ML20140D640
| ML20140D640 | |
| Person / Time | |
|---|---|
| Issue date: | 12/17/1984 |
| From: | Stello V Committee To Review Generic Requirements |
| To: | Jennifer Davis, Harold Denton, Minogue R NRC |
| References | |
| NUDOCS 8412180592 | |
| Download: ML20140D640 (15) | |
Text
_ - _ _ - _ _.
DEC 171984
- MEMOP!ANDUMFOR:
Those on Attached List FROM:
Victor Stello, Jr., Chairman Comittee to Review Generic Requirements SUBJECY:
LONG-RANGE CRGR AGENDA Based on input from your offices, enclosed is the Long-Range CRGR Agenda for the period from December 1984 through December 1985.
I plan to update and issue a new agenda every 6 months and will be soliciting your input about May 1985.
From a brief review of the agenda items, it appears that there is a similarity and close relationship between certain of the items.
For example, item No.15 (proposed revision of 10 CFR 50 concerning acceptance criteria for ECCS) appears very closely related to items 108, 109 and possibly 110 and 113.
Item No. 113 appears very closely related to matters that are to be covered by the severe accident policy and attendant rulemaking efforts for future plants.
Items 6, 107, Ill,113,114,11G and 124 all seem to hear a close relationship as do items 121, 125, 127 and 134.
Item 142 would seem to have been already covered by resolution of USI A-49 (PTS). These observations lead me to the conclusion that the sponsoring offices need to integrate efforts so that a cohesive agency position is taken on the issues. We intend to pay particular attention to this during the CRGR review process.
Coments concerning the agenda should be referred to Walt Schwink (x28639).
Original Signed r V. Stello Victor Stello, Jr., Chairman Comittee to Review Generic Requirements -
Enclosure:
Long-Range CRGR Distribution:
Agenda VStello JRoe PDR JSniezek TRhem SStern cc: Comission (5)
P.Erickson EFox JHenry SECY WLittle JZwetzig JPhillips i
W. J. Dircks FHebdon ETriner Central File CRGR Members DEDR0GR cf R0GR Staff Regional Administrators l
Y
?m &
CORRESPONDENCE PDR-j
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i0FC. :ROGR
- ROGRfD
- DEDROGR l_____:_.
,.____:.9 y.._____:____________: ________...:____________:____________:___________
' NAME :W k
- JSu'ezek
- VStello l
l DATE :12/13/84..___:____________:__r_O/84
- 12/ /84
- 12/
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s
~ ADDRESSEE FOR MEMORANDUM DATED DEC 1.7 1984
~
' H.' Denton-
- J. Davis
- R. Minogue R. DeYoung.
G. W. Kerr G. Cunningham' P. Norry
- J. Shea '
. L. Barry.
C. Heltemes ini m i
.s
r December 1984 CRGR LONG. RANGE AGENDA (Deceseer 1984 through December 1985)
DATE OF SUBMITTAL TO CRGR COGNIZANT (CALENDARYEAR/
OFFICE, CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 1
Proposed revision of 10 CFR dart 73.71, Reporting Requirements CY84/4 NMSS, P. Dwyer W. Schwink for Safeguards Events x74773 x28639 2
Proposed revision of 10 CFR Parts 21 and 50, Reporting of Defects CY84/4 IE, J. Zudans E. Blackwood and Noncompliance x27205 x24359 3
Proposed revision of 10 CFR 20 concerning Residual Levels of CY84/4 RES, D. Harmon W. Schwink Radiation in Nonrestrictive Areas x74566 x28639 4
Advanced Notice of Proposed Revision of 10 CFR Part 50, CY84/4 RES, J. Jenkins T. Cox General Design Criteria for Nuclear Power Plants to Incorporate x37657 x24357 General Human Factors Criteria for New Construction 5
New Reg. Guide concerning Application of Progransnable Digital CY84/4 RES, A. Hintze J. Conran Computers in Safet; Systems of Nuclear Power Plants x37690 x24354 6
New Reg. Guide concerning Criteria for El&CS Portions of Protection CY84/4 RES, A. Hintze M. Taylor Systems, Protective Active Systems and Auxiliary Support Features x37690 x24356 7
Proposed revision to Reg. Guide 1.99, Radiation Damage to Reactor CY84/4 RES, P. Randall M. Taylor Vessel Materials x37603 x24356 8
Revision of Reg. Guide 1.35 Determining Prestressing Forces for CY84/4 RES H. Ashar J. Conran Inspection of Prestressed Concrete Containment Structures x37892 x24354 9
Proposed IE Bulletin concerning Testing of Licensee's Emergency CY84/4 IE, M. Hawkins E. Blackwood Notification System and Health Physics Network Telephones x24145 x24359 10 Proposed IE Bulletin concerning Steam Bin <1ing of Auxiliary Feedwater CY84/4 IE, M. Wegner
- T. Cox Pumps x24511 x24357 11 Proposed Resolution of USI A-46, Seismic Qualification of Equipment in CY84/4 NRR, T. Speis J. Conran Operating Plants and GI 21 Vibration Qualification of Equipment x27517 x24354
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Contact:
Walt Schwink (492-8639).
December 1984 CRGR LONG-RANGE AGENDA (December 1984 through DecesEer 1985)
DATE OF SUBMITTAL TO CRGR COGNIZANT (CALENDAR YEAR /
0FFICE, CONTACT ROGR -CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 12 Proposed revision of 10 CFR Part 50, Appendix J, Primary CY85/1 RES, G. Arndt M. Taylor Reactor Containment Leakage Testing for Water-Cooled Power x37860 x24356 Reactors 13 Proposed revision of 10 CFR 50 concerning Emergency Preparedness CY85/1 IE, E. Jordan E. Blackwood Reporting Requirements (Deletion of Unusual Event as Emergency Class) x24848 x24359 14 Final revision of 10 CFR Part 73 concerning Protection Requirements CY85/1 C. Sawyer W. Schwink for Spent Fuel Shipments x74186 x28639 15 Proposed revision of 10 CFR 50 concerning Acceptance Criteria for CY85/1 RES, M. Fleishman M. Taylor Emergency Core Cooling Systems for Light-Water-Cooled Nuclear Power x37616 x24356 Plants 16 Reg. Policy and Practice Implications of Revised Source CY85/1 NRR, R. Bernero M. Taylor Term x27373 x24356 17 Proposed Criteria for Qualification of NDE Inspectors and Equipment CY85/1 RES, C. Serpan T. Cox x37907 x24357 18 Proposed Reg. Guide on Qualification Connectors CY85/1 RES. N. Kondic M. Taylor x37970 x24356 19 Proposed Reg. Guide on Fire Protection in LWR Fuel Fabrication CY85/1 RES, D. Notley J. Conran Plants x37546 x24354 20 Revision of Reg. Guide 1.82, Sump for an Emergency Core CY85/1 RES, L. Prose T. Cox Cooling and Containment Spray System (Part of USI A-43) x37850 x24357 21 Proposed Resolution of GI B-19 Thermal-Hydraulic Stability CY85/1 NRR, R. Bernero M. Taylor x27373 x24356 22 Proposed Resolution of GI 29, Bolting Degradation or Failure in CY 85/1 NRR, R. Vollmer M. Taylor Nuclear Power Plants x27207 x24356 CRGR
Contact:
Walt Schwink (492-8639).
4 December 1984 CRGR LONG-RANGE AGENDA (December 1984 through December 1985)
DATE OF SU8MITTAL TO CRGR COGNIZANT (C.MINDAR YEAR /
OFFICE, CONTACT ROGR CONTACT'
. ITEM-TITLE OR DESCRIPTION QUARTER)
.AND TELEPHONE AND TELEPHONE 23 Revision of Standard Review Plan Chapter 13.52 CY85/1 NRR, H. Thompson T..Cox
..._________............__..-__...._____....___x29595 x24357 24 Final revision of 10 CFR 73, Miscellaneous Amendments CY85/2 MMSS T. Allen W. Schwink-concerning Physical Protection of Nuclear Power Plants (Part of Insider Rule Package) x74753 x28639' 25 Final revision of 10 CFR 73, concerning Search of Individuals CY85/2 NMSS, T. Allen W. Schwink at Power Reactor Facilities (Part of Insider Rule Package) x74753 x28639 26 Final revision of 10 CFR 50 & 73, concerning Personnel Access CY85/2 MMSS, T. Allen W. Schwink Authorization Requirements for Nuclear Power Plants (Part of Insider j
Package) x74753 x28639 27 Proposed revision of 10 CFR 71 concerning Transportation Provisions CY85/2 RES, D. Hopkins W. Schwink Pertaining to the Shipment of Low Specific Activity Material x37878 x28639 28 Draft Reg. Guide concerning Models and Parameters for Translating CY85/2 RES, D. Harmon W. Schwink Residual Radioactvity to Doses x74566 x28639 29 Draft Reg. Guide concerning Techniques and Instrumentation to CY85/2 RES, D. Harmon W. Schwink Measure Residual Radioactviity for License Termination x74566 x28639 30 Proposed Revision to Reg. Guide 1.73, Qualification of Valve CY85/2 RES,'A. Hintze M. Taylor i
Operators x37690 x24356 31 New Reg. Guide concerning Radiation Protection Instrument Test and Calibration CY85/2 RES, R. Nee)
W. Schwink x74559 x28639 32 Revision of Reg. Guide 1.33, QA Program Requirements (Operations)
CY85/2 IE, W. Scott.
E. Blackwood x24220 x24359 33 Revision of Reg. Guide 8.13 Instruction Concerning Prenatal CY85/2 RES, D. Nellis W. Schwink-Radiation Exposure x74588 x28639 CRGR
Contact:
Walt Schwink (492-8639)
_3-s 4
0 3
i.
December 1984 CRGR LONG-RANGE AGENDA (December 1984 through December 1985)
DATE OF SUBNITTAL TO CRGR COGNIZANT (CALENDARYEAR/
OFFICE, CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 34 Proposed Ro tolution of GI A-30, Adequacy of Safety Related DC CY85/2 NRR, R. Bernero M. Taylor Power Suppl) x27373 x24356 35 Proposed Resolution of USI A-49. Pressurized Therwel Shock CY85/2 NRR, T. Speis M. Taylor (Reg. Guide) x27517 x24356 36 Proposed Resolution of USI A-45, Shutdown Decay Heat Removal Requirements CY85/2 NRR, T. Spels M. Taylor x27517 x24356 37 Proposed *evision of GE Standard Technical Specifications CY85/2 NRR, D. Eisenhut T. Cox x27672 x24357
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38 Final Rule concerning Operator Licenses. Plant Specific CY85/3 NRR, H. Thompson T. Cox Simulators and Examination and Testing Requirements, including x29595 x24357 Operating Tests. Includes RGs 1.8. 1.34, 1.49 and NUREG on Training, and RG 1.114 39 Proposed revision of 10 CFR 50 concerning Westinghouse Standard CY85/3 RES, D. Pyatt M. Taylor Technical Specifications (Addition of Scram System Requirement) x37631 x24356 40 Final revision of 10 CFR 50 concerning Station Blackout Requirements CY85/3 NRR, T. Speis M. Taylor (USI A-44) x27517 x24357 41 Proposed Revision to Reg. Guide 1.63, Electric Penetration Assemblies CY85/3 RES, S. Aggarwal T. Cox x37946 x24357 42 Revision of Reg. Guide concerning Requirements for Qua?'fication CY85/3 RES, D. Guzy T. Cox Tests and Products Tests for Piping and Equipment Snubbers x37860 x24357 43 Revision of Reg. Guide 1.12. Seismic Instrumentation for Nuclear CY85/3 RES, R. Kenneally J. Conran Power Plants x37892 x24354 44 Final Resolution of USI A-46, Seismic Qualification of CY85/3 NRR, T. Speis J. Conran Equipment in Operating Plants x27517 x24354 CRGR
Contact:
Walt Schwink (492-8639)
-4
Dec W r 1984 CRGR LONG-RANGE AGENDA (December 1984 through December 19RS)
DATE OF SU8MITTAL TO CRGR COGNIZANT
-(CALENDARYEAR/-
0FFICE, CONTACT.
.ROGR CONTACT-ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 45 Proposed Resolution of USI A-17, Systems Interaction CY85/3 NRR, T. Spels.
M. Taylor-x27517' x24356-46 Proposed Resolution of USI A-47, Safety Implications of Control Systems CY85/3 NRR, T. Spets M. Taylor x27517 x24356 5
47 Proposed Resolution of GI 48 LCO for Class IE Vital Instrument Buses CY 85/3 NRR, R. Be nero T. Cox in Operating Reactors x27373 x24357
==.........--.............--..........--...........________===.....--................. --........--......................--......
48 Proposed revision of 10 CFR 20 concerning Maintenance of CY85/4 RES, K. Bissell' W. Schwink Radioactive Material Packages on Receipt x37920 x28639 49 Final revision of 10 CFR 30, 40, 50, 51, 70 and 72 concerning CY85/4 RES, K. Steyer W. Schwink Decommissioning Criteria for Nuclear Facilities x37918 x28639 50 Proposed revision of 10 CFR Part 71.97, Advance Notification CY85/4 K.-Bissell W. Schwink of Shirment of Nuclear Waste x37920 x20639 51 Final revision of 10 CFR 73 concerning Medical Standards for CY85/4.
RES B. Taylor T. Cox Employment of Security Personnel x37634 x24357 52 Draft Rule on Operating Experience on Shift CY85/4-NRR, H. Thompson T. Cox x29595 x24357 I
53 Proposed revision to Reg. Guide 1.100 Seismic Qualification of CY85/4 RES, S. Aggartel J. Conran Safety Related Equipment x37946 x24354 54 Revision of Reg. Guide 1.89, Qualification of Class IE Equipment CY85/4 RES S. Aggarwal M. Taylor for Nuclear Power Plants x37946 x24356 55 Final Resolution of USI 49, Pressurized Thermal Shock CY85/4 NRR, T. Speis M. Taylor 4
(Reg. Guide) x27517 x24356 56 Final Resolution of USI A-45, Shutdown Decay Heat Removal CY85/4 HRR, T. Speis M. Taylor j
Requirements x27517 x24356
?
Contact:
Walt Schwink (492 8639),
i i
1
December 1984 CRGR LONG-RANCE AGENDA (December 1984 through December 1985)
DATE OF SUBMITTAL TO CEGR COGNIZANT (CALENDAR YEAR /
OFFICE, CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 57 Proposed Resolution of USI A-40 Seismic Design Criteria - Short-Term CY85/4 NRR, R. Vollmer J. Conran Program x27207 x24354 58 Proposed Resolution of GI 23, Reactor Coolant Pump Seal Failures CY 85/4 NRR, R. Vollmer M. Taylor (Candidate for USI) and Proposed Resolution of GI 65, Probability of x27207 x24356 Core-Melt Due to Component Cooling Water Water System Failures 59 GI B-5, Buckling Behavior of Steel Containments CY85/4 NRR, R. Vollmer T. Cox x27207 x24357 60 Revision of Standard Review Plan Chapter 18 CY85/4 NRR, H. Thompson T. Cox x29595 x24357
_ _ _ _ _.. _ _ _ _................ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. = = = _ _ _ _ = = =. _ _ _ _ _ _ _ _. _ _ _ _ _ _..... _ _ _ _ _ _ _ _... _ _ _ _ _.............. _ _........ _ _ _ _................. _ _ _ _ _.......... -
Future Items - To Be Scheduled After CY85 61 Final revision of 10 CFR 50 concerning a Degree Requirement for NRR, H. Thompson Senior Manager on Shift x29595 62 Final revision of 10 CFR Part 50 to add section requiring licensees to follow technical specifications 63 Final major revision of 10 CFR Part 20, Standards for Protection RES, R. Baker Against Radiation x74570 64 Final revision of 10 CFR Part 50 concerning Technical Specifications NRR, D. Eisenhut for Nuclear Power Reactors x27672 65 Preposed Revision of 10 CFR 73.67 concerning Security Improvecents NMSS, C. Withee for Nonpower Reactors x74768 66 Proposed revision of 10 CFR 50 concerning Requirements for Extension of Construction Completion Date CRGR
Contact:
Walt Schwink (492 8639) 6-e
December 1984 CRGR LONG-RANGE AGENDA (Deceder 1984 thrcugh Deceder 1985)
DATE OF SUBMITTAL TO CRGR COGNIZANT (CALENDARYEAR/
OFFICE CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 67 Final revision of 10 CFR 50 concerning Extension of Criminal RES, D. Hopkins Penalties 68 Final revision of 10 CFR 2 & 50 concerning Temporary Operating Licenses 69 Proposed revision of 10 CFR 19 & 20 concerning Lower Radiation RES. W. Cool Exposure Levels for Fertile Women x74579 70 Proposed revision of 10 CFR 19 & 20 concerning Changes in RES, W. Cool Radiation Dose-Limiting Standards x74579 71 Final revision of 10 CFR 2, 50 & 51 concerning Licensing and RES, P. Hayes Regulatory Policy and Procedures for Environmental Protection x74628 Alternative Site Reviews 72 Proposed Rule concerning Closure of Open Ended Record Retention 73 Proposed revision of 10 CFR 61 concerning Technical Aspects of of the Program 74 Proposed revision of 10 CFR 50, 51 and 100 concerning the Policy and RES, W. Ott Regulatory Practice Governing the Siting of Nuclear Power Reactors x74615 75 Final revision of 10 CFR 50 concerning Protection of Contractor RES, A. DiPalo Employees x37613 76 Final revision of 10 CFR SC concerning Design and Other Changes in Nuclear Power Plant Facilities After Issuance of Construction Pemit 77 Final revision of 10 CFR 2, 30, 40,i50, 51, 61, 70, 72 & 110 concerning Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions l
Contact:
Walt Schwink (492-8639) f
-1 December 1984 CRGR LONG-RANGE AGENDA
~*
(December 1984 through December 1985)
I DATE OF SUBMITTAL l
TO CRGR COGNIZANT l
(CALENDARYEAR/
OFFICE, CONTACT.
ROGR CONTACT l
ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 78 Proposed revision of 10 CFR 50 concerning Severe Accident Design RES, M. Fleishman Criteria x37616 l
1 79 Proposed revision of 10 CFR 100, concerning Seimsic and Geological RES, L. Bera an I
Siting Criteria for Nuclear Power Plants x74370 1
80 Revision of Reg. Guide 8.8, Occupational Radiation Exposure at Nuclear Power Plants l
l 81 New Reg. Guide, Anchoring Supports to Concrete RES. H. Graves x37892 82 Modifications of Regs, Reg Guides, SRP to Accomplish Revised Source Term 83 Revision of CE Standard Technical Specification concerning ESFAS Subgroup Relay Testing 84 Resolution of PORY issues for Westinghouse, B&W and CE Plants 85 Revision of NUREG 0041, Manual for Respiratory Protection Against RES, R. Neel Airborne Radiation Material x74559 L
86 Proposed Resolution of USI A-48. Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment 87 Proposed Resolution of GI A-38, Tornado Missiles NRR, R. Bernero x27373 l
l 88 Proposed Resolution of GI A-19, Digital Computer Protection System 89 Proposed Resolution of GI A-21, Main Steam Line Break Inside Contain-ment - Evaluation of Conditions for Equipment Qualification CRGR
Contact:
Wait Schwink (492-8639) l
December 1984 CRGR LONG-RANGE AriNDA (December 1984 through Dec M r 1985)
DATE OF SUBMITTAL TO CRGR COGNIZANT (CALENDARYEAR/
OFFICE, CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 90 Proposed Resolution of GI A-23 Containment Leak Testing 91 Proposed Resolution of GI A-25, Monsafety Loads on Class IE Power Sources 92 Proposed Resolution of GI A-27, Reload Applications 93 Proposed Resolution of GI A-29 Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage 94 Proposed Resolution of GI A-41, Long-Tem Seismic Program 95 Proposed Resolution of GI B-6, Loads, Load Cosbinations and Stress Limits 96 Proposed Resolution of GI B-17, Criteria for Safety-Related Operator Actions 97 Proposed Resolution of GI B-22, LWR Fuel 98 Proposed Resolution of GI B-26, Structural Integrity of Containment Penetrations 99 Proposed Resolution of GI B-29. Effectiveness of Ultimate Heat Sinks 100 Proposed Resolution of GI B-31 Das Failure Model I
101 Proposed Resolution of GI B-32. Ice Effects on Safety-Related Water Supplies 102 Proposed Resolution of GI B-50, Post-Operating Basis Earthquake Inspectioh 103 Proposed Resolution of GI B-54, Ice Condenser Containments CRGR
Contact:
WaltSchwink'(492-8639) !
Decester 1984.
CRGR LONG-RANGE AGENDA (Decerber 1984 through December 1985) 1 DATE OF SUBMITTAL TO CRGR COGNIZANT-(CALENDARYEAR/
OFFICE, CONTACT R0GR CONTACT ITEM TITLE OR DE*,CRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 104 Proposed Resolution of GI B-55. Improved Reliability of Target Rock Safety-Relief Valves 105 Proposed Resolution of GI B-58, Passive Mechanical Failures 106 Proposed Resolution of GI B-59, N-1 Loop Operation in BWRs and PWRs 107 Proposed Resolution of GI B-61, Allowable ECCS Equipment Outage Periods
~
108 Proposed Resolution of GI C-4 Statistical Methods for ECCS Analysis 109 Proposed Resolution of GI C-5, Decay Heat Updates 110 Proposed Resolution of GI C-6, LOCA Heat Sources 111 Proposed Resolution of GI C-11, Assessment of Failure and Reliability of Pumps and Valves 112 Proposed Resolution cf GI C-14 Stom Surge Modes for Coastal Sinks 113 Proposed Resolution of GI D-2, Emergency Core Cooling System Capability for Future Plants 114 Proposed Resolution of GI 2. Failure of Protective Devices on Essential Equipment 115 Proposed Resolution of GI 12 BWR Jet Pump Integrity 116 Proposed Resolution of GI 24, Automatic Emergency Core Cooling System Switch to Recirculation 117 Proposed Resolution of GI 30, Potential Generator Missiles - Generator Rotor Retaining Rings 118 Preposed Resolution of GI 35, Degradation of Internal Appurtenances CRGR
Contact:
Walt Schwink (492-8639),
[
l
' December 1984 CRGR LONG-RANGE AGENDA.
(December 1984 through December 1985).
~
DATE OF SUBMITTAL TO CRGR COGNIZANT (CALENDARYEAR/
OFFICE, CONTACT R0GR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE i
j 119 Proposed Resolution of GI 37, Steam Generator Overfill and Combined Primary and Secondary Blowdown 120 Proposed Resolution of GI 38, Potential Recirculation System Failure as a Consequence of Injection of Containment Paint Flakes or Other j
Fine Debris l
121 Proposed Resolution of GI 49 Interlocks and LCOs for Redundant I
Class IE Tie Breakers 122 Proposed Resolution of GI 51, Proposed Requirements for Iuproving NRR. R. Bernero the Reliability of Open Cycle Service Water Systems x27373 123 Proposed Resolution of GI 53, Consequences of a Postulated Flow Blockage Incident in a BWR 124 Proposed Resolution of GI 54, Valve Operator-Related Events Occurring During 1978, 1979, and 1980 i
125 Proposed Resolution of GI 55, Failure of Class IE Safety-Related l
Switchgear Circuit Breakers to Close on Demand l
i 126 Proposed Resolution of GI 57, Effects of Fire Protection System j
Actuation on Safety-Related Equipment 127 Proposed Resolution of GI 59. Technical Specification Requirements for Plant Shutdown when Equipment for Safe Shutdown Is Degraded or-Inoperable j
128 Proposed Resolution of GI 61, SRV Line Break Inside the BWR Wetwell Airspace of Mark I and II Containments 129-Proposed Resolution of GI 62, Reactor Systems Bolting Applications i
i CRGR
Contact:
WaltSchwink(492-8639) '
s s
9
December 1984 CRGR LONG-RANGE AGENDA (December 1984 through DecEr 1985)
DATE OF SUBMITTAL TO CRGR CDGNIZANT (CALENDAR YEAR /
OFFICE, CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 130 Proposed Resolution of GI 63, Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis 131-Proposed Resolution of GI 67, Steam Generator Staff Actions 132 Proposed Resolution of GI 68, Postulated Loss of Auxiliary Feedwater NRR, R. Bernero System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam x27373 Supply Line Rupture 133 Proposed Resolution of GI 69, Make-up Nozzle Cracking in B&W Plants 134 Proposed Resolution of GI 70, PORV and Block Valve Reliability NRR, R. Bernero x27373 135 Proposed Resolution of GI 71 Failure of Resin Demineralizer Systems and their Effects on Nuclear Power Plant Safety 136 Proposed Resolution of GI 72, Control Rod Driva Guide Tube Support Pin Failures 137 Proposed Resolution of GI 73 Detached Therral Sleeves 138 Proposed Resolution of GI 74, Reactor Coolant Activity Limits for Operating Reactors b
139 Proposed Resolution of GI 76, Instrumentation and Control Power Interactions 140 Proposed Resolution of GI 77. Flooding of Safety Equipment NRR, R. Bernero Compartments by Backflow through Floor Drains x27373 141 Proposed Resolution of GI 78, Monitoring of Fatigue Transient Limits for Reactor Coolant System CRGR CIntact: Walt Schwink (492-8639).
4
December 1984 CRGR LONG-RANGE AGENDA (December 1984 through December 1985)
DATE OF SUBMITTAL I
TO CRGR COGNIZANT (CALENDARYEAR/
OFFICE, CONTACT ROGR CONTACT ITEM TITLE OR DESCRIPTION QUARTER)
AND TELEPHONE AND TELEPHONE 142 Proposed Resolution of GI 79, Unanalyzed Reactor Vessel Therinal i
Stress during Natural Convection Cooldown l
143 Proposed Resolution of GI 80, Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywell of BWR Mark I and II
)
Containments 144 Proposed Resolution of GI 81, Potential Safety Problems Associated with Locked Doors and Barriers in Nuclear Power Plants 145 Proposed Resolution of GI 82, Beyond Design Basis Accidents in Spent NRR, R. Bernero Fuel Pools x27373 146 Proposed Resolution of GI 83, Control Room Habitability dRR, R. Bernero x27373 147 Proposed Resolution of GI 85, Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments l
l CRGR
Contact:
Walt Schwink (492-8639).
.. _ _ _ _......,...........,...