ML17254A147
| ML17254A147 | |
| Person / Time | |
|---|---|
| Site: | Brunswick, North Anna, Ginna, Farley, Cook, 05000000, Crane |
| Issue date: | 12/18/1984 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Bernero R, Speis T, Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8412310415 | |
| Download: ML17254A147 (54) | |
Text
MEMORANDUM FOR:
FROM:
SUBJECT:
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.'-NRC-P.DR
. 'LP,DR ORBIIIl RDG Gray file Memo file Themis P. Speis, Director CParrish Division of Safety Technology KJohnston SVarga Richard H. Vollmer, Director DVassallo Division of Engineering JMiller JStolz Robert Bernero, Director JZwolinski Division of Systems Integration DCrutchf s el d LEng1 e GLainas JThoma Hugh L. Thompson, Director Division of Human Factor Safety EReeves Darrell G. Eisenhut, Director Division of Licensing PRIORITY OF SAFETY EVALUATIONS FOR BRUNN(888 8.
C.
- COOK, FARLEY, GINNA, NORTH ANNA AND TMI 1
As an NRR demonstration to show that the backlog of multi plant, TMI, and plant specific actions can be completed in a timely manner, the subject
- plants, Brunswick, D.
C. Cook, Farley, Ginna, North Anna, and TMI 1, have been chosen to complete 75% of their actions, open prior to July 1,
- 1984, by July 1, 1985.
In general, these plants were chosen because of licensee interest in cooperyting in this effort and because the status of the open items was such that, with proper priority and management attention given to them, there appeared to be a reasonable chance to achieve the goal.
Enclosed are the lists of open items for each plant.
Included on each list is the "SE Input Date" which is the date DL requires your staff's input in order to meet the goal of completing 75% of the open items.
In addition, where requests for additional information (RAI's) have been received or are forthcoming from the review branch, a date is listed in the "RAI Date" column.
If there is a targeted licensee response date it is listed in the "RAI Response Date" column.
Where no dates are shown in these
- columns, we are not aware of any forthcoming RAI's or response targets.,
Please include in your review, where appropriate, projected dates for RAI's and needed licensee response date to meet the projected "SER Input Date."
Some of these dates have been negotiated by the PM's, others have not.
The safety evaluations for the subject plants are to be considered priority actions.
'The reviews for these plants should be given priority over similar reviews for other'perating reactors unless there are overriding safety issues.
You are requested to provide appropriate priorities for reviews under your authority.
I request that you and your staff evaluate these dates for those branches under your cognizance and indicate therein for each item your concurrence 84123i04i5 84i2iB PDR *DOCK 05000244 p
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December 18, 1984 or what other actions will be deferred in order to meet these dates.
Please advise us as soon as possible of any schedular impacts or other problems that you may have.
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Darrell G. Eisenhut, Director Division of Licensing 1'
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- See previous white for concurrences ORB¹l: DL*
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JZwolinski 12/11/84 C-ORB¹1: DL SVarga 12/11/84 AD:SA:DL*
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or what other actions will be deferred in order o meet these dates.
Please advise us as soon as possible of any s hedular impacts. or other problems that you may have.
The contact for this matter is G. Lainas (27817).
Darrell G. Eisenhut, Director Division of Licensing
- See previo s white for concurrences ORB¹1:
KJohns on/ts 12/10 84 C-ORB¹5:DL*
JZwolinski 12/11/84 C-ORB¹1: DL*
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II If concurrence or what other actions will be deferred in rder to meet these dates.
please advise us as soon as possible of any sched ar impacts on other problems that you may have.
The contact for thi matter in G. Lainas (27817).
D rell G. Eisenhut, Director ivision of Licensing
- See previou white for concurrences ORB¹1'*
KJoh ston/ts 12/10/84 C-ORB¹
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Jl1iller JStolz 12/11/84 12/11/84 D;DL DEisenhut 12/
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MEMORANDUM FOR:
See Distribution List FROM:
SUBJECT:
Darrell G. Eisenhut, Director Division of Licensing PRIORITY OF SAFETY EVALUATIONS FOR BRU CK, D.
C.
- COOK, FARLEY, GINNA, NORTH ANNA AND T As an NRR demonstration to show that backlog of multi t, TMI, and plant specific actions can be completed in a timely manner, e subject plants, Brunswick, D.
C. Cook, Farley, Ginna, North Anna, an MI 1, have been chosen to complete 755 of their actions, open prior to July
, 1984, by July 1, 1985.
In general, these plants were chosen because of 1'see interest in cooperating in this effort and because the statu of the open items was such that, with proper priority and management tention given to them, there appeared to be a reasonable change to a eve the goal.
Enclosed are the lists of open items for ea plant.
Included on each list is the "SE Input Date" which is the need d
e in order to meet the goal of completing 75K of the open items.
In ad tion, where requests for additional information (RAI's) have been received are forthcoming from the review
- branch, a date is listed in the "RAI D e" column.
If there is a targeted licensee response date it is listed i the "RAI Response Date" column.
Where no dates are shown in these co umns, we are not aware of any forthcoming RAI's or response targets.
Please nclude in your review, where appropriate, projected dates for RAI's and nee d licensee response date to meet the projected "SER Input Date."
Som of these dates have been negotiated by the PM's, others have not.
The safety evaluations for th subject plants are to be considered priority actions.
The reviews for th se plants should be given priority over similar reviews for other operatin reactors unless there are overriding safety issues.
You are requeste to provide appropriate priorities for reviews under your authority.
I request that you and our staff evaluate these "need" dates for those branches under your c nizance and indicate therein for each item your concurrence or what her actions will be deferred in order to meet these dates.
Please contact me if you h'ave any questions regarding this request.
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MEMORANDUM FOR:
FROM:
SUBJECT:
See Distribution List Darrell G. Eisenhut, Director Division of Licensing PRIORITY OF SAFETY EVALUATIONS FOR BRUNSWICK, D.
C.
- COOK, FARLEY, GINNA, NORTH ANNA AND TMI 1 As an NRR demonstration to show that backlog of multi plant, TMI, and plant specific actions can be completed in a timely manner, the subject plants, Brunswick, D.
C.
Cook, Farley, Ginna, North Anna, and TMI 1, have been chosen to complete 75% of their actions, open prior to July 1, 1984, by July 1, 1985.
These plants were chosen
- because, from the appearance of the present status of open items and from licensee interest in cooperation on this effort.
There is a reasonable chance of meeting this goal.
Enclosed. are the lists of open items for each plant.
Included on each list is the "SE Input Date" which is the need date in order to meet the goal of completing 75% of the open. items.
In addition, where requests for additional informatioh- (RAI's) have been 'received or are forthcoming from the review
- branch, a date is listed in the "RAI Date" column.
If there is a targeted licensee response date it is listed in the "RAI Response Date" column.
Where no dates are shown, in these
- columns, we are not aware of any forthcoming RAI's or response targets.'lease include in your review, where appropriate, projected, dates for RAI's and needed, licensee response date to meet the projected l'SER ',Input Date."
Some of these dates have been negotiated by the PM's, others have not.'he safety evaluations for'he subject plants are now to be considered priority actions.
The reviews for these plants should be given priority over similar reviews fqr other operating reactors unless there are overriding safety issues.
You are requested to provide appropriate priorities for reviews under your authority.
I request that, you and your staff evaluate these "need" dates for those branches under your cognizance and indicate therein for each item your concurrence or what other actions will be deferred in order to meet these dates.
Please contact me if you have any questions regarding this request.
OR KJ on/ts 12// /84 12/]
84 Darrell G. Eisenhut, Director Division of Licensing C-ORB82:DL C-ORB83:DL C-ORBP4:DL DVassallo JMiller JStolz 12/
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/84 C-ORB85:DL JZwolinski 12/
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- SA:DL DCrutchfield 12/
/84 AD:OR:DL GLainas 12/
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/84
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FARLEY 2 LICENSING ACTIONS OPEN AS OF 7/1/84 November 30, 1984 TAC No.
Response
Branch Date Date SE Input Date Licensing Action Date Completion Status 43965 C-10 Heavy Loads (NUREG 0612) 44440 F-12 PASS Modifications 44580 F-14 RV and SV Testing ASB CHEB MEB 45133 F-26 Inadequate Core Cooling Inst.
CPB 45825 F-57 SB LOCA Outline RSB 46590 B-60 Equipment EQ (NUREG-0588) 47479 Modified CTMT Vent and Purge System 48016 B-46 Request to Delete License Condition 2.C.(19)(D)
C SE INPUT RECEIVED BY ORB-1 T
TENTATIVE SCHEDULE DATE EQB CSB ORB-1 45944 F-63 Technical Support Conter Region 2
46015 F-64 Operational Support Center Region 2
46087 F-65 Emergency Operations Facility Region 2
46303 F-68 Meteorological Data Upgrade METB 11/30/84 12/30/84T 7/25/84C 9/28/84C 12/31/84 1/30/85 3/30/85 8/30/85 8/30/85 8/30/85 6/30/85 12/30/84 9/21/84C 6/04/82C 7/25/84 10/11/84 01/31/85 2/28/85 4/30/85 9/30/85 9/30/85 9/30/85 9/30/85 1/30/85 12/1,5/84 12/21/84 COMPLETE COMPLETE OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN
TAC No.
Title Review Branch RAI Date RAI
Response
Date SE Input Date Licensing Action Date November 30, 1984 Compl eti on Status 48164 F-58 Compliance with 10 CFR 50.46 RSB 48570 B-41 Appendix R Schedular Exemptions ORB-1 48715 Pressure Isolation Valve TS Change MEB 49021 49067 RCS Depressurization Backup PAD 3.3 as applicable to succes-sive fuel cycles RSB CPB 49212 Delete Lic. Condition 2.C.(18)
EQ ORB-1 49213 Delete Lic. Cond.2.C. (20)
ORB-1 49214 Delete Lic. Cond.
2.C. (21)
PTRB 49215 Delete Lic. Cond.2.C.(21)(b)
RSB 49216 Delete Lic. Cond.2.C. (21)(g)
RSB 49217 Delete Lic. Cond.2.C. (21)(h)(1)
RSB 49218 Delete Lic. Cond.2.C. (21)(h)(2)
RSB 49220 Delete Lic. Cond.2.C. (21) (i ) (4)
RSB 49689 G-01 Reactor Coolant Pump Trip RSB 51089 A-17 R.G.1.97 Instrumentation ICSB 3/31/86 9/5/84C 05/31/85 5/30/84C NA NA 5/10/83C 5/27/83C 5/27/83C 5/27/83C 5/27/83C 5/27/83C 3/31/85 6/30/87 5/30/86 10/4/84 10/15/84 6/30/85 12/21/84 12/21/84 12/21/84 12/21/84 12/21/84 12/21/84 12/21/84 12/21/84 12/21/84 4/30/85 8/30/87 OPEN COMPLETE COMPLETE OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN November 30, 1984 TAC No.
Title Review Branch RAI Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 51159 51239 51631 52021 52227 F-08 Control Room Design Review F-09 Safety Parameter Display System HFEB HFEB Revise Tech Specs for Batteries PSB UV Confirmatory Life Test Program EQB C-15 Control of Heavy Loads (PII)
ASB 1/30/85T 2/28/85T 10/10/84C 2/15/85 12/6/84 7/19/84C 3/30/85 10/10/84 4/15/85 2/11/85 9/5/84 4/30/85 COMPLETE OPEN OPEN COMPLETE OPEN 52756 52837 52918 B-76 Post-trip Review Program B-77 RTS Components Equip. Class.
and Vendor Interface B-78 Post Maintenance Testing-RTS Comp.
LQB ICSB Region 2
4/1/85 7/1/85 8/1/85 5/1/85 8/1/85 9/1/85 OPEN OPEN OPEN 52999 53070 53123 53173 53266 53402 B-80 Reactor Trip System Reliability B-81 Prev. Maint. Reactor Trip Breakers B-82 Shunt Trip Attachment Reactor Vessel Capsule Report Snubber TS Table 3.7-4A Region 2
EQB ICSB MTEB Region 2
B-79 Post Main. Testing-Tech Specs ICSB 3/30/85 9/30/85 3/30/85 7/23/84C 11/30/84 6/7/84C 4/30/85 10/30/85 4/30/85 7/23/84 1/28/85 8/24/84 OPEN OPEN OPEN COMPLETE OPEN COMPLETE
November 30, 1984 TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 53469 54234 54236 Radiodine Canister Exemption Revise Tech Specs Heatup/Cool-down curves TS Per Gen. Let. 83-43 RAB MTEB Region 2
54390 RCS Vents Tech Specs ORAB 54451 Revise Met Tower Tech Specs 54453 Admin. Tech Spec Changes METB Region 2
54673 TS Changes
- Increased Fuel Enrichment 55030 Management Change - Admin TS 55170 IST Relief - Accum 8
RWST Check Valves 55413 TS Fig. 6.2-2 Change 55464 Petition License Cond.
2.F (Anti-trust)
CPB Region 2
SGEB RAB Region 2
SAB 54532 B-83 Gen. Ltr's. 83-36, 83-37 TS ORAB I
8/13/84 11/30/84 12/28/84 6/20/84C 7/31/84C 7/27/84C 6/24/84C 8/10/84C 7/26/84C 8/3/84C 8/24/84C 10/19/84C 3/1/85 10/23/84 1/28/85 2/21/85 9/12/84 10/4/84 9/21/84 9/12/84 11/9/84 11/13/84 11/15/84 11/27/84 4/30/85 COMPLETE OPEN OPEN COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE OPEN
D.C.
COOK 1
LICENSING ACTIONS OPEN AS OF 7/1/84 December 7, 1984 TAC No.
Title 11331 A-14 IST of Pumps 5 Valves Review Branch MEB 42460 B-60 Environmental Qualification EQB RAI RAI
Response
Date Date 2/1/85 T
3/1/85 T
SE Input Date 5/30/85 12/14/84 Licensing Action Date 6/25/85 2/1/85 Compl etion Status OPEN OPEN 43072 Structural Analysis of the Con-tainments Ultimate Strength 43523 Equipment Survivability:
Hydrogen Burn 44294 F-05 Procedures Generation Packages 44433 F-12 Post Accident Sampling Modifications 44573 F-14 RV and SV Testing 45126 F-26 Inadequate Core Cooling Instrumentation 45818 F-57 SB LOCA Outline 45937 F-63 Technical Support Center C
SE INPUT RECEIVED BY ORB-1 T
TENTATIVE SCHEDULE DATE SGEB CHEB HFBR CHEB NEB CPB RSB 8/15/84 8/15/84 12/19/83 1/30/85 T
2/1/85 2/1/85 1/1/85 1/1/85 3/1/85 3/1/85 3/30/85 10/30/85 3/1/85 3/1/85 2/1/85 2/1/85 4/15/85 4/1/85 4/30/85 11/30/85 OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN
D.C.
COOK 1
December 7,
1984 TAC No.
Ti t1e Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 46008 46080 46296 48158 48291 49520 49701 51080 51150 51230 51323 51602 52217 52746 52827 ISI Supplement MTEB Surveillance Reference to 4.0.5 MEB C-15 Control of Heavy Loads -
ASB Phase II B-76 Post Trip Review Program LQB B-77 RTS Components Equip. Class.
ICSB and Vendor Interface F-64 Operational Support Center F-65 Emergency Operations Facility F-68 Meteorological Data Upgrade METB F-58 Compliance with 10 CFR 50.46 RSB Miscellaneous T.S. Changes'QB Hydrogen Control Final Resolution CSB G-01 Reactor Coolant Pump Trip ISCB A-17 RG 1.97 Instrumentation ISCB F-08 Control Room Design Review HFEB F-09 Safety Parameter Display HFEB System 8/15/84 1/1/85 T
10/30/85 10/30/85 2/1/85 3/30/86 2/1/85 4/1/85 3/31/85 10/30/85 1/1/85 3/1/85 6/28/84 C
2/28/85 3/31/85 4/1/85 4/1/85 11/30/85 11/30/85 4/1/85 4/30/86 3/1/85 5/1/85 4/30/85 12/31/85 2/1/85 4/1/85 12/1/84 3/30/85 4/30/85 5/1/85 5/1/85 OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN
D.C.
COOK 1 December 7,
1984 TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 52908 52989 53064 B-78 Post Maintenance Testing RTS Comp.
B-79 Post Maint. Testing - TS B-80 Reactor Trip System Reliability ORB-1 11/14/84 ICSB EQB I
4/1/85 4/1/85 5/1/85 10/24/84 5/1/85 OPEN COMPLETE OPEN 53117 B-81 Prev.
Maint. Reactor Trip EQB Breakers 4/1/85 5/1/85 OPEN 53167 8-82 Shunt Trip Attachment ICSB 4/1/85 5/1/85 OPEN 53514 54385 RCS Vents Tech Specs RCS Vents Tech Specs per NUREG ORAB 0737 Item II.B.1 8/24/84 C
8/24/84 C
8/24/84 8/24/84 COMPLETE COMPLETE 54525 B-83 Tech Spech Per Gen. Ltr.
83-36$
83-37 ORAB 8/13/84 3/1/85 4/1/85 OPEN 55809 55951 Fire Exemptions Part 2 Hatch/Gap ISI/IST Start Date with reliefs MTEB 3/1/85 11/1/84 C
4/1/85 12/15/84 OPEN OPEN
D.C.
COOK 2 LICENSING ACTIONS OPEN AS OF 7/1/84 December 7,
1984 TAC No.
Title Review Branch RAI Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 04997 11334 Elec.
Sys.
Qual. for Steam Break LOCA A-14 IST of Pump 8 Yalves EQB MEB 2/1/85 3/1/85 T
12/14/84 5/30/85 2/1/84 6/25/85 OPEN OPEN 12619 42461 Panel 5 Elec.
Switchgear Qualification EQB B-60 Environmental Qualification EQB 2/21/84 12/7/84 T
12/7/84 12/1/84 2/1/85 2/1/85 OPEN OPEN 43071 43524 44295 44434 Structural Analysis of Contain-ments Ultimate Strength Equipment Survivability: Hydrogen Burn F-05 Procedures Generation F-12 Post Accident Sampling Modifications SGEB CHEB HFBR CHEB 8/15/84 8/15/84 2/1/85 2/1/85 1/1/85 1/1/85 3/1/85 3/1/85 2/1/85 2/1/85 OPEN OPEN OPEN OPEN 45127 45819 45938 46009 46081 46297 48159 F-26 Inadequate Core Cooling Inst.
CPB F-57 SB LOCA Outline F-63 Technical Support Center F-64 Operational Support Center RSB F-65 Emergency Operations Facility F-68 Meteorological Data Upgrade METB F-58 Compliance with 10 CFR 50.46 RSB 12/19/83 1/30/85 T
3/1/84 3/30/85 10/30/85 10/30/85 10/30/85 2/1/85 3/30/86 4/1/85 4/30/85 11/30/85 11/30/85 11/30/85 4/1/85 4/30/86 OPEN OPEN OPEN OPEN OPEN OPEN OPEN
D.C.
COOK 2 December 7,
1984 TAC No.
Title Review RAI Branch Date RAI SE
Response
Input Date Date Licensing Action Date Completion Status 48292 49519 49702 51081 51151 51231 51324 51603 52218 52747 52828 ISI Supplement MTEB Surviellance Reference to 4.0. 5 MEB C-15 Control of Heavy Loads -
ASB Phase II B-76 Post Trip Review Program LgB B-77 RTS Components Equip. Class.
ICSB and Vendor Interface Miscellaneous T.S.
Changes LOB Hydrogen Control Final Resolution G-Ol Reactor Coolant Pump Trip RSB A-17 RG 1.97 Instrumentation ISCB F-08 Control Room Design Review HFEB F-09 Safety Parameter Display HFEB System 8/15/84 1/1/85 T '/1/85 4/1/85 3/31/85 11/30/85 1/1/85 3/1/85 C
6/28/84 C
2/28/85 3/31/85 4/1/85 4/1/85 3/1/85 5/1/85 4/30/85 12/31/85 2/1/85 4/1/85 12/1/85 3/30/85 4/30/85 5/1/85 5/1/85 OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN 52909 52990 53065 53118 B-78 RTS Components Post Maint.
'Testing Procedures B-79 RTS Post Maint. Testing-Tech. 'Specs.
B-80 Reactor Trip System Reliability B-81 Prev. Maint. Reactor Trip Breakers ORB-1 ICSB EgB
'EQB 11/14/84 4/1/85 4/1/85 4/1/85 5/1/85 10/29/84 5/1/85 5/1/85 COMPLETE OPEN OPEN
D.C.
COOK 2 December 7,
1984 TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 53168 54386 54526 B-82 Shunt Trip Attachment RCS Vents Tech Specs B-83 Tech Spec Per Gen. Ltr.
83-36, 83-37 ICSB ORAB ORAB 8/13/84 4/1/85 8/24/84 C
3/1/85 5/1/85 8/24/84 4/1/85 OPEN COMPLETE OPEN 55810 55952 Fire Exemptions Part 2 Hatch/Gap ISI/IST Start Date with reliefs MTEB 3/1/85 11/1/84 C
4/1/85 12/15/84 OPEN OPEN
LICENSING ACTIONS FOR GINNA TAC NO.
TITLE REVIEW BRANCH SE INPUT.
DATE LICENSING ACTION DATE COMPLETION STATUS 08414 08416 11220 12461 42520 42910 43047 TS Surveillance - Hydraulic Snubbers MEB TS Surveillance for Mechanical Snubbers MEB Test Results Conversion POL to FTOL Tendon Surveillance Prog'ram ORB F5 ME8 SGEB Masonry Wall Design
Response
to IE Bulletin 80-11 Technical Specifications Defining Operability for Safety Systems SGEB PMAB ORB 0'4 Region I Environmental Qualification of Safety EQB Related Electrical Equipment (80-CLI-21)
ORAB 03/30/85 03/30/85 01/30/85 05/30/85 01/30/85 04/30/85 04/30/85 12/14/84 02/28/85 04/30/85 06/30/85 02/28/85 OPEN OPEN COMPLETE OPEN OPEN OPEN OPEN 43307 44305 44584 45829 48474 Non Tech Spec TMI Related Items Procedures Generation Package (Supplement 1, NUREG-0737)
RV and SV Testing NUREG-0737 II.K.3.30, SB LOCA Outline Review of Additional Submittals on SGTR ORB 375 DRAB DST MEB RSB MTEB RAB MEB 12/30/84 10/06/82C 11/29/84C 12/31/84 09/30/85 05/31/85 05/30/85 01/30/85 OPEN OPEN OPEN OPEN OPEN
TAC NO.
TITLE REVIEW BRANCH SE INPUT DATE LICENSING ACTION DATE COMPLETION STATUS 48880 49135 49175 49177 49178 49292 49346 49677 49734 52099 52231 52396 52399 Tech Spec Changes for SEP Topics II-A and III-7.A Pump 5 Valve Inservice Testing Valve Exercising and Surveillance Requirements Allow Low Power Physics Testing Prior to or During Certain Valve Testing TS change for RWST Operability and other clarifications Heatup and Cooldown - Reactor Surveillance Capsule T
STGR Procedures Followup Reactor Coolant Pump Trip Generic Letter 82-16 Management Consolidation Control of Heavy Loads - Phase II (Followup of MPA C-10)
Delete
Response
Time Testing of Auxiliary Feedwater Systems and Containment Isolation Valve Circuits SEP TS change SEPB MEB MEB ORB 85 RSB ORB j/5 MTEB CPB RAB RSB RSB CBP ORB 85 ASB ICSB ORB P5 SFPB 07/31/85 I
05/30/85 04/30/85 07/29/83C 01/30/85 04/08/83C 11/30/84C 03/31/85 02/01/84C 12/31/84 02/15/85 08/30/85 06/30/85 05/30/85 01/30/85 02/28/85 01/31/85 07/19/84 04/31/85 07/30/84 08/14/84 06/31/85 01/30/85 04/30/85 OPEN OPEN OPEN OPEN OPEN OPEN COMPLETE OPEN COMPLETE COMPLETE OPEN OPEN OPEN
TAC NO.
TITLE REVIEW BRANCH SE INPUT DATE LICENSING ACTION DATE COMPLETION STATUS 52404 52760 52841 52922 53003 53072 53125 53174 53431 53432 53433 TS Chanae - Revise List of Hydraulic Snubbers Item 1. 1 - Post Trip Review Program Description and Procedures ORB 0'5 LQB Reactor Trip System Reliability-Vendor Related Modifications Items 4.2. 1 5 4.2.2 - Preventative Maintenance Program for Reactor Trip Breakers - Maintenance 5 Trending DRAB EgB ORAB Item 4.3 - Automatic Actuation of Shunt ICSB Trip Attachment for W and BSW Plants ORAB Alternative Shutdown System-Appendix R
Process Control Program CMEB ASB RAB Adjustment of ISI Pgm 10 year Interval MTEB Start Dates MEB Item 2.1 - Equipment Classification ICSB and Vendor Interface - RTS Components ORAB Items 3. 1. 1 8 3. 1.2 - Post Maintenance ORAB Testing Procedures/Vendor Recommendations RTS Components Item 3. 1.3 - Post Maintenance Testing -
ORAB Chanqe to TSs - RTS Components ICSB 03/30/85 12/30/84 11/30/84 04/31/85 07/30/85 07/30/85 07/30/85 07/30/85 07/30/85 06/30/85 09/30/85 01/31/85 11/07/84 12/30/84 OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN COMPLETE OPEN
TAC NO.
TITLE REVIEW BRANCH SE INPUT DATE LICENS ING ACTION DATE COMPLFTION STATUS 53592 53758 53841 53912 53985 54068 54291 54357 54363 Item 1.2 - Post Trip Review - Data and Information Capability Items 3.2. 1 5 3.2.2 - Post Maintenance Testing Procedures and Vendor Recommendations
- All SR Components Item 3.2.3 - Post Maintenance Testing-Changes:to Tech Specs - All SR Components Items 4.2.3 8 4.2.4 - Preventative Maintenance Program for Reactor Trip Breakers - Life Testing and Replacement Items 4.5.2 5 4.5.3 - Reactor Trip Functional Testing - Alternatives 8 Test Intervals Item 4.5. 1 - Reactor System Functional Capability Exemption Request - Emergency Exercise Management Personnel Change Delete Restriction on Movement of Shipping Cask with Auxiliary Bldg Crane HFEB ORAB ORAB ICSB ORAB E(B ORAB ICSB ORAB ORAB ORB 85 ORB 85 ASB 10/05/84C 09/30/85 09/30/85 09/30/85 08/30/85 08/30/85 08/30/85 10/26/84 07/30/84C 12/30/84 OPEN OPEN OPEN OPEN OPEN OPEN COMPLETE COMPLETE OPEN 54364 54369 Delete Spacing Restrictions of Recently Discharged Fuel in Spent Fuel Racks AEB
'SB SEP Structural Upgrade Program Followup SEPB 01/31/85 02/28/85 10/05/84 OPEN COMPLETE TAC NO.
TITLE REVIEW BRANCH SE INPUT DATE LICENSING ACTION DATE COMPLETION STATUS 54371 54392 RCS Vents Technical Specifications (NUREG-0737, Item II.B.1)
ORAB Seismic Structural Eval. Main Control SEPB Board SEP III-6 01/31/85 I
12/31/84 02/28/85 02/28/85 OPEN OPEN 54509 54536 54659 54762 54849 55300 55316 55356 Disposal of Low Level Radioactive Waste Technical Specifications Covered by Generic Letter 83-36, 83-37 for NUREG-0737 Reporting Requirements
- Conformance with 50.72, 50.73 and 50.49 Increase Capacity of Spent Fuel Pool Storage Racks License Conversion SER Supplement Exemption - Inspection of Containment Tendons for Broken Wires Justification of Westinghouse DNBR W-3 Correlation Design Limit below 1000 PSIA Item 4.3(TS) - Automatic Actuation of Shunt Trip for W and B 5 W Plants RAB ORAB Region I ASB CPB AEB RAB EHEB SGEB CMEB ORB 85 ORB P5 CPB RSB ORAB 12/30/84 01/31/85 01/30/85 10/23/84 01/31/85 02/28/85 11/14/84 10/17/84 02/28/85 10/17/84 09/30/85 COMPLETE OPEN OPEN COMPLETE COMPLETE OPEN COMPLFTE OPEN
TAC NO.
TITLE REVIEW BRANCH SE INPUT DATE LICENSING ACTION DATE COMPLETION STATUS 55437 55624 55862 Request for Modification of (Item II.D.3.4) TMI Confirmatory Order Deletion of Outdated Hot Channel Factors Diesel Generator Reliability TSs (GL 84-15)
ll/16/84C 12/30/84 01/30/85 01/30/85 03/31/85 OPEN OPEN OPEN
North Anna, Units 152 LICENSING ACTIONS OPEN AS OF 7/1/84 December 10, 1984 TAC No.
UNIT TITLE REVIEW BRANCH RAI RAI
RESPONSE
DATE DATE SE LICENSING INPUT ACTION COMPLETION DATE DATE STATUS 52248 1
C-15 Heavy Loads (PII) 52249 2
C-15 Heavy Loads (PII) 51110 1
A-17 R.G.1.97 Instrumentation 51111 2
A-17 R.G.1.97 Instrumentation 42497 1
B-60 EQ NUREG-0588 42540 2
B-60 EQ NUREG-0588 42895 1
B-59 Masonry Walls 56382 2
B-59 Masonry Walls 52777 1
B-76 Post Trip Review Program 52778 2
B-76 Post Trip Review Program 52858 1
B-77 RTS Comp.
Equip Class 52859 2
B-77 RTS Comp.
Equip Class 52939 1
B-78 Post Main-Test Procedure 52940 2
B-78 Post Main-Test Procedure (XX/XX/XX)
PM Date to meet 75K completion 7/1/85
- SER TO BE ISSUED WITH OPEN ITEMS ASB ASB ICSB ICSB EOB SGEB SGEB LQB LQB ICSB ICSB Region 2
Region 2
13109 1
B-48 Station Electrical Distribution PSB 48331 2
B-48 Station Electrical Distribution PSB (5/1/85) 6/01/85 (5/1/85) 6/01/85 OPEN OPEN (5/15/85) 6/15/85 OPEN (5/15/85) 6/15/85)
OPEN 8/7/84C 11/13/84 COMPLETE 8/7/84C 11/13/84 COMPLETE 3/30/85 4/30/85 OPEN 3/30/85 4/30/85 OPEN 11/28/84* 12/28/84 OPEN 11/28/84* 12/28/84 OPEN 11/29/84C 12/29/84 OPEN 12/05/84C 12/29/84 OPEN 2/30/85 3/30/85 OPEN 2/30/85 3/30/85 OPEN 4/1/85 5/01/85 OP EN 4/1/85 5/01/85 OPEN
TAC No.
UNIT TITLE REVIEW RAI BRANCH DATE RAI
RESPONSE
DATE SE LICENSING INPUT ACTION COMPLETION DATE DATE STATUS 53020 53021 53081 53082 53134 53135 53181 53182 51180 51181 51260 51261 45150 45151 44249 44250 1
8-79 Post.
Maint Testing T.S.
2 B-79 Post.
Maint Testinq T.S.
1 B-80 Reactor Trip Reliability 2
B-80 Reactor Trip Reliability ICSB ICSB Region II Region II 1
8-81 Prev Maint Reac Trip Breaker EQB 2
8-81 Prev Maint Reac Trip Breaker EQB 1
B-82 Shunt Trip Attachment 2
B-82 Shunt Trip Attachment ICSB ICSB 1
F-09 SPD System 2
F-09 SPD System HFEB HFEB 1
F-26 Inadequate Core Cooling Inst CPB 2
F-26 Inadequate Core Cooling Inst CPB 1
Inadeouate Core Cooling Guide 2
Inadequate Core Cooling Guide 1
F-08 Control Room Design Review HFEB 2
F-08 Control Poom Design Review HFEB
{4/30/85) 5/30/85 OPEN (4/30/85) 5/30/85 OPEN (5/15/85) 6/15/85 OPEN (5/15/85) 6/15/85 OPEN (3/30/85) 4/30/85 OPEN (3/30/85) 4/30/85 OPEN 7/23/84C 7/24/84 COMPLETE 7/23/84C 7/24/84 10/10/84C 11'/19/84 COMPLETE COMPLETE 9/21/84C 11/06/84 9/21/84C 11/06/84 COMPLETE COMPLETE 7/02/84 COMPLETE 7/02/84 COMPLETE 10/10/84C 11/19/84 COMPLETE 3/31/85 4/31/85 OPEN 3/31/85 4/31/85 OPEN Tnc No.
HIIIT TITLE REVIEW BRANCH 463?1 463?.2 45843 45844 48182 48183 44598 44599 45962 1
F-68 Meteorological Data Upgrade HETB 2
F-68 Meteorological Data Upgrade HETB RSB RSB 1
F-57 SB Loca Outline 2
F-57 SB Loca Outline 1
F-58 Compliance with 10 CFR 50.46 RSB 2
F-58 Compliance with 10 CFR 50.46 RSB MEB HEB Region II 1
F-14 RY & SV Testing 2
F-14 RV
& SV Testing 1
F-63 Technical Support Center RAI DATE RAI
RESPONSE
DATE SE L ICENS ING INPUT ACTION DATE DATE (5/30/85) 6/30/85 COUPLET ION STATUS OPEN (5/30/85) 6/30/85 OPEN 3/30/85 4/30/85 OPEN 3/30/85 4/30/85 OPEN 3/30/86 4/30/86 OPEN 3/30/86 4/30/86 OPEN 3/30/85 4/30/85 OPEN 3/30/85 4/30/85 OPEN TO BE SCHEDULED OPEN 46033 1
F-64 Operational Support Center 46034 2
F-64 Operational Support Center 46105 1
F-65 Emerg.
Operation Center 46106
?
F-65 Emerg.
Operation Center 45963 2
F-63 Technical Support Center EPB Region II EPB Region II EPB Region II EPB Region II EPB Region II TO BE SCHEDULED OPEN (5/30/85) 6/30/85 OPEN (5/30/85) 6/30/85 OPEN TO BE SCHEDULED OPEN TO BE SCHEDULED OPEN
TAC No.
UNIT TITLE REVIEW BRANCH RAI RAI
RESPONSE
DATE DATE SE INPUT DATE LICENSING ACTION COMPLETION DATE STATUS 44319 44320 46921 1
F-05 Abnorm. Tran. Oper. Guide'ls PSRB 2
F-05 Abnorm. Tran. Oper. Guide'.ls PSRB 2
Control Room Human Factors Rev.
HFEB 12/30/85 2/15/85'2/30/85 2/15/85 (3/15/85) 4/15/85 OPEN (3/15/85) 4/15/85 OPEN (1/30/85) 2/15/85 OPEN 53528 53529 54789 54790 1
PM Briefing Book 2
EA Spent Fuel 1
and Transportation Hearing Issue SER E
EA Spent Fuel 2
and Transportation Hearing OPB-3 ORB-3 Multi Branch Multi Branch 7/01/84 COMPLETE 7/01/84 COMPLETE 5/18/84C 7/02/84 COMPLETE-5/18/84C 7/02/84 COMPLETE 44870 1
Revise TS Augmented Spent Fuel ORB-3 44869 2
Revise TS Auamented Spent Fuel ORB-3 By ASLB Order By ASLP Order 12/20/84 OPEN 12/20/84 OPEN 44868 1
Amend TS Receipt Surry Spent Fuel ORB-3 44867 2
Amend TS Receipt Surry Spent Fuel ORB-3 54472 1
Relief ASME XI Vol. Acc.
8 Boron Tank MTEB 54473 2
Relief ASME XJ Vol. Acc.
8 Boron Tank MTEB 54165 2
Reg.
Pev. Vital Area Validation SSPB 7/2/84C IN HEARING OPEN 7/2/84C IN HEARING OPEN 8/6/84C 8/31/84 COMPLETE 8/6/84C 8/31/84 COMPLETE 2/2/84C 7/20/84 COMPLETE
TAC No.
UNIT TITLE REVIEW RAI BRANCH DATE RAI LICENSEE SE
RESPONSE
INPUT DATE DATE LICENSING ACTION COMiPLET ION DATE STATUS 52575 2
Revise TS Fract.
Pow. Multip.
(0.2 to 0.3) 49523 2
Revise TS RCS TAV to 587.8 Phase Il 53522 1
,Revise Reactor Trip Sys.
P-7 Interlock Multi Branch Multi Branch=
ORB-3 I
10/3/84C 10/3/84C 10/3/84C 10/15/84 COMPLETE 10/3/84C 10/15/84 COMPLETE 11/15/84C 12/6/84 COMiPLETE 53523 2
Revise Reactor Trip Sys.
P-7 Interlock ORB-3 49525 ORB-3 1
Evaluate Main Transformer Fault LLNL 11/15/84C 12/6/84 COMPLETE 4/29/84C 11/27/84 COMPLETE 46734 2
Follow up on 7/3/81 Transformer ORB-3 Faul ts LLNL 52478 1
Peduce Time Core Surveillance Rpt ORB-3 52479 2
Reduce Time Core Surveillance Rpt ORB-3 54501 2
Revise TS Generic Letter 83-30 ORB-3 ORB-3 53524 1
Revise TS for LCO in Modes 3,455 SSPB 53525 2
ORB-3 Pevise TS for LCO in Modes 3,455'SPB 4/29/84C 11/27/84 COMPLETE ll/8/84C 12/3/84 COMPLETE 11/8/84C 12/3/84 COMPLETE 11/13/84C 11/28/84 COMPLETE 1/26/85 1/31)85 OPEN I/26/85 1/31/85 OPEN 54505 1
Revise TS for LER Report 50.72 E
50.73 ORB-3 11/21/84C 1/26/85 1/31/85 OPEN
TITLE TAC No.
UNIT 2
Revise TS for LER Report 50.72 8
50.73 54506 1
Revise TS for SG/RGP Support Snubbers 54465 2
Revise TS for SG/RGP Support Snubbers 2
Revise S
1 out of 2 H2 Recombiners In Op. 53253 53521 53134 1
83-28, Item 4.2.1 8 4.2.2 2
83-28, Item 4.2.1 5 4.2.2 1
Administrative Changes 2
Administrative Changes 1
G-01 Reactor Coolant Pump Trip 2
G-01 Reactor Coolant Pump Trip 53135 52053 53052 49665 49666 1
A-14 Inservice Testing (P&V)
I 2
A-14 Inservice Testing (P8V) 52414 54858 1
8-83 Gen Ltrs 83-36, 83-37 2
B-83 Gen Ltr's 83-36, 83-37 54549 54550 LICENSING ACTION COMPLETION DATE STATUS RAI LICENSEE SE
RESPONSE
INPUT DATE DATE REVIEW RAI BRANCH DATE I
11/21/84C 1/26/85 1/31/85 OPEN ORB-3 MEB 11/27/84 12/27/84 11/27/84 12/27/84 OPEN OPEN MEB SSPB ORB-3 11/27/84 12/27/84 EOB 11/23/84 12/30/84 EgB 11/23/84 12/30/84 OPEN OPEN OPEN ORB-3 ORB-3 11/13/84 OPEN 1 1/13/84 OPEN 3/31/85 4/31/85 OPEN 3/31/85 4/31/85 OPEN (4/30/85) 5/30/85 OPEN (4/30/85) 5/30/85 OPEN 11/15/84 1/30/85 OPEN 1 1/15/84 1/30/85 OPEN RSB RSB MEB MEB ORAB DRAB
TAC No.
UNIT TITLE REVIEW RAI BRAMCM DATE RAI LICENSEE
RESPONSE
DATE SE INPUT DATE LICENSING ACTION COMPLETION DATE STATUS 54400 1
RCS Vent TS 54401 2
RCS Vent TS 54832 1
Appendix R Reanalysis Exemp.
54833 2'ppendix R Reanalysis'xemp.
54845 1
Core Reload Methodology 54846 2
Core Reload Methodology 54834 2
TS Valves Tested Event V
ORAB ORAB CHEB ASB CHEB ASB CPB CPB 2/30/84 3/30/85 OPEN 2/30/84 3/30/85 OPEN (4/15/85) 5/15/85 OPEN (4/15/85) 5/15/85 OPEN 6/19/84 7/2/84 COMPLETE 6/19/84 7/2/84 COMPLETE (2/30/85) 3/30/85 OPEN
BRUNSMICK UNIT 1 - LICENSING ACTIONS OPEN AS OF 07/Ol/84 December 10, 1984 TAC No.
Title Review Branch P,AI RAI
Response
Date Date SE Input Date Licensing Action Date Completion Status 11264 A-14 10 CFR 50.55(a)(g)
IST 12829 42484 42876 43418 43737 48489 8-48 Adeq. of Station Dist.
B-60 Environmental gual.
B-59 Hasonry Mall Design B-41 New Appendix R
B-65 Pipe Breaks in BMR E-04 Single Loop Operation Reg II PS EOB SGEB ASB/ChEB 3/29/84C 9/27/84 11/30/84C 4/27/84C 4/24/84C WB/ASB 1/30/85 2/28/85 CPB 1/15/85 7/6/84 2/28/85 12/30/84 11/30/84 12/30/84 3/30/85 2/15/85 51076 A-17 Instrumentation per RG 1.97 ICB 10/26/84C 1/30/85 '/30/85 52742 52823 52904 52985 54521 8-76 Salem Item 1.1 8-77 Salem Item 2.1 B-78 Salem Item 3.1.1
& 3.1.2 B-79 Salem Item 3.1.3 8-83 NUREG-0737 TIS L(B ICB ICB ICB ORAB 3/20/84C 11/07/83C 11/07/83C 11/07/83C ll/07/83C 3/30/85 4/1/85 12/30/84 8/30/85 6/30/85 52213 C-15 Control of Heavy Loads (II)
ASB 9/5/84 3/30/85 1/30/85 12/30/84 1/30/85 4/30/85 3/15/85 7/30/85 4/30/85 5/1/85 1/31/85 9/30/85 7/30/85 8/13/84 Complete Complete
n' TAC No.
Title Review Branch RAI RAI
Response
Date Date SE Input I
Date Licensing Action Date Completion Status 44287 45119 45587 45930 46001 F-64 III.A.1.2 OSC 46073 46289 47585 47656 47727 51146 51226 F-65 III.A.1.2 EOF F-68 III.A.2.P Met. Data F-23 II.F.1.4 Cont. Press.
F-24 II.F.1.5 Cont. Water F-25 II.F.1.6 Cont.
Hydrogen F-08 I.D.1 C.R. Design Rev.
F-09 I.D.2 S.P.D.S.
F-05 I.C. I.3.a PAP F-26 II.F.P.3 ICC Inst F-46 II.K.3.16 R.V. Challenge F-63 III.A.1.2 TSC PTRB CPB RSB HFEB HFEB 7/27/84C 10/31/84 11/30/84 5/17/84 12/31/84 12/31/84 12/31/84 12/31/84 9/17/84 3/30/85 3/30/85 3/30/85 3/30/85 3/9/84C 3/9/84C 12/31/84 6/29/84 6/29/84 12/31/86 2/28/85 3/9/84C 6/29/84 12/30/84 ll/14/84 4/30/85 4/30/85 4/30/85 4/30/85 7/30/84 7/30/84 7/30/84 I/3I/87 3/28/85
.Hold for GI 850 Complete Complete Complete Complete
TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input I
Date Licensing Action Date Completion Status 49276 51816 52537 53233 54190 Elect. Dist. Voltage Thermal Hydraulic Code
Response
to 7/22/83 Order Disposal of llaste Oil Radwaste Scaling Factors 54354 54840 54961 54999 55031 PSV Operability Cont. Integ. - HSIV Closure Raychem Cable Test Delete Snubber Table Correct T/S Admin 55036 SALP Review 55230 Channel Trip 55232 Operating Conditions 54193 Degraded Voltage T/S 54270 1983 ISI Report PS CPB HETB HETB HETB PS HEB EQB CSB EQB Reg II Reg II Reg II Reg II 9/27/84C 7/31/84C 4/6/84C 4/20/84C 12/30/84 11/14/84C 1/31/85 2/28/85 10/3/84 9/1/84 11/30/84 1/30/85 2/28/85 11/6/84C 11/30/84 8/31/84 8/23/84 9/27/84 9/27/84 10/18/84 2/28/85 9/4/84 1/1/85 3/30/85 10/22/84 9/1/84 12/30/84 2/28/85 3/30/85 10/22/84 9/18/84 2/1/85 12/30/84 9/10/84 9/22/84 9/7/84.
1?/04/84 12/04/84
.Complete Complete Complete Complete Complete Complete Complete Complete Complete TAC No.
Title 55252 55254 55256 Hark I Contain Control Rod Assembly Admin Controls 55419 55494 Pipe Crack Inspection App R Exemption 55258 SFP Mater Level Review RAI Branch Date CSB CPB
~ AEB NETB ChEB RAI
Response
Date 10/9/84C SE Input Date 8/31/84 8/13/84 1J/1/84 9/10/84 10/18/84 Licensing Action Date 9/22/84 9/22/84 ll/1/84 10/25/84 10/18/84 8/21/84 Completion Status Complete
- Complete Complete Complete Complete Complete
BRUNSWICK UNIT 2 - LICENSING ACTIONS OPEN AS OF 07/01/84 December 10, 1984 TAG No.
Title 11265 A-14 10 CFR 50.55(a}(q} IST Review 8ranch Reg II RAI Date RAI
Response
Date SE Input Date 7/6/84 Licensing Action Date 9/5/84 Completion Status Complete 12830 42485 42877 43417 43735 46779 51077 52214 52743 52824 5?905 52986 54522 B-48 Adeq. of Station Dist.
B-60 Environmental equal.
8-59 Masonry Wall Design B-41 New Appendix R
B-65 Pipe Breaks in BWR E-04 Single Loop Operation EljB SGEB ASB/ChEB 9/27/84C 11/30/84C 4/27/84 4/24/84C E(B/ASB 1/30/85
?/?8/85 CPB 1/15/85 2/28/85 12/30/84 ll/30/84 12/30/84 3/30/85 2/15/85 B-76 Salem Item 1.1 B-77 Salem Item 2.1 B-78 Salem Item 3.1.1
& 3.1.2 B-79 Salem Item 3.1.3 B-83 NUREG-0737 TIS LQB
!CB ICB ICB ORAB 10/26/84C 1/30/85 6/30/85 3/20/84C 11/07/83C 11/07/83C 11/07/83C ll/07/83C 3/30/85 4/1/85
'2/30/84 8/30/85 6/30/85 A-17 Instrumentation per RG ].97 ICB C-15 Control of Heavy Lnads
( II}
ASB 3/30/85 1/30/85 12/30/84 1/30/85 4/30/85 3/15/85 7/30/85.
4/30/85 5/1/85 1/31/85 9/30/85 7/30/85 8/13/84 Complete
TBC No.
Title 44288 45120 45588 45931 46002 46074 46290 47586 47657 47728 51147 51227 F-05 I.C.I.3.a PGP F-26 II.F.2.3 ICC Inst F-46 II.K.3e16 R.V.. Challenge F-63 III.A.1.2 TSC F-64 III.A.1.2 OSC F-65 III.A.1.2 EOF F-68 III.A.2.2 Net.
Data F-23 II.F.1.4 Cont. Press.
F-24 II.F.1.5 Cont. Water F-25 II.F.1.6 Cont.
Hydrogen F-08 I.D.1 C.R. Desiqn Rev.
F-n9 I.De2 S.P.O.S.
Review Branch PTRB CPB RSB HFEB HFFB RAI RAI
Response
Date Date 7/27/84C 10/31/84C 5/17/84 12/31/84 12/31/84 12/31/84 12/31/84 3/9/84C 3/9/84C 3/9/84C 12/31/84 SE Input Date I
11/30/84 9/17/84 3/30/85 3/30/85 3/30/85 3/30/85 6/29/84 6/29/84 6/29/84 12/31/86 2/28/85 Licensina Action Date 12/30/84 ll/14/84 4/30/85 4/30/85 4/30/85 4/30/85 7/30/84 7/30/84 7/30/84 1/31/87 3/28/85 Completion Status
. Hold for GI 850 Complete Complete Complete Complete TAC Ho.
Title 49277 Elect. Dist. Voltage 51817 Thermal Hydraulic Code 53234 Disposal of Waste Oil 54147 Battery Capacity 54191 Radwaste Scaling Factors 54194 Degraded Voltage T/S 54355 PSV Operabi1 ity 54839 Cont. Integ. - HSIV Closure 54962 Raychem Cable Test 54966 EQ Extension Request 55000 Delete Snubber Table 55001 Check Valve Surv Ext.
55032 Correct T/S Admin 55037 SALP Review 55231 Channel Trip Review RAI Branch Date PS CPB HETB RAI
Response
Date 9/27/84C 7/31/84 4/20/84C ll/30/84 12/30/84 PS CSB EQB EOB Reg II Reg II Reg II 11/6/84C Reg II ll/14/84C 1/31/85 2/28/84C SE Input Date 2/28/85 10/3/84 11/30/84 12/30/84 1/30/85 2/28/85 9/4/84 1/1/85 11/30/84 9/27/84 8/31/84 8/23/84 9/27/84 Licensing Action Date 3/30/85 10/22/84 12/30/84 1/30/85 2/28/85 3/30/85 9/18/84 2/1/85 12/30/84 9/28/84 9/10/84 8/10/84 9/22/84 9/7/84 12/04/84 Completion Status
, Complete Complete Complete Complete Complete Complete Complete Complete
TAC No.
Title 55233 Operating Conditions 55253 55255 55257 55259 05420 55495 h1ark I Contain Control Rod Assembly Admin Controls SFP Mater Level Pipe Crack Inspection App R Exemption 5525l Reload 5 T/S Reviewer Branch Reg II CPB CSB
~ CPB
Response
Date 10/9/84C SE Input Date 9/27/84 8/31/84 8/13/84 ll/1/84 9/10/84 10/18/84 Licensing Action Date 12/04/84 9/22/84 9/22/84 9/22/84 11/1/84
]n/25/84 10/18/84 8/21/84 Compl eti on Status Complete Complete Complete Complete Complete Complete Complete Complete
Three Mi,le Island I LICENSING ACTIONS OPEN AS OF 7/1/84 December 8, 1984 TAC No.
Multi lant Titie RAI Review RAI
Response
Branch Date Date SE Input
'ate Licensing Action Date Completion Status 11286 Three Mile Island 1 - TS for DL Hydraulic Snubbers (TSCR 105) (B-17) 8/31/84(c) 12/31/84 42127 51361 Three Mile Island 1 - Instru-mentation to Follow the Course of an Accident (R.G.
1.97)
(A-17)
ICSB Three Mile Island 1 - Decay Heat
. RSB Removal Capability Tech Specs (B-57) 7/9/84
- 1/30/85 2/30/85 5/30/85 3/15/85 6/30/85 52808 52889 52970 53051 Three Mile Island 1 - Item 1.1 Post Trip Review Program Description and Procedures (Salem)
(B-76)
Three Mile Island 1 - Item 2.1 Equipment Classification and Vendor Interface - RTS Components (Salem)
(B-77)
Three Mile Island 1 - Items 3. 1. 1 and 3. 1.2 - Post Maintenance Testing Procedures/Vendor Recommendations RTS Components (Salem)
(B-78)
Three Hile Island 1'
Item 3. 1.3 Post Maintenance Testing-Changes to Tech Specs-RTS Components (Salem)
(B-79)
LOB ICSB R:I ICSB 5/30/85 5/30/85 5/30/85 5/30/85 6/30/85 6/30/85 6/30/85 6/30/85
TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 53105 53158 Three Mile Island I - Reactor R: I Trip System Reliability - Vendor Related Modifications (Salem)
(8-80)
Three Mile Island 1 - Items 4.2. 1 EgB and 4.2.2 - Preventative Maintenance Program for Reactor Trip Breakers-Maintenance 5 Trending (Salem)
(8-81) 5/30/85 2/28/85 6/30/85 3/31/85 53200 Three Mile Island 1 - Item 4.3 -
ICSB Automatic Actuation of Shunt Trip Attachment for W and BOW Plants (Salem)
(8-82) 6/27/84(c) 7/12/84 Complete 43513 Three Mile Island 1 - Environ-mental qualification of Safety Related Electrical Equipment (80-CLI-21) (8-60)
EgB 1/15/85 1/30/85 43043 Three Mile Island 1 - Technical Specifications Defining Oper-ability for Safety Systems (TSCR 139)
(D-17)
R:I 6/19/84(c) 8/7/84 Complete 47131 52279 Three Mile Island 1 - Control of ASB Heavy Loads at Nuclear Power Plants (NUREG-0612)
(C-10)
Three Hile Island 1 - Control of ASB Heavy Loads Phase II (Followup of HPA¹C-10) (C-15) 12/15/84 3/30/85 12/30/84 4/30/85 49698 Three Nile Island 1 - Reactor Coolant Pump Trip '(G-1)
RSB 5/30/85 6/30/85 42602 Three Mile Island 1
Long Term CSB Review Containment Purge and Vent (8-24) 1 3/23/84(c) 1/30/85
TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status NUREG-0737 47049 Three Nile Island 1 - NUREG-0737 AEB III.D.3.4 Control Room Habitability (F-70) 7/13/84(c) 8/22/84 Complete 48286 45987 46058 46130 48287 51211 51291 Three Nile Island 1 - NUREG-0737 RSB II.K.3.30 SBLOCA Methods (F-57)
Three Mile Island 1 - NUREG-0737 R: I III.A.1.2, Technical Support Center '(F-63)
Three Nile Island 1 - NUREG-0737 R: I III.A.1.2, Operational Support Center (F-64)
Three Mile Island 1 - NUREG-0737 R: I III.A.1.2, Emergency Operations Facility (F-65)
Three Mile Island 1 - NUREG-0737 HETB III.A.2.2, Heterological Data Upgrade (F-68)
Three Mile Island 1 - I.D. 1 Control Room Design Review (F-8)
HFEB Three Mile Island 1 - I.D.2 HFEB Safety Parameter Display Sys.
(F-9) 5/30/85 TBD TBD TBD TBD 12/15/84 2/28/85 6/30/85 TBD TBD TBD TBD 1/30/85 3/31/85
- (FY-86)
- (FY-86)
- (FY-86)
- (FY-86) 44624 Three Hile Island 1 -
RV and SV HEB Testing '(.F-14)
- Not scheduled. before 7/1/85.
6/15/84(c) 8/22/84 Complete
1F
TAC No.
48208 47048 Title Three Mile Island 1 - NUREG-0737 II.K.3.31, Compliance with 10 CFR 50.46 (F-58)
Three Mile Island 1 - NUREG-0737 II.F.2, Inst. to Detect ICC (F-26)
Review RAI Branch Date CPB RSB RAI
Response
Date SE Input Date 10/31/85 TBD Licensing Action Date 11/30/85 8/30/86 Completion Status
~(FV-86}
- (FY-86)
Plant S ecific 55039 54243 55112 55302 55301 55040 54600 Three Mile Island 1 - Management Integrity Issues Review Three Mile Island 1 - Management Integrity (Cert Item 64)
Three Mile Island 1 - Staff
Response
to Comm. Order on ALAR-772 Three Mile Island 1 - NUREG-0680 Supplement 5
Three Mile Island 1 - Fire Proof Cable Test Report Review Three Mile Island 1 - Neutron Source Data for Flux Reduction Veridication Three Mile Island 1
Emergency Feedwater Auto-Initiation (II.E.1.2. Part 1)
DL DL DL DL CMEB CPB ICSB 7/26/84 7/26/84 7/26/84 7/26/84 12/30/84 6/21/84 7/31/85(Est.)
8/31/85 7/26/84 7/26/84 7/26/84 7/26/84 9/15/84 1/30/85 9/30/85 Complete Complete Complete Complete Complete
- Not scheduled. before 7/1/85.
TAC No.
54504 53302 53295 55111 Titie Three Nile Island 1 - Back-Up Incore Thermocouple Operability (TSCR 130)
Three Mile Island 1 - Pre-Operational Testing Review Three Nile Island
- 1. - Steam Generator Hearings Three Nile Island 1 - Staff Action on FEMA Findings (1983 Exercise)
Revi ew RAI Branch Date CPB DL DL IE RAI
Response
Date SE Input Date 6/7/84(c) 2/14/85 Licensing Action Date 12/21/84 9/13/84 12/31/84 2/28/85 Completion Status Complete 55234 55382 Three Mile Island 1 - TSCR 8135 METR Waste Gas Holdup - Hydrogen/
Three Nile Island 1 - Item 4.3 TS DL Automatic Actuation of Shunt Trip for W and BSW plants - TS 11/20/84(c) 2/15/85 9/15/84 Complete 52588 49831 Three Nile Island 1 - TSCR 38 Fuel Cask Drop Three Nile Island 1 - TSCR 123 Steam Generator Repair TSs DL 3/30/85 6/30/85 12/31/84 51412 Three Nile Island 1 - TSCR 110 NETB Aux Bldg/FHB Exhaust Flow 12/13/84 TBD TBD TBD
- (FY-86) 47484 Three Nile Island 1 - Steam Generator Tube Leaks DL 7/5/84 Complete
- Not scheduled before 7/1/85.
TAC No.
Title Review RAI Branch Date RAI
Response
Date SE Input Date Licensing Action Date Completion Status 46948 49619 52003 53385 53511 52007 Three Nile Island 1 - TSCR 104 Surveillance Capsules Three Mile Island 1 - TSCR 114 Post Accident Monitoring Instrumentation Three Nile Island 1.- Fire Protection Schedular Extension (9/30/83)
Three Nile Island 1 - TSCR 97 Rev.
1 Fire Protection Changes Three Mile Island 1 -
UCS 2.206 Petition Three Nile Island 1 - Backup Incore Thermocouple Review (Certification Item)
DL DL DL CMEB DL DL 11/7/84 10/1/84 9/15/84 10/5/84 9/30/84 8/23/84 Complete Complete Complete Complete Complete Complete 52589 53386 53399 47050 Three Nile Island 1 - TSCR 126 Surveillance Standards Three Mile Island 1 - Fire Area vs.
Zone Exemption Request Three Mile Island 1 - TSCR 116 Rev.
1, Containment Purging R:!
DL CSB Three Nile Island 1 - IST Review MEB 5/15/84(c) 8/8/84 5/30/85 6/12/84(c) 2/30/85 9/30/84(c) 10/23/84 Complete Complete
TAC No.
Title Revi ew RAI Branch Date RAI
Response
Date SE'nput Date Licensing Action Date Completion Status 55318 55107 Three Mile Island 1 - gualifi-cation nf NOE Personnel MTEB Three Nile Island 1 - Response MEB'o Aamodt Motion on Health Effect 12/31/84 7/11/84 1/31/85 Complete 55311 55310 Three Nile Island 1 - Iodine Sampling Program for Main Condenser off Gas Three Mile Island 1 - TSCR 115 Admin. Changes, CRD Breaker Shunt Trip Addition, Pass Program NETB DL 11/21/84(c) 12/15/84 8/31/84(c) 12/21/84
0