupture and potential locations.
Not all restraints need be eliminated.)
Issue No:
A-21
Title:
Main Steamline Break Inside Containment - Evaluation of Environmental Conditions for Equipment Qualification Proposed NRC Staff Priority:
The NRC Staff has codified the interim criteria {NUREG-0588) in the new Rule, 10 CFR 50.49.
The environmental conditions inside containment appear to be based on successful operation of isolation devices such as the Main Steam Isolation Valves (MSIVs), turbine stop valves, and control valves to preclude the blowdown of more than one steam generator inside contain-ment.
The reliability of these valves to perform their isolation function should be evaluated.
The ACRS will follow implementation.
2437 June 20, 1983 ATTACHMENT 2 (Cont'd)
Issue No:
A-23
Title:
Containment Leak Testing Proposed NRC Staff Priority:
REGULATORY IMPACT ISSUE ACRS Comments:
The ACRS agrees with the Staff's proposed priority, but only within the strict context of the issue as described, not with the broader context of the title of the issue.
Issue No:
B-1
Title:
Environmental Technical Specifications Proposed NRC Staff Priority:
ENVIRONMENTAL ISSUE (RESOLVED)
ACRS Comments:
The ACRS agrees with the Staff's proposed priority. However, it urges that, in revising these Specifications, the NRC Staff attempt to minimize the accompanying work load on the utilities. Data that are not necessary should not be required. Consideration should also be given to changing the title of this issue. The current title could imply that it pertains to the environmental qualification of safety-related nuclear power plant equipment.
Issue No:
Title:
Buckling Behavior of Steel Containments Proposed NRC Staff Priority:
MEDIUM ACRS Comments:
If buckling could lead to early failure of the containment in some of the core-melt scenarios, the consequences could be changed more than in the analyses limited only to design basis accidents. This might justify a higher priority.
However, research is now under way and probably cannot be accelerated much.
2438 June 20, 1983 ATTACHMENT 2 {Cont'd)
Issue No:
B-6
Title:
loads, load Combinations, and Stress limits Proposed NRC Staff Priority:
HIGH ACRS Comments:
This continues to be a matter of controversy between the Staff and licensees.
It is a broader aspect of the issue A-18, "Pipe Rupture Design Criteria," applying to all structures. This has to be dealt with probabilistically.
The work to date is confusing and the requirements lack consistency.
Needs Staff work but should address all types of structures (piping, containments, supports, equipment, instrumentation, and controls) as influenced by structural loads.
Issue No:
B-16
Title:
Protection Against Postulated Piping Failures in Fluid Systems Outside Containment Proposed NRC Staff Priority: Covered in A-18 which has a priority ranking of DROP.
ACRS Comments:
Requirements for these piping failures have been in place for a long time but questions have been raised about the interpretation and applicability of the requirements to older plants.
The issue needs clarification. The Interim Reliability Evaluation Program {IREP) studies should indicate what is needed.
No current basis exists for judging need for priority attention.
2439 June 20, 1983 ATTACHMENT 2 (Cont'd)
Issue No:
B-26
Title:
Structural Integrity of Containment Penetrations Proposed NRC Staff Priority:
MEDIUM ACRS Comments:
If the research on penetration integrity in severe accidents shows that the penetrations are weak spots and containment is breached at lower pressure than gross failure, the consequence estimates in the Staff's analyses may be in-creased significantly. The cost of a fix might also be increased greatly. For these reasons, it is hard to prioritize the narrow issue defined here.
MEDIUM may be OK for now, but the more general (and probably more important) issue of containment and penetration is clearly of HIGH priority.
Issue No:
B-27
Title:
Implementation and Use of Subsection NF of the ASME Code Proposed NRC Staff Priority:
LICENSING ISSUE ACRS Comments:
This requirement for structural supports is intended to assure adequacy of materials on which Code vessels are supported. This needs follow-up by the Office of Inspection and Enforcement (IE) and should be covered in the Interim Reliability Evaluation Program studies.
Issue No:
B-47
Title:
Inservice Inspection of Support Classes 1, 2, 3 and MC Components Proposed NRC Staff Priority:
DROP ACRS Comments:
This issue is not clear. The need for inspection depends on the safety concerns.
The Staff needs to clarify the issue.
2440 June 20, 1983 ATTACHMENT 2 (Cont'd)
Issue No:
C-1
Title:
Assurance of Continuous Long-Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment Proposed NRC Staff Priority:
RESOLVED ACRS Comments:
This problem appears to be resolved by the codification of NUREG-0588 and the Division of Operating Reactor (DOR)
Guidelines.
Requirements have been established and are being implemented.
Apparently, during the equipment qualification evaluation, maintenance procedures are reviewed.
However, details of the NRC Staff requirements are not known.
In addition, this issue appears to be limited to moisture ingress through damaged hermetic seals. Other areas, such as moisture ingress through conduits should be evaluated.
Issue No:
C-7
Title:
PWR System Piping Proposed NRC Staff Priority:
RESOLVED ACRS Comments:
The interpretation of this issue is unclear.
BWR piping systems have problems but PWRs have no identifiable diffi-culties unless they are in pressure-letdown circuits.
Issue No:
C-10
Title:
Effective Operation of Containment Sprays in a LOCA Proposed NRC Staff Priority:: RESOLVED ACRS Comments:
It is not clear that the evaluation of damage to equipment by inadvertent actuation has been fully resolved. The documents cited as resolving this issue (SRP 6.5.2 and ANSI/ANS 56.5-1979) do not address damage to equipment.
It should be noted also that chemical addition systems for containment spray are considered optional.
2441 June 20, 1983 ATTACHMENT 2 (Cont'd)
Issue No:
111.D.1.4
Title:
Radwaste System Design Features to Aid in Accident Recovery and Decontamination Pro~osed NRC Sta f Priority:
DROP ACRS Comments:
Experience shows that *radwaste systems in existing nuclear power plants are inadequate to meet post-accident decon-tamination requirements. Although this situation does not justify backfitting such systems on existing plants, the ACRS believes that this issue should be "flagged" for reconsideration if and when applications for construction permits are forthcoming.
2442
Issue No:
B-32 ATTACHMENT 3 LIST OF ITEMS FOR WHICH THE ACRS DISAGREES WITH THE PRIORITY RANKINGS PROPOSED BY THE NRC STAFF June 20, 1983
Title:
Ice Effects on Safety-Related Water Supplies Proposed NRC Staff Priority:
LICENSING ISSUE ACRS Recommendation:
MEDIUM Reasons:
The ACRS believes that interference with supply of cooling water to safety-related equipment could decrease the reliability of ultimate heat sink to adequately cool the core.
An evaluation is required to determine what contribution a reduction in ultimate heat sink reliability makes to overall core melt.
Issue No:
I.F.2(1)
Title:
Assure the Independence of the Organization Performing the Checking Function Proposed NRC Staff Priority:
MEDIUM or HIGH Reasons:
Why is this issue ranked LOW when significant IE resources are being expended on related QA initiatives, particularly those looking at designated representatives and third party audits?
2443 June 20, 1983 ATTACHMENT 3 (Cont'd)
Issue No:
I.F.2(4)
Title:
Establish Criteria for Determining QA Requirements for Specific Classes of Equipment Pro7osed NRC Sta f Priority:
MEDIUM or HIGH Reasons:
Why is this issue ranked LOW when resources are being expended in this area? This issue is being addressed by the study required under P.L. 97.415, Section 13b(l). The Commission is required to report to the Congress with the results of that study by April 1984.
The Staff has sche-duled study completion accordingly.
IE also has ongoing research related to a graded QA approach to assuring plant quality.
In addition, the ACRS has expressed its interest in this general area (Ref. NUREG-0963, Section 2.3).
Issue No:
I.F.2(5)
Title:
Establish Qualification Requirements for QA and QC Personnel Proposed NRC Staff Priority:
MEDIUM or HIGH Reasons:
Why is this issue.ranked LOW when significant IE resources are being expended on related QA initiatives, particularly those related to the qualification and certification of QA/QC personnel?
2444 June 20, 1983 ATTACHMENT 3 {Cont'd)
Issue No:
II.A.1
Title:
Siting Policy Reformulation Proposed NRC Staff Priority:
MEDIUM ACRS Recommendation:
LOW Reasons:
Because of the lack of applications for construction permits for new nuclear power plants, and the existence of a regulatory basis for reviewing and approving sites for such plants, the ACRS recommends that consideration be given to downgrade the priority of this issue from MEDIUM to LOW.
Issue No:
II.B.5(3)
Title:
Effects of Hydrogen Burning and Explosions on Containment Structure Proposed NRC Staff Priority:
MEDIUM ACRS Recommendation:
HIGH Reasons:
Why is this ranked MEDIUM in view of the fact that extensive and expensive research on this subject is either in progress or planned?
2445 June 20, 1983 ATTACHMENT 3 (Cont'd)
Issue No:
III.D.2.1
Title:
Radiological Monitoring of Effluents Pro~osed NRC Sta f Priority:
MEDIUM or HIGH Reasons:
The ACRS is concerned that the NRC regulations currently do not require that monitors for airborne effluents be in duplicate.
As a result, when such monitors are out of service, little or no information on release to the environ-ment would be available. Although frequently both low-range (for routine releases) and high-range (for accidental releases) monitors are available in the same effluent line, the low-range units would provide no useful information for high-range releases.
In addition, the Subcommittee believes that the high-range instruments should contain the capabi-lities for specific radionuclide analyses.
2446