ML20147H627
| ML20147H627 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1997 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML20147H624 | List: |
| References | |
| NUDOCS 9704040141 | |
| Download: ML20147H627 (140) | |
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I-ATTACHMENT 1
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l
FIRST QUARTER FY-97 UPDATE i
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0FFICE OF NUCLEAR REGULATORY RESEARCH FEBRUARY 1997 l
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9704040141 970325 PDR ORG NREB PDR
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n 11 TABLE OF CONTENTS (a)
Generic Issue Management Control System (1)
Description (2)
Legend (3)
Data Elements
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(b)
Table 1 -
Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (c)
Table 1A - Summary of Generic Safety Issues Scheduled for 4
Resolution, Issues Resolved, and Issues Integrated (d)
Table 2 -
Number of Generic Safety Issues Resolved by Fiscal Year (Through 1st Quarter FY-97)
(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 1st Quarter of FY-97 (1)
Table 6 -
Generic Issues Prioritized as of 1st Quarter FY-97 (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 O
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V GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 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 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 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 througn 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 fG 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 reorganization of April 12, 1987, NRR Office Letter No. 40 was used for i
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 those 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.
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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 of 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 FIN Financial Identification Number FRN Federal Register Notice FTR Final Technical Resolution i
GL Generic letter GSI Generic Safety Issue i
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 PD31 -
Project Directorate III-1 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.)
1-I S0W Statement of Work l
SPLB -
Plant Systems Branch a
SRP Standard Review Plan i
SRXB -
Reactor Systems Branch 1
STS Standard Technical Specification l
T/A Technical Assistance TAP Task Action Plan a
i TBD To be Determined i
TI Temporary Instruction i
TS.
Technical Specification i
USI Unresolved Safety Issue 1
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a vi DATA ELEMENTS Management and control indicators used in GIMCS are defined as follows:
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Issue No.
Generic Issue Number 2.
Title
- 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.
Iypfe
- Generic Safety (GSI), Licensing (LI), or Regulatory Impact (RI) 6.
Priority
- High (H) or Medium (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.
Action Level
- Active Technical assistance funds appropriated for resolution and/or Task Manager actively pursuing resolution Inactive -
No 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 Ng requirements);
i 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 j
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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 14.
fjE 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 Scone
- describes briefly the work necessary to technically resolve and complete the generic 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 p
the original Task Action Plan plus additional milestone dates added during i
task resolution; (b) changes in the original scheduled dates 1
are listed under " Current";
(c) actual completion dates are listed under " Actual" O
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O TABLE 1 GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED-FY-83 THROUGH FY-97(IST GUARTER)
FY-83 FY-84 FY-85 ISSUE GIs New GIs GIs New GIs GIs New GIs TYPE Start +
Issues - Resolved - End Start +
Issues - Resolved - End Start +
Issues - Resolved - End i
4 USI lb 0
2 14' 14 0
2 12 12 0
0 12 t
HIGH 24 2
0 26 26 1-1 26 22*
41 6
57 MEDIUM 31 2
0 33 33 4
3 34 28*
I 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 l
FY-86 FY-87 ISSUE GIs New GIs ISSUE GIs New GIs GIs TYPE Start +
Issues - Resolved - End TYPE Start + Issues
- Resolved - Integrated End 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 I
4 5
16 NR 19 (3)*
-3 13 NR 13 0
1 1
11 TOTAL:
107 (12)*
9 86 TOTAL:
86 5
10 13 68 i
- Extensive revisions to Human Factors issues resulted in priority changes.
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T1-1 As of 1st Quarter FY-97 m
TABLE 1 (Continu;di' GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-97(IST 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 NP, 9
0 2
0 7
TOTAL:
68 4
16 6
50 TOTAL:
50 2
18 1
33 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 MED!UM 9
3 1
0 11 NR 7
0 3
0 4
NR 4
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TOTAL:
33 1
7 0
27 TOTAL:
27 6
4 0
29 FY-92 FY-93 ISSUE GIs New GIs GIs ISiUE GIs New GIs GIs TYPE Start + Issues - Resolved - Integrated = End TYFE Start + Issues - Resolved - Integrated = End HIGH 14 0
4 0
10 HI1H 10 0
7 0
3
.NEDIUM 11 1
2 0
10 MIDIUM 10 0
3 0
7 NR 4
2 1
0 5
Nf:
5 2
0 0
7 TOTAL:
29 3
7 0
25 T)TAL:
25 2
10 0
17 T1-2 As of 1st Quarter FY-97 e
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4 TABLE 1 (Continued)
G*NERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-97(IST 00ARTER)
FY-94 FY-95 ISSUE GIs New GIs GIs ISSUE GIs New GIs GIs i
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
TOTAL:
17 2
5 0
14 TOTAL:
14 2
1 0
15 i
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
.t HIGH 4
0 1
0 3
HIGH 3
0 0
0 3
MEDIUM 6
0 1
0 5
MEDIUM 5
0 0
0 5
NR 5
5 1
0 9
NR 9
0 0
0 9
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15 5
3 0
17 TOTAL:
17 0
~ 0 0
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i TI-3 As of ist Quarter FY-97 t
Table IA
SUMMARY
OF GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED. AND ISSUES INTEGRATED CUMULATIVE TOTALS FY-83'THROUGH FY-97(IST OVARTER)
ISSUE GIs New GIs GIs TYPE Start + Issues = Sub-Total - Resolved -
Integrated" - Remainder USI 16 0
16 16 0
0 HIGH 24 34*
58 45 10 3
NEDIUM 31 18 49 35 9
5 NR 20 28*
48 38 1
9 TOTAL:
91 80 171 134 20 17
- Extensive revisions to Human Factors issues resulted in priority changes in FY-85 and FY-86.
" GIs Inteorated 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.l.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 1st Quarter FY-97 9
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1 TABLE 2 NUMBER OF GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR FY-83 THROUGH FY-97 (IST 00ARTER) l 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 i
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 Total:
6 15 23 9
10 16 18 7
4 7
10 5
130 TOTAL FROM PRIORITY ABOVE FY-95 FY-96 FY-97 TOTAL i
USI 16 0
0 0
16
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t HIGH 44 0
1 0
45 1
MEDIUM 34 0
1 0
35 NR 36 1
1 0
38 Total:
130 1
3 0
134 i
T2-1 As of 1st Quarter FY-97
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O TABLE 3 r
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR i
Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-83 A-ll 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 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 l
II.E.5.1 (B&W) Design Evaluation NR No. Req.
NRR-0P FY83 03/21/83 i
IV.C.1 Extend Lessons Learned From NR No. Req.
NRR-0P FY83 04/15/83 TMI to Other NRC Programs t
i FY-84 12 BWR Jet Pump Integrity Medium No. Req.
NRR-0P FY83 09/25/84 t
20 Effects of Electromagnetic NR NUREG/
NRR-OP FY83 11/15/83 Pulse on Nuclear Plant Systems CR-3069 40 Safety Concerns Associated NR MPA B-65 07/18/83 12/27/83 With Breaks in the BWR Scram System 45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather i
T3-1 As of 1st Quarter FY-97
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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-84 (Cont.)
50 Reacter 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 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-OP 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-OP 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 NRP-0P FY83 09/28/84 Response Task Force III.D.2.5 Offsite Dose Calculation Manual NR NUREG/
NRR-OP FY83 01/17/84 CR-3332 T3-2 As of 1st Quarter FY-97 e
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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 f.L-E.1 22 Inadvertent Boron Dilution NR GL 85-05 11/05/82 10/15/84 Events A-41 Long Term Seismic Program Medium No Reg.
NRR-0P FY83 10/10/84 B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/65 B-54 Ice Condenser Containments Medium NUREG/
NRR-OP FY83 10/22/84 CR-4001 B-58 Passive Mechanical Failures
. Medium No Req.
NRR-0P FY83 07/09/85 C-Il Assessment of Failure and Medium No Req.
NRR-OP FY83 07/09/85 Reliability of Pumps and Valves I.A.2.2 Training and Qualifications High Policy NRR-0P.FY83 06/24/85 of Operating Personnel Statement (No Req.)
I.A.2.6(4)
Operator Workshops Medium No Req.
NRR-0P FY83 09/25/85 I.A.2.7 Accreditation of Training Medium Policy NRR-0P FY83 06/24/85 Institutions Statement (No Req.)
I.A.3.4 Licensing of Additional Medium Policy NRR-OP FY83 02/12/85 Operations Personnel Statement (No Req.)
I.G.2 Scope of Test Program Medium No Reg.
NRR-OP FY83 10/05/84 T3-3 As of 1st Quarter FY-97
l TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date' Approved Date Number Title Priority Product for Resolution Resolve.d FY-85 (Cont.1 II.B.6 Risk Reduction For Operating High No Req.
NRR-0P FY83 09/25/85 Reactor.s at Sites With High Population Densities II.B.8 Rulemaking Proceedings on High Degraded Core Accidents (a) Hydrogen Rule Rule /
NRR-OP FY83 07/19/85 (b) Severe Accidents Policy NRR-OP FY83 08/12/85 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-0P FY83 07/25/85 and Anomalous Transients III.A.I.3(2)
Maintain Supplies of Thyroid-NR Policy NRR-OP FY83 08/15/85 i
Blocking Agent for Public Statement III.A.3.4 Nuclear Data link Medium No Req.
NRR-OP 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-OP FY83 08/28/85 and Plants that Require Revision Consideration of liquid Pathway Interdiction Techniques III.D.2.3(3)
Establish Feasible Method of NR ESRP NRP,-OP FY83 08/28/85 Pathway Interdiction Revision T3-4
' As of 1st Quarter FY-97 9
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[d' TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR t
i Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 (Cont.)
III.D.2.3(4)
Prepare a Sumary Assessment NR ESRP NRR-OP 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-OP FY83 05/19/86 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 i
(No Req.)
61 SRV Discharge Line Break Medium No Req.
I'l/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-OP FY83 06/07/85 of Procedures ~
III.D.3.1 Radiation Protection Plans High No Req.
NRR-OP FY83 05/19/86 f
HF1.2 Engineering Expertise on High No Req.
10/01/84 10/28/85 l
Shift l
l HFl.3 Guidance on limits and High No Req.
10/01/84 06/26/86 Conditions of Shift Work T3-5 As of 1st Quarter FY-97 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-87 91 Main Crankshaft Failures in NR NUREG-1216 07/85 09/87 Transamerica Ddlaval 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 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 Require. ment 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.I.1 Oraanization and Management 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 Reg.
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 T3-6 As of 1st Quarter FY-97 e
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. TABLE 3 (Continued) i GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR l
Issue Resolution Date Approved Date Number Title Priority Product for Resolution -Resolved i
f.ldE
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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 l
(Req.)
93 Steam Binding of Auxiliary High GL 88-03 10/84 02/88 Feedwater Pumps (No Req.)
t I
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 i
(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 i
Program Statement (No Req.)
I.A.4.2(4)
Review Simulators for High Rule NRR-0P FY83 05/88 Conformance (Req.)
{
A-44 Station Blackout 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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T3-7 As of 1st Quarter FY-97 i i
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.)
from Steam Generator During a Line Break A-3,4,5 Steam Generator Tube Integr.ity 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.)
FY-89 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.)
T3-8 As of 1st Quarter FY-97 9
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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
- /89 of Westinghouse Sulid 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 Backfits (Req.)
125.I.3 SPDr Availability NR GL 89-06 05/06/88 04/89 (No. Req.)
134 Rule on Degree and Experience High Policy 01/86 08/89 Requirements for Senior Statement Operators (No Req.)
A-17 Systems Interaction USI NUREG-ll74 01/79 08/89 (No Req.)
l A-40 Seismic Design Criteria USI SRP Revisions 01/79 09/89 (Req.)
l A-47 Safety Implications of Control USI GL 89-19 02/81 08/89 Systems (Req.)
l A-48 Hydrogen Control Measures and USI Rules (Req.)
02/81' 04/89 i
Effects of Hydrogen Burns on Safety Equipment HF1.1 Shift Staffing High Reg. Guide 10/01/84 05/89 1.114, Rev. 2 (Req.)
T3-9 As of 1st Quarter FY-97
. ~. - -. -. - - -
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Resolution Date Approved Date Number Title Priority Product for Retolution Resolved Issue FY-89 (Cont.)
HF4.1 Inspection Procedure for High IN 86-64 10/01/84 10/88 Upgraded Emergency Operating (No Req.)
Procedures I.F.1 Expand QA List High No Req.
NRR-OP FY83 01/89 II.C.4 Reliability Engineering High No Req.
NRR-OP FY83 10/88 II.E.6.1 Test Adequacy Study Medium GL 89-10 NRR-OP FY83 06/89 (Req.)
FY-90 70 PORV and Block Valve Medium GL 90-06 05/14/84 06/90 Reliability 75 Generic Im?lications of NR Req.
10/19/83 05/90 ATMS Event s 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 Haximum Precipitation (Req.)
As of 1st Quarter FY-97 T3-10 8
9 e
D Ch O
V TABLE 3 (Continued) t
- GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR 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 Design for the Reduction 3
of Vulnerability to
[
Industrial Sabotage i
C-8 Main Steam Line High No Req.
. NRR-OP FY83 03/90
,i Isolation Valve Leakage' Control Systems j
l 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 System Failures at (Req.)
Multiplant Sites t
135 Steam Generator Medium No Req.
05/27/86 03/91 and Steam Line Overfill II.J.4.1 Revise Deficiency NR Rule NRR-OP FY83 07/91 Report Requirements (Req.)
j 4
FY-92 29 Bolting Degradation or High No Req.
NRR-0P FY-83 10/91 Failure in Nuclear Power Plants i
i T3-Il As of 1st Quarter FY-97
..m
____.__m._m________,. _ _.
m
.. m.
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 CR-6010 (No Req.)
79 Unanalyzed Reactor Medium GL 92-02 NRR-0P FY-84 05/92 Vessel Thermal Stress (No Req.)
During Natural Convection Cooldown 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 T3-12 As of 1st Quarter FY-97 9
9 9
/
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL' YEAR Issue Resolution Date Approved Date Number Title Priority Product-for Resolution Resolved FY-93 Cont.)
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 1.9, Rev. 3; 1.160.(Req.)
HF4.4 Guidelines for Upgrading Other High No Req.
10/01/84 07/93 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.D.3 Safety System Status Nonitoring Nedium No Req.
NRR-0P FY83 09/93 FY-94 57 Effects of Fire Protection Medium No Req.
06/08/88 02/94 System Actuation on Safety-(NUREG-Related Equipment 1472) 106 Piping and Use of Highly Nedium 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 T3-13 As of 1st Quarter FY-97
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-0P FY83 02/94 Conditions Inside the TMI-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 1st Quarter FY-97 9
9 9
7 9
-YF re L
t r
A a
T 3
5 9
7 u
O 1
Q T
ts i
f 0,
B.
s 58031 A
D 46779 5
B 11111 T
2.
0 0
YF_
)
RA E
Y LA 1
C 0
S 0
I Y
F F
YB f
NO I
T 0
4 U
0 L
0 1
E O
Y L
S F
B 4
E A
T R
T R
f O
F D
E 9
A.
L 9
23 2
U 77 D
Y 11 E
F HC S
s I
SG 8
7 9
51 0
1 67 9
3 Y
11 1
F 7
9 88751 6
3 75156 6
7 Y
2 1 - - -
1 F
BBB YT I
M R
U L
O H
I A
I G
D T
R I
E R
O P
H M
N T
a w
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-96 Date 23 Reactor Coolant Pump Seal RES/ DER /GSIB H
NRR-OP FY83 01/97 04/97 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 06/97 12/97 Subsequent to A LOCA 78 Monitoring of Fatigue Transient RES/ DER /GSIB M
07/10/92 11/96 02/97 Limits for Reactor Coolant System 158 Performance of Safety-Related RES/ DER /GSIB M
01/26/94 08/97 08/97 Power-Operated Valves Under Design Basis Conditions B-17 Criteria for Safety-Related RES/DSR/HFBR M
03/22/82 06/97 06/97 Operator Actions B-55 Improve Reliability of Target NRR/DE/EMEB M
NRR-OP FY83 08/97 08/97 Rock Safety Relief Valves B-61 Allowable ECCS Equipment Outage RES/DSR/PRAB M
NRR-OP FY83 01/97 04/97 Periods 145 Actions to Reduce Common RES/DSR/PRAB NR 02/11/92 02/97 TBD Cause Failures 166 Adequacy of Fatigue Life RES/ DER /GSIB NR 04/01/93 11/96 02/97 of Metal Components 168 Environmental Qualification HRR/DSSA/SPLB NR 04/01/93 TBD TBD of Electrical Equipment T4-2 As of 1st Quarter FY-97 e
e e
._..._.. _-..-._ _.~. _ _. _
O O
O Table 4A (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current i
Issue Lead Office /
Approved for Date at end Resolution i
Number Title Division / Branch Priority Resolution of FY-96 Date I
170 Reactivity Transients and RES/DSR/RPSB NR 11/09/94 TBD TBD Fuel Damage Criteria for High Burn-Up Fuel t
172 Multiple System Responses RES/DSR/PRAB NR 12/07/95 12/98 12/98 i
Program i
173.A Spent Fuel Storage Pool:
NRR/DSSA/SPLB NR 06/24/96 10/98 10/98 Operating Facilities l
173.B Spent Fuel Storage Pool:
NRR/DSSA/SPLB NR 06/24/96 TBD TBD Permanently Shutdown Facilities 190 Fatigue Evaluation of Metal RES/ DER /GSIB NR 08/26/96 12/97 12/97 Components for 60-Year Plant Life 191 Assesstnent of Debris Accumulation RES/ DER /GSIB NR 09/--/96 TBD TBD
t Total:
17 i
~
l T4-3 As of 1st Quarter FY-97
O O
O TABLE 5 NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 THROUGH THE IST 00ARTER OF FY-97 ISSUE TYPE FY-83 EyY-Bi FY-85 FY-86 FY-87 FY-88 fl-Bj! FY-90 EY-M Ey-E 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/EI 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'
O 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 1st Quarter FY-97
TABLE 5 (Crntinued)
NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 THROUGH THE IST OVARTER OF FY-97 ISSUE TYPE Total (B/F) FY-95 FY-96 FY-97 Total Issues Identified 266 2
21 0
289 to be Prioritized Issues Identified 25 0
3 0
28 to be Reprioritized Total:
291 2
24 0
317 New Issues (Entered into GIMCS)
High 59 1
0 0
60 Medium 18 0
0 0
18 Nearly-Resolved 21 1
5 0
27
'0 2
5 0
105 Sub-total:
5 Resolved 11 0
5 0
16 Low 18 0
0 0
18 Drop 82 0
0 0
82 RI/LI/EI 50 0
7 0
57 Integrated 29 0
0 0
29 Total Issues Prioritized:
288 2
17 0
307
[ Annual Progress]/
Remaining Issues to be Prioritized or Reprioritized:
[
3 0
+7 0]
10
=
T5-2 As of 1st Quarter FY-97 e
e e
J G
O 1
TABLE 6 GENERIC ISSUES PRIORITIZED AS OF IST GUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-83 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 42 Combination Primary / Secondary System LOCA 09/82 04/83 S(18) 45 Inoperability of Instrumentation Due to Extreme 09/82 09/83 NR 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 l
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.I) l Applied to a Steam Generator Overfill Event 58 Inadvertent Containment Flooding 09/82 08/83 DROP 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 i
Natural Convection Cooldown D-1 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 T6-1 As of 1st Quarter FY-97
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF IST OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-84 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 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 Wetwel! Airspace is/82 11/83 MEDIUM 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 HEDIUM 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 II 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 Iodine Spiking 09/82 06/84 DROP T6-2 As of 1st Quarter FY-97 e
e e
._,_m t
O O
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF IST GUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority f.hE 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 Human 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 1st Quarter FY-97
TABLE 6 (Continutd)
GENERIC ISSUES PRIORITIZED AS OF IST OVARTER FY-97 Identification Date Current Action Item /
Date Prioritized Priority Issue No.
Title FY-85 (Cont.)
B-19 Thermal 11ydraulic 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)
FY-86 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 OROP 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 As of 1st Quarter FY-97 T6-4 8
9 e
TA8LE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF IST GUARTER FY-97 Identification Date Current Action Item /
Issue No.
T1tle Date Prioritized-Priority FY-86 (Cont.1 125.I.2.a PORV. Reliability - Test Program 11/85 06/86 S(70) 125.1.2.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)
Environment 125.II.3-Review Steam / Feed Line Break Mitigation 11/85 08/86 DROP Systems for Single Failure 125.11.4 OTSG Dryout and Reflood Effects 11/85 09/86 DROP 125.11.7 Reevaluate Provisions to Automatically 11/85 09/86 HIGH Isolate Feedwater from Steam Generator During Line Break-125.11.9 Enhance Feed-and-Bleed Capability 11/85 08/86 S(A-45) 125.II.14 Retrote Operation of Equipment Which Must 11/85 08/86 LOW Now be Operated Locally 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 C-4 Statistical Methods for ECCS Analysis 02/83 06/86 RI(R)
C-5 Decay Heat Update 02/83 06/86 RI(R)
C-6 IOCA 58 eat Scurces 02/83 06/86 RI(R)
FY-87 113 Dynamic Qualification Testing of large Bore-03/85 07/87 IIIGH Hydraulic Snubbers
-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.I.8 Procedures and Staffing for Reporting to 11/85 06/87 DROP NRC Emergency Response Center T6-5 As of Ist Quarter FY-97
^
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF IST 00ARTER FY-97 Identification Date Current Action Item /
Issue No.
Title Date Prioritized Priority FY-87 (Cont.)
125.II.l.a Two-Train AFW Reliability 11/85 10/86 DROP 125.II.1.b Review Existing AFW Systems for Single Failure 11/85 10/86 HIGH 125.II.l.c NUREG-0737 Reliability Improvements 11/85 10/86 DROP 125.II.I.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.II.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 03/87 DROP 125.II.10 Hierarchy of Impromptu Operator Actions 11/85 02/87 DROP 125.II.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 Power 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 HIGH 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 1st Quarter FY-97 e
_.__. _..._ _...__..__.-._--. _ -.. _ _. _..-. _ _ _~.. _ _ m.
\\
TABLE 6 (Continued) 1 GENERIC ISSUES PRIORITIZED AS OF IST 00ARTER FY-97 i
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 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 i
125.11.11 Recovery of Main Feedwater as Alternative to AFW 11/85 06/88 DROP 11/85 03/88 DROP 125.II.13 Operator Job Aids 126 Reliability of PWR Main Steam Safety Valves -
03/86 03/88 LI 136 Storage and Use of Large Quantities of 09/86 03/88 LI i
Cryogenic Combustibles on Site C-14 Storm Surge Model for Coastal Sites 02/83 05/88 LI(DROP)
III.D.1.l(2) Review Information on Provisions for leak 12/82 09/88 DROP t
r Detection f
111.D.1.1(3) Develop Proposed System Acceptance Criteria 12/82 09/88 DROP i
f.EE.9.
15*
Radiation 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 1
1 T6-7 As of.Ist Quarter FY-97 1
t m.
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF IST 00ARTER FY-97 Identification Date Current Action Item /
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 12/86 02/90 DROP 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 S(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 1st Quarter FY-97
3(V pJ Q
V TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF IST QUARTER FY-97 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority 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 l
100 Once-Through Steam Generator Level 09/84 09/91 DROP 120 On-line Testability of Protection Systems 08/85 11/90 MEDIUM 143 Availability of Chilled Water Systems and 10/87 03/91 HIGH Room Cooling 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 118 Tendon Anchorage Failure 07/85 01/92 RESOLVED Previous Priority Evaluation Published in NUREG-0933 T6-9 As of 1st Quarter FY-97
l l
TABLE 6 (Continu*d)
GENERIC ISSUES PRIORITIZED AS OF IST OVARTER FY-97 Identification Date Current Action Item /
Date Prioritized Priority Issue No.
Title i
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/N DROP 138 Deinerting of BWRs With MARK I and II 10/86 10/L LOW Containments During Power Operations Upon Discovery oi Reactor Cooling System Leakage or a Train of a 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 156.2.1 Severe Weather Effects on Structures 02/91 01/92 DROP 156.2.2 Design Codes, Criteria, and Load 02/91 07/92 DROP Combinations As of 1st Quarter FY-97 T6-10 8
9 e
s O
O O
?
TABLE 6 ftontinueo)
GENERIC ISSUES PRIORITIZED AS OF IST GUARTER FY-97 i
Identification Date Current Action Item /
Issue No.
Title Date
_Prioritized Priority t
I 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-l and Components j
156.3.1.1 Shutdown Systems 02/91 03/92 DROP 156.3.1.2 Electrical Instrumentaion and Control 02/91 03/92 DROP 156.3.2 Service and Cooling Water Systems 02/91 03/92 DROP 7
156.3.3 Ventilation Systems 02/91 09/92 DROP
~
156.3.4 Isolation of High and Low Pressure 02/91 12/h DROP Systems 156.3.5 Automatic ECCS Switchover 02/91 11/91 5(24)
,f 156.3.6.1 Emergency AC Power 02/91 02/92 S(B-56) l
}
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
,i FY-93 l
146 Support Flexibility of Equipment and Components 01/89 09/93 RESOLVED i
04/89 10/92 LOW l
149 Adequacy of Fire Barriers 03/90 01/93 LOW i
152 Design Basis for Valves That Might Be 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 159 Qualification of Safety-Related Pumps While 10/91 09/93 DROP Running on Minimum Flow 160 Spurious Actions of Instrumentation Upon 10/91 09/93 DROP i
Restoration of Power 161 Use of Non-Safety-Related Power Supplies in 10/91 03/93 DROP i
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 t
T6-11 As of 1st Quarter FY i
-. _ _. _ _ _. _ ~ _ -.. - _ _, _.... _.,.. _, _
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. _ _. _... ~,... -. _ - - _ _ _ _ _.. - - _, _. -. _ - _ _ -.. - _ _...,. - -...
. TABLE 6 w ntinueal GENERIC ISSUES PRIORITIZED AS OF IST 00ARiER FY-97 Identification Date Current Action Item /
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 FY-94 158 Performance of Power-0perated Valves Under 09/91 01/94 MEDIUM Design Basis Conditions 165 Spring-Actuated Safety and Relief Valve 10/92 11/93 HIGH Reliability 167 Hydrogen Storage Facility Separation 06/93 09/94 LOW FY-95 170 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-Oil 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 179 Core Performance 02/96 05/96 LI 180 Notice of Enforcement Discreticn 02/96 05/96 LI (Resolved) 181 Fire Protection 02/96 05/96 LI
' As of ist Quarter FY-97 T6-12
o o
IABLE b (Lontinueus i
GENERIC ISSUES PRIORITIZED AS OF IST 00ARTER FY-97.
Identification Date Current Action Item /_
Date Prioritized Priority Issue No.
Title.
FY-96 (Cont.)
i 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 E!
l 190 Fatigue Evaluation of Metal Components for 08/96 08/96 NR 60-Year Plant Life 191 Assessment of Debris Accumulation on PWR 09/96 09/96 NR Sump Performance i
f i
T6-13 As of Ist Quarter FY-97
O O
O TABLE 7 GENERIC ISSUES TO BE PRIORITIZED AS OF IST OUARTER FY-97 Identification Current Action Item /
Date Schedule Title Issue No.
02/91 03/97 156.6.1 Pipe Break Effects on Systems and Components 06/92 02/97 Multiple Steam Generator Tube Leakage 10/93 02/97 163 BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure Door Interlock Failure Resulting from Faulty MicroSelectron-High 04/96 TBD 169 NMSS-0001 Dose Rate Remote Afterloader 07/96 TBD Significant Quantities of Fixed Contamination Remain in Krypton-85 NMSS-0002 Leak-Detection Devices After Venting 07/96 TBD Corrosion of Sealed Sources Caused by Sensitization of Stainless NMSS-0003 Steel Source Capsules During Shipment 07/96 TBD Overex;iosures Caused by Sources Stolen from Facility of Bankrupt l
NMSS-0004 Licensee TOTAL: 7
.t As of 1st Quarter FY-97 '
-T7-1
=
O O
TABLE 8 GENERIC ISSUES TO BE REPRIORITIZED AS OF IST 00ARTER Q-9].
Previous Ident.
Current Action Item /
Issue No.
Title Priority Date Schedule 71 Failure of Resin Demineralizer Systems and Thcar Effects LOW 04/96 09/97 on Nuclear Power Plant Safety 107 Nain Transformer Failures LOW 04/96 09/97 152 Design Basis for Valves That Might Be Subjected to LOW 04/96 09/97 Significant Blowdown Loads TOTAL: 3 T8-1 As of 1st Quarter FY-97
- - -,.. ~. -. _.. - _... _ _ _ _ _ _. _ _ _ _ _ _ _ _, _ _
TABLE 9 REGULATORY IMPACT ISSUES SCHEDUtED FOR RESOLUTION
?
AS OF IST UUARTER FY-97 Lead Office /
l Division /
Resolution i
Issue Branch Date Number Title NRR/DRPW/P031 TBD
{
182 General Electric Extended Power Uprate f
r
?
TOTAL:
1 i
t i
-1 L
t
?
i i.
I
)
i Asof1stQuarterFY-97j T9-1 i
.~.?
O
(
. O TABLE 10 LICENSING-ISSUES SCHEDULED FOR RESOLUTION AS OF IST 00ARTER FY-97 Lead Office /
Issue Division /
Resolution Number Title Branch Date 148 Smoke Control and Manual Fire-Fighting Effectiveness RES/DSR/PRAB TBD 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
TOTAL: 4 T10-1 As of 1st Quarter FY-97 i
- =
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l i
TABLE 11 l
ENVIROMENTAL ISSUES SCHEDULED FOR RESOLUTION AS OF IST GUARTER FY-97 i
Lead Office /
l
. Division /
Resolution Issue Branch Date Number Title i
184 Endangered Species NRR/DRPM/PDND TBD r
i TOTAL: 1 i
i i
7 i
f i
i
~
i L
1 4
h l
Til-1 As of 1st Quarter FY-97 i
a O
O TABLE 12 RESOLVED GENERIC ISSUES WITH ONGOING ACTIVITY.
AS OF IST 00ARTER FY-97 Lead Office /
Issue Division /
Resolution Number Title Branc'a Date 116 Accident Management NRR/DSSA/SCSB TBD 155.1 More Realistic Source Term Assumptions NRR/DRPM/PERB TBD HF5.2 Review Criteria for Human Factors Aspects of Advanced RES/DSR/HFBR 12/97 Controls and Instrumentation II.E.6.1 In-Situ Testing of Valves NRR/DE/EMEB TBD TOTAL: 4 T12-1 As of ist Quarter FY-97
O O
O TABLt 13 RELATED GENERIC ACTIVITIES AS OF IST GUARTER FY-97 Lead Office /
Issue Division /
Resolution Number Title Branch Date RGA-001 Boiling Water Reactor Internals 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 11/97 RGA-006 SRP Revision NRR/ DISP /PIPB TBD RGA-007.1.2D PRA Implementation Plan - Graded QA NRR/DRCH/HQMB 04/98 TOTAL: 6 T13-1 As of 1st Quarter FY-97
f
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RUN DATE: 02/24/97 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 SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS 12 155.1 MORE REALISTIC SOURCE TERM ASSUMPTIONS 14 158 DERF OF SAFETY-RELATED POWER-OPERATED VALVES UNPER DESIGN 8 ASIS CONDIT 18 165 SPAING-ACTUATED SAFETY AND RELIEF VALVE REL M81LITY 20 166 ADEQUACY OF FATIGUE LIFE OF METAL COMPONEXTS 24 168 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 26 170 REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH 8URNUP FUEL 28 171 ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA 32 172 MULTIPLE SYSTEM RESPONSES PROGRAM 34 173.A SPENT FUEL STORAGE POOL: OPERATING FACILITIES 35 173.8 SPENT FUEL STORAGE POOL: PERMANENTLY SHUTDOWN FACILITIES 37 178 EFFECT OF HURRICANE ANDREW ON TURKEY POINT 39 179 CORE PERFORMANCE 41 181 FIRE PROTECTION 44 182 GENERAL ELECTRIC EXTENDED POWER UPRATE 47 184 ENDANGERED SPECIES 50 190 FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR PLANT LIFE 52
,191 ASSESSMENT OF DE8RIS ACCUMULATION ON PWR SUMP PERFORMANCE 54
RUN DATE: 02/24/97 INDEX OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER TITLE PAGE B-17 CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS 56 B-55 IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES 58 B-61 ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS 61 HF 5.2 REV. CRIT. FOR HUHAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
64 II.E.6.1 IN-SITU TESTING OF VALVES 66 RGA 001 BOILING WATER REACTOR INTERNALS 70 RGA 002 REACTOR PRESSURE VESSEL FRACTURE TOUGHNESS 73 RGA 003 DRY CASK STORAGE OF SPENT FUEL 75 RGA 004 THERMO-LAG FIRE BARRIERS 78 RGA 005 RCS DRAINDOWN 80 RGA 006 SRP REVISION 82 RGA 007.1.2D PRA IMPLEMENTATION PLAN - GRADED QA 84 9
9 9
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
1 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES j
IDENTIFICATION DATE: 12/BOC PRIORITIZATION DATE: 04/83C TYPE: GSI PRIORITY: H t
TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS-l TAC NUMBERS:
RESOLUTION DATE: 04/97 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN, (APPENDIX G)
I FIN CONTRACTOR CONTRACT TITLE A3751 BNL REACTOR COOLANT PUMP (RCP) SEAL INTEGRITY A3771 BNL ASSESS EFFECT OF MECH. MAINT. RCP SEAL A3806 BNL EVAL. ADEQ. OF RCP SEAL INSTR. & RESP. TO RCP A6322 INEL RCP SHAFT SEAL BEHAVIOR DURING ST. BLACKOUT 82953 PNL REACTOR COOL. PUMP SEAL FAIL. VAL. IMP. MALYSIS B3049 ETEC LEAK RATE ANALYSIS OF WESTINGHOUSE RCP D1760 SCIENTECH REG. ANAL. FOR GI-23. RCP SEAL FAILURES l
W6211 BNL SOLUTIONS TO MAINTAIN RCP SEAL INTEGRITY i
[
t WDRK SCOPE THE TAP FOR THIS ISSUE WAS REVISED TO INCOR-SHOULD TAKE, IF ANY. TO REDUCE RCP SEAL FAILURE TO AM PORATE WORK NECESSARY TO COMPLETE GSI 65.
REVIEW ACCEPTABLE LEVEL COMMENSURATE WITH THE PO TENTIJL SAFETY PWR RCP SEAL FAILURES CAUSED BY MECHANICAL FAILURES CONSEQUENCES OF SEAL FAILURE. THE PROGRA*. CONSISTS OF AND LOSS OF SEAL COOLING TO ASCERTAIN IF INCREASED RRC 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 - E'fALUATE RCP SEAL COOLING FOR ALL MODES OF OPERA-OPERATION, TESTING. AND MAINTENANCE ON SEAL FAILURE TION FOR WHICH SEAL COOLING IS REQ'D U'3ING THE MECHANISMS. REVIEW THE RELIAB. OF SEAL COOLING SYSTEMS RELIABILITY OF TYPICAL RCP SEAL COOLIDG SYSTEM i
AND IDENTIFY METH00S TO MINIMIZE THE EFFECTS OF LOSS OF DESIGMS.
t SEAL COOLING. PERFORM A RISK ASSESSMENT OF SEAL FAILURE TASK 3 - REVIEW MECHANICAL AND MAINTENANCE-IMPUCED L
FROM MAINTENANCE AND MECHANICAL EFFECTS.
FAILURE MECHANISMS.
THIS PROGRAM WILL DETERMINE WHAT STEPS THE NRC TASK 4-FEASIBILITY STUDY TO IDENTIFY MOST EFFECTIVr FIx, i
STATUS AM NRR GENERIC LETTER FOR INFORMATION ONLY WAS ISSUED REGULATORY GUIDE DG-1008 AND THE DRAFT REGULATORY ANALYSIS, 1
MAY 2, 1991. TO INFORM LICENSEES OF THE POTENTIAL IMPACT NUREG-1401. THE STAFF DECIDED TO PROCEED WITH A RULEMAKING i
DN SB0 ANALYSES. A FEDERAL REGISTER NOTICE WAS PUBLISHED FOR OFF-NORMAL CONDITIONS. WHILE THE NORMAL CONDITIONS HAVE L
APRIL 19, 1991, REQUESTING PUBLIC COMMENT ON DRAFT BEEN ADDRESSED BY APPROPRIATE GENERIC COMMUNICATIONS.
l i
AS OF FY97 QUARTER 1 L
ii
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
2 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES AFFECTED DOCUMENTS PROBLEM / RESOLUTION (1) kbkFblLbWIkbREPbRhkbkVkbEENIkSbkb hhhkhkFFkkkkbbbkkbbkTEbCkbkbbkhEkkk$kbEkhkhF 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-4821. " REACTOR COOLANT PUMP SHAFT SEAL STABILITY REVISED AND PROVIDED TO THE COMMISSICN FDR REVIEW AND DURING STATION BLACKOUT" APPROVAL. THE COMMISSION DISAPPROVED ISSUANCF 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 KAINTENANCE-ABDUT THE COMMISSION'S DECISION ON THE RESOLUTION OF GI-23 INDUCED FAILURE OF MAIN 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 RELAYED TO'GI-23, REACTOR COOLANT PUMP SEAL FAILURES" NUREG/CR-5167, " COST BENEFIT ANALYSIS FOR GI-23. REACTOR COOLANT PUMP SEAL FAILURE" DRAFT NUREG/CR-5918 " ANALYSIS OF PUBLIC COMMENTS ON GI-23, REACTOR COOLANT PUMP SEAL FAILURE" (DRAFT REPORT IN PDR)
(2) RULEMAKING RDB-333 (3) DRAFT REGULATORY GUIDE DG-1008 (WITHDRAWN BY CRGR)
ORIGINAL CURRENT ACTUAL MILEST0NE5 DATE DATE DATE TAP ISSUED FOR COMMENT 04/83 03/83 TAP APPROVED BY DSI DIR 10/83 10/83 ISSUED REQUEST FOR PROPOSAL TO BNL FOR 11/83 11/83 COMPONENT COOLING WATER PRA TRANSFER RESOLUTION REPONSIBILITY FROM DSI TO 06/84 06/84 DE TRANSFER RESOLUTION RESPONSIBILTY FROM DE TO 05/85 05/85 DST /GIB AS OF FY97 QUARTER 1 O
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RUM DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL. SYSTEM PAGE:
3 ISSUE NUMBERt 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE COMPLETE DOCUMEN. OF BACKGROUNO 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 REY. RCP SEAL COOLING INSTR. (TASK 2)
EVALUATE MECHANICAL ANG MAINTENANCE-INDUCED 01/85 01/88 FAILURE MECHANISMS (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 08/85 05/90 ACRS REVIEW OF DTR COMPLETE 11/85 09/90 CONCURRENCE BY OTHER OFFICES 09/85 10/90 l
DTR SENT TO CRGR 10/85 10/90 CRGR REVIEW OF DTR COMPLETE 11/85 03/9, g
FRN OF ISSUANCE OF PROPOSED RESOLUTION FOR 12/85 04/91 i
PUBLIC COMMENT DRAFT PERFORMANCE 07/91 08/91 s
PUBLIC COMMENT PERIDO ENDS 09/91 11/91 l
COMPLETE REVIEW AND COMPILATION OF PUBLIC 04/86 02/92 COMMENTS RECEIPT OF GUIDANCE FROM EDO ON RULEMAKING 05/92 11/92 I
r AS OF FY97 QUARTER 1 i
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
4 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PkbPbSEbkPPRbEbbThNkkFbkkbkMkbbPERITkbk 55hhh 5hhhh 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 $80 05/93 10/93 ACRS AND CRGR REVIEW OF PROPOSED itULE 12/92 03/94 PROPOSED RULE TO EDO 02/93 09/94 PROPOSED RULE TO COMMISSION-02/93 11/94 COMMISSION'S REVIEW 03/93 03/95 PUBLICATION OF IN 95-42 INFORMING INDUSTRY' 09/95 09/95 0F COMMISSION'S DECISION CLOSE THE ISSUE BY GENERIC COMMUNICATION 09/95 04/97 O
AS OF FY97 QUARTER 1 O
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
5 ISSUE MUMBER: 78 TITLE: MONITDRING DF FATIGUE TRANSIENT LIMITS FOR REACTDR CDOLANT t
IDENTIFICATION DATE: OS/83C PRIDRITIZATION DATE: 07/92C TYPE:
PRIORITY: M
[
TASK MANAGER: K. SHAUKAT OFFICE /DIVISIDM/ BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: 4 TAC MUMBERS:
RESOLUTIDM DATE: 02/97 WORK AUTHORIZATION: 7/10/92 MEM0/BECKJORD TO MINNERS. " MONITORING OF FATIGUE..."
4/1/93 MEM0/BECKJDRD TO SNIEZEK. " RESOLUTION OF FATIGUE..."
FIN CONTRACTDR CONTRACT TITLE W6077 ANL STATISTICAL ANALYSIS OF FATIGUE DATA WDRK SCOPE
[
TO DEVELOP GUIDANCE ON POTENTIAL FATIGUE DEGRADATION OF GUIDANCE IS APPLICABLE TO THOSE REMAINING YEARS OF PLANT COMPONENT OF THE RCPB FDR ALL OPERATING PLANTS. THIS OPERATION UNDER THE CURRENT 40-YEAR LICENSE.
i 5TATUS BECAUSE THE DRIGINAL DESIGN BASIS OF THE REACTOR CDOLANT INTO NRR'S GENERIC ISSUE 166 ENTITLED " MONITORING DF PRESSURE BOUNDARY (RCPB) DID MOT ACCDUMT ADE @ TELY FOR THE FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT."
r EFFECTS OF THE REETOR COOLANT HARSH ENVIRONENTS DURING THE OUTCOME OF THE GI-78 AND 166 WORK IS THAT NO i
OPERATION ON THE RCPB FATIGUE RESISTANCE. GENERIC ISSUE 78 FATIGUE CONCERNS EXIST FDR 40-YEAR PLANTS, BUT MORE STUOY 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 SHDWED EVALUATION IS PLANNED UNDER A NEW GENERIC ISSUE GI-190.
i THE RISK OF FAILURE OF REACTDR PRIMARY CIRCUIT CDNPDNENTS TO A CLOSE-DUT MEMO TO THE EDO IS BEING PREPARED.
BE ACCEPTABLY LDW FDR 40-YEAR PLANTS. THIS WAS INTEGRATED l
r AFFECTED DDCUMENTS PRDBLEM/ RESOLUTION
- T0 8E DETERMINED NONE.
i t
DRIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GI-78 ASSIGNED TO RES/DSIR/EIB 07/92 07/92 l
AS OF FY97 QUARTER 1 b
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
6 ISSUE NUMBER: 78 TITLE: MONITORING OF 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 DIVISIONS 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 ANL 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 ANL PRESENTATION 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 STEL.. 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)
CLOSEQUT MEMO AND PRA ANALYSIS (STAINLESS 05/95 08/95 AND NICKEL ALLOY STEELS) TO NRR FATIGUE ACTION PLAN (NRR), INCLUDES GI-78 09/95 09/95 WORK AS OF FY97 QUARTER 1 O
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7-ISSUE NUMBER: 78 TITLE: MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE CLOSEOUT MEMO TO EDO FROM RES 06/95 02/97 9
F AS OF FY97 QUARTER 1 O
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8 ISSUE NUMBER: 116 TITLE: ACCIDENT MANAGEMENT IDENTIFICATION DATE: 04/85C PRIORITIZATION DATE: 09/90C TYPE: GSI PRIORITY: H TASK MANAGER: R. PALLA 0FFICE/ DIVISION / BRANCH: NRR / OSSA /SCSB ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE:
TAC NUMBERS: M91966 M91641 WORK AUTHORIZATION: SECY-B8-147, " INTEGRATION PLAN FOR CLOSURE OF SEVERE ACCIDENT ISSUES." 05/25/B8 FIN CONTRACTOR CONTRACT TITLE L1697 ORNL TECHNICAL ASSISTANCE IN SUPPORT OF THE REACTOR SYSTEMS BRANCH WDRK SC0PE hPkbiFibkbk[bkh[kbLbbkbikEkkEfkkbhibkPLkkkRE[
bbkPLkkE3[Lbh ikSPhbh[bkh kkb FblLbbP kbl5 bElbLbP k (1) COMPLETE THE REVIEW OF BWROG SAMG DOCUMENTS, (2) CONDUCT INSPECTION PROCEDURE FOR USE AT REMAINING PLANT AND HOLD A SITE VISITS IN 1996 TO OBSERVE HOW THE ELEMENTS OF THE PUBLIC WORKSHOP. DASED 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 INFCRMATION APPROACH AND SCHEDULE FOR EVALUATING A/M IMPLEMENTATION FOR AND PERSPECTIVES OBTAINED THROUGH THE SITE VISITS, (4)
THE REMAINING PLANTS.
STATUS SEVERE ACCIDENT MANAGEMENT GUIDELINE DOCUMENTS HAVE BEEN PILOT INSPECTIONS HAS BEEN COMPLETED. COMMENTS ON THE DRAFT SUBMITTED BY EACH OF THE PWR OWNERS GROUPS AND REVIEWED TI HAVE BEEN RECEIVED FROM THE NRC REGION OFFICES. THE BY THE STAFF. THE BWROG SUBMITTED A SEVERE ACCIDENT STAFF MET WITH INDUSTRY ON FEBRUARY 22, 1996. AND ACRS ON MANAGEMENT OVERVIEW DOCUMENT ON FEBRUARY 3, 1995 AND A MARCH 1, 1996. TO DISCUSS PLANS FOR INSPECTING UTILITY RESP 0MSE TO STAFF COMMENTS ON THE OVERVIEW DOCUMENT ON IMPLEMENTATION OF THE FORMAL INDUSTRY POSITION ON SEVERE MARCH 6, 1996. THE BWROG SUBMITTED REV. 0 0F THE ACCIDENT MANAGEMENT AND MAJOR ELEMENTS OF THE DRAFT TI.
THE EMERGENCY PROCEDURE AND SEVERE ACCIDENT GUIDELINES (EP/ SAG)
STAFF WILL VISIT APPROXIMATELY 2 TO 4 SITES IN AND TECHNICAL BASIS REPORT ON AUGUST 29, 1996. THE STAFF LATE 1996/EARLY 1997 FOR THE PURPOSE OF OBTAINING AN EARLY HAS CONTRACTED WITH DAK RIDGE NATIONAL LABORATORY TO UNDERSTANDING OF HOW THE VARIOUS ELEMENTS OF THE FORMAL PERFORM A HIGH LEVEL REVIEW OF THE DOCUMENTS. THE INDUSTRY POSITION ARE BEING IMPLEMENTED. THE INFORMATION TARGET DATE FOR COMPLETING THE REVIEW OF THE BWROG AND PERSPECTIVES OBTAINED THROUGH THESE VISITS AS WELL AS MATERIAL IS DECEMBER 1996. A MEETING TO DISCUSS SPECIFIC 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 IN NOVEMBER 1996.
THE PUBLIC AFTER THE INFORMATION-GATHERING VISITS.
LICENSEE TARGET DATES FOR COMPLETING A/M IMPLEMENTATION SIE NRR DIRECTOR'S MONTHLY REPORT FOR LATEST STATUS.
HAVE BEEN SUBMITTED TO NRC, AND A DRAFT TI FOR USE IN THE AS OF FY97 QUARTER 1 O
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9 ISSUE MUMBER: 116 TITLE: ACCIDENT MANAGEMENT AFFECTED DOCUMENTS PROBLEM / RESOLUTION GL 88-20. SUPPLEMENT 2 NONE 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) DF TI FOR 11/95 11/95 PILOT INSPECTIONS REVIEW BWROG SEVERE ACCIDENT MANAGEMENT 08/96 12/96 GUIDANCE (SAMG) DOCUMENTS SITE VISITS OF "IN-PROGRESS" ACTIVITIES 11/96 02/97 REVISED DRAFT OF TI FDR PILOT INSPECTIONS 12/96 03/97 TO MEI AND PUBLIC FINAL TI FOR PILOT INSPECTIDMS 03/97 05/97 COMPLETE PILOT INSPECTIONS AND FOLLOWUP 12/97 12/97 ISSUE DRAFT REVISED INSPECTION PROCEDURES 03/98 03/98 (IP)
HOLD PUBLIC MEETING / WORKSHOP 05/98 05/98 ISSUE FINAL IP 07/98 07/98 REVIEW REMAINING PLANTS AS OF FY97 QUARTER 1
RUN DATE: 02/24/97 GENERI'C ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
10 ISSUE NUMBER: 145 TITLE: ACTIONS TD REDUCE COMMON CAUSE FAILURES IDENTIFICATION DATE: 07/85C PRIORITIZATID'N DATE: 02/92C TYPE: GSI PRIORITY: M TASK MANAGER: E. CHELLIAH OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE:
WORK AUTHORIZATION: MEMORANDUM FROM E. S. BECKJORD TO W. MINNERS DATED FEBRUARY 11, 1992 FIN CONTRACTOR CONTRACT TITLE L1125 L2553 BNL TECHNICAL SUPPORT TO GI-145 W0RK SC0PE THE ACTIONS REQUIRED TO RESOLVE THE ISSUE ARE MINIMAL. THE AVAILABLE ON COMMON MODE FAILURES AND PUBLISH IT IN A SCOPE OF THE ISSUE IS ONLY TO COLLECT THE INFDRMATION NUREG REPORT. SO AS TD BE READILY AVAILABLE TO LICENSEES.
STATUS
____________________________________________________________________________________________________________ ION WILL BE BNL SUBMITTED A FINAL REPORT IN DECEMBER 1993. THE STAFF NEEDED TO RESOLVE THE ISSUE. THIS CONCLUS FOUND THAT NO ADDITIONAL REQUIREMENTS ON THE LICENSEES WERE SUBMITTED TO THE PRAB BRANCH CHIEF IN 02/97.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION Pbh5fBLkkbkEb/bR$
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ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbMPLkT[bhbFb[PkibkkTikT[bh bhhhh bhhbh COMPLETION OF TAP 04/92 04/92 ISSUE CONTRACT FUND 01/93 04/93 AS OF FY97 QUARTER 1 O
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ACTUAL M I L E S T.0 M E S DATE DATE DATE CONTRACTOR'S DRAFT FINDINGS 06/92 10/93-CONTRACTOR'S FINAL FINDINGS 09/92 12/93 STAFF'S DRAFT FINDINGS 10/92 11/93 i
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12 ISSUE NUMBER: 148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS IDENTIFICATION DATE: 04/09C PRIORITIZATION DATE: OB/92C TYPE: LI PRIORITY:
TASK MANAGER: J. CHEN OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE:
TAC NUMBERS:
WORK AUTHORIZATION: MEMDRANDUM 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' MANUAL FIRE-FIGHTING EFFECTIVENESS.
IPEEE SUBMITTALS RELATED TO THE EFFECTS OF SMOKE AND STATUS TASK REASSIGNED TO SAIB/SECTION B IN FEBRUARY 1993 AND IS IPEEE SCHEDULE.
BEING PREPARED BY SANDIA. SCHEDULE CHANGED TO CONFORM TO AFFECTED DOCUMENTS PROBLEM / RESOLUTION POSSIBLE NUREG/CR.
DRAFT REVIEW GUIDANCE PLACED IN CONCURRENCE BY TASK MANAGER ON 02/29/96.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GI-148 ASSIGNED TO RES/DSIR/RPSI 09/92 09/92 REASSIGNED TO SAIB 02/93 02/93 DRAFT STAFF REVIEW GUIDANCE 09/93 02/96 AS OF FY97 QUARTER 1 9
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13 ISSUE NUMBER: 148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS ORIGINAL CURRENT ACTUAL j
MILESTONES DATE DATE DATE ISSUE FINAL STAFF REVIEW GUIDANCE 09/93 ISSUE CLOSE OUT MEMO 06/95 i
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10 ISSUE NUMBER: 155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS IDENTIFICATION DATE: 03/79 PRIORITIZATION DATE: 02/92C TYPE: GSI PRIORITY:
TASK MANAGER: A. HUFFERT OFFICE / DIVISION / BRANCH: NRR /DRPM/PERB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: MB95BS RESOLUTION DATE: 03/95C WORK AUTHORIZATION: MEMD FOR W. MINNERS FROM E. BECKJORD DATED 2/26/92 FIN CONTRACTOR CONTRACT TITLE bbb5k bkk kbbikkbbkhkbLFbkMb L1535 BNL RADIONUCLIDE RELEASE CHARACTER L1611 INEL TIMING ANALYSIS OF FUEL FAILURES L2035 SNL SOURCE TERM REMOVAL MECHANISMS W6067 ORNL CHEMICAL FORM OF SOURCE TERMS WDRK SC0PE khkhhkkkkkhikhEbhhkkkkhkUbkkbbbbhkkhkkbPkkPkkkb bbhhf5hIbhkhkbhkhhkR bbkhbkibEbkkkhkbbMhkkkkbk A COMMISSION PAPER AND DECISION LETTER THAT DESCRIBES A PAPER, THE PLAN IS TO REBASELINE TWD NUREG-1150 PLANTS GENERIC IMPLEMENTATION APPROACH. THE STAFF PRESENTED THE AND THEN REVIEW PILOT PLANT APPLICATIONS AND DETERMIME COMMISSION PAPER AND DECISION LETTER TO THE NRR EXECUTIVE WHETHER RULEMAKING AND EXEMPTIONS ARE NECESSARY FOR TEAM AND CRGR IN SEPTEMBER AND THE ACRS IN NOVEMBER. THE IMPLEMENTATION.
COMMISSION PAPER AND DECISION LETTER WERE SENT TO THE STATUS kkihbbkikhEbIhhbkkkkibkkhkUbkkbbbbhEkhkkkbhEhkkk ibhb[hbUPbkhkikbbkhkhbkThkhhkTbhbFkRbIhkkVikhbF 1995 FOR NRC REVIEW AND APPROVAL. PILOT PLANT APPLICATIONS THE GENERIC FRAMEWORK DOCUMENT. A MEETING WAS HELD WITH HAVE BEEN RECEIVED FROM BROWNS FERRY, MILLSTONE, AND VIRGINIA POWER ON NOVEMBER 26 1996, TO DISCUSS THE INDIAN POINT. GRAND GULF AND PERRY ARE ALSD PREPARING THEIR REBASELINING OF SURRY. THE STAFF COMPLETED ITS REVIEW OF PILOT PLANT SUBMITTALS. THE STAFF MET WITH NEI ON THE FRAMEWORK DOCUMENT AND PREPARED A COMMISSION PAPER JANUARY 23, 1996, TO DISCUSS THE GENERIC FRAMEWORK, AND DESCRIBING HOW IT INTENDS TO CONDUCT ITS GENERIC REVIEW OF SEPARATE MEETINGS WERE HELD ON FEBRUARY 7 MAY 30, AND PILOT PLANT SUBMITTALS. BRIEFINGS OF THE NRR EXECUTIVE
. AUGUST 29, 1996, TO DISCUSS THE BROWNS FERRY, PERRY, AND TEAM, CRGR AND ACRS HAVE BEEN COMPLETED. A SERIES OF PILOT GRAND GULF PILOT PLANT SUBMITTALS, RESPECTIVELY. INDIAN PLANT SUBMITTALS HAS BEEN SUBMITTED. SURRY AND GRAND GULF POINT AND OYSTER CREEK ALSO EXPECTED TO SUBMIT PILOT PLANT WILL BE REBASELINED IN 1997. WORK ON THE REMAINING PILOT APPLICATIONS. A MEETING WAS HELD WITH NEI ON OCTOBER 2, PLANT SUBMITTALS WILL BEGIN IN 1997.
AS OF FY97 QUARTER 1 O
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15 ISSUE NUMBER: 155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS AFFECTED DOCUMENTS PROBLEM / RESOLUTION R.G. I.3. 1.4. SRP 15.6.5 MONE.
R.G. 1.7 1.25 MUREG-1465 ORIGINAL CURRENT ACTUAL MILEST0MES DATE DATE DATE IODINE / TID SCHEDULE TO COMMISSIOM' 04/90 05/90 PRA BASED SOURCE TERM PAFER TO COMMISSION 05/90 05/90 08/90 FISSIDM PRODUCT TIMING PAPER TO COMMISSION 07/90 REVISED BML DRAFT REPORT 07/90 08/90 TID REPORT SCHEDULE - IODIME CHEMICAL FORM 12/90 07/91 REPORT ISSUED FOR COMMENT PROPOSED REV. TO TID TO RES DIRECTOR 07/91 09/91 PROPOSED REVISION TO NRR/0GC 09/91 09/91 DRAFT TID TO ACRS 11/91 12/91 COMPLETE ACRS REVIEW 12/91 01/92 0FFICE CONCURRENCE ON TID 10/91 04/92 DRAFT BNL REPORT ISSUED FOR COMMENT 07/91 02/92 TID TO EDO 01/92 04/92
~
TID TO COMMISSION 02/92 04/92 FISSION PRODUCT TIMING REPORT ISSUED FOR 12/90 03/92 COMMENT (INEL) 07/92 ISSUE REVISED TID FOR COMMENT 02/92 AS OF FY97 QUARTER 1
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16 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT AC1UAL MILEST0NES DATE DATE DATE
[hhbEbkkLibb5kEREPbRTkhFkkkL b4)bh bk/bh 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 DRAFT SOURCE TERM 08/92 10/92 NUREG RESPONSE TO SRM ON IMPACT OF INCREASED 09/92 11/92 AMOUNT OF RAD ATION (WITS 9200124) -- DRAFT COMMISSION PAPER AVAILABLE
-- RES CONCURRENCE 09/92 12/92
-- COMMISSION PAPER TO EDO AND OFFICE 10/92 01/93 CONCURRENCE
-- COMMISSION PAPER TD COMMISSION 11/92 02/93 SNL SPRAY NUREG/CR ISSUED FINAL 11/92 06/93 ORNL NUREG/CR ON MELCOR ISSUED 09/93 09/93 SNL REPORT ON POOL OF MUREG/CR ISSUED FINAL 11/92 11/93 ISSUE BNL REPORT FINAL 06/92 11/93 SNL NUREG/CR ON MELCOR ISSUED 11/93 03/94 NEI LETTER 07/94 07/94 BRIEF ACRS 09/94 09/94 09/94 09/94 COMMISSION MEMORANDUM NEI RESPONSE 09/94 09/94 NEI/NRC HEETING 10/94 10/94 AS OF FY97 QUARTER 1 O
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17 ISSUE NUMBER: 155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS t
t ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE i
COMPLETE REVISED SOURCE TERM MUREG 11/92 02/95 PUBLICATION OF NUREG-1465 02/95 02/95 ISSUE CLOSEOUT MEMO (L. SOFFER. PROJECT 12/92 03/95 MANAGER. RES/ DST)
NEI/NRC MEETINGS 06/95 06/95 l
NEI/NRC MEETINGS 10/95 10/95 SUBMITTAL OF GENERIC FRAMEWORK DOCUMENT 11/95 11/95 (FROM NEI) 12/95 FIRST PILOT PLANT SUBMITTAL 12/95 NEI/NRC MEETINGS 01/96 01/96 PRESENT COMMISSION PAPER IN E-TEAM BRIEFrNG 08/96 09/96 BRIEF CRGR ON COMMISSION PAPER 09/96 10/96 BRIEF ACRS ON COMMISSION PAPER 10/96 11/96 SEND COMMISSION PAPER TO EDD/ COMMISSION 10/96 11/96 RESPONSE TO DECISION LETTER 11/96 02/97 BEGIN RESASELIMING 11/96 02/97 COMPLETE REBASELIMING l
s COMPLETE PILOT PLANT REVIEWS t
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RUD DATE: 02/24/97 GECERIC 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:
RESOLUTION DATE: 08/97 TAC NUMBERS:
WORK AUTHORIZATION: MEMORANDUM FROM E. BECKJORD TO J. MURPHY OM JANUARY 26, 1994 CONTRACT TITLE FIN CONTRACTOR W6354 INEL PDWER OPERATED VALVE PERFORMANCE WDRK SC0PE PROGRAM WILL DETERMINE IF THERE ARE SAFETY-RELATED AIR-OPERATED VALVES. SOLENDID-OPERATED VALVES AND PROBLEMS, THE SDLUTION OF THE PROBLEMS AND WHETHER HYDRAULIC-OPERATED VALVES HAVE NOT BEEN SUBJECTED TO A IMPLEMENTATION OF THE SOLUTIONS ARE COST BENEFICIAL.
COMPREHENSIVE RISK EVALUATION: HENCE. THESE VALVES LACK THE REGULATORY SCRUTINY APPLIED TO THE OTHER EQUIPMENT. THIS STATUS PkElkkkNkkhbkkFhkkPbkhhkkkUBMkkkEbEhkHbCbkfkkbibkkkb REVibhEbkhkkkI PROBLEM / RESOLUTION AFFECTED DOCUMENTS WITH THIS ISSUE. A DECISION HAS BEEN MADE TO ENLIST CONTRACTOR ASSISTANCE TO SORT AND CATEGORIZE THE DATA AND ASSIST IN THE RESDLUTION. DATA ANALYSIS COMPLETED BY INEL. NRR REVIEWED AND COMMENTED ON INEL DRAFT REPORT.
CONTRACTDR REVISING DRAFT REPORT IN RESPONSE TO NRR COMMENTS.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 04/94 04/94 QUICK REVIEW COMPLETE AS OF FY97 QUARTER 1 9
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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 SELFCTED 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 SELECTIOh 12/94 09/95 CDF/ RISK ESTIMATION 06/95 10/95 DRAFT INEL REPORT RECEIVED 11/95 10/95 DTR PACKAGE FOR RES/NRR/AE00 REVIEW 01/96 03/97 RESOLUTION PACKAGE FOR ACRS/CRGR REVIEW 02/96 06/97 ACRS/CRGR MEETINGS 03/96 07/97 RESOLUTION MEMORANDUM TO THE EDO 04/96 08/97 AS OF FY97 QUARTER 1 m.
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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. MINNERS FIN CONTRACTOR CONTRACT TITLE TBb kbBkbkTE TbBkbkkkRMINkb W0RK SC0PE I.
SELECT OR LDAD PRA*S FOR ANALYSIS IN SARA VERSIONS 4.0 INCLUDING RELIEF VALVES IN THE PRAS.
6.
PERFDRM COST / BENEFIT ANALYSES TO DETERMINE THE BEST OR 5.0.
2.
DETERMINE WHAT SYSTEMS HAVE SPRING-ACTUATED RELIEF FIX FOR THE PROBLEM AND WHICH VALVES SHOULD BE TESTE0.
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 CLOSEQUT MEMO IF THE COST / BENEFIT IS FAILURE REQUIRED TO FAIL THE SYSTEM IN WHICH THEY OPERATE.
NEGLIGIBLE.
4.
REVIEW LERS TO MORE ACCURATELY DETERMINE 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 CMANGE IN CDRE DAMAGE FREQUENCY FROM LICENSE RENEWAL PERIOD OF 20 YEARS.
~
STATUS A CONTRACTOR REPORT HAS BEEN RECEIVED AND IS BEING EVALUATED LICENSEES. IF THAT CASE IS SUPPORTED, A MUCH MORE SIMPLE AND EFFICIENT CLOSEOUT MAY BE POSSIBLE. THE RESULTS IN REGARD TO ITS SUITABILITY TO SUPPORT CLOSE OUT OF THE OF THE CONTRACTOR SCOPING STUDY CONTINUE TO OFFER PROMISE ISSUE. A FAIRLY COMPREHENSIVE REVIEW INDICATES THAT IT MAY BE SUITABLE. BUT FURTHER STUDY IS RE A FEW MINOR FOR AN EARLY AND INEXPENSIVE CLOSEOUT. COMMENTS ON THE ADDITIONS RELATING TO COMPLETENESS G, QUIRED.
REPORTING VS.
REPORT ARE BEING ADDRESSED. THE REPORT PRESENTS A STRONG COMPLETENESS OF THE ANALYSES HAVE BEEN IDENTIFIED AND CASE FOR CLOSING OUT THE ISSUE WITHOUT ANY ACTION ON THE AVAILABILITY OF CONTRACTOR RESOURCES TO MAKE THE t'DITIONS PART OF LICENSEES. IF THAT CASE IS SUPPORTED. A MUCH MORE IS BEING EVALUATED. THE REPORT PRESENTS A STRONG CASE FOR SIMPLE AND EFFICIENT CLOSEOUT MAY BE POSSIBLE.
CLOSING OUT THE ISSUE WITHOUT ANY ACTION ON THE PART OF AS OF FY97 QUARTER I 9
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21 ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELI ABILITY AFFECTED DOCUMENTS PRD8LEM/RESDLUTION ASME DM CDDE.
AT THE CDNTRACTDR* S SUGGESTIDN. WE ADOPTED A TOP DOWN PRA SYSTEM IMPORTANCE-BASED APPROACH TO IDENTIFYING IMPORTANT
. SYSTEMS AND IMPORTANT SRV*S IN IMPDRTANT SYSTEMS, RATHER THAN THE BOTTOM UP APPRDACH OF IDENTIFYING SRV*S FIRST AS ORIGINALLY PLANNED. THE RESULT APPEARS TO BE SOMEWHAT BROADER IN SCOPE THAN ORIGINALLY PLANNED. COVERING MORE SYSTEMS AND MORE PLANTS. HOWEVER, THE APPROACH STILL NEEDS TO BE CAREFULLY EVALUATED TO ENSURE THAT IT ACCOMPLISHES THE ORIGINAL DBJECTIVES AND THAT A COMPLETE AND FULLY
~
SUPPORTED MUREG CAN BE ISSUED AS THE BASIS FDR CLOSING OUT THE GENERIC ISSUE. THE SCHEDULE FDR TASK 4 REFLECTS THE PREPARATION OF THE ADDITIONAL CONTRACTOR REPORT, BUT ANTICIPATES SHORTER INTERVALS FDR REVIEW AND APPROVAL FDR A MORE SIMPLE RESOLUTIDM THAN ORIGINALLY PLANNED. THIS HAS RESULTED IN A PROJECTED SCHEDULE SL1P IN THE FIRST FEW MONTHS BUT, SINCE WE ANTICIPATE THAT THE ISSUE CAN BE CLOSED OUT DN THE BASIS THAT NO INCREASE IN CDF RESULTS FRDM FAILURES OF THE TYPES OF SRV*S IM QUESTIDN. AND FURTHER.
THAT MANY OF THE REMAINING STEPS WILL BE SHORTENED OR ELIMINATED, WE ARE CDNFIDENT THAT THE CLOSEDUT DATE OF JUNE 1998 CAN BE MAINTAINED.
THE CONTRACTOR REPORT AND APPRDACH ARE STILL UNDERGOING l
CAREFUL EVALUATIDN TO ENSURE THAT THEY ACCDMPLISH THE l
ORIGINAL DBJECTIVES AND THE REPORT CAN SERVE AS A SUFFICIENT
(
BASIS FOR CLOSING DUT THE GENERIC ISSUE.
ONE SIGNIFICANT COMMENT HAS BEEN THAT NO B&W PLANTS WERE EXAMINED. THIS IS BECAUSE NO B&W PLANT PRA*S ARE CURRENTLY AVAILABLE TO NRC IN ELECTRONIC FDRM.
THE CDMTRACTDR WILL i
SEARCH FOR SUITABLE SURROGATE SYSTEMS IN OTHER PRA*S WHICH HAVE IMPORTANCE MEASURES SIMILAR TO THOSE IN THE HARD CDPY B&W PRA*S WHICH ARE AVAILABLE. IF SUCH SURRDGATES CAN BE FOUND. IT MAY BE POSSIBLE TO PERFORM BDUNDING CALCULATIDMS TO SEE WHETHER RESULTS FOR B&W PLANTS WOULD BE SIMILAR TO THOSE FOR THE PLANTS STUDIED. IF IT IS
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MECESSARY TO WAIT FDR ADDITIONAL RESOURCES AND A B&W PRA A SIGNIFICANT DELAY MAY BE EXPERIENCED. A PARALLEL EFFDRT IS
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UNDERWAY TO ACWIRE AN ELECTRONIC PRA FOR A B&W PLANT.
ON 01/29/97 NRC MET WITH THE CDN1RACTDR AND AGREED UPON A PLAN TO M RESS THE THREE MOST IMPORTANT COMMENTS WITHIN AVAILABLE RESOURCES. AN IM-HOUSE EFFORT WILL ADDRESS THE REMAINDER. IF A MAJOR REWORK TO INCORPORATE A B&W PRA CAN BE AVOIDED, THE JUNE 1998 SCHEDULE LEADING TO A f
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22 ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY PROBLEM / RESOLUTION AFFECTED DOCUMENTS JUNE 1998 CLOSEOUT APPEARS TO BE ACHIEVABLE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 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.
AEOD. AND hRR FOR COMMENT 08/94 10/94 INCORPORATE COMMENTS IN TAP FINAL TAP APPROVED BY DSIR DIRECTOR 11/94 12/94 12/94 12/94
$UBTASK 1.1 - SELECT PLANTS SUBTASK 1.2 - REVIEW P&ID'S 02/95 02/95 SUBTASK 1.3 - REVIEW OPERATING EXPERIENCE 02/95 03/95 DATA SUBTASK 1.4 - PERFORM FAILURE ANALYSIS 05/95 08/95 TASK 2 - PERFORM RISK ANALYSIS 08/95 07/96 02/97 02/97 REVISE TAP TASK 4 - FINAL CONTRACTOR REPORT 12/95 04/97 TASK 5 - PROPOSE ISSUE RESOLUTION 02/96 04/97 TASK 6 - TRANSMITTAL OF "FOR COMMENT" 04/96 04/97 RESOLUTION PACKAGE TO DET DIRECTOR FOR CONCURRENCE TASK 7 - NRR INTERFACE WITH LICENSEES AND 04/96 04/97 INDUSTRY GROUPS AS OF FY97 QUARTER 1 9
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23 ISSUE NUMBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE TASK 8 - MRR COORDINATION PLAN 04/96 04/97 TASK 9 - AEOD COORDINATION PLAN 04/96 04/97 TASK 10-TRANSMITTAL OF "FOR COMMENT" RESOLU-05/96 04/97 l
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 07i97 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 TASK 17 - TRANSMITTAL OF FINAL RESOLUTION 12/97 02/98 PACKAGE TO CRGR AND ACRS TASK IB - ISSUANCE OF FINAL RESOLUTION 02/98 04/98 PACKAGE TO NRR TASK 19 - NRR ISSUANCE OF FINAL REQUIREMENTS 05/98 06/98 TO LICENSEES TASK 20 - ISSUE CLOSEOUT MEMO 06/98 06/98 f
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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 DATE: 02/97 TAC NUMBERS: M86344 WORK AUTHORIZATION: APRIL 1. 1993. MEMORANDUM FROM T. MURLEY TO J. SNIEZEK FIN CONTRACTOR CONTRACT TITLE J2bbk kkk TkbbkkbELEkkkkhkbbkkkbPPbkhbFhhEFkkkbbkEbkkbhPLkk WDRK SC0PE khkthkThFkhkbbkkhkQbkbhbFbPkkhfkbPLkhbbhPbkkkhk kk hhk kkk bkkkbhbk kkkbLbhfbk 5LL ikbthbk bbkkkbkkkkkbh bk ACCORDANCE WITH 5/5/94 MEMORANDUM TO THE NRR DIRECTOR FROM A LICENSE RENEWAL PERIDO OF 20 YEARS.
STATUS FkhkbbkkbhkbhPLkkkFkP kbhkVkkkkkkRkbbkPLkhkFbk kkhkkbkkkkkkLFkkkbbkbik[FbkkkkkkbkbPkRkbbbF
~
OPERATING REACTORS DURIN LICENSED OPERATING LIFE.
STAFF OPERATION. WILL BE THE FOCUS OF STAFF ACTIVITIES FOR RESOLUTION OF GI-166.
ISSUE TRANSFERRED FROM NRR TO RES ON ACTIVITIES AND CONCLUSIONS ARE DESCRIBED IN SECY-95-245 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 ISSUF. GI-190 (MEMO FROM RES TO NRR 08/26/96).
PROBLEM / RESOLUTION AFFECTED DOCUMENTS NONE.
NUREG/CR-6260 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE FIRST MEETING WITH INDUSTRY (PERIODIC) 09/93 09/93 PROGRAMMATIC REVIEW 12/93 12/93 AS OF FY97 QUARTER 1 9
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25 ISSUE NUMBER: 166 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS ORIGINAL CURRENT ACTUAL i
MILEST0NES DATE DATE DATE i
1 INFORM COMMISSION (PERIDOIC 6 MONTHS) 04/94 07/94 i
DATA COLLECTION AND ANALYSIS 05/94 07/94 RISK ASSESSMENT 03/94 09/94 01/95 f
TECHNICAL ISSUES 05/94 f
COMPLETION OF ACTIVITIES FOR OP. LIFE 06/94 09/95 CLOSEOUT MEMO TO EDO 11/96 02/97 I
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26 ISSUE NUMBER: 168 TITLE: ENVIRONMENTAL QUALIFICATIUN 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 OATE:
WORK AUTHORIZATION: APRIL 1, 1993. MEMORANDUM FROM T. MURLEY TO J. SNIEZEK FIN CONTRACTOR CONTRACT TITLE A2336 ANL RISK IMPACT OF EQ E2097 SCIENTECH E FOR OPERATING REACTORS W6169 BNL E RESEARCH PROGRAM WORK SC0PE 1
TbbkTbkR RkV[Eh[EkbkVELbkTEbPERkkiNGkXPERiENCE kS5bbikTEbhITHE7555bkkI DATA AND EQUIPMENT REPLACEMENT SCHEDULES FOR NUCLEAR POWER IN ACCORDANCE WITH THE 5/5/94 MEMORANDUM 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 STATUS DETAILED STATUS INFORMATION FOR GI-168 HAS BEEN SUBMITTED TO CAN BE REDUCED AS A RESl?tT OF A PUBLIC MEETING HELD TO IN A MEMORANDUM DATED NOVEMBER 15 1996.
DISCUSS THE FINDINGS FRC4 THE LITERATURE REVIEW. PLANNED THE COMMISSION THE DRAFT PROGRAM REVIEW REPORT ISSUED IN APRIL 199R RESEARCH TO INVESTIGATE INCERTAINTIES WITH ACCELERATED IS CURRENTLY UNDER MANAGEMENT REVIEW. FOR DATA AGING AND TO REVIEW PROMISING CABLE CONDITION WONITORING COLLECTION AND ANALYSIS THE REVIEW OF EQ-RELATED METHODS BEGAN IN MAY 1996. WYLE LABORATORY WAS SELECTED PUBLISHED DOCUMENTS AND INDUSTRY REPORTS, REVIEW OF TO PERFORM AGING AND LOSS-OF-COOLANT ACCIDENT TESTING.
EQUIPMENT FAILURES ASSOCIATED WITH THE ACCIDENT AT THERMAL PREAGING OF THE'FIRST TEST CABLES BEGAN IN THREE MILE ISLAND, AND THE DEVELOPMENT OF AN INTEGRATED NOVEMBER 1996. RESULTS FROM THE PLANNED RESEARCH PROGRAM DATABASE OF EQ TEST REPORTS, RESEARCH TESTS, AND ARE EXPECTED IN FISCAL YEARS 1997 AND 1998. OVER THE NEXT OTHER TEST ACTIVITIES ARE COMPLETED. A ORAFT FINAL REPORT SEVERAL MONTHS, SPLB WILL WORK TO CLOSE OUT CERTAIN ITEMS ON EQ RISK ISSUES ISSUED IN APRIL 1996 IS CURRENTLY UNDER IN THE EQ-TAP AND TRANSFER THE REMAINING OPEN ITEMS TO RES MANAGEMENT REVIEW. THE STAFF IS EVALUATING WHETHER THE FOR RESOLUTION.
~
19 UNRESOLVED ISSUES WITHIN THE SCOPE OF PLANNED RESEARCH AS OF FY97 QUARTER 1 9
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27 i
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DATA COLLECTION AND ANALYSIS 08/94 04/96 STATUS REVIEW 02/95 11/96 4
RISK ASSESSMENT 10/94 03/97 PP.0GRAMMATIC REVIEW 06/94 03/97 f
TECHNICAL ISSUES 10/94 10/98 OPTIONS FOR RESCLUTION IMPLEMENTATION i
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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: MEND 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)
WDRK SC0PE kkkEk k PkkLfhkh kh kkFkhh khhkhkhkkh kh PkkFbkkkb kk khbbbkkhkkPkkkkkhkkkVkhkbbkhkkhhhkkkbbbPkRkhkbhkh ACTION PLAN WAS DEVELOPED THAT ADOPTED AN EARLIER USER NEED ASSESSING SAFETY EVALUATIONS. CONFIRMATION OR REVISION LETTER AND DEFINED ADDITIONAL ACTIONS TO ASSESS THE OF FUEL DAMAGE CRITERIA WILL BE OBTAINED AS A RESULT OF ADEQUACY OF FUEL DAMAGE CRITERIA AT HIGH BURNUPS. RESEARCH THIS WORK. AND THE NEED FOR ANY REGULATORY ACTIONS WILL BE WILL BE PERFORMED, AND RESULTS FROM INTERNATIONAL RESEARCH DETERMINED.
PROGRAMS WILL BE ANALYZED. DISCUSSIONS WILL BE HELD WITH STATUS WHILE WORK IS UNDERWAY TO ASSESS A NUMBER OF FUEL DAMAGE BASIS FOR INTERIM CRITERIA THAT COULD BE USED FOR ANALYZING CRITERIA. ATTENTION HAS BEEN FOCUSED ON THE CRITERIA USED THE REACTIVITY ACCIDENTS. THE NRC STAFF WILL NOT APPROVE FOR ANALYZING THE REACTIVITY ACCIDENTS. ALL MAJOR FURTHER EXTENSIONS OF BURNUP LIMITS UNTIL ADDITIONAL INVESTIGATORS ARE PREPARING DATA ASSESSMENTS THAT WILL BE INFORMATION ON REACTIVITY ACCIDENTS IS RECEIVED, REVIEWED.
PUBLISHED IN A SPECIAL ISSUE OF THE NRC*S NUCLEAR SAFETY AND FOUND TO FORM AN ACCEPTABLE BASIS FOR SUCH ACTIONS.
JOURNAL. IT IS EXPECTED THAT THESE PAPERS WILL PROVIDE A AFFECTED DOCUMENTS PROBLEM / RESOLUTION kkbbLkTbkhbbihk((hh hhkkkkbh9bSbkhkhPbSih[bhPkPkkkhbkCkkEhEb AS OF FY97 QUARTER I O
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29 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FDP HIGH BURNUP FUEL AFFECTED DOCUMENTS PROBLEM / RESOLUTION SRP SECTION 4.2 FURTHER INDUSTRY ACTION, BASED ON LDW SAFETY SIGNIFICANCE 10 CFR 50.46 AND LOW PRDBA81LITY OF DCCURRENCE. THE RES EVALUATIONS TO IN 94-64 DATE INDICATE THAT THE CURRENT DATA BASE CANNOT BE CORRELATED TO DESIGN-BASED CRITERIA AND THAT CONCLUSIVE EXPERIMENTAL DATA WILL NOT BE AVAILABLE FOR SEVERAL YEARS.
EVEN WITH SUBSTANTIAL INDUSTRY AMO RES SUPPORT.
NRR MAY HAVE TO DEVELOP AN INTERIM POSITION BASED ON AVAILABLE INFORMATION WHILE AWAITING LONGER TERM RESEARCH.
RESULTS.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSUE USER NEED LETTER TO RES 10/93 10/93 CONTRACTS ISSUED BY RES 03/94 03/94 ISSUE INFDRMATION MOTICE (IN 94-64) 08/94 08/94 ANNDUNCING NEW RIA DATA COMMISSION PAPER ON HIGH BURNUP FUEL 09/94 09/94 PRESENT HIGH BURNUP DATA AT WATER REACTOR 10/94 10/94 SAFETY MEETING SCHEDULE / COORDINATE INDUSTRY MEETINGS TO 10/94 10/94 DISCUSS ACTIONS COMMISSION PAPER ON HIGH BURNUP FUEL 11/94 11/94 DETERMINE NEED FOR FURTHER GENERIC 11/94 11/94 COMMUNICATIONS ISSUE LETTER TO VENDDRS 11/94 11/94 ISSUE IDENTIFIED FOR DOCUMENTATION IN 01/95 01/95 NUREG-0933 ISSUE IN 94-64 SUPPL. 1. PROVIDING DATA 03/95 03/95 AND VENDDR LETiER AS OF FY97 QUARTER 1 s
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30 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE CSNI SPECIALISTS MEETING ON THE TRANSIENT 09/95 09/95 BEHAVIOR OF HIGH BURNUP FUEL REVIEW INDUSTRY NEI RESPONSE 09/9 5 09/95 ASSESS EFFECTS ON DESIGN BASIS ACCIDENTS OF 09/9 5
~
09/95 REDUCED FAILURE THRESHOLD FOR HIGH BURNUP FUEL CSNI SPECIALISTS MEETING ON THE TRANSIENT 09/95 09/95 BEHAVIOR OF HIGH BURNUP FUEL WATER REACTOR SAFETY INFORMATION_ MEETING ON 10/95 10/95 HIGH BURNUP COMMISSION PAPER ON HIGH BURNUP FUEL 03/96 03/96 ACR3 BRIEFING BY RES 04/96 04/96 CSNI EXPERTS MEETING ON TRANSIENT BEHAVIOR 05/96 05/96 rr *:1GH BURNUP FUEL INITIATE RESEARCH PROGRAM ON LOCA CRITERIA 09/96 09/96 AT HIGH BURNUP WATER REACTOR SAFETY INFORMATION MEETING 10/96 10/96 ON HIGH BURNUP FUEL CORE PERFORMANCE ISSUES WORKSHOP WITH 10/96 10/96 INDUSTRY COMMISSION PAPER ON HIGH BURNUP FUEL 11/96 11/96 ISSUES ISSUE LETTER TO NEI ASSESSING INDUSTRY 09/96 02/97 ACTIONS RIL WITH TECH BASIS FOR INTERIM RIA 12/96 02/97 ACCEPTANCE CRITERIA AS OF FY97 QUARTER 1 O
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31 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DEVELOP INTERIM RIA ACCEPTANCE CRITERIA 12/96 03/97 NUREG/CR REPORT ON METALLURGICAL EFFECTS OF 09/96 03/97 w-HIGH BURNUP DN DAMAGE CRITERIA COMMISSION BRIEFING ON HIGH BUf.KJP FUEL 03/97 03/97 ISSUE GL TO DEFINE INTERIM RIA CI'ITERIA AND 02/97 04/97 REQUEST EVALUATION MOU WITH EPRI FOR C00PERATIOP4 DN LOCA 04/97 04/97 l
CRITERIA MOU WITH DOE FOR COOPERATION ON LOCA 04/97 04/97 CRITERIA ACRC SUBCOMMITTEE MEETING ON HIGH BURNUP 05/97 05/97 l
FUEL l
SPECIAL ISSUE OF NRC'S NUCLEAR SAFETY 06/97 06/97 JOURNAL ON RIA RESEARCH t
CLOSE OUT MEMO TO THE E00 i
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32 ISSUE NUMBER: 171 TITLE: ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA IDENTIFICATION DATE: 02/95C PRIORITIZATION DATE: OS/95C TYPE: GSI PRIORITY: H TASK MANAGER: A. SERKIZ OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC MUMBERS:
RESOLUTION DATE: 12/97 WORK AUTHORIZATION: MEMORANDUM TO L. SHA0 FROM D. HDRRISON ON JUNE 16, 1995 FIN CONTRACTOR CONTRACT TITLE hhh5h bkL
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kVLUhibkbFhkkkkhkhhbb5h5Pk[bkkkkkkkkbkkkhbhPh[bkh W0RK SC0PE INITIAL SAFETY ISSUE EVALUATIONS RESULTED IN RANKING THE PRIMARY OBJECTIVE OF THIS BNL STUDY IS TO REVIEW Akr.
THIS EVALUATION WAS BASED ON CONSERVA-EVALUATE ASSUMPTIONS RELATED TO THE PROBABILITY OF NON-TIVE ASSUMPTIONS REGARDING FAILURE RATES, EQUIPMENT DAMAGE RECOVERABLE DAMAGE TO EDG*S AND ECCS PUMPS USED IN THE AND NONRECOVERY FROM POTENTIAL OVER-CURRENT LQAD EFFECTS.
. INITIAL ISSUE PRIORITIZATION.
STATUS EkLhkNkLhh5hkhkEkkkkbbbhPLkhfbkkkbhUEkkhblikkHbh bk[bkI bPbh bbhPLkh[bh bF hhkFF RkVkkh kkL h RkPbkh hill THAT PRIOR ASSUMPTIONS USED TO PRIORITIZE THIS ISSUE WERE BE ISSUED AS A NUREG/CR AND WILL BE USED TO SUPPORT ISSUANCE OVERLY CONSERVATIVE. HOWEVER, THE ISSUE STILL REMAINS A 0F A GENERIC LETTER REQUESTING CONFIRMATION THAT PLANTS SAFETY CONCERN AND IS JUDGED TO WARRANT FURTHER GENERIC ARE ADEQUATELY DESIGNED FOR THE LOCA/ LOOP SCENARIO.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 93-17.
NRR PLANS TO PREPARE A GENERIC LETTER WHICH WOULD REQUEST LICENSEE CONFIRMATION THAT THE PLANT HAS BEEN ADEQUATELY DESIGNED FOR THE LOCA/ LOOP EVENTS IDENTIFIED BY GI-171.
CRGR AND ACRS REVIEWS WILL PACE ISSUANCE OF A LETTER. THE GENERIC LETTER REQUIRES ISSUANCE OF A "FOR COMMENT" VERSION AND THEREFORE THE RESOLUTION SCHEDULE SHOWN BELOW IS TENTATIVE FOR DATES FOLLOWING CRGR REVIEW PENDING REQUIRED REVISIONS AND ACTIONS.
AS OF FY97 QUARTER 1 l
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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 03/9 6 07/96 BNL TASK 2 RESULTS 04/96 07/96 BNL TASK 3.1 09/96 09/96 BNL TASK 3.2 10/96 10/96 BNL TASK 3.3 11/96 12/96 UPDATiD SAFETY EVALUATION (DRAFT) 09/96 12/96 BNL TASK 4 (NUREG/CR) 03/9 7 03/97 REEVALLATION OF SAFETY ISSUE (DRAFT 11/96 03/97 NUREC/:.R)
ORAFT ::RGR PACKAGE (INCLUDES GENERIC LETTER) 11/96 03/97 CRGR AND ACRS REVIEW 12/96 05/97 CONCLUDING REVISIONS AND ACTIONS 02/97 76/97 ISSUE GL FOR PUBLIC COMMENT 04/97 07/97 COMMENT PERIOD ENDS 11/97 11/97 REVISE GL AND ISSUE 12/97 12/97 CLOSE00T MEMO TO ECO 06/97 12/97 AS OF FY97 QUARTER 1
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34 ISSUE NUMBER: 172 TITLE: MULTIPLE SYSTEM RESPONSES PROGRAM IDENTIFICATION DATE: 07/91C PRIORITIZATION DATE: 12/95C TYPE: GSI PRIORITY:
TASK MANAGER: M. CUNNINGHAM OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE: 12/98 WORK AUTHORIZATION: MEMORANDUM TO D. MORRIS 0N FROM L. SHAD DATED AUGUST 2 1995 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE PRAB WILL PREPARE A REPORT ON HOW 11 MSRP ISSUES WERE ADDRESSED BY LICENSEES IN IPE/IPEEE PROCESS.
STATUS DISCUSSED STAFF PROPOSED TREATMENT OF MSRP ISSUES AT 427TH 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 FY97 QUARTER 1 O
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35 ISSUE NUMBER:
173.A TITLE: SPENT FUEL STDRAGE POOL: CPERATING 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: M88094 RESOLUTION DATE: 10/98 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE SPECIFIC ACTIONS INCLUDED IN PART A 0F THE GENERIC ACTIONS TO ADDRESS SIGNIFICANT ISSUES AT OPERATING AND ACTION PLAN ARE: (1) DETERMINATION OF THE SAFETY PERMANENTLY SHUTDOWN FACILITIES. BASED ON FINDINGS FROM SIGNIFICANCE OF IDENTIFIED CONCERNS, (2) DETERMINATION THESE REVIEW AREAS AND THEIR RISK SIGNIFICANCE, THE STAFF OF THE FACILITIES WHERE THE CONCERNS MAY BE APPLICABLE.
WILL DEVELOP CRITERIA FOR SPECIFIC SPENT FUEL POOL L3? EVALUATION OF THE ADEQUACY DF PRESENT SFP DESIGMS, OPERATIONS FOR POTENTIAL USE IN FORMULATING GENERIC 4 - EVALUATION OF THE ADE ACY OF CURRENT NRC GUIDANCE FDR COMMUNICATIONS, REVISIONS OF REGULATORY GUIDANCE. AND FNDESIGMS.AND(5)EVAlbATIONOFTHENEEDFDRGENERIC OTHER APPROPRIATE REGULATORY ACTIONS.
STATUS THE ACTION PLAN IS CLOSED. TASKS FDR RESOLUTION WILL
- 2) CONDUCT PLANT SPECIFIC REGULATORY ANALYSIS FOR BE TRACKED SEPARATELY. RESOLUTION COMPRISED OF THREE PARTS:
HARDWARE EACKFITS AT SELECTED SITES:
- 1) CONDUCT REGULATORY ANALYSIS TO EVALUATE JUSTIFICATION
- 3) UPDATE REGULATORY GUIDANCE.
FOR IMPOSING FUEL STORAGE PDOL OPERATIONS RULE:
AFFECTED DOCUMENTS PRDBLEM/ RESOLUTION kh95583 kbkUPPLEMkhT1 AA EbkE AA IN 94-38 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP APPROVED 10/94 10/94 AS OF FY97 QUARTER 1
0;UN DATE: 02/24/97 GECERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
36 ISSUE NUMBER:
173.A TITLE: SPENT FUEL STORAGE POOL: OPERATING FACILITIES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE REVIEW EXISTING KRC GUIDANCE AND 08/94 08/94 REQUIREMENTS IDENTIFY SIGNIFICANT SFP CONCERNS 12/94 12/94 REPORT SIGNIFICANT SFP PROBLEMS TO NRR 12/94 12/94 MANAGEMENT DEVELOP AM SFP INSPECTION PLAN 01/95 01/95 CONDUCT INSPECTIONS OF SELECTED PLANTS 06/95 06/95 EVALUATE AND REPORT RESULTS OF INSPECTIONS 09/95 09/95 COMMISSION BRIEFING ON SFP ISSUES O2/96 02/96 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 RADI0 ACTIVE MATERIAL STORAGE 06/96 07/96 PRACTICES PROPOSED COURSE OF ACTION SUBMITTED TO 06/96 07/96 COMMISSION COMMISSION MEETING FOR RESOLUTION 08/96 08/96 ACRS MEETING 08/9 6 08/96 PLANT-SPECIFIC REG. ANALYSIS FOR MARDWARE 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 FY97 QUARTER 1 e
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37 ISSUE NUMBER:
173.8 TITLE: SPENT FUEL STORAGE 2 DOL: PERMANENTLY SHUTDOWN FACILITIES IDENTIFICATION DATE: 02/96C PRIDRITIZATION DATE: 06/9fic TYPE: GSI PRIDRITY:
TASK MANAGER: S. JONES OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS: MR TAC NUMBERS: M40004 M90441 M93805 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTDR CONTRACT TITLE W0RK SC0PE SPECIFIC ACTIONS INCLUDED IN PART B DF THE GENERIC AND IMPLEMENTATION OF ADDITIONAL REQUIREMENTS SPECIFICALLY ACTION PLAN ARE: (1) THE DETERHINATION DF SIGNIFICANT APPLICABLE TO PERMANENTLY SHUT DDWM FACILITIES WITH IDENTIFIED CDMCERMS FROM PART A APPLICABLE TO STDRED. IRRADIATED FUEL.
PERMANENTLY SHUTDOWN FACILITIES AND (2) THE EVALUATION STATUS THE STAFF DETERMINED THAT ALL SIGNIFICANT IDENTIFIED DIVISION OF SYSTEHS SAFETY AND ANALYSIS WILL PROVIDE CONCERNS FROM PART A APPLICABLE TO PERMANENTLY SHUTDOWN TECHNICAL SUPPDRT FOR THAT ACTICN PLAN AND OTHER EXISTING FACILITIES WERE ENCOMPASSED BY THE SPECIAL INSPECTION ACTION PLANS ASSOCIATED WITH RULEMAKING FOR DECDMMISSIONING ACTIVITIES. THE SPECIAL INSPECTIDMS FOUND NO SIGNIFICANT FACILITIES. STAFF RESDURCES WILL BE TRACKED THROUGH DEFICIENCIES OTHER THAN AT DRESDEN 1.
IN RESPONSE TO THE TACS ASSIGNED TO THE ASSOCIATED ACTION PLANS.
DRESDEN 1 SPECIAL INSPECTION FINDINGS, PDMD WILL PRDCEED
- SEE NRR DIRECTDR*S MONTHLY REPORT FOR STATUS.
WITH ISSUANCE OF THEIR DECOMMISSIONING ACTION PLAN. THE AFFECTED DDCUMENTS PROBLEM / RESOLUTION
- BULLETIN 94-01 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP APPROVED 10/94 10/94 AS OF FY97 QUARTER 1
RUM DATE: 02/24/97 GENEQ2C ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
38 ISSUE NUMBER:
173.B TITLE: SPENT FUEL STORAGE POOL: PERMANENTLY SHUTDOWN FACILITIES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IDENTIFY SIGNIFICANT SFP CONCERNS 11/95 11/95 APPLICABLE TO PERMANENTLY SHUT-00VN FACILITIES DECISION ON RULE OR OTHER GENERIC 09/9 6 09/96 ACTIVITY CLOSE OUT ISSUE 09/9 6 AS OF FY97 QUARTER 1 i
i.
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39 ISSUE NUMBER:
178-TITLE: EFFECT OF HURRICANE ANDREW ON TURKEY POINT IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: LI PRIORITY:
TASK MANAGER: R. CROTEAU OFFICE / DIVISION / BRANCH: NRR /DRPE/PD23 ACTION LEVEL: ACTIVE STATUS:
4 TAC NUMBERS: M86716 M86717 RESOLUTION DATE: 11/96 WORK AUTHORIZATION: MEMO FROM T. MURLEY TO J. TAYLOR ON JULY 22, 1993 FIN CONTRACTOR CONTRACT TITLE 9
WDRK SCOPE A TEMPORARY INSTRUCTION HAS 8EEN DEVELOPED FOR INSPECTORS TIONS, WERE EVALUATED TO DETERMINE IF GUIDANCE TO TO REVIEW LICENSEE OFFSITE COMMUNICATION CIRCUITS DURING LICENSEES. IN THE FORM OF GENERIC COMMUNICATION, IS EMERGENCY PREPAREDNESS INSPECTIONS SCHEDULED AT POWER NECESSARY TO PROVIDE EITHER SURVIVA8ILITY OR RAPID 1-REACTOR FACILITIES BETWEEN FEBRUARY AND JUNE 1996. DATA RECOVERASILITY OF THESE CIRCUITS FROM A SEVERE NATURAL-COLLECTED FROM THOSE INSPECTIONS. AS WELL AS PAST INSPEC-EVENT.
STATUS (ITEM 1 A TEMPORARY INSTRUCTION (T! 2515/131)
THROUGH 06/ 0/96.
ISSUED 01/1 /96, INCORPORATING REGIONAL COMMENTS, HAS BEEN (ITEM 2 THE ACTION TO PROVIDE GUIDANCE FOR INSPECTORS WRITTEN TO PROVIDE REGIONAL INSPECTORS GUIDANCE FOR HAS BEEN IN ORPORATED INTO THE PRA IMPLEMENTATION PLAN.
COLLECTING INFORMATION ON OFFSITE NOTIFICATION CIRCUITS.
- SEE NRR DIRECTOR *S MONTHLY REPORT FOR STATUS.
THE TI HAS BEEN PERFORMED AT SEVENTEEN PLANTS FROM 92/01/96 1
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG-1474 TWO NEGATIVE FINDINGS WERE IDENTIFIED AS A RESULT OF THE IN 93-53 TI.
THESE WILL BE COVERED IN AN INFO NOTICE TO BE SENT TO TI 2515/131 ALL REACTOR LICENSEES. ALSO. A CHANGE IS BEING MADE TO THE INSPECTIDM PROCEDURE 82701.
Y AS OF FY97 QUARTER 1
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40 ISSUE NUMBER: 178 TITLE: EFFECT OF HURRICANE ANDREW ON TURKEY POINT ORIGINAL CURRENT ACTUAL MILE 5T0NES DATE DATE DATE TAP APPROVED 07/93 07/93 EVAL THE ADEQUACY OF NRC GUIDANCE FOR REVIEW-05/96 05/96 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 AN#1YZE 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 COMMUNICATIONS FOR NATURAL DISASTERS WITHIN THE PLANT DESIGN BASIS CLOSE OUT ISSUE 11/96 11/96 AS OF FY97 QUARTER 1 O
O O
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41 ISSUE MUMBER:
179-TITLE: CORE PERFORMANCE IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: LI PRIORITY:
TASK MANAGER: E. KENDRICK OFFICE / DIVISION / BRANCH: NRR /DSSA/SRXS ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91257 M91602 M95674 RESOLUTION DATE: 12/97 WORK AUTHORIZATION:
}
FIN CONTRACTOR CONTRACT TITLE J2029 PNL CORE PERFORMANCE EVALUATION [ ACTION PLAN SUPPORTh ACTION PLAN SUPPORTl J2512 PNL CORE PERFORMANCE EVALUATION '
J2513 PNL CORE PERFORMANCE EVALUATION lACTION PLAN SUPPORTL L1351 PARAMETERS CORE PERFORMANCE EVALUATION 1, ACTION PLAN SUPPORT ll WDRK SC0PE SPECIFIC ACTIONS INCLUDED IN THE ACTION PLAN ARE:
DSSA - THE ACTION PLAN IDENTIFIES ONE OR MORE LICENSEE (1) EVALUATE FUEL VENDORS PERFORMANCE THROUGH PERFORMANCE-INSPECTIONS IN EACH REGION THAT SHALL BE PERFORMED IN BASED INSPECTIONS THAT EVALUATE THE RELOAD CORE DESIGN.
COORDINATION WITH THE REGIONAL INSPECTORS. TO ASSE$S SAFETY ANALYSIS AND LICENSING PROCESS. FUEL ASSEMBLY LICENSEE PERFORMANCE IN RELOAD CORE ANALYSIS OVERSIGHT AND MECHANICAL DESIEN ANO FUEL FABRICATION ACTIVITIES PARTICIPATION. LICENSEE INSPECTIONS WILL NORMALLY BE ISSUE-l (2) EVALUATE THE fERFORMANCE OF LICENSEES THAT PERf0RM CORE DRIVEN BUT A TOTAL OF 10 LICEN3EE/ VENDOR INSPECTIONS IS RELOAD ANALYSIS FUNCTIONS, (3) IDENTIFY DOCUMENT AND BL'0GETdD FOR FY '97.
THE DATA ACQUIRED THROUGH LICENSEE /
CATEGORIZE CORE PERFORMANCE PROBLEMS AN6 ROOT CAU$E VENDOR INSPECTIONS WILL BE INTEGRATED WITH INFORMATION EVALUATIONS THAT WILL BE FURTHER EVALUATED DURING THESE SUPPLIED BY THE REGIONS AND OTHER SOURCES AND WILL BE EVAL-INSPECTIONS PROVIDE INPUT TO SALP EVALUATIONS AS WELL AS UATE6.% GENERIC CORE PERFORMANCE INDICATORS AND INDUSTRY REGIONAL ENf0RCEMENT ACTIONS AS APPROPRIATE (4 TRAIN AND CO'4FORMANCE TO CURRENT REGULATORY REQUIREMENTS. THE END COORDINATE REGIONAL SUPPORT STAFF PARTICIPAIING)IN THESE PR3 DUCT OF THE OVERALL ASSESSMENT WILL INCLUDE GUIDANCE FOR ACTIVITIES, AND (5)ING GENERIC COMMUNICATIONS, REVISIONS OF EVALUATE THE RESULTS OF THESE ACTIVITIES RESIDENT INSPECTORS AND REGIONAL STAFF. THESE ACTIVITIES FOR USE IN FORMULAT
/eRE SCHEOULED TO BE COMPLETED IN FY '97.
THE ONGOING REGULATORY GUIDANCE ANO GUIDANCE FOR REGIONAL INSPECTORS ACTIVITIES TO CAPTURE AND ADDRESS EARLY WARNING OF EMERGING AND OTHER APPROPRIATE REGULATORY ACTIONS. IN ADDITION. AS ISSUES WILL CONTINUE INTO FY '97, AND THE ACTION PLAN WILL A RESULT OF RECENT GENERIC CONCERNS, INCLUDING THE FAILURE BL UPDATED TO REFLECT THE LIVING PLAN.
OF CONTROL RODS TO FULLY INSERT, THE ACTION PLAN IS BEING DISP - THE ACTION PLAal 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 ANO TO CONDUCT A WORKSHOP DN CORE PERFORMANCE ISSUES CONTRACTED TECHNICAL ASSISTANCE. THESE INSPECTIONS BEGAN IN (TASK 7) IN THE FALL OF 1996.
1994 AND WILL BE COMPLETED IN 1997.
STATUS DSSA - THE DATA ACQUIRED FROM THE ONGOING VENDOR INSPECTIONS ARE BEING EVALUATED FOR GENERIC IMPACT 1
AS OF FY97-QUARTER 1
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RUN DATE: 02/24/97 GECERIC ISSUE MANAGEMEOT CONTROL SYSTEM PAGE:
42 ISSUE NUMBER: 179 TITLE: CORE PERFORMANCE 5TATdS AND IDENTIFICATION OF EMERGING ISSUES. AN ISSUE-DRIVE INTEGRATE AND PRIORITIZE ITS ACTIVITIES. OPTIONS AND VENDOR INSPECTION AT GE WAS CONDUCTED IN MAY 1996, SUPPORTED RECOMMENDATIONS WERE PROVIDED FOR MANAGEMENT REVIEW AND WERE BY SRXB/DSSA STAFF AND CONTRACT SPECIALISTS IN RELOAD PRESENTED TO THE EDO IN SEPTEMBER 1996.
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.
IS UNLIKELY THAT LICENSEE INSPECTIDMS IN EACH REGION CAN BE THE REMAINING PLANNED ISSUE-DRIVEN INSPECTIONS INCLUDE ABB SUPPORTED UNTIL FY '97.
SRXB PARTICIPATED IN THE REGION I COMBUSTION ENGINEERING *S SUPPLY OF A BWR TRANSITION CORE INSPECTOR COUNTERPARTS MEETINGS IN DECEMBER 1995 AND MAY RELOAD FOR WNP-2 AND A COMPREHENSIVE FOLLOWUP INSPECTION OF 1996. DSSA IS REEVALUATING THE ACTICM PLAN TO BETTER SIEMENS POWER CORPORATION ISSUES.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kkSPEbhkPb(PhRkkhFbLLhhhP) bbfhk bbfhk INSPECT ZION RELDAD ANALYSIS 10/94 10/94 INSPECT ABB/CE (PWR RELDADS) 11/94 11/94 INSPECT TELEDYNE-WAH CHANG (TWC) 12/94 12/94 INSPECT SANDVIK SPECIALTY METALS (SSM) 12/94 12/94 INSPECT DUKE RELDAD ANALYSIS 03/95 03/95 INSPECT WESTINGHOUSE 07/95 07/95 INSPECT GE 10/95 10/95 INSPECT TMI-1 RELOAD ANALYSIS 12/95 12/95 IDENTIFY' ISSUES FOR CORE PERFORMANCE 06/96 06/96 WDRKSHOP AS OF FY97 QUARTER 1 9
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43 ISSUE NUMBER: 179 TITLE: CORE PERFORMANCE 4
ORIGINAL CURRENT ACTUAL i
MILEST0NES DATE DATE DATE INSPECT GE (SLMCPR & LOW DENSITY PELLETS) 07/96 07/96 L
INSPECT FRAMATOME/COGEMA (B&W FUELS) 08/96 10/96 CONDUCT CORE PERFORMANCE WORKSHOP 10/96 10/96 COMPREHENSIVE REINSPECTION OF SPC 02/97 02/97 INSPECT REGION I LICENSEE (S) 03/97 03/97 INSPECT A8B/CE BWR (WMP-2 TRANSITION CODE) 10/96 05/97 INSPECT REGION II LICENSEE (S) 06/97 06/97 INSPECT REGION III LICENSEE (S) 09/97 09/97 I
COMPLETE CORE PERFORMANCE EVALUATION 12/96 09/97 ANALYSIS EVALUATE LEAD TEST PROGRAMS FOR 12/96 12/97 IDENTIFICATION OF CORE PERFORMANCE PROBLEMS INSPECT REGION IV LICENSEE (S) 12/97 12/97 EVALUATE INSPECTION GUIDANCE 12/96 12/97
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44 ISSUE NUMBER: 181 TITLE: FIRE PROTECTION IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/9EC 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 I). RECOMMENDA-THE FPFI PROGRAM AND ALL OTHER REAEi'JR FIRE PROTECTION TIONS FOR FURTHER STUDY (FART 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 IMPLEMENTING THE REr0"hiNDATIONS. IN PRIORITY ORDER, AS PROTECTION PROGRAM WHICH IS COMMENSURATE WITH THE SAFETY RESDURCES 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 hk FF bbhPLkTEb bb5h5bkkL kMkLL kbkLE Fikk hE5h5 iUk kbvi5bkh bbkhihhEE bk kEkbhbR h FEGb kbb kbkh) bk 0F FIRE BARRIER MATERIALS OTHER THAN THERMO-LAG AT NIST.
FEBRUARY 29, 1996.
BY LETTER OF MARCH 15, 19 6. THE ACRS THE TEST RESULTS WERE PROVIDED BY NIST IN ITS REPORT OF SUBMITTED ITS COMMENTS TO THE 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 ASSESSING THE RECOMMENDATIONS MADE BY THE ACRS AND AUGUST 20, 1996. THE SYAFF*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 LABORATORY (BN ), ITS TECHNICAL ADDRESS A VARIETY OF FIRE SAFETY ISSUES. CONSISTENT WITH ASSISTANCE CONTRACTOR. TO EVALUATE THE RISK ASSOCIATED WITH THIS COMMITMENT. THE STAFF HAS INCLUDED ITS REVIEW CF 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 INDUCED 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 FY97 QUARTER 1 O
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45 L
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ISSUE NUMBER: 181 TITLE: FIRE PROTECTIca i
STATUS FOR DEVELOPING THE FIRE PROTECTION FUNCTIONAL INSPECTION CALENDAR YEAR 1997.
1 (FPFI) PROCEDURES. SCIENTECH AND BNL SUBMITTED THE FIRST THE DEVELOPMENT OF A FIRE PROTECTION TRAINING PROGRAM l
DRAFT OF THEIR WORK PRODUCT ON SEPTEMBER 6 AND SEPTEMBER 16 IS ON HOLD UNTIL THE FPFI PPOGRAM IS IMPLEMENTED.
RESPECTIVELY. THE STAFF IS PREPARING A SECY PAPER TO INFORM THE STAFF ISSUED THE SEMIANNUAL REPCRT TO THE COMMISSION THE COMMISSIDM OF THE DETAILS DF THE FPFI PROGRAM AND TO ON THE STATUS OF THE FP-TAP DN OCTOBER 31. 1996. THE NEXT PROVIDE STAFF PLANS FOR IMPLEMENTING THE PROGRAM. THE STAFF STATUS REPORT IS DUE APRIL 1997. NRR/SPLB IS PREPARING AM HAS SELECTED 12 CANDIDATE PILOT PLANTS L3 PER REGION). THE RES USERS MEED MEMO OUTLIMING THE NECESSARY TECHNICAL t
STAFF IS CURRENTLY WORKING WITH THE REG :DNAL OFFICES TO ISSUES THAT NEED TO BE ADDRESSED IN ORDER TO SUPPORT AND TO SCHEDULE PERFORMANCE-BASED FIRE PROTECTION APPROACHES AT NUCLEAR SELECT 4 FINAL CANDIDATES (1 PER REGION t
THE 4 FPFI PILOT INSPECTIONS. THE STAFN PLANS TO BEGIN THE POWER PLANTS. RES IS PREPARING A RULEMAKING PLAN WHICH PILOT INSPECTIONS NO LATER THAN THE FIRST QUARTER OF IS SCHEDULED TO BE COMPLETED BY FEBRUARY 199/.
i AFFECTED DOCUMENTS PROBLEM / RESOLUTION
..__________.... _...._.. _____..-------=---
NUREG/CR-6224 NOME.
BULLETIN 95-02 IN 95-47. REVISION 1 IN 93-34 AND SUPPLEMENT 1 BULLETIN 93-02 AND SUPPLEMENT 1 IM 92-85 IN 92-71 IM 88-28
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ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE OTHER ISSUES (PART IV) 08/95 08/95 SEMIANNUAL COMMISSION STATUS REPORT 04/96 04/96 6
10/96 SEMIANNUAL COMMISSION STATUS REPORT 10/96 RECOMMENDATIONS FOR FUTURE STUDY (PART II) 05/97 10/96 CONFIRMATION ISSUES 05/97 10/96 i:
AS OF FY97 QUARTER 1 1
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46 ISSUE NUMBER: 181 TITLE: FIRE PROTECTION ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE RECOMMENDATIONS FOR ACTION (PART I) 01/97 02/97 SEMIANNUAL COMMISSION STATUS REPORT 04/97 04/97 i
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47 ISSUE MUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE t
IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:'06/96C TYPE: RI PRIORITY:
TASK MANAGER: T. J. KIM OFFICE /DIVISIOM/ BRANCH: MRR /DRPW/PD31 ACTIDM LEVEL: ACTIVE STATUS:
I TAC MUMBERS: M91571 RESOLUTION DATE:
WORK AUTHORIZATION:
FIM CONTRACTOR CONTRACT TITLE i
W0RK SC0PE SPECIFIC ACTIONS INCLUDED IN THE GENERIC ACTION PLAN
(
REVIEW THE LEAD PLANT APPLICATION AND ISSUE A SAFCTY ARE: (1) REVIEW ELTR1 AND ISSUE A STAFF POSITION PAPER.
E LUATIDM REPORT. AMD (4) DEVELOP A STANDARD REVIEW (2) REVIEW ELTR2 AMD ISSUE A SAFETY EVALUATIDM REPORT, PROCEDURE BASED OM ELTRI. ELTR2, AND THE LEAD PLANT REVIEW.
STATUS THE STAFF POSITIDM PAPER ON THE BWR EXTENDED POWER SUBMITTED ELTR2, THE GENERIC BOUNDING ANALYSES SUPPORTING
+
UPRATE PROGRAM WAS ISSUED ON FEBRUARY 8 1996 (COMPLETION THE EXTENDED POWER UPRATE PROGRAM. THE STAFF REVIEW OF OF MILESTONE 2).
THE STAFF ALSD MET WIYH GE AND THE ELTR2 IS OMGOING. THE LEAD PLANT APPLICATION FROM INTERESTED BWR UTILITIES ON FEBRUARY 14, 1996. TO DISCUSS MONTICELLO IS MOW EXPECTED IM JUNE 1996.
THE COMTENTS OF THE STAFF POSITION PAPER AND THE OVERALL
- SEE MRR DIRECTOR'S MONTHLY REPORT FOR STATUS.
STATUS OF THE POWER UPRATE PROGRAM. ON MARCH 26, 1996 GE AFFECTED DOCUMENTS PROBLEM / RESOLUTION MEDC-32424 GENERIC GUIDELINES FOR GE BWR EXTENDED POWER MONE.
UPDATE ORIGINAL CURRENT ACTUAL MILE 5T0MES DATE DATE DATE GE TOPICAL ELTR1 SUBMITTED 03/95 03/95 AS OF FY97 QUARTER 1 I
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48 ISSUE NUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE ORIGINAL CURRENT ACTUAL MILEST0NES 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 09/9 5 09/95 INCORPORATE INFORMATION ON FOREIGN 10/95 10/95 EXFERIENCE OBTAINED FROM SRXB DEVELOP 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 RAI*S ON GE ELTR2 ACTIONS 10/96 10/96 RAI'S 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 FY97 QUARTER 1 9
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTRDL SYSTEM PAGE:
SI ISSUE MUMBER: 184 TITLE: ENDANGERED SPECIES ORIGINAL CURRENT ACTUAL MILE $ TONES DATE DATE DATE IDENTIFY INDIVIDUAL LICENSEE PROGRAMS AND 05/96 05/96-ACTIVITIES BEING CONDUCTED TO FURTHER THE CONSERVATION OF PROTECTED SPECIES DETERMINE PRIORITY FOR SITES WARRANTING 06/96 03/97 FOLLOWUP ACTIONS RECOMMEND SITE-SPECIFIC FOLLOWUP ACTIONS TD 12/96 03/97 PROJECTS DEVELOPMENT AND IMPLEMENTATION OF PROCESS FOR 03/97 04/97 MAINTAINING STATUS AND COMPLIANCE WITH THE ESA AT EACH SITE CLOSE OUT ISSUE AS OF FY97 QUARTER I I
- _ _ _ _ _ _- - -,, ~.
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RUM DATE: 02/24/97 GECERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
52 ISSUE NUMBER: 190 TITLE: FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR PLANT LIFE IDENTIFICATION DATE: 08/96C PRIORITIZATION DATE: 08/96C TYPE: GS1 PRIDRITY:
TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 12/97 WORK AUTHORIZATION: MEMO TO A. TRADANI FROM T. SPEIS ON 08/26/96 "GSI-166,
- ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS *"
FIN CONTRACTOR CONTRACT TITLE hb6h5 Pk[
hkhibbkkkkkhbkhbhbkLkbhEhbbkPbkkkkhhbkbb5hkkkPLkkhLkhk WDRK SC0PE EVkLUkhkhkhfbbkkbkUkbhbhbPkkkkkkbPLkkhbbkPbkEkkk$
hkbkkkkkEhbikkbTbk'kkkbLbhibk'hlLL[kbLbbkbbkkkbkkkkkbk IN ACCORDANCE WITH 0 /05/94 MEMORANDUM TO THE NRR DIRECTOR OF A 60-YEAR PROJECTED PLANT LIFE.
5TATUS Fkkibbh k Lhhih bh bbkPbkkkkh hbR bb hkkk PLkki L5Fh kk bk 7b kkb kkk kEh5bbkL hbkk bk bk-5bb h5LL bk bkkkkkb hk UNDERWAY. THIS WORK COMPLETES THE ONGOING WORK UNDER UNDER THIS GENERIC ISSUE.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG/CR-6260 PNL REQUESTED TO EXTEND PERIOD OF PERFORMANCE BY TWO MONTHS TO ALLOW TIME TO RESPOND TO NRC STAFF COMMENTS ON DRAFT FINAL REPORT.
ORIGINAL CURRENT ACTUAL MILEST3NES DATE DATE DATE RES DECISION TO ESTABLISH NEW GSI 08/96 08/96 EXTEND THE RES RISK STUDY OF FATIGUE 09/9 6 02/97 FAILURE FROM 40 TO 60-YEAR PLANT LIFE AS OF FY97 QUARTER I O
O O
RUM DATE: 02/24/97-GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: - 53 ISSUE NUMBER: 190 TITLE: FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR FLANT LIFE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bEhkLbPkhTkFFhbb5TihkhkPkRFbRLkbEkhk b5f9h b3hbh RENEWAL MEET-WITH CRGR ON LICENSE RENEWAL RECOMMENDA-03/97 04/97 TION IN THE STAFF POSITION MEET WITH ACRS OM ?.ICENSE REMEWAL RECOMMENDA-05/97 05/97 TION IN THE STAFF 70SITION RESOLUTION PLAN Fi1R LICENSE RENEWAL 09/97 09/97 CLOSE OUT MEMO TO E00 12/97 12/97 AS OF FY97 QUARTER 1
_m_._._--_-m.,___m____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _, _ _ _ _ _ _,, _ _ _ _ _ _
QUC DATE: 02/24/97 GENERIC ISSUE MACAGEMENT CONTROL SYSTEM PAGE:
54 ISSUE NUMBER: 191 TITLE: ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFDRMANCE IDENTIFICATION DATE: 09/96C PRIORITIZATION DATE: 09/95C TYPE: GSI PRIDRITY:
TASK MANAGEk: M. MARSHALL OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE:
WORK AUTHORIZATION: MEMO TO D. MORRISON FROM W. RUSSELL, " THIRD SUPPLEMENTAL USER NEED REQUEST... ACCIDENT GENERATED DEBRIS " 12/07/95 FIN CONTRACTOR CONTRACT TITLE W0RK
$ COPE ik LibHk bh kHb Rkhbtbhkbh ff$k$ kkb khllkh[k bb b5 kb bEBkkhkLbbKkbkbhPbkhbkPhUILLBEkkhhkkkEbib REGULATORY GUIDE 1.B2, REV. 2) 0F Tii S'HCERN FOR THE DETERMINE IF THERE IS A NEED FOR FURTHER ACTIONS TO BE
" POTENTIAL FOR LOSS OF EMERGENCY COOLINb 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),
STATUS bkbUhk~bhhTkkhEkbbbkkkkbhbkLkk5bbkbbLibikkhibkh bkkfL kHk F[khk Obkkkkk bh hh bh$
~~'~~~~~
THE ISSUANCE OF AN S0W FOR THIS REASSESSMENT WAS DELAYED AFFECTED DOCUMENTS PROBLEM / RESOLUTION j ? REGULATORY GUIDE 1.82, REV. 2 NONE i NUREG-0800 l h GENERIC LETTER 85-22 ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE NRR USER NEED REQUEST SENT TO RES 12/95 12/95 AS OF FY97 QUARTER I G
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55 t
ISSUE NUMBER: 191 TITLE: ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 1
y USER NEED REQUEST ASSIGNED TO GSIB 01/96 01/96 REASSESSMENT DECLARED A NEW GSI 09/96 09/96 ISSUE SOW FOR REASSESSMENT 11/96 11/96 i
i COMPLETE REASSESSMENT 04/97 04/97 ISSUE CLOSE-0UT MEMO TO EDO f
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RUN DATE: 02/24/97 GECERIC ISSUE MANAGEMENT CONTROL SYSTER PAGE:
56 ISSUE NUMBER:
B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS IDENTIFICATION DATE: 06/7BC PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: M TASK MANAGER: J. KRAMER OFFICE / DIVISION / BRANCH: RES /DSR /HFBR ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE: 06/97 TAC NUMBERS:
WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE kbkSS LLkL khkkGkkkkbhhkkbkkkPkkkbkkkkbhkkbhbkhFb[LhkkibkkkkkLkkkL[kh EVALUATION PROCESS (TASKS 5 AND 6)
WDRK SC0PE kkkhbkKbbbPkkkbLbbkk bEVEkbPhikkbk[TEkibh kkkb L bPkkkkbk kbhfbk bk bhbkkh[b kbh[bk$ hkk hbbPk bk FOR SAFETY RELATED OPERATOR ACT S: 2) DETERMINE WHETHER THIS GENERIC ISSUE COVERS DESIGN BASIS ACCIDENTS OR EVENTS.
OR NOT AUTOMATIC ACTUATION WILL BE RE UIRED: AND (3) DEVELOP CRITERIA FOR SAFETY RELATED OPERATOR ACTIDMS DURING SEVERE GUIDANCE AND REVIEW CRITERI A FOR LICE SEE 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 HEMO 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 VERE 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 PROBLEM / RESOLUTION AFFECTED DOCUMENTS hbBkPkbh[bkbLTkk kkkhkhbkkLkkhbkkhhkkkRkhkhEbkb[kbkbbkhikkFbk 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 FY97 QUARTER 1 9
9 e
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57 ISSUE N;AER:
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 58.8 04/92 04/92 COMPLETE DRAFT OF 58.8 08/92 08/92 NUPPSCO BALLOTS DRAFT STD 58.8 10/92 03/93 i
DEVELOP REGULATORY GUIDE TO ENDORSE 03/94 03/94 AMS 58.8 NUPPSCO ISSUES FINAL 58.8 08/93 08/94 03/95 l
ANSI /ANS 58.8 PUBLISHED I
ISSUE DRAFT REG GUIDE FOR 60-DAY COMMENT 12/93 07/95 PERIOD REVISE REG GUIDE TO REFLECT PUBLIC COMMENTS 05/94 09/95 t
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 t
ISSUE REQUEST TO GSIB FOR REASSESSMENT OF 11/96 11/96 RISK ANALYSIS REVISE DG-1052 TO REFLECT PUBLIC COMMENTS 07/96 02/97 j
ACRS REVIEW 09/9 6 04/97 ISSUE FINAL REG GUIDE 09/94 06/97
{
CLOSE OUT ISSUE WITH MEMORANDUM TO EDO 09/94 06/97 l
AS OF FY97 QUARTER 1 f
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
$8 ISSUE NUMBER:
B-55 TITLE: IMPROVE RELI ABILITY OF TARGET ROCK SAFETY-RELIEF VALVES IDENTIFICATION DATE: 06/7BC PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY: M TASK MANAGER: G. HAMMER OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE: 08/97 TAC NUMBERS:
WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN, (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE
... -...---_ ---_--_---- _--_--_--_-----.------__ ---_----_-__~_--_---
W0RK SCDPE kkhkkW BWk bkkLkkk kPPkbkbHkk Tb kkbkkkkkkG EkV CbhFbkMkkbhkbkkkkVkkhbkkkkTkbbTkbkk$(2 RELIABILITY TO OBTAIM SUFFICIENT DATA BASE TO SUPPORT DEMONSTRATING SUFFICIENT RELIABILITY OF 2-5 AGE VALVES AFTER DESIGN AND/OR SYSTEM MODIFICATIONS, AND (3)
THE CONCLUSION THAT THIS ISSUE HAS BEEN RESOLVED.
USING DIFFERENT VALVES AND DEMONSTRATING THEIR THE UTILITY APPROACHES MAY INCLUDE: (1) DEMONSTRATING RELIABILTY.
SUFFICIENT RELIABILITY OF 3-STAGE VALVES BY STRICT s
STATUS WHILE INITIAL PERFORMANCE WITH THE PH 13-8 MO REFLACE-SINCE MOST OF THE NRC STAFF EFFORT RELATED TO THE MENT DISCS INDICATED AN IMPROVEMENT, ADDITIONAL PERFORMANCE BALANCE OF THE GENERIC RESOLUTION OF THIS GENERIC ISSUE WAS EXPECTED TO BE UNDERTAKEN WITHIN NRR, AND SINCE DATA MADE IT APPARENT THE NEW DISCS ARE NOT PROVIDING THE ANY PLANT MODIFICATIONS RESULTING FROM THE RESOLUTION OF IMPROVED PERFORMANCE THAT WAS ORIGINALLY EXPECTED. THE THIS ISSUE WERE EXPECTED TO BE EITHER VOLUNTARY OR BWROG CONCLUDED THE PH 13-B MG REPLACEMENT DISCS ARE NOT A JUSTIFIED ON A " COMPLIANCE" BASIS, RES HAS FORMALLY VIABLE SOLUTION FOR ELIMINATING SFTPOINT DRIFT AND RECOM-TRANSFERRED THE ISSUE TO NRR FOR THE BALANCE OF THE GENERIC MENDED THEY NO LONGER BE INSTALLED TO RESOLVE THIS PROBLEM.
BECAUSE CORRDSION BONDING OF THE PILDT DISK TO ITS SEAT WAS RESOLUTION PERIOD AND SUBSEQUENT PLANT SPECIFIC IMPLEMENTA-IDENTIFIED AS THE CAUSE OF THE UPWARD SETPOINT DRIFT, THE TION.THE STAFF MET WITH THE BWROG ON APRIL 24, 1996. TO BWROG THEN DEVELOPED A PLATINUM ALLOY PILOT DISK DESIGN.
DISCUSS THE PERFORMANCE OF THE CATALYTIC DISKS AND SEAT THIS CATALYST DISK WAS VERY EFFECTIVE IN REDUCING OXYGEN CONCENTRATION AT THE PILOT DISK SEAT LOCATION WHICH COULD LEAKAGE ISSUES. THE BWROG HAS DETERMINED THAT, BY THE BWROG ALSO DEVELOPED SPRING 1997 ENDUGH SETPOINT DATA SHOULD BE AVAILABLE TO
- THEN REDUCE THE CORROSION BONDING.
AN EQUAL PARALLEL CONTINGENCY OPTION WHICH INVOLVES THE USE EVALUATE THE DISKS. THE BWROG 15 ALSO DEVELOPING OF PRESSURE SWITCHES SIMILAR TO THOSE USED ON BWR/6 PLANTS.
RECOMMENDATIONS TD LESSEN LEAKAGE BY BETTER MONITORING AND MAINTENANCE, SINCE LEAKAGE MAY AFFECT THE SETPOINT A LICENSING TOPICAL REPORT AND ADDITIONAL INFDRMATION FOR PERFORMANCE. CURRENTLY, THE STAFF PLANS TO DISCUSS THE THE PRESSURE SWITCH DESIGN WAS SUBMITTED WHICH NRR HAS AVAILABLE TEST DATA WITH THE BWROG IN THE SPRING 1997 AND SEVERAL OF THE CATALYTIC DISKS HAVE BEEN INSTALLED IN SEVERAL BWR'S ON A TRI AL BASIS FOR SUBSEQUENT EVALUATE THE PERFORMANCE OF THE PLATINUM ALLOY DISKS AND RECENTLY APPROVED.
ADDITIONAL ACTIONS IF NECESSARY.
SETPOINT TESTING.
AS OF FY97 QUARTER 1 9
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i RUM OATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
59' ISSUE NUMBER:
8-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES STATUS AFFECTED DOCUMENTS PROBLEM / RESOLUTION
______________...______..____ ___..... ___.._=_
NOME NOME.
t ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE t
MEETING WITH BWR OWNERS SETPOINT DRIFT 12/83 11/83 COMMITTEE BWR OWNERS REPORT SUBMITTED 07/84 06/84 BOSTON EDISON REPORT SUBMITTED 08/84 COMPLETION OF NRR EVALUATION OF OWNERS 10/84 10/84 GROUP ANO BOSTON EDISON REPORTS COMMUNICATION TO OG RE: MRC 03/85 COMMENTS / CONCERNS OG PRESENTATION TO THE STAFF 10/85 10/85 i
STAFF RECEIVES OWNER $* PROGRAM FOR 10/85 10/85 ELIMINATING SET POINT DRIFT OWNERS BEGIN TO INSTALL NEW PILOT DISKS 01/86 01/86 TO TEST IN PLANT FOR ONE FUEL CYCLE ISSUE STATUS REPORT ON INDUSTRY EFFORTS 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 AS OF FY97 QUARTER 1 i
s 1
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________.__..____._._,.m.______.___-__________.____.__-___m_____._____m_-
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RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
60 ISSUE NUMBER:
B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE BWROG SELECT / DESIGN CATALYST 03/91 02/91 NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 06/91 08/91 PROGRESS BWROG COMPLETES FINALIZING DESIGN AND 04/92 07/92 LABORATORY TESTING NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 03/92 08/92 PROGRESS REASSESS ISSUE 03/93 05/93 REASSIGN TO NRR "8/93 08/93 NRR RESPONSE TO REASSIGNMENT 10/93 10/93 BWROG SUBMIT TOPICAL REPORT TO NRC 12/91 04/94 DESCRIBING PRESSURE SWITCH OPTION OWNERS BEGIN TO INSTALL CATALYSTS TO TEST 06/94 04/94 IN PLANTS FOR FIRST FUEL CYCLE TRANSFER OF BALANCE OF GSI TO MRR 11/94 04/95 NRR ISSUE APPROVAL FOR PRESSURE SWITCH 02/95 10/95 OPTION EVALUATE PERFORMANCE OF PLATINUM OISKS AND 05/97 05/97 DETERMINE ADDITIONAL ACTIONS IF NECESSARY ISSUE CLOSE9UT MEMORANDUM TO E00 08/97 08/97 AS OF FY97 QUARTER 1 9
9 9
+
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WCN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
61 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT DUTAGE PERIDDS IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: 11/83C TYPE: GSI PRIDRITY: M TASK MANAGER: A. BUSLIK OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTIDM DATE: 04/97 WORK AUTHORIZATIDN: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE MONE MONE NOME W0RK SC0PE IN GENERAL PLANTS WILL BE CLASSIFIED SUCH THAT OF SUPPDRT SYSTEM DUTAGES MUST BE INCLUDED. DETAILS IN EACH CLASS SIMILAR ECCS DUTAGE UNAVAILABILITIES OF THE WORK SCOPE ARE CONTAINED IN THE DRAFT ACTION WILL HAVE SIMILAR IMPACTS ON RISK.
THE EFFECT DF A PLAN.
BECAUSE CUMULATIVE DUTAGE TIMES ON COMPONENTS OTHER GIVEN ECCS AVAILABILITY ON RISK WILL BE DETERMINED.
THAN ECCS CDNPONENTS APPEAR IMPORTANT THE WORK SCDPE HAS FOR EACH CLASS OF PLANT, AS WELL AS THE IMPACTS OF ANY BEEN EXPANDED TO INCLUDE ALL SAFETY-R$ LATED COMPONENTS.
CHANGES IN ALLOWABLE ECCS OUTAGE PERIOD. CDMSIDERATION STATUS hkbK i Hkh BEkN bbhPLkT[bI hkhb kb kbkh hkTH PkbPbhkb bkPbkh bkkkbhbk bkk$
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RESOLUTION WAS INITIATED BY PRAB IM 09/96: MEMO IS WITH AFFECTED DOCUMENTS PROBLEM / RESOLUTION TECHNICAL SPECIFICATION CHANGES ARE POSSIBLE.
THE MAJOR PROBLEM ASSOCIATED WITH THE RESOLUTION OF B-61 IS REVISED INSPECTION GUIDANCE FOR VOLUNTARY ENTRY INTO AN ANALYSIS OF THE COSTS AND BENEFITS OF THE IMPOSITION '0F LCO*S.
A CUMULATIVE OUTAGE REQUIREMENT. A STUDY DF THE NEED FOR CONTROL OF CUMULATIVE DUTAGE IS BEING PERFORMED IN-HOUSE.
THE WORK TAKES INTO ACCDUMT THE MAINTENANCE RULE AND THE NUMARC GUIDANCE FOR THE IMPLEMENTATION OF THE MAINTENANCE RULE. AS WELL AS CURRENT INSPECTION GUIDANCE ON VOLUNTARY ENTRY INTO LIMITED CONDITIONS OF OPERATIDM ACTION STATEMENTS TO PERFORM PREVENTIVE MAINTENANCE. AN INITIAL RECOMMENDA-TION FDR STAFF COMMENTS WAS COMPLETED IN SEPTEMBER 1992:
THIS INCLUDED A PROPOSED DRAFT TECHNICAL RESOLUTION.
AS OF FY97 QUARTER I ma.-
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RUO DATE: 02/24/97 GENERfC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
62 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT DUTAGE PERIODS AFFECTED DOCUMENTS PROBLEM / RESOLUTION COMMENTS VERE RECEIVED ON THIS PROPOSED DTR FRDM IMMEDIATE MANAGEMENT IN AUGUST 1993.
IT IS CLEAR THAT A CUMULATIVE DUTAGE 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 SHDULD BE SELECTED. MODIFICATIONS TO THE GUIDANCE FOR THE MAINTENANCE RULE TO EMPHASIZE THE RISK IMPLICATIONS OF PERFORMING SCHEDULED MAINTENANCE ON RISK-SIGNIFICANT COMPONENTS DURING POWER OPERATION APPEAR DESIRABLE. A MEMORANDUM FROM RES TO NRR SUGGESTING THAT B-61 BE RESOLVED THRDUGH THE MAINTENANCE RULE. BY MODIFYING THE INSPECTION GUIDANCE FOR THE MAINTENANCE RULE HAS BEEN SENT.
THIS MEMORANDUM INDICATED THAT, SINCE YHE IPE*S HAVE NOT INDICATED ANY VULMERABILITIES WITH RESPECT TO ONLINE MAINTENANCE OF COMPONENTS, IF THE INSPECTION GUIDANCE FOR 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 DRAFT TAP ISSUED FOR DD APPROVAL 01/84 GI/84 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 04/85 DEVELOPMENT COMPLETED TASK II-APPLY TO A PWR OR BWR 02/85 02/92 AS OF FY97 QUARTER I O
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ISSUE MUMBER: B-61 TITLE: ALLOWABLE ECCS EQUIPMENT DUTAGE PERIDOS f
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE t
DEVELOP AN INITIAL RECOMMENDATION FOR STAFF 08/87 09/92 COMMENTS r
09/92 APPLY METHODOLOGY TO A SELECTION OF PLANTS 08/85 f
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PREPARE DRAFT DTR 04/86 04/94 06/96 DRAFT RESOLUTION 02/95
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DTR TO ACRS 08/9 6 03/97 CLOSE OUT ISSUE 02/95 04/97 i
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64 ISSUE NUMBER: HF 5.2 TITLE: REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
IDENTIFICATION DATE: 08/83C PRIORITIZATION DATE: 10/84C TYPE: GSI 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 WDRK SC0PE THIS ISSUE COMBINES THE ISSUES FROM THE HUMAN FACTORS USE OF INFORMATI'1N FROM CONTROL BOARD ANNUNCIATORS. THE PROGRAM PLAN OF SECTION 1.5.2 RESULTS FROM A PLA ESTABLISHED THE MAGNITUDE OF THE RISK LA? COMPUTER AND COMPUTER DISPLAYS INVOLVED AND THE POTENTIAL REDUCTION IN RISK EXPECTED. A LBJ EVALUATION OF OPERATOR AID SYSTEMS VALUE/ IMPACT ANALYSIS WAS COMPLETED AND ESTIMATED THE COST LC ' ANNUNCIATORS OF POTENTIAL MODIFICATIONS TO ANNUNCIATORS.
LDj 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 ALSD 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 SY LETTER DATED DECEMBER 29, 1987. THE 50W FOR THE VALUE-COMPLETED IN NOVEMBER 1988. ALARM REDUCTION STUDY BEGAN IMPACT STUDY WAS FORWARDED TO BNL.
PROJECT-AND BUDGET OCTOBER 1990. WORK TERMINATED. (SEE MEMORANDUM FROM RECEIVED MARCH 7, 1988.
C. BECKJORD TO THE EDO ON JUNE 29, 1993.)
PROPOSAL FOR NRC WORK (NRC FORM 189)/ IMPACT STUDY WAS BNL BEGAN WORK IN APRIL 1988. VALUE AS OF FY97 QUARTER 1 O
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65 ISSUE MUM 8ER: HF 5.2 TITLE: REV. CRIT FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AMO INSTRUMENT.
AFFECTE0 00CUMENTS PROBLEM / RESOLUTION MUREG/CR-6105, " HUMAN FACTORS ENGIMEERING GUIDANCE FOR THE MONE.
REVIEW OF ADVAMCEO ALARM SYSTEMS."
ORIGINAL CURRENT ACTUAL MILEST0MES DATE DATE DATE C
1 04/88 BEGIN VALUE/IitPACT STUOY OF AMMUMCIATORS 02/88 10/88 f
COMPLETE VALLE/ IMPACT STUOY 07/88 11/88 i
MRC COMPLETE'S REVIEW OF STUDY RESULTS 09/88 1
ISSUE S0W FOR ALARM REDUCTION EVALUATION 11/88 01/89 BEGIM ALARM REOUCTION STUOY 01/89 03/89 PREPARE CLOSEOUT PACKAGE 04/93 04/93 l
CLOSE OUT HEMO TO EDO 06/93 06/93 s
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66 ISSUE NUMBER:
II.E.6.1 TITLE: IN-SITU TESTING OF VALVES IDENTIFICATION DATE: 05/8DC PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: M TASK MANAGER: T. SCARBROUGH OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M80330 MB2072 M75089 MB8898 RESOLUT7DN DATE: 06/89C WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE A3821 BNL ADEQUACY OF CURRENT VALVE INSERVICE TEST METHODS WDRK SC0PE SPECIFIC ACTIVITIES INCLUDED IN THE GENERIC ACTION PLAN TO (2) EPRI MOV PERFORMANCE PREDICTION PROGRAM - ON MARCH 15.
IMPROVE MOV PERFORMANCE ARE:
1996 THE STAFF ISSUED SE ON THE EPRI MOV PERFORMANCE (1) REGULATORY IMPROVEMENTS - THE STAFF IS WORKING WITH ASME PREDICTION PROGRAM. THE STAFF IS REVIEWING THE HAND-TO IMPROVE THE INSERVICE TESTING REQUIREMENTS IN THE ASME CALCULATION MODELS FOR TWO UNIQUE GATE VALVE DESIGNS.
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. ASME ISSUED CODE CASE TO PROVIDE RECOMMENDATIONS ON THE PERIODIC VERIFICATION OMN-1, " ALTERNATIVE RULES FOR PRESERVICE AND INSERVICE TEST-0F MOV DESIGN-BASIS CAPABILITY.
ING OF CERTAIN ELECTRIC MOTOR OPERATED VALVE ASSEMBLIES IN (4) ECTION MODULE FOR MOV INSPECTION MODULE - THE STAFF PLANS TO PREPARE AN INSP 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 COORDINATION WITH INDUSTR" AND SUPPORT TO NRC REGIONAL STAFF HAS BEEN ALERTING LICENSEES, NEI, AND EPRI TO THE 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 COMMUNICATING 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 MOV PERFORMANCE PREDICTION PROGRAM.
ACTIVITIES. WITH ISSUANCE OF GL 96-05, STAFF WORKING TO THE STAFF IS REVIEWING THE REMAINING EPRI MODELS 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 IN EARLY 1997. THE AS OF FY97 QUARTER I 9
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67 ISSUE NUM8ER:
II.E.6.1 TITLE: IN-SITU TESTING OF VALVES PRO 8LEM/ RESOLUTION AFFECTED DOCUMENTS
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I l MUREG-1352 dj GL 96-05 ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE INSERVICE TESTING OF CHECK VALVES (IMPO) ISSUE SOER REGARDING 07/86 10/86 AUGMENTED TESTING OF CHECK VALVES 10/86 02/87 (NRR/RES) REVIEW SOER TO SEE IF NRC CONCERMS ON IM-SITU TESTING OF " SIMPLE" CHECK VALVES SATISFIED. ISSUE RPT &/OR LTR 05/87 11/87 (MSSS OWNERS GROUP) ISSUE OWIERS GROUP APPLICATIDM GUIDE FOR CHECK 7
VALVES 08/87 01/88 (NRR/RES) REVIEW OWNERS GROUP APPL GUIDE TO SEE IF NRC CONCERMS ON IN-SITU TEST OF
" SIMPLE" CHECK VALVES ARE SATIFIED 08/87 03/88 (NRR/RES) REPORT (ACRS)
THERMAL OVERLEAD PROTECTION OF MOV*S 10/87 (RES/EI8) COMPLETE REVIEW TO DETERMINE REQ'O 05/85 MODS, IF ANY. TO RG 1.106 REGARDING TOL PROTECTION
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CLOSE OUT MEMO ON CHECK VALVES & TOL 01/89 06/89 i
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68 ISSUE NUMBER:
II.E.6.1 TITLE: IN-SITU TESTING DF VALVES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE INSERVICE TESTING OF MOV'S (RES) ISSUE MOVATS REPORT REGARDING USE OF 09/85 01/86 SIGNATURE TRACING TECHNIQUES TO EVAL. THE OPERABILITY OF MOV*S (NRR/RES) REVIEW MOVATS REPORT AND AE00 11/85 08/86 COMMENTS ON MOVATS REPORT (MRR) 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 OMAL AND/OR MODIFIED IN SITU TESTING OF MOV*S (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 DUT MEMO TO EDO TASK MANAGER - OWEN 06/89 06/89 ROTH8 ERG. EIB/DSIR/RES ISSUE GL 89-10 SUPPLEMENT 7 01/95 01/95 AS OF FY97 QUARTER 1 O
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69 ISSUE NUMBER:
II.E.6.1 TITLE: IN-SITU TESTING OF VALVES I
ORIGINAL CURREMT ACTUAL MILEST0NES DATE DATE DATE ISSUE NEW GENERIC LETTER ON MOV PERIDOIC 02/96 02/96 VERIFICATION FOR PUBLIC COMMENT SER ON EPRI MOV PERFORMANCE PREDICTION 02/96 03/96 I
PROGRAM FINAL ISSUANCE OF NEW GENERIC LETTER OM 06/96 09/96 MOV PERIODIC VERIFICATION SER SUPPLEMENT ON EPRI MOV PERFORMANCE 08/96 01/97 PREDICTION PROGRAM CLOSE 00T ISSUE 01/97 02/97 PREPARE MOV INSPECTION MODULE 10/96 06/97 f
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70 ISSUE NUMBER: RGA 001 TITLE: BOILING VATER 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:
RESOLUTION DATE:
TAC NUMBERS: M91898 M93627 M93925 M93926 M94959 M94975 M95369 WORK AUTHORIZATION:
CONTRACT TITLE FIN CONTRACTOR WORK SCDPE OF INDUSTRY AND STAFF RESOURCES THA3 WILL BE NEEDED THE STAFF WILL CONTINUE TO ASSESS THE REPORTS THAT HAVE BEEN IN THE FUTURE, IT IS IMPORTANT F0p. THE STAFF TO OR HAVE YET TO BE SUBMITTED BY THE BWRVIP CONCERMING CONTINUE INTERACTING WITH THE INDUSTRY ON A GENERIC INSPECTIONS OF BWR INTERNALS AND REINSPECTIONS OF CORE SHROUDS. THE STAFF WILL ALSO CONTINUE TO ASSESS CORE BASIS IN ORDER TO ENCOURAGE THEM TO CONTINUE THEIR SHROUD REPAIR DESIGNS ON A CASE-BY-CASE BASIS. THE PROACTIVE EFFORTS TO RESOLVE IGSCC OF BWR INTERNALS.
THE BWRVIP HAS SUBMITTED 12 GENERIC DOCUMENTS SUPPORTING STAFF WILL ISSUE SEPARATE SAFETY EVALUATIONS REGARDING PLANT-SPECIFIC SUBMITTALS FOR STAFF REVIEW. THE STAFF IS THE ACCEPTABILITY OF CORE SHROUD REPAIR DESIGNS. THE ENSURING THAT THE GENERIC REVIEWS ARE INCORPORATING RECENT STAFF HAS BEEN INTERACTING WITH THE BWRVIP AND OPERATING EXPERIENCE ON ALL BWR INTERNALS.
INDIVIDUAL LICENSEES. IN AN EFFORT TO LOWER THE NUMBER 5TATUS Lkbkkhkkh klLB hbbhPLkTkbIhhPkbT[bkhbkkkPkkkhbbbbRk B
THE BWRVIP HAS ISSUED 12 GENERIC REPORTS FOR STAFF SHROUDS DURING REFUELING OUTAGES AS OF THE Fall 0F 1996.
REVIEW. THE NRC STAFF HAS ISSUED REQUESTS FOR ADDITIONAL VARIOUS REPAIR METHODS HAVE BEEN USED TO PROVIDE ALTERNATE INFORMATION ON 5 BWRVIP REPORTS AND RECEIVED RESPONSES INCLUDING PREEMPTIVE REPAIRS, ON 3 REPORTS. THE STAFF IS CONTINUING ITS REVIEW OF ALL LOAD CARRYING CAPABILITY, INSTALLATION OF A SERIES OF CLAMPS, AND USE OF A SERIES OF 12 GENERIC REPORTS.
THE NRC HAS REVIEWED AND APPROVED ALL TIE-ROD ASSEMBLIES.
SHROUD MODIFICATION PROPOSALS THAT HAVE BEEN SUBMITTED BY PROBLEM' RESOLUTION AFFECTED DOCUMENTS NUREG-1544 AS OF FY97 QUARTER I i
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71 ISSUE NUMBER: RGA 001 TITLE: BOILING WATER REACTOR INTERNALS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
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ISSUE GL 94-03 07/94 07/94 TAP APPROVED 04/9 5 04/9 5 COMPREHENSIVE PLAN (BWRVIP-06) RECEIVED BY 12/95 10/95 NRC BWRVIP-07 RECEIVED BY NRC 02/96 02/96 ISSUE NUREG-1544 03/96 03/96 REVIEW BWR VESSEL SHELL WELD INSPECTION 08/96 03/97 RECOMMENDATIONS (BWRVIP-05)
REVIEW RPV AND INTERNALS EXAMINATION GUIDE-06/96 03/97 LINES (BWRVIP-03)
REVIEW GUIDELINES FOR REINSPECTION OF CORE 08/96 03/97 SHROUDS (BWRVIP-07)
REVIEW BOUNDING ASSESSMENT OF BWR/2-6 RPV 03/97 03/97 INTEGRITY ISSUES (BWRVIP-06)
SAFETY ASSESSMENT OF BWR REACTOR INTERNALS 08/96 06/97 (BWRVIP-06)
EVALUATION OF CRACK GROWTH IN BWR STAINLESS 12/':S 06/97 STEEL-RPV INTERNALS (BWRVIP 14)
REVIEW ASSESSMENT OF BW3 JET PUMP RISER ELBOW 06/97 06/97 TO THERMAL SLEEVE CRACKING CORR SPRAY INTERNAL INSPECTION AND FLAW 07/97 07/97 I
EVALUATION GUIDELINES (BWRVIP-15)
REVIEW GENERIC REPAIR TECHNOLOGY, CRITERIA 08/96 08/97 AND GUIDANCE
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72 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 DESIGN ~
09/97 09/97 CRITERIA (BWRVIP-19)
REVIEW ROLL / EXPANSION OF CRD AND IN-CORE 09/97 09/97 INSTRUMENT PENETRATIONS IN BWR VESSELS (BWRVIP-17)
REVIEW CORE PLATE INSPECTION AND FLAW 09/97 09/97 EVALUATION GUIDELINE (BWRVIP-25)
REVIEW TOP GUIDE INSPECTION AND FLAW 09/97 09/97 EVALUATION GUIDELINE CLOSE OUT ACTIVITY AS OF FY97 QUARTER 1 O
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73 ISSUE NUMBER: RGA 002 TITLE: REACTOR PRESSURE VESSEL FRACTURE TOUGHMESS IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER: B. ELLIOT OFFICE / DIVISION / BRANCH: NRR /DE /EMCB ACTION LEVEL: ACTIVE STATUS:
RESOLUTION DATE: 10/96 TAC NUMBERS: M92310 M92313 M93329 M93330 M93331 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE I
WDRK SCOPE SPECIFIC ACTIONS INCLUDED IN THE GENERIC ACTION PLANS ARE:
TO NUREG-1511 IN 1996 AND ISSUE SUPPLEMENT 2 TO NUREG-1511 (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 AM NRC/IMDUSTRY WORK-REVISION 2 W THE RVID IN 1997 (7) OBSERVE INDUSTRY ANNEAL-ING DEMONSTRATIONS, (8 REVIEW AND EVALUATE THE PALISADES ANNEALING PLAN, AND (9))
SHOP DN RPV ISSUES, 4) REVIEW FIRST AND SECOND ROUND OF RESPONSES TO GL 92-0(1 SUPPLEMENT 1.
(5) ISSUE SUPPLEMENT 1 REVIEW THE PALISADES ANNEAL.
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THE REACTOR PRESSURE VESSEL FRACTURE TOUGHNESS ACTION BE COMPLETED UNDER PLANT SPECIFIC TAC M92310 (TAC M92313 PLAN WAS CLOSED DUT BECAUSE ALL TASKS HAVE EITHER BEEN WAS ALSO OPENED FOR STUDY OF THE ANNEALING DEMONSTRATION COMPLETED, WILL BE COMPLETED AS PART OF INDIVIDUAL PLANT PROJECTS).
MUREG-1511 REACTOR PRESSURE VESSEL STATUS REPORT, REVIEWS OR AS MULTI-PLANT ACTION ITEMS, OR WILL BE REVIEWED SUPPLEMENT 2. AND ISSUANCE OF THE REACTOR VESSEL INTEGRITV AS PART OF NRR OVERSIGHT OF RES PROGRAMS.
DATABASE. REVISION 2. WILL BE COMPLETED AS PART OF MPA REVIEW OF THE RESPONSES TO GENERIC LETTER 92-01, SUPPLEMENT 1. WILL BE COMPLETED UNDER MULTIPLANT ACTION L201.
COORDINATION WITH RESEARCH IS ONGOING.
- (MPA)EVIEW OF THE PALISADES ANNEALING PLAN AND ANNEAL WILL L201.
R AFFECTED DOCUMENTS PROBLEM / RESOLUTION GL 92-01 REV. 1 NONE MUREG-1511 NRC ADMINISTRATIVE LETTER 95-03 RG 1.99 AS OF FY97 QUARTER 1 o
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74 ISSUE NUMBER: RGA 002 TITLE: REACTOR PRESSURE VESSEL FRACTURE TOUGHNESS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP APPROVED ISSUE GL 92-01 REV. 1 03/92 03/92 ISSUE GL 92-01. REV.1 (SUPPLEMENT 1) 05/95 05/95 NRC/ INDUSTRY WORKSHOP DN RPV ISSUES 07/95 07/95 REVIEW OF RESPONSES TO GL 92-01. SUPPLEMENT 1 10/95 10/95 (FIRST ROUND) 06/96 06/96 ISSUE RVID. REV. 1 OBSERVE INDUSTRY ANNEALING DEMONSTRATION 12/96 07/96 NUREG-1511 RPV STATUS REPORT. SUPPLEMENT 1 06/96 10/96 01/97 01/97 -
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75 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 M94108 RESOLUTION DATE:
WORK AUTHORIZATION: MEMO FROM C. PAPERIELLO TO W. RUSSELL AND J. TAYLOR ON JULf 28 1995 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE kbhibkh ikbLbbkb ik hhk PL k Ekk[ 5 kEVfkh kkbb bkkkkkL bkVkLbPbbkkkbh[hbkbhIbkhFbREkbbPkbblEb[Ekb ISSUE AND IDENTIFY THE SPECIFIC PR B EMS TO BE ADDRESSED, IMPLEMENT THE CORRECTIVE ACTIONS.
STATUS TUkFbLLbhikbkbhkbhPLkk5hhbkkbVkBEkkbbhPLkkkb hkkbEkkibhbkbFbkbbbhEkh Pb8LibbbkhkkkhEkEbbkbh CASK TRUNNIONS, CASK WEEPING. HYDROSTATIC TESTING SAFE-JUNE 18, 1996. ALL OF THE COMMUNICATIONS ISSUES ARE ONGOING GUARDS CONCERNS, PART 72 REPORTING REQUIREMENTS, INSPECTION EFFORTS WITH NO SPECIFIC CRITERIA FOR CLOSURE. HOWE VE R,
OF SITE ACTIVITIES, AND VENDOR INSPECTIONS. THE INSPECTION THERE HAVE BEEN SIGNIFICANT IMPROVEMENTS IN THESE AREAS.
PROCEDURES FOR DRV CASK ACTIVITIES (SITE AND VENDOR) WERE THE REGIONS, NMSS, 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 CONSIDERATION 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 ISS'JES ASSOCIATED WITH CASK LOADING AND UNLOADING. THE THE STORAGE OF DAMAGED FUEL HAS BEEN CHANGED TO 03/97 DUE TO WORKING GROUP IS IMPLEMENTING ITS RECOMMENDATIONS, UNTIMELY RESPONSES FROM THE APPLICANT. NMSS/SFP0 INCLUDING THE PREPARATION OF AN INFORMATION NOTICE SPONSORED A PUBLIC WORKSHOP DN DRY CASK STORAGE ON MAY 17 CONCERNING LOADING AND UNLOADING ISSUES. RECENT INFORMATION 1996.
WELL OVER 300 PEOPLE ATTENDED FROM THE PLANTS, (E.G., HYDROGEN IGNITION AT POINT BEACH) MAY REQUIRE STATES, INDUSTRY GROUPS, VENDORS, AND THE STAFF. THE STAFF ADDITIONS TO THE ACTION PLAN.
THE REMAINING TECHNICAL BRIEFED THE COMMISSION ON THE STATUS OF THE DRY CASK ISSUE (HEAVY LDAD CONTROL) IS ON SCHEDULE. A 50.59 ISSUE STORAGE PROGRAM ON MAY 30 1996.
IN RESPONSE TO A INVOLVING HEAVY LOAD CONTROL IN GENERAL IS 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 NUTICE 96-34 ON MAY 31, 1996.
AS OF FY97 QUARTER 1
RtG DATE: 02/24/97 GECERlC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
76 ISSUE NUMBER: RGA 003 TITLE: DRY CASK STORAGE OF SPENT FUEL AFFECTED DOCUMENTS PROBLEM / RESOLUTION i
- T 0 BE DETERHINED NONE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kkhbE[hbkhki5MkbkEbbikkMkhThlbkPkbh bb/hb bb/hb DEVELOP ACTION PLAN 07/95 07/95 MEET WITH NEI ON CASK WEEPING 08/95 08/95 DEVELOP POSITION ON REPORTING REQUIREMENTS 09/9$
09/95 DEVELOP STAFF POSITION ON CASK TRUNIONS 09/95 09/95 FORM WORKING GROUP ON CASK LOADING / UNLOADING 10/95 10/95 PROCEDURES DEVELOP WORKING GROUP PLAN ON HEAVY LOADS /
11/95 11/95 CRANES HYDROSTATIC TESTING 12/95 12/95 COMPLETE ANALYSIS OF SAFEGUARDS DESIGNS 12/95 12/95 ISSUE REVISED PROCEDURES FOR VENDOR 02/96 02/96 INSPECTICNS ISSUE REVISED PROCEDURES FOR INSPECTION OF 02/96 02/96 SITE ACTIVITIES ISSUE SRP AND 10 CFR 50.59 GUIDANCE 03/96 03/96 COMPLETE ACTION ON HEAVY LOADS / CRANES 12/96 12/96 REVIEW PROPOSED SOLUTIONS FOR FAILED FUEL 03/97 03/97 STORAGE AS OF FY97 QUARTER 1 G
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77 ISSUE NUMBER: RGA 003 TITLE: DRY CASK STORAGE OF. SPENT FUEL f
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78 ISSUE NUMBER: RGA 004 TITLE: THERMO-LAG FIRE BARRIERS IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER: S. WEST OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: MB2809 M90203 M90284 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE b
WDRK SC0PE hPhbkhfb kbhfbkh kkbLbbk [ Tkk kkhbLbh[bh bk bbkbkRNh kkb kkkkFFkEbbkkEkbhibkkbkEbbtVbThkkkb5Lbbbkbkkkhbh GENERIC ISSUES RAISED BY H SPECIAL REVIEW TEAM AND REQUIRING COMPLIANCE WITH EXISTING NRC REQUIREMENTS AND TO (2) RESOLUTION OF PLANT-SPECIFIC ISSUES THAT EMERGE FROM PERHIT PLANT-SPECIFIC EXEMPTIONS, WHERE JUSTIFIED.
THE GENERIC ISSUES. IN JUNE 1994. THE COMMISSION APPROVED STATUS THE STAFF COMPLETED THE THERMO-LAG ACTION PLAN.
SCHEDULES.
SPECIFICALLY, THE STAFF COMPLETED THE REMAINING GENERIC THE STAFF IS HANDLING THE REVIEW OF PLANT-SPECIFIC ISSUES. THE MECHANICAL PRCPERTIES TEST PROGRAM, AND THE CORRECTIVE ACTIONS AS MULTIPLANT ACTION MPA-L208 UNDER FIRE CURVE FEASIBILITY STUDY. THE STAFF ALSO COMPLETED ITS GENERIC LETTER (GL) 92-08, "THERMO-LAG 330-I FIRE BARRIERS."
REVIEW OF LICENSEES
- RESPONSES TO GENERIC LETTER (GL) 92-08, AND THE REVIEW OF RELATED PLANT-SPECIFIC ISSUES, SUCH AS
" THERMAL-LAG 330-I FIRE BARRIERS" AND DETERMINED THAT MOST FIRE PROTECTION EXEMPTION REQUESTS AND AMPACITY DERATING CORRECTIVE ACTION PLANS ARE ACCEPTABLE. HOWEVE R, THE STAFF EVALUATIONS AND ANALYSES, AS PLANT-SPECIFIC LICENSING IS CONCERNED THAT SOME LICENSES MAY NOT BE MAKING PROGRESS ACTIONS. THE MPA AND PLANT-SPECIFIC LICENSING ACTIONS ARE TOWARD RESOLVING THE PLANT-SPECIFIC ISSUES, AND SOME TRACKED BY THE WORKLOAD INFORMATION AND SCHEDULING PROGRAM (WISP}SEENRRDIRECTOR'SMONTHLYREPORTFORSTATUS.
IMPLEMENTATION SCHEDULES MAY BE EITHER TOO TENUOUS OR TOO AND ARE NOT A PART OF THE THERMO-LAG ACTION PLAN.
PROTRACTED. THE STAFF HAS ALSD ESTABLISHED A PROCESS FOR MONITORING LICENSEES
- CORRECTIVE ACTION PLANS AND AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 91-47: IN 91-79 AND SUPPLEMENT I: IN 92-46: IN 92-55:
MONE.
IN 92-82: IN 94-22: IN 94-34: IN 94-86, SUPPLEMENT 1:
IN 95-27: IN 95-32: IN 95-49 AS OF FY97 QUARTER 1
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79 ISSUE MUMBER: RGA 004 TITLE: THERMO-LAG FIRE BARRIERS l
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AFFECTED DOCUMENTS PROBLEM / RESOLUTION t
SULLETIN 92-01 AND SUPPLEMENT 1 GL 92-03: GL 86-10. SUPPLEMENT 1 i
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ASSESS NRC FIRE PROTECTION PROGRAM (PART IV) i 02/93 02/93 TESTING (PART II) SUBMITTED TO NRC 04/95 04/95
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t NEI SUBMITS EXECUTIVE
SUMMARY
OF MUCOM 10/95 10/95 REPORT NIST DRAFT REPORT SUBMITTED TO NRC 11/95 11/95 i
NRC PROVIDES COMMENTS AND TECHNICAL 12/95 12/95 DIRECTION TO MIST SEMIANNUAL COMMISSION STATUS REPORT 04/9 6 04/96 t
RESOLVE TECHNICAL ISSUE (PART I) 09/96 09/96 l
SEMIANNUAL COMMISSION STATUS REPORT 10/96 10/96 1
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80 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: M91621 M92635 M93568 RESOLUTION DATE: 11/97 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE SPECIFIC ACTIONS INCLUDED IN THE GENERIC ACTION PLAN ARE:
10 CFR 50.54(F) GENERIC LETTER (GL)) TO PROVIDE INFORMATION (1) IN 95-03 ISSUED 01/12/95 AND SUPPLEMENT TO IN 95-03 N DRAINDOWN VULNERABILITIES AND THE MEASURES THEY ISSUED 03/25/96:
IMPLEMENTED TO DIMINISH THE PROBABILITY OF A DRAINDOWN.
(2) REQUCST ALL PWR LICENSEES, VIA AN INFORMATION GATHERING STATUS BYkkkUfhbkhhkkbkTkbb5hhhhb7 bbbhkkhibNkkQU[kkh kkFkkkkbkhTbGbb3kkkbbkkhbblbBkkkPLbkbliThEbkk THAT STAFF (1) ALLOW A PUBLIC COMMENY PERIOD OF NO LESS THAN GENERAL LANGUAGE CONCERNING REGULATORY AND LICENSING 30 DAYS PRIOR TO ISSUANCE OF THE GL AND (2) CERTAIN REQUIREMENTS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 95-03 STAFF HAS MADE THE CHANGES AS REQUIRED BY THE SRM AND IS AEOD/S95-01 ARRANGING TO PUBLISH IT IN THE FEDERAL REGISTER FOR PUBLIC COMMENTS. COMMISSION REQUIREMENTS, AS STATED ABOVE WILL HAVE IMPACT ON THE DATE OF ISSUE OF THE GL.
ORIGINAL CURRENT ACTUAL MILESTONE 5 DATE DATE DATE TAP APPROVED AS OF FY97 QUARTER 1
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ISSUE NUMBER: RGA 005 TITLE: RCS DRAINDOWN J
ORIGINAL CURRENT ACTUAL MILEST04ES DATE DATE DATE IN 95-03 ISSUED 01/95 01/95 t
DRAFT GL 11/95 11/95 l
ISSUE SUPPLEMENT 1 TO IN 95-03 03/96 03/96 GL TO CRGR 06/96 08/96 COMPLETE DRAET TI-ISSUE TO REGIONS FOR 06/96 03/97 COMMENTS ISSUE GENERIC LETTER 06/96 03/97 f
REC 6IVE REGIONAL COMMENTS ON TI 08/96 05/97 i
COMPLETE EVALUATION OF RESPONSES TO GL 11/96 08/97 ISSUE TI 11/96 08/97 COMPLETE INSPECTIDMS 02/97 11/97 i
CLOSE OUT ACTIVITY 11/97 11/97 i
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82 ISSUE NUMBER: RGA 006 TITLE: SRP REVISION IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIDRITY:
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 W0RK SC0PE SPECIFIC TASKS INCLUDED IN THE ACTION PLAN ARE: 1) IDENTIFY INCORPORATE THE CHANGES RECOMMENDED: 4 FREPARE NEW DRAFT ESTABLISHED STAFF POSITIONS AND NEW REGULATORY REQUIREMENTS SRP SECTIONS THAT ARE SUPPORTED BY EST BLISHED STAFF FROM A REVIEW OF GENERIC REGULATORY DOCUMENTS ISSUED SINCE POSITIONS OR ARE FULLY ADDRESSED IN THE EVOLUTIONARY DESIGN THE 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 AND STANDARDS VERSUS THE CURRENT VERSION OF THE STANDARD:
REQUIREMEhIS.
- 3) PREPARE DRAFT REVISIONS OF THE CURRENT SRP SECTIONS TO STATUS THE WORK APPROACH AND DETAILED PROCEDURES HAVE BEEN CODE AND STANDARD NUREGS HAVE BEEN PUBLISHED. REVIEW COMPLETED FOR THE DEVELOPMENT OF SRP DRAFT REVISION BY TECHNICAL BRANCHES IS BEING COMPLETED ON A RESOURCE PACKAGES 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 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.
- SEE NRR DIRECTOR'S MONTHLY REPORT FOR STATUS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION AS OF FY97 QUARTER 1 O
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ISSUE NUMBER: RGA 006 TITLE: SRP REVISION I
ORIGINAL CURRENT ACTUAL MILE 5T0NES DATE DATE DATE
- i
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84 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 CONTRACTOR CONTRACT TITLE W0RK SC0PE THE GOAL OF THE ACTION PLAN IS TO UTILIZE THE LESSONS ESTABLISHED TO PREPARE THE REGULATORY GUIDANCE DOCUMENTS LEARNED FROM THE 3 VOLUNTEER LICENSEES TO MODIFY STAFF-AND TEST THEIR IMPLEMENTATION DURING THE EVALUATION OF DEVELOPED DRAFT GUIDANCE TO FORMULATE REGULATORY GUIDANCE VOLUNTEER PLANT ACTIVITIES.
ON ACCEPTABLE HETHODS FOR IMPLEMENTING GRADED QA.
THE IN ADDITION TO THE ABOVE, THE FOLLOWING TAC NUMBERS STAFF WILL DEVELOP A REGULATORY GUIDE
- STANDARD REVIEW WERE INITIATED: M91432 M91433 M91434. M91435, M91436 PLAN REVISION FOR CHAPTER 17. AND A R$ ACTIVE INSPECTION AND M91437.
PROCEDURE (IP) FOR GRADED QA.
AN INTEROFFICE TEAM HAS BEEN STATUS bbhLikEhbFkbkkFhkEb$GbibE kbkkPFbkBbhHkkkK bbhkkkbhbRh)$ ShkFF bbkhEhkh WEkE PkbVhbEb kb hhp bbRfhG 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 11 NEI SUBMITTED 96-02 " GUIDELINE FOR IMPLEMENTING A GRADED 3
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 TBRDUGH THE VOLUNTEER PLANT EFFORT.
THE LICENSEES CONTEND THAT EXISTING INDUSTRY GUIDANCE (PSA THE STAFF INFORMED NEI GY LETTER DATED MAY 2, 1996. THAT APPLICATION GUIDE AND EPRI-5652) ARE SUFFICIENT FOR THOSE THE GUIDE IS NOT ADEQUATE (AS A STAND ALONE DOCUMENT) TO TOPICS. THE STAFF RECEIVED WRITTEN COMMENTS FROM NEI ON 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.
NEl 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 (HQMB, SPSB, RES, RIV. AND NRC
- SEE NRR DIRECTOR'S MONTHLY REPORT FOR STATUS.
AS OF FY97 QUARTER 1 9
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85 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA STATUS AFFECTED DOCUMENTS PROBLEM / RESOLUTION REGULATORY GUIDE 1.160 DEPENDENCE ON VOLUNTEER PLANT PROGRAM IMPLEMENTATION 3 IN 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 COULO DIVERT STAFF RESOURCES FROM THIS ACTION PLAN EFFORT. THE IMPOSITION OF COMMLSSION LEVEL APPROVAL OF QA PROGRAM CHANGES THAT RELY ON RISK INFORMED DECISIONMAKING INVOLVING POLICY ISSUES CCULD JEOPARDIZE THE PROJECTED GRADED QA MILESTONE SCHEDULES.
ORIGINAL CURRENT ACTUAL MILEST0NES 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 r
REVISION 3 0F DRAFT EVALUATION GUIDE FOR 07/95 07/95 VOLUNTEER PLANTS ISSUED FOR STAFF COMMENT REVISION 4 0F DRAFT EVALUATION GUIDE FOR 10/95 10/95 VOLUNTEER PLANTS ISSUED FOR STEERING GROUP REVIEW L
ISSUE LTR TO 3 VOLUNTEER PLANTS OUTLINING PRO 01/96 01/96 GRAM DBJECTIVES & REVIEW EXPECTATIONS. DIS-TRIBUTE STAFF EVALUATION GUIDE TO LICENSEES.
EVALUATION GUIDE ISSUED FOR USE BY STAFF IN 01/96 01/96 EVALUATING VOLUNTEER PLANTS AS OF FY97 QUARTER 1
RUN DATE: 02/24/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
86 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ACRS BRIEFING: EXPERT PANEL AND DETERMINIS-02/96 02/96 TIC CONSIDERATIONS ACRS BRIEFING: GRADED QA 04/96 04/96 NCETING 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 09/96 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 CS/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 INSDECTION GUIDANCE (REACTIVE 05/97 12/97 IP)
FINAL DRAFT SRP AND RG FOR INTEROFFICE 12/97 12/97 CONCURRENCE PUBLISH FINAL SRP AND RG 12/97 12/97 AS OF FY97 QUARTER 1 9
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87 ISSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE CONDUCT NRC STAFF TRAINING 05/97 01/98 PUBLIC WORKSHOPS OM GRADED QA 02/97 02/98 ISSUE SECY UPDATE (CLOSEOUT OF ACTION PLAN) 12/97 04/98 i
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