ML19308B893
| ML19308B893 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/16/1979 |
| From: | Lanning W NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001170540 | |
| Download: ML19308B893 (10) | |
Text
r DRAFT WDLanning:me 7/16/79 REGULATORY REQUIREMENTS REVIEW COMMITTEE
SUMMARY
The RRRC considers matters that could have a substantial impact on operating plants, plants undergoing an operating license review, plants under construction, plants undergoing a construction permit review, appproved standard designs, standard designs under review, approved sites, sites under review for early approval and on new applications of future plants, designs, and sites.
Thus, the RRRC's recomendations are to:
(1) reject or defer the proposed changes; (2) implement the proposed change on new and future applications only (a Category I matter); (3) implement the proposed change on new and future applications and evaluate whether operating plants and plants with construction permits should be backfitted on a case-by-case basis (a Category II matter); and (4) implement the proposed change on all applicable plants, designs and sites (a Category III matter). A more complete description of the Cagegory I, II and III matters is as follows:2_/
The regulatory position of each approved proposed guide (or proposed guide revision) will be characterized by the Committee as to its backfitting potential, by placing it in one of three categories:
Category I - Clearly forward fit only.
No further staff consideration of possible backfitting is required.
Category II - Further staff consideration of the need for backfitting appears to be required for certain identified items of the regulatory position -- these individual issues are such that existing plants need to be evaluated to determine their status with regard to these safety issues in order to determine the need for backfitting.
2] Meeting Sumary-of the RRRC Meeting No. 31 dated July 11, 1975.
l 1
8001170 0
2 Category III - Clearly backfit.
Existing plants should be evaluated to determine whether identified items of the regulatory position are resolved in accordance with the guide or by some equivalent alternative.
HIGHLIGHTS 1.
Established March 1974 by M. Muntzing Press Release 3/8/74 Memo to Licensing Staff from O' Leary, 4/2/74 Memo to Reactor Projects' Staff from Giambusso, 4/2/74 Memo to Technical Review Staff from Hendrie, 4/2/74 2.
Backfitting criteria / categories defined July 11, 1975 RRRC meeting 31, July 11,1975 Note that these categories are guidance to staff for implementing staff position requirements, not for implementation section of Regulatory Guides.
The regulatory position in R.G..is characterized by placing it in one of the three categories.
Note that there are no criteria established for placing issues in the categories.
3.
Clarification of the implementation of Regulatory Guide documented September 1975.
RRRC meeting 31, September 24, 1975 Memo, A. Giambusso to E. Case, REGULATORY GUIDE IMPLEMENTATION, 6/24/74 Concluded that approval of RG should be uncoupled from con-sideration of their backfit applicability to avoid delay of RRRC approval.
R.G. implementation section should, in general, only reflect
't forfNt considerations, Exceptions handled on case-by-case basis. Therefore, RRRC categorization should not appear in Guide.
3 4.
Summary of RRRC presented to Commission on or about July 1977 by R. DeYoung.
(copy of vugraphs)
Discussed charter of RRRC, decision process, summary of decisions (number of category 3 items actually less than presented), and recent changes to process.
Changes included RRRC consideration of RG and SRPs only after public comments are solicited on RG and value/impet statement.
Notice of meetings published in Federal Register with public opportunity to appeal decisions, and implementation of decisions delayed until they are made public.
5.
Acknowledgement that present program for controlling "ratcheting" has been effective and minimized backfit changes.
Letter, E. Case to S. Freeman, TVA, April 6,1978 Implicit referenced NRR Office Letter Number 9 in response to question on reevaluation of safety issues for standard and docketed plants. Referenced the RRRC for controlling changes to Regulatory requirements.
Pointed out that seven out of more than 200 items considered by RRRC were backfitted. An additional 22 (
ik2)itemshadbeenidentifiedforpossiblebackfitting.
6.
Implementation of RRRC Recommendations Memo, Boyd to Denton and Mattson, February 10, 1978 Memo, Boyd to
, March 28, 1978 Memoranda addressed backlog of Category 2 and 3 matters.
Listed plants which generic letter will be sent requesting status of compliance with request to these categories (listed specific RGs and BTPs). TMI-2 and DB-1 were to be resolved by D0R. Only 5 operating plants were to be addressed.
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4 7.
Coninents on RRRC Category 2 Items Memo, Varga to Vassallo, October 13, 1978 Recommended deletion of Category 2 items.
Postulated that Category 2 was established because the RRRC could not ascertain whether or not issue required backfitting. Appears recommendation was result of questions raised in September 1978 memorandum from Chilk to Gossick regarding changes in reactor licensing criteria and requirements.
Noted a decrease in issues after RRRC required staff intentions with respect to backfitting requirements. Recommended against RRRC documenting the basis for decisions, especially those which are judgemental.
8.
Need for Changes in Reactor Licensing Criteria and Requirements SECY-79-8,
Subject:
Improving the Process for Determining the Need for New Reactor Requirements, January 2, 1979 Responds to Chilk to Gossick memorandum of September 1,1978.
Discusses role of RRRC. Staff attempted to define the criteria used by RRRC for categorizing issues.
Identified changes in current RRRC practices (listed in Item 4).
Discusses " Substantial, Additional Protection" in Section 50.109(a).
Identifies an NRR Category IV which implements licensing requirements prior to RRRC review of issue.
9.
Current members of RRRC 1.
E. G. Case 2.
R. B. Minogue 3.
R. C. DeYoung l
i 4.
V. Stello 5.
R. J. Mattson 6.
N. C. Moseley i
7.
H. D. Thornburg 8.
T. E. Murley j
R. S. Boyd was a member until June 1.
5 10.
IssuesConsideredbyRRRCwhichmayhavegIelationship*toTMI-2 Accident (i.e., backfitting) (In addition to Enclosure 1 from Boyd Memorandum (see item 6 above))
A.
R.G.1.97 - Instrumentation For Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following the Accident Meeting 37,10/3/75, Category 1 Meeting 62, 5/17/79, Revision 1: Category 3 for applications undergoing Q-2 Category 2 for Operating Plants B.
ATWS, NUREG 0460, Volume 3 C.
R.G. 8 JB, " Radiation Training at Nuclear Power Plants,"
Meeting 80, 11/21/78 - Referred back to Staff for backfit recommendations D.
R.G.1.134, Rev.1, " Medical Evaluation of Personnel Requiring Operator Licenses" Meeting 80, 11/21/78 - Category 1 E.
DRAFT, " Criteria for Electric, Instrumentation & Control Portions of Safety Systems" Meeting 79, 10/19/78 - Returned to staff for backfit recommendations F.
SRP 13 & 13.4 " Management and Technical Support Organization" and
" Operational Review" Meeting 79, 10/19/78 - Category 1 G.
Draft R.G., " Functional Specification for Safety-Related Valve Assemblies in Nuclear Power Plants" Degree of relevancy has yet to be determined.
6 Meeting 76, 6/20/78 - Returned to Staff for rework of value/ impact assessment.
H.
R.G.1.68, Rev. 2
" Initial Test Programs for Water-Cooled Nuclear Power Plants" Meeting 76, 6/20/78 - Category 1 Note: There is no R.G. addressing Testing of Feedwater and Condensate Systems for PWRs.
R.G.1,68.1 is for BWRs only.
I.
Implementation Procedures for Division 1 R.G.
Meeting 75, 12/31/78 - Approved with Categorization J.
Standard Radiological Effluent Technical Specifications Meeting 74, 5/16/78 - Category 3 (implicit)
K.
R.S. B.T.P. " Reactor Coolant System Overpressurization Protection" Meeting 72, 3/14/78 - Category 1 for OLs prior to 3/14/78 Category 3 for all others L.
R.G. 1.7, " Control of Combustible Gas Concentrations in Containment Following Loss-of-Coolant Accident" Meeting 71, 1/31/78 - Category 1 M.
R.G.1.141 (For Comment), " Containment Isolation Provisions for Fluid Systems" Meeting 71, 1/ 31/78 - Category 2 N.
SRP 5.4.7 and BTP 5-1, " Residual Heat Removal System" Meeting 71, 1/31/78 - Category 2 Meeting 69, 11/29/77 - Referred back to staff to rework Implementation Section.
Staff had recomended backfit.
Meeting 50, 6/24/76 - First Revision to SRP 5.4.7 - Category 2 l
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7 0.
R.G.1.32, Rev. 2, " Criteria for Safety Related Electric Power Systems for Nuclear Power Plants" Meeting 57,1/14/77, Cagegory 1 P.
Amendment to 10 CFR Part 50 to require Periodic Updating of FSAR's Meeting 45, 2/27/76.
Referred back to staff for rework and resubmittal. Was not considered subsequently.
Q.
R.G. 1.105 " Instrument Spans and Setpoints" Meeting 54,12/21/76, Category 2 Meeting 31, 6/25//6, Category 1 Although TS deviations were the most frequent abnormal occurrence between January 1972 to 1973.
R.
EVALUATION OF TECHNICAL COMPETENCE OF UTILITY APPLICANTS Meeting 14, 10/4/74 - Referred back to Staff without discussion.
No future consideration Note: Currently, final evaluation of Technical competency of applicants is determined by LPM with inputs from 0AB.
S.
BP on Auxiliary Feedwater Pump Drives Meeting 9, 8/12/74 - Recommended diverse energy supplies for AFW.
Imposed for application for which SER not written.
OSD should investigate backfit problem.
Note:
May be important to Oconee I, II, III and TMI-l T.
R.G.1.4, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident (for Pressurized Water Reactors" Meeting 4, 5/24/74 - Category I (implicit)
- 11. OBVIOUS ISSUES NOT ADDRESSED BY RRRC A.
Initial SRPs B.
Generic Issues
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I CATEGORY 2 NO.
ITEM SUBJECT l.
RG 1.27, Revision 2 (1/76)
Ultir. ate Heat Sink for Nuclear Power Plants 9
2.
RG 1.52, Revision 1 n
(7/76)
Design, Testing, and Maintenance n..
Criteria for Engineered Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants 3.
RG 1.59, Revision 2 (8/77)
Design Basis Floods for Nuclear Power Plants J '.
4.
RG 1.63, Revision 1 (5/77)
Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants 5.
RG 1.63, Revision 1 (1/77)
Initial Test Programs for Water-Cooled Reactor Power Plants 6.
RG 1.91, Revision 1
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(Draft)
Evaluation of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants i-7.
RG 1.97, Revision 1 (8/77)
Instrumentation for Light ' ater-W Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident 8.
RG 1.100 (3/76)
.l,:
Seismic Qualification of Electric Equipment for Nuclear Power z
Plants i-9.
RG 1.102, Revision 1 g'..
(10/ 76)
Flood Protection for Nuclear PowerW P1 ants RG 1.105, Revision 1
- y 10.
(11/76)
Instrument Setpoints
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11.
RG 1.108, Revision 1 (8/77)
Periodic Testing of Diesel Generators Used as Onsite Electric Pcwer Systems at Nuclear Pcwer Plants.
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12.
RG 1.115, Revision 1
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Protection -Against 1.cw-Trijectory
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ITEM 5'_'50 E CT 13.
RG 1.117 (6/76)
Tornado Design Classification I$'
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14.
RG 1.118 (6/76)
Periodic Testing of Electric Fower and Protection Systems 15.
RG 1.124, Revision 1 Service Limits and loadinc Com-O/13/78) binations for Class 1 Linear Type Component Supports 16.
RG 1.130 (7/77)
Design Limits and Loading Com-binations for Class 1 Plate-and Shell-Type Comaonent Supports 17.
RG 1.137 Fuel Oil Systems for Standby (1/18/78)
Diesel Generators 18.
RG 8.8, Revision 2 Information Relevant to Ensuring
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(3/77) that OccuDational Radiation Ex-v.
posures at Nuclear Power Stations
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Will Be As low As Is Reasonably r?""
Achievable F-19.
BTP APCSB 9.5.1 Guidelines for Fire Protection (8/76) for Nuclear Pcaer Plants Under Review and Construction 20.
BTP MTEB 5-7 BWR Coolant Pressure Boundary e,
(7/77)
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ITEM SUBJECT 1.
RG 1.39, Revision 1 Housekeeping Requiremer.ts for (10/76)
Water Cooled Nuclear Power Plants 2.
RG 1.68.2 (1/77)
Initial Startup Test Program to Demonstrate Remote Shutdown Cap-ability for Water-Cooled Nuclear Power Plants 3
RG 1.99, Revision 1 Effects of Residual Elements on
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(4/77)
Predicted Radiation Damage to Reactor Vessel Materials 4.
RG 1.101, Revision 1 Emergency Planning for Nuclear (2/77)
Power Plants 5.
RG l.114, Revision 1 Guidance on Being Operator at the (11/76)
Controls of a Nuclear Power Plant 6
RG 1.121 (8/76)
Cases for Plugging Degraded PWR Steam Generator Tubes
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7.
RG 1.127, Revision 1 Inspection o' Water-Control (Draft)
Structures Associated with Nuclear Power Plants b.
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