ML20195G326
| ML20195G326 | |
| Person / Time | |
|---|---|
| Issue date: | 07/29/1987 |
| From: | Jordan E Committee To Review Generic Requirements |
| To: | Beckjord E, James Keppler, Mcdonald W, Murley T, Thompson H NRC |
| Shared Package | |
| ML20195G243 | List:
|
| References | |
| FOIA-87-714, TASK-029, TASK-099, TASK-101, TASK-103, TASK-29, TASK-99, TASK-A-40, TASK-A-45, TASK-C-08, TASK-C-8, TASK-OR NUDOCS 8708060428 | |
| Download: ML20195G326 (15) | |
Text
/.g July 29, 1987 MEMORANDUM FOR:
Those on Attached List FROM:
Edward L. Jordan Chairman Committee to Revlew Generic Requirements
SUBJECT:
LONG-RANGE CRGR AGENDA Based on input from your offices, enclosed is the current version of the Long-Range CRGR Agenda for the period through December 1988. The list includes no letSS itees since none were received.
R. Bernero plans to discuss potential
)#tSS itees for CRGR review at a CRGR meeting in the near future.
For those itees which are scheduled for CRGR consideration by the end of CY 1988, please review the agenda to ensure it is complete and accurate concerning the follow-ing infonnation:
1.
Official title and brief description of the ites.
l 2.
Date (calendar year and quarter) item is to be submitted for CRGR consideration.
3.
Cognizant office, office contact and telephone number.
Please provide your input to J. Conran by August 21, 1987.
An annotated copy of the agenda will suffice.
g Edward L. Jordan, Chairman Committee to Review Generic Requirements
Enclosure:
l Long-Range CRGR Agenda cc w/ enclosure:
Commission (5)
SECY V. Stello J. Taylor i
CRGR Members i
Regional Administrators J. Lieberman R. Fraley W. Parler Distribution:
Central File T. Speis l
CRGR CF R. Bernero E. Jordan F. Hebdon J. Zerbe R. Hernan T. Rehe CRGR Staff l
OFC : CRGR: AEOD :A/CR 00 :C/CRGR:AEOD :
NAME :
TCox:
- JZ E
DATE :
7/ /87 7/l)/87 7Si/87 0'FFICIAL RECORD COPY l.
Wressees for Menorandue Dated July 29, 1987 J. Keppler W. Mcdonald T. Murley H. Thoepson E. Backjord l
l 1
i
-.y
.y-
_-yy
.y 9m
-.. -m
[
CRGR LONG-RANGE AGENDA (ThroughDecember1988)
Date of Submittal to CRGR Cognizant 1
(Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
i 1
Generic Letter on IPEs - the Generic Letter (per 10 CFR 50.54f) with 87/2 RES, F. Coffman i
its attachments to initiate the Individual Plant Examinations (IPEs) 24609 as called for by the Severe Accident Policy.
2 BWR Rod Sequence Control System - allow BWRs to remove BWR rod sequence 87/2 NRR, H. Richings control.
27140 3
Nuclear Power Plant Staff Working Hours Policy Paper - consolidation 87/2 NRR, G. West of current Commission documents.
24887 4
Generic Letter on Changing Moderator Temperature Coefficients - change 87/2 NRR, D. Fieno l
in MTC to account for new fuel designs / extended core lifetimes.
27141 5
USI A-40:
Seismic Design Criteria - concerned with seismic input and 87/3 RES, K. Shaukat the response of structures, systems and components.
27821 6
Regulatory Guide 1.99, Revision 2:
Radiation Damage to Reactor Vessel 87/3 RES, P. Randall Materials - to update the embrittlement-fluence curves for the inf.luence 37711 of copper and nickel based on surveillance data alone.
7 Proposed Rulemakirg on Severe Accident Requirements - request 87/3 RES, Z. Rosztoczy Commission approval to begin steps toward implementation of the 37966 Severe Accident Policy for new applications and for certification of reference designs.
Contact:
Jim Conran (492-9855).
I l
CRGR LONG-RANGE AGENDA (ThroughDecember;,ves)
I l
Date of Submittal l
to CRGR Cognizant l
(Calendar Year /
Office, Contact i
Item Title or Description Quarter)
& Telephone Ext.
8 Regulatory Guide OP713-4:
Criteria for Establishing Bioassay Programs 87/3 RES, 8. Brooks for Tritium - regarding a bioassay program for any licensee handling or 37677 processing tritium either as pure gas or in various compounds.
j 9
USI A-45:
Shutdown Decay Heat Removal - complete resolution package on 87/3 RES, A. Marchese i
requirements to improve reliability of decay heat removal systems.
27477 10 Guidance on PRAs - the Severe Accident Policy required PRAs on all future 87/3 RES F. Coffman power plant designs and calls for staff guidance on the form, role, and 246d9 I
content of PRAs.
NUREG/CR-4812 has been prepared to define the minimum content of PRAs on future designs.
i 11 Maintenance Policy Statement - Commission policy paper on maintenance, 87/3 NRR, G. rwalina j
including acknowledgement of industry self-initiatives.
24045 i
i 12 Shr t.Tenn Technical Specification Improvement - TS line item 87/3 NRR, E.
1 modifications.
28393 13 New SRP Chapter 11.4, Appendix 8. Solid Waste Management Systems -
87/3 NRR, L. Cunningham i
provides NRC guidance for review of licensee's programs for disposal 24734 of very low level solid radioactive waste to verify compliance with i
1 i
14 Final Technical Specification Policy Statement - review of TS policy 87/3 NRR, E. Butcher statement following resolution of public comments.
28393 2
i l
I l
Contact:
Jim Conran (492-9855) 4 l
CRGR LONG-RANGE AGENDA (ThroughDecember1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact.
Item Title or Description Quarter)
& Telephone Ext.
15 Generic Issue 29:
Bolting Degradation or Failures in Nuclear Power 87/4 RES, R. Johnson Plants - concerning the risk associated with bolting failures.
This 28129 issue is constrained by the schedule of USI A-45, Shutdown Decay Heat I
Removal Requirements, which may result in requirements lessening the severity of small-to medium loss of-coolant accidents related to bolt j
failures in the reactor coolant pressure boundary.
16 Generic Issue 103:
Design for Probable Maximum Precipitation -
87/4 RES, L. Heller proposing the use of new National Weather Service procedures for 27646 determining the probable maximum precipitation to be used in evaluating the acceptability of reactor designs.
17 Regulatory Guide, Task Number EE404-4 (Final):
Environmental 87/4 RES, S. Aggarwal 4
Qualification of Connection Assemblies for Nuclear Power Plants -
37840 l
specifies acceptable methodology for environmentally qualifying quick-disconnect electric cor.-'. tors used in safety-related systems.
l l
18 Regulatory Guide 1.47, Revision 1 (For Public Comment): Bypassed and 87/4 RES, S. Aggarvel Inoperable Status Indicators for Nuclear Power Plant Safety Systems -
37840 provides acceptable design criteria for automatic and manual systems used for indicating the bypassed or inoperable status of safety-related components and systems.
d 19 Modular HTGR Concept review SER on DOEs modular HTGR concept.
87/4 RES, J. Wilsen 24727 4
Contact:
Jim Conran (492-9855).
CRGR LONG-RANGE AGENDA (Through December 1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
20 Revisions to Regulatory Guides 1.3 and 1.4 - implementation of source 87/4 RES, J. Hulman l
term and severe accident research through revisions related to the 28016 radiological consequences of limiting design basis accidents (
Reference:
Issue the revisions for public comment.
21 Standard Review Plan Section 6.5.5, BWR Suppression Pools, and 6.5.2 87/4 RES L. Soffer SprayAdditivesforPWRs-reviewpubliccommentsandproposedrevisions 279YS to SRPs 6.5.2 and 6.5.5 on implementing source term and severe accident research for estimating the radiological consequences of the limiting design basis accidents (
References:
SECY-86-76 and previous CRGR review of revisions issued for public comment.)
22 Final Emergency Planning Rule for Fuel Cycle Facilities - Commission 87/4 RES, S. McGuire Paper recommending an emergency planning rule for fuel cycle and 37735 material licensee facilities. The requirements for this rule result from Sequoyah fuel plant accident.
23 Rulemaking: Acceptance Criteria for Emergency Core Cooling Systems 87/4 RES, J. Reyes (ECCS) for Lighi. Water Nuclear Power Reactors - the NRC is proposing 37890 an amendment that would allow the use of alternative met"ods to demonstrate that the ECCS would protect the nuclear reactor core during a postulated design basis LOCA. The amendment is proposed because research, performed since the current rule was written, has shown that calculations performed using current methods and in accordance with the current requirements result in estimates of cooling system performance CRGR
Contact:
Jim Conran (492-9855) l
-m.
y
CRGR LONG-RANGE AGENDA (Through December 1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
that are significantly more conservative than estimates based on the improved knowledge gained from this research.
In addition, the operation of some nuclear reactors is being unnecessarily restricted by the rule, resulting in increased costs of electricity generation.
The proposed rule, while continuing to allow the use of current methods and require-ments, would also allow the use of more recent information and knowledge to demonstrate that the ECCS would protect the reactor during a LOCA. The proposed amendment, which would apply to all applicants for and holders of construction permits or operating licenses for light water reactors, would also relax requirements for certain reanalyses which do not contribute to safety.
24 Generic Issue 101: BWR Water Level Redundancy - BWR level 87/4 RES, C. Graves instrumentation requirements assuming leaks plus a single failure.
28357 25 Generic Issue 99:
RHR Suction Line Interlocks on PWRs - assess RHR 87/4 RES, A. Spano potential improvements during shutdown.
27476 26 Issue C-8: Main Steam Line Leakage Control (8WRs) need to maintain 87/4 RES C. Graves BWR MSIV Leakage Control System; increase MSIV allowable leakage.
283$7 27 Appendix J Revision - short-term rule change to allow use of mass 87/4 NRR, J. Kudrick point method for containment integrated leak rate testing.
28698 28 Operator License Fundamentals Examination Policy Paper - Commission 87/4 NRR, A. Mendiola policy paper on new approach to licensed operator examinations.
29695 CRGR
Contact:
Jim Conran (492-9855) _
CRGR LONG-RANGE AGENDA (Through December 1988)
Date of Submittal to CRGR Cognizt.nt (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
29 Standard Review Plan for Statistical Sampling provide guidance for 87/4 NRR, F. Rosa j
review of statistical sampling plans.
27225
)
30 Generic Letter Implementing ATWS Rule Technical Specifications 87/4 NRR, J. Mauck 24417 1
31 Short Ters Technical Specification Improvement - TS line item 87/4 NRR, E. Butcher modifications.
28393 i
32 Regulatory Guide, Task Number EE006-5 (Final):
Qualification of 88/1 RES, S. Aggarwel Safety-Related Lead Storage Batteries for Nuclear Power Plants -
37840 specifies acceptable methodology for qualifying station batteries.
l 33 Regulatory Guide 1.128, Revision 2 (For Public Comment):
Installation 88/1 RES, S. Aggamal of Large Lead Storage Batteries for Nuclear Power Plants - describes 37840 acceptable methodology for installing station batteries.
34 Regulatory Guide:
Neutron Dosimetry for Pressure Vessel Surveillance -
88/1 RES, A. Taboada to codify the presently used practices for calculating and measuring 37979 the neutron spectrum, flux and fluence in the pressure vessel wall of LWRs.
35 PRISM and SAFR LMR Concepts - review SERs on DOEs PRISM and SAFR LMR 88/1 RES J. Wilson i
concepts.
247}7 CRGR
Contact:
Jim Conran (492-9855) l l
CRGR LONG-RANGE AGENDA (Through December 1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact' Item Title or Description Quarter)
& Telephone Ext.
36 Proposed Revision of 10 CFR 20-- review proposal regarding the 88/1 RES, W. Lahs destination of low level radioactive waste streams below regulatory 37632 concern.
37 Revisions to Regulatory Guide 1.52 and Related Control Room 88/l RES, C. Ferrell Habitability Issues - issue for comment proposed changes to Regulatory 28349 Guide 1.52 regarding filtration systems and control room habitability
(
Reference:
SECY-86-76). This work implements source term research into the licensing process.
38 Changes to 10 CFR 50.47 and 10 CFR 50, Appendix E on Emergency 88/1 RES, M. Jangochian Planning proposed notice of rulemaking related to implementing 37657 source ters and severe accident research into the regulatory process by demonstrating the need for prompt evacuation only in close-in areas where risks require such action (
Reference:
39 Changes to 10 CFR 50.49 and Regulatory Guide 1.89 Reflecting the 88/l RES, J. Glynn Impacts of Source Ters and Severe Accident Research - a notice of 37630 rulemaking related to implementing the results of source term and severe accident research on equipment qualification requirements.
40 Commission Information Paper Describing Impacts of Source Tem and 88/l RES, J. Lane Severe Accident Research on Containment Leak Rates an assessment of 24446 the impacts of source ters and severe accident research on existing containment leak rate requirements, including potential needs for changes to 10 CFR 50, Appendix J, and related regulatory guidance
(
Reference:
________________=- = = =_________________________________ -___________________________________________---_________________
Contact:
Jim Conran (492-9855)
CRGR LONG-RANGE AGENDA (ThreughDecember1988) i Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
l 41 Backfit Requirements for Hydrogen Ignitors at Ice Condenser and SWR 88/1 RES C. Ferrell l
NK III Plants - assessment of any new requirements for AC independent 283d9 l
igniters at ice condenser and BWR MK III plants.
Backfit assessment I
is a post completion ites planned for resolution of Generic Safety Issue A-48.
42 Relief for Containment Isolation Valve Closure Times source term and 88/1 RES, J. Lane l
severe accident research has indicated the 5-second closure times 24446 required for many containment isolation valves is too stringent.
Bases i
for regulatory relief through a generic letter and SRP changes to be j
discussed.
l 43 Generic Issue 105:
Interfacing System LOCA - assess risk of PIV 88/1 RES, R. Woods i
failures causing breaks outside containment.
24712 1
l 44 Standard Review Plan for Station Blackout - SRP section to implement 88/l NRR, F. Rosa i
proposed Station Blackout Rule and regulatory guide already prepared 27255 by RES.
4 45 Short Term Technical Specification Improvements - TS line item 88/l NRR, E. Butcher modifications.
28393 46 B&W Plant Design Reassessment - staff requirements that may result from 88/l NRR, D. Crutchfieli the B&W reassessment.
27373 47 Generic Letter on Channel Functional Tests 88/l NRR, R. Stevens 28984 l
Contact:
Jim Conran (492-9855)
CRGR LONG-RANGE AGENDA (ThroughDecember1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
48 USI A-17:
System Interactions in Nuclear Power Plants - concerning 88/2 RES, D. Thatcher interactions between systems that can result in common mode failures 28358 of safety systems.
49 USI A-47:
Safety Implications of Control System - concerning the 88/2 RES, A. Szukiewicz risk to plant safety associated with the failure of control systems 28392 that are not classified as safety related.
50 Generic Issue 23:
Reactor Coolant Pump Seal Failures - concerning the 88/2 RES, J. Jackson risk to nuclear power plants resulting from reactor coolant pump seal 28544 failures.
51 Generic Issue II.E.6.1:
In-Situ Testing of Valves - concerning industry 88/2 RES, O. Rothberg practices, plant technical specifications, and current ASME Section XI 28204 inservice test methods that do not provide adequate assurance of valve operability during accidents.
52 10 CFR 100, Revised Reactor Siting Criteria - Commissic.' Paper 88/2 RES, M. Jangochian requesting approval to issue revisions to 10 CFR 100 fc future reactors 37657 that implements source term and severe accident research (
References:
SECY-86-76 and previous notices of rulemaking).
53 Revisions to Regulatory Guide 1.97, Instrumentation to Follow the 88/2 RES, J. Read Course of an Accident - issue for comment revisions to Regulatory 24958 Guide 1.97 that implement the results of source ters and severe accident research with respect to radiation environments.
_--===-
=
- =----.=- =-
======-------------------------------------------------------------------------------------.--
Contact:
Jim Conran (492-9855).
CRGR LONG-RANGE AGENDA (ThroughDecember1988)
Date of Submittal to CRGR Cognizant (Caler.dar Year /
Office, Contact Item Title or Description Quarter)
& telephone Ext.
54 Generic Issue 94:
LTOP - detemine the need for added low-temperature 88/2 RES, E. Throm overpressure protection requirements.
24712 55 Generic Issue 82: Beyond D8As in Spent Fuel Pools assess risk in 88/2 RES, E. Throm spent fuel pools and consider risk reduction alternatives.
24712 3
56 Generic Issue 130: Service Water Pumps at Two Plant Sites -
88/2 RES, V. Leung requirements at two plant sites.
24707 I
57 Decommissioning Standard Review Plan - SRP to support rule and reg.
88/2 NRR, F. Witt guide being issued by RES.
29539 58 Short Term Technical Specification Improvements - TS line item 88/2 NRR, E. Butcher modifications.
28393 50 MK I Containment Initiatives action to improve ability of MK I 88/2 NRR, J. Kudrick containments to respond to severe accidents.
28698 60 Generic Letter on Control Room Habitability - address system 88/2 NRR, J. Werniel t
inadequacies that could result in failure to meet GDC 19.
29412 61 Generic Issue B-5: Buckling Behavior of Steel Containments concerning 88/3 RES, L. Heller reinforcement needed to assure that steel containments will not buckle 27646 due to asymmetry resulting from large penetrations.
Contact:
Jim Conran (492-9855) f-i i
CRGR LONG-RANGE AGENDA (Through December 15es) 1 Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
I 62 Generic Issue 51:
Proposed Requirements for Improving Reliability of 88/3 RES, C. Hickey i
Open Cycle Service Water Systems concerned with the risk to nuclear 28395
)
plant safety resulting from biofouling or silting of service wai.er l
systems and the loss of the decay heat removal capability.
I 63 Generic Issue 70:
PORV and Block Valve Reliability - concerning the 88/3 RES, R. Kirkwood fundamental safety requirements of PORVs and block valves. Of particular 28058 concern are various accidents ased plant protection features including steam generator tube rupture events, loss of offsite power, and operability of RCS vents.
I 64 Regulatory Guide 1.32, Revision 1 (For Public Comment):
Criteria for.
88/3 RES, S. Aggarwal Safety-Related Power Systems provides acceptable design criteria for
-37840 preferred and standby power systems.
65 Regulatory Guide (For Public Comment): Qualification of Isolation 88/3 RES, S. Aggarwal Devices provides acceptable test methods for electrical devices'that 37840 isolate safety-related from nonsafety-related devices.
i 66 Generic Issue 87:
Failure of HPCI Steam-Line Without Isolation -
88/3 RES R. Woods i]
determine the capability and risk of isolation valves to close against 24712 full break flow.
l 1
67 Generic Issue 67.5.2:
Reevaluate SG Tube Design Basis - determine 88/3 RES, J. Hopenfeld if SRP for tube rupture accident should be revised.
37985 i
i l
i CRGR
Contact:
Jim Conran (492-9855)
- 11 _
1
i CRGR LONG-RANGE AGENDA (Through December 1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact q
Item Title or Description Quarter)
& Telephone Ext.
68 Short Tern Technical Specification Improvements - TS line item 88/3 NRR, E. Butcher 3
modifications.
28393 69 Regulatory Guide 1.100, Revision 2 (Final):
Seismic Qualification of 88/4 RES, S. Aggarwal Safety-Related Equipment for Nuclear Power Plants provides acceptable 37840 methodologies for the seismic qualification of safety-related electrical i
and mechanical equipment.
70 Regulatory Guide 1.129, Re' vision 2 (For Public Comment): Maintenance, 88/4 RES, S. Agganval Testing, and Replacement of Large Lead Storage Batteries for Nuclear 37840 Power Plants - describes acceptable methods.
l 71 Review of Final NUREG-1225:
"Implementation of NRC Policy on Nuclear 88/4 RES, T. King l
Power Plant Standardization 27014 I
[
72 Proposed Rulemaking on Standardization - review proposed rulemaking on 88/4 RES, T. King standardization (Appendices D, M, N, and 0 to 10 CFR 50) consistent 27014 i
with Commission guidance on standardization policy.
73 Proposed Rulemaking on "Important to Safety" - review, consistent with 88/4 RES, T. King Commission guidance from review of SECY-86-164.
27014 74 Generic Letter on External Hazards IPEs - the Generic Letter on IPEs is 88/4 RES, F. Coffman for internal hazards only. A separate generic letter is being prepared 24609 for external hazards which are part of the Severe Accident Policy.
Contact:
Jim Conran (492-9855) a CRGR LONG-RANGE AGENDA (Through December 1988)
Date of Submittal to CRGR Cognizant (Calendar Year /
Office, Contact Item Title or Description Quarter)
& Telephone Ext.
75 Short Ters Technical Specification Improvements - TS line item 88/4 NRR, E. Butcher i
i modifications.
28393 l
]
76 Proposed Revision to Regulatory Guide 1.28 - review proposal to endorse RES, T. King l
the 1986 edition of ANSI /ASME-NQA-1 standard regarding QA standards.
27014 77 Proposed New Regulatory Guide, ANSI /ASME-NQA review proposal to RES, T. King endorse ANSI /ASME-NQA-2 regarding QA standards.
27014 78 Proposed Appendix S to 10 CFR 50 - review proposal regarding "License RES, T. King by Test" option for certifying new reactor designs.
27014 70 Revision of Regulatory Guide 1.33 - regarding QA Program Requirements RES, T. King (Operations).
27014 CRGR
Contact:
Jim Conran (492-9855) w