ML19308C933
| ML19308C933 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/06/1979 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.027, RTR-REGGD-01.052, RTR-REGGD-01.056, RTR-REGGD-01.059, RTR-REGGD-01.063, RTR-REGGD-01.091, RTR-REGGD-01.097, RTR-REGGD-01.099, RTR-REGGD-01.101, RTR-REGGD-01.102, RTR-REGGD-01.108, RTR-REGGD-01.114, RTR-REGGD-01.115, RTR-REGGD-01.117, RTR-REGGD-01.121, RTR-REGGD-01.124, RTR-REGGD-01.127, RTR-REGGD-01.130, RTR-REGGD-01.137, RTR-REGGD-01.141, RTR-REGGD-1.027, TASK-TF, TASK-TMR NUDOCS 8002110673 | |
| Download: ML19308C933 (6) | |
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UNITED STATES y
NUCLEAR REGULATORY COMMiss!ON
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j WASHINGTON, D. C. 20555 S.
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April 6, 1979 MEMORANDUM FOR: Systematic Evaluation Program Branch Members Dennis Ziemann, Chief, Operating Reactors Branch #2, D0R FROM:
Don K. Davis, Chief, Systematic Evaluation Program Branch, D0R
SUBJECT:
INCORPORATION OF REGULATORY REQUIREMENTS REVIEW COMMITTEE CATEGORY 2 AND 3 ITEMS INTO SYSTEMATIC EVALUATION PROGRAM REVIEW The Systematic Evaluation Program (SEP) has been directed to implement, on the eleven SEP facilities, those Regulatory Guides and other staff positions (such as branch technical position papers) designated as 3
Category 2 and 3 by the Regulatory Requirements Review Committee (R C).
3 These categories are defined in the September 24, 1975 minutes of R C Meeting 31 as follows:
Category 2 - 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.
Category 3 - Clearly backfit.
Existing plants should be evaluated to deteE5Tne whether identified items of the regulatory position are resolved in accordance with the guide or by some equivalent alternative.
Category 1 matters are clearly " forward fit" only and will not be considered in SEP.
Attached is a listing of Category 2 and 3 matters to be considered.
3 This list was complete as of February 23, 1979 (R C Meeting 82), which we shall use as our cutoff date, thereby delaying any future items characterized as backfit-eligible until such time that a decision is made on the extent and nature of SEP Phase III (extension of current SEP beyond the eleven plants).
Each SEPB member is to review the attached list for the topics over which he has cognizance. The following action should then be ta' Ken:
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8%s 11 o G73 to
i Multiple Addressee April 6, 1979 1.
Assure that review of each referenced SEP topic includes a 3
comparison specifically against the R C Category 2 and 3 items and that all deviations are specifically noted, with appropriate bases documented for their acceptability. As in other SEP reviews, decisions on specific backfit of these items will be made at the completion of the integrated assessment.
2.
Comparisons against the R3C requirements must be thoroughly documented for each applicable plant in order that a record of SEP action is maintained.
For consistency in evaluations, the following statement (or an equivalent) should be included in the applicable topic assessment or DBE evaluation:
"As part of this review, the guidance of Regulatory Guides /
Standard Review Plan / Branch Technical Position Paper was compared against the facility design. This RG/SRP F had been specifically identified by the NRC's Regulatory Requirements Review Committee as needing consideration for backfit on operating reactors. The review documents whether the facility design complies with the guidance of the RG/SRP/BTP or has some equivalent alternative accept-able to the staff. The acceptability or non-acceptability of the deviations listed below and the need for further action shall be judged during the integrated assessment for this facility."
Regulatory Guide 1.97 is the exception to the above review plan in that no implementation guidance has been developed. Although no action is necessary at this time, D. Mcdonald will be responsible for implementation should guidance be issued prior to January 1980.
The assistance of OIE will be requested to assess compliance with Regulatory Guide 1.114. A letter requesting such assistance, with reporting to ORB #2, is being written.
Each of you is responsible for documentation of the review on each of these matters. This procedure wi 1 assure management awareness andaccountabilityofthoseissuesR}Cdeterminedtobeofpotential safety significance for backfit.
3 Three R C Category 2 or 3 matters have been removed from SEP review 3
for the following reasons:
)
Multiple Addressee April 6, 1979 4
1.
Regulatory Guide 1.105 " Instrument Setpoints" - This matter was included in the SEP Topic VII-1 B and was resolved on the basis of the NUREG-0138 discussion of the topic. However, D0R generic action on specific instrumentation such as LPRM drift in BWRs is continuing (such action was noted in the NUREG) and these generic reviews. may be expanded if the need to do so is identified.
2.
Regulatory Guide 8.8 "Information Relevant to Ensuring That Occupational Radiation Exposure at Nuclear Power Stations Will Be As Low As is Reasonably Achievable (Nuclear Power Reactors)" -
This matter is presently being proposed for resolution by DOR /EEB on a generic basis. Since ALARA issues were not included in the initial SEP scope it would be inappropriate to include this one unique issue now.
3.
Regulatory Guide 1.68.2 " Initial Startup Test Program to Demonstrate Remote Shutdown Capability for. Water-Cooled Nuclear 3
Power Plants"-- This matter was determined, by R C, to be applicable to plants in the OL stage of licensing.
V Don K. Davis, Chie'f Systematic Evaluation Program Branch, D0R Attachments:
1.
List of Category 2 and 3 Items cc:
V. Stello E. Case W. Russell S. Varga R. Snaider
_C.Jofmayer D. Ziemann L. Barrett l
R. Vollmer D. Eisenhut D. Davis ORB #2 Members
CATEGORY 2 MATTERS Document Number Revision Date Title Toeic RG 1.27 2
1/76 Ultimate Heat Sink for Nuclear II-3.C Power Plants RG 1.52 1
7/76 Design, Testing, and Maintenance VI-8 Criteria for Engineered-Safety-
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Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Power Plants (Revision 2 has been published but the changes from Revision.1 to Revision 2 may, but need not, be considered.
RG 1.59 2
8/77 Design Basis Floods for Nuclear II-3.B Power Plants RG 1.63 2
7/78 Electric Penetration Assemblies in
!II-12 Containment Structures for Light Water Cooled Nuclear Power Plants RG 1.91 1
2/78 Evaluation of Explosions Postul'ated II-l.C to Occur on Transportation Routes Near Nuclear Power Plant Sites RG 1.102 1
9/76 Flood Protection foe Nuclear Power II-3.B Plants RG 1.108 1
8/77 Periodic Testing of Diesel VIII-2 Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants l
RG 1.115 1
7/77 Protection Against Low-Trajectory III-4.B Turbine Missiles RG 1.117 1
4/78 Ternado Design Classification III-4.A RG 1.124 1
1/78 Service Limits and Loading III-9 j
Combinations for Class 1 111-11 Linear Type Component Supports RG 1.130 0
7/77 Design Limits and Loading Combinations III-9 l
for Class 1 Plate-and Shell-Type III-ll Component Sapports (Continued)
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CATEGORY 2 MATTERS (CONT'D)
Continued Document Nunter Revision Date Title Topic RG 1.137 0
1/78 Fuel 011 Systems for Standby VIII-2 Diesel Generators (Paragraph C.2)
BTP ASB Guidelines for Fire Protection for IX-6 9.5-1 1
Nuclear Power Plants (5ee Implementation Section. Section D)
BTP MTEB 5-7 4/77 Material Selection and Processing V-4 Guidelines for BWR Coolant Pressure Boundary Piping RG 1.141 0
4/78 Containment Isolation Provisions VI-4 for Fluid Systems l
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e-CATlGORY 3 MATTERS Document Number Revision Date Title Topic RG 1.99 1
4/77 Effects of Residual Elements on V-6 Predicted Radiation Damage to Reactor Vessel Materials (Paragraphs C.1 and C.2.
RG 1.101 1
3/77 Emergency Planning for Nuclear XIII-l Power Plants RG 1.114 1
11/76 Guidance on Being Operator at the ORB #2 Controls of a Nuclear Power Plant RG 1.121 0
8/76 Bases for Plugging Degraded PWR V-8 Steam Generator Tubes RG 1.127 1
3/78 Inspection of Water-Control Structures III-3.C Associated with Nuclear Power Plants RSB'5-1 1
1/78 Branch Technical Position: Design Require VII-3 ments of the Residual Heat Remcyal System V-II.B RSB 5-2 0
3/78 Branch Technical Position: Reactor V-6 Coolant System Overpressurization Protection RG 1.97 1
8/77 Instrumentation for Light Water VII-5 Cooled Nuclear Power Plants to (No specific Assess Plant Conditions During guidance on and Following an Accident implementa-(Paragraph C.3 - with additional tion has been guidance on paragraph C.3.d to developed) be provided later)
RG 1.56 1
7/78 Maintenance of Water Purity in V-12. A Boiling Water Reactors i
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