ML20132B200
| ML20132B200 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1996 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML20132B186 | List: |
| References | |
| REF-GTECI-MI, REF-GTECI-SC NUDOCS 9612170099 | |
| Download: ML20132B200 (138) | |
Text
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ATTACHMENI i
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' GENERIC ISSUE MANAGEMENT CONTROL SYSTEM FOURTH QUARTER FY-96 UPDATE i
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OFFICE OF NUCLEAR REGULATORY RESEARCH i
NOVEMBER 1996 i
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9612170099 961209 3
O ii TABLE OF CONTENTS (a)
Generic Issue Management Control System (1)
Description (2)
Legend (3)
Data Elements (b)
Table 1 -
Generic Safety Issues Scheduled for Resolution, i
Issues Resolved, and Issues Integrated j
(c)
Table 1A - Summary of Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated j
(d)
Table 2 -
Number of Generic Safety Issues Resolved by Fiscal Year (Through 4th Quarter FY-96)
(e)
Table 3 -
Generic Safety Issues Resolved by Fiscal Year (f)
Table 4 -
Generic Safety Issues Scheduled for Resolution (by Fiscal Year)
(g)
Table 4A - Generic Safety Issues Scheduled for Resolution (by Priority)
(h)
Table 5 -
Number of Generic Issues Prioritized from FY-83 Through the 4th Quarter of FY-96 (i)
Table 6 -
Generic Issues Prioritized as of 4th Quarter FY-96 (j)
Table 7 -
Generic Issues to be Prioritized (k)
Table 8 -
Generic Issues to be Reprioritized (1)
Table 9 -
Regulatory Impact Issues Scheduled for Resolution (m)
Table 10 - Licensing Issues Scheduled for Resolution (n)
Table 11 - Environmental Issues Scheduled for Resolution (o)
Table 12 - Resolved Generic Issues With Ongoing Activity (p)
Table 13 - Related Generic Activities (q)
Work Scope & Schedules for Generic Issues and Related Generic Activities
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GENERIC ISSUE MANAGEMENT CONTROL SYSTElj DESCRIPTION The Generic Issue Management Control System (GIMCS) provides appropriate information necessary to manage the resolution of safety-related as well as non-safety-related generic issues. For the purpose of this management control j
system, resolved is defined as the point where the staff's final resolution product is issued and a memorandum summarizing the resolution is issued to the 4
EDO. For safety-related issues, this generally occurs when the resolution has been incorporated into one or more of the following documents:
(a)
Commission Order (e)
Regulatory Guide (b)
NRC Policy Statement (f)
Generic Letter (c)
Rule (g)
Bulletin (d)
Standard Review Plan (SRP)
(h)
Information Notice GIMCS is part of an integrated system of reports and procedures that is designed to manage generic safety issues through the stages of prioritization and resolution (development of new criteria, management review and approval, public comments, and incorporation into the regulations, as appropriate). The priority evaluation for each issue listed in this report is contained in NUREG-0933, "A Prioritization of Generic Safety Issues." The Procedures for Identification, Prioritization, Resolution, and Tracking of Generic Issues is outlined in RES Office Letter No. 7, dated February 16 1996, which superseded
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RES Office Letter No. 1, Revision 4, dated June 2, 1994.
(Prior to the NRC l
reorganization of April 12, 1987, NRR Office Letter No. 40 was used for identifying new issues.)
GIMCS provides the proposed schedules for managing and controlling the resolution of: (1) issues that are ranked HIGH-priority; (2) issues that are ranked MEDIUM-priority; (3) issues for which possible resolutions have been identified for evaluation; (4) issues for which technical resolutions are available (as documented by memorandum, analysis, NUREG, etc.); and (5) other issues designated to receive resources for resolution.
Issues ranked as either LOW or DROP are not allocated resources for resolution and, therefore, are not tracked in GIMCS.
Some prioritized generic issues may not have resources allocated for resolution; these issues are listed in GIMCS as inactive issues. Generally, these will be MEDIUM-priority issues that have no safety deficiency demanding high-priority attention, but have the potential for safety improvements or reduction in uncertainty of analysis that may be substantial and worthwhile.
Efforts for the resolution of these issues will be planned over the next several years, but on a basis that will not interfere with work on the resolution of HIGH-priority generic issues or other high-priority work. Thus, some (MEDIUM-priority) generic issues may be inactive until such time as resources become available to resolve them. The detailed schedule for resolving generic issues is monitored by GIMCS.
I iv LEGEND AEBR -
Accident Evaluation Branch ANPRM -
Advance Notice of Proposed Rulemaking BNL Brookhaven National Laboratory BTP Branch Technical Position DE Division of Engineering DER Division of Engineering Technology DISP -
Division of Inspection and Support Programs DRCH -
Division i,f Reactor Controls and Human Factors DRPE -
Division of Reactor Projects I/II DRPM -
Division of Reactor Program Management DRPW -
Division of Reactor Projects III/IV DSR Division of Systems Technology DSSA -
Division of Systems Safety and Analysis DTR Draft Technical Resolution EMCB -
Materials and Chemical Engineering Branch EMEB -
Mechanical Engineering Branch EMMB -
Electrical, Materials, and Mechanical Engineering Branch EPRI -
Electric Power Research Institute Financial Identification Number FIN Federal Register Notice FRN FTR Final Technical Resolution GL Generic letter GSI Generic Safety Issue GSIB -
Generic Safety Issues Branch H
HIGH-priority GSI HFBR -
Control, Instrumentation, and Human Factors Branch HQMB -
Quality Assurance and Maintenance Branch IEB Inspection & Enforcement Bulletin IN Information Notice INEL -
Idaho Nuclear Engineering Laboratory LI Licensing Issue M
MEDIUM-priority GSI NR NEARLY-RESOLVED GSI ORNL -
Oak Ridge National Laboratory PD23 -
Project Directorate II-3 Project Directorate III-1 PD3I PDND -
Non-Power Reactor and Decommissioning Project Directorate PERB -
Emergency Preparedness and Radiation Protection Branch PIPB -
Inspection Program Branch PNL Pacific Northwest Laboratories PRA Probabilistic Risk Assessment PRAB -
Probabilistic Risk Analysis Branch RAI Request for Additional Information RG Regulatory Guide RGA Related Generic Activity RI Regulatory Impact RPSB -
Reactor and Plant Systems Branch 5
Subsumed in Another Issue (No.)
SCSB -
Containment Systems and Severe Accident Branch SFP0 -
Spent Fuel Project Office O
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LEGEND (Cont.)
S0W-Statement of Work SPLB -
Plant Systems Branch SRP Standard Review Plan SRXB -
Reactor Systems Branch STS Standard Technical Specification l
T/A Technical Assistance j
TAP Task Action Plan TBD To be Determined l
TI Temporary Instruction TS Technical Specification USI Unresolved Safety Issue i
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vi DATA ELEMENTS Management and control indicators used in GIMCS are defined as follows:
1.
Issue No.
- Generic Issue Number 2.
litle
- Generic Issue Title 3.
Identification Date
- Date the issue was identified 4.
Prioritization Date
- The date that the prioritization evaluation was approved by the RES Director 5.
Typs
- Generic Safety (GSI), Licensing (LI), or Regulatory impact (RI) 6.
Priority
- High (H) or Medi'm (M) 7.
Task Manaaer
- Name of assigned individual responsible for resolution 8.
Office / Division / Branch - The Office, Division, and Branch of the Task Manager who has lead responsibility for resolving the issue.
9.
A_ction level
- Active Technical assistance funds appropriated for resolution and/or Task Manager actively pursuing resolution Inactive -
tio technical assistance funds appropriated for resolution, Task Manager assigned to more important work, or no Task Manager assigned Resolved -
All necessary work has been completed and no additional resources will expended 10.
Status
- Coded summary as follows:
NR - (Nearly-Resolved);
3A - (Resolved with requirements);
3B - (Resolved with [Lo requirements);
5 - (Licensing or Regulatory impact issue that has been assigned resources for completion) 11.
TAC Number
- Task Action Control (TAC) number assigned to the issue O
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Resolution Date
- Scheduled resolution date for the issue 13.
Work Authorization
- Who or what authorized work to be done on the issue i
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14.
flh
- Financial identification number assigned to contract (if any) for technical assistance 15.
Contractor
- Contractor name 16.
Contract Title
- Contract Title (if contract issue) 17.
Work Scope
- describes briefly the work necessary to i
technically resolve and complete the generic i
issue 18.
Status
- Describes current status of work 19.
Affected Documents
- Identifies documents into which the technical resolution will be incorporated 20.
Problem / Resolution
- Identifies problem areas and describes what actions are necessary to resolve.them 21.
Milestones
- Selected significant milestones:
(a) the " original" scheduled dates reflect the original Task Action Plan plus i
additional milestone dates added during l
task resolution; (b) changes in the original scheduled dates are listed under " Current";
(c) actual completion dates are listed under " Actual" i
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O TABLE 1 3
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-96(4TH OUARTER)
FY-83 FY-84 FY-85 l
ISSUE GIs New GIs Gls New GIs Gis New GIs TYPE Start +
Issues - Resolved - End Start +
Issues - Resolved - End Start +
Issues - Resolved - End USI 16 0
2 14 14 0
2 12 12 0
0 12 HIGH 24 2
0 26 26 1
1 26 22*
41.
6 57 MEDIUM 31 2
0 33 33 4
3 34 28*
1 10 19 NR 20 3
4 19 19 5
9 15 15 11 7
19 TOTAL:
91 7
6 92 92 10 15 87 77 53 23 107
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FY-86 FY-87 ISSUE Gis New GIs ISSUE Gls New GIs GIs i
TYPE Start +
Issues - Resolved = End TYPE Start + Issues
- Resolved - Integrated End i
l USI 12 0
1 11 USI 11 0
2 0
9 HIGH 57 (16)*
3 38 HIGH 38 4
3 7
32 MEDIUM 19 7
2 24 MEDIUM 24 1
4 5
16 NR 19 (3)*
3 13 NR 13 0
1 1
11 TOTAL:
107 (12)*
9 86
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TOTAL:
86 5
10 13 68
- Extensive revisions to Human Factors issues resulted in priority changes.
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TI-l As of 4th Quarter FY-96
TABLE I (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-96(4TH 00ARTER)
FY-88 FY-89 ISSUE GIs New GIs GIs ISSUE GIs New GIs GIs TYPE Start + Issues - Resolved - Integrated - End TYPE Start + Issues - Resolved - Integrated - End USI 9
0 5
0 4
USI 4
0 4
0 0
HIGH 32 1
6 3
24 HIGH 24 1
9 0
16 MEDIUM 16 2
2 3
13 MEDIUM 13 1
3 1
10 NR 11 1
3 0
9 NR 9
0 2
0 7
TOTAL:
68 4
16 6
50 TOTAL:
50 2
18 1
33
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FY-90 FY-91 ISSUE GIs New GIs GIs ISSUE GIs New GIs GIs TYPE Start + Issues - Resolved - Integrated - End TYPE Start + Issues - Resolved - Integrated = End HIGH 16 0
2 0
14 HIGH 14 2
2 0
14 MEDIUM 10 1
2 0
9 MEDIUM 9
3 1
0 11 NR 7
0 3
0 4
NR 4
1 1
0 4
TOTAL:
33 1
7 0
27 TOTAL:
27 6
4 0
29 FY-92 FY-93 ISSUE Gls New GIs GIs ISSUE Gis New GIs GIs Issues - Resolved - Integrated = End Issues - Resolved - Integrated - End TYPE Start +
TYPE Start +
HIGH 14 0
4 0
10 HIGH 10 0
7 0
3 MEDIUM 11 1
2 0
10 MEDIUM 10 0
3 0
7 NR 4
2 1
0 5
NR 5
2 0
0 7
TOTAL:
29 3
7 0
25 TOTAL:
25 2
10 0
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TABLE I (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-96(4TH OUARTER)
FY-94 FY-95 ISSUE GIs New GIs GIs ISSUE CIs New GIs GIs TYPE Start + Issues - Resolved - Integrated - End TYPE Start + Issues - Resolved - Integrated - End HIGH 3
1 1
0 3
HIGH 3
1 0
0 4
MEDIUM 7
1 2
0 6
MEDIUM 6
0 0
0 6
NR 7
0 2
0 5
NR 5
1 1
0 5
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17 2
5 0
14 TOTAL:
14 2
1 0
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i FY-96 FY-97 ISSUE GIs New GIs GIs ISSUE GIs New GIs GIs TYPE Start + Issues - Resolved - Integrated - End TYPE Start + Issues - Resolved - Integrated = End HIGH 4
0 1
0 3
HIGH MEDIUM 6
0 1
0 5
MEDIUM l
NR S
5 1
0 9
NR TOTAL:
15 5
3 0
17 TOTAL:
P s
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Table 1A
SUMMARY
OF GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED. AND ISSUES INTEGRATED CUMULATIVE TOTALS FY-83 THROUGH FY-96(4TH OUARTER)
ISSUE GIs New GIs Gls TYPE Start + Issues - Sub-Total - Resolved -
Integrated" - Remainder USI 16 0
16 16 0
0 HIGH 24 34*
58 45 10 3
MEDIUM 31 18 49 35 9
5 NR 20 28*
48 38 1
9 TOTAL:
91 80 171 134 20 17
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- Extensive revisions to Human Factors issues resulted in priority changes in FY-85 and FY-86.
" GIs Intearated FY-87:
Issues 48, 49, and A-30 into Issue 128 Total (13)
Issue 65 into Issue 23 Issues 68; 122.1.a; 122.1.b; 122 1.c; and 125.II.1.b into Issue 124 Issues I.B.I.l(6) and I.B.I.l(7) into Issue 75 Issue B-6 into Issue 119.1 Issue 67.7 into 135 FY-88:
Issue 77 into A-17 Total (6)
Issues I.D.5(5), II.B.5(1), II.B.5(2), II.B.5(3), and II.F.5 were integrated into the Research Activities Program and were reclassified as Licensing Issues.
FY-89:
Total (1)
Issue 131 was integrated into the External Events IPE Program.
TI-4 As of 4t ter FY-96
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TABLE 2 NUMBER OF GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR FY-83 THROUGH FY-96 (4TH 00ARTER)
PRIORITY FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-89 FY-90 FY-91 FY-92 FY-93 FY-94 TOTAL USI 2
2 0
1 2
5 4
0 0
0 0
0 16 HIGH 0
1 6
3 3
6 9
2 2
4 7
1 44 MEDIUM 0
3 10 2
4 2
3 2
1 2
3 2
34 NR 4
9 7
3 1
3 2
3 1
1 0
2 36
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Total:
6 15 23 9
10 16 18 7
4 7
10 5
130 TOTAL FROM PRIORITY AB0VE FY-95 FY-96 TOTAL i
USI 16 0
0 16 i
HIGH 44 0
1 45 MEDIUM 34 0
1 35 NR 36 1
1 38 Total:
130 1
3 134 i
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i T2-1 As of 4th Quarter FY-96
TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-83 A-Il Reactor Vessel Materials USI GL 82-26 01/79 10/82 Toughness A-16 Steam Effects on BWR Core Spray NR MPA D-12 NRR-0P FY83 03/29/83 Distribution I
A-39 Determination of Safety USI SRP Revision 01/79 10/82 Relief Valve (SRV) Pool' Dynamic loads and Temperature Limits for BWR Containment B-53 Load Break Switch NR SRP Revision NRR-0P FY83 07/28/83 II.E.5.1 (B&W) Design Evaluation NR No. Req.
NRR-0P FY83 03/21/83 IV.C.1 Extend Lessons Learned From NR No. Req.
NRR-0P FY83 04/15/83 i
TMI to Other NRC Programs FY-84 12 BWR Jet Pump Integrity Medium No. Req.
NRR-0P FY83 09/25/84 e
20 Effects of Electromagnetic NR NUREG/
NRR-0P FY83 11/15/83 Pulse on Nuclear Plant Systems CR-3069 40 Safety Cancerns Associated NR MPA B-65 07/18/83 12/27/83 With Braaks in the BWR Scram System 45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather T3-1 As of 4th Quarter FY-96
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-84 (Cont.)
50 Reactor Vessel Level NR MPA F-26 07/28/83 09/06/84 Instrumentation in BWRs 69 Make-Up Nozzle Cracking in NR MPA B-43 12/06/83 09/27/84 B&W Plants
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A-1 Water Hammer USI SRP Revision 01/79 03/15/84 A-12 Steam Generator and Reactor USI SRP Revision 01/79 10/83 Coolant Pump Supports B-10 Behavior of BWR Mark III High SRP Revision NRR-0P FY83 09/10/84 Containments B-26 Structural Integrity of Medium No Req.
NRR-0P FY83 09/27/84 Containment Penetrations B-60 Loose Parts Monitoring NR GL NRR-0P FY83 09/25/84 Systems (LPMS)
I.A.I.4 Long-Term Upgrading of NR New Rule NRR-0P FY83 01/01/84 Operating Personnel II.A.1 Siting Policy Reformulation Medium No Req.
NRR-0P FY83 09/20/84 II.E.5.2 (B&W) Reactor Transient NR NUREG-0667 NRR-OP FY83 09/28/84 Response Task Force III.D.2.5 Offsite Dose Calculation Manual NR NUREG/
NRR-OP FY83 01/17/84 C,R-3332 T3 As of 4th er FY-96
E TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 i
22 inadvertent Baron Dilution NR GL 85-05 11/05/82 10/15/84 Events l
A-41 Long Term Seismic Progra:n Medium No Req.
NRR-0P FY83 10/10/84 B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/
NRR-OP FY83 10/22/84
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CR-4001 B-58 Passive Mechanical Failures Medium No Req.
NRR-OP FY83 07/09/85 t
C-Il Assessment of Failure and Medium No Req.
NRR-0P FY83 07/09/85 i
Reliability of Pumps and Valves I.A.2.2 Training and Qualifications High Policy NRR-0P FY83 05/24/85
'i of Operating Personnel Statement (No Req.)
l 1.A.2.6(4)
Operator Workshops Medium No Req.
NRR-OP FY83 09/25/85 I.A.2.7 Accreditation of Training Medium Policy NRR-0P FY83 06/24'/85 Institutions Statement (No Req.)
l I.A.3.4 Licensing of Additional Medium Policy NRR-0P FY83 02/12/85 i
Operations Personnel Statement l
(No Req.)
t I.G.2 Scope of Test Program Medium No Req.
NRR-OP FY83 10/05/84 i
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TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 (Cont.)
II.B.6 Risk Reduction For Operating High No Req.
NRR-0P FY83 09/25/85 Reactors at Sites blith High Population Densities II.B.8 Rulemaking Proceedings on High Degraded Core Accidents (a) Hydrogen Rule Rule /
NRR-0P FY83 07/19/85 (b) Severe Accidents Policy NRR-0P FY83 08/12/85
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Statement II.C.1 Interim Reliability Evaluation High No Req.
NRR-OP FY83 07/09/85 Program II.C.2 Continuation of Interim High No Req.
NRR-OP FY83 09/25/85 Reliability Evaluation Program II.E.2.2 Research on Small-Break LOCAs Medium No Req.
NRR-OP FY83 07/25/85 and Anomalous Transients III.A.I.3(2)
Maintain Supplies of Thyroid-NR Policy NRR-0P FY83 08/15/85 Blocking Agent for Public Statement III.A.3.4 Nuclear Data Link Medium No Req.
NRR-0P FY83 06/26/85 III.D.2.3(1)
Develop Procedures to Dis-NR ESRP NRR-0P FY83 08/28/85 criminate Between Sites / Plants Revision III.D.2.3(2)
Discriminate Between Sites NR ESRP NRR-0P FY83 08/28/85 and Plants that Require Revision Consideration of Liquid Pathway Interdiction Techniques Ill.D.2.3(3)
Establish Feasible Method of NR ESRP NRR-0P FY83 08/28/85 Pathway Interdiction Revision T
As of 4t ter FY-96
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TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date tumber Title Priority Product for Resolution Resolved j
FY-85 (Cont.)
III.D.2.3(4)
Prepare a Summary Assessment NR ESRP NRR-0P FY83 08/28/85 Revision IV.E.5 Assess Currently Operating High No Req.
NRR-0P FY83 09/25/85 Plants FY-86 3
Setpoint Drift in NR Reg Guide NRR-0P FY83 05/19/86
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Instrumentation Rev.
(No Req.)
14 PWR Pipe Cracks NR No Req.
NRR-0P FY83 10/04/85 36 Loss of Service Water NR SRP Revision 02/15/84 05/13/86 (No Req.)
61 SRV Discharge Line Break Medium No Req.
11/30/83 08/08/86 Inside the Wetwell Airspace of BWR Mark I and Mark II Containments A-43 Containment Emergency USI SRP Revision 01/79 10/85' Sump Performance (Req.)
I.C.9 Long-Term Plan for Upgrading Medium No Req.
NRR-0P FY83 06/07/85 of Procedures III.D.3.1 Radiation Protection Plans High No Req.
NRR-0P FY83 05/19/86 HFl.2 Engineering Expertise on High No Req.
10/01/84 10/28/85 Shift HF1.3 Guidance on Limits and High No Req.
10/01/84 06/26/86 Conditions of Shift Work T3-5 As of 4th Quarter FY-96
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-87 91 Main Crankshaft Failures in NR NUREG-1216 07/85 09/87 Transamerica Delaval Diesel (No Req.)
Generators A-46 Seismic Qualification of USI GL 87-02 02/81 02/87 Equipment in Operating Plants (Req.)
A-49 Pressurized Thermal Shock USI Rule / Reg.
12/81 02/87 g
Guide 1.154 (Req.)
I.A.2.6(1) long-Term Upgrading of High Reg. Guide 10/82 05/87 Training and Qualifications -
1.8 (Req.)
Revise Reg. Guide 1.8 I.A.3.3 Requirement for Operator High No Req.
12/82 01/87 Fitness I.A.4.2(1)
Research on Training High Reg. Guide 10/84 05/87 Simulators 1.149, Rev. 1 (Req.)
I.B.l.1 Oraanization and Manaaement Lona-Term Imorovements I.B.I.l(l)
Prepare Draft Criteria Medium No Req.
12/82 01/87 I.B.I.l(2)
Prepare Commission Paper Medium No Req.
12/82 01/87 I.B.I.l(3)
Issue Requirements for the Medium No Req.
12/82 01/87 Upgrading of Management and Technical Resources I.B.I.l(4)
Review Responses to Determine Medium No Req.
12/82 01/87 Acceptability T3-As of 4th
'er FY-96
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TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-88 86 Long Range Plan for Dealing NR NUREG-0313, 10/84 01/88 with Stress Corrosion Cracking Rev. 2, in BWR Piping GL 88-01 (Req.)
93 Steam Binding of Auxiliary High GL 88-03 10/84 02/88 Feedwater Pumps (No Req.)
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I.D.4 Control Room Design Standard Medium No Req.
NRR-OP FY83 03/88 II.E.4.3 (Containment) Integrity Check High NUREG-1273 NRR-OP FY83 03/88 (No. Req.)
B-5 Ductility of Two-Way Medium No Req.
NRR-0P FY83 04/88 Slabs and Shells and Buckling Behavior of Steel Containments HF8 Maintenance and Surveillance High Policy 03/85 05/88 Program Statement (No Req.)
L I.A.4.2(4)
Review Simulators for High Rule NRR-OP FY83 05/88 i
Conformance (Req.)
A-44 Station B1ackout USI Rule / Reg.
01/79 06/88 Guide 1.155 (Req.)
43 Reliability of Air Systems High GL 88-14 12/87 09/88 (Req.)
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t T3-7 As of 4th Quarter FY-96
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-88 (Cont.)
66 Steam Generator Requirements NR NUREG-0844 11/83 09/88 (No Req.)
102 Human Error in Events Involving NR NUREG-1192 02/85 09/88 Wrong Unit or Wrong Train (No Req.)
125.11.7 Reevaluate Provision to High NUREG-1332 09/86 09/88 Automatically Isolate Feedwater (No Req.)
g from Steam Generator During a Line Break A-3,4,5 Steam Generator Tube Integrity USI NUREG-0844 01/79 09/88 (No Req.)
A-45 Shutdown Decay Heat Removal USI NUREG-1289 02/81 09/88 Requirements (No Req.)
1.1.- 8,9 51 Proposed Requirements for Medium GL 89-13 06/83 08/89 Improving Reliability of Open (Req.)
Cycle Service Water Systems 82 Beyond Design Bases Accidents Medium NUREG-1353 12/07/83 04/89 in Spent Fuel Pools (No Req.)
99 RCS/RHR Suction Line Interlocks High GL 88-17 08/85 11/88 on PWRs (Req.)
101 BWR Water Level Redundancy High GL 89-11 05/06/85 06/89 (Req.)
9 T3 As of 4th ter FY-96
~.,.
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-89 (Cont.)
115 Enhancement of the Reliability High NUREG-1341 07/07/86 04/89 of Westinghouse Solid State (No Req.)
Protection System 122.2 Initiating Feed-and-Bleed High No Req.
01/86 04/89 124 Auxiliary Feedwater System NR 2 Plant-02/86 01/89 Reliability Specific
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Backfits (Req.)
i 125.I.3 SPDS Availability NR GL 89-06 05/06/88 04/89 (No. Req.)
134 Rule on Degree and Experience High Policy 01/86 08/89 t
Requirements for Senior Statement Operators (No Req.)
A-17 Systems Interaction USI NUREG-ll74 01/79 08/89 i
(No Req.)
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A-40 Seismic Design Criteria USI SRP Revisions 01/79 09/89 I
(Req.)
A-47 Safety Implications of Control USI GL 89-19 02/81 08/89 Systems (Req.)
A-48 Hydrogen Control Measures and USI Rules (Req.)
02/81 04/89 Effects of Hydrogen Burns on i
Safety Equipment HFl.1 Shift Staffing High Reg. Guide 10/01/84 05/89 1.114, Rev. 2 (Req.)
T3-9 As of 4th Quarter FY-96 l
~ '
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-89 (Cont.)
HF4.1 Inspection Procedure for High IN 86-64 10/01/84 10/88 Upgraded Emergency Operating (No Req.)
Procedures 1.F.1 Expand QA List High No Req.
NRR-0P FY83 01/89 II.C.4 Reliability Engineering High No Req.
NRR-OP FY83 10/88 g
II.E.6.1 Test Adequacy Study Medium GL 89-10 NRR-OP FY83 06/89 (Req.)
LL22 70 PORV and Block Valve Medium GL 90-06 05/14/84 06/90 Reliability 75 Generic Implications of NR Req.
10/19/83 05/90 ATWS Events at the Salem Nuclear Power Plant 84 CE PORVs NR SECY-90-232 02/27/85 06/90 (No Req.)
94 Additional Low-Temperature High GL 90-06 07/23/85 06/90 Overpressure Protection for (Req.)
LWRs 103 Design for Probable NR GL 89-22 09/04/85 11/89 Naximum Pracipitation (Req.)
T3 As of 4t
-ter FY-96
TABLE 3 (Continued) i GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR I
Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-90 (Cont.)
A-29 Nuclear Power Plant Medium No Req.
NRR-OP FY83 10/89 r
Design for the Reduction j
of Vulnerability to l
Industrial Sabotage l
C-8 Main Steam Line High No Req.
NRR-0P FY83 03/90 Isolation Valve Leakage Control Systems FY-91 128 Electrical Power High GL 91-06, 11/28/86 09/91 Reliability GL 91-11
{
(Req.)
130 Essential Service Water High GL 91-13 03/10/87 09/91 i
System Failures at (Req.)
Multiplant Sites l
135 Steam Generator Medium No Req.
05/27/86 03/91 and Steam Line Overfill l
II.J.4.1 Revise Deficiency NR Rule NRR-0P FY83 07/91' I
Report Requirements (Req.)
j FY-92 29 Bolting Degradation or High No Req.
NRR-0P FY-83 10/91 Failure in Nuclear Power-Plants t
T3-Il As of 4th Quarter FY-96 1
l l
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-92 (Cont.)
73 Detached Thermal Sleeves NR NUREG/
08/20/91 09/92 i
CR-6010 (No Req.)
79 Unanalyzed Reactor Medium GL 92-02 NRR-OP FY-84 05/92 Vessel Thermal Stress (No Req.)
During Natural Convection Cooldown I
87 Failure of HPCI Steam High No Req.
09/26/85 12/91 Line Without Isolation 113 Dynamic Qualification High No Req.
07/02/87 08/92 Testing of Large Bore Hydraulic Snubbers 121 Hydrogen Control for High No Req.
09/26/85 03/92 Large, Dry PWR Containments 151 Reliability of ATWS Medium No Req.
08/27/91 09/92 Recirculation Pump Trip in BWRs FY-93 105 Interfacing Systems LOCA High No Req.
06/11/85 06/93 at LWRs 120 On-Line Testability Medium No Req.
11/23/90 03/93 of Protection Systems 142 Leakage Through Electrical Medium No Req.
06/20/90 03/93 Isolators T3-As of 4th
- er FY-96
O l
O TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR i
Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved l
l FY-93 Cont.)
i 143 Availability of Chilled Water High No Req.
03/29/91 09/93
[
Systems and Room Cooling 153 Loss of Essential Service High No Req.
03/29/91 06/93 Water in LWRs B-56 Diesel Reliability High Reg Guides:
NRR-OP FY83 06/93 g
1.9, Rev. 3; 1.160 (Req.)
i HF4.4 Guidelines for Upgrading Other High No Req.
10/01/84 07/93 i
Procedures HF5.1 Local Control Stations High No Req.
10/01/84 06/93 HF5.2 Review Criteria for Human High No Req.
10/01/84 06/93 Factors Aspects of Advanced
[
Controls and Instrumentation
~
i I.D.3 Safety System Status Monitoring Medium No Req.
NRR-0P FY83 09/93 l
i FY-94 57 Effects of Fire Protection Medium No Req.
06/08/88 02/94 l
System Actuation on Safety-(NUREG-Related Equipment 1472) 106 Piping and Use of Highly Medium No Req.
11/03/87 11/93 Combustible Gases in Vital Areas I.D.5(3)
On-Line Reactor Surveillance NR No Req.
NRR-OP FY83 11/93 Systems j
T3-13 As of 4th Quarter FY-96
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-94 (Cont.)
II.H.2 Obtain Technical Data on the High No Req.
NRR-OP FY83 02/94 Conditions Inside the THI-2 Containment Structure B-64 Decommissioning of Nuclear Nearly-Rule NRR-OP FY84 09/94 Reactors Resolved (Req.)
FY-95
\\
155.1 More Realistic Source Term Nearly-Req.
02/26/92 03/95 Assumptions Resolved (NUREG
-1465)
FY-96 15 Radiation Effects on Reactor High No Req.
02/--/89 05/96 Vessel Supports (NUREG
-1509) 24 Automatic Emergency Core Medium No Req.
07/--/91 10/95 Cooling System Switch to Recirculation 83 Control Room Habitability NR No Req.
08/--/83 06/96 (NUREG/CR
-5669)
T3 -14 As of 4t
-ter fY-96
.. ~... -.
[
t i
i TABLE 4 17 GSis SCHEDULED FOR RESOLUTION (BY FISCAL YEAR) i t
3..
f i
4 PRIORITY FY-97 FY-98 FY-99 FY-00 FY-01 FY-02 TBD TOTAL j
i HIGH 23 165 3
.i 171 l
t I
l
~
MEDIUM 78 5
158 j
B-17 i
\\
B-55
{
B-61 i
i t
NR 145 190 172 168 9
i 166 173.A 170 l
173.B t
191 l
I L
TOTAL:
9 2
2 0
0 0
4 17 i
t f
[
1
)
l i
i i
l 1
T4-1 As of 4th Quarter FY-96
[
m e
f
-- i
TABLE 4A GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current Issue Lead Office /
Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-95 Date 23 Reactor Coolant Pump Seal RES/ DER /GSIB H
NRR-OP FY83 06/96 01/97 Failures 165 Spring-Actuated Safety and RES/ DER /GSIB H
11/26/93 06/98 06/98 Relief Valve Reliability 171 ESF Failure from LOOP RES/ DER /GSIB H
06/16/95 TBD 06/97 Subsequent to A LOCA
\\
78 Monitoring of Fatigue Transient RES/ DER /GSIB M
07/10/92 03/96 11/96 Limits for Reactor Coolant System 158 Performance of Safety-Related RES/ DER /GSIB M
01/26/94 04/96 08/97 Power-0perated Valves Under Design Basis Conditions B-17 Criteria for Safety-Related RES/DSR/HFBR M
03/22/82 12/95 06/97 Operator Actions B-55 Improve Reliability of Target NRR/DE/EMEB M
NRR-0P FY83 08/97 08/97 Rock Safety Relief Valves B-61 Allowable ECCS Equipment Outage RES/DSR/PRAB M
NRR-0P FY83 11/95 01/97 Periods 145 Actions to Reduce Common RES/DSR/PRAB NR 02/11/92 03/96 02/97 Cause failures 166 Adequacy of Fatigue Life RES/ DER /GSIB NR 04/01/93 TBD 11/96 of Metal Components 168 Environmental Qualification NRR/DSSA/SPLB NR 04/01/93 TBD TBD of Electrical Equipment T4-2 As of 4t
-ter FY-96
O O
d U
Table 4A (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current Issue Lead Office /
Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-95 Date 170 Reactivity Transients and RES/DSR/RPSB.
NR 11/09/94 TBD TBD Fuel Damage Criteria for High Burn-Up Fuel 172 Multiple System Responses RES/DSR/PRAB NR 12/07/95 NA 12/98 Program 173.A Spent fuel Storage Pool:
NRR/DSSA/SPLB NR 06/24/96 NA 10/98
\\
Operating Facilities 173.B Spent fuel Storage Pool:
NRR/DSSA/SPLB NR 06/24/96 NA TBD Permanently Shutdown Facilities 190 Fatigue Evaluation of Metal RES/ DER /GSIB NR 08/26/96 NA 12/97 Components for 60-Year Plant Life 191 Assessment of Debris Accumulation RES/ DER /GSIB NR 09/--/96 NA TBD on PWR Sump Performance Total:
17 r
T4-3 As o'f 4th Quarter FY-96
^
,g
,e y p.\\
TABLE 5 NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 THROUGH THE 4TH OVARTER OF FY-96 ISSUE TYPE FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-89 FY-90 FY-91 FY-92 FY-93 FY-94 Total Issues Identified 56 19 54 45*
6 3
38 3
29 7
5 1
266 to be Prioritized Issues Identified 19 2
0 1
1 2
0 0
0 0
0 0
25 to be Reprioritized Total:
75 21 54 46 7
5 38 3
29 7
5 1
291 New Issues (Entered into GIMCS)
\\
High 2
1 41 6
4 1
1 0
2 0
0 1
59 Medium 2
4 1
1 1
2 0
1 3
2 0
1 18 Nearly-Resolved 3
5 6
1 0
1 0
0 1
2 2
0 21 Sub-total:
7 10 48 8
5 4
1 1
6 4
2 2
98 Resolved 4
0 1
0 0
1 1
1 0
2 1
0 11 Low 1
4 0
2 1
0 0
2 0
4 3
1 18 Drop 1
4 4
6 13 9
2 8
5 24 6
0 82 RI/Ll/El 0
0 4
6 0
2 33 1
1 3
0 0
50 Integrated 8
2 3
6 0
1 1
3 0
5 0
0 29 Total Issues 21 20 60 28 19 17 38 16 12 42 12 3
288 Prioritized:
[ Annual Progress]/ [+54
+1
-6
+18
-12
-12 0
-13
+17
-35
-7
-2]
3 Remaining Issues to be Prioritized or Reprioritized:
Extensive Revisions to Human Factors Issues Resulted in Priority Changes.
T5-1 As of 4th Quarter FY-96
TABLE 5 (Continued)
NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 THROUGH THE 4TH OVARTER OF FY-96 ISSUE TYPE Total (B/F) FY-95 FY-96 Total Issues Identified 266 2
21 289 to be Prioritized Issues Identified 25 0
3 28 to be Reprioritized Total:
291 2
24 317 New Issues (Entered into GIMCS)
High 59 1
0 60 g
Medium 18 0
0 18 Nearly-Resolved 21 1
5 27 Sub-total:
98 2
5 105 Resolved 11 0
5 16 Low 18 0
0 18 Drop 82 0
0 82 RI/LI/EI 50 0
7 57 Integrated 29 0
0 29 Total Issues Prioritized:
288 2
17 307
[ Annual Progress]/
Remaining Issues to be Prioritized or Reprioritized: [
3 0]
+7 10
O O
TABLE 6 GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-96 Action Item /
Identification Date Current issue No.
Title Date Prioritized Priority FY-83 i
31 Natural Circulation Cooldown 09/82 07/83 S(i.C.1) 32 Flow Blockage in Essential Equipment Caused 09/82 05/83 S(51) by Corbicula 33 Correcting Atmospheric Dump Valve Opening Upon 09/82 08/82 S(A-47)
Loss of Integrated Control System Power 39 Potential for Unacceptable Interaction Between 09/82 07/82 S(25) the CRD System and Non-Essential Control Air System
\\
40 Safety Concerns Associated with Pipe Breaks in 09/82 07/83 NR
[
the BWR Scram System 41 BWR Scram Discharge Volume Systems 09/82 07/83 RESOLVED l
42 Combination Primary / Secondary System LOCA 09/82 04/83 S(18) 45 Inoperability of Instrumentation Due to Extreme 09/82 09/83 NR l
Cold Weather 46 Loss of 125 Volt DC Bus 09/82 02/83 S(76) 47 Loss of Off-Site Power 09/82 04/83 RESOLVED 50 Reactor Vessel Level Instrumentation in BWRs 09/82 07/83 NR 51 Proposed Requirements for Improving the 09/82 06/83 MEDIUM Reliability of Open Cycle Service Water Systems 52 SSW Flow Blockage by Blue Mussels 09/82 05/83 S(51) 56 Abnormal Transient Operating Guidelines as 09/82 02/83 S(A-45/I.D.1)
[
Applied to a Steam Generator Overfill Event 58 Inadvertent Containment Flooding 09/82 08/83 Dit0?
64 Identification of Protection System Instrument 10/82 02/83 RESOLVED Sensing Lines 65 Probability of Core-Melt Due to Component 02/83 07/83 HIGH Cooling Water System Failures 77 Flooding of Safety Equipment Compartments by 06/83 09/83 HIGH Back-Flow Through Floor Drains 79 Unanalyzed Reactor Vessel Thermal Stress During 06/83 07/83 MEDIUM Natural Convection Cooldown D-l Advisability of a Seismic Scram 09/82 06/83 LOW i
IV.E.2 Plan for Early Resolution of Safety Issues 09/82 06/83 RESOLVED L
T6-1 As of 4th Quarter FY-96
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-96 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority f.hE.4 34 RCS Leak 09/82 02/84 DROP 35 Degradation of Internal Appurtenances in LWRs 09/82 02/84 LOW 36 Loss of Service Water 09/82 02/84 NR 43 Contamination of Instrument Air Lines 09/82 11/83 DROP 44 Failure of Saltwater Cooling System 09/82 10/83 S(43) 48 LCO for Class IE Vital Instrument Buses in 09/82 10/83 NR Operating Reactors 49 Interlocks and LCOs for Redundant Class IE 09/82 07/84 MEDIUM g
Tie Breakers 53 Consequences of a Postulated Flow Blockage 09/82 09/84 DROP Incident in a BWR 60 Lamellar Tearing of Reactor Systems Structural 10/82 11/83 S(A-12)
Supports 61 SRV Line Break Inside the BWR Wetwell Airspace 10/82 11/83 HEDIUM of Mark I and II Containments 66 Steam Generator Requirements 06/83 11/83 NR 68 Postulated loss of Auxiliary Feedwater System 06/83 04/84 HIGH Resulting from Turbine-Driven Auxiliary feedwater Pump Steam Supply Line Rupture 69 Make-up Nozzle Cracking in B&W Plants 06/83 12/83 NR 70 PORV and Block Valve Reliability 06/83 05/84 MEDIUM 75 Generic Implications of ATWS Events at the Salem 06/83 10/83 NR Nuclear Plant 80 Pipe Break Effects on Control Rod Drive Hydrau-06/83 01/84 LOW lic Lines in the Drywells of BWR Mark I and 11 Containments 82 Beyond Design Basis Accidents in Spent Fuel 08/83 12/83 MEDIUM Pools 90 Technical Specifications for Anticipatory Trips 02/84 08/84 LOW 92 Fuel Crumbling During LOCA 04/83 07/84 LOW B-65 lodine Spiking 09/82 06/84 DROP T6-2 As of 4t ter FY-96
p O
O O
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-96 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-85 37 Steam Generator Overfill and Combined Primary 09/82 05/85 S(A-47) and Secondary Blowdown 54 Valve Operator-Related Events Occurring 09/82 06/85 S(II.E.6.1)
During 1978, 1979, and 1980 55 Failure of Class IE Safety-Related Switchgear 09/82 03/85 DROP Circuit Breakers 59 Technical Specification Requirements for Plant 10/82 02/85 RI Shutdown 67 Steam Generator Staff Actions 06/83 03/85 MEDIUM
\\
81 Potential Safety Problems Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants 83 Control Room Habitability 11/83 06/84 NR 84 CE PORVs 11/83 02/85 NR 85 Reliability of Vacuum Breakers Connected 11/83 07/85 DROP to Steam Discharge Lines Inside BWR Containments 86 NRC Pipe Cracking Review Group Study 12/83 10/84 NR 87 Failure of HPCI Steam Line Without Isolation 01/84 09/85 HIGH 91 Transamerica Delaval Emergency Diesel Generator 03/84 07/85 NR Main Crankshaft Failure 93 Steam Binding of Auxiliary Feedwater Pumps 07/84 10/84 HIGH 94 Additional Low Temperature Overpressure 08/84 07/85 HIGH Protection for Light Water Reactors 98 CRD Accumulator Check Valve Leakage 09/84 02/85 DROP 99 RCS/RHR Suction Line Interlocks on PWRs 09/84 08/85 HIGH 101 BWR Water Level Redundancy 09/84 05/85 HIGH 102 Iluman Error in Events Involving Wrong Unit or 09/84 02/85 S(HF-02)
Wrong Train 103 Design for Probable Maximum Precipitation 10/84 09/85 NR 105 Interfacing Systems LOCA at LWRs 10/84 06/85 HIGH 108 BWR Suppression Pool Temperature Limits 12/84 02/85 RI(LOW) 119 Piping Review Committee Recommendations 07/85 09/85 RI(NR) 121 Hydrogen Control For large Dry PWR 08/85 09/85 HIGH Containments T6-3 As of 4th Quarter FY-96
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-85 (Cont.)
B-19 Thermal-Hydraulic Stability 02/83 01/85 NR B-50 Post Operating Basis Earthquake Inspection 02/83 04/85 RI(LOW)
B-59 N-1 Loop Operation in BWRs and PWRs 02/83 06/85 RESOLVED HF-01 Human Factor Program Plan (HFPP with 24 08/83 10/84 HIGH subtasks)
HF-02 Maintenance and Surveillance Program Plan 04/84 03/85 HIGH (MSPP with 10 subtasks)
\\
f.EE.5 21 Vibration Qualification of Equipment 03/83 06/86 DROP 30 Potential Generator Missiles - Generator Rotor 09/82 10/85 DROP Retaining Rings 74 Reactor Coolant Activity Limits for Operating 06/83 05/86 DROP Reactors 97 PWR Reactor Cavity Uncontrolled Exposures 09/84 10/85 S(III.D.3.1) 111 Stress Corrosion Cracking of Pressure Boundary 01/85 11/85 LI Ferritic Steels in Selected Environments 112 Westinghouse RPS Surveillance Frequencies and 01/85 10/85 RI(R)
Out-of-Service Times 114 Seismic-Induced Relay Chatter 03/85 06/86 S(A-46) 115 Reliability of Westinghouse Solid State 04/85 07/86 HIGH Protection System 122.1.a Common Mode Failure of Isolation Valves in 08/85 01/86 HIGH Closed Position 122.1.b Recovery of Auxiliary Feedwater 08/85 01/86 MEDIUM 122.1.c Interruption of Auxiliary Feedwater Flow 08/85 01/86 HIGH 122.2 Initiating Feed-and-Bleed 08/85 01/86 HIGH 122.3 Physical Security System Constraints 08/85 01/86 LOW 124 Auxiliary Feedwater System Reliability 12/85 02/86 NR T6-4 As of 4t ter FY-96
,--------.w sw...~.-+ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
O 1
i TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 f
Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-86 (Cont.)
125.I.2.a PORV Reliability - Test Program 11/85 06/86 S(70) 125.I.2.b PORV Reliability - Surveillance 11/85 06/86 S(70)
[
125.I.2.c Auto Block Valve Closure 11/85 06/86 DROP 125.I.2.d Equipment Qualification for Feed-and-Bleed 11/85 06/86 S(A-45) f Environment i
125.II.3 Review Steam / Feed Line Break Mitigation 11/85 08/86 DROP l
Systems for Single Failure l
125.II.4 OTSG Dryout and Reflood Effects 11/85 09/86 DROP t
125.II.7 Reevaluate Provisions to Automatically 11/85 09/86 HIGH
[
\\
Isolate Feedwater from Steam Generator i
During Line Break i
125.11.9 Enhance Feed-and-Bleed Capability 11/85 08/86 S(A-45) i 125.11.14 Remote Operation of Equipment Which Must 11/85 08/86 LOW i
Now be Operated Locally j
133 Update Policy Statement on Nuclear Plant 07/86 07/86 LI Staff Working Hours 134 Rule on Degree and Experience Requirement 07/86 07/86 HIGH i
C-4 Statistical Methods for ECCS Analysis 02/83 06/86 RI(R)
C-5 Decay Heat Update 02/83 06/86 RI(R)
I C-6 LOCA Heat Sources 02/83 06/86 RI(R) l t
FY-87 i
t 113 Dynamic Qualification Testing of Large Bore 03/85 07/87 HIGfi Hydraulic Snubbers f
125.I.1 Availability of the STA 11/85 07/87 DROP 125.I.4 Plant-Specific Simulator 11/85 02/87 DROP 125.I.7.b Realistic Hands-On Training 11/85 03/87 DROP 125.1.8 Procedures and Staffing for Reporting to 11/85 06/87 DROP l
NRC Emergency Response Center f
f i
T6-5 As of 4th Quarter FY-96 i
m
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-87 (Cont.)
125.II.I.a Two-Train AFW Reliability 11/85 10/86 DROP 125.II.l.b Review Existing AFW Systems for Single Failure 11/85 10/86 HIGH I25.II.1.c NUREG-0737 Reliability Improvements 11/85 10/86 DROP 125.II.l.d AFW Steam and Feedwater Rupture Control 11/85 10/86 DROP System /ICS Interactions in B&W Plants 125.11.2 Adequacy of Existing Maintenance Requirements 11/85 06/87 DROP for Safety-Related Systems 125.11.5 Thermal-Hydraulic Effects of Loss and 11/85 06/87 DROP Restoration of Feedwater on Primary System
\\
Components 125.11.6 Reexamine PRA Estimates of Core Damage Risk 11/85 03/87 DROP from Loss of All Feedwater 125.II.8 Reassess Criteria for Feed-and-Bleed Initiation 11/85 U3/87 DROP 125.11.10 Hierarchy of Impromptu Operator Actions 11/85 02/87 DROP 125.11.12 Adequacy of Training Regarding PORV Operation 11/85 03/87 DROP 127 Testing and Maintenance of Manual Valves in 05/86 06/87 LOW Safety-Related Systems 128 Electrical Pcwer Reliability 05/86 11/86 HIGH 130 Essential Service Water Pump Failures at 06/86 03/87 HIGH Multiplant Sites 135 Steam Generator and Steam Line Overfill 05/86 06/87 MEDIUM FY-88 43*
Reliability of Air Systems 04/87 12/87 HfGH 55*
Failure of Class IE Safety-Related Switchgear 09/85 02/88 DROP Circuit Breakers to Close on Demand 57 Effects of Fire Protection System Actuation 09/82 06/88 MEDIUM on Safety-Related Equipment Previous Priority Evaluation Published in NUREG-0933 T6-6 As of 4t ter FY-96
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 i
l Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-88 (Cont.)
62 Reactor Systems Bolting Applications 10/82 08/88 S(29) 88 Earthquakes and Emergency Planning 01/84 10/87 RESOLVED 104 Reduction of Boron Dilution Requirements 10/84 08/88 DROP 106 Piping and Use of Highly Combustible Gases 10/84 11/87 MEDIUM in Vital Areas 4
125.I.3 SPDS Availability 11/85 05/88 NR 125.I.6 Valve Torque Limit and Bypass Switch Settings 11/85 12/87 DROP 125.I.7A Recover Failed Equipment 11/85 12/87 DROP 125.11.11 Recovery of Main Feedwater as Alternative to AFW 11/85 06/88 DROP i
\\
125.11.13 Operator Job Aids 11/85 03/88 DROP l
126 Reliability of PWR Main Steam Safety Valves 03/86 03/88 LI i
136 Storage and Use of Large Quantities of 09/86 03/88 LI l
Cryogenic Combustibles on Site C-14 Storm Surge Model for Coastal Sites 02/83 05/88 LI(DROP) 111.D.1.l(2) Review Information on Provisions for Leak 12/82 09/88 DROP r
Detection III.D.I.l(3) Develop Proposed System Acceptance Criteria 12/82 09/88 DROP 1
FY-89 I
15*
Padiation Effects on Reactor Vessel Supports 09/88 02/89 HIGH 125.I.5 Safety Systems Tested in All Conditions-11/85 11/88 DROP i
Required by Design Basis Analysis 131 Potential Seismic Interaction Involving the 07/86 07/89 S(IPE)
'i Moveable In-Core Flux Mapping System Used in Westinghouse Plants 139 Thinning of Carbon Steel Piping in LWRs 12/86 11/88 RESOLVED B-31 Dam Failure Model
.02/83 02/89 LI(DROP)
D-2 ECCS Capability for Future Plants 06/83 10/88 DROP i
i l
Previous Priority Evaluation Published in NUREG-0933-t T6-7 As of 4th Quarter FY-96 l
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-90 63 Use of Equipment Not Classified as 10/82 02/90 DROP Essential to Safety in BWR Transient Analysis 71 Failure of Resin Demineralizer Systems and 06/83 02/90 LOW Their Effects on Nuclear Power Plant Safety 81*
Impact of Locked Doors and Barriers on 12/BG 02/90 DPs0P Plant and Personnel Safety 95 Loss of Effective Volume for Containment 08/84 02/90 RESOLVED Recirculation Spray
\\
96 RHR Suction Valve Testing 04/84 02/90 S(105) 107 Generic Implications of Main Transformer 11/84 02/90 LOW Failures 109 Reactor Vessel Closure Failure 12/84 02/90 DROP 116 Accident Management 04/85 09/90 S
117 Allowable Time for Diverse Simultaneous 05/85 02/90 DROP Equipment Outages 129 Valve Interlocks to Prevent Vessel 05/86 02/90 DROP Drainage During Shutdown Cooling 137 Refueling Cavity Seal Failure 10/86 05/90 DROP 140 Fission Product Removal Systems 03/87 02/90 DROP 141 LBLOCA With Consequential SGTR 04/87 05/90 DROP 142 Leakage Through Electrical Isolators 06/87 06/90 MEDIUM B-29 Effectiveness of Ultimate Heat Sinks 02/83 08/90 LI(RESOLVED)
B-32 Ice Effects on Safety-Related Water Supplies 02/83 08/90 5(153)
FY-91 24 Automatic Emergency Core Cooling 03/83 07/91 MEDIUM System Switch to Recirculation 38 Potential Recirculation System 09/82 08/91 DROP Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris T6-8 As of 41
-ter FY-96
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 Action item /
Identification Date Current i
Issue No.
Title Date Prioritized Priority i
FY-91 (Cont.)
72 Control Rod Drive Guide Tube Support Pin 06/83 10/90 DROP Failures 73 Detached Thermal Sleeves 06/83 08/91 NR 100 Once-Through Steam Generator Level 09/84 09/91 DROP 120 On-line Testability of Protection Systems 08/85 11/90 MEDIUM l
143 Availability of Chilled Water Systems and 10/87 03/91 HIGH Room Cooling i
150 Overpressurization of Containment 04/89 08/91 DROP
\\
Penetrations 151 Reliability of Anticipated Transient 04/89 08/91 MEDIUM Without Scram Recirculation Pump Trip in BWRs 153 Loss of Essential Service Water in LWRs 05/90 03/91 HIGH A-19 Digital Computer Protection System 02/83 11/90 LI B-22 LWR Fuel 02/83 06/91 DROP FY-92 2
Failure of Protective Devices on Essential 05/83 07/92 DROP Equipment 76 Instrumentation and Control Power 06/83 04/92 DROP Interactions 78 Monitoring of Fatigue Transient Limits for 06/83 07/92 MEDIUM Reactor Coolant System 81*
Impact of Locked Doors and Barriers on 08/91 04/92 LOW Plant and Personnel Safety 89 Stiff Pipe Clamps 02/84 08/92 MEDIUM 110 Equipment Protection Devices on 12/84 06/92 DROP Engineered Safety Features i
118 Tendon Anchorage Failure 07/85 01/92 RESOLVED
{
Previous Priority Evaluation Published in NUREG-0933
[
I T6-9 As of 4th Quarter FY-96 i
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-96 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-92 (Cont.)
123 Deficiencies in the Regulations 11/85 12/91 DROP Governing DBA and Single Failure Criterion Suggested by the Davis-Besse Incident of June 9,1985 132 RHR Pumps Inside Containment 07/86 03/92 DROP 138 Deinerting of BWRs With MARK I and II 10/86 10/91 LOW Containments During Power Operations Upon Discovery of Reactor Cooling System Leakage or a Train of a t
Safety System Inoperable 144 Scram Without a Turbine / Generator Trip 03/88 03/92 LOW 145 Actions to Reduce Common Cause Failures 09/88 02/92 NR 147 Fire-Induced Alternate Shutdown / Control Room 04/89 08/92 LI Panel Interactions 148 Smoke Control and Manual Fire-Fighting 04/89 08/92 LI Effectiveness 154 Adequacy of Emergency and Essential Lighting 09/90 01/92 LOW 155.1 More Realistic Source Term Assumptions 02/91 02/92 NR 155.2 Establish Licensing Requirements for 02/91 04/92 RI Non-Operating Facilities 155.4 Improve Criticality Calculations 02/91 08/92 DROP 155.5 More Realistic Severe Reactor Accident Scenario 02/91 06/92 DROP 155.6 Improve Decontamination Regulations 02/91 08/92 DROP 155.7 Improve Decommissioning Regulations 02/91 04/92 DROP 156.1.1 Settlement of Foundations and Buried Equipment 02/91 08/92 S(IPEEE) 156.1.2 Dam Integrity and Site Flooding 02/91 01/92 DROP 156.1.3 Site Hydrology and Ability to Withstand Floods 02/91 01/92 DROP 156.1.4 Industrial Hazards 02/91 03/92 DROP 156.1.5 Tornado Missiles 02/91 01/92 DROP 156.1.6 Turbine Missiles 02/91 10/91 DROP 156.2.]
Severe Weather Effects on Structures 02/91 01/92 DROP 156.2.2 Design Codes, Criteria, and Load 02/91 07/92 DROP Combinations
(3
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TABk
/(Continued)
V 1
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-92 (Cont.)
156.2.3 Containment Design and Inspection 02/91 05/92 DROP 156.2.4 Seismic Design of Structures, Systems, 02/91 03/92 DROP and Components 156.3.! 1 Shutdown Systems 02/91 03/92 DROP 156.3.1.2 Electrical Instrumentalon and Control 02/91 03/92 DROP 150 't.Z Service and Cooling Water Systems 02/91 03/92 DROP 156.3.3 Ventilation Systems 02/91 09/92 DROP 156.3.4 Isolation of High and Low Pressure 02/91 12/91 DROP Systems 156.3.5 Automatic ECCS Switchover 02/91 11/91 S(24) g 156.3.6.1 Emergency AC Power 02/91 02/92 S(B-56) 156.3.8 Shared Systems 02/91 06/92 DROP 156.4.1 RPS and ESFS Isolation 02/91 11/91 S(142) 156.4.2 Testing of the RPS and ESFS 02/91 03/92 S(120) 157 Containment Performance 10/91 02/92 RESOLVED lh91 146 Support Flexibility of Equipment and Components 01/89 09/93 RFSOLVED la9 Adequacy of Fire Barriers 04/89 10/92 LOW 152 Design Basis for Valves That Hight Be 03/90 01/93 LOW Subjected to Significant Blowdown Loads 155.3 Improve Design Requirements for Nuclear 02/91 01/93 DROP Facilities 156.3.6.2 Emergency DC Power 02/91 03/93 LOW 2 159 Qualification of Safety-Related Pumps While 10/91 09/93 DROP Running on Minimum Flow 160 Spurious Acticas of Instrumentation Upon 10/91 09/93 DROP Restoration of Power 161 Use of Non-Safety-Related Power Supplies in 10/91 03/93 DROP Safety-Related Circuits 162 Inadequate Technical Specifications for Shared 10/91 07/93 DROP Systems at Multiplant Sites When One Unit Is Shut Down 164 Neutron Fluence in Reactor Vessel 10/92 03/93 DROP T6-Il As of 4th Quarter FY-96
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-96 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-93 (Cont.)
166 Adequacy of Fatigue Life of Metal Components 04/93 04/93 NR 168 Environmental Qualification of Electrical 04/93 04/93 NR Equipment fh2.1 158 Performance of Power-Operated Valves Under 09/91 01/94 HEDIUM Design Basis Conditions 165 Spring-Actuated Safety and Relief Valve 10/92 11/93 HIGH Reliability g
167 Hydrogen Storage Facility Separation 06/93 09/94 LOW Lh2.E 170 Reactivity Transients and Fuel Damage Criteria 01/95 01/95 NR for High Burn-Up Fuel 171 ESF Failure from LOOP Subsequent to A LOCA 02/95 06/95 HIGH FY-96 172 Multiple System Responses Program 10/89 12/95 NR 173.A Spent Fuel Storage Pool: Operating Facilities 02/96 05/96 NR 173.B Spent Fuel Storage Pool: Permanently Shutdown 02/96 05/96 NR Facilities 174.A Fastener Gaging Practices: SONGS Employees' 02/96 05/96 RESOLVED Concern 174.B Fastener Gaging Practices: Johnson Gage 02/96 05/96 RESOLVED Company Concern 175 Nuclear Power Plant Shift Staffing 02/96 05/96 RESOLVED 176 Loss of Fill-0il in Rosemount Transmitters 02/96 05/96 RESOLVED 177 Vehicle Intrusion at TMI 02/96 05/96 RESOLVED 178 Effect of Hurricane Andrew on Turkey Point 05/96 05/96 LI i
179 Core Performance 02/96 05/96 LI 180 Notice of Enforcement Discretion 02/96 05/96 LI (Resolved) 181 Fire Protection 02/96 05/96 LI I
l T6-12 As of 4t rter FY-96
~
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(
TABre (Continued)
GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-96 l
Action Item /
Identification.Date Current Issue No.
Title Date Prioritized Priority l
FY-96 (Cont.)
182 General Electric Extended Power Uprate 05/96 05/96 RI 183 Cycle-Specific Parameter Limits in Technical 02/96 05/96 RI Specifications 184 Endangered Species 05/96 05/96
.EI 190 Fatigue Evaluation of Metal Components for 08/96 08/96 NR 60-Year Plant Life
.j 191 Assessment of Debris Accumulation on PWR 09/96 09/96 NR j
Sump Performance I
\\
f f
I t
h i
o i
i i
i i
i TS-13 As of 4th Quarter FY-96
- =
~ -.
~ -
TABLE 7
'f GENERIC ISSUES TO BE PRIORITIZED AS OF 4TH OUARTER FY-96 Action Item /
Identification Current Issue No.
Title Date Schedule 156.6.1 Pipe Break Effects on Systems and Components 02/91 12/96 163 Multiple Steam Generator Tube Leakage 06/92 TBD l
169 BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure 10/93 02/97 NMSS-0001 Door Interlock Failure Resulting from Faulty MicroSelectron-High 04/96 TBD i
Dose Rate Remote Afterloader NMSS-0002 Significant Quantities of Fixed Contamination Remain in Krypton-85 07/96 TBD Leak-Detection Devices After Venting NMSS-0003 Corrosion of Sealed Sources Caused by Sensitization of Stainless 07/96 TBD Steel Source Capsules During Shipment NMSS-0004 Overexposures Caused by Sources Stolen from Facility of Bankrupt 07/96 TBD
\\
Licensee TOTAL: 7 k
L L
i I
r i
I T7-1 As of 4th Quarter FY-96 l
t I
t TABLE 8
}
GENERIC ISSUES TO BE REPRIb3ITIZED AS OF 4TH OUARTER FY-96 l
I Action Item /
Previous Ident.
Current I
Issue No.
Title Priority Date Schedule 4
71 Failure of Resin Demineralizer Systems and Their Effects LOW 04/96 TBD j
on Nuclear Power Plant Safety 107 Main Transformer Failures LOW 04/96 TBD i
152 Design Basis for Valves That Hight Be Subjected to LOW 04/96 TBD Significant Blowdown Loads l
TOTAL: 3 I
h i
I
.t t
i t
l i
h t
f f
T8-1 As of 4th Quarter FY-96 m
....m
.m m
e O
O t
6 TABLE 9 REGULATORY IMPACT ISSUES SCHEDULED FOR RESOLUTION i
AS OF 4TH OUARTER FY-96 Lead Office /
l Issue Division /
Resolution i
Number Title Branch Date 182 General Electric Extended Power Uprate NRR/DRPW/PD31 TBD I
183 Cycle-Specific Parameter Limits in Technical Specifications NRR/DSSA/SRXB TBD i
L TOTAL: 2 I
\\
l i
i i
1 L
I i
T9-1 As of 4th Quarter FY [
i
_ _ _. _... _ _ _ _... _. _. _ _ _ _. _ _ _ _ ~. _.... _ -.... _ _ _. _.
i I
\\
TABLE 10 LICENSING ISSUES SCHEDULED FOR RESOLUTION
+
AS OF 4TH 00ARTER FY-96 Lead Office /
. Issue Division /
Resolution l
Number Title Branch Date e
f 148 Smoke Control and Manual Fire-Fighting Effectiveness RES/95R/PRAB ~
TBD I
178 Effect of Hurricane Andrew on Turkey Point NRR/DRPE/PDII 11/96 179 Core Performance NRR/DSSA/SRXB 12/97 181 Fire Protection NRR/DSSA/SPLB TBD l
t g TOTAL: 4 j
i i
r f
'i l
i I
i l
i i
I i
i I
T10-1 As of 4th Quarter FY-96 i
.. m m
m
4 TABLE 11 r
ENVIRONMENTAL ISSUES SCHEDULED FOR RESOLUTION l
AS OF 4TH OUARTER FY-96 i
Lead Office /
Issue Division /
Resolution
't Number Title Branch
-Date It is4 Endangered Species NRR/DRPM/PDND TBD i
TOTAL: 1 i
t
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l t
i t
t i
5
.i f
i L
F t
ta f
t t.t Tll-1 As of 4th Quarter FY-96 'f i
t I
O TABLE 12 RESOLVED GENERIC ISSUES WITH ONGOING ACTIVITY AS OF 4TH OVARTER FY-96
)
t Lead Office /
Issue Division /
Resolution Number Title Branch Date i
i 116 Accident Management NRR/DSSA/SCSB TBD 155.1 More Realistic Source Term Assumptions NRR/DRPM/PERB TBD t
HF5.2 Review Criteria for Human Factors Aspects of Advanced RES/DSR/HFBR 12/97 L
Controls and Instrumentation II.E.6.1 In-Situ Testing of Valves NRR/DE/EMEB TBD t
i t
TOTAL: 4 i
i t
t t
f i
e t
I i
i I
l T12-1 As of 4th Quarter FY-96 t
-i
~
i TABLE 13 RELATED GENERIC ACTIVITIES
-l AS OF 4TH OUARTER FY-96 Lead Office /
Issue Division /
Resolution Number Title Branch Date l
[
RGA-001 Boiling Water Reactor Internals NRR/DE/EMCB TBD RGA-002 Reactor Pressure Vessel Fracture Toughness NRR/DE/EMCB TBD RGA-003 Dry Cask Storage of Spent Fuel NMSS/SFP0 TBD RGA-004 Thermo-Lag Fire Barriers NRR/DSSA/SPLB TBD RGA-005 RCS Draindown NRR/DSSA/SRXB TBD RGA-006 SRP Revision NRR/ DISP /PIPB TBD RGA-007.1.20 PRA Implementation Plan - Graded QA NRR/DRCH/HQMB 04/98 l
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TOTAL: 7 j
F 1
I t
f f
i T13-1 As of 4th Quarter FY-96
..._.-__--_..m..
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s RUN DATE: 11/21/96 INDEX OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER TITLE PAGE 23
-REACTOR COOLANT PUMP SEAL FAILURES 1
78 MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT 5
116 ACCIDENT MANAGEMENT 8
145 ACTIONS TO REDUCE COMMON CAUSE FAILURES 10 148 SMDKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS 12 155.1 MORE REALISTIC SOURCE TERM ASSUMPTIONS 14 158 PERF OF SAFETY-RELATED POWER-OPERATED VALVES UNDER DESIGN BASIS CONDIT 18 165 SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY 20 g166 ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS 24 168 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 26 170 REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL 28
?
171 ESF FAILURE FROM LDOP SUBSEQUENT TO LOCA 32 I
172 MULTIPLE SYSTEM RESPONSES PROGRAM 34 173.A SPENT FUEL STORAGE POOL: OPERATING FACILITIES 35 173.B SPENT FJEL STORAGE POOL: PERMANENTLY SHUT 00WN FACILITIES 37 178 EFFECT OF HURRICANE ANDREW ON TURKEY POINT 39 179 CORE PERFORMANCE 41 181 FIRE PROTECTION 44 i
182 GENERAL ELECTRIC EXTENDED POWER UPRATE 47 i
f 183 CYCLE-SPECIFIC PARAMETER LIMITS IN TS 50 184 ENDANGERED SPECIES 52 190 FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR PLANT LIFE 54
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RUN DATE: 11/21/96 INDEX OF ISSUES I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER TITLE PAGE 191 ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE 56 B-17 CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS 58 6
B-55 IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES 60 t
B-61 ALLOWABLE ECCS EQUIPMENT OUTAGE PERIOOS 63
[
HF 5.2 REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
66 II.E.6.1 IN-SITU TESTING OF VALVES 68 f
RGA 001 BOILING WATER REACTOR INTERNALS 72 RGA 002 REACTOR PRESSURE VESSEL FRACTURE TOUGHNESS 75 RjiA 003 DRY CASK STORAGE OF SPENT FUEL 78 t
RGA 004 THERMO-LAG FIRE BARRIERS 81 RGA 005 RCS DRAINDOWN 83 RGA 006 SRP REVISION 85 RGA 007.1.2D PRA IMPLEMENTATION PLAN - GRADED QA 87 i
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RUN DATE: 11/2I/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
1 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURFS IDENTIFICATION DATE: 12/BOC PRIORITIZATION DATE: 04/83C TYPE: GSI PRIORITY: H TASK MANAGER:
K.
SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 01/97 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN. (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE A3751 BNL REACTOR COOLANT PUMP (RCP) SEAL INTEGRITY A3771 BNL ASSESS EFFECT DF MECH. MAINT. RCP SEAL A3806 BNL EVAL. ADEQ. OF RCP SEAL INSTR & RESP. TO RCP A6322 INEL RCP SHAFT SEAL BEHAVIDR DURING ST. BLACKDUT B2953 PNL REACTOR COOL. PUMP SEAL FAIL. VAL. IMP. ANALYSIS B3049 ETEC LEAK RATE ANALYSIS OF WESTINGHOUSE RCP D1760 SCIENTECH REG. ANAL. FOR GI-23. RCP SEAL FAILURES W6211 BNL SOLUTIONS TO MAINTAIN RCP SEAL INTEGRITY
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NY PORATE WORK NECESSARY TO COMPLETE GSI 65.
REVIEW ACCEPTABLE LEVEL COMMENSURATE WITH THE POTENTIAL SAFETY PWR RCP SEAL FAILURES CAUSED BY MECHANICAL FAILURES CONSEQUENCES OF SEAL FAILURE. THE PROGRAM CONSISTS OF AND LOSS OF SEAL COOLING TO ASCERTAIN IF INCREASED NRC THE FOLLOWING MAJOR TASKS:
REQUIREMENTS ARE NECESSARY TO MINIMIZE SEAL FAILURES.
TASK 1 - DETERMINE ACTUAL SEAL FAILURE MECHANISMS.
EVALUATE THE EFFECTS OF SYSTEM DESIGN. MATERIALS.
TASK 2 - EVALUATE RCP SEAL COOLING FOR ALL MODES OF OPERA-OPERATION. TESTING, AND MAINTENANCE ON SEAL FAILURE TION FOR WHICH SEAL COOLING IS REQ'O USING THE MECHANISMS. REVIEW THE RELIAB. OF SEAL COOLING SYSTEMS RELIABILITY OF TYPICAL RCP SEAL COOLING SYSTEM AND IDENTIFY METHODS TO MINIMIZE THE EFFECTS DF LOSS OF DESIGNS.
SEAL COOLING. PERFORM A RISK ASSESSMENT OF SEAL FAILURE TASK 3 - REVIEW MECHANICAL AND MAINTENANCE-INDUCED FROM MAINTENANCE AND MECHANICAL EFFECTS.
FAILURE MECHANISMS.
THIS PROCRAM WILL DETERMINE WHAT STEPS THE NRC TASK 4-FEASIBILITY STUDY TO IDENTIFY MOST EFFECTIVE FIX.
STATUS
____--__.----..--..---.-------------------------------------------------_----_-_-.._____.__s_.._____...
AN NRR GENERIC LETTER FOR INFORMATION ONLY WAS ISSUED REGULATORY GUIDE DG-1008 AND THE DRAFT REGULATORY ANALYSIS.
MAY 2 1991. TO INFORM LICENSEES OF THE POTENTIAL IMPACT NUREG-1401. THE STAFF DECIDED TO PROCEED WITH A RULEMAKING ON 580 ANALYSES. A FEDERAL REGISTER NOTICE WAS PUBLISHED FOR OFF-NORMAL CONDITIONS. WHILE THE NORMAL CONDITIONS HAVE APRIL 19. 1991. REQUESTING PUBLIC CDMMENT ON DRAFT BEEN ADDRESSED BY APPROPRIATE GENERIC COMMUNICATIONS.
AS OF FY96 QUARTER 4
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RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
2 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES AFFECTED DOCUMENTS PROBLEH/ RESOLUTION (k) khEhblLbbkNbkEPbkkkbVEbkkhkkkUbb khk kkkFh kkk bbbkhbbkkhb bkbk bbhkkkkk['khE kh kh NUREG/CR-4077 " REACTOR COOLANT PUMP SHAFT SEAL BEHAVIOR" BRIEFED COMMISSIONERS
- ASSISTANTS ON INSIGHTS LEARNED FROM NUREG/CR-4294 " LEAK RATE ANALYSIS OF THE WESTINGHOUSE IPE*S REGARDING GI-23. THIS BRIEFING RESULTED IN SOME REVI-REACTOR COOLANT PUMP" SION TO THE PROPOSED RESOLUTION PACKAGE. THE PACKAGE WAS NUREG/CR-482I. " REACTOR COOLANT PUMP SHAFT SEAL STABILITY REVISED AND PROVIDED TO THE COMMISSION FOR REVIEW AND DURING STATION BLACKOUT" APPROVAL. THE COMMISSION DISAPPROVED ISSUANCE OF THE PRO-NUREG/CR-4643. " EVALUATION OF CORE DAMAGE SEQUENCES POSED RULE FOR PUBLIC COMMENT AND DIRECTED THE STAFF TO INITIATED BY LOSS OF REACTOR COOLANT COMMUNICATE THIS DECISION TO REACTOR LICENSEES.
PUMP SEAL COOLING" AN INFORMATION NOTICE 95-42 WAS ISSUED TO THE LICENSEES NUREG/CR-4400 "THE IMPACT OF MECHANICAL AND HAINTENANCE-ABOUT THE COMMISSION'S DECISION ON THE RESOLUTION OF GI-23 INDUCED FAILURE OF HAIN REACTOR COOLANT ON SEPTEMBER 22. 1995.
THE STAFF IS DETERMINING PUMP SEALS ON PLANT SAFETY" EFFECTIVE WAYS TO PROCEED WITH THE RESOLUTION / CLOSEOUT OF NUREG/CR-4544 " REACTOR COOLANT PUMP SEAL-RELATED INSTRU-THIS ISSUE BY GENERIC COMMUNICATION.
MENTATION AND OPERATOR RESPONSE" NUREG/CR-4948. " TECHNICAL FINDINGS RELATED TO GI-23 REACTOR COOLANT PUMP SEAL FAILURES" SNUREG/CR-5I67 " COST BENEFIT ANALYSIS FOR GI-23. REACTOR COOLANT PUMP SEAL FAILURE" NUREG/CR-5918 " ANALYSIS OF PUBLIC COMMENTS ON GI-23.
REACTOR COOLANT PUMP SEAL FAILURE" (UNDER CONSIDERATION TO BE PUBLISHED) 1 RULEHAKING RDB-333 DRAFT REGULATORY GUIDE DG-1008 (WITHDRAWN BY CRGR)
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE hkPkhkbkbFbkbbhkkhk b4hb3 b3)h3 '
TAP APPROVED BY DSI DIR 10/83 10/83 ISSUED REQUEST FOR PROPOSAL TO BNL FOR 11/83 11/B3 COMPONENT COOLING WATER PRA TRANSFER RESOLUTION REPONSIBILITY FROM DSI TO 06/84 06/B4 DE TRANSFER RESOLUTION RESPONSIBILTY FROM DE TO 05/85 05/85 DST /GIB AS OF FYS6 QUARTER 4 O
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RUN DATE: 11/21/9E GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
3 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES ORIGINAL CURRENT ACTUAL M1LEST0NES DATE DATE DATE COMPLETE DOCUMEN. OF BACKGROUND PAST 05/85 12/85 SEAL FAILURES. INCLUDING LER SEARCH.REV 0F INDUST. EXP.& REV.0F BWR SCR.(TASK 1)
EVAL. RCP SEAL COOLING. INCL. DETERM. EFFECT 12/84 08/86 0F LOSS COOLING. EVAL RELIAB. OF COOLING SYS.
AND REV. RCP SEAL COOLING INSTR. (TASK 2)
EVALUATE MECHANICAL AND MAINTENANCE-INDUCED 01/85 01/88 FAILURE HECHANISMS (TASK 3)
DRAFT SCIENTECH REPORTS TO IDENTIFY MOST 03/85 01/89 EFFECTIVE FIX. (TASK 4)
REVIEW & FINALIZE SCIENTECH REPORTS 05/89 03/90 DTR PACKAGE COMPLETE 07/85 04/90 DIVISION DIRECTOR REVIEW COMPLETED 08/8 5 05/90 ACRS REVIEW OF DTR COMPLETE 11/85 09/90 CONCURRENCE BY OTHER OFFICES 09/8 5 10/90 DTR SENT TO CRGR 10/85 10/90 CRGR REVIEW OF DTR COMPLETE 11/85 03/91 FRN OF ISSUANCE OF PROPOSED RESOLUTION FOR 12/85 04/91 PUBLIC COMMENT ORAFT FERFORMANCE 07/91 08/91 PUBLIC COMMENT PERIOD ENDS 09/91 11/91 COMPLETE REVIEW AND COMPILATION OF PUBLIC 04/86 02/92 COMMENTS RECEIPT OF GUIDANCE FROM EDO ON RULEMAKING 05/92 11/92 AS OF FY96 QUARTER 4
l l
RUN DATE: 11/21/96 j
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
4 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES i
DRIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PkbPbSEbkPPRbkCHkbhRkFbkhbkNLbPEkkTbN kkhbh khhbh PREPARE PROPOSED RULE 09/92 05/93 DIVISION DIRECTOR REVIEW OF PROPOSED RULE 10/92 06/93 COMPLETED CONCURRENCE BY OTHER OFFICES OF PROPOSED 11/92 07/94 RULE LETTER TO NRR FOR BWR SEALS UNDER S80 05/93 10/93 ACRS AND CRGR REVIEW OF PROPOSED RULE 12/92 03/94 PROPOSED RULE TO EDO 02/93 09/94 g
PROPOSED RULE TO COMMISSION 02/93 11/94 COMMISSION'S REVIEW 03/93 03/95 PUBLICATION OF IN 95-42 INFORMING INDUSTRY 03/95 09/95 0F COMMISSION'S DECISION CLOSE THE ISSUE BY GENERIC COMMUNICATION 09/95 01/97 AS OF FY96 QUARTER 4 O
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5
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ISSUE NUMBER: 78 TITLE: MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT
[
f IDENTIFICATION DATE: 05/83C PRIORITIZATION DATE: 07/92C TYPE:
PRIORITY: M TASK MANAGER: K.
SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: 4 t
TAC NUMBERS:
RESOLUTION DATE: 11/96 WORK AUTHORIZATION: 7/10/92 MEM0/BECKJORD TO MINNERS. " MONITORING OF FATIGUE..."
i 4/1/93 MEM0/BECKJORD TO SNIEZEK. " RESOLUTION OF FATIGUE.. "
FIN CONTRACTOR CONTRACT TITLE W6077 ANL STATISTICAL ANALYSIS OF FATIGUE DATA WDRK SC0PE ibbkVkLbPbbfbkkbEbkPbkEkkkkLkkkkbbkbEbkkbkhIbhbk bbkbkkbb[S PPLkbkbLkkbkHbSkkEkikkkbYkkRkbkPLkkh CD PONENT OF THE RCPB FOR ALL OPERATING PLANTS. THIS OPERATION UNDER THE CURRENT 40-YEAR LICENSE.
STATUS
'kEbUkEkbEbRibikLbEkibkBkkikbkkHkRkkbibkbbbtEkk ikib kkkIk bkkkk[b'[kkUk'Ibb kkfiftkb'"kbk[ibk[kb bk""
PRESSURE BOUNDARY (RCPB) DID NOT ACCOUNT ADE @ TELY FOR THE FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT."
i EFFECTS OF THE REACTOR COOLANT HARSH ENVIRONM NTS DURING THE OUTCOME OF THE GI-78 AND 166 WORK IS THAT NO L
OPERATION ON THE RCPB FATIGUE RESISTANCE. GENERIC ISSUE 78 FATIGUE CONCERNS EXIST FOR 40-YEAR PLANTS. BUT MORE STUDY WAS ESTABLISHED TO ASSESS THE INCREASE IN RISK DUE TO OPERA-IS NEEDED TO DETERMINE THE STATUS OF A 60-YEAR LICENSED TION UNDER THE HARSH ENVIRONMENT.
PLANT. A PEER REVIEW DF THE RISK ANALYSIS AND 60-YEAR A RISK ANALYSIS WAS COMPLETED IN LATE FY'95 THAT SHOWED EVALUATION IS PLANNED UNDER A NEW GENERIC ISSUE GI-190.
THE RISK OF FAILURE OF REACTOR PRIMARY CIRCUIT COMPONENTS TO A CLOSE-DUT MEMO TO THE EDO IS BEING PREPARED.
l BE ACCEPTABLY LOW FOR 40-YEAR PLANTS. THIS WAS INTEGRATED P
AFFECTED DOCUMENTS PROBLEM / RESOLUTION T0 BE DETERMINED NONE.
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ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GI-78 ASSIGNED TO RES/DSIR/EIB 07/92 07/92 AS OF FY96 QUARTER 4 k
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RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
6 ISSUE NUMBER: 18 TITLE: MONITORING GF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DRAFT PRA PARAMETRIC STUDY ISSUED FOR PEER 10/92 11/92 REVIEW AND COMMENT TO OTHER NRC DIV!
105 PREPARE DRAFT S0W FOR ANL CONTRACT 02/93 02/93 FIN-6077-3 S0W APPOVED BY DSIR DIRECTOR 03/93 03/93 ISSUE S0W FOR AHL CONTRACT FIN-6077-3 03/93 03/93 ANL RECEIVES NRC/RES APPROVAL TO START WORK 05/93 06/93 ANL/RES MEETING TO DISCUSS STATISTICAL 07/93 07/93 STUDIES
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ANL PRESENTAT(pN TO RES AND NRR 02/94 02/94 ANL COMPLETES DRAFT REPORT 08/93 03/94 ANL COMPLETES FINAL REPORT (CARBON STEEL AND 09/93 08/94 LOW ALLOY STEEL)
REVISE PRA ANALYSIS OF FATIGUE ISSUE 03/94 08/94 PRA ANALYSIS (CARBON STEEL AND LOW ALLOY 04/94 09/94 STEEL)
ANL COMPLETES STAINLESS AND NICKEL ALLOY 12/94 12/94 STEEL ANALYSIS ANL COMPLETES DRAFT REPORT (STAINLESS AND 01/95 01/95 NICKEL ALLOY STEELS)
ANL COMPLETES FINAL REPORT (STAINLESS AND 04/95 06/95 NICKEL ALLOY STEELS)
CLOSEOUT MEMO AND PRA ANALYSIS (STAINLESS 05/95 08/95 AND NICKEL ALLOY STEELS) TO NRR FATIGUE ACTION PLAN (i1RR). INCLUDES GI-78 09/95 09/95 WORK AS OF FY96 QUARTER 4 O
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8 ISSUE NUMBER: 116 TITLE: ACCIDENT MANAGEMENT IDENTIFICATION DATE: 04/8SC PRIORITIZATION DATE: 09/90C TYPE: GSI PRIORITY: H TASK MANAGER: R. PALLA OFFICE / DIVISION / BRANCH: NRR /DSSA/SCSB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91966 M91641 RESOLUTION DATE:
VORK AUTHORIZATION: SECY-BB-147 " INTEGRATION PLAN FOR CLOSURE OF SEVERE ACCIDENT ISSUES." 05/25/88 FIN CONTRACTOR CONTRACT TITLE LIE 97 ORNL TECHNICAL ASSISTANCE IN SUPPORT OF THE REACTOR SYSTEMS BRANCH W0RK SC0P E kPkbkFkb kbTkbbk khbtbbEb kh kHk k/M kbkkbh PLkh Rh bbHPLkkE Pktbh kkSPEbkkbkk kkb FbLLbbbP$ kb (S bEVELbPkh fil COMPLETE THE REVIEW OF BWROG SAMG DOCUMENTS. (2) CONDUCT INSPECTION PROCEDURE FOR USE AT REMAINING PLANT AND HOLD A
$1rE VISITS IN 1996 TO OBSERVE HOW THE ELEMENTS OF THE PUBLIC WORKSHOP. BASED ON FEEDBACK FROM THE WORKSHOP. THE FORMAL INDUSTRY POSITION ARE BEING IMPLEMENTED. (3) COMPLETE STAFF WILL FINALIZE THE INSPECTION PROCEDURE AND THE THE DRAFT TEMPORARY INSTRUCTION (TI) USING THE INFORMATION APPROACH AND SCHEDULE FOR EVALUATING A/H IMPLEMENTATION FOR AND PERSPECTIVES OBTAINED THROUGH THE SITE VISITS. (4)
THE REMAINING PLANTS.
STATUS
_____.....___________.______..__..____-._____-__-_-______--_-____.-_..__-.~.-.._..______....____..._________...______.._____
SEVERE ACCIDENT MANAGEMENT GUIDELINE DOCUMENTS HAVE BEEN HAVE BEEN SUBMITTED TO NRC. AND A DRAFT TI FOR USE IN THE SUBMITTED BY EACH OF THE PWR OWNERS GROUPS AND REVIEWED PILOT INSPECTIONS HAS BEEN COMPLETED. COMMENTS ON THE DRAFT BY THE STAFF.
THE BWROG SUBMITTED A SEVERE ACCIDENT TI HAVE BEEN RECEIVED FROM THE NRC REGION OFFICES. THE MANAGEMENT OVERVIEW DOCUMENT ON FEBRUARY 3, 1995. AND A STAFF HET WITH INDUSTRY ON FEBRUARY 22 1996. AND ACRS ON RESPONSE TO STAFF COMMENTS ON THE OVERVIEW DOCUMENT ON MARCH 1, 1996. TO DISCUSS PLANS FOR INSPECTING UTILITY MARCH 6 1996.
THE 8WROG SU8HITTED REV. 0 0F THE IMPLEMENTATION OF THE FORMAL INDUSTRY POSITION ON SEVERE EMERGENCY PROCEDURE AND SEVERE ACCIDENT GUIDELINES (EP/ SAG) ACCIDENT MANAGEMENT AND MAJOR ELEMENTS OF THE DRAFT TI.
THE 1996.
THE STAFF STAFF WILL VISIT APPROXIMATELY 2 TO 4 SITES IN AND TECHNICAL BASIS REPORT ON AUGUST 29, HAS CONTRACTED WITH OAK RIDGE NATIONAL LABORATORY TO LATE 1996/EARLY 1997 FOR THE PURPOSE OF OBTAINING AN EARLY PERFORM A HIGH LEVEL REVIEW OF THE DOCUMENTS. THE UNDERSTANDING OF HOW THE VARIOUS ELEMENTS OF THE FORMAL TARGET DATE FOR COMPLETING THE REVIEW OF THE BWROG INDUSTRY POSITION ARE BEING IMPLEMENTED. THE INFORMATION IS DECEMBER 1996. A HEETING TO DISCUSS SPECIFIC AND PERSPECTIVES OBTAINED THROUGH THESE VISITS AS WELL AS MATERIAL COMMENTS FROM THE REGION OFFICES WILL BE USED TO UPDATE THE STAFF CONCERNS REGARDING THE BWROG PRODUCTS IS EXPECTED DRAFT TI.
THE DRAFT TI WILL BE MADE AVAILABLE TO NEI AND 1996.
IN NOVEMBER LICENSEE TARGET DATES FOR COMPLETING A/H IMPLEMENTATION THE PUBLIC AFTER THE INFORMATION-GATHERING VISITS.
AS OF FY96 QUARTER 4 O
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9 ISSUE NUMBER: 116 TITLE: ACCIDENT MANAGEMENT i
AFFECTED DOCUMENTS PROBLEM / RESOLUTION GL 88-20. SUPPLEMENT 2 NOME ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE REVIEW SEVERE ACCIDENT TRAINING MATERIALS 06/95 06/95 AND BWROG PRIORITIZATION METHODOLOGIES INITIAL DRAFT (FOR INTERNAL USE) 0F TI FOR 11/95 11/95 PILOT INSPECTIONS REVIEW BWROG SEVERE ACCIDENT MANAGEMENT 08/96 12/96 GUIDANCE (SAMG) DOCUMENTS I
SITE VISITS OF "IN-PROGRESS" ACTIVITIES 11/96 02/97 REVISED DRAFT OF TI FDR PILOT INSPECTIONS 12/96 03/97 TO NEI AND PUBLIC r
FINAL TI FOR PILOT INSPECTIONS 03/97 05/97 COMPLETE PILOT INSPECTIONS AND FOLLOWUP 12/97 12/97 ISSUE DRAFT REVISED INSPECTION PROCEDURES 03/98 03/98 (IP) l HOLD PUBLIC MEETING / WORKSHOP 05/98 05/98 t
ISSUE FINAL IP 07/98 07/98 REVIEW REMAINING PLANTS i
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10 ISSUE NUMBER: 145 TITLE: ACTIONS TO REDUCE COMMON CAUSE FAILURES IDENTIFICATION DATE: 07/B5C PRIORITIZATION DATE: 02/92C TYPE: GSI PRIORITY: H TASK MANAGER: E. CHELLIAH OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE: 02/97 WORK AUTHORIZATION: HEHORANDUM FROM E. S. BECKJORD TO W. MINNERS DATED FEBRUARY 11, 1992 FIN CONTRACTOR CONTRACT TITLE L1125 L2553 BNL TECHNICAL MIPPORT TO GI-145 W0RK SC0PE hh kkkbbk Rkhbkkkb kb kESbLhk hhk kkkbh RE MkhkhkL kHk V kLkBLk bh CbkHbh hbbk F kLbRkk kb PbbLkkH kh kh SC PE OF THE ISSUE IS ONLY TO COLLECT THE INFORMATION NUREG REPORT, 50 AS TO BE READILY AVAILABLE TO LICENSEES.
STATUS BNL SUBMITTED A FINAL REPORT IN CECEMBER 1993. THE STAFF NEEDED TO RESOLVE THE ISSUE.
FOUND THAT NO ADDITIONAL REQUIREMENTS ON THE LICENSEES WERE AFFECTED DOCUMENTS PROBLEH/ RESOLUTION POSSIBLE NUREG/CR.
NONE.
ORIGINAL CURRENT ACTUAL MILE 5T0NES DATE DATE DATE bbHPLEhkbhbFbkPkkbkkkkbhkbh bbh9h bhhhh COMPLETION OF TAP 04/92 04/92 ISSUE CONTRACT FUND 01/93 04/93 AS OF FY96 QUARTER 4 O
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11 f
I ISSUE NUMBER: 145 TITLE: ACTIONS TD REDUCE COMMON CAUSE FAILURES ORIGINAL CURRENT ACTUAL i
MILESTONES DATE DATE DATE i
i CONTRACTOR'S DRAFT FINDINGS 06/92 10/93 CONTRACT 00 S FINAL FINDINGS 09/92 12/93 i
6 STAFF S DRAFT FINDINGS 10/92 11/93 i
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DECISION ON STAFF *S FINDINGS
~11/92 12/93
{
DTR TO NRR FOR COMMENTS 04/95 04/95 BNL PUBLICATION TO JOURNALS 05/95 05/95 NRR PROVIDES COMMENTS ON BNL'S FINDINGS 02/95 07/95 f
BNL CORRECTIONS TO FINAL TS REPORTS 08/95 09/95 5
FTR COMPLETE 08/95 11/95 FTR TO ACRS 09/96 12/96 f
PRAB PUBLISH CCF METHODS REPORT 04/9 6 12/96 i
ISSUE CLOSURE MEMO TO EDO 04/96 02/97 t
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12 ISSUE NUMBER: 14B TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS IDENTIFICATION DATE: 04/B9C PRIORITIZATION DATE: OB/92C TYPE: LI PRIORITY:
TASK MANAGER: J. CHEN OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE:
WORK AUTHORIZATION: MEMORANDUM FROM E. S. BECKJORD TO W. MINNERS DATED AUGUST 26 1992 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE
~~--------------------------------------------------------------___
TO DEVELOP STAFF GUIDANCE FOR THE REVIEW OF LICENSEES
- HANUAL FIRE-FIGHTING EFFECTIVENESS.
IP{EE SUBMITTALS RELATED TO THE EFFECTS OF SMOKE AND STATUS TASK REASSIGNED TO SAIB/SECTION S IN FEBRUARY 1993 AND IS IPEEE SCHEDULE.
BEING PREPARED BY SANDIA.
SCHEDULE CHANGED TO CONFORM TO AFFECTED DOCUMENTS PROBLEM / RESOLUTION POSSIBLE NUREG/CR.
GUIDANCE PLACED IN CONCURRENCE BY TASK MANAGER ON 02/29/96.
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE GI-14B ASSIGNED TO RES/DSIR/RPSI 09/92 09/92 REASSIGNED TO SAIB 02/93 02/93 DRAFT STAFF REVIEW GUIDANCE RELATED TO SMOKE 09/93 AND MANUAL FIRE-FIGHTING EFFECTIVENESS AS OF FY96 QUARTER 4 O
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13 i
ISSUE NUMBER: 148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS l
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IkkbEbLbSEbbTMEHb 06/95 1
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14 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS IDENTIFICATION DATE: 03/79 PRIORITIZATION DATE: 02/92C TYPE: GSI PRIORITY:
TASK MANAGER: R.EMCH/A.HUFFERT OFFICE / DIVISION / BRANCH: NRR /DRPM/PERB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: MB95BS RESOLUTION DATE: 03/95C WORK AUTHORIZATION: MEMO FOR W. MINNERS FROM E. BECKJORD DATED 2/26/92 FIN CONTRACTOR CONTRACT TITLE B0b5k bRNL kbbfNEbHEMiCLFbRMS LI535 BNL RADIONUCLIDE RELEASE CHARACTER L1611 INEL TIMING ANALYSIS OF FUEL FAILURES L2035 SNL SOURCE TERM REMOVAL MECHANISMS W6067 ORNL CHEMICAL FORM OF SOURCE TERMS W0RK SC0PE
--\\------------------------------------------------------------- BY NOVEMBER. AS DESCRIBED IN THE COMMISSION PAPER. THE THE STAFF HAS REVIEWED THE FRAMEWORK DOCUMENT AND IS PREPARING A DRAFT COMMISSION PAPER AND DECISION LETTER THAT PLAN IS TO REVIEW PILOT PLANT APPLICATIONS AND DETERMINE DESCRIBES A GENERIC IMPLEMENTATION APPROACH. THE STAFF WHETHER RULEMAKING AND EXEMPTIONS ARE NECESSARY FOR PRESENTED THE COMMISSION PAPER AND DECISION LETTER TO THE IMPLEMENTATION AT ADDITONAL PLANTS. THE CURRENT SCHEDULE NRR EXECUTIVE TEAM AND CRGR IN SEPTEKBER AND WILL SUBMIT IS TO REBASELINE TWO PLANTS AFTER THE COMMISSION PAPER THE COMMISSION PAPER AND DECISION LETTER TO THE COMMISSION HAS BEEN REVIEWED BY THE COMMISSION.
$TATUS NEI SUBMITTED ITS GENERIC FRAMEWORK DOCUMENT IN NOVEMBER THE STATUS OF NRC*$ REVIEW OF THE GENERIC FRAMEWORK 1995 FOR NRC REVIEW AND APPROVAL. PILOT PLANT APPLICATIONS DOCUMENT. THE STAFF HAS COMPLETED ITS REVIEW OF THE HAVE BEEN RECEIVED FROM BROWNS FERRY. MILLSTONE. AND FRAMEWORK DOCUMENT AND IS PREPARING A DRAFT COMMISSION PAPER INDIAN POINT. GRAND GULF AND PERRY ARE ALSO PREPARING THEIR DESCRIBING HOW IT INTENDS TO CONDUCT ITS GENERIC REVIEW OF PILOT PLANT SUBMITTALS. THE STAFF MET WITH NEI ON PILOT PLANT SUBMITTALS. BRIEFINGS OF THE NRR EXECUTIVE JANUARY 23, 1996. TO DISCUSS THE GENERIC FRAMEWORK AND TEAM AND CRGR HAVE BEEN COMPLETED. AND A BRIEFING FOR THE SEPARATE MEETINGS WERE HELD ON FEBRUARY 7 MAY 30 AND ACRS IS BEING SCHEDULED. A SERIES OF PILOT PLANT AUGUST 29 1996 TO DISCUSS THE BR0VMS FERRY. PERRY AND SUBMITTALS HAS BEEN SUBMITTED. AND TWO OR MORE ADDITIONAL GRAND GULF PILOT PLANT SUBMITTALS. RESPECTIVELY. A MEETING PILOT PLANT SUBMITTALS ARE EXPECTED BEFORE THE END OF 1996.
WAS HELD WITH NEI ON OCTOBER 2.
1996. TO UPDATE INDUSTRY ON AS OF FY96 QUARTER 4 O
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15 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS I
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
[
R.G.
1.3 1.4 SRP 15.6.5 NOME.
R.G.
1.7.
1.25 NOREG-1465 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 7
IODINE / TID SCHEDULE TO COMMISSION 04/9 0 05/90 i
PRA BASED SOURCE TERM PAPER TO CDMMISSION 05/90 05/90 FISSION PRODUCT TIMING PAPER TO COMMISSION 07/90 08/90 REVISED BNL DRAFT REPORT 07/90 08/90 t
TID REPORT SCHEDULE - IODINE CHEMICAL FORM 12/90 07/91 REPORT ISSUED FOR COMMENT PROPOSED REY. TO TID TO RES DIRECTOR 07/91 09/91 l
PROPOSED REVISION TO NRR/0GC 09/91 09/91 DRAFT TID TO ACRS 11/91 12/91 l
COMPLETE ACRS REVIEW 12/91 01/92 OFFICE CONCURRENCE ON TID 10/91 04/92 DRAFT BNL REPORT ISSUED FOR COMMENT 07/91 02/92
[
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TID TO COMMISSION 02/92 04/92
(
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ISSUE REVISED TID FDR COMMENT 02/92 07/92 AS OF FY96 QUARTER 4 i
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ISS.I TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IkkbEbRkLkbbkkEREPbRT kFkkL 04hh2
~
b4hh2 SNL REPORT ON POOL DF NUREG/CR ISSUED FOR 08/92 09/92 COMMENT ISSUE INEL REPORT FINAL 08/92 09/92 END COMMENT PERIOD ON ORAFT SOURCE TERM 08/92 10/92 NUREG RESPONSE TO SRM ON IMPACT OF INCREASED 09/92 11/92 AMOUNT OF RADIATION (WITS 9200124) -- ORAFT COMMISSION PAPER AVAILABLE
-- RES CONCURRENCE 09/92 12/92
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-- COMMISSION PAPER TO EDO AND OFFICE 10/92 01/93 CONCURRENCE
-- COMMISSION PAPER TO COMMISSION 11/92 02/93 SNL SPRAY NUREG/CR ISSUED FINAL 11/92 06/93 ORNL NUREG/CR ON HELCOR ISSUED 09/93 09/93 SNL REPORT ON POOL OF NUREG/CR ISSUED FINAL 11/92 11/93 ISSUE BNL REPORT FINAL 06/92 11/93 SNL NUREG/CR ON HELCOR ISSUED 11/93 03/94 NEI LETTER 07/94 07/94 BRIEF ACRS 09/94 09/94 COMMISSION MEMORANDUM 09/94 09/94 NEI RESPONSE 09/94 09/94 NEI/NRC MEETING 10/94 10/94 i
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155,1 TITLE: MORE REALISTIC SDURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE COMPLETE REVISED SOURCE TERM NUREG 11/92 02/95 PUBLICATION OF NUREG-1465 02/95 02/95 ISSUE CLOSEOUT MEMO (L. SOFFER. PROJECT 12/92 03/05 MANAGER, RES/ DST)
NEI/NRC MEETINGS 06/95 06/95 NEI/NRC MEETINGS 10/95 10/95
$UBMITTAL OF GENERIC FRAMEWORK DOCUMENT 11/95 11/95 (FROM NEI)
FIRST PILOT PLANT SUBMITTAL 12/95 12/95
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NEI/NRC MEETINGS 01/96 01/96 PRESENT COMMISSION PAPER IN E-TEAM BRIEFING 08/96 09/96 BRIEF CRGR ON COMMISSION PAPER 09/96 10/96 BRIEF ACRS ON COMMISSION PAPER 10/96 11/96 SENO COMMISSION PAPER TO ED0/ COMMISSION 10/96 11/96 PUBLISH DECISION LETTER 11/96 11/96 BEGIN PILOT PLANT REVIEWS 11/96 11/96 (A) ISSUE RAl*S ON PILOT PLANT 01/97 01/97 (B) RESPONSE TO RAI*$ FRDM PILOT PLANT 04/97 04/97 (C) PROVIDE PILOT PLANT SER TO PROJECTS 06/97 06/97 (D) PREPARE LICENSE AMENDMENT FOR PILOT 07/97 07/97 PLANT AS OF FY96 QUARTER 4
RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
18 ISSUE NUMBER: 158 TITLE: PERF OF SAFETY-RELATED POWER-OPERATED VALVES UNDER DESIGN BASIS CONDIT IDENTIFICATION DATE: 09/91C PRIORITIZATION DATE: 01/94C TYPE: GSI PRIORITY: M TASK MANAGER: V. LEUNG OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 08/97 WORK AUTHORIZATION: MEMORANDUM FROM E. BECKJORD TO J. MURPHY ON JANUARY 26 1994 FIN CONTRACTOR CONTRACT TITLE U6bsk kkkL PbhkRbPkRkkkbhkLhbPkkFbkhkbh
~~~~~~~~~~
W0RK SC0PE kkbPkkkkkbVkLVkS SbLkkb5b bPkkkkkb h LVkk kNb PkbGkkhh[LLhkkkRkkNEkFkHkRbkkkkFkhYkELhkb
' ~~
5 HYORAULIC-OPERATED VALVES HAVE NOT BEEN SUBJECTED TO A PROBLEMS. THE SOLUTION OF THE PROBLEMS. AND WHETHER C0yPREHENSIVE RISK EVALUATION: HENCE. THESE VALVES LACK THE IMPLEMENTATION OF THE SOLUTIONS ARE COST BENEFICIAL' REGULATORY SCRUTINY APPLIED TO THE OTHER EQUIPMENT. THIS STATUS PRELIMINARY DRAFT REPORT WAS SUBMITTED BY THE CONTRACTOR AND REVIEWED BY NRR.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
---~~--~~~~~~~j---~~--~~~~--~~--~~--------~~~~~--------~~~~
~~--~~~--~~~--~~~---------
WITH THIS ISSUE. A DECISION HAS BEEN MADE TO ENLIST CONTRACTOR ASSISTANCE TO SORT AND CATEGORIZE THE DATA AND ASSIST IN THE RESOLUTION. DATA ANALYSIS COMPLETED BY INEL.
NRR REVIEWED AND COMMENTED ON INEL DRAFT REPORT.
CONTRACTOR REVISING ORAFT REP 01T IN RESPONSE TO NRR COMMENTS.
ORIGINAL CURRENT ACTUAL MILEST0NES OATE
, DATE DATE QUICK REVIEW COMPLETE 04/94 04/g4 AS OF FY96 QUARTER 4 O
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19 ISSUE NUMBER: 158 TITLE: PERF OF SAFETY-RELATED POWER-OPERATED VALVES UNDER DESIGN BASIS CONDIT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PROGRAM PLAN COMPLETE 05/94 05/94 CONTRACTOR SELECTED 06/94 06/94 PROGRAM ASSUMPTION 06/94 07/94 NRC FORM 189 RECEIVED 08/94 09/94 PROPOSAL ACCEPTED 08/94 09/94 DATA ANALYSIS 11/94 06/95 MODEL SELECTION 12/94 09/9 5 g
CDF/ RISK ESTIMATION 06/95 10/95 DRAFT INEL REPORT RECEIVED 11/95 10/95 DTR PACKAGE FOR RES/NRR/AEOD REVIEW 01/96 03/97 RESOLUTION PACKAGE FDR ACRS/CRGR REVIEW 02/96 06/97 ACRS/CRGR MEETINGS 03/96 07/97 RESOLUTION MEMORANDUM TO THE EDO 04/96 08/97 4
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20 ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY IDENTIFICATION DATE: 10/92C PRIORITIZATION DATE: 11/93C TYPE: GSI PRIORITY: H TASK MANAGER: O. GORMLEY OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE: 06/98 TAC NUMBERS:
WORK AUTHORIZATION: NOVEMBER 26, 1993. MEMORANDUM FROM E. BECKJORD TO W. MINNER5 FIN CONTRACTOR CONTRACT TITLE hkb kbkkbkkk kbBEbkhEkkkkEb
~~~~~~~~
WORK SC0PE k$ kktkbk bk Lbkb Pk k Fbk kk LhSkk kh k Rk hkkkkbbk 4$b kkCLbbkkbkELkkFhLhkkkkhhEPkkh 6.
PERFORM COST / BENEFIT ANALYSES TO DETERMINE THE BEST OR 5.0.
2.I DETERMINE WHAT SYSTEMS HAVE SPRING-ACTUATED RELIEF FIX FOR THE PROBLEM AND WHICH VALVES SHOULD BE TESTED.
VALVES AND OTHER IMPORTANT INFORMATION BY REVIEWING P& IDS 7.
PREPARE REGULATORY ANALYSIS.
8.
RESOLVE GSI-165 WITH EITHER THE IMPLEMENTATION OF THE
.FROM THE SELECTED PRAS.
3.
PERFORM ANALYSIS TO DETERMINE THE EXTENT OF VALVE BEST FIX OR A CLOSEOUT MEMO IF THE COST / BENEFIT IS FAILURE REQUIRED TO FAIL THE SYSTEM IN WHICH THEY OPERATE.
NEGLIGIBLE.
4.
REVIEW LERS TO MORE ACCURATELY OETERMINE THE FAILURE IN ACCORDANCE WITH 5/5/94 MEMO TO NRR DIRECTOR FROM THE PROBABILITY FOR SPRING-ACTUATED RELIEF VALVES.
RES DIRECTOR. RESOLUTION WILL INCLUDE CONSIDERATION OF A 5.
CALCULATE THE CHANGE IN CORE DAMAGE FREQUENCY FROM LICENSE RENEWAL PERIOD OF 20 YEARS.
STATUS bbkkRkbTbR kEPbRh Hkk BEEK REbEkhEb kb [S BEkkG EhELbkkEb hkkLEBkLkkhbFCbkhkbhbRRhkbbRbhkhbMKEkHE bbkkkbkk IN REGARD TO ITS SUITABILITY TO SUPPORT CLOSE OUT OF THE IS BEING EVALUATED. THE REPORT PRESENTS A STRONG CASE FOR ISSUE. A FAIRLY COMPREHENSIVE REVIEW INDICATES THAT IT MAY CLOSING OUT THE ISSUE WITHOUT ANY ACTION ON THE PART OF BE SUITABLE. BUT FURTHER STUDY IS REQUIRED. A FEW MINOR LICENSEES. IF THAT CASE IS SUPPORTED. A MUCH MORE ADDITIONS RELATING TO COMPLETENESS OF REPORTING VS.
SIMPLE AND EFFICIENT CLOSE00T MAY BE POSSIBLE.
COMPLETENESS OF THE ANALYSES HAVE BEEN IDENTIFIED, AND AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~~---~~--------------------------------------
--~~~~~~--------_-------------------------------~~----------
AT THE CONTRACTOR'S SUGGESTION. WE ADOPTED A TOP DOWN PRA ASME OM CODE.
SYSTEM IMPORTANCE-BASED APPROACH TO IDENTIFYING IMPORTANT SYSTEMS AND IMPORTANT SRV*S IN IMPORTANT SYSTEMS RATHER AS OF FY96 OUARTER 4 O
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21 ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY AFFECTED DOCUMENTS PROBLEM / RESOLUTION
--.----------~~ - ------------------------------------------
~~~----------------------
ORIGINALLY PLANNED. THE RESULT APPEARS TO BE SOMEWHAT BROADER IN SCOPE THAN ORIGINALLY PLANNED. COVERING MORE SYSTEMS AND MORE PLANTS. HOWE VER. THE APPROACH STILL NEEDS TO BE CAREFULLY EVALUATED TO EMSURE THAT IT ACCOMPLISHES THE ORIGINAL OBJECTIVES AND THAT A COMPLETE AND FULLY SUPPORTED NUREG CAN BE ISSUED AS THE BASIS FOR CLOSING OUT THE GENERIC ISSUE. THE SCHEDULE FOR TASK 4 REFLECTS THE PREPARATION OF THE ADDITIONAL CONTRACTOR REPORT BUT ANTICIPATES SHORTER INTERVALS FOR REVIEW AND APPROVAL FOR A MORE SIMPLE RESOLUTION THAN ORIGINALLY PLANNED. THIS HAS -
RESULTED IN A PROJECTED SCHEDULE SLIP IN THE FIRSE FEW MONTHS BUT. SINCE WE ANTICIPATE THAT THE ISSUE CAN BE CLOSED 00T ON THE BASIS THAT NO INCREASE IN CDF RESULTS FROM FAILURES OF THE TYPES OF SRV*S IN QUESTION, AND FURTHER.
THAT MANY OF THE REMAINING STEPS WILL BE SHORTENED OR g
ELIMINATED. WE ARE CONFIDENT THAT THE CLOSEOUT DATE OF JUNE 199B CAN BE MAINTAINED.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
~~.-----------------------------------
y GSI 165 ASSIGNED TO RES/DSIR/EIB 11/93 11/93 DRAFT TAP TO DSIR DEPUTY DIRECTOR 04/94 04/94 DRAFT TAP APPROVED BY DSIR DIRECTOR AND 06/94 04 /94 FORWARDED TO OTHER RES DIVISION DIRECTORS.
AE00. AND NRR FOR COMMENT INCGRPORATE COMMENTS IN TAP 08/94 10/94 FINAL TAP APPROVED BY DSIR DIRECTOR 11/94 12/94 SUBTASK 1.1 - SELECT PLANTS 12/94 12/94 l
SUBTASK 1.2 - REVIEW P&ID'S 02/95 02/95 SUBTASK 1.3 - REVIEW OPERATING EXPERIENCE 02/95 03/95 t
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22 ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY ORIGINAL CURRENT ACTUAL M1LEST0NES DATE DATE DATE SUBTASK 1.4 - PERFORM FAILURE ANALYSIS 05/95 08/95 TASK 2 - PERFORM RISK ANALYSIS 08/95 07/96 REVISE TAP 02/97 02/97 TASK 4 - FINAL CONTRACTOR REPORT 12/95 04/97 TASK 5 - PROPOSE ISSUE RESOLUTION 02/96 04/97 T ASK 6 - TRANSMITTAL OF "FOR COMMENT" 04/96 04/97 RESOLUTION PACKAGE TO DET OIRECTOR FOR CONCURRENCE TASK 7 - NRR INTERFACE WITH LICENSEES AND 04/96 04/97 g
INDUSTRY GROUPS TASK 8 - NRR COORDINATION PLAN 04/96 04/97 TASK 9 - AE00 COORDINATION PLAN 04/96 04/97 TASK IO-TRANSMITTAL OF "FOR COMMENT" RESOLU-05/96 04/97 TION PACKAGE TO OTHER NRC OFFICES FOR CONCUR-RENCE (INCL. LICENSE RENEWAL CONSIDERATION)
TASK 11 - TRANSMITTAL OF "FOR COMMENT" 08/96 04/97 RESOLUTION PACKAGES TO CRGR AND ACRS TASK 12 - ISSUANCE PACKAGE TO CRGR AND ACRS 11/96 07/97 FOR PUBLIC COMMENTS TASK 13_- END OF PUBLIC COMMENTS 02/97 09/97 TASK 14 - PREPARATION OF FINAL RESOLUTION 05/97 10/97 PACKAGE TASK 15 - TRANSMITTAL OF FINAL RESOLUTION 06/97 11/97 PACKAGE TO DET DIRECTOR FOR CONCURRENCE TASK 16 - TRANSMITTAL OF FINAL RESOLUTION 10/97 01/98 PACKAGE TO OTHER NRC OFFICES FOR CONCURRENCE AS OF FY96 QUARTER 4 O
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23 t
i ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY l
r ORIGINAL CURRENT ACTUAL HILEST0NES DATE DATE DAIE TASK 17 - TRANSMITTAL OF FINAL RESOLUTION 12/97 02/98 PACKAGE TO CRGR AND ACRS i
TASK 18 - ISSUANCE OF FINAL RESOLUTION 02/98 04/98 PACKAGE TO NRR I
TASK 19 - NRR ISSUANCE OF FINAL REQUIREMENTS 05/98 06/98 i
TO LICENSEES TASK 20 - ISSUE CLOSEOUT MEMO 06/98 06/98 t
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24 ISSUE NUMBER: 166 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY:
TASK MANAGER: K.
SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: NR RESOLUTION DALE:
TAC NUMBERS: M86344 WORK AUTHORIZATION: hPRIL I, 1993. MEMORANDUM FROM T. MURLEY TO J.
$NIEZEK FIN C0hTRACTOR CONTRACT TITLE J2081 INEL TECHNICAL ASSISTANCE IN SUPPORT OF THE FATIGUE ACTION PLAN W0Ri SC0PE kVkthkhk hkh[bbk bkQUEbh bh bPkk hkNb PLkN bbkPbhkNh5 h
hhkRkkbkkEbhbR kkkbLbkkbNhkLLkhbLbbEbbbkkbkhIkkbkbh ACCORDANCE WITH 5/5/94 MEMORANDUM TO THE NRR DIRECTOR FROM A LICENSE RENEWAL PERIOD OF 20 YEARS.
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STATUS hh[bbkIbh[bhPL k khEPf bhkhkhkkS kkk bbhPLkhk hbR EhVfRbkhkNhkL kkhkbbE b hk kbR kkhEbbkb Pkkkbb bh
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OPERATING REACTORS DURING LICENSED OPERATIHG LIFE.
STAFF OPERATION. WILL BE THE FOCUS OF STAFF ACTIVITIES FOR ACTIVITIES AND CONCLUSIONS ARE DESCRIBED IN SECY-95-245 RESOLUTION OF GI-166.
ISSUE TRANSFERRED FROM NR2 TO RES ON ISSUED ON SEPTEMBER 25, 1995. FATIGUE ASSESSMENT OF 06/03/96. RES IS CARRYING OUT THE RESIDUAL WORK UNDER A NEW COMPONENTS IN OPERATING FACILITIES USING LATEST AVAILABLE GENERIC ISSUE GI-190 (MEMO FROM RES TO NRR 08/26/96).
PROBLEM / RESOLUTION AFFECTED DOCUMENTS NONE.
NUREG/CR-6260 ORIGINAL CURRENT ACTUAL MILEST0NE$
DATE DATE DATE h[kkhh((hkhbhkhbkhbbkhRhfPkRkbbkbh bhkh3 bh)h3 ~
12/93 12/93 PROGRAMMATIC REVIEW AS OF FY96 QUARTER 4 O
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25 ISSUE NUMBER: I66 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IhFbRh bbhh hh bh PER[bbfC, 6 Mbh bS b4bk bhhb4 DATA COLLECTION AND ANALYSIS 05/94 07/94 RISK ASSESSMENT 03/94 09/94 TECHNICAL ISSUES 05/94 01/95 COMPLETION OF ACTIVITIES FOR OP. LIFE 06/94 09/95 CLOSEOUT MEMO TO EDO 11/96 11/96
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AS OF FY96 QUARTER 4 s
RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
26 ISSUE NUMBER: 168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY:
TASK MANAGER: G. HUBBARD OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M85648 RESOLUTION DATE:
WORK AUTHORIZATION: APRIL 1.
1993. MEMORANDUM FROM T. MURLEY TO J. SNIEZEK FIN CONTRACTOR CONTRACT TITLE A2336 ANL RISK IMPACT OF EQ E2097 SCIENTECH EQ FOR OPERATING REACTORS W6169 BNL EQ RESEARCH PROGRAM W0RK SC0PE 5$ kb bkhHkk[ kkVfkh$ Ekb kVILb hk bPkRkh[kG kkPkkkkkCk kkkbbfAkkbhkhHkQkbhbkk$
~~~ ~~~~~~~~~
DAIA AND EQUIPHENT REPLACEMENT SCHEDULES FOR NUCLEAR POWER IN ACCORDANCE WITH THE 5/5/94 HEMORANDUM TO THE PLANTS TO PROVIDE INSIGHT AS TO WHERE NRC SHOULD FOCUS ITS NRR DIRECTOR FROM THE RES DIRECTOR. RESOLUTION WILL INCLUDE RESOURCES IN THE PERFORMANCE OF EQ AGING REVIEWS.
CONSIDERATION OF A LICENSE RENEWAL PERIOD OF 20 YEARS.
2.
TO PERFORM A DETAILED ASSESSMENT OF THE RISK
$TATUS bkfA5LkbhfEhbh[kkbkMEh[bhkbkbi-k6bbkkBkkkPkEPkkkbkbk kbMBkkbFbkRkkblVkbkhkbkkhkhHkkkhkkbbPkbkPLkkkkb THE COMMISSION AND SHOULD BE ISSUED SHORTLY. THE LAST RESEARCH FROM 19 TO 7 AS A RESULT OF A PUBLIC MEETING HELD UPDATE REPORT WAS ISSUED AUGUST 22. 1996.
THE DRAFT PROGRAM TO DISCUSS THE FINDINGS FROM THE LITERATURE REVIEW.
REVIEW REPORT ISSUED IN APRIL 1996 IS CURRENTLY UNDER PLANNED RESEARCH TO INVESTIGATE UNCERTAINTIES WITH MANAGEMENT REVIEW. FOR DATA COLLECTION AND ANALYSIS. THE ACCELERATED AGING AND TO REVIEW PROMISING CABLE CONDITION REVIEW OF EQ-RELATED PUBLISHED DOCUMENTS AND INDUSTRY MONITORING HETHODS BEGAN IN MAY 1996. WYLE LABOP.ATORY WAS REPORTS. REVIEW OF EQUIPMENT FAILURES ASSOCIATED WITH THE SELECTED TO PERFORM AGING AND LOSS-OF-COOLANT ACCIDENT ACCIDENT AT THREE MILE ISLAND. AND THE DEVELOPMENT OF AN TESTING. THERMAL PREAGING OF THE FIRST TEST CABLES IS INTEGRATED DATABASE OF EQ TEST REPORTS. RESEARCH TESTS. AND SCHEDULED TO BEGIN IN NOVEMBER 1996.
RESULTS FROM THE OTHER TEST ACTIVITIES ARE COMPLETED. A DRAFT FINAL REPORT PLANNED RESEARCH PROGRAM ARE EXPECTED IN FISCAL YEARS 1997 ON EQ RISK ISSUES ISSUED IN APRIL 1996 IS CURRENTLY UNDER AND 1998. OVER THE NEXT SEVERAL MONTHS. SPLB WILL WORK TO MANAGEMENT REVIEW.
THE STATUS REVIEW CONTINUES TO REFINE CLOSE OUT CERTAIN ITEMS IN THE EQ-TAP AND TRANSFER THE THE SCOPE OF THE PLANNED RESEARCH. THE STAFF MAY REDUCE THE REMAINING OPEN ITEMS TO RES FOR RESOLUTION.
AS OF FY96 QUARTER 4 O
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27 ISSUE NUMBER: 168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT AFFECTED DOCUMENTS PROBLEM / RESOLUTION
[5~gj.~5i~Ihh~h5.'35$~~ '~~ '~~~'~'~ ~ ~ ~~
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ORIGINAL CURRENT ACTUAL MILEST0NES.
DATE DATE DATE kkFbRhCbkhkhhkbh bb/bb bb/bh ~
OATA COLLECTION AND ANALYSIS 08/94 04/96 STATUS REVIEW 02/95 12/96 RISK ASSESSMENT 10/94 01/97 PROGRAMMATIC REVIEW 06/94 01/97
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TECHNICAL ISSUES 10/94 10/98 OPTIONS FOR RESOLUTION IMPLEMENTATION AS OF FY96 QUARTER 4
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28 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL IDENTIFICATION DATE: 01/95C PRIORITIZATION DATE: 01/95C TYPE: GSI PRIORITY:
TASK MANAGER: R. MEYER OFFICE / DIVISION / BRANCH: RES /DSR /PSB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M91256 RESOLUTION DATE:
WORK AUTHORIZATION: MEMO TO COMMISSIONERS FROM J. TAYLOR ON 11/9/94 " REACTIVITY TRANSIENTS AND FUEL DAMAGE CRIERIA FOR HIGH BURNUP FUEL" FIN CONTRACTOR CONTRACT TITLE W6194 INEL FUEL ROD BEHAVIOR CODE IMPROVEMENTS W6200 PNL DATA REVIEW AND MODEL DEVELOPMENT FOR HIGH BURNUP FUEL W6382 BNL ANALYSIS OF REACTIVITY TRANSIENTS W6483 ANL CLADDING METALLURGY OF HIGH BURNUP FUEL W6497 CEA CABRI HIGH BURNUP FUEL TEST (COOPERATIVE PROGRAM, FRANCE)
W6500 RRC IGR HIGH BURNUP FUEL TEST (COOPERATIVE PROGRAM, RUSSIA)
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WDRK SC0PE
. ---.....-..._-------_--_--___-~_----_--------------_.-------__.---------_ --------------. ___ -_-_ --... --___.-_--_--_---
AFTER A PRELIMINARY SAFETY ASSESSMENT WAS PERFORMED, AN WITH INDUSTRY WOULD BE SCHEDULED TO DISCUSS THEIR PLANNED ACTION PLAN WAS DEVELOPED TO INCLUDE A USER NEED LETTER TO ACTIONS AND TO SOLICIT COOPERATION WITH THE SAFETY EVALUA-RES AND THE ISSUANCE OF CONTRACTS TO ASSESS ALL ASPECTS OF TIONS. BASED ON A COMPLETE REVIEW OF ALL AVAILABLE FUEL THE HIGH BURNUP FUEL ISSUE. CONCURRENTLY. MEETINGS WOULD BE TRANSIENT DATA RELEVANT TO DESIGN BASIS EVENTS. NRR/RES SCHEDULED WITH THE NONDOMESTIC EXPERIMENTERS AND REGULATORY WOULD DEFINE ACCEPTANCE CRITERIA. ESTABLISH A SCHEDULE FOR AUTHORITIES TO DISCUSS THE EXPERIMENTAL DATA AND TO ASSESS FINAL ASSESSMENT. AND STATE NEED FOR FURTHER REGULATORY POTENTIAL CONSEQUENCES AND REGULATORY ACTIONS. MEETINGS ACTION.
STATUS kEbkkkbkbbMM[ifkEH((f[kbbkikkSkEbhbFkEhbbkhkkbhbR kbPPbkkikbEHkkkkPbSkhibkikkkPEbhkb[kJbkkI~~kkkkk PROGRAMS WAS HELD IW 04/96. AN NEI LETTER. SUMMARIZING THE DOCUMENTS WILL BE REVIEWED TO PREPARE THE NRR RESPONSE.
INDUSTRY POSITION. WA5 RECEIVED. AND THE EPRI REPORT AFFECTED DOCUMENTS PROBLEM / RESOLUTION kkbbLkhbRhbbibE{*jj'
~
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THk kki b4 h6 khkk kh PbbiTibk P Pkk [kbfb kkk kb FURTHER INDUSTRY ACTION, BASED ON LOW SAFETY SIGNIFICANCE P SECTION 4*2 AND LOW PROBABILITY OF OCCURRENCE. THE RES EVALUATIONS TO O CFR 50.46 AS OF FY96 QUARTER 4 O
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29 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 94-64 DATE, PRESENTED AT THE ACRS MEETING, INDICATE THAT THE CURRENT DATA BASE CANNOT BE CORRELATED TO A DESIGN BASED CRITERIA AND THAT CONCLUSIVE EXPERIMENTAL DATA WILL NOT BE AVAILABLE FOR SEVERAL YEARS. EVEN WITH SUBSTANTIAL INDUSTRY AND/OR RES SUPPDRT.
MRR MAY HAVE TO DEVELOP AN INTERIM POSITION BASED ON CRITERIA TO BE GAINED FROM LEAD TEST ASSEMBLY SURVEILLANCE PROGRAMS. MEETINGS WITH ABB/CE AND APS WERE HELD IN 04/96 TO DISCUSS SHORT TERM PLANNING. AN FCF Ti?ICAL REPORT ON EXTENDED BURNUP DESIGN CRITERIA IS CURRENTLY t!NDER EVALUATION AND FCF PLANS TO SUPPORT RIA ANALYSES WITH 30 TRANSIENT MODELING.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
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ISSUE USER NEED LETTER TO RES 10/93 10/93 CONTRACTS ISSUED BY RES 03/94 03/94 ISSUE INFORMATION NOTICE (IN 94-64) 08/94 08/94 ANNOUNCING NEW RIA DATA PRESENT HIGH BURNUP DATA AT WATER REACTOR 10/94 10/94 SAFETY MEETING SCHEDULE / COORDINATE INDUSTRY MEETINGS TO 10/94 10/94 DISCUSS ACTIONS DETERMINE NEED FOR FURTHER GENERIC 11/94 11/94 COMMUNICATIONS ISSUE LETTER TO VENDORS 11/94 11/94 ISSUE IDENTIFIED FOR DOCUMENTATION IN 01/95 01/95 NUREG-0933 ISSUE IN 94-64 SUPPL.
1, PROVIDING DATA 03/9 5 03/95 AND VENDOR LETTER AS OF FY96 QUARTER 4
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30 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE CSNI SPECIALISTS MEETING 09/95 09/95 REYIEW INDUSTRY (NEI) RESPONSE 09/9 5 09/95 ASSESS EFFECTS ON DESIGN BASIS ACCIDENTS 09/95 09/95 OF REDUCED FAILURE THRESHOLD FOR HIGH BURNUP FUEL COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLA-09/9 5 09/95 TIONS SPECIALISTS MEETING ON THE TRANSIENT BEHAVIOR OF HIGH BURNUP FUEL WATER REACTOR SAFETY INFORMATION MEETING ON 10/95 10/95 HIGH BURNUP g
CNRA (DECD) COMMITTEE ON NUCLEAR REGULATORY 11/95 11/95 ACTIVITIES AND CSNI ANNUAL MEETINGS ACRS BRIEFING BY RES 04/96 04/96 CORE PERFORMANCE ISSUES WORKSHOP 10/96 10/96 ESTABLISH SCHEDULE FOR LOCA RESOLUTION AND 09/96 10/96 FINAL ASSESSMENT - DETERMINE NEED FOR FURTHER REGULATORY ACTION ISSUE LETTER TO NEI ASSESSING INDUSTRY 09/9 6 11/96 ACTIONS COMPLETE REVIEW OF AVAILABLE FUEL TRANSIENT 12/96 12/96 DATA RELEVANT TO DESIGN BASIS EVENT DEVELOP INTERIM ACCEPTANCE CRITERIA 12/96 12/96 RES COMPLETES RESPONSE TO NRR USER NEED 09/96 02/97 LETTERS ISSUE GL TO DEFINE INTERIM CRITERIA AND 02/97 02/97 REQUEST POST-LOCA EVALUATION AS OF FY96 QUARTER 4 O
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3I ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL i
DRIGINAL CURRENT ACTUAL MILEST0MES DATE DATE DATE 8
JOINT EPRI PAPER BY MRC, JAPAN, FRANCE, AND 06/97 06/97 RUSSIA CLOSEOUT MEMO TO THE EDO 5
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32 ISSUE NUMBER: 171 TITLE: ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA IDENTIFICATION DATE: 02/95C PRIORITIZATION DATE: 06/95C TYPE: GSI PRIORITY: H TASK MANAGER: A.
SERKIZ OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 06/97 WORK AUTHORIZATION: MEMORANDUM TO L. SHA0 FROM D. MORRISON ON JUNE 16, 1995 FIN CONTRACTOR CONTRACT TITLE W6617 BNL EVALUATION OF SAFETY ISSUE 171 PRIORITIZATION ASSUMPTIONS WORK SC0PE INITIAL SAFETY ISSUE EVALUATIONS RESULTED IN RANKING THE PRIMARY OBJECTIVE OF THIS BNL STUDY IS TO REVIEW AND GSI 171 AS "HIGH."
THIS EVALUATION WAS BASED ON CONSERVA-EVALUATE ASSUMP!!ONS RELATED TO THE PROBABILITY OF NON-TIVE ASSUMPTIONS REGARDING FAILURE RATES. EQUIPMENT DAMAGE RECOVERABLE D# MAGE TO EDG'S AND ECCS PUMPS USED IN THE ANg NONRECOVERY FROM POTENTIAL OVER-CURRENT LOAD EFFECTS.
INITIAL ISSUt PRIORITIZATION.
STATUS Bkl k EVILbAfibh bh Gki-kh PRkbR[h5ZEkibh SSbMPhkbkk [S kPEb[F[bbE5[bhhER[kBkLkkhbh[LkbiRibkLPRbhkbhkVE CONTINUING. EFFORT TO DATE SHOWS THAT CERTAIN ASSUMPTIONS DEVICES AND LOGIC CIRCUITS PREVENTS ARRIVING AT A GENERIC IN THE INITIAL PRIORITIZATION WERE OVERLY CONSERVATIVE.
CONCLUSION DUE TO A LACK OF ALL-INCLUSIVE PLANT SPECIFIC HOWEVER, A REVIEW OF IPE SUBMITTALS HAS SHOWN THAT GSI-171 INFORMATION.
BNL*S CONCLUDING EFFORT WILL BE DIRECTED AT ACCIDENT SCENARIOS HAVE NOT BEEN MODELED AND REESTIMATES OF MODELING THE LOCA/ LOOP SCENARIO USING THE IRRAS CODE FOR A INITIATING EVENT (S) FREQUENCY DO NOT PLACE T3*$ SAFETY ISSUE BWR AND PWR REFERENCE PLANT WHICH WILL BE USED TO SUPPORT INTO A LESS THAN HIGH RANKING.
IN ADDITION, Te?E PLANT ISSUE RESOLUTION ACTION.
AFFECTED DOCUMENTS PROBLEH/ RESOLUTION
~~~--~~~____....__....---_-_----.----------.---------
IN 93-17*
OBTAINING PLANT SPECIFIC INFORMATION ON PROTECTIVE DEVICE FEATURES CONTINUES TO BE A PROBLEM. SINCE THE ISSUE DOES NOT APPEAR AMENABLE TO REDUCING THE RANKING BELOW HIGH (GIVEN CURRENT PLANT INSIGHTS), NRR IS CONSIDERING ISSUANCE OF A GENERIC LETTER REQUESTING LICENSEE CONFIRMATION THAT THE PLANT HAS BEEN DESIGNED TO HANDLE THE LOCA/ LOOP OR LOOP /LOCA SCENARIOS IDENTIFIED BY GSI-171.
AS OF FY96 QUARTER 4 O
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33 ISSUE NUMBER: 171 TITLE: ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSUE TASK ACTION PLAN 12/95 12/95 INITIATE INDEPENDENT EVALUATION 01/96 02/96 BNL TASK 1 RESULTS 03/96 07/96 BNL TASK 2 RESULTS 04/9 6 07/96 BNL TASK 3 (REVISED) RESULTS 09/9 6 10/96 BNL TASK 3.1 09/9 6 10/96 BNL TASK 3,2 10/96 10/96 BNL TASK 3.3 11/96 11/96 I-UPDATED SAFETY EVALUATION (DRAFT) 09/9 6 12/96 REEVALUATION OF SAFETY ISSUE 11/96 12/96 CRGR AND ACRS REVIEWS (IF NEEDED) 12/96 02/97 CONCLUDING REVISIONS AND ACTIONS 02/97 03/S7 PROCESS REQUIRED ACTIONS 04/97 06/97 CLOSE-0UT MEMO TO THE EDO 06/97 06/97 O
AS OF FY96 0UARTER 4 L
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34 ISSUE NUMBER: 172 TITLE: MULTIPLE SYSTEM RESPONSES PROGRAM IDENTIFICATION DATE: 07/91C PRIORITIZATION DATE: 12/9SC TYPE: GSI PRIORITY:
TASK MANAGER: M. CUNNINGHAM OFFICE / DIVISION / BRANCH: RES /DSR /PRA8 ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE: 12/98 WORK AUTHORIZATION: MEMORANDUM TO D. MORRISON FROM L. SMAO DATED AUGUST 2. 1995 FIN CONTRACTOR CONTRACT TITLE
<p--------_------_----------.------------
VORK SC0PE PRAB WILL PREPARE A REPORT ON MOW 11 MSRP ISSUES WERE ADDRESSED BY LICENSEES IN IPE/IPEEE PROCESS.
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STATUS
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DISCUSSED STAFF PROPOSED TREATMENT OF MSRP ISSUES AT 427TM TO THE 06/03/96 ACRS LETTER.
ACRS MEETING ON 12/07/95. THE STAFF IS PREPARING A RESPONSE AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~~-----~~-----------------------------------------------
NUREG/CR-5420 NONE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE EDO RESPONSE TO ACRS 6/3/96 LETTER 07/96 11/96 COLLECT DATA AND PREPARE
SUMMARY
REPORT 12/98 12/98 TO ACRS CLOSE OUT ISSUE WITH MEMORANDUM TO EDO 12/98 12/98 AS OF FY96 QUARTER 4 O
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173,A TITLE: SPENT FUEL STORAGE POOL: OPERATING FACILITIES IDENTIFICATION DATE: 02/96C PRIORIT!ZATION DATE: 06/96C TYPE: GSI PRIORITY:
TASK MANAGER:
S. JONES OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M88094 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE 1
7 I
WORK SCOPE SPECIFIC ACTIONS INCLUDED IN PART A 0F THE GENERIC ACTIONS 10 ADDRESS SIGNIFICANT ISSUES AT OPERATING AND ACTION PLAN ARE: (1) DETERMINATION OF THE SAFETY PERMANENTLY SHUTDOWN FACILITIES. BASED ON FINDINGS FROM SI IDENTIFIED CONCERNS. (2) DETERMINATION THESE REVIEW AREAS AND THEIR RISK SIGNIFICANCE. THE STAFF 0F(NIFICANCE OFTHE FACILITIES WHERE THE CONCERNS MAY BE APPLICABLE.
WILL DEVELOP CRITERIA FOR SPECIFIC SPENT FUEL POOL l
EVALUATION OF THE ADEQUACY OF PRESENT SFP DESIGNS, OPERATIONS FOR POTENTIAL USE IN FORMULATING GENERIC EVALUATION OF THE ADEQUACY OF CURRENT NRC GUIDANCE FOR COMMUNICATIONS, REVISIONS OF REGULATORY GUIDANCE, AND DESIGNS, AND (S) EVALUATION OF THE NEED FOR GENERIC OTHER APPROPRIATE REGULATORY ACTIONS.
t STATUS THE ACTION PLAN IS CLOSED. TASKS FOR RESOLUTION WILL
- 2) CONDUCT PLANT SPECIFIC REGULATORY ANALYS!$ FOR BE TRACKED SEPARATELY. RESOLUTION COMPRISED OF THREE PARTS:
HARDWARE BACKFITS AT SELECTED SITES:
- 1) CONDUCT REGULATORY ANALYSIS TO EVALUATE JUSTIFICATION -
- 3) UPDATE REGULATORY GUIDANCE.
FOR IMPOSING FUEL STORAGE POOL OPERATIONS RULE:
AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 93-83 AND SUPPLEMENT 1 NONE IN 94-38 ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE AS OF FY96 00ARTER 4 l
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36 ISSUE NUMBER:
173.A TITLE: SPENT FUEL STORAGE POOL: OPERATING FACILITIES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE REVIEW EXISTING NRC GUIDANCE AND 08/94 08/94 REQUIREHiNTS IDENTIIY SIGNIFICANT SFP CONCERNS 12/94 12/94 REPORT SIGNIFICANT SFP PROBLEMS TO NRR 12/94 12/94 MANAGEMENT DEVELOP AN SFP INSPECTION PLAN 01/95 01/95 CONDUCT INSPECTIONS OF SELECTED PLANTS 06/95 06/95 EVALUATE AND REPORT RESULTS OF INSPECTIONS 09/9 5 09/95 COMMISSION BRIEFING ON SFP ISSUES 02/96 02/SS
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COMMISSION BRIEFING ON SFP ISSUES 04/96 04/96 ASSESS RISK / SIGNIFICANCE OF INDIVIDUAL 06/96 07/96 CONCERNS ASSESS MONITORING OF POTENTIAL OFFSITE 06/96 07/96 RELEASES ASSESS RADIQACTIVE MATERIAL STORAGE 06/96 07/96 PRACTICES PROPOSED COURSE OF ACTION SUBMITTED TO 06/96 07/96 COMMISSION COMMISSION HEETING FOR RESOLUTION 08/96 08/96 ACRS HEETING 08/96 08/96 FLANT-SPECIFIC REG. ANALYSIS FOR HARDWARE 05/97 05/97 BACKFITS AT SELECTED SITES REVISE R.G.
1.13 10/98 10/98 REVISE SRP 9.1.2. 9.1.3 10/98 10/98 AS OF FY96 QUARTER 4 O
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37 ISSUE NUMBER:
173.B TITLE: SPENT FUEL STORAGE POOL: PERMANENTLY SHUTDOWN FACILITIES IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: GSI PRIORITY:
TASK MANAGER: S. JONES OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M40004 M90441 M93B05 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE SPECIFIC ACTIONS INCLUDED IN PART B 0F THE GENERIC AND IMPLEMENTATION OF ADDITIONAL REQUIREMENTS SPECIFICALLY ACTION PLAN ARE: (I) THE DETERMINATION OF SIGNIFICANT APPLICABLE TO PERMANENTLY SHUT DOWN FACILITIES WITH IDENTIFIED CONCERNS FROM PART A APPLICABLE TO STORED, IRRADIATED FUEL.
PE M NENTLY SHUTDOWN FACILITIES,%ND (2) THE EVALUATION
$TATUS THE STAFF DETERMINED THAT ALL SIGNIFICANT IDENTIFIED WITH ISSUANCE OF THEIR DECOMMISSIONING ACTION PLAN.
THE CONCERNS FROM PART A APPLICABLE TO PERMANENTLY SHUTDOWN OlVISION OF SYSTEMS SAFETY AND ANALYSIS WILL PROVIDE FACILITIES WERE ENCOMPASSED BY THE SPECIAL INSPECTION TECHNICAL SUPPORT FOR THAT ACTION PLAN AND OTHER EXISTING ACTIVITIES. THE SPECIAL INSPECTIONS FOUND NO SIGNIFICANT ACTION PLANS ASSOCIATED WITH RULEMAKING FOR DECOMMISSIONING DEFICIENCIES OTHER THAN AT DRESDEN 1.
IN RESPONSE TO THE FACILITIES. STAFF RESOURCES WILL BE TRACKED THRDUGH DRESDEN 1 SPECIAL INSPECTION FINDINGS, PDND WILL PROCEED TACS ASSIGNED TO THE ASSOCIATED ACTION PLANS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION BULLETIN 94-01 ORIGINAL CURRENT ACTUAL MILE $T0NES DATE DATE DATE AS OF FY96 QUARTER 4
RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
38 ISSUE NUMBER:
173.8 TITLE: SPENT FUEL STORAGE POOL: PERMANENTLY SHUTDOWN FACILITIES ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE IDENTIFY SIGNIFICANT SFP CONCERNS 11/95 11/95 APPLICABLE TO PERHANENTLY SHUT-DOWN FACILITIES DECISION ON RULE OR OTHER GENERIC 09/9 6 09/96 ACTIVITY CLOSE OUT ISSUE 09/9 6 l
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39 ISSUE NUMBER: 178 TITLE: EFFECT OF HURRICANE ANDREW ON TURKEY POINT i
IDENTIFICATION DATE: 02/96C PRIORITIZATIDN DATE: 06/96C TYPE: LI PRIDRITY:
TASK MANAGER: R. CROTEAU DFFICE/ DIVISION / BRANCH: NRR /DRPE/PD23 ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M86716 M86717 RESOLUTION DATE: 11/96 WORK AUTHORIZATION: MEMD FROM T. MURLEY TO J. TAYLOR ON JULY 22, 1993 FIN CONTRACTOR CONTRACT TITLE i
t l
t W0RK SC0PE kTkMPbkRkkhkkkhbkkbhHkkBEkkbEhElbPEbkbkkkSPEbkbRh kkbkk$ WkRE kh LbkkEb Tb bkTkkMkkE kF bbkbkkkE kb
~"
TO REVIEW LICENSEE OFFSITE COMMUNICATION CIRCUITS DURING LICENSEES. IN THE FDRM OF GENERIC COMMUNICATION. IS EMERGENCY PREPAREDNESS INSPECTIONS SCHEDULED AT POWER NECESSARY TO PROVIDE EITHER SURVIVABILITY OR RAPID REACTOR FACILITIES BETWEEN FEBRUARY AND JUNE 1996.
DATA RECOVERABILITY DF THESE CIRCUITS FROM A SEVERE NATURAL COLLECTED FROM THOSE INSPECTIONS. AS WELL AS PAST INSPEC-EVENT.
STATUS (ITEM 1) A TEMPORARY INSTRUCTION (TI 2515/131)
THE TI HAS BEEN PERFORMED AT SEVENTEEN PLANTS FRDM 02/01/96 ISSUED 01/18/96 IhCORPORATING REGIONAL COMMENTS HAS BEEN THRDUGH 06/30/96.
i WRITTEN TO PROVIDE REGIONAL INSPECTDRS GUIDANCE FOR (ITEM 2) THE ACTION TO PROVIDE GUIDANCE FDR INSPECTORS COLLECTING INFORMATION ON OFFSITE NOTIFICATION CIRCUITS.
HAS BEEN INCORPORATED INTO THE PRA IMPLEMENTATION PLAN.
l AFFECTED DOCUMENTS PRDBLEM/ RESOLUTION NUREG 1474 TWO NEGATIVE FINDINGS WERE IDENTIFIED AS A RESULT OF THE T!l$j53 IN TI.
THESE WILL BE COVERED IN AN INFO NOTICE TO BE SENT TO 5/131 ALL REACTOR LICENSEES.
ALSO. A CHANGE IS BEING MADE TO THE i
INSPECTION PROCEDURE B2701.
DRIGINAL CURRENT ACTUAL MILEST0NES DATE
, DATE DATE
~~
AS OF FY96 QUARTER 4 i
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RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
40 ISSUE NUMBER: 178 TITLE: EFFECT OF HURRICANE ANDREW ON TURKEY POINT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE EVkL THE kbkQbkbh bbhRb GbkbkNbk FbR RkhfEY-bShb6 bS/b6 ING LICENSEE PREPARATION & RESPONSE TO NATUR-AL DISASTERS & INDUSTRY PREPLANNED SUPPORT COLLECT INFORMATION ON LICENSEE COMMUNICATION 07/96 06/96 CAPABILITIES AND VULNERABILITIES VIA REGION INSPECTION ANALYZE INSPECTION FINDINGS AND REPORT ON 10/96 08/96 RESULTS ESTABLISHED SCHEDULE FOR ISSUANCE OF GENERIC 11/96 10/96 CORRESPONDENCE (IF NECESSARY)
EVALUATE THE ADEQUACY OF LICENSEE OFFSITE 01/97 11/96 g
COMMUNICATIONS FOR NATURAL DISASTERS WITHIN THE PLANT DESIGN BASIS 11/96 11/96 CLOSE OUT ISSUE AS OF FY96 QUARTER 4 9
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4I ISSUE NUMBER: 179 TITLE: CORE PERFORMANCE I
IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: LI PRIORITY:
TASK MANAGER: E. KENORICK OFFICE / DIVISION / BRANCH: NRR /DSSA/SRXB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91257 M91602 RESOLUTION DATE: 12/97 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE bhbh9 Pkt bbkEPEkkbkkkbEEVkLbkhkbk(kbkkbhPLkkkbPPbkh)
~~~~
TBD TO BE DETE TO BE DETERMINED 1
WDRK SC0PE
~~~'kPkbikib bhkbkk [kb[bbkb [k bE kbhkbk PE k kkE
~
~bkkk5~hkk~EbfibkPLIk[bEkhikIESbkkbkkbk[~LichkS[k
(1) EVALUATE FUEL VENDORS PERFORMANCE THRDUGH PERFORMANCE-INSPECTIONS IN EACH REGION THAT SHALL BE PERFORMED, IN BAS (D INSPECTIONS THAT EVALUATE THE RELOAD CORE DESIGN, CODRDINATION WITH THE REGIONAL INSPECTORS. TO ASSESS SAFETY ANALYSIS, AND LICENSING PROCESS, FUEL ASSEM3LY LICENSEE PERFORMANCE IN RELOAD CDRE ANALYSIS OVERSIGHT AND MECHANICAL DESIGN, AND FUEL FABRICATION ACTIVITIES, PARTICIPATION. LICENSEE INSPECTIONS WILL NDRMALLY BE ISSUE-(2) EVALUATE THE PERFORMANCE OF LICENSEES THAT PERFORM CORE DRIVEN BUT A TOTAL OF 10 INSPECTIONS IS BUDGETED FOR FY97 RELDAD ANAIYSIS FUNCTIONS, (3) IDENTIFY, DOCUMENT, AND THE DAIA ACQUIRED THROUGH LICENSEE /VENDDR INSPECTIONS WILL' CATEGORIZE CORE PERFORMANCE PROBLEMS AND ROOT CAUSE BE INTEGRATED WITH INFORMATION SUPPLIED BY THE REGIONS AND l
EVALUATIONS THAT WILL BE FURTHER EVALUATED DURING THESE OTHER SOURCES AND WILL BE EVALUATED FOR GENERIC CORE INSPECTIONS, PROVIDE INPUT TO SALP EVALUATIONS AS WELL AS PERFDRMANCE INDICATORS AND INDUSTRY CONFORMANCE TO CURRENT REGIONAL ENFORCEMENT ACTIONS AS APPROPRIATE, (4) TRAIN AND REGULATORY REQUIREMENTS. THE END PRDOUCT OF THE OVERALL COORDINATE REGIONAL SUPPORT STAFF PARTICIPATING IN THESE ASSESSMENT WILL INCLUDE GUIDANCE FOR RESIDENT INSPECTORS AND ACTIVITIES AND (5) EVALUATE THE RESULTS OF THESE ACTIVITIES REGIONAL STAFF. THESE ACTIVITIES ARE SCHEDULED TO BE FOR USE IN FORMULATING GENERIC CDMMUNICATIONS, REVISIONS OF COMPLETED IN FY '97.
THE ONGOING ACTIVITIES TO CAPTURE AND REGULATORY GUIDANCE AND GUIDANCE FOR REGIONAL INSPECTDRS.
ADDRESS EARLY WARNING OF EMERGING ISSUES WILL CONTINUE INTO AND OTHER APPROPRIATE REGULATORY ACTIONS.
IN ADDITION, AS FY '97, AND THE ACTION PLAN WILL BE UPDATED TO REFLECT A RESULT OF RECENT GENERIC CONCERNS. INCLUDING THE FAILURE THE LIVING PLAN.
OF CONTROL RODS TO FULLY INSERT. THE ACTION PLAN IS BEING DISP - THE ACTION PLAN IDENTIFIES 10 VENDOR INSPECTIONS EXTENDED THROUGH 1997 AND EXPANDED TO REVIEW THE ADEQUACY OF THAT SHALL BE PERFORMED BY MULTI-DISCIPLINED INSPECTION VENDOR LEAD TESTING PROGRAMS FOR NEW FUEL DESIGNS (TASK 6)
TEAMS LED BY THE SPECIAL INSPECTION BRANCH (PSIB) WITH AND TO CONDUCT A WORKSHOP ON CORE PERFORMANCE ISSUES CONTRACTED TECHNICAL ASSISTANCE. THESE INSPECTIONS WILL (TASK 7) IN THE FALL OF 1996.
BE COMPLETED IN 1997.
STATUS
~~~~bkkk~2~hkkbkTIkhobik[bkkbhTkhbkhbfkb Nb[bEkkkFfbhkbkbFEkEkbikbikkbkk5~~k'[kkb[5bRfVh
~~~
VENDOR INSPECTIONS ARE BEING EVALUATED FOR GENERIC IMPACT VENDOR INSPECTION AT GE WAS CONDUCTED IN MAY 1996, SUPPORTED AS OF FY96 QUARTER 4
l l
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42 ISSUE NUMBER: 119 TITLE: CORE PERFORMANCE STATUS.------ ----------------------_----_---------------_---_----
_ -_--_-_--__-------------- -----~~------------------------ PRESENTED TO THE EDO IN SEPTEMBER 1996.
SRXB/DSSA STAFF AND CONTRACT SPECIALISTS IN RELOAD BY DESIGN.
INTERACTION WITH THE REGIONS IS ONGOING TO GENERATE DISP - THE INSPECTION OF FRAMATOME COGEMA FUELS A LICENSEE INSPECTION SCHEDULE. HOWEVER. DUE TO DIVERSION (FORMERLY BABCOCK AND WILCOX FUEL COMPANY) LOCATED IN OF RESOURCES TO REVIEW LEAD TEST ASSEMBLY PROGRAMS. IT LYNCHBURG, VIRGINIA, OCCURRED IN MARCH AND APRIL 1996.
15 UNLIKELY THAT LICENSEE INSPECTIONS IN EACH REGION CAN BE THE REMAINING PLANNED ISSUE-DRIVEN INSPECTIONS INCLUDE ABB SUPPORTED UNTIL FY
'97.
SRXS PARTICIPATED IN THE REGION I COMBUSTION ENGINEERING'S SUPPLY OF A 8WR TRANSITION CORE INSPECTOR COUNTERPARTS HEETINGS IN DECEMBER 1995 AND MAY RELOAD FOR WNP-2 AND A COMPREHENSIVE FOLLOWUP INSPECTION OF 1996.
DSSA IS REEVALUATING THE ACTION PLAN TO BETTER SIEMENS POWER CORPORATION ISSUES.ELOAD FOR WNP-2 AND INTEGRATE AND PRIORITIZE ITS ACTIVITIES. OPTIONS AND A COMPREHENSIVE FOLLOWUP INSPECTION OF SIEMENS POWER RECOMMENDATIONS WERE PROVIDED FOR MANAGEMENT REVIEW AND WERE CORPORATION ISSUES.
PROBLEM / RESOLUTION AFFECTED DOCUMENTS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE INSPECT SPC (PWR AIT FOLLOWUP) 06/94 06/94 INSPECT ZION RELOAD ANALYSIS 10/94 10/94 INSPECT ABB/CE (PWR RELuADS) 11/94 11/94 INSPECT TELEDYNE-WAH CHANG (TWC) 12/94 12/94 INSPECT SANDVIK SPECIALTY METALS (SSM) 12/94 12/94 INSPECT DUKE Rela ? ANALYSIS 03/95 03/95 INSPECT WESTINGh
>E 07/95 07/95 10/95 10/95 INSPECT GE INSPECT TMI-l RELOAD ANALYSIS 12/95 12/95 IDENTIFY ISSUES FOR CORE PERFORMANCE 06/96 06/96 WORKSHOP AS OF FY96 00ARTER 4 O
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43 I
ISSUE NUMBER: 179 TITLE: CORE PERFORMANCE
[
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE r
INSPECT GE (SLMCPR & LOW DENSITY PELLETS) 07/96 07/96 1
INSPECT FRAMATOME/COGEMA (B&W FUELS) 08/9 6 10/96 CONDUCT CORE PERFDRMANCE WORKSHOP 10/96 10/96 f
COMPRERENSIVE REINSPECTION OF SPC 02/97 02/97 t
INSPECT ABB/CE BWR (WNP-2 TRANSITION CORE) 10/96 05/97 t
COMPLETE CORE PERFORMANCE EVALUATION 12/96 09/9 7 ANALYSIS t
EVALUATE LEAD TEST PROGRAMS FOR 12/96 09/9 7
}
IDENTIFICATION OF CORE PERFDRMANCE PROBLEMS
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EVALUATE INSPECTION GUIDANCE-12/96 59/97 t
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44 ISSUE NUMBER:
IB*
TITLE: FIRE PROTECTION IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: LI PRIORITY:
TASK MANAGER: D. OUDINOT OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M86652 M82809 M84592 M85142 M89509 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE
------------------------------------------------~~-----------------------------------------------------_------
THE FP-TAP TRACKS THE IMPLEMENTATION OF A WIDE RANGE OF WITH EMPHASIS ON THE FIRE PROTECTION FUNCTIONAL INSPECTION TECHNICAL AND PROGRAMMATIC FIRE PROTECTION ISSUES. IT (FPFI) PROGRAM AND CENTRALIZING THE MANAGEMENT. BY NRR. OF INCLUDES RECOMMENDATIONS FOR ACTION (PART !). RECOMMENDA-THE FPFI PROGRAM AND ALL OTHER REACTOR FIRE PROTECTION TIORS FOR FURTHER STUDY (PART II). CONFIRMATION ISSUES WORK.
THE PRINCIPAL OBJECTIVE OF THESE EFFORTS IS TO ENSURE (PART III). AND LESSONS LEARNED (PART IV).
THE STAFF IS THAT THE NRC HAS A STRONG. BROAD-BASED AND COHERENT FIRE lMPL EMENTING THE RECOMMENDATIONS. IN PRIORITY ORDER. AS PROTECTION PROGRAM WHICH IS COMMENSURATE WITH THE SAFETY RESOURCES ALLOW.
THE STAFF FOCUS IS NOW ON IMPLEMENTING ITS SIGNIFICANCE OF THE SUBJECT.
PLAN FOR FUTURE DIRECTION OF THE NRC FIRE PROTECTION PROGRAM STATUS
hhk kh kk bbhPLkIEb bbkhkbk L kk LL Sb Lk kirk kkkkk khkkbV5SbkhbbkkkikkkbkkkEbibk'kkkkGbIkbk'( bRk)bk
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5 OF FIRE BARRIER MATERIALS OTHER THAN THERMO-LAG AT NIST.
FEBRUARY 29. 1996.
BY' LETTER OF MARCH 15 1996. THE ACRS THE TEST RESULTS WERE PROVIDED BY NIST IN ITS REPORT OF SUBMITTED ITS COMMENTS TO 'HE COMMISSION. THE STAFF TEST FR 4008 " PILOT-SCALE FIRE-ENDURANCE TESTS OF FIRE RESPONDED TO THE ACRS BY LETTER OF APRIL 25. 1996. THE BARRIER PANELS AND PANEL / BLANKET COMBINATIONS." DATED STAFF IS ASSES $1NG THE RECOMMENDATIONS MADE BY THE ACRS AND AUGUST 20. 1996.
THE STAFF
- S REVIEW OF THE REPORT OF TEST HAS REFERRED THESE COMMENTS TO THE PRA REVIEW COMMITTEE FOR FR 4008 IS ONGOING.
FURTHER CONSIDERATION.
THE PLANT SYSTEMS BRANCH (SPLB) CONTINUED TO WORK WITH IN SECY-96-134. THE STAFF STATED THAT. AS PART OF THE PROBABILISTIC RISK ASSESSMENT (PRA) BRANCH STAFF AND RULEMAKING. IT WOULD REVIEW OPERATING EXPERIENCE AND WOULD BROOKHAVEN NATIONAL LABORATGRY (BNL). ITS TECHNICAL ADDRESS A VARIETY OF FIRE SAFETY ISSUES. CONSISTENT WITH ASSISTANCE CONTRACTOR. TO EVALUATE THE RISK ASSOCIATED WITH THIS COMMITMENT. THE STAFF MAS INCLUDED ITS REiiEW OF TWO THE POST-FIRE SAFE-SHUTDOWN METHODOLOGY THAT IMPOSES A SELF-REMAINING ISSUES FOR FURTHER STUDY. ADEQUACY OF OPERABILITY INDUCED STATION BLACKOUT. THE STAFF PLANS TO APPLY THE PRA REQUIREMENTS FOR POST-FIRE SAFE SHUTDOWN EQUIPMENT AND MODEL FOR ASSESSING THE RISK SIGNIFICANCE OF THE SELF-ADEQUACY OF FIRE BARRIER SURVEILLANCE REQUIREMENTS. AND THE INDUCE 0 STATION BLACKOUT METHODOLOGY TO TWO PLANT-SPECIFIC REMAINING CONFIRMATION ISSUES IN ITS PLAN FOR THE FIRE CASES DURING FY '97.
THE STAFF AND BNL DISCUSSED THE PROTECTION RULEMAKING.
PRELIMINARY RESULTS OF THIS STUDY AND FUTURE PLANS WITH SCIENTECH AND BNL ARE PROVIDING TECHNICAL ASSISTANCE AS OF FY96 QUARTER 4 O
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45 ISSUE NUMBER: 181 TITLE: FIRE PROTECTION STATUS kbRbkVktbPkkbhkkkhkEPkbkkbkkbkkbhbkkbkkL[kkPkbkkbh kkk 4 kPkk PkLbh khkPkbkkbkk$ hbb kkkkk~PLkkk kb Bbb k kkk (FPFI) PROCEDURES. SCIENTECH AND BNL SUBMITTED THE FIRST PILOT INSPECTIONS NO LATER THAN THE FIRST QUARTER OF ORAFT OF THEIR WORK PRODUCT ON SEPTEMBER 6 AND SEPTEMBER 16, CALENDAR YEAR 1997.
RESFCCTIVELY. THE STAFF IS PREPARING A SECY PAPER TO INFORM THE DEVELOPMENT OF A FIRE PROTECTION TRAINING PROGRAM THE CD.NISSION OF THE DETAILS OF THE FPFI PROGRAM AND TO IS ON HOLD UNTIL THE FPFI PROGRAM IS IMPLEMEMIED.
PROV!DE S'AFF PLANS FOR IMPLEMENTING THE PROGRAM. THE STAFF THE STAFF ISSUED THE SEMIANNUAL REPORT TO THE COMMISSION HAS SELECTfD 12 CANDIDATE PILOT PLANTS (3 PER REGION). THE ON THE STATUS OF THE FP-TAP DN OCTOBER 31. 1996.
THE NEXT STAFF IS CORRENTLY WORKING WITH THE REGIONAL OFFICES TO STATUS REPORT IS DUE APRIL 1997.
r SELECT 4 FINAL CANDIDATES (1 PER REGION) AND TO SCHEDULE t
F AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG/CR-6224 NONE.
BULLETIN 95-02 IN 95-47, REVISION 1 IN 93-34 AND SUPPLEMENT I BULLETIN 93-02 AND SUPPLEMENT 1
[
IN 92-85 IN 92-71 IN 88-28 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE l
TAP APPROVED 02/93 02/93 I
OTHER ISSUES (PART IV) 08/9 5 08/95 SEMIANNUAL COMMISSION STATUS REPORT 04/96 04/96 SEMIANNUAL COMMISSION' STATUS REPORT 10/96 10/96 RECOMMENDATIONS FOR FUTURE STUDY (PART II) 05/97 10/96 l
CONFIRMATION ISSUES 05/97 10/96 RECOMMENDATIONS FOR ACTION (PART !)
01/97 01/97 AS OF FY96 QUARTER 4 l
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46 ISSUE NUMBER: 181 TITLE: FIRE PROTECTION i
ORIGINAL CURRENT ACTUAL I
MILEST0NES DATE DATE DATE SEMIANNUAL COMMISSION STATUS REPORT 04/97 04/97 l
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ISSUE NUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: RI PRIORITY:
TASK MANAGER: T. J. KIM OFFICE /DIVISIOM/ BRANCH: NRR /DRPW/PD31 ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91571 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE SPECIFIC ACTIONS INCLUDED IN THE GENERIC ACTION PLAN
(
REVIEW THE LEAD PLANT APPLICATION AND ISSUE A SAFETY ARE: (1) REVIEW ELTRI AND ISSUE A STAFF POSITION PAPER.
E LUATION REPORT. AND (4) DEVELOP A STANDARD REVIEW (2)gREVIEW ELTR2 AND ISSUE A SAFETY EVALUATION REPORT.
PROCEDURE BASED ON ELTRt. ELTR2. AND THE LEAD PLANT REVIEW.
(
STATUS
~~~'khEkTkkkPbkkkkbhPEPkkbhkhkhhRkXkkhbEbPbhkk khkhbh bk khk Pbbkk bPkkkk Pkbbkkh$ bk kkkbh kb['[bhh['bk" 1
UPRATE PROGRAM WAS ISSUED ON FEBRUARY 8, 1996 (COMPLETION SUBMITTED ELTR2. THE GENERIC BOUNDING ANALYSES SUPPORTING OF MILESTONE 2).
THE STAFF ALSO MET WITH GE AND THE THE EXTENDED POWER UPRATE PROGRAM. THE STAFF REVIEW OF i
INTERESTED BWR UTILITIES ON FEBRUARY 14 1996. TO DISCUSS ELTR2 IS ONGOING. THE LEAD PLANT APPLICATION FROM i
THE CONTENT S OF THE STAFF POSITION PAPER AND THE OVERALL MONTICELLO IS NOW EXPECTED IN JUNE 1996.
r AFFECTED DOCUMENTS PROBLEM / RESOLUTION EEbb5b242k bkhkRkb bbkbELkEE5 Fbk bE BhR kkkEbbEb PbhEk EbkE$
UPDATE i
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GE TOPICAL ELTR1 SUBMITTED 03/9 5 03/95 AS OF FY96 QUARTER 4 L
F
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48 ISSUE NUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE ORIGINAL CURRENT ACTUAL MILE $T0NES DATE DATE DATE
~~~-----------------------.------------------
MEETING WITH GE/NSP 04/95 04/95 IDENTIFY DIFFERENCES BETWEEN LTR1 AND ELTR1 08/95 08/95 ISSUE RAl*S AS APPROPRIATE 09/95 09/95 INCORPORATE INFORMATION ON FOREIGN 10/95 10/95 EXPERIENCE OBTAINED FROM SRXB OEVELOP POWER UPRATE DATABASE FOR ALL 10/95 10/95 U.S. PLANTS ISSUE STAFF POSITION PAPER 02/96 02/96 MEETING WITH GE/ INDUSTRY 02/96 02/96
\\
RECEIVE ELTR2 PARTS 1 & 2 06/96 06/96 RECEIVE LEAD PLANT APPLICATION 06/96 06/96 MEETING WITH MONTICELLO 06/96 06/96 ISSUE SECY INFORMATION PAPER 07/96 07/96 ISSUE RAl*S ON GE ELTR2 ACTIONS 10/96 10/96 RAl*5 INPUT ON ON LEAD PLANT SE FROM TECH 11/96 11/96 BRANCHES ISSUE RAI*S ON LEAD PLANT SE AS APPROPRIATE 11/96 11/96 INPUT TO THE SE ON ELTR2 FROM TECHNICAL 02/97 02/97 BRANCHES ISSUE SE ON ELTR2 04/97 04/97 ACRS PRESENTATION ON ELTR2 04/97 04/97 INPUT TO THE LEAD PLANT SE FROM TECH 06/97 06/97 BRANCHES AS OF FY96 QUARTER 4 O
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GENERIC. ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
49 i
ISSUE NUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED F0WER UPRATE i
)
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ORIGINAL CURRENT ACTUAL t
MILEST0NES DATE DATE DATE ISSUE LEAD PLANT SE 06/97 06/97 4
DEVELOP A STANDARD REVIEW PROCEDURE AND 06/97 06/97
~i INCORPORATE LESSONS LEARMED FROM LEAD PLANT l
ACTIVITY CLOSE OUT ISSUE t
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50 ISSUE NUMBER: 183 TITLE: CYCLE-SPECIFIC PARAMETER LIMITS IN TS IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: RI PRIORITY:
TASK MANAGER: L. KOPP OFFICE / DIVISION / BRANCH: NRR /DSSA/SRXB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M89033 M85023 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE W0RK
$C0PE PREPARE A SUPPLEMENT TO GL 83-11 WHICH PRESENTS BY COMPLYING WITH THESE CRITERIA. THE LICENSEE WOULD CRITERI A INTENDED FOR LICENSEES WHO WISH TO PERFORM THEIR ELIMINATE THE NEED TO SUBMIT A TOPICAL REPORT QUALIFYING OWN LICENSING ANALYSES USING PREVIOUSLY APPROVED METHODS.
ITS USE OF A PREVIOUSLY APPROVED METHODOLOGY.
\\
$TATUS
_--------------- --------_--------------------~~----------------------------------------------------------------
THE PROPOSED SUPPLEMENT TO GL 83-11 WAS PUBLISHED DECEMBER II, 1995.
ISSUANCE OF THE SUPPLEMENT HAS BEEN FOR PUBLIC COMMENT IN THE FEDERAL REGISTER ON CANCELLED AS PER FEDERAL REGISTER NOTICE OF OCTOBER 25. 1995.
THE COMMENT PERIOD EXPIRED OCTOBER 30, 1996.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION GL 88-16 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbkTkkbibkkEPbkTkEbkIVEbbNkELbkb b6h94 5
~~bhhhk'~~
REPORT CONTENT COMPLETE DRAFT GUIDANCE FOR GL 88-16 REVISION 08/94 08/94 AS OF F Y96 QUARTER 4 O
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. GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
51 4
ISSUE NUMBER: 183 TITLE: CYCLE-SPECIFIC PARAMETER LIMITS IN TS' i
i ORIGINAL CURRENT ACTUAL' I
MILEST0NES DATE DATE DATE CbhPLEhEbRkkhbbbkkCkbhbbkhENTSbh Obhhk bbhbk'
{
RELOAD PACKAGE (REGULATORY GUIDE) AND GL 83-11 REVISION r
OFFICE CONCURRENCES ON GL 83-11 REVISION 09/95 09/95 l
PUBLISH PROPOSED GL 83-11 REVISION FOR 10/95 10/95 i
PUBLIC COMMENT RECEIVE PUBLIC COMMENTS ON GL 83-11 12/95 12/95 REVISION CANCELLATION OF GL 83-11 REVISION 10/96 10/96 i
CLOSE OUT ISSUE l
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52 ISSUE NUMBER: 184 TITLE: ENDANGERED SPECIES IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: El PRIORITY:
TASK MANAGER: J. WILSON OFFICE / DIVISION / BRANCH: NRR /DRPHAPGEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M88282 RESOLUTION DATE:
WORK AUTHORIZATION: COMMISSION HEMORANDUM DATED JULY 30 1991 FIN CONTRACTOR CONTRACT TITLE WORK SC0PE bbhbbbkkVkLbkkkbbsbhPLkhkSPkbkFkbL5SkSbFEhbkhbEkEb khFbRkLbRFbRkkLbbkSbLhkkbhWkkHkkhHkRkHbhkkkbbkl SPECIES AND E)? STING LICENSEE COMMITHENTS TO FURTHER THE HARINE FISHERIES SERVICE OR THE FISH AND WILDLIFE SERVICE CONSERVATION Of THE PROTECTED SPECIES AND DETERMINE IF 15 WARRANTED.
\\
STATUS
_----_-------------------------------------------ITH RESPECT TO SEPARATING GENERIC AND PLANT-SPECIFIC A LIST OF CURRENTLY LISTED PROTECTED SPECIES IN THE W
VICINITY OF EACH NUCLEAR POWER PLANT SITE WAS DEVELOPED BY ASPECTS AS PART OF HILESTONE 4.
A REPORT IS EXPECTED IN A CONTRACTOR AND DELIVERED TO NRC ON 04/25/96. THIS REPORT NOVEMBER THAT PRIORITIZES SITES AND RECOMMENDATIONS FOR IS NOW UNDER REVIEW. THIS ACTION PLAN WILL BE EVALUATED FOLLOWUP ACTIONS.
AFFECTED DOCUHENTS PROBLEH/ RESOLUTION
~~-----------------------------------------------------
ORIGINAL CURRENT ACTUAL MiLEST0NE$
DATE DATE DATE
'b'hb5 b[VELbPkbkkbhPLkh b6b5 S
DEVELOP LIST OF CURRENTLY LISTED PROTECTED 11/95 11/95 SPECIES IN THE VICINITY OF EACH NUCLEAR POWER PLANT SITE AS OF FY96 QUARTER 4 9
9 9
. _. ~.. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
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ORIGINAL CURRENT ACTUAL
_____..____f...b.--...bb-___......._--
- b. _
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IDENTIFY INDIVIDUAL LICENSEE PRDGRAMS AND 05/96 05/96 i
ACTIVITIES BEING CONDUCTED TO FURTHER THE CONSERVATION OF PROTECTED SPECIES i
DETERMINE PRIORITY FOR SITES WARRANTING 06/96' 11/96 FOLLOWUP ACTIONS t
RECOMMEND SITE-SPECIFIC FOLLOWUP ACTIONS TO 12/96 12/96 PROJECTS i
DEVELOPMENT AND IMPLEMENTATIDN OF PROCESS FOR 03/97 04/97 MAINTAINING STATUS AND COMPLIANCE WITH THE ESA AT EACH SITE
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54 ISSUE NUMBER: 190 TITLE: FATIGUE EVALUATION OF METAL COMFONENTS FOR 60-YEAR PLANT LIFE IDENTIFICATION DATE: 08/96C PRIORITIZATION DATE: 08/9E TYPE: GSI PRIORITY:
TASK MANAGER:
K.
SHAUKAT OFFICE / DIVISION /GRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 12/97 WORK AUTHORIZATION: MEMO TO A.
THADANI FROM T. SPEIS ON 08/26/96. "GSI-166.
' ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS *"
FIN CONTRACTOR CONTRACT TITLE bbbhk PhL kkkkbbk khkLkhkh bF kkLkbkkb bbkPbkkkkh Fbk~bb5kkkk PLkkk LkFk
~
VORK
$C0PE khILbIkkkIkkbbkkbkObkbhbFbPEkkkkkbPLkhkbbkPbkkhhh FRbkkkkkk$bkkkbhbR[kkhbtbk[bE'h[LLkkbtbbk~bbkk[b[kkf{bh
~
~
IN ACCORDANCE WITH 05/05/94 MEMORANDUM TO THE NRR DIRECTOR OF A 60-YEAR PROJECTED PLANT LIFE.
g STATUS FkkkGbb khkLksks bk bbkPbhkhkk FbR 6b kk k PLkhk LkFk kh bk hk khb kHE kkhkbbIL UbkK bk~bk2kkb'h LL hk bkkRkkb~bk~
~
UNDERWAY.
THIS WORK COMPLETES THE ONGOING VORK UNDER UNDER THIS GENERIC ISSUE.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION TO ALLOW TIME TO RESPOND TO NRC STAFF COMMENTS ON DRAFT FINAL REPORT.
ORIGINAL CURRENT ACTUAL MILEST0NE$
DATE DATE DATE kkhbkbkkkbhkbkhkkbLkkhhkhGhk bbh9b bbhh6 EXTEND THE RES RISK STUDY OF FATIGUE 09/96 11/96 FAILURE FROM 40 TO 60-YEAR PLANT LIFE AS OF FY96 QUARTER 4 O
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55 ISSUE NUMBER: 190 TITLE: FATIGUE EVALUATION OF METAL CDMPONENTS FOR 60-YEAR PLANT LIFE i
r DRIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bEvktbPkkkkhhPbk[TfbhhPkkFbkLfbkhkk bk/hh b5/h7 2'~~~~
4 i
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MEET WITH CRGR ON LICENSE RENEWAL RECOMMENDA-03/97 03/97
[
TION IN THE STAFF POSITION MEET WITH ACRS ON LICENSE RENEWAL RECOMMENDA-05/97 05/97 I
TION IN THE STAFF POSITION i
RESOLUTION PLAN FDR LICENSE RENEWAL 09/97 09/97 CLOSE DUT MEMO TO EDO 12/97 12/97 l
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56 ISSUE NUMBER: 191 TITLE: ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE IDENTIFICATION DATE: 09/96C PRIORITIZATION DATE: 09/96C TYPE: GSI PRIORITY:
TASK MANAGER: M.
MARSHALL OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: NR RESOLUTION DATE:
TAC NUMBERS:
WORK AUTHORIZATION: MEMO TO D. MORRISON FROM W. RUSSELL. " THIRD SUPPLEMENTAL USER NEED REQUEST... ACCIDENT GENERATED DEBRIS " 12/07/95 FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE
--- - - -- - -- - - -- - - - -- -- - - --- ----------------------------- --------- D E BR I S B L OCKAGE OF P WR SUMP S W I L L B E R E AS S E S SE D T O IN LIGHT OF THE RESOLUTION (I.E.. NRC BULLETIN 96-03 AND REGULATORY GUIDE I.82. REV. 2) 0F THE CONCERN FOR THE DETERMINE IF THERE IS A NEED FOR FURTHER ACTIONS TO BE
" POTENTIAL FOR LOSS OF EMERGENCY COOLING IN BWR*S DUE TO TAKEN FOR PWR'S BEYOND THE ORIGINAL RESOLUTION OF USI A-43.
LOCA GENERATED DEBRIS" (I.E., THE BWR EMERGENCY CORE
" CONTAINMENT EMERGENCY SUMP PERFORMANCE."
COOLING SYSTEMS" SUCTION STRAINER BLOCKAGE).
5TATUS bEb bkk bh Sh Fk kkb bbkhkkbhbkL Rbhbbkbb LfHfk h[bkk) bkh[L kHk Fkkkh QUkkkkR bF Fh bh[
~ ~ '''''''''''''
THE ISSUANCE OF AN S0W FOR THIS REASSESSMENT WAS DELAYED AFFECTED DOCUMENTS PROBLEM / RESOLUTION AA k b k k AA*
b5kkbbL kbkh bbibE 55b25 Rkh 2 h NUREG-0800 l h GENERIC LETTER B5-22 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE NRR USER NEED REQUEST SENT TO RES 12/95 12/95 AS OF FY96 QUARTER 4 O
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57 ISSUE NUMBER: 191 TITLE: ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE USER NEED REQUEST ASSIGNED TO GSIB 01/96 01/96 REASSESSMENT DECLARED A NEW GSI 09/96 09/96 ISSUE S0W FOR REASSESSMENT 11/96 11/96 COMPLETE REASSESSMENT 04/97 04/97 ISSUE CLOSE-0UT MEMO TO EDO 1
AS OF FY96 QUARTER 4
RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
58
!SSUi NUMBER:
B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY: M TASK MANAGER: J. KRAMER OFFICE / DIVISION / BRANCH: RES /DSR /HFBR ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 06/97 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE b4b5 LLhl
[hhkbRhkbhbFbbkkhPkRFbRhkbhFkbhbRhFbLLhkkhbkbkRkLfkBkLkkh EVALUATION PROCESS (TASKS 5 AND 6)
W0RK
$C0PE khkhbhKkbbPkkhbLbbkk 5)bkVkLbPhfhkbkkkkkkbh kkNb L bPkk hbR kbhfbk bk kbhbkkkkb bhfbk[~ yhk'hbbp[~bh~~~
FOR SAFETY RELATED OPERATOR ACT ONS: (2) DETERMINE WHETHER THIS GENERIC ISSUE COVERS DESIGN BASIS ACCIDENTS OR EVENTS.
OR NOT AUTOMATIC ACTUATION WILL BE REQUIRED: AND (3) DEVELOP CRITERIA FOR SAFETY RELATED OPERATOR ACTIONS DURING SEVERE GUIDANCE AND REVIEW CRITERI A FOR LICENSEE PROPOSALS TO USE ACCIDENTS WILL BE COVERED UNDER THE SEVERE ACCIDENT PROGRAM.
STATUS THIS ISSUE WAS TRANSFERRED FROM NRR TO RES WITH THE 4/87 NRC WORK WAS COMPLETED BY NRR ON THIS ISSUE. WORK HAS BEGUN REORGANIZATION (4/10/87 MEMD FROM W. RUSSELL TO T. SPEIS).
WHICH SHOULD LEAD TO RESOLUTION OF THIS GSI BY ENDORSING NO WORK HAD BEEN COMPLETED ON THE ISSUE PRIOR TO TRANSFER.
ANSI /ANS 58.8.
THIS STANDARD IS BEING REVISED BASED ON NEW DURING 1983 AND 1984 RES WORKED ON THIS ISSUE. DURING INDUSTRY DATA.
LLNL BEGAN WORK TO MANAGE THE TECHNICAL THAT TIME DATA WERE COLLECTED BY RES CONCERNING OPERATOR EFFORT INVOLVING EPRI AND A SUBCONTRACTOR TO EPRI IN MARCH RESPONSE TIMES. ANSI /ANS 58.8 WAS PUBLISHED IN SEPTEMBER 1989.
1984.
THE GENERIC ISSUE WAS LATER TRANSFERRED TO NRR.
NO AFFECTED DOCUMENTS PROBLEH/ RESOLUTION
'-~~~~--- --------------------------------------------
TO BE PROVIDED LATER LAST TWO MILESTONES WERE REVISED TO INCLUDE TIME FOR COMPLIANCE WITH SBRFA LEGISLATION AS OGC IS NOT LIKELY TO GRANT GENERIC EXEMPTION ON FINAL REG. GUIDES.
ALSO.
ADDITIONAL PROPRIETARY DATA TO BE RECEIVED FROM WESTINGHOUSE WILL HAVE TO BE PROCESSED. EVALUATED, AND TRANSMITTED TO ACRS.
AS OF FY96 QUARTER 4 O
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59 ISSUE NUMBER:
8-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE MEET WITH ANSI /ANS 58.8 07/88 06/89 DEVELOP TAP 08/87 06/89 NUPPSCO SUBMITS DRAFT OF 58.9 04/92 04/92 COMPLETE DRAFT OF 58.8 08/92 08/92 NUPPSCO BALLOTS DRAFT STD 58.8 10/92 03/93.
DEVELOP REGULATORY GUIDE TO ENDORSE 03/94 03/94 AN S 58. 8 NUPPSCO ISSUES FINAL 58.8 08/93 08/94 g
ANSI /ANS 58.8 PUBLISHED 03/95 ISSUE DRAFT REG GUIDE FOR 60-DAY COMMENT 12/93 07/95 e
PERIOD l
REVISE REG GUIDE TO REFLECT PUBLIC COMMENTS 05/94 09/95 ACRS REVIEW 07/94 11/95 ISSUE FRN AND REVISED DRAFT REG GUIDE 03/96 11/96 DG-1052 FOR 60-DAY PUBLIC COMMENT PERIOD ISSUE REQUEST TO GSIB FOR REASSESSMENT DF 11/96 11/96 RISK ANALYSIS REVISE DG-1052 TO REFLECT PUBLIC COMMENTS 07/96 02/97 ACRS REVIEW 09/9 6 03/97 ISSUE FINAL REG GUIDE 09/94 06/97 CLOSE OUT ISSUE WITH MEMORANDUM TO EDO 09/94 06/97 i
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60 ISSUE NUMBER:
B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: M TASK MANAGER: G. HAMMER OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 08/97 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN. (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE kkhkkh Bhk bhkLkhh PPRbICHE5 Tb kEbREkkkhG kRh bbNFbkMkbhTbhkSkhkkbbkkhkTRUbhkbkk$'f2 RELIABILITY TO OBTAIN SUFFICIENT DATA BASE TO SUPPORT DEMONSTRATING SUFFICIENT RELIABILITY OF 2-5 AGE VALVES THE CONCLUSION THAT THIS ISSUE HAS BEEN RESOLVED, AFTER DESIGN AND/OR SYSTEM MODIFICATIONS, AND (3)
THR UTILITY APPROACHES MAY INCLUDE: (1) DEMONSTRATING USING DIFFERENT VALVES AND DEMONSTRATING THEIR SUFFICIENT RELIABILITY OF 3-STAGE VALVES BY STRICT RELIABILTY.
STATUS WHILE INITIAL PERFORMANCE WITH THE PH 13-8 MO REPLACE-SETPOINT TESTING.
HENT DISCS INDICATED AN IMPROVEMENT. ADDITIONAL PERFORMANCE SINCE MOST OF THE NRC STAFF EFFORT RELATED TO THE DATA MADE IT APPARENT THE NEW DISCS ARE NOT PROVIDING THE BALANCE OF THE GENERIC RESOLUTION OF THIS GENERIC IMPROVED PERFORMANCE THAT WAS ORIGINALLY EXPECTED. THE ISSUE WAS EXPECTED TO BE UNDERTAKEN WITHIN NRR, AND SINCE BWROG CONCLUDED THE PH 13-8 MO REPLACEMENT DISCS ARE NOT A ANY PLANT MODIFICATIONS RESULTING FROM THE RESOLUTION OF VIABLE SOLUTION FOR ELIMINATING SETPOINT DRIFT AND RECOM-THIS ISSUE WERE EXPECTED TO BE EITHER VOLUNTARY OR MENDED THEY NO LONGER BE INSTALLED TO RESOLVE THIS PROBLEM.
JUSTIFIED ON A " COMPLIANCE" BASIS. RES HAS FORMALLY BECAUSE CORROSION BONDING OF THE PILOT DISK TO ITS SEAT WAS TRANSFERRED THE ISSUE TO NRR FOR THE BALANCE OF THE GENERIC IDENTIFIED AS THE CAUSE OF THE UPWARD SETPOINT DRIFT THE RESOLUTION PERIOD AND SUBSEQUENT PLANT SPECIFIC IMPLEMENTA-BWROG THEN DEVELOPED A PLATINUM ALLOY PILOT DISK DESIGN.
TION.
THIS CATALYST DISK WAS VERY EFFECTIVE IN REDUCING OXYGEN THE STAFF MET WITH THE BWROG ON APRIL 24 1996 TO CONCENTRATION AT THE PILOT DISK SEAT LOCATION WHICH COULD DISCUSS THE PERFORMANCE OF THE CATALYTIC DISKS AND SEAT THEN REDUCE THE CORROSION BONDING. THE BWROG ALSO DEVELOPED LEAKAGE ISSUES. THE BWROG HAS DETERMINED THAT, BY AN EQUAL PARALLEL CONTINGENCY OPTION WHICH INVOLVES THE USE SPRING 1997 ENOUGH SETPOINT DATA SHOULD BE AVAILABLE TO OF PRESSURE SWITCHES SIMILAR TO THOSE USED ON BWR/6 PLANTS.
EVALUATE THE DISKS. THE BWROG IS ALSO DEVELOPING A LICENSING TOPICAL REPORT AND ADDITIONAL INFORMATION FOR RECOMMENDATIONS TO LESSEN LEAKAGE BY BETTER MONITORING AND THE PRESSURE SWITCH DESIGN WAS SUBMITTED WHICH NRR HAS MAINTENANCE, SINCE LEAKAGE MAY AFFECT THE SETPOINT RECENTLY APPROVED. SEVERAL OF THE CATALYTIC DISKS HAVE BEEN PERFORMANCE.
INSTALLED IN SEVERAL BWR*S ON A TRIAL BASIS FOR SUBSEQUENT AS OF FY96 QUARTER 4 O
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_.. ~ ~... ~.. - _ - _ _ _ - _ _ - _ - - _ _ _ - - - - _ - _ - - - - - - - _ - - - - - - _ _ - _ - - - - _ _ - _ - _ _ _ - - _ _ - _ - - _
J
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ISSUE NUMBER:
B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES i
L AFFECTED DOCUMENTS PRD8LEM/ RESOLUTION ORIGINAL CURRENT ACTUAL MILESTOMES DATE DATE DATE MEETING WITH BWR OWNERS SETPOINT DRIFT 12/83 11/83 COMMITTEE BWR OWNERS REPORT SUBMITTED 07/84 06/84 i
BOSTON EDISDN REPORT SUBMITTED 08/84 COMPLETION OF NRR EVALUATION DF OWNERS 10/84 10/84 GROUP AND BOSTON EDISON REPDRTS COMMUNICATION TO OG RE: NRC 03/85 COMMENTS / CONCERNS
?
OG PRESENTATION TO THE STAFF 10/85 10/85 t
i STAFF RECEIVES OWNERS
- PRDGRAM FDR 10/85 10/85 ELIMINATING SET POINT DRIFT OWNERS BEGIN TO INSTALL NEW PILOT DISKS 01/86 01/8s TO TEST IN PLANT FOR ONE FUEL CYCLE t
ISSUE STATUS REPORT ON INDUSTRY EFFDRTS 12/87 01/88 ISSUE PROGRESS REPORT ON INDUSTRY EFFORTS 11/88 11/88 BWROG APPROVAL FOR FUNDING CATALYST / PRESSURE 06/90 06/90 SWITCH PROGRAM BWROG SELECT / DESIGN CATALYST 03/91 02/91 1
NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 06/91 08/91 PROGRESS BWROG COMPLETES FINALIZING DESIGN AND 04/92 07/92 LABORATORY TESTING AS OF FY96 QUARTER 4 i
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62 ISSUE NUMBER:
B-SS TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE NRC STAFF ISSUE STATUS REPORT ON IMOUSTRY 03/92 08/92 PROGRESS REASSESS ISSUE 03/93 05/93 REASSIGN TO NRR 08/93 08/93 NRR RESPONSE TO REASSIGNMENT 10/93 10/93 BWROG SUBMIT TOPICAL REPORT TO NRC 12/91 04/94 DESCRIBING PRES $URE SWITCH OPTION OWNERS BEGIN TO INSTALL CATALYSTS TO TEST 06/94 04/94 IN PLANTS FOR FIRST FUEL CYCLE
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TRANSFER OF BALANCE OF GSI TO NRR 11/94 04/95 NRR ISSUE APPROVAL FOR PRESSURE SWITCH 02/95 10/95 OPTION ISSUE CLOSEOUT HEHORANDUM TO EDO 08/97 08/97 AS OF FY96 QUARTER 4 O
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63 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT GUTAGE PERIODS IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: M TASK MANAGER: A. BUSLIK OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 01/97 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE IN GENERAL. PLANTS WILL BE CLASSIFIED SUCH THAT OF SUPPORT SYSTEM OUTAGES MUST BE INCLUDED. DETAILS I
IN EACH CLASS SIMILAR ECCS OUTAGE UNAVAILABILITIES OF THE WORK SCOPE ARE CONTAINED IN THE DRAFT ACTION WILL HAVE SIMILAR IMPACTS ON RISK.
THE EFFECT OF A PLAN. BECAUSE CUMULATIVE DUTAGE TIMES ON COMPONENTS OTHER GIVEN ECCS AVAILABILITY ON RISK WILL BE DETERMINED.
THAN ECCS COMPONENTS APPEAR IMPORTANT. THE WORK SCOPE HAS FOR EACH CLASS OF PLANT. AS WELL AS THE IMPACTS OF ANY BEEN EXPANDED TO INCLUDE ALL SAFETY-RELATED COMPONENTS.
CHANGES IN ALLOWABLE ECCS OUTAGE PERIOD. CONSIDERATION t
I STATUS TASK I HAS BEEN COMPLETED. MEMO TO ACRS WITH PROPOSED DEPUTY DIRECTOR. DSR.
RESOLUTION WAS INITIATEG BY PRAB IN 09/96: MEMO IS WITH AFFECTED DOCUMENTS PRD8LEM/ RESOLUTION
~~~~~kkbhk[bLkPkbfFkbkk[bHbHkNGES kkPbskiblE$
khkkkhbkPkbbLkhkkkbbkkkEbhkkbkhkkEbbLbkkbhbkb55[k 6
REVISED INSPECTION GUIDANCE FOR VOLUNTARY ENTRY INTO AN ANALYSIS OF THE COSTS AND BENEFITS OF THE IMPOSITION OF LCO*5*
A CUMULATIVE OUTAGE REQUIREMENT. A STUDY OF THE NEED FOR CONTROL DF CUMULATIVE OUTAGE IS BEING PERFORMED IN-HOUSE.
THE WORK TAKES INTO ACCOUNT THE MAINTENANCE RULE AND THE NUMARC GUIDANCE FOR THE IMPLEMENTATION OF THE MAINTENANCE i
RULE. AS WELL AS CURRENT INSPECTION GUIDANCE ON VOLUNTARY i
ENTRY INTO LIMITED CONDITIONS OF OPERATION ACTION STATEMENTS TO PERFORM PREVENTIVE MAINTENANCE. AN INITIAL RECOMMENDA-TION FDR STAFF CDMMENTS WAS COMPLETED IN SEPTEMBER 1992:
i THIS INCLUDED A PROPOSED DRAFT TECHNICAL RESOLUTION.
AS OF FY96 QUARTER 4 i
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64 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT GUTAGE PERIOOS AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~~~-----------------
-------------. - T IS CLEAR THAT A CUMULAT MANAGEMENT IN AUGUST 1993 I
OUTAGE REQUIREMENT ON UNSCHEDULED MAINTENANCE WILL NOT BE IMPOSED. THE CURRENT PLAN IS TO ARGUE THAT EXISTING PROGRAMS (MAINTENANCE RULE, CURRENT INSPECTION GUIDELINES)
ARE SUFFICIENT TO CONTROL THE CUMULATIVE MAINTENANCE UNAVAILABILITY AND THAT THE "NO ACTION" ALTERNATIVE SHOULD BE SELECTED. MODIFICATIONS TO THE GUIDANCE FOR THE MAINTENANCE RULE TO EMPHASIZE THE RISK IMPLICATIONS OF PERFORMING SCHEDULED MAINTENANCE ON RISK-SIGNIFICANT COMPONENTS DURING POVER OPERATION APPEAR DESIRABLE. A MEMORANDUM FROM RES TO NRR SUGGESTING THAT B-61 BE RESOLVED THROUGH THE MAINTENANCE RULE, BY MODIFYING THE INSPECTION GUIDANCE FOR THE MAINTENANCE RULE, HAS BEEN SENT.
THIS MEMORANDUM INDICATED THAT, SINCE THE IPE'S HAVE NOT INDICATED ANY VULNERABILITIES WITH RESPECT TO ONLINE MAINTENANCE OF COMPONENTS. IF THE INSPECTION GUIDANCE FOR
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THE MAINTENANCE RULE REQUIRED THAT THE ASSUMPTIONS MADE IN THE PLANT IPE WITH RESPECT TO ONLINE MAINTENANCE WERE VERIFIED AS VALID. THEN THIS WOULD SATISFY THE INTENT OF B-61.
HOWEVER. NRR REPLIED THAT SUCH A MODIFICATION OF THE INSPECTION GUIDANCE WAS NOT APPROPRIATE.
DISCUSSIONS WITHIN RES ON THE APPROPRIATE COURSE OF ACTION ARE TAKING PLACE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bRkhT hkP [SSUEb kbR bb PPRbV L b1h84 S
0[hk4 ~
COMPLETE COORDINATION OF TECHNICAL RESOLUTION 04/84 08/84 WITH RES TAP APPROVED BY DIVISION DIRECTOR 05/84 07/84 TASK I-METHODOLOGY REVIEW AND 11/84 04/g5 DEVELOPMENT COMPLETED TASK II-APPLY TO A PWR OR BWR 02/85 02/92 AS OF FY96 00ARTER 4 O
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B-61 TITLE: ALLOWABLE ECCS EQUIPMENT DUTAGE PERIODS
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ORIGINAL CURRENT ACTUAL M I L E.S T O N E S DATE DATE DATE
'bEVELbPkk~kkkikkLkkCbkkkkbki5bkFbkSkhk Obhbh 2-
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~~~
COMMENTS APPLY METHODOLOGY TO A SELECTION OF PLANTS 08/8 5 09/92-PREPARE DRAFT DTR 04/86 04/94 DRAFT RESOLUTION 02/95 06/96 I
~
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66 ISSUE NUMBER: HF S.2 TITLE: REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
IDENTIFICATION DATE: 08/83C PRIORITIZATION DATE: 10/84C TYPE: G s!
PRIORITY: H TASK MANAGER: J. WACHTEL OFFICE / DIVISION / BRANCH: RES /DSR /HFBR ACTION LEVEL: ACTIVE STATUS: 38 TAC NUMBERS:
RESOLUTION DATE: 06/93C WORK AUTHORIZATION: MEMO TO H.
THOMPSON FROM H.
DENTON DATED 10/1/84
" HUMAN FACTORS PROGRAM PLAN" FIN CONTRACTOR CONTRACT TITLE A3967 BNL ANNUNCIATORS W0RK
$C0PE kh[kkkkbhbbhbkhkkkHkkkkbbkFRbHkHkHbMkhFkbibRS USkbFkhFbRMkhkbhFRbbbbkhRbLBbkkbkNhbNbkkhbRh kHk PR$ GRAM PLAN OF SECTION 1.5.2 RESULTS FROM A PRA ESTABLISHED THE MAGNITUDE OF THE RISK FAL COMPUTER AND COMPUTER DISPLAYS INVOLVED AND THE POTENTIAL REDUCTION IN RISK EXPECTED. A J h EVALUATION OF OPERATOR AID SYSTEMS VALUE/ IMPACT ANALYSIS WAS COMPLETED AND ESTIMATED THE COST J h ANNUNCIATORS OF POTENTIAL MODIFICATIONS TO ANNUNCIATORS.
I ) SAFETY STATUS INDICATION AND APPLICATIONS OF AUTO-THE RESULTS OF THE VALUE/ IMPACT ANALYSIS REQUIRE THAT MATION AND ARTIFICIAL INTELLIGENCE.
ADDITIONAL EXPERIMENTAL WORK ON ANNUNCIATOR UPGRADES BE A MANAGEMENT REVIEW OF THESE ISSUES RESULTED IN A CONDUCTED ON A TTC SIMULATOR TO RESOLVE THE ANNUNCIATOR DECISION TO RETAIN ONLY THE ANNUNCIATOR ISSUE AS A GENERIC ISSUE.
IN EVALUATING ALARM REDUCTION TECHNIQUES. WE ALSO ISSUE.
THIS DECISION ALSO CONCLUDED THAT THE REMAINING PLAN TO USE THE RESEARCH RESULTS ON ADVANCED ALARM SYSTEMS ISSUES BE REASSIGNED AS RESEARCH ISSUES. A RESEARCH CONDUCTED AT THE HALDEN PROJECT. THE RESULTS FROM THIS PROJECT ENTITLED " REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS EFFORT WILL DEVELOP GUIDELINES ON COMPUTER-BASED ANNUNCIATOR OF ADVANCED CONTROL AND INSTRUMENTAION." FIN B0852 SYSTEMS. THESE GUIDELINES WILL SERVE AS THE BASIS FOR A ADDRESSES THESE ISSUES.
NUREG ON ANNUNCIATORS. NRR WILL INCORPORATE RESULTS OF THIS THE GOAL OF THIS WORK IS TO DETERMINE THE RISK TO WORK IN THEIR MODIFICATIONS TO THE STANDARD REVIEW PLAN.
PUBLIC HEALTH AND SAFETY RESULTING FROM HUMAN ERROR IN THE STATUS
~~------------....---------------------------------------
BY LETTER DATED DECEMBER 29, 1987. THE S0W FOR THE VALUE-COMPLETED IN NOVEMBER 1988. ALARM REDUCTION S UDY BEGAN IMPACT STUDY WAS FORWARDED TO BNL.
PROJECT AND BUDGET DCTOBER 1990.
WORK TERMINATED. (SEE MEMORANDUM FROM PROPOSAL FOR NRC WORK (NRC FORM 189) RECEIVED MARCH 7, 1988.
E. BECKJORD TO THE EDO ON JUNE 29, 1993.)
BNL BEGAN WORK IN APRIL 1988.
VALUE/ IMPACT STUDY WAS AS OF FY96 QUARTER 4 O
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ISSUE NUMBER: HF 5.2 TITLE: REV. CRIT. FDR MUMAN FACTDRS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
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AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG/CR-6105 " HUMAN FACTORS ENGINEERING GUIDANCE FOR THE NONE.
REVIEW OF ADVANCED ALARM SYSTEMS."
ORIGINAL CURRENT ACTUAL MILESTONES DALE DATE DATE j.
BEGIN VALUE/ IMPACT STUDY OF ANNUNCIATORS 02/88 04/88 l
COMPLETE VALUE/ IMPACT STUDY 07/88 10/88 NRC COMPLETES REVIEW OF STUDY RESULTS 09/88 11/88 l
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COMPLETE ALARM REDUCTION STUDY 11/89 12/97 i
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T.
SCARBROUGH OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M80330 M82072 M75089 M88898 RESCLUTION DATE: 06/89C WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE bEbbbhbkbbkkkkhhkLhkkhkkkhkbhhkkhhkhbbbh
~ ~
~~~~
k3b2k BNL WDRK SC0PE kPkbkFkb Ibkkhkh kk hbLbbEb [h khk bkkEkkb kbhkbh PL h hb kPkk Hbh PkRFbkkkkbE PkEbkbhkbh PkbbRkk bh hIRbb kk[~
IMPROVE HOV PERFORMANCE ARE:
- 6. THE STAFF ISSUED SE ON THE EPRI MOV PERFORMANCE REGULATORY IMPROVEMENTS - THE STAFF IS WORKING WITH ASME PREDICTION PROGRAM. THE STAFF IS REVIEWING THE HAND-(I{ IMPROVE THE INSERVICE TESTING REQUIREMENTS IN THE ASME CALCULATION HODEl.S FOR TWO UNIQUE GATE VALVE DESIGNS.
TO CODE. AND THE STAFF IS WORKING WITH OM TO DEVELOP GUIDELINES (3) MOV PERIODIC VERIFICATION GENERIC LETTER - ON FOR PERIODIC VERIFICATION OF MOV DESIGN-BASIS CAPABILITY TO SEPTEMBER 18, 1996 THE STAFF ISSUED GENERIC LETTER 96-05 REPLACE STROKE-TIME TESTING. RECENTLY, ASME ISSUED CODE CASE TO PROVIDE RECOMMENDATIONS ON THE PERIODIC VERIFICATION OMN-1. " ALTERNATIVE RULES FOR PPESERVICE AND INSERVICE TEST-OF MOV DESIGN-BASIS CAPABILITY.
ING OF CERTAIN ELECTRIC MOTOR OPERATED VALVE ASSEMBLIES IN (4)PECTION HODULE FOR MOV INSPECTION HODULE - THE STAFF PLANS TO PREPARE AN INS INSPECTING MOV PROGRAMS OVER THE LONG LWR POWER PLANTS OM - CODE 1995 EDITION: SUBSECTION ISTC."
STAFF REFERENCES CODE CASE IN GL 96-05.
TERM AND PROVIDE APPROPRIATE TRAINING FOR INSPECTORS.
STATUS bbbhbkh ((bh hkib kkbbkfkh kb SbPPbRh kb hRb kEbkbh L ShkFkkkBkk[.kLERhkkbLkbkhkkkk)hkk[kkbkPRkhbhhk STAFF, EFFORTS ON CODES AND STANDARDS, AND MOV RESEARCH AND STAFF's FINDINGS FROM THE EPRI PROGRAM REVIEW AND HAS BEEN ANALYSIS ARE ONGOING ACTIVITIES. ON SEPTEMBER 18, 1996 COMMUNICATINC STAFF VIEWS WITH INDUSTRY REGARDING PERIODIC STAFF ISSUED GL 96-05 ON MOV PERIODIC VERIFICATION. ON VERIFICATION. IN ADDITION. THE STAFF HAS BEEN FACTORING THE MARCH 15, 1996, THE STAFF ISSUED A NONPROPRIETARY SAFETY OVERALL FINDINGS FROM THE EPRI PROGRAM INTO STAFF EVALUATION OF THE EPRI HOV PERFORMANCE PREDICTION PROGRAM.
ACTIVITIES. WITH ISSUANCE OF GL 96-05, STAFF WORKING TO THE STAFF IS REVIEWING THE REMAINING EPRI HODELS FOR TWO COMPLETE SE SUPPLEMENT ON EPRI MOV TOPICAL REPORT BEFORE UNIQUE GATE VALVE DESIGNS AND PLANS TO ISSUE A SUPPLEMENT CLOSING MOV ACTION PLAN.
TO THE SE ADDRESSING THESE TWO MODELS LATER IN 1996. THE AS OF FY96 QUARTER 4 O
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J2h GL 89-10 AND 7 SUPPLEMENTS J3h NUREG-1352 L4? GL 96-05 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE INSERVICE TESTING OF CHECK VALVES (INPO) ISSUE SOER REGARDING 07/86 10/86 AUGMENTED TESTING OF CHECK VALVES (NRR/RES) REVIEW SOER TO SEE IF NRC 10/86 02/87 i
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CONCERNS ON IN-SITU TESTING OF " SIMPLE" CHECK VALVES SATISFIED, ISSUE RPT &/OR LTR (NSSS OWNERS GROUP) ISSUE OWNERS 05/87 11/87 GROUP APPLICATION GUIDE FOR CHECK VALVES (NRR/RES) REVIEW OWNERS GROUP APPL GUIDE TO 08/87 01/88 I
SEE IF NRC CONCERNS ON IN-SITU TEST OF
" SIMPLE" CHECK VALVES ARE SATIFIED (NRR/RES) REPORT (ACRS) 08/87 03/88 THERMAL OVERLEAD PROTECTION OF MOV'S (RES/EIB) COMPLETE REVIEW TO DETERMINE REQ'D 05/85 10/87 MODS. IF ANY. TO RG 1.106 REGARDING TOL PROTECTION FINAL NUREG ISSUED 07/88 06/88 LETTERS TO ASME & IEEE 12/88 12/88 CLOSE OUT MEMO ON CHECK VALVES & TOL 01/89 06/89 AS OF FY96 QUARTER 4
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II.E.6.1 TITLE: IN-SITU TESTING OF VALVES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE INSERVICE TESTING OF MOV*S (RES) ISSUE HOVATS REPORT REGARDING USE OF 09/85 01/86 SIGNATURE TRACING TECHNIQUES TO EVAL. THE OPERABILITY OF MOV*S (NRR/RES) REVIEW MOVATS REPORT AND AEOD 11/85 08/86 COMMENTS ON MOVATS REPORT (NRR) REVIEW RESPONSES TO IE BULLETIN 85-03 01/87 12/88 FROM LICENSEES AND APPLICANTS (RES/EIB) PREPARE STAFF POSITION ON ADDITI-02/86 10/87 ONAL AND/OR MODIFIED IN SITU TESTING OF MOV*S
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(RES/IEB) PREPARE VALUE/ IMPACT STMT & COST /
04/87 02/88 BENEFIT ANALYSIS FOR STAFF POSITION ON MOV IN-SITU TEST COMPLETE PROPOSED RESOLUTION PACKAGE 03/88 06/88 DIVISION DEPUTY DIRECTOR RES REVIEW COMPLETED 04/88 06/88 PACKAGE TO CRGR AND ACRS 06/88 09/88 GL TO NRR 02/89 02/89 CRGR REVIEW COMPLETE 08/88 03/89 ACRS REVIEW COMPLETE 10/88 05/89 RES SEND GL TO NRR 04/89 05/89 NRR ISSUANCE OF GENERIC LETTER ON MOV*S 09/89 06/89 CLOSE OUT MEMO TO EDO TASK MANAGER - OVEN 06/89 06/89 ROTMBERG. EIB/DSIR/RES ISSUE GL 89-10, SUPPLEMENT 7 01/95 01/95 AS OF FY96 QUARTER 4 O
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l ORIGINAL CURRENT ACTUAL I
MILESTONES DATE DATE DATE i
IkkbEkEEbEkEkIbLkTkEkbhhb[Pkkkbbkb Ohhhb bhhhh f'
VERIFICATION FOR PUBLIC COMMENT SER ON EPRI MOV PERFORMANCE PREDICTION 02/96 03/96
{
PROGRAM 3
FINAL ISSUANCE OF NEW GENERIC LETTER ON 08/96 09/96 I
MOV PERIODIC VERIFICATION
{
SER SUPPLEMENT ON EPRI MOV PERFORMANCE 08/96 10/96 PREDICTION PROGRAM j
PREPARE MOV INSPECTION MODULE 10/96 01/97 CLOSE OUT ISSUE 01/97 01/97
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72 ISSUE NUMBER: RGA 00I TITLE: BOILING WATER REACTOR INTERNALS IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER: D. TERA 0 0FFICE/ DIVISION / BRANCH: NRR /DE /EMCB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91898 M93627 M93925 M93926 M94959 M94975 M95369 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE hkk kh kk hfLL kbh kb b
HkSbbPkSkHkhHkVkhkh kNEkkbkhkbLbbERkHkkbkBkkbFkkhbkhkhkhbkhkk
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TO BE SUBMITTED BY LICENSEES CONCERNING INSPECTIONS OR RESOURCES THAT WILL BE NEEDED IN THE FUTURE, IT IS IMPORTANT REINSPECTIONS OF THEIR CORE SHROUDS. THE STAFF WILL ALSO FOR THE STAFF TO CONTINUE INTERACTING WITH THE INDUSTRY CORTINUE TO ASSESS CORE SHROUD INSPECTION RESULTS AND ANY ON A GENERIC BASIS IN ORDER TO ENCOURAGE THEM TO CONTINUE APPROPRIATE CORE SHROUD REPAIR DESIGNS ON A CASE-BY-CASE THEIR PRDACTIVE EFFORTS TO RESOLVE IGSCC OF BWR INTERNALS.
BASIS.
THE STAFF WILL ISSUE SEPARATE SAFETY EVALUATIONS THE BWRVIP HAS SUBMITTED 9 GENERIC DOCUMENTS SUPPORTING REGARDING THE ACCEPTABILITY OF CORE SHROUD INSPECTION PLANT-SPECIFIC SUBMITTALS FOR STAFF REVIEW. THE STAFF IS RESULTS AND CORE SHROUD REPAIR DESIGNS. THE STAFF HAS BEEN ENSURING THAT THE GENERIC REVIEWS ARE INCORPORATING RECENT INTERACTING WITH THE BWRVIP AND INDIVIDUAL LICENSEES. IN OPERATING EXPERIENCE ON ALL BWR INTERNALS.
STATUS
~~~~Itkbkf'ELLBhRkbbhPLkIkb[hkPkbkhbkkbkRkPkRkbk k kkPbRh BURVkP b6 bbkbHhhk~kRbkhkkkPkELihihkRY ~~ ~
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5 CORE SHROUDS DURING REFULEING OUTAGES IN THE FALL OF 1995.
REVIEW IN ICATES WA NOT COMPREHENSIVE. THE NRC STAFF HAS VARIOUS REPAIR METHODS HAVE BEEN USED TO PROVIDE ALTERNATE SENT A REQUEST FOR ADDITIONAL INFORMATION. IN ADDITION, THE LOAD CARRYING CAPABILITY, INCLUDING PREEMPTIVE REPAIRS.
INDUSTRY GROUP SUBMITTED A REPORT ON REINSPECTION OF INSTALLATION OF A SERIES OF CLAMPS, AND USE OF A SERIES OF REPAIRED AND NONREPAIRED CORE SHROUDS (BWRVIP-07) IN TIE-ROD ASSEMBLIES. THE NRC HAS REVIEWED AND APPROVED ALL FEBRUARY 1996.
THE STAFF IS CURRENTLY REVIEWING THIS REPORT SHROUD MODIFICATION PROPOSALS THAT HAVE BEEN SUBMITTED BY AND HAS SENT A REQUEST FOR ADDITIONAL INFORMATION. THE NRC BWR LICENSEES. REVIEW BY NRC CONTINUES ON INDIVIDUAL IS ALSO REVIEWING NEW INFORMATION SUBMITTED BY GE ON THE INSPECTION RESULTS AND PLANT-SPECIFIC ASSESSMENTS.
SAFETY SIGNIFICANCE OF AND RECOMMENDED INSPECTIONS FOR TOP IN OCTOBER 1995. INDUSTRY'S SPECIAL REVIEW GROUP ISSUED GUIDE AND CORE PLATE RING CRACKING.
AS OF FY96 QUARTER 4 O
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73 ISSUE NUMBER:- RGA 001 TITLE: BOILING WATER REACTOR INTERNALS AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG-1544 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSUE GL 94-03 07/94 07/94 TAP APPROVED 04/95 04/95 COMPREHENSIVE PLAN (BWRVIP-06) RECEIVED BY 12/95 10/95 NRC BWRVIP-07 RECEIVED BY NRC 02/96 02/96
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ISSUE NUREG-1544 03/96 03/96 REVIEW BWR VESSEL SHELL WELD INSPECTION 08/9 6 10/96 RECOMMENDATIONS (BWRVIP-05)
REVIEW RPV AND INTERNALS EXAMINATION GUIDE-08/96 12/96 LINES (BWRVIP-03) t REVIEW GUIDELINES FOR REINSPECTION OF CORE 08/96 12/96 SHROUDS (BWRVIP-07)
SAFETY ASSESSMENT OF BWR REACTOR INTERNALS 08/96 12/96
' WRVIP-06)
EVALUATION OF CRACK GROWTH IN BWR STAINLESS 12/96 03/97 STEEL RPV INTERNALS (BWRVIP-14)
CORE SPRAY INTERNAL INSPECTION AND FLAW 07/97 07/97 EVALUATION GUIDELINES (BWRVIP-18)
REVIEW GENERIC REPAIR TECHNOLOGY, CRITERIA 08/96 08/97 AND GUIDANCE REVIEW GENERIC MITIGATION GUIDELINES AND 08/97 08/97 CRITERIA AS OF FY96 QUARTER 4 i
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74 ISSUE NUMBER: RGA 001 TITLE: BOILING WATER REACTOR INTERNALS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE REVIEW GENERIC NDE TECHNOLOGIES FOR 08/97 08/97 EXAMINATIONS OF BWR INTERNAL COMPONENTS AND ATTACHMENTS CORE SPRAY PIPING AND SPARGER REPAIR 09/9 7 09/97 DESIGN CRITERIA (BWRVIP-19)
CLOSE OUT ACTIVITY
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TYPE:
PRIORITY:
TASK MANAGER: B. ELLIOT OFFICE / DIVISION /BRANCM: NRR /DE /EMCB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M92310 M92313 M93329 M93330 M93331 RESOLUTION DATE:
w WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WORK SCOPE SPECIFIC ACTIONS INCLUDED IN THE GENERIC ACTION PLANS ARE:
TO NUREG-1511 IN 1996 AND ISSUE SUPPLEMENT 2 TO NUREG-1511 I
(1) ISSUE SUPPLEMENT 1 TO GL 92-01. (2) COORDINATION WITH IN 1997 (6) ISSUE REVISION 1 0F THE RVID IN 1996 AND ISSUE RES ON RPV INTEGRITY ISSUES, (3) HOLD AN NRC/ INDUSTRY VORK-REVISION 2 0F THE RVID IN 1997 (7) OBSERVE INDUSTRY ANNEAL-SFSP ON RPV ISSUES. (4) REVIEW FIRST AND SECOND ROUND OF ING DEMONSTRATIONS, (8) REVIEW AND EVALUATE THE PALISADES RESPONSES TO GL 92-01 SUPPLEMENT 1.
(5) ISSUE SUPPLEMENT 1 ANNEALING PLAN. AND (9) REVIEW THE PALISADES ANNEAL.
STATUS GL 92-01, SUPPLEMENT 1 HAS BEEN ISSUED. NRC/ INDUSTRY HAS ALSO SUBMITTED A REVISED PTS EVALUATION. THE KEWAUNEE WORKSHOP HAS BEEN COMPLETED. A REQUEST FOR RESEARCH ON RPV EVALUATION IS BEING REVIFWED BY THE STAFF. THE STAFF HAS INTEGRITY ISSUES HAS BEEN ISSUED. THE REACTOR VESSEL COMPLETED THE REVIEW Dr THE GINNA PTS EVALUATION, WHICH IS INTEGRITY DATABASE (RVID) HAS BEEN ISSUED (NRC ADMINISTRA-DOCUMENTED IN A MARrh 22. 1996 LETTER TO THE LICENSEE.
TIVE LETTER 95-03) TO ALL LICENSEES AND TO ALL INDIVIDUALS BASED ON THE CURRENTLY AVAILABLE CHEMISTRY AND SURVEILLANCE REQUESTING A COPY.
DATA, THF GINNA rdACTOR VESSEL IS PROJECTED TO BE BELOW THE THE STAFF HAS COMPLETED THE REVIEW OF LICENSEES' INITIAL PTS SCREEhi.NG CRITERIA AT THE EXPIRATION OF ITS LICENSE.
RESPONSES TO SUPPLEMENT 1 TO GL 92-01.
THE LICENSEE FOR CONSUMERS POWER COMPANY HAS SUBMITTED A NUMBER OF KEWAUNEE IN A LETTER FROM CLARK R.
STEINHARDT DATED SECTIONS OF ITS THERMAL ANNEALING REPORT. THESE AUGUST 21. 1995. PROVIDED THE ONLY NOTABLE RESPONSE. THEY SECTIONS ARE CURRENTLY UNDER STAFF REVIEW.
THE STAFF PROVIDED THREE METH005 0F ANALYSIS OF THEIR SURVEILLANCE ISSUED A REQUEST FOR ADDITIONAL INFORMATION ON SECTION 3*
DATA THAT INDICATE THE KEWAUNEE REACTOR VESSEL WILL BE BELOW
" FRACTURE TOUGHNESS RECOVERY AND REEMBRITTLEMENT THE PTS SCREENING CRITERIA AT THE EXPIRATION OF ITS LICENSE.
ASSURANCE PROGRAM." AND THE LICENSEE RESPONDED. THE THE LICENSEE FOR GINNA IN A LETTER DATED OCTOBER 11, 1995 LICENSEE *S RESPONSE IS UNDER STAFF REVIEW.
[
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NRC/ INDUSTRY WORKSHOP ON RPV ISSUES 07/95 07/95 REVIEW OF RESPONSES TO GL 92-01. SUPPLEMENT 1 10/95 10/95 (FIRST ROUND)
ISSUE RVID. REY. 1 06/96 06/96 OBSERVE INDUSTRY ANNEALING DEMONSTRATION 12/96 07/96 NUREG-1511 RPV STATUS REPORT. SUPPLEMENT 1 06/96 10/96 REVIEW OF RESPONSES TO GL 92-01. SUPPLEMENT 1 12/96 12/96 (SECOND ROUND)
REVIEW AND EVALUATE THE PALISA0ES ANNEAL 12/96 12/96 PLAN NUREG-1511 RPV STATUS REPORT. SUPPLEMENT 2 06/97 06/97 ISSUE RVID REV. 2 06/97 06/97 COORDINATE WiTH RES 07/97 07/97 REVIEW PALISADES ANNEAL 08/98 08/98 AS OF FY96 QUARTER 4 O
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7B ISSUE NUMBER: RGA 003 TITLE: DRY CASK STORAGE OF SPENT FUEL IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER:
P.
ENG OFFICE / DIVISION / BRANCH: NHSS/SFP0/
ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M93821 M93927 M94107 M9410B RESOLUTION DATE:
WORK AUTHORIZATION: MEHO FROM C. PAPERIELLO TO W. RUSSELL AND J. TAYLOR ON JULY 28. 1995 FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE bkkbkkkhbLbbEbkhkhkPL h kkk fk) Rkhkkh k bh Gkhkkkk bkhkLbP CbkRkbkkhk bkkbhk FbR kkbb Pkb8Lkk[ Ikb ISpuE AND IDENTIFY THE SPECIFIC PROBLEMS TO BE ADDRESSED, IMPLEMENT THE CORRECTIVE ACTIONS.
5TATUS khk kbLtbbkhb bkkbh PLEk [kkbbk kkhk BEkh bbhPLkTkb k S BEEh kkSbkb kbk bbkhkkk$ Pb8Lkb bbkhkkkk Rb bbk Bh ~
CASK TRUNNIONS. CASK V(EPING. HYDROSTATIC TESTING, SAFE-JUNE 18, 1996. ALL OF THE COMMUNICATIONS ISSUES ARE ONGOING GUARDS CONCERNS. PART T2 REPORTING REQUIREMENTS, INSPECTION EFFORTS WITH NO SPECIFIC CRITERIA FOR CLOSURE. HOWEVER.
OF SITE ACTIVITIES. AND VENDOR INSPECTIONS. THE INSPECTION THERE HAVE BEEN SIGNIFICANT IMPROVEMENTS IN THESE AREAS.
PROCEDURES FOR DRY CASK ACTIVITIES (SITE AND VENDOR) WERE THE REGIONS, NMS$ AND NRR HOLD REGULAR INTERFACE CALLS TO ISSUED IN FEBRUARY 1996.
THESE PROCEDURES INCLUDED RESOURCE DISCUSS DRY CASK ISSUES TRAINING HAS BEEN GIVEN TO THE ESTIMATES FOR INSPECTION ACTIVITIES. THE STAFF INCORPORATED AFFECTED STAFF. AND NRC HAS ESTABLISHED OPEN COMMUNICATIONS ADDITIONAL GUIDANCE ON SEISMIC ISSUES INTO INSPECTION WITH THE NEWLY-FORMED NUCLEAR ENERGY INSTITUTE DRY CASK PROCEDURE IP) 60851 AND ADDITIONAL GUIDANCE CONCERNING STORAGE ISSUE TASK FORCE. BASED ON THESE IMPROVEMENTS. THE CONSIDERAT(IUN OF FAILED FUEL IN UNLOADING PROCEDURES INTO STAFF WILL REVIEW THESE ISSUES FOR CLOSURE IN THE COMING IP 60854.
THE WORKING GROUP HAS COMPLETED ITS REVIEW OF THE MONTHS. THE ECD FOR THE REVIEW OF THE FIRST SUBMITTAL FOR ISSUES ASSOCIATED WITH CASK LOADING AND UNLDADING. THE THE STORAGE OF DAMAGED FUEL HAS BEEN CHANGED TO 03/97 DUE TO WORKING GROUP IS IMPLEMENTING ITS RECOMMENDATIONS, UNTlHELY RESPONSES FROM THE APPLICANT. NHS$/SFPO INCLUDING THE PREPARATION OF AN INFORMATION NOTICE SPONSORED A PUBLIC WORKSHOP ON DRY CASK STORAGE ON MAY 17, RECENT INFORMATION 1996.
WELL OVER 300 PEOPL E ATTENDED FROM THE PLANTS.
CONCERNING LOADING AND UNLOADING ISSUES (E.G.,
HYDROGEN IGNITION AT POINT BEACHj MAY REQUIRE STATES. INDUSTRY GROUPS, VENDORS. AND THE STAFF. THE ST AFF ADDITIONS TO THE ACTION PLAN.
THE REMAINING TECHNICAL BRIEFED THE COMMISSION ON THE STATUS OF THE ORY CASK ISSUE (HEAVY LOAD CONTROL) IS ON SCHEDULE. A 50.59 ISSUE STORAGE PROGRAM ON MAY 30, 1996.
IN RESPONSE TO A INVOLVING HEAVY LOAD CONTROL IN GENERAL 15 THE SUBJECT OF HYDROGEN IGNITION EVENT AT POINT BEACH ON MAY 28 THE STAFF NRC BULLETIN 96-02, ISSUED APRIL 11, 1996. THE DRAFT SRP ISSUED INFORMATION NOTICE 96-34 ON MAY 31, 1996.
AS OF FY96 QUARTER 4 O
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ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE ISSUE IN ON SEISHIC REQUIREMENTS FOR PADS 06/95 06/95 DEVELOP ACTION PLAN 07/95 07/95 HEET WITH NEI ON CASK WEEPING 08/95 08/95 s
DEVELOP POSITION ON REPORTING REQUIREMENTS 09/9 5 09/9 5 I
DEVELOP STAFF POSITION ON CASK TRUNIONS 09/9 5 09/95 FORM WORKING GROUP ON CASK LOADING / UNLOADING 10/95 10/95 PROCEDURES DEVELOP WORKING GROUP PLAN ON HEAVY LOADS /
11/95 II/95 CRANES HYDROSTATIC TESTING 12/95 12/95 L
COMPLETE ANALYSIS OF SAFEGUARDS DESIGNS 12/95 12/95 l
ISSUE REVISED PROCEDURES FOR VENDOR 02/96 02/96
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INSPECTIONS ISSUE REVISED PROCEDURES FOR INSPECTION OF 02/96 02/96
'i SITE ACTIVITIES ISSUE SRP AND 10 CFR 50.59 GUIDANCE 03/96 03/96 COMPLETE ACTION ON HEAVY LOADS / CRANES 12/96 12/96 REIEW PROPOSED SOLUTIONS FOR FAILED FUEL 03/97 03/97 c1 AGE AS OF FY96 QUARTER 4 i
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81 ISSUE NUMBER: ' RGA 004 TITLE: THERHO-LAG FIRE BARRIERS IDENTIFICATION DATE: 02/96C PRIDRITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER:
S. WE ST OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE:
TAC NUMBERS: M82809 M90203 M90284 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE t
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WORK SCOPE j
SPECIFIC ACTIONS INCLUDE THE RESOLUTION OF CONCERNS AND A STAFF RECOMMENDATION TO RESOLVE THERMO-LAG CONCERNS BY GENERIC ISSUES RAISED BY SPECIAL REVIEW TEAM AND REQUIRING COMPLIANCE WITH EXISTING NRC REQUIREMENTS AND TO PERMIT PLANT-SPECIFIC EXEMPTIONS. WHERE JUSTIFIED.
(2) RESOLUTION OF PLANT. SPECIFIC ISSUES THAT EMERGE FROM TH( GENERIC ISSUES, IN JUNE 1994 THE COMMISSION APPROVED l
t STATUS LG bhkbhPLkh FbRhbkkkbRkhGLkbEhSEESIbbkRkbhkVEkbhkbhPLESIhb~~~
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THE STAFF IS HANDLING THE REVIEW OF PLANT-SPECIFIC
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ISSUES, THE MECHANICAL PROPERTIES TEST PROGRAM. AND THE FIRE CURVE FEASIBILITY STUDY.
THE STAFF ALSO COMPLETED ITS CORRECTIV' ACTIONS AS MULTIPLANT ACTION MPA-L208 UNDER REVIEW OF LICENSEES' RESPONSES TO GENERIC LETTER 92-08, GENERIC L;!TER (GL 92-08. "THERMO-LAG 330-1 FIRE BARRIERS."
" THERMAL-LAG 330-1 FIRE BARRIERS" AND DETERMINED MOST AND THE REVIEW OF ELATED PLANT-SPECIFIC ISSUES. SUCH AS
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CORRECTIVE ACTION PLANS ARE ACCEPTABLE. HOWEVER. THE STAFF FIRE PROTECTION EXEMPTION REQUESTS AND AMPACITY DERATING EVALUATIONS AND ANALYSES. AS PLANT-SPECIFIC LICENSING I
IS CONCERNED THAT SOME LICENSES MAY NOT BE MAKING PROGRESS ACTIONS. THE MPA AND PLANT-SPECIFIC LICENSING ACTIONS ARE r
TOWARD RESOLVING THE PLANT-SPECIFIC ISSUES. AND SOME TRACKED BY THE WORKLOAD INFORMATION AND SCHEDULING PROGRAM IMPLEMENTATION SCHEDULES MAY BE EITHER TOO TENUOUS OR TOO PROTRACTED. THE STAFF HAS ALSO ESTABLISHED A PROCESS (WISP) AND ARE NOT A PART OF THE THERMO-LAG ACTION PLAN.
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PROBLEM / RESOLUTION AFFECTED DOCUMENTS i
IN 91-47: IN 91-79 AND SUPPLEMENT I: IN 92-46: IN 92-55:
NONE.
IN 92-82: IN 94-22: IN 94-34: IN 94-86 SUPPLEMENT I:
IN 95-27: IN 95-32: IN 95-49 f
BULLETIN 92-01 AND SUPPLEMENT I AS OF FY96 QUARTER 4 I
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82 ISSUE NUMBER: RGA 004 TITLE: THERMO-LAG FIRE BARRIERS AFFECTED DOCUMENTS PROBLEH/ RESOLUTION
.---------------------------------~~----------------
GL 92-03: GL 86-10 SUPPLEMENT 1 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ASSESS NRC FIRE PROTECTION PROGRAM (PART IV) 02/93 02/93 TESTING (PART II) SUBMITTED TO NRC 04/95 04/95 NEI SUBMITS EXECUTIVE
SUMMARY
OF NUCON 10/95 10/95 REPORT NIST DRAFT REPORT SUBMITTED TO NRC 11/95 11/95
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NRC PROVIDES COMMENTS AND TECHNICAL 12/95 12/95 DIRECTION TO NIST SEMIANNUAL COMMISSION STATUS REPORT 04/96 04/96 RESOLVE TECHNICAL ISSUE (PART I) 09/96 09/96 SEMIANNUAL COMMISSION STATUS REPORT 10/96 10/96 CLOSE OUT ACTIVITY AS OF FY96 QUARTER 4 O
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83 ISSUE NUMBER: RGA 005 TITLE: RCS DRAINDOWN IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER: M. RAZZAQUE OFFICE / DIVISION / BRANCH: NRR /DSSA/SRXB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: H91621 M92635 M93568 RESOLUTION DATE: 07/97 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE W0RK SCDPE kPEbiFkb kbhibkk khbLbbEb [h kHE bEhEk[b bh[bh PLkh kkk f5b bFR 5b 54fFf bEkEkkb LEkkER [bl f kb Pkbv[bE fkFbkkkh[bh (1) IN 95-03 ISSUED 01/12/95 AND SUPPLEMENT TO IN 95-03 ON DRAINDOWN VULNERABILITIES AND TH HEASURES THEY ISSUED 03/25/96:
IMPLEMENTED TO DIMINISH THE PROBABILITY OF A DRAINDOWN.
(2) REQUEST ALL PWR LICENSEES. VIA AN INFORMATION GATHERING STATUS Tbk bL b k bEkh PPkbvEb bh kHk bkbk khkblkk kbhhkbbhkkkkkbhhfkhkkhhhPPkR
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CURRENTLY AT THE EDO*S OFFICE. BEING PREPARED TO BE SENT AFFECTED DOCUMENTS PROBLEH/ RESOLUTION IN 95-03 UESTION RAISED BY THE UPPER MANAGEMENT REGARDING THE NEED AEOD/595-01 OR PUBLIC COMMENT PERIOD FOR THE DRAFT GL. AND THIS MAY HAVE AN IMPACT ON THE DATE OF ISSUE OF THE GL.
STAFF PREPARED JUSTIFICATION THAT PUBLIC COMMENT PERIOD IS NOT REQUIRED FOR THE GL.
MANAGEMENT DECISION IS NECESSARY.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE
.DATE DATE
....---------- -- --------------------~~
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AS OF FY96 QUARTER 4
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RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
84 ISSUE NUMBER: RGA 005 TITLE: RCS DRAINDOWN ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IN 95-03 ISSUED 01/95 01/95 DRAFT GL 11/95 11/95 ISSUE SUPPLEMENT 1 TO IN 95-03 03/96 03/96 GL TO CRGR 06/96 08/96 COMPLETE DRAFT TI-ISSUE TO REGIONS FOR 06/96 11/96 COMMENTS ISSUE GENERIC LETTER 06/96 11/96 RECEIVE REGIONAL COMMENTS ON TI 08/96 01/97
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COMPLETE EVALUATION OF RESPONSES TO GL 11/96 04/97 ISSUE TI 11/96 04/97 COMPLETE INSPECTIONS 02/97 07/97 CLOSE OUT ACTIVITY AS OF FY96 QUARTER 4 O
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RUN DATE: 11/21/96
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
8S ISSUE NUMBER: RGA 006 TITLE: SRP REVISION IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER: A.
MASCIANTONIO OFFICE / DIVISION / BRANCH: NRR / DISP /PIPB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M40047 M83832 RESOLUTION DATE:
WORK AUTHORIZATION: MEMORANDUM FROM J. TAYLOR TO THE CHAIRMAN ON 11/18/91.
FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE SPECIFIC TASKS INCLUDED IN THE ACTION PLAN ARE: 1) IDENTIFY INCORPORATE THE CHANGES RECOMMENDED: 4) PREPARE NEW DRAFT ESTABLISHED STAFF POSITIONS AND NEW REGULATORY REQUIREMENTS SRP SECTIONS THAT ARE SUPPORTED BY ESTABLISHED STAFF FROM A REVIEW OF GENERIC REGULATORY DOCUMENTS ISSUED SINCE POSITIONS OR ARE FULLY ADDRESSED IN THE EVOLUTIONARY DESIGN i
TWT LAST SRP REVISION AND FROM A REVIEW OF NRR STAFF SAFETY REVIEWS: 5) AUTOMATE THE SRP TO MAKE FUTURE REVISIONS AND EVALUATION REPORTS FOR EVOLUTIONARY LWR DESIGNS: 2) PREPARE ACCESSIBILITY EASIER TO ACCOMPLISH: AND 6) MAINTAIN THE A SIDE-BY-SIDE COMPARISON OF THE SRP-CITED VERSION OF CODES PROGRAM DATA BASE TO REFLECT NEW STAFF POSITIONS AND t
AND STANDARDS VERSUS THE CURRENT VERSION OF THE STANDARD:
REQUIREMENTS.
- 3) PREPARE DRAFT REVISIONS OF THE CURRENT SRP SECTIONS TO
$TATUS
~bEWbRKkPPRbkbhhhbbkT[LEbPkbbEbbkkkbhEBkEk
~ bbbE kb kTkkbERb kbREb5 bEhE BEEh Pb8LibbEb$ k[hi[h
~~
T COMPLETED FOR THE DEVELOPMENT OF SRP DRAFT REVISION BY TECHNICAL BRANCHES IS BEING COMPLETED ON A RESOURCE PACKAGE S AND FOR NEW SRP SECTION DEVELOPMENT. BOTH AVAILABLE BASIS CONSISTENT WITH A PRIORITY 3 EFFORT. AN CONTRACTORS HAVE COMPLETED DRAFT REVISION WORK FOR AUTOMATED VERSION OF THE CURRENT SRP HAS BEEN DEVELOPED CURRENT SRP SECTIONS AND NEW SRP SECTIONS. PNL HAS AND IS OPERATIONAL. THIS AUTOSRP HAS BEEN INSTALLED ON i
COMPLETED CODE AND STANDARD COMPARISON WHICH INVOLVES THE NRC LAN.
THE UPDATED SRP HAS BEEN ISSUED FOR PUBLIC THE PREPARATION OF SIDE-BY-SIDE COMPARISONS BETWEEN THE COMMENT. A FINAL REVISED SRP WILL BE PUBLISHED AFTER CITED VERSION OF CODES AND STANDARDS AND THE LATEST RESOLUTION OF PUBLIC COMMENTS AND COMPLETION OF STAFF VERSION, TO ALLOW SRP REVIEWERS TO USE THE MORE CURRENT REVIEW.
VERSION AND TO SUPPORT SRP UPDATES OF THE CITATIONS.
AFFECTED DOCUMENTS PROBLEH/ RESOLUTION
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86 ISSUE NUMBER: RGA 006 TITLE: SRP REVISION ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE CLOSE OUT ACTIVITY
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87 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER:
S. BLACK OFFICE / DIVISION / BRANCH: NRR /DRCH/HQMB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91429 M91431 M92420 M92450 M92451 M92447 M92448 M92449 M88650 M91431 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN L '4 T U TOR CONTRACT TITLE i
WORK SCOPE l
THE GOAL OF THE ACTION PLAN IS TO UTILIZE THE LESSONS ESTABLISHED TO PREPARE THE REGULATORY GUIDANCE DOCUMENTS i
LEARNED FROM THE 3 VOLUNTEER LICENSEES TO MODIFY STAFF-AND TEST THEIR IMPLEMENTATION DURING THE EVALUATION OF i
DEVELOPED DRAFT GUIDANCE TO FORMULATE REGULATORY GUIDANCE VOLUNTEER PLANT ACTIVITIES.
ON ACCEPTABLE METHODS FOR IMPLEMENTING GRADED QA.
THE IN ADDITION TO THE ABOVE. THE FOLLOWING TAC NUMBERS ST1FF WILL DEVELOP A REGULATORY GUIDE. A STANDARD REVIEW WERE INITIATED: M91432 M91433. M91434 M91435. M91436 I
PLAN REVISION FOR CHAPTER 17. AND A REACTIVE INSPECTION AND M91437.
1 PROCEDURE (IP) FOR GRADED QA.
AN INTEROFFICE TEAM HAS BEEN STATUS i
bbkt[kkkbh bRkhh Rkb bbkbh kkb SkP FbR BbhH kkkK CbkhRkbhbkkf ShkFhbbHMkkhkWkkkPkbVibhbkbkhPbbRIkb RANKING AND GRADING OF QA CONTROLS HAVE BEEN PREPARED AND A MEETING ON JUNE 19 AND VIA LETTER DATED AUGUST 16 1996.
CIRCULATED FOR REVIEW FOR THE INTEROFFICE TEAM. A MEETING STAFF IS AWAITING SUBMITTAL OF A REVISED QA PROGRAM.
- ALSO, WAS HELD WITH THE THREE VOLUNTEER LICENSEES ON APRIL II.
NEI SUBMITTED 96-02 " GUIDELINE FOR IMPLEMENTING A GRADED 1996 TO RECEIVE THEIR FEEDBACK ON THE STAFF DEVELOPED APPROACH TO QUALITY" DATED MARCH 21 1996.
THE STAFF HAS EVALUATION GUIDE.
THE LICENSEES EXPRESSED CONCERNS ABOUT PERFORMED A CURSORY REVIEW OF THE DOCUMENT AND CONCLUDED THE LEVEL OF DETAIL CONTAINED IN THE GUIDE. PARTICULARLY THAT IT DOES NOT REFLECT THE PROGRESS AND LEVEL OF DETAIL THAT RELATED TO PRA AND COMMERCIAL GRADE ITEM DEDICATION.
THAT HAS BEEN ACHIEVED THROUGH THE VOLUNTEER PLANT EFFORT THE LICENSEES CONTEND THAT EXISTING INDUSTRY GUIDANCE (PSA THE STAFF INFORMED NEI BY LETTER DATED MAY 2 1996 THAT APPLICATION GUIDE AND EPRI-5652) TEN COMMENTS FROM NEI ON ARE SUFFICIENT FOR THOSE THE GUIDE IS NOT ADEQUATE (AS A STAND ALONE DOCUMENT) TO TOPICS.
THE STAFF RECEIVED WRIT IMPLEMENT GRADED QA BUT THAT IT WILL BE CONSIDERED AS THE THE EVALUATION GUIDE BY LETTER DATED MAY 24 1996.
THE NEI STAFF DEVELOPS THE GRADED QA REGULATORY GUIDE AND STANDARD LETTER QUESTIONS THE NEED FOR ADDITIONAL REGULATORY REVIEW PLAN.
NEI SUBMITTED AN UPDATED VERSION OF 96-02 ON GUIDANCE FOR THE GRADED QA APPLICATION. NEI CONTENDS THAT JULY 16 WHICH IS UNDER STAFF REVIEW. THE STAFF MET WITH EXISTING INDUSTRY GUIDANCE IS SUFFICIENT.
GRAND GULF PERSONNEL ON AUGUST 27 TO DISCUSS QUESTIONS SOUTH TEXAS SUBMITTED THEIR QA PROGRAM REVISION FOR PERTAINING TO THE GRAND GULF SAFETY SIGNIFICANCE THEIR GRADED QA EFFORT ON MARCH 28 1996.
THE CHANGE WAS DETERMINATION PROCESS.
REVIEWED BY THE STAFF (HQHB, SPSB. RES RIV. AND NRC AS OF FY96 QUARTER 4
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88 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA STATUS AFFECTED DOCUMENTS PROBLEH/ RESOLUTION kkbbLkhbRhbbfbbk.hh'~
~
PkhbkhCEbhVbLbEkEkkPL kkPkbbkkHkhPLkhkkkkT[bbS[h NUMARC 93-01 ORDER TO GAIN LESSONS LEARNED MAY DELAY SCHEDULES IF THESE UTILITIES REVISE THEIR PLANS FOR IMPLEMENTING GRADED QA PROGRAMS. OTHER UTILITIES MAY PROCEED WITH GRADED QA BEFORE GUIDANCE IS ISSUED, AND THIS COULD DIVERT STAFF RESOURCES FROM THIS ACTION PLAN EFFORT. THE IMPOSITION OF COMMISSION LEVEL APPROVAL OF QA PROGRAM CHANGES THAT RELY ON RISK INFORMED DECISIONHAKING INVOLVING POLICY ISSUES COULD JEOPARDIZE THE PROJECTED GRADED QA HILESTONE SCHEDULES.
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ORIGINAL CURRENT ACTUAL MILEST0NE$
DATE DATE DATE ISSUED SECY 95-059 03/95 03/95 BEGIN INTERACTIONS WITH VOLUNTEER 05/95 05/95 LICENSEES (PALO VERDE. GRAND GULF, SOUTH TEXAS)
REVISION 3 OF DRAFT EVALUATION GUIDE FCR 07/95 07/95 VOLUNTEER PLANTS ISSUED FOR STAFF COMMENT REVISION 4 OF DRAFT EVALUATION GUIDE FOR 10/95 10/95 VOLUNTEER PLANTS ISSUED FOR STEERING GROUP REVIEW ISSUE LTR TO 3 VOLUNTEER PLANTS OUTLINING PRO 01/96 01/96 GRAM OBJECTIVES & REVIEW EXPECTATIONS. DIS-TRIBUTE STAFF EVALUATION GUIDE TO LICENSEES.
EVALUATION GUIDE ISSUED FOR USE BY STAFF IN 01/96 01/96 EVALUATING VOLUNTEER PLANTS ACRS BRIEFING: EXPERT PANEL AND DETERMINIS-02/96 02/96 TIC CONSIDERATIONS AS OF FY96 QUARTER 4 O
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89 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE ACRS BRIEFING: GRADED QA 04/9 6 04/96 MEETING HELD WITH VOLUNTEER PLANTS TO RECEIVE 04/96 04/96 FEEDBACK ON STAFF EVALUATION GUIDE ON 04/11/96.
INDUSTRY COMMENTS ON STAFF EVALUATION GUIDE 05/96 05/96 PROVIDED DRAFT SRP AND RG FOR COGNIZANT OFFICE 07/96 10/96 REVIEW AND COMMENT DRAFT SRP AND RG FOR INTEROFFICE REVIEW AND 09/9 6 10/96 CONCURRENCE DRAFT SRP AND RG FOR ACRS/CRGR REVIEW 10/96 10/96 DRAFT SRP AND RG FOR PUBLIC COMMENT 12/96 12/96 DRAFT SRP AND RG PUBLIC COMMENT PERIOD 03/97 03/97 ENDS COMPLETE STAFF INTERACTIONS WITH VOLUNTEER 06/97 06/97 PLANTS ISSUE LESSONS LEARNED NUREG REPORT REGARDING 02/97 09/97 GRADED QA PROGRAMS AT VOLUNTEER PLANTS FINAL DRAFT SRP AND RG FOR ACRS/CRGR REVIEW 09/97 09/97 ISSUE STAFF INSPECTION GUIDANCE (REACTIVE 05/97 12/97 IP)
FINAL DRAFT SRP AND RG FOR INTERDFFICE 12/97 12/97 CONCURRENCE PUBLISH FINAL SRP AND RG 12/97 12/97 CONDUCT NRC STAFF TRAINING 05/97 01/98 AS OF FY96 QUARTER 4
RUN DATE: 11/21/96 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
90 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE PbbllbbbRkkHbPhbNbkbEbhk b2)bh b2)bb ISSUE SECY UPDATE (CLOSEOUT OF ACTION PLAN) 12/97 04/98
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